ORNL-TM-0908A.txt

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OAK RIDGE NATIONAL LABORATORY
operated by

UNION CARBIDE CORPORATION
for the

U.S. ATOMIC ENERGY COMMISSION

ORNL - TM~- 908,
Volume |

. A
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IN NUCLEAR SCIERCE ABSTRACES

MSRE DESIGN AND OPERATIONS REPORT
PART VIIl, OPERATING PROCEDURES

R.H. Guymon

TR S 4 Sebeane e e b e Gl AL (g

NOTICE This document contains information of o preliminary nature
and was prepared primarily for internal use at the Oak Ridge National
Laboratory. It is subject to revision or correction and therefore does
not represent a final report.

Cde e e ey -y

DISCLAIMER

This report was prepared as an account of work sponsored by an
agency of the United States Government. Neither the United States
Government nor any agency thereof, nor any of their employees,
makes any warranty, express or implied, or assumes any legal liability
or responsibility for the accuracy, completeness, or usefulness of any
information, apparatus, product, or process disclosed, or represents
that its use would not infringe privately owned rights. Reference
herein to any specific commercial product, process, or service by
trade name, trademark, manufacturer, or otherwise does not
necessarily constitute or imply its endorsement, recommendation, or
favoring by the United States Government or any agency thereof. The
views and opinions of authors expressed herein do not necessarily
state or reflect those of the United States Government or any agency
thereof.

DISCLAIMER

Portions of this document may be illegible in electronic image
products. Images are produced from the best available
original document.
ORNL-TM-908,

Volume |
MSRE DESIGN AND OPERATIONS REPORT
PART VIII, OPERATING PROCEDURES
R.H. Guymon
T TR I AT O N
i e v e —— A
o, v s . '-T\ ‘fl*-.w

e P UL :

© Bl S RIS 1o, the wocipient 118
+ w—TonTIeREE Aid Shopld nak.be-abstraeted-or-futthe
= 1 EECIos el yithaut the.approvai-or e bR E R ingdre
* L installation er-BEHEXIEHEIR, O R idge.

DECEMBER 1965

IN FUCER Sopmice

A

ABSTRACRS

OAK RIDGE NATIONAL LABORATORY
Odk Ridge, Tennessee
Operated by
UNION CARBIDE CORPORATION
for the

UNITED STATES ATOMIC ENERGY COMMISSION
iii
PREFACE

The report on the Molten-Salt Reactor Experiment (MSRE) has been
arranged into twelve major parts as shown below. Each of these covers
a particular phase of the project, such as the design, safety analysis,
operating procedures, etc. An attempt has thus been made to avoid much
of the duplication of material that would result if separate and inde-
pendent reports were prepared on each of these major aspects.

Detailed references to supporting documents, working drawings, and
other information sources have been made throughout the report to make
it of maximum value to ORNL personnel. Fach of the major divisions of
the report contains the bibliographical and other appendix information
necessary for that part.

The final voliumes of the report, Part XIT, contain rather extensive
listings of working drawings, specifications, schedules, tabulations,
etc. These have been given a limited distribution.

Most of the reference material is available through the Division
of Technical Information Extension, Atomic Energy Commission, P.0. Box
62, Oak Ridge, Tennessee. For material not available through this source,
such as inter-ILaboratory correspondence, etc., special arrangements can
be made for those having a particular interest.

None of the information contained in this report is of a classified
nature.

All the reports are listed below.

ORNL-TM-T728% MSRE Design and Operations Report, Part I, Descrip-
tion of Reactor Design, by R. C. Robertson
‘\%,.ORNL-TM—729 MSRE Design and Operations Report, Part II,

Nuclear and Process Instrumentation, by
J. R. Tallackson

ORNL-TM-T730% MSRE Design and Operations Report, Part ITIT,
Nuclear Analysis, by P. N. Haubenreich,
J. R. Engel, B. E. Prince, and H. C. Claiborne

N
- ORNIL-TM-T731 MSRE Design and Operations Report, Part IV,
Chemistry and Materials, by F. F. Blankenship
and A. Taboada

*
Issued.
iv

th (o r<ORNL-TM-T732% MSRE Design and Operations Report, Part V,

JY Reactor Safety Analysis Report, by S. E. Beall,
P. N. Haubenreich, R. B. Lindauer, and
J. R. Tallackson

,é9£@114§RNL'TM'733* MSRE Design and Operations Report, Part VI,
Operating Safety Limits for the Molten-Salt
Reactor Experiment, by S. E. Beall and
R. H. Guymon

/fi;&q;;QBNL-TM—9OT* MSRE Design and Operations Report, Part VITI,
Fuel Handling and Processing Plant,
by R. B. Lindauer

ORNL~T™-908 MSRE Design and Operations Report, Part VIIT,
Operating Procedures, by R. H. Guymon
M’ ORNI~TM-909 MSRE Design and Operations Report, Part IX,

Safety Procedures and Emergency Plans,
by A. N. Smith

v ORNL-TM-910 MSRE Design and Operations Report, Part X,
9 Maintenance Equipment and Procedures,
by E. C. Hise and R. Blumberg

\/ORNL—TM-911 MSRE Design and Operations Report, Part XI,
N Test Program, by R. H. Guymon and
P. N. Haubenreich

MSRE Design and Operations Report, Part XII,
Lists: Drawings, Specifications, Line Schedules,
Tnstrument Tabulations (Vol. 1 and 2)
Acknowledgement

The Operating Procedures were written primarily by members of the
MSRE Operations Department of the ORNL Reactor Division. Substantial
contributions were made by members of the Development Department of the
Reactor Division and by members of the Instruments and Controls Division
who wrote and reviewed various sections. All contributions are gratefully

acknowledged.
PREFACE

vii

CONTENTS

Volume T

ACKNOWLEDGEMENT

1 INTRODUCTION
1A  Explanation of Operating Procedures

2B List

of Other Material Available

2 NUCLEAR ASPECTS OF OPERATTON
2A  Simplified Reactor Theory

1

= W

BN

2B MSRE
1
2
3
4
3 OPFRATION

Glossary

Atomic Structure

Radioactivity and Radiation

The IMission Process

Cross Sections and Reaction Rates

The Fission Chain Reaction in an Infinite Reactor
Effect of Neutron Leakage

Criticality

Extraneous Neutron Sources and Subceritical Multiplication
Reactor Kinetics

Nuclear Instrumentation

Reactor Control

Xenon and Samarium

Nuclear Characteristics

Core Reactivity Iactors

Heat Generation and Temperature Distributions
Instrumentation

Kinetics and Safety

OF AUXILIARY SYSTEMS

3A Electrical System

= w N

System Startup
Normal Operation
Emergency and Special Operations

Normal Shutdown
3F

3G

3H

31

o N O F

ix

Special Equipment Room

West Tunnel and South Electric Service Area
Charcoal Bed Pit

Filter Pit

Auxiliary Cells

Ventilation System

1
2
3
L
P

Startup

Normal Operation

Operation during Maintenance
Special Operations

Shutdown

Leak-detector System

1
2

3
L

Startup
Normal Opersation
Location of Leaking Flanges

Shutdown Procedures

Instrumentation

O o1 & Ww D+

Controllers and Indicators
Scanner

Computer
Annunciators
Jumper Board
Other Instruments
6.1 FqIl-569-A
6.2 A05-566-A
6.3 PJAE-RC-E
6.4 ABe-A-AD3
6.5 A05-548

6.6 AH,0-5U8

Freeze Valves

1
2

3

Definitions and Criteria
Basic Operation and Interlocks

Operation of Freeze Valves
3d

3K

Liquid Waste System

Jetting Reactor Cell and Drain Tank Cell Sumps
Sampling Reactor and Drain Tank Cell Sumps
Jetting Auxiliary Cell Sumps

Building Sump Operation

Pit Pump Operstion

Treatment and Disposal of Waste Contents

N4 Ovwu W o

Clarification of Decontamination Tank or Decontamination
Cell Liquid

8 Backwash of the Waste Filter

) General Decontamination and Clean Up

Be Monitoring System

1 General Building Air Sampling System

2 Ventilation System Air Handling

3 NSL Be Air Monitoring Unit

n Coolant System Stack Be Monitoring Unit

AUXTLIARY SYSTEMS STARTUP CHECK LISTS

ha
LB
Le
LD
LE
LF
LG
LH
LT

Electrical System

Instrument Air System

Cooling Water Systems
Component Cooling Systems
Shield and Containment Systems
Ventilation System

Leak-detector System

Instrumentation

Freeze Valves

Volume I1

REACTOR STARTUP

S5A
5B
5C
5D
5E
S5F
oG
S5H

Purging Oxygen and Moisture from the Salt System

Startup of Cover-gas and Offgas Systems

Heatup of Drain Tank System |

Addition of Fuel, Flush, and Coolant Salt to the Drain Tanks
Startup of Lube-0il Systems for the Fuel and Coolant Pumps
Heatup of Fuel and Coolant Systems

Prepare Drain Tank Systems for Reactor Startup

Routine Pressure Test
xi

51 Filling the Fuel and Coolant Systems
5J  Criticality and Power Operation
1 Preparation for Power Operation
2 Starting Power Operation using Automatic Load Control
and Rod Servo
3 Manual and Special Power Operation
5K Normal Operating Conditions
SAMPLING AND ADDITTIONS
6A TFuel System Sampling and Enriching
1 General Description of Sampling the Fuel System
P General Description of Adding Enriching Capsules to the
Fuel System
Fuel System Sampling Check List
Fuel System Enriching Check List
Fuel System Sampler Startup
Fuel System Sampler Shutdown

-~ O 1 F W

Unusual Operating Conditions for the Sampler Enricher
6B Coolant System Sampling
1 General Description of Sampling the Coolant System
2 Coolant System Sampling Check List
3 Coolant System Sampler Startup
L Coolant System Sampler Shutdown
6C Water System
Treatment of Treated Water or Nuclear Penetration
Treatment of Cooling Tower Water
Condensate
Procedure for Total Inhibitor Analysis
Procedure for Chromate Analysis

Procedure for Hardness Analysis

~N O F W

PH Measurement
6D Cell Air
6E ILube 0il System
1 Sampling of New 0il as Received
2 Sampling at Oil Packages
3 Addition of Lube 0Oil to Oil Packages
6F Cover Gas
6G  Offgas System
HEAT BALANCE _

- TA  General Description
7B Computer Heat Balance
7C Manual Heat Balance

xii

PERTODIC INSTRUMENT CALIBRATION AND CIRCUIT CHECKS

557 (Offgas from Charcoal Beds)
528 (Coolant System Offgas)

565 (Cell Offgas)

500 (Main Helium Supply)

Monitors (Service Tunnel)

8A  Neutron Level ‘
1 Wide-range Counting Channels
2 Nuclear Safety Channels
3 Linear Power Channels
8B Calibration Check of Process Radiation Monitors
1 Preparation
p Radiation Monitor
3 Radiation Monitor
L Radiation Monitor
5 Radiation Monitor
6 Process Monitor 596 (Outside Transmitter Room)
7 Process Monitor 827 (Treated Water)
8 0il System Process
8C Calibration of Personnel Monitors and Stack Monitors
1 Routine Source Check
e Alarm Matrix Check
3 Evacuation Alarm Test
b Contaimment Stack Monitor Tests
8D Safety Circuit Checks

Fuel Pump and Over
Helium Supply Pres
FP and OFT Bubbler

Rod Scram Circuits

Coolant Pump Speed

Sampler-Enricher

WV & 39 Oy a1 & W

Exercise Control R

flow Tank Pressure
sure

S

Emergency Fuel Drain

High/Low Reactor Cell Pressure

and Coolant Salt Plow

ods
xiii

9 UNUSUAL ‘OPERATING CONDITIONS
QA Loss of Electrical Power
Loss of Preferred TVA Feeder
Complete Loss of TVA Power - All Diesels Operable
Failure of DG-3 during a TVA Power Outage
Failure of DG-4 during a TVA Power OQutage
Failure of DG-5 during a TVA Power Outage
Failure of DG~3 and 4 during a TVA Power Outage
Failure of DG-3 and 5 or 4 and 5 during a TVA Power Outage
Loss of zZ50v DC Systems
Loss of Instrument Power
OB Loss of Cooling Water
1 Treated Water System

O OO -3 Ol W

pa Cooling Tower Water
9C Loss of Fuel or Coolant Pump
1 Loss of Fuel Pump
2 Loss of Coolant Pump
OD Loss of Instrument Air
1 Air Compressor Electrical Difficulties
2 Other Air Compresgor Difficulties
3 Effects of Loss of Instrument Air
OF Radiation Increases
1 Personnel Monitors
2 Process Radiation Detectors
3 High Stack Activity
O9F Control-rod Drive Difficulty
9G Loss of Computer
O9H Iwbe-oil System Difficulties
1 Coolant Salt Pump Lube System Failure
a Fuel Salt Pump ILube System Failure
3 Total 01l System Failure
L Excess 0Oil Seal Leakage
ol Salt in Overflow Tank
OJ Loss of Helium Purge to the Circulating Pumps

OK Loss of Component Cooling Blowers
10

11

xiv

OL Removal of Water from the Steam Domes

OM  Regeneration of Helium Dryer

ON High Cell Leak Rate Indication

1
2

3
L

Salt Leaking into the Cell
Water Leaking into the Cell
Loss of Reactor or Drain Tank Space Coolers
Actual High Cell Leak Rate

REACTOR SHUTDOWN
10A Normal Shutdown

1
2

3
L

5

1
2

3

Power Reduction and Going Subcritical
Draining and Flushing the Fuel System
Draining the Coolant System

Cooldown of Fuel and Coolant Systems

Shutdown of Remaining Equipment

10B Special Shutdown

Power Reduction and Going Subcritical
Draining and Flushing the Fuel System

Shutdown of Remaining Equipment

SHUTDOWN OPERATIONS
11A Fuel or Flush Salt Transfers

W &0 12 vy &~ W v M

e e e e
= W N = O

Preparation for Transfers
Transfer from FD-1 to FST
Transfer from FD-2 to FST
Transfer from FFT to FST
Transfer from FST to FD-1
Transfer from FST to FD-z
Transfer from FST to FFT
Transfer from FD-1 to FD-2
Transfer from FD-2Z to FD-1
Heatup of FST

Heatup of Line 111

Heatup of Waste Line 112
Heatup of Fill Line 203

Heatup of Transfer and Salt Addition Freeze Valve Assemblies
12

13

XV

11B Opening Reactor Cell, Drain Tank Cell, and Coolant Cell Shields
1 Reactor Cell Heater Shutdown Check List
2 Drain Tank Cell Heater Shutdown Check List
3 Coolant Cell Heater Shutdown Check List
b Cooling Water Shutdown Check List
5 IFreeze Valve Shutdown Check List
6 Component Cooling Air to Components Shutdown Check List
T Component Cooling Pumps Shutdown Check List
8 Electrical Breakers Shutdown Check List
9 Opening Reactor Cell and Drain Tank Cell
10 Opening the Coolant Cell
11C Graphite Sampling
11D Routine Inspection and Testing of Equipment
1 Process Systems
2 Auxiliary Systems
3 Pregsgsure Relief Valves
L Rupture Discs
5 Reactor Cell and Drain Tank Cell Containment Vessels
6 Secondary Contaimment Vessels
ROUTINE OBSERVATIONS
12A Logs
12B Check Lists
12C Recorders and Indicators
12D Computer
12E Tags and Signs
MAINTENANCE AND CHANGES
13A Maintenance
13B Modifications
13C Changes in Operating Procedures

13D
13E

Changes in Computer Program

Revisions of Approved Documents
Approved by ...+ "’-'5:"“\‘/{"/‘ At el 1 9/2/65
. " 7

MSRE DESIGN AND OPERATIONS REPORT

Part VIII
OPERATING PROCEDURES

R. H. Guymon

1. Introduction

The first draft of the operating procedures was written during design
and construction of the reactor as an aid in producing a complete, work-
able design. This draft was then used during operator training, for
prenuclear shakedown of the reactor, and for the zero-power nuclear
experiments. During this time, changes were made in the master copy as
the need arose. The present issue is the result of a comprehensive
review and updating, and incorporates all changes and additions found

necessary up to the beginning of power operation.
Y 'J f,f

Approved by;gfij?z/jgyfl@y'g‘fi§«\ 14-1
V 9/2/65

1A EXPLANATION OF THE OPERATING PROCEDURES

The- prime purpose of this part of the MSRE Design and Operations
Report is to aid in the training of operating personnel and to provide
readily available reference material needed for operation. Details which
are not thought to be needed in normal operation are omitted. These can
be found in the other parts of the Design and Operations report and in the
material referenced in Section_lB.

Section 2, Nuclear Aspects of Operation, gives a simplified discussion

of basic nuclear facts, explains the nuclear behavior of the MSRE and sets
down the wvalues of characteristic properties.

Section 3, Operation of the Auxiliary'Systems, covers in detail the

operation of each auxiliary system. In order to avoid repétition with
section 4, not all line, valve, switch or instrument numbers are enumerated,
but often they are referred to in general terms or as groups (such as

"The cooling water is turned on to all space coolers.") However, when

it adds to clarity the numbers are also given. In general, flow rates,
utemperatures, pressures, etc., are not given but are covered by the

startup check lists, log sheets, run instructions, and daily shift in-
structions.

Section 4, Auxiliary Systems Startup Check ILists, covers the minute

details necessary in getting the auxiliary systems ready for startup.

The position of each valve and switch is listed, and a test for each
instrument under actual or simulated operating conditions is described
in detail. The check lists are written in logical order for each system;
however, since there is an interdependence between systems, it may be
necessary to do portions of one check list before portions of another.
When logical sequence permits, all operations in a physical area are
listed together in order to expedite completion of these lists. All
items in this section must be completed before each startup unless the
omission is approved by the operations chief.

Section 5, Reactor Start Up, covers the actual startup of the

reactor and operation at power. FEach step is outlined in detail. All

instrument settings and switch and valve positions are given. This
Approved by /fifiéfi%&m\ 2
9/2/65

section is written in chronological sequence and tells what is to be done,
when it can be done, why certain precautions are necessary, and suggests
corrective action in case of difficulty.

Section 6, Sampling and Adaptations, describes all samples which are

to be taken, frequency of sampling, analyses to be made and allowable
limits. Details of sampling procedures are given. 5alt additions,
chemical additions, etc., are described.

Section 7, Heat Balance, describes the method used to determine the

power being produced by the reactor.

Section 8, Instrument Calibrations and Operation, gives the procedure

used to periodically check the safety circuits and other instrumentation
and assure that they are functioning properly.

Section 9, Unusual Operating Conditions, attempts to anticipate

possible difficulties and suggest corrective action to be taken.

Section 10, Reactor Shutdown, describes in detail normal and

special shutdowns of the reactor and lists possible causes for a shutdown
and actions to be taken by operating personnel.

Section 11, Shutdown Operations, provides procedures for operational

activities involved while the reactor is shut down including graphite
sampling.

Section 12, Routine Observations, describes the taking of data,

marking of charts, storing of data, logging equipment, and other routine
duties of the shift personnel.

Section 13, Maintenance and Changes, describes the methods used for

getting maintenance done safely and for making modification to the system

or to approved documents.
Approved by W/‘a/ V“'}t/ /t«m/\

1B -1
9-2-65

1B LIST OF OTHER MATERTIAL AVATIIABLE

The MSRE is well documented with drawings and reports to cover all

phases of

information is needed routinely for operation of the reactor.

following
personnel.
1.

Not all of this
The

the design, development, and construction.
list has been compiled expressly as an aid to operating

MSRE Design and Operations Report

ORNL- M- 728 Part I Description of Reactor Design
ORNIL~TM-T729 Part IT Nuclear and Process Instrumentation
ORNL-TM-730 Part ITI  Nuclear Analysisl
ORNL-TM-T31 Part IV Chemistry and Materials
ORNIL~TM-T732 Part V Reactor Safety Analysis Report
ORNL-TM-T733 Part VI Operating Lfifiits
ORNL-THM-907 Part VII  Fuel Hanaling and Processing Plant
ORNL-TM-908 Part VIITI Operating Procedures
ORNL-TM~909 Part IX Safety Procedures and Emergency Plans
ORNI~TM-910 Part X Maintenance Equipment and Procedures
ORNL-TM-911 Part XTI Test Program

Part XIT Iists: Drawings, Specifications,

Line Schedules, Instrument Tabulations
Miscellaneous Reports and Literature
MSRE Semi-Annual Repofts
MSR 63-36 Line Schedule
CF 60-10-62 T and C Electrical Standards and Graphical Symbols
CF 57-2-1
CF 63-6-30

Manufacturer's Literature (File)

Instrumentation Flow Plan Symbols
Design Data Sheets

Valve Tabulation _ .
Instrument Application Tebulation (Book)
Tnstrument Specification (Book)

Test Reports {Book)
Approved by ,fj??;y%zif?fl%fli_

L.

1B -2
. 9-2-65

ORNL Radiation Safety and Control Training Manual (Book)

ORNL Radiation Safety and Control (Book)
ORNL Health Physics Manual (Book)
ORNI, Emergency Manual (Book)
Miscellaneous Unpublished Information
Facts Book
Run Instructions (Book)
Shift Instructions (Book)
Calibration Curves (Book)
Log Books Previous Operations (File)
Logger Data (File)
Building Log (File)
Recorder Charts (File)
Rough Data From Previous Tests (File)
Daily Reports (File)
Run Reports (File)
Test Memos (File)
Thermocouple Tapulation Logs (Book)
Photographs 5f Construction (File)
Drawings
Process Flow Sheets
Fuel System
Coolant System
Fuel Drain Tank System
Off Gas & Containment Ventilation Systems
Cover Gas System
0il Systems for Fuel & Coolant Pumps
Fuel Processing System
Liguid Waste System
Cooling Water System
Ieak Detector System

D-AA-A-L0880
D-AA-A-40881
D-AA-A-40882
D-AA-A-40883
D-AA-A-4088L
D-AA-A-L40885
D-AA-A-L088T
D-AA-A-L40OBBS
D-AA-A-140889
D-AA-A-40890

Instrument Air Distribution One Line D-HH-Z-41782 & 41783
Approved by,223?fi224駧;?94dw

Maintenance Elementaries

Safety Circuits

Containment Circuits

Control Interlock Circuits

Master Control Circuits

Radiator Load Control System

Rod Control Circuits

Fission Chamber Drives

I.A.C. #1, F.O.P. #1 & C. O. P. #1

1B -3
9-2-65
Instrument Application Diagrams
Fuel Salt System D-AA-B-10500
Coolant Salt System D-AA-B-40501
Fuel Drain Tank System D-AA-B-40502
Cover Gas System D~AA-B-40503
0il System for Fuel Salt Pump D-AA-B-L0504
Sampler-Enricher System D-AA-B-40505
Ligquid Waste System D-AA-B-L40506
0il System for Coolant Salt Pump D-AA-B-40508
Water System D-AA-B-40509
Off Gas & Component Air Coolant Systems D-AA-B-40510
Fuel Loading & Storage System D-AA-B-40513
Chemical Processing System D-AA-B-4O51L
Containment Air D-AA-B-40515
Nuclear Instrument D-AA-B-40523
Annunciator Schematics
Main Control Board D-HH-Z-41723 & 41738
Auxiliary Bontrol Board E-HH-Z-L172k
Sampler Enricher D-HH-Z- 41726
Chem. Processing B-HH-Z-554TT
Sampler Enricher D-HH-Z-555775
Nuclear Control Board D-HH-Z-57k428
Instrument Power Distribution One Line E-HH-Z-41695

D-HH-B-57372-3
D-HH-B-5T7374-7
D-HH-B-5T7378 & 91
D-HH-B-57379-83
D-HH-B-57384-6
D-HH-B-57387-9
D-HH-B-57390
D-HH-B-57357
Approved by ,4€§¢55L€%§éfl¢aag
</

1B -4
9-2-65".
I.A.C. #1, F.O.P. #2 & C. 0. P. #2 D-HH-B-57358
Auxiliary A.C. Control Circuits D-HH~Z~-57359-63
Cover Gas System : D-HH-B-41759 & 63
Indicator Lamps D-HH-B-40516 &
Los545
Freeze Valves D-HH-B-57345-56
E.C.I. Connection Diagram
Fuel Salt System D-HH-B-40636
Coolant Salt System D-HE-B-40637-L40
Safety Circuits D-HH-B-41571
Annunciators E-HH-Z-41696 &

D-HH-Z-55589-91

Instrument Power Panels E-HH-D-5T7369-T70 &
E-HH-D-5T7364-67

Engineering Elementaries (Control Schematics)

Safety Circuits D- HH- B-57312-3
Containment Circuits D-HH-B-57314-7
Control Interlock Circuits D-HH-B-57318 &

| 57327
Master Control Circuits D- HH- B-57319-21
Radiator lead Control System D-HH-B-57322
Rod Control Circuits D-HH-B-57324-25
Fission Chamber Drives D-HH-B-57326
Instrument Air Compressors D-KK-C-41159
T.A.C. # 1 & 2, F.O.P. #1 & 2 & C.0.P.

#1 & 2 D-HH-D-57306
Auxiliary A.C. Control Circuits D-HH-Z-57307-311
Freeze Valve Control Circuits D-HH-B-57300-305
Block Diagrams

Master Control D-HH-B-57330-1
Rod Control | D-HH~B-57332-3
Radiator ILoad Control System D-HH-B-5733k4

Safety System D-HH-B-257335
Approved by235552324%?2;;f4¢4491
;7’

Coolant Salt System

Containment System

Auxiliary Process Control Systems

Freeze Valves

Electrical-Process Equipment--ILocations

Process Equipment Distribution System
(one line)

Auxiliary Power System One Line

480v Switchgear

Schematics Electrical

Electric Heating
Main Power-Electric Heating

Panels FP1, FP2 & RCH3 Reactor Cell
' Elec. Heating

Panels RCH-4, Hx1, Hx2 & Hx3 Reactor Cell

Elec. Heating

Panels RCH-1, 2 & T Reactor Cell Elec.
. Heating

Panels RCH 5 & 6, H 102¢2 Reactor Cell
Elec. Heating

Elec. Heating Distribution Panels R1-2 & 3

Fuel Drain & Flush Tank Heating

Elec. Heating - Radiator Inlet & Outlet

Elec. Heating - Radiator

Elec Heating - Radiator

Elec. Heating Distribution Panels
H200-13, H201-12, H202-2, Sp-1 & 16

Panel G5-2-% |

Distribution Panels G5-1A1 through

G5-1-A5

Panel 65-B5 Radiator Heating

Distribution Panels G5-1-Cl, €2, & C3

Distribution Panels G5-1D2, D3, & Dk

1B -5
9-2-65
D-HH-B-57336
D-HH-B-5T7337-8

D-HH-B-57339-41

D-HH-B-57342
D-KK-C-41139

D-KK-C-L41152
D-KK-C-4113k4
D-KK-C-41175-6

E-MM-C-51620
E-MM-C-L40850

E-MM-C-51618
E-MM-C-51619

E-MM-C-51698

E-MM-C-51699
E-MM-C-56234
E-MM-C-51655
E-MM-C-40818
E-MM-C-40822
E-MM-C-40823

E-MM-C-40840
E-MM-C-40828

E-MM-C-51653
E-MM-C-L40821
E-MM-C-5165k
E-MM-C-408L4L
Approved bY1523§3§%§é§;12ac4_

Panel T-1~A Elec. Heating

Panel T-1-B Elec. Heating

Panel T-1-C Elec. Heating

Distribution Panels T-2-V1, T-2-W1 & W2

Panel T-2-Y Elec. Heating

Elec. Heating Flush & Drain Tanks,
Panels G5-1-Al & A2

Panel G5-1-A5

Panel G5c-1-C2 Elec. Heating

Panel G5-1-C3 and D2 Elec. Heating

Panel G5-1-D3 & D4 Elec. Heating

Panel T-2-V1 Elec. Heating

Panel T-2-W2 Elec. Heating

Panel T-2-Wl1 Elec. Heating

13 KV Automatic Transfer

MG Sets 2 & 3

Heater Locations

Fuel and Coolant Salt Systems - Reactor
Cell

Coolant Cell - Fill Line 203
Coolant Salt System
Flush & Drain System - Drain Tank Cell

Radiator Heating

Thermocouple Locations

Fuel Pump & Overflow Tank

Heat Exchanger.

Fuel Storage Tank

Reactor Vessel

Coolant Salt Pump

Coolant Pump Float Level Indicator
Radiator

Radiator Cell

1B -6

G-2-65
E-MM~-C-40846
E-MM-C-4084T
E-MM-C-40848
E-MM-C-408L41.
E-MM-C~1408L49

E-MM-C-51662
E-MM-C-56236
E-MM-C-51665
E-MM-C-40845
E-MM-C-51673
E-MM-C-40839
E-MM-C-40842
E-MM-C-40843
D-KK-C-L1177
D-KK-C-55112

E~-MM-A-51600
D-MM-A-5T7492
E-MM-A-40832
E-MM-A-51660
E-MM-B-40802

D-HH-B-40525
D-HH-B-L40526
D-HH- B-40527
D- HH- B-10528
D-HH-B-40529

Sk-JWK-2-16-6k
E-HH-B-56283-4

D-HH-B-40530
Approved byizfifiifz/gfiéfirthg:gw

1B -7
o-9-2-65
Coolant Drain & Fill Tank D-HH-B-40532
Fuel Fill & Drain Tank No. 1 D-HH-B-40533
Fuel Fill & Drain Tank No. 2 D-HH- B-40534
Fuel Flush Tank D-HH-B-40535
Typical Freeze Flange D-HH-B-40542
Typical Freeze Valve GG-C-55509
Freeze Valves, | D-HH-B-40543
- Fuel & Coolant Salt Systems, Reactor Cell E-HH-B-L0536
~ Coolant Salt System, Coolant Cell E-HH-B-L40537
Flush & Drain System, Drain Tank Cell E-HH- B-L1771
Fuel Loading & Storage System Salt Lines E-HH-B-40553
Chemical Processing'System Gas Lines E-HH- B-40554
Heater and Thermocouple Locations
 Fuel Drain Tank Cell E-MM-A-148758
- Reactor Cell | E-MM-A-48759
Coolant Cell E-MM-A-48760
FD-1, FD-2, and FFT E-MM-A-L48762
Radiator E-MM-A-L48T76L4
Reactor Vessel E-MM-A-L8T765
Panel Drawings
Console E-HH-B-40568
Main Control Board E-HH-B-40555
Auxiliary Control Board D- HE- B-L064L
Transmitter Panels E- HH- B- 40642
Sampler Enricher Panesl D-HH-Z-41720
. Water Panel b—HH—B-uo6u5
0il Panels D-HH-B-L41722
* Jumper Panel | E-HH-B-57L400-3
T. C. Scanner Panel . D-HH-B-41648 & 61

Cover Gas System Panel D-HH-B-41757 & 61
| P
Approved bygéfi?éi‘ TN
'v

1B -8
9-2-65
Containment Air Panel D-HH-Z-L40621 &

55559
Diesel Panels - Local & Remote D-KK-C-41178
Diesel Panels - Switch House : | D-KK-C-55151
Diesel Panels Auxiliary Control Room D-KK-C-55152
Heater Control Panels E-MM-Z-5162k
Motor Control Center T-1, G3 & T-2 D-KK-C-41160
Motor Control Center G5-1, Gb & G5-2. D-KK-C-41161

MG Sets 2 & 3 Control Panel D-KK-C-55108
Approved by'figzz Z%é%%%%f}vvfifl\_ 7/23/65

SECTION 2

NUCLEAR ASPECTS OF OPERATION

Nuclear safety has been designed into the MSRE. Furfihermore,
qualified operators must have a working understanding of the consid-
erations involved in nuclear operation, in order to operate the reactor
in a manner which is both safe and efficient.

The purpose of this section is to provide information to which the
operator can conveniently refer for a review of the nuclear aspects
of the operation of the MSRE. First, there is a simplified explanation
of how uranium can be made to produce heat in a controlled manner through
a nuclear fission chain reaction. Then the specific characteristics of
the MSRE are discussed briefly. This includes a discussion of how the
nuclear instrumentation and controls work, how the nuclear power responds
to the controls, and why precautions must be taken in the management of
the fuel. The subject of radiation safety and control is not covered
completely, since adequate treatment would be lengthy and is readily

available to the operator in other publications.
Approved by. e 2A-1
7/21/65
2 A SIMPLIFIED REACTOR THEORY

This section, of necessity, gives only a very simplified and
somewhat sketchy treatment of reactor theory and those areas of nuclear
pPhysics which are important in reactors. Convenient and fairly simple
treatments of these fields are given in books by Glasstonel;2 and

3

Stephenson~.

1  GIOSSARY

Words peculiar to nuclear physics or reactor theory which will be
used are defined as follows: _

age - a measure of the distance traveled by a neutron while slowing
down by collisions with nuclei in a given material.

atom - the smallest particle of matter retaining its chemical
identity, composed of a nucleus surrounded by orbital electrons.

atomic weight - the weight of an atom expressed in atomic mass

units. The atomic weight is approximately equal to the combined number
of protons and neutrons in the nucleus.

atomic mass unit (a.m.u.) - one-sixteenth the weight of an oxygen

atom.
barn - a unit of area equal to 10-2u sq. cm. (This is the order of
magnitude of the cross sectional area of a nucleus.)

beta particle - a high-speed electron emitted when a fmcleus

undergoes certain internal changes.
blanket - a region surrounding the core of a reactor, whose

function is the useful absorption of neutrons.

s, Glasstone, Sourcebook on Atomic Energy, Van Nostrand, 2nd ed, 1958

28. Glasstone, Principles of Nuclear Reactor Engineering, Van Nostrand,

1955

3R. Stephenson, Introduction to Nuclear Engineering, McGraw-Hill,

ond ed., 1958.
Approved by Op=D

T/21/65

buckling - a factor in the spatial distribution of the neutron
flux, characteristic of the size and geometry of a reactor.
capture - an event in which a neutron enters and remains in a

nmacleus.

€hain reaction - a reaction in which one event triggers or produces

another similar event.
core -~ the heart of a reactor, in which the chain reaction is
sustained.

cross section - a measure of the probability of a nuclear reaction.

criticality - a condition in which each fission produces exactly

one other fission.
decay - radioactive disintegration.

diffusion length - a measure of the average distance a neutron

moves from the time it reaches thermal energy until it is absorbed.

e-folding time - same as period.

electron - a particle with a unit negative charge and a mass of

0.00055 a.m.u.
electron volt (ev) - a gquantity of energy equal to 1l.52 x 10-22Btu.

fission - a reaction in which a nucleus splits into two or more

heavy fragments.

fission product - a nuclide produced by fission (most are radio-

active).

flux ~ the product of the number of neutrons per unit volume and
their speed.

fuel -~ fissionalbe material.

gamma ray - high-energy electromagnetic radiation.

generation time - the average time between sequential fissions

in a chain reaction.
isotopes - nuclides having the same number of protons but different
numbers of neutrons.

moderator - material used to slow down neutrons.

multiplication factor - the ratio of fissions in successive

generations of a chain reaction.
Approved by.fifzr *fié;'*“fl\ 2h-3

T/21/65

neutrino - a neutral particle emitted in conjunction with a beta

particle.

neutron - a neutral particle having a mass of about 1 a.m.u.

nucleus ~ the dense core of an atom, composed of protons and neutrons.

nuclide - a species of atom characterized by the numbers of neutrons
and protons it contains.

period - when the neutron density is changing exponentially, the time
to change by a factor of e (e = 2.72).

finnmpt neutron lifetime - the average time between the birth of a

fission neutron and its ultimate absorption.
proton - a particle with a unit positive charge and a mass of about
1l a.m.u.

radiocactive - subject to spontaneous change of the nucleus, usually

by emission of a beta particle and gamma rays.

reactivity - the quantity (k - 1)/k where k is the multiplication

factor.

reflector - material added on the outside of a reactor to reflect

neutrons.

resonance energy - a neutron energy range in which the probability

of reaction is véry high.

scattering - an event in which a neutron interacts with a nucleus to

change its direction and speed.
2 ATOMIC STRUCTURE

The world around us is made up of a wide variety of substances.

Each "chemically pure" substance is comprised of molecules, each identical
with all otheré of that substance. The molecules in turn are combinations
of atoms, an extremely small unit of matter (~lO-8cm). An atom contains

a nucleus, whose diameter is only about 1/10,000 of that of the atom,

but which contains nearly all of its mass. Around the nucleus are orbiting
electrons, negatively charged particles with little mass. The nucleus,
which is positively charged, contains protons and neutrons. The nuclear
particles (nucleons) are about equal in mass, but the proton has a positive
charge, equal in magnitude to the negative charge of the electron, while

the neutron is uncharged. The atom is neutral, having as many negative
g2 o
Approved byfflégr {?V”fiffl 7/21/65

electrons as positive protons.

A nuclide is comprised of all atoms having the same number of
neutrons and the same number of protons. WNaturally occurring nuclides
range from normal hydrogen, whose nucleus is simply a proton, to uranium-
238, which has 92 protons and 146 neutrons in its nucleus.

Atoms of any one element all have the same number of protons énd
orbital electrons. Because chemical properties are determined by the
orbital electrons, all atoms of an element are chemically alike. But
not all atoms of an element necessarily have the same number of neutrons.
Nuclides of the same element with different numbers of neutrons are called
isotopes of that element.

An exafiple of isotopes is shown in Fig. 2A-]1, which depicts
schematically the two isotopes of lithium. Both have 3 protons and 3
el$ctrons, and behave alike chemically. But Li6 has 3 neutrons and
Li

number of nucleons or the atomic mass number.) This difference in the

has 4, (The superscript number on the element symbol is the total

number of neutrons causes these isotopes to have quite different nuclear
6

properties--Li is 30,000 times more likely to absorb a neutron, and it is

for this reason that separated LiT is used in the MSRE salt manufacture.

(Natural lithlum is comprised of 92.5% Li7 and T.5% Li6.)

6 :
Ii  atom. LlT atom.

Fig. 2A-1 Representation of Two Isotopes of Lithium.
Approved by /ffgégéfii;gmw«. 2A-5
| V4 7/21/65

The positively charged nucleus is held together by extremely strong
short-range forces, while the electrons are much less fightly bound to the
atom by attraction to the positive nucleus. In chemical reactions, which"
involve the orbital electrons, the energy for a reaction is on the order
of a few electron volts (ev). Much more energy (on the order of millions
of electron volts) is involved in changes in the nucleus because of the
stronger forces of attraction. 1Indeed, so much energy is involved that
a nuclear reaction can produce a significant change in mass of the re-
acting pérticles as mass is converted to energy, or vice versa. (The
conversion follows Einstein's famous E = mcg.)

Consider Figure 2A-2, which is a plot of the mass per nucleon (the
ratio of nuclear mass to atomic number, or number of nucleons) against
atomic number. It is seen that the average mass of nucleons in nuclides
of intermediate number is significantly less than the averages at either
end. A consequence of this is that if heavy nuclides can be split to
form lighter fragments the total mass decreases. The difference appears
in the form of energy. This is the basis of power from nuclear fission.

(Fusion involves building up from the low-A end of the scale.)

Mass per
Nucleon

A, Atomic Number

Fig. 2A-2 Average Mass per Nucleon

3 RADIOACTTVITY AND RADIATION

The number of nucleons in naturally occurring muclides covers a wide

range, from 1 to 238. But if one plots the number of neutrons against
the number of protons in each naturally occurring nuclide, it is found

that all of the points lie in a rather narrow band as shown in Fig. 2A-3.
Approved by 4:///,5449/741,»;\ "
4 T/21/65

146

Number of
Neutrons

Stable

Number of Protons

FPig. 2A-3 DNuclear Composition of Naturally Occurring Nuclides

Some nuclides found in nature are radioactive; that is, the nucleil
may spontaneously change, or "décay.'" ©Nearly all of these naturally
radiocactive nuclides are at the heavy end of the band and decay by the
emission of an alpha particle from the nucleus. An alpha particle
consists of two protons and two neutrors (identical with a helium-4
nucleus), so this type of decay produces a nuclide nearer the stable band.

The fact that the band in Fig. 2A-3 is curved has an important
implication. If a heavy nuclide is split, or fissioned, the fission
£ragment nuclei usually have a composition near the straight line joining
the original point to the origin. Thus the primary fission products
usually lie outside the stable band, on the side of too many neutrons,
and are radioactive. The tendency is for change toward the stable band,
sometimes by emission of a neutron from the nucleus but much more often
by the process called betg decay. In this process a high-speed electron
(beta particle) is emitted from the nucleus, reducing the number of neutrons

by one and adding one to the number of protons.

4
ApprovedAbyfléngigéiz;z{»qfiL, 7, | DA-T
* 7/21/65

Another process (besides fission) which can prodnce radioactive
nuclides is neutron absofption. A passing neutron may be absorbed in
almost any nucleus (the probability of absorption varies widely,
howevér). When fhis happens, a certain amount of energy, called the
binding energy of the added neutron, is immediately released, usually in
the form of gamma rays, called capture gammas. The new nucleus, containing
the added neutron, may be stable or it may be radioactive. Radioactivity
produced by neutron absorption is called induced radioactivity, or the
material is said to be activated. TInduced radioactivity is usually in
the form of beta decay.

Beta decay is always accompanied by the emission of a neutrino. The
neutrino is a particle with very small mass, which 1s so unlikely to
interact with matter that it is extremely difficult to detect. Neu-
trinoés are important in a reactor only in that they éarry away a sig-
nificant amount of energy in a form which is not recoverable.

Most radioactive decay processes, whether they be alpha decay or
beta decay, are accompanied by the emission of gamma rays, calied decay
gammas.

Radiocactlive decay is a statistical process, that is, the rate can
be predicted only for large numbers of nuclei. The probability that a
nucleus will decay in a given interval of time is.called the decay
constant, usually represented by A. Thus, when there are N nuclei of a
of a radicactive nuclide present, the fate of decay is NA disintegrations
Per unit time. If there are N nuclei at a particular time, then a time t
later there will be No e_kt nuclei remaining.

-At
N =N, e

This formula means that the number of nuclei present (and the rate of
disintegration) decreases by a certain fraction in any equal lengths of
time. The time required to decrease by a factor of two is the half-life.
Half'-lives of fission products range from a fraction of a second to many
years. Naturally occurrifig radicactive nuclides are usually very long

4235

lived. For examplec decays by alpha emission with a half life of

TO0 million years.
P
Approved byléfifiaéizéiéy%Z/fl DA-8

T/21/65

Amounts of radicactive material are usually expressed in units of ¢
curies. A curie is defined as the mmount of material which undergoes
3.7 x lOlO disintegrations per second.

Alpha particles, beta particles and gamma rays all deposit energy
and cause local damage along their path through matter. This can cause
problems of heating, changes in physical properties of materials and
bioclogical injury.

Charged particles give up energy as they move through matter by the
process of ionization. The charged particles and the orbital electrons
exert forces on each other which slow down the moving particle and draw .
many electrons from their atoms, leaving positively charged atoms oxr
ions. Thousands of ion pairs must be formed in the course of stopping
an alpha particle or a beta particle, but in ordinary matter this will
occur in a short distance. Thus charged particles have a limited range.
For example, a 1-Mev beta can travel O.1lL in. in water (or flesh).
Alpha particles produce more dense ionization, and the range of a l-Mev
alpha in water is only 0.0002 in.

Gamma rays do not ionize directly since they are electiromagnetic
vadiation with no charge. They interact through any of three processes
to produce high~speed electrons which in turn ionize the medium. The
gammas always travel at the speed of light, but their energy can be
decreased, even to zero, by scattering collisions with electrons. (Tt
is useful for some purposes to think of gammas as particles since they -
have direction, energy and momentum and can have collisions.) The |
linear rate of energy loss by gammas in matter is far less than that of
charged particles. Consequently they do not have a definite range.
Instead the intensity of a stream of gammas falls off exponentially with
distance through matter.

I=1, e ¥

Shielding consists of absorbing the energy of radiation in material
interposed between the source of the radiation and objects which are to

be protected from the erlfects of the radiation.

LI
'

e

wo 2A-9

Approved by 7/21/65

L  THE FISSTION PROCESS

There are some nuclides in which the nucleus will fission, or split
into a number of smaller particles, when a neutron collides with it.

Some nuclides, such as U238, will fission only if the neutron is travelling
at very high speed; neutrons of any energy will cause certain other
nuclides to fission. U235, which is fissionable with neutrons of any
energy, is the fuel in the MSEE.

In the fission process, a neutron enters a nucleus, causing so much
disturbance that the forces which hold the nucleus together are overcome
and the nucleus splits into two or more smaller nuclei or fission frag-
ments. The exact manner in which U235 nuclei split is not always the
same, but in most fissions the nucleus (atomic mass 235) bresks up into
two unequally-sized particles having atomic mass numbers around 95 and
140. Tn addition to the fission fragment nuclei, there are many other
smaller particles resulting from the fission. These are bets particles,

gamma rays, neutrinos and neutrons. On the average, the fission of a
U235 nucleus gives off 2.5 neutrons and it 1s this fact which makes a

chain reaction possible, since these new neutrons, if they are properly
handled, can cause other fissions.

Nuclear fission is important because of the relatively large amount
of energy released in the process, compared to the energy available from
chemical reactions, which involve only the loosely bound orbital electrons.
To illustrate, when a carbon atom burns, or combines chemically with an
oxygen molecule, the energy released is 4 ev. In contrast, when a single
U°3° micleus fissions, the total energy released is about 200,000,000 ev
(200 Mev). The distribution of this energy is shown in Table 2A-1. All
of this energy eventually appears as heat, but not all of it in places
where it can be utilized. The fission fragments are all slowed down and
stopped within a few thousandths of an inch, so their energy appears as
heat essentially at the point of the fission. Beta particles have a
range of only an inch or less. Neutrinoes, on the other hand, travel such
great distances without creating heat (or leaving any trace) that as far
as power production is concerned they might as well not even exist. A

fission neutron usually gives up its energy in a series of collisions
‘<3€y9f
Approved by;fiégfiéjk 6224%2f7 2A-10

7/21/65

along a zigzag path a few feet long; A gamma ray may penetrate as much
as several feet in a straight line before its energy is converted to
heat. The available energy in Table 2A-1 is the estimated amount which
produces useful heat in the MSRE*. The rest of the energy escapes and

appears as heat in the shield or elsewhere outside the reactor.

Table 2A-1 Distribution of Fission Energy

Energy, Mev

Total Available
Kinetic energy of fission fragments - 168 168
Kinetic energy of fission neutrons 5 4
Instantaneous gamma rays T
Gamma rays from fission product decay 6 5
Beta particles from fission products 8 8
Neutrinos 11 0

\ - 205 192

Although most of the fission heat is generated practically instanta-

neously, the beta particles and gamma rays from the fission products are

*the that Table 2A-1 lists only the energy directly produced by fission.
In a reactor there is also energy produced by non-fission capture of
neutrons which produces gamma rays at the instant of capture and gamma
and beta rays by the decay of the capture products. The ratio of
captures to fissions depends on the reactor; in the MSRE this source
releases about 6 Mev/fission, nearly all of which appears as useful

heat.

4
2 ¢

Approved byg“ffizfié%;//bwzfl 2A-11
a < 7/21/65

liberated over a period of time by radicactive decay. The fission prcducts
are a mixture of nuclides with half lives ranging from a fraction of

a second to many years. Thus, in a nuclear reactor the heat source from
the fission product decay decreases after the fission reaction is stopped,
rapldly at first, then more slowly and never completely dying out. The
energy release after shutdown, called "afterheat", is a serious problem

in high-power reactors.

Nearly all of the fission neutrons, are emitted almost instantaneously,
but a few are liberated by the decay of certain short-lived fission product
isotopes, called precursors. These delayed neutrons comprise only 0.6L4
per cent of the total neutrons, and they are nearly all emitted within
the first minute after a fission, but they play an important part in
making the fission chain reaction more easily controlled, as will be
seen later.

Although the amount of energy produced per fission is large compared
with that in chemical reactions, the absolute amount is so tiny that an
extremely large number of fisslons must occur to produce a useful amount
of heat. (198 Mev is only 3.0 x lO-lh Btu. At 198 Mev/fission, the
fission rate required to produce 1 watt is 3.16 x 101° fissions/sec.)

To illustrate, when the MSRE is operating at a nuclear power of one

megawatt, about one trillion (1012) fissions occur each second in each

cubic inch of fuel salt. The important consequence of such high fission
rates is that the laws of probability apply very well, so the analysis
of the nuclear behavior of a reactor can be based upon probabilities. .

5 CROSS SECTTONS AND REACTION RATES

Tn the calculation of rates of reaction between nuclei and neutrons,
use is made of probabilities expressed in terms of nuclear cross sections.
The following illustration is helpful in understanding the significance
of the term "cross section". Consider a thin element of volume containing
a number of spheres (nuclei) as shown in Fig. 2A-4. TIf a neutron, which
can be pictured as a tiny projectile, enters perpendicularly to a face,
the chance that it will collide with a sphere is equal to the fraction
of the area o0f a face covered by the circles which are the projections

of the spheres.
» |
Approved by Afi?fifiLév%%/)fif7)_ - 2A-12

7/21/65

This fraction is

N a2 ix ¢ = No dx

2
a

Since this is the probability that a neutron will suffer a collision

while traveling a distance dx, the probability per unit distance traveled
is found by dividing by dx. This probability of collision per unit
neutron path length, No, is called the macroscopic cross section,

symbolized by Z, with dimensions of reciprocal length.

Figo 2A-L|'
e
r = radius of sphere ~{L

2 *
g = Ar = cross sectional
area of sphere

N = number of spheres per

unit volume i a i
Na2 dx = number of spheres cp oYe) —!-
in volume element O o a
O o] |

Now picture a box containing nuclei and randomly moving neutrons
as shown in Fig. 2A-5. The combined distance traveled each second by
all the neutrons in the box is a3nv° (Assume the neutron density in
the box is not changing, so if some of the original neutrons leave,
others come in to take their place.) The path length per unit volume

3

per second is a”nv divided by the volume, a3. This quantity is called

the neutron flux, ¢.

neutrons eutrons\
¢ = nv
- sec

Since the number of collisions per unit path length is Z, the rate of
collisions per unit veolume is the product of the path length per unit
volume per unit time and the probability of a collision per unit path

léngth;fi

LI}
_ |
Approved b312§;§522;/§2/hmgv 2A-13
4

7/21/65

collisions neutron-cm collisions
R 3 = ¢ 3 X 2
cm~ - sec cm~ -~ sec neutron - cm
Fig. 2A-5
n = number of neutrons per

unit volume

-\-—w—A

v = gpeed of neutrons
33n = number of neutrons
in volume element
The foregoing picture of cross sections is inadeguate in several
respects.

In the first place, the experimentally determined cross sections
show that for most isotopes the effective neutron target area, o, is
many times the actual nrg of the nucleus. Further more, ¢ varies with
neutron speed, usually in such a way that the nucleus appears to present
to passing neutrons a target which becomes larger the slower the neutron.

Another difficulty with the simple picture is that a neutron may
undergo any of several different reactions with nuclei of a particular
type; The fission reaction has already been mentioned. Another reaction
is radiative capturé, in which the neutron is absorbed and a gamma ray
is emitted from the ndcleus. A neutron may also undergo an elastic
scattering or "billiard ball' collision with a nmucleus. The nucleus
has a different probability or cross section for each type of reaction,
and in geheral 2ll the cross sections vary with neutron velocity. Cross
sections for different reactions are identified by subscripts; f for
fission, ¢ for radiative capture, a for absorption, s for scattering and

%
+ for total .

* .
Absorption includes both fission and radiative capture. Total includes

absorption plus scattering. Thus o5 = op + Oy and o, = 0, + O
2A-1k4
7/21/65

In view of the inadequacy of the "hard sphere' picture of neutron-

Approved by 7 -

nucleus collisions, it is perhaps best to think purely in terms of
probability. The probability that a neutron, while passing a unit

distance through a region inhabited by N nuclei per unit volume, will
undergo a particular reaction is No, where ¢ is a measure of probability
whose magnitude depends upon the type of nuclei, the type of reaction and
the neutron speed. The probabilities are additive, i. e., the probability
that a reaction of some sort will occur is the sum of the probabilities for
reactions of all the possible types. For exampie, in a region contaihing

two types of nuclei identified by subscripts 1 and 2

= — +
Za Zal * Za2 ngal Néan

Z,= N (o0 +0,) + 0, (0., + 0,)

It follows that the fraction of the absorptions which occur in nuclei of

type 1, say, is

+
Za Zal Za.2

6 THE FISSION CHAIN REACTION IN AN INFINITE REACTOR
235

Because each U fission releases, on the average, 2.5 neutrons

the feasibility of a self-sustaining chain reaction would at first seem
obvious, &ince to maintain such a reaction only one of the 2.5 neutrons
need cause another fission. However, a practical reactor must contain
materials other than fuel and these other materials absorb part of the
available neutrons. Furthermore, a certain fraction of the neutrons will
escape from the reactor without reactinhg. Therefore, the primary problem
of reactor theory is the specification of materials and an arrangement
which will conserve neutrons and result in a self-sustaining chain reaction.
Such an assembly is a reactor.

The chances that a neutron will escape from a reactor decrease as

the reactor is made larger, of course. The leakage probability is also
i)

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Approved byjfjg;jgyéé§97fikflfl 2A-15

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reduced as the macroscopic cross section of the materials is increased.
Thus a self-sustaining chain reaction is possible in a small reactor if the
macroscopic cross section is adequately large. This requires either a

high concentration of fuel or a large microscopic cross section. Because

fission and absorption cross sections are much larger for slow neutrons
than for fast, most reactors utilize slow neutrons.* This is done by
ineluding in the reactor a substance, having a low atomic weight, a large
scattering cross section, and a small absorption cross section. This mate-
rial, called the moderator, slows down (moderates) the fast neutrons by
elastic scattering. It also helps to conserve neutrons by diverting those
that are headed out of the reactor. (Sometimes material with a hggh
scattering cross section is added around the outside of a reactor for the
sole purpose of scattering back or "reflecting" neutrons which would
otherwise escape. This is then called a reflector.)

In order to see how the requirements for a self-sustaining chain
reaction can be calculated, let us consider the various fates which may
befall a neutron in a reactor which contains fuel, moderator and other
neutron-absorbing material. There are several things that can happen and
they all affect the chance that one of the neutrons emitted in a fission
will survive to cause another fission. First, we will examine how the
individual probabilities of the different events combine to give the
overall probability of a fission neutron causing another fission. Then
we will see how the probabilities are determimed by the materials and
geometry of the reactor.

For simplicity, first consider the case of a reactor which we imagine
is so large that leaRage can be neglected. (Infinite reactor case.)
Suppose we begin with a large number, say x,'neutrons which have just been

235

born in U fissions caused by slow neutrons. (Refer to Fig. 24-6)

Some of these very fast neutrons will collide with uranium nuclei (either
235 238
U or U =)

the total number of fast neutrons will be increased by a factor, €, called

and result in fissions which produce more neutrons. Thus

%
Most reactorssutilize "thermal"” neutrons, i.e., neutrons which have been

slowed down until they reach an energy range fixed by the temperature of

the medium.
2,
Approved by4¢£§fiéé;;?zz@fl7 2A-16

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the fast fission factor. Now if neutrons which have suffered a few col-~

238

lisions so their energy is in the intermediate range pass near a U
nucleus, the chances are they will be swallowed up in radiative capture.*
The probability that neutrons will be slowed down past the resonance energy
without being absorbed is called the resonance escape probability, p

After the neutrons have been slowed down to thermal energies, only a
fraction are absorbed in U235. This fraction is the thermal utilization
factor, £ . (In an infinite reactor the remainder of the neutrons are

U235 are radiative

absorbed in other materials.) Some of the abéorptions in
capture, while others result in fission with a production of v neutrons per
fission. Thus one cycle is completed. The ratio of the neutrons present
after one cycle, or generation, to those present initially is called the
infinite multiplication factor or reproduction factor. (It is called
infinite because it applies only to a very large reactor where leakage

is negligible.)

The average number of fission neutrons produced per neutron absorbed
in U°3 is called eta (1), and for the absorption of thermal neutrons it
has a value of 2.08. The fast fission factor is a function of the ratio
of moderator to fuel, approaching unity for large values of the ratio.

The resonance escape probability also is a function of moderator-to-fuel
ratio, increasing to unity as the ratio increases. The thermal utilization
factor, in a homogeneous reactor, is just the ratio of the macroscopic
absorption cross section of the fuel to the total cross section of all the
components in the reactor. Even though only a very small fraction of

235

, the thermal utilization factor 1is usually

235

the atoms in a reactor are U
greater than 0.8 because the cross section of U is so high compared
with the other nuclides in the core. (Typical values are 690 barns for
U235; less than 0.01 barn for Be, C, or F.) Because in a heterogeneous
reactor the fuel, moderator and structure are not exposed to exactly the
same flux of neutrons, €, p, and f are all dependent on the size and

spacing of the fuel and moderator regions.

* 238
F'or neutrons of intermediate energy, U 3 has a very high cross section for

radiative capture. This 1s referred to as the resonance energy range.
’1

Approved by/fi225z32/%£?’ fiQZfl? 2A=-17

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X fast neutrons from slow neutron fission of U-235

increase due to fast fissions

xe | fast neutrons from both slow and fast fissions
l\\Xe(l-p) neutrons absorbed in U-238 in resonance energy range
XEP | neutrons slowed down to thermal energy range
\\Xép(l-f) thermal neutrons absorbed in materials other than U-235
xepf thermal neutrons absorbed in U-235
\“xe pf crc/oa radiative captures in U-235
xe pf Gf/Oa fissions in U-235 caused by slow neutrons
xe pf vcf/oa fast neutrons from slow neutron fission of U-235
i xevacf/ca
X
no= v Of/Oa
k = n € pf

Fig. 2A-6 Fission Chain in Infinite Reactor (No leakage)

T  EIFFECT OF NEUTRON ILEAKAGE

Because a significant fraction of £he_neutrons escape from even large
reactors, the neutron leakage probabilities must be considered in calcula-
ting the multiplication factor which can actually be attained.

Iet us suppose that l-pl, is the probability that a fast neutron will
leak out of the reactor before it is slowed down or absorbed. Then Pl
is the fast non-leakage probability. There is a probability that a neutron
can escape from the reactor after it has become thermalized, and a slow

non-leakage probability, PQ’ can be defined. With the Inclusion of leakage

}
"":F) /'/
Approved by 7 447 AN 2A-18

7/21/65

probabilities, the diagram of the chain reaction becomes as shown in Fig. 2A-T7.

-_7 M\

X€ (l—Pl)
[\\‘-- X€ P (1-p)
xe P pP
1\‘ xe P.pP (1-f)
T
xe PlpP
P.pP T
XG lp Y
xnepf P P
- 12
K = = = kw P1P2

Fig. 2A-7 Fission Chain Reaction in a Finite Reactor
The non-leakage probabilities depend on the size and compbsition of
the reactor. Two-group diffusion theory, a simplified mathefiatical descrip-
tlon of neutron slowing down and diffusion, gives the follow1ng expressions

for P, and P, in an unreflected (bare) reactor.

1 2
1
P =
1 1+ Baf
1
P, =
L + L2B2

These will serve to illustrate the‘dependence of Pl and Pgon the physical
dimensions and properties of the reactor.
2
The factor B, called the buckling, is a function of the reactor size

and shape. For a bare, cylindrical reactor of radius R and height H.

-

L J
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2A-19

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Approved by ééjf?jadg/;fi?cfihmn T/21/65

2 2
2 _ 20405\ NE

R H

It can be seen that if the dimensions are made larger, 32 decreases rapidly

and_P:L and P2 increase.

T , called the age, is determined primarily by the moderator. It is
equal to one-sixth the mean squere of the distance traveled by a neutron
fihile slowing down. L is cclled the thermal diffusion length, and L2 is
one-sixth the mean square of the (crow-flight) distance a neutron covers
from the time it reaches thermal energy until it is captured. L2 is given
approximately by

2 1

L. =
3T %

where ZS and Za are the scattering and absorption cross sections of the
reactor material. Reduction of T by introduction of more efficient
moderator material and L2 by either better scattering or more absorber

reduces P_. and P 0
1 2

8 CRITICALITY

In the preceding sections we followed a group of neutrons through one

cycle, or generation, and derived a quantity, k, which is the ratio of
neutron production in successive generations. It 1s clear that if X = 1,
the fission chain reaction is self-sustaining and the neutron population,
the flux, the fission rate, and all reaction rates will be stationary in
time, without any contribution from neutron sources other than fission. The
critical condition is defined as that in which k = 1. Note that criticality
does not imply any particular power level, merely that the chain reaction

is exactly self-sgtstalning.

9 EXTRANEOUS NEUTRON SOURCES AND SUBCRITICAL MULTTIPLICATTION

Besides the fission process, several other nuclear reactions lead to

the emission of meutrons. Most important :of these are the interattion

of high-energy gamma rays or alpha particles with any of several materials,

the most important of which is Be9.
A»neutron source may be constructed using gamma rays from some fission

product, a neutron-activated material, or the natural radiocactive element,

radium. This is called'a photoneutron source, and the most common form

contains antimony-124 (60-day half-life, produced by neutron irradiation of
Approved by¢5§fl224}§3//¢£fly\ 2A~-20

T/21/65

123) and beryllium. An alpha-n source may contain a mixture of beryllium

Sb
with 138-day polonium-210 or long-lived radium or plutonium, all of which
emit alpha particles in their decay.

The MSRE fuel salt contains an inherent neutron source resulting from
interaction of alphas from uranium decay with the beryllium of the salt.

In addition, after fission products have built up in the reactor, a strong
photoneutron source will result from the fission product decay gammas
interacting with the beryllium.

The importance of these extraneous sources of neutrons is that they can
be used to maintain some neutron population or fission rate in a reactor
even when the fission chain reaction is not self-sustaining.

Consider a reactor which is subcritical, i.e., k < 1. On the average,
each fast neutron introduced by an extraneous source will produée in the
first generation k neutrons; in the second Ke; and so on. Thus for each

source neutron, there eventually appear a number of neutrons M given by

. 2 .3 B 1
M=21+k+k +k” +eeee =

If source neutrons are being introduced at a rate S, then the total rate

of neutron appearance in the reactor is SM. The population of neutrons in
the reactor is the product of the birth rate and the average time a neutron
spends in the reactor before being absorbed or leaking out. If the lifetime
is a constant in a reactor with an extraneous source, the population and
the flux will be proportidénzl”. to M. For this reason M is called thé
subcritical multiplication factor.

M becomes very large as k approaches a value of 1. Thus, theoretically,
if a source is present, any flux or power could be reached with the reactor
slightly subcritical. Practically speaking, however, the source becomes
insignificant when the power reaches a few watts or so, and the reactor
behaves as if no source were present; i.e., the power rises when the reactor
is supercritical (k > 1) and decreases when it is suberitical,

10  REACTOR KINETICS

Consider a hypothetical reactor in which all of the neutrons have the

same generation time, #. Neglecting any extraneous source, the fractional
change in flux, or power in one generation is k - 1. Thus the rate of change

of power is
Approved by4§???gy%?2é/flQ¢nL 2A~21

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- Ap P (k- 1)
‘ At 2

In this case, if k is constant, the power changes exponentially; i.e.,

for an initial power Po’ the power after a time t is

pop ot (- D/

o}
The quantity £/(k - 1) is called the period, or the e-folding time since
it is the period required for an e-fold change in power. Somewhat more

ganerally, the period 1s defined as the instantaneous value of

dP 4 (In P)

B dt

H -
C'.

In an actual reactor the generation time is not the same for all
neutrons. The lifetime is about the same for all (typically less than a

millisecond) but the generation time includes the "gestation period" for

the delayed neutrons {(on the order of several seconds). The delayed neutrons
usually therefore exert a strong slowing down or damping influence on power
changes. Although the mathematical expressions for the kinetics become
complicated when delayed neutrons are included, the behavior is still
basically exponential and an important characteristic of a reactor is the
"inhour curve" which relates the inverse period to the reactivity.
(Reactivity is defined as (k - 1)/k.)

The inverse‘period increases with reactivity and this increase becomes
much sharper above the point where the reactivity equals B, the fraction of
the neutrons which are delayed. This point is called prompt critical
because at higher reactivity, the chain reaction can diverge with prompt
neutrons alone, without waiting for the delayed neutrons. At a constant k -

above prompt critical the power behavior is approximately given by

*
where £ 18 here the prompt neutron lifetime. The reactivity is sometimes

measured in "dollars", or multiples of . (One dollar is promptycritical.)

e
Approved bx4¢§f%2V%%6;V/wfw 2A-22
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In the normal operation of a reactor the reactivity is adjusted (by
means to be described later) to hold to power steady or to go from one

power level to another at a reasonable rate.

11  NUCLEAR TINSTRUMENTATTION

The most satisfactory means of continuously monitoring the nuclear
power of a reactor is to follow the neutron flux at some point. The
detector can be located outside of the reactor itself, because the flux
produced by neutrons leaking from the reactor rises and falls with the
power inside.

The most common form of neutron detector is the ionization chamber.

In such a device, neutrons interact with some material to produce high-
speed particles which ionize (strip electrons from atoms) in a gas in the
chamber. An electric potential causes the electrons and positive ions to
be drawn to opposite electrodes, and appropriate circuitry either counts
the pulses of ions or measures the average current.

Boron-10, which emits an ionizing alpha particle upon absorption
of a neutron, is commonly used in ion chambers, either as a coating or in
the form of BF3 gas. A form of ion chamber called a fission chamber
contains U235, and the fission fragments produce the ionization.

Gamma, radiation interferes with the measurement of low fluxes of
neutrons, because the gamma rays also produce ionization and contribute to
the current in a neutron-sensitive chamber. This 1s no problem in a
fission chamber because the counting circuit can be made to discriminate
between the large pulses caused by fission fragments and the much smaller
events caused by individual gamma photons. The compensated ion chamber
was developed to provide a current proportional only to neutron flux even
in high gamma fields. This type of detector has two chambers which produce
equal ionization currents when exposed only to gamma rays. One of the
chambers contains & boron coating so that 1t is sensitive to neutrons as
well as to gammas. The desired signal is obtained by bucking or subtracting
the currents from the two parts of the detector.

Because the reactor power may vary over many decades from sub-critical
source multiplication to full power and because the time variation is often
exponential, it is common to use circuitry to produce a signal proportional

to the logarithm of the power. This may be a log count rate meter or &
..

Approved bx/fifizi/;%?f/%¢n1 2A-23

T/21/65
logarithmic current amplifier. 1In either case the time derivative is the
inverse of the period, and, displayed on properly marked dials or charts,
provides a useful indication of the period.

Note that the nuclear instruments give a signal which is only pro-

portional to power. The proportionality factor muist generally be determined

by heat balance measurements and simultaneous nuclear instrument readings.

12  REACTOR CONTROL

The function of reactor control is to regulate the power and/or
temperature in the desired ranges, to prevent excessive power or temperature,
and to shut the fission chain reaction down to very low levels whenever
necessary. To do this, the reactivity is varied, usually bj the movement
of neutron absoroing material (generally called a rod, regardiess of
shape) into and out of the core.

Small, fairly quick, variations in reactivity (less than a dollar)
are required to maintain the power within a narrow band. This is the regula-
ting function and a special rod for thié is called a regulating rcd.

Rods which can rapidly insert considerable poison if required to
prevent power or temperature excursions are called safety rods.

There are several factors affecting reactivity which produce rather
s10W changes during an operating cycle (startfip, power operation and shut-
down). At some stages the net effect is a tendency to reduce k; at other
times, k tends to increase. In order to keep k at or near 1, control
rods may be occasionally or gradually adjusted. Rods performing this
function are called shim rods.

An important effect on reactivity is that of core temperatures. As
temperatures rise, materials grow less dense and microscopic ciross sections
change. The net effect is usually a negative temperaturs coefficient of
reactivity, so that the reactivity must be increased by some other means
if the operating temperature is to be raised. Distinet from shifts in the
overall temperature distribution are the changes in temperature distribution
accompanying power changes. As the power is raised, temperatures in various
parts of the core diverge, and in order to hold some desired temperature
(or temperature average) constant it is generally necessary to adjust the
reactivity by shim rod movement. The power coefficient of reactivity is the

amount of rod motion required to produce tThe desired effect.
7Y ft
Approved byizg;flzégk%z»zfiw\_ 2A-2L
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Temperature coefficients of reactivity not only affect shim require-
ments but also have an important effect on kinetics, since negative reactivity
coefficients tend to produce a stable, self-regulating system when the
power is high enough to produce a feédback effect.

235

During power operation, consumption of U by fission and by radiative

capture tends to reduce reactivity. This burnup effect is slow, since

only a very small fraction of the inventory is consumed in a day. Shim

rod movement and periodic additions of uranium compensate for this effect.
Another effect of power operaticn is the produétion of fission product

poisons which tend to reduce k. Most of these poisons are stable and have

relatively small cposs sections, so they continue to build up. Shim rods

compensate for these poisons. (In the MSRE the U235 inventory is increased.)

A few poisons with high cross sections produce transient effects, with time

constants on the order of hours, and these effects require the use of the

shim rods.

In & circulating-fuel reactor one more effect on reactivity is observed: -

the loss of delayed neutrons by emission outside of the core. This causes
a slight reduction in k (the effective value of v is reduced) but more

importantly it affects the kinetics (the value of the "dollar" is reduced).

13 XENON AND SAMARTUM

The most important single fission product nuclide is xenon-135. This

radioactive nuclide (9-hour half life) has a thermal neutron cross seciion

1
32 is produced by the decay of iodine-135,

of about 3 million barns. Most Xe
which has a half-life of 5 hours and a small cross section. When the
reactor is operated at power, the I135 and then the Xe135 concentrations
build up. The Xel35
radiocactive decay and by transmutation by neutron absorption. Typically

135 is about 2 to 3% in k. When the

concentration at first increases be-

concentration at power is limited by its natural

the equilibrium poisoning effect of Xe
reactor power is reduced, the Xe135
cause the destruction by neutron capture decreases before the production
by I135 decay changes appreciably. Radioactive decay of the X8135 causes
the concentration to begin to decrease after a few hours and eventually

it would all disappear.

-
.‘

Approved by;fifizéK§%$/%@¢71 2A-25

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135

Xenon is normally a gas, and in fluid-fuel reactors the Xe concen-
tration may be significantly affected by mechanisms which remove xenon
from the fuel.

Another fission product which has an important effect on the reactivity
is samarium-149, a stable nuclide formed by decay of 53-hour promethium-149,
Semarium-149 has a cross section of about 40,000 barns, so its concentration
is held down by burnup when the reactor. is at power. After the power is

reduced, the burnup stops, but the Pml)+9

149

increase in Sm

continues to decay, causing an

1k9

Being stable, the Om remains high until the power

is raised and 1t comes back to the equilibrium value at power. Typical

149

values of the Sm reactivity effect are: equilibrium at full power,

0.9% 8k/k; and increase at zero power 0.2% &k/k.
-

10/19/65

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Approved bylfiéészégegéigé;fifififlf\ ' 2B-1

2B MSRE NUCLEAR CHARACTERISTICS

The preceding general description of reactor theory is applicable to
the MSRE, as it is to all reactors. This section describes the uvnusual
features of the MSRE and provides gquantitative information on its nuclear
characteristics in a condensed form. A much more detailed treatment is
given in MSRE Design and Operations Report — Part III, Nuclear Analysis,
ORNL TM-730.

1. Core Reactivity Factors

The uvnique feature of the MSRE, which sets it apart from other
reactors, is that the uranium fuel is contained in a molten mixture of
fluoride salts which is circulated through a heat exchanger to remove
the heat produced by the fission process in the core.

Although the fissionable material is dispersed throughout the fuel
system, the fission chain reaction is confined to the core. The fuel 1is
not chain-reacting in the piping because the neutron leakage prcbability
is much too high because of the small dimensions. In the heat exchanger,
the parasitic absorption of neutroné by the tubes combines with high
leakage to rule out criticality. Even in the drain tanks, the leakage
is too high for criticality. (Resonance capture in 2387 and absorption
in the cooling thimbles also tend to reduce k.) The high leakage and
resonance absorption are direct consequences of the poor moderation in
the salt. In the core, on the other hand, there is graphite to slow
the neutrons down with but little absorption, and with the slow neutrons
the vessel is large enough to give a low probability of leakage.

The reactivity of the core is a function of several variables.
These are:

.  the concentration of 33U in the fuel salt,
the temperatures of the fuel and the graphite,
the presence of gas bubbles in the core,

the positions of the neutron-absorbing control rods,

i w

the concentrations of neutron poisons in the fuel salt and in

the graphite, and
s /’,f / //‘ . )
Approved by ST INSA AW py . 2B-2
| - | ©10/19/65

6. the number of neutrons emitted in the core per fission (as

affected by the loss of delayed neutrons during fuel circu-
lation). | | |
Each of these variables is discussed separately in this section.

1.1 Fuel Salt Concentration

The minimum amount of 35U required for criticality in the MSRE is
about 50 kg (in 73 ft? of salt) or a concentration in the fuel salt of
0.2 mole % of highly enriched uranium. For the first exploratory opera-
tion of the MSRE, a higher uranium concentration is desired for reasons
of chemistry. (If fluorine loss from the salt should occur, more UF,
could go to UFs before U precipifiatibn would occur.) Therefore in the
original charge of fuel salt the uranium concentration will first be
brought up to 0.5 mole % by the addifiion of 150 kg of depleted uranium.
(The #35U fraction of this uranium is only 0.002.) Then, during the
initial critical experiment, the 233U concentration will be brought up
by addition of highly enriched uranium (93% 225U) to the "clean critical”
concentration. This is the concentration required for criticality with
no fission product poisons in the reactor, all control rods fully with-
drawn, the fuel salt stationary, and the reactor at a uniform temperature
of 1200°F. The predicted critical loading is 69 kg of 235U, giving a
total uranium concentration in the salt of 0.80 mole % U. This salt is
sometimes referred to as fuel C, having a molar composition of 65 LiF-29.2
BeF>-5.0 Z2rF,~0.8 UF,. The values quoted later in this section for
nuclear parameters apply when the reactor is fueled with this salt.

Addition of highly enriched uranium when the concentration 1s near
the critical value causes an increase of 0.22% 8k/k for each percent
increase in 235U concentration. Thus the addition of 85 g 25U (the
amount in an enriching capsule) would produce an increase of only
0.03% dk/k.

After the initial critical loading, about 7 kg of 25U will be
added as highly enriched uranium to bring the fuel salt up to the opera-
ting concentration (0.28 mole % 35U, 0.83 mole % total U). The increase
is required to compensate for effects which will appear when the reactor

is operated at high power, namely:

>
[ d

£B-3
10/19/65

Approved by, =

1. elevation of fuel and graphite temperatures,
partial insertion of the control rods to permit power
regulation,

3. fission product'poisons,

L, loss of delayed neutrons due to emission outside the core,

Burnup — When the reactor is operated at power, 35U is consumed by
fission and by radiative capture} (The ratio of captures to fissions is
0.18.) The rate amounts to 1.25 g/Mwd, which means that the amount
which can be added in one capsule would be consumed in about 7 days at
10 Mw. When the reactor is operated at full power, additions of enriched
uranium will be mede at intervals of 7 days or less so that not only is
the loss due to burnup made up but the 235y inventory is actually in-
creased to compensafe for the negative reactivity effects of fission pro-
ducts which are building up.

Non-uniform Uranium Distributions ~ The coefficient of reactivity

for changes in 235U concentration which was quoted above applies to uni-
form inecreases in the concentration. Although no significant non-uniformi-
ties in uranium concentration are anticipated in operation, the reactivity
effects of localized uranium are worth noting. The reactivity effect of

a given amount of 235U could be much greater if it were all in the core
than if it were evenly dispersed throughout the 75 cu ft of fuel salt.
Uranium evenly distributed in the core is worth 3 times as much as the
average over the entire loop. A small amount of uranium at the point of
maximum importance (near the center of the core) would be worth 15 times
as much as the loop average.

1.2 Temperature and Power

Changes in fuel temperature and in graphite temperature affect
reactivity in different ways. The primary effect of graphite temperature
is through its influence on the thermal neutron velocity distribution;
an increase in temperature resulting in higher energies and lower cross
sections. The reactivity is affected by fuel salt temperature mainly

because thermal expansion of the salt reduces the amount of 25U in the
L f
Approved by -‘f;',f<t€}4#/fi4\ 2B-4
, 10/19/65

core. Other, less important effects are the decrease in moderation by
Li, Be and I as the salt expands and the influence of salt temperature
on thermal neutron energies.

I1f the temperature of the fuel and graphite is uniform throughout
the core, an increase in the overall temperature would produce a decrease
in reactivity; the ratio is the temperature coefficient of reactivity,
~7.0 X 1075 °F"%, (To illustrate, a 10°F increase over the entire core
would cause the reactivity to decrease by 0.07% 8k/k.)

If a uniform change could be produced throughout the fuel in the
core without changing the graphite temperature, the reactivity effect
would be -3.3 X 1075 °F™L, A uniform change in graphite temperature
alone would give -3.7 X 10°® °F 2. The sum of the fuel coefficient and
the graphite coefficient is the total coefficient, -7.0 X 1075 “F71,

When the reactor is operated at power, temperature distributions
are established in which the rate of fuel temperature increase as the
salt rises along a channel is proportional to the heat generation at
the point. The graphite temperature at any point is above that of the
fuel by an amount proportional to the local heat generation. (See later
section on fluxes, heat generation and temperatures.) As the power is
raised and the temperatures depart from isothermal, the net reactivity
effects of the change in fuel temperature can be regarded as the product
of the fuel temperature coefficient of reactivity and the change in an
average temperature which appropriately reflects the reactivity effect
of the actual distribution of fuel temperatures. This is called the
nuclear average temperature of the fuel (NAT). An NAT can be similarly
defined for the graphite: Calculations indicate the fuel and graphite
NATs (T% and T*) are related to the fuel temperatures entering and

leavingfthe refctor vessel as follows:

Tout * Tin

% = ( 5 ) +1.1P="T_, -1hP
Tout + Tin

Tje%;:( 5 )+5.5P-—"Tout+3.0P

where P is the power in megawatts.

bl
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Approved byfif;;gzzegzég%%;flofgfifl o | 2B-3

10/19/65

The shapes of the temperature distributions at power are charac-
teristics of the physical system. On the other hand, the entire
temperature distribution can be shifted up or down simply by moving the
control rods to obtain any desired relation of the temperatures at power
to the isothermal temperature before the power was raised. (When the
rods are moved the entire temperature distribution must shift to produce
a compensating effect to keep the reactor just critical.) The amount
of reactivity change which must be produced with the rods to'obtain the
desired temperature response is called the power coefficient of reac-
tivity. The MSRE rod servo system holds the reactor outlet temperature
constant. The power coefficient for this mode of operation is
-6 x 107° Mw~ L,
1.3 Control Rod Positions

When the control rods are inserted in the core, they absorb neutrons
which might otherwise cause fission, thereby reducing keff' Except when

the nuclear power 1is shut down to practically zero, k is always kept

e
in the range 1.000 *+ 0.001. This is done by adjustingfihe rods as
regquired to compensate for other changes which tend to take k out of
that range.

The change in reactivity per unit distance of rod movement is the
sensitivity. The upper end of the poison section‘extends out the top
of the core at all times, so the movement of a rod is equivalent to
adding or removing a length of poison from the core at the lower end
of the rod. The reactivity effect of adding poison in the core depends
on where it is added, being approximately proportional to the square of
the ratio of the local neutron flux to the average flux. The flux
distribution from top to bottom of the core is approximately a sine
curve. Thus the sensitivity of a control rod varies with the position
of its lower end approximately as (sin ny/L)Z, where L is the effective
length of the core and y is the distance from the top of the "effective
core"” to the lower end of the poison. The effective limits of the core

are where the flux distributions in the core extrapolate to zero.

The poisoning effect of a rod at any given position is the integral
9/,
Approved by<22?§2ifz%£é%;/flz4nt 2B-6

10/19/65

of its sensitivity from completely out to that position. Thus the

proisoning effect is approximately proportional to
y
2 . T
wiy) = 2 /7 sin2() ay
0

which is an s-shaped curve as shown in Fig. 2B-1. This expression is
only approximate because the insertion of the rod depresses the flux

in its vicinity so that the sensitivity does not follow exactly a sin®

curve. The relation of the actual worth curve to the simple approxi-
mation is shown in Fig. 2B-1.
1.0

7
Actual*~:;/;)
/

Fractional Worth

0.5 1.0
Fractional Insertion, y/L

Fig. 2B-1 ©Shape of Rod Worth Curves

Table 2B-1 gives the predicted effect of configurations in which
rods are either all the way out or all the way in. Rod numbers here
identify rod positions in the core, and as indicated by the diagrams,
rod 2 is the one diagonally opposite the core sample assembly. (The
rod identification numbers on the console may not correspond; the 'rod
1" instruments and controls on the console are connected to whichever
rod is being used as the regulating rod.) The effective height of the

core to which these total-worth values apply is about 78 in. Since the
[

Approved b%f"f'ffiéifa%;;n&zzfiy 2B-T

10/19/65

Table 2B-1

CONTROI, ROD EFFECTIVENESS

(Initial Critical Conditions)

Reactivity

Rod 1  Rod 2  Rod 3 Effect (% dk/k) -

a Out out out 3o 0
b n out out 8o —2.36
c out In Out 80 ~2.26
a out In In o ~}.03
e In out In 2o —4.33
f In In In :. - —5.51
Worth (% 8k/k)
a~Db Rod 1 (rods 2 and 3 out) 2,36
d—f Rod 1 (rods 2 and 3 in) 1.48
a—c¢ Rod 2 (rods 1 and 3 out) 2.26
e — T Rod 2 (rods 1 and 3 in) 1.18
~ d Rods 2 and 3 (rod 1 out) k.03
- F Rods 2 and 3 (rod 1 in) 3.15

Approved by flfl . '{::‘f At P y 2I/3é8
10/19/65

rod travel is only 51 in. between limit switches, the available worth .
of a rod is only 0.927 of the total. Application of this factor to
the total predicted worth of rod 1 gives an available worth of 2.2%
Ne/k. The first evaluation of the worth of rod 1 gave 2.18%.
Because of the core symmetry, rods 1 and 3 are identical in worth;
rod 2 is somewhat less than either because it is more "shadowed" by the
other rod thimbles or rods. The worths listed in this table were pre-
dicted for the initial, clean core. When fission product poisons build
up and more #3°U is added to the fuel, the neutron diffusion length in .
the core is reduced, making the rods worth less. This effect is ex-
pected to reduce the figures in Table 2B-1 by about 6 percent. A
Any rod can be designated as the regulating rod (rod 1 on the con-
sole) by wiring it in to the servo system which controls flux or reactor
outlet temperature. The other two rods are the shim rods. Because it
is an advantage to be able to shift the regulating function from one
rod to another without changing either the regulating rod worth or the
shim worth, Rod 1 will be designated as regulating rod initially and
if a change is necessary, Rod 3 will become the regulating rod.
The effect of flux depression or "shadowing" which shows in Fig.
2B-1 and Table 2B-1 also causes the sensitivity of a rod to change sharply .
as i1ts end moves by that of another rod. (Picture a rod moving up into
or down out of the "shadow" around another rod.) For this reason the
two rods used as shims are kept well above the regulating rod, so that
its sensitivity does not change sharply. One reason for this is that "
the reactivity balance calculation uses approximations for rod worth
which fit better when the rod tips are not too close. (See MSR-64-1k,
"On-Line Computation of Control Rod Effect for Reactivity Balance.")
1.4 Xenon-135
In the MSRE, 135%e is produced at a rate of 6.3 atoms per 100

fissions. About 97 percent appears first as +3°I vwhich decays with a
6.7-hr half-life to *>°Xe. The other 3 percent is formed directly in
fission. ZIodine-135 is uniformly distributed throughout the fuel salt,
giving a distributed source of 135%e. (Any uranium in the graphite

gives rise to a localized source of iodine and xenon, but this is

LY
[ %

2B-9

Approved by
10/19/65

relatively unimportant.) Xenon-135 which appears in the circulating
fuel salt may (1) decay to long-lived *3°Cs (2) capture a neutron and
go to stable 13%Xe, (3) be transferred to the gas in the pump bowl or
(k) be transferred into the gas-filled pores in the core graphite.
Xenon-135 in the graphite may decay, be burned up by neutron capture
or move back into the salt.

The time constants for the decay and burnup are well known. The
half-life of *35Xe for natural decay is 9.2 hrs., giving a decay con-
stant of 0.075 hr *. The effective cross section (in the MSRE neutron
energy spectrum) is 1.5 x 10° barns, giving a burnup time constant for
13°Xe dispersed around the fuel system of 0.02 hr '. For *35Xe evenly
distributed throughout the graphite in the core, the burnup time constant
would be 0.07 hr *. (These burnup time constants are at 10 Mw and are
proportional to reactor power.) The rate constants for the other
processes are not well known, and an important objective of the MSRE
operation is to determine values for them. It is expected that the
transfer to the pump bowl offgas will be relatively fast, resulting in
low steady-state xenon-poisoning {only 0.1% Ek/k or less at 10 Mw).
1.5 Other Fission Products

If 135Xe poisoning is kept low by gas stripping as expected, the

individual fission product contributing most to the neutron poisoning
in the MSRE will be *4®sm. The steady state poisoning of 149y in the
MSRE at any significant power will be about 0.9% 8k/k. (The steady-
state level is independent of power because both the burnup time con-
stant, ¢o, and the production rate are proportional to power, and the
steady-state level is the ratio.) The initial ingrowth of 149gm will
be slow, s0 the reactor must be operated at high power for several
months before the 14%gm reaches steady state.

The transients in +4®sm poisoning have a much shorter time constant,
namely that of the decay of 53-h 14%pm, the precursor of *%%m. When
the power is shut down, the destruction of 14%Sm stops and the 148py
which is present scon decays into l498m, increasing its poisoning effect
on reactivity. The steady-state amount of 4®pp is proportional to
power, and hence so is the size of the 149y poisoning transient following

a shutdown. When the power is shut down from 10 Mw, the 149gm transient
Approved by% > adiaN 2B=10
T S—

10/19/65

will be about 0.03% 8k/k.
There are a few other high-cross-section fission products which
saturate in roughly the same length of time as 149Sm, and some exhibit
similar transients. The combined effect of these will be about 0.2
that of +4°gm.
The large majority of fission products (all those except 136Xe and
the "Samarium" group) contribute to a poisoning effect which will grow
approximately linearly with integrated power in the MSRE. The rate will v
be about 1 x 10 4% 8k/k per Mw-day.
1.6 Delayed Neutrons

When the fuel salt is stationary all of the delayed neutron pre-
cursors decay in the core. When the fuel is circulating, part of the
precursors decay outside of the core and these delayed neutrons are lost
to the chain reaction.

The delayed neutrons comprise 0.0064 of the total neutrons released
by fission. Because their initial energies are lower than the average
for all fission neutrons, the delayed neutrons are less apt to leak

during slowing down, and the effective fraction of delayed neutrons in

the non-circulating case is 0.0067. When the fuel is circulating, the
delayed neutrons emitted in the main part of the core are 0.0039 of
the total. DBut because many of the delayed neutrons are now emitted
in the reactor-vessel heads, from which some reach the core, the effective
fraction is 0.0046. Thus circulation causes an effective loss of 0.0021
of the neutrons, or a decrease in reactivity of 0.21% Sk/k. .
The changes in reactivity assoclated with the delayed neutron pre-
cursor transport reach steady state within a minute or two after circu-
lation is stopped or started. When the pump is stoppéd, the reactivity
increagses as precursors are no longer swept out of the core. Time
constants are those associated with coastdown of the flow and the half-
lives for precursor decay which govern the concentration transients.
When fuel circulation is first started, the concentrations of precursors
will immediately drop below the steady-state values as salt with practi-
cally no precursors flows into the core. There will be some small per-

turbations as the salt which was in the core comes back, but this effect

-
‘r’

L 'fljgiflfij;«“ : _
Approved by -7y @ % % 2B-11
rd </ 10/19/65
is smeared out by mixing. Of course when circulation is first started
the reactivity changes are unimportant because the reactor is well
subcritical. (The rods are inserted before the fuel pump is started.)
1.7 BEntrained Gas in Fuel

Development testing of the prototype of the fuel circulating pump
indicated that undissolved helium bubbles to the extent of 0.5-1% by
colume could be expected to circulate with the fuel salt. These bubbles
were introduced by the action of the spray ring in the pump bowl.
Operation at the MSRE has showed that essentially no bubbles circulate
with the salt if the level in the pump bowl is at the normal operating
point or higher (>60%). However a bubble fraction of 2-3% was observed
at an abnormally low salt level.

When gas bubbles appear in the fuel salt in the core, the density
of the salt-gas mixture decreases, the neutron diffusion length increases
and as a result, reactivity decreases. The fuel density coefficient of
reactivity was calculated to be 0.18. Thus, a bubble fraction of 1%
would result in a reactivity decrease of 0.18% ak/k. The presence of
bubbles causes the fuel density, and hence the reactivity to respond
to pressure changes. With ~ 2 1/2% bubbles, the pressure coefficient
of reactivity was 3 x 10°° 6k/k per psi for slow pressure changes and
1.4 x 107% for rapid changes.

Since the MSRE will normally operate with no bubbles circulating,
the effects described above will not be observable. However, they may
appear under abnormal circumstances (low pump-bowl level).

2. Heat Generation and Temperature Distributions

About 93% of the heat associated with the fisgsion process in the
MSRE is produced within the fuel by fission fragments and the various
radiation scattering and capture processes. About 6.5% is generated
in the graphite and transferred to the fuel in the core. This leaves
only about 0.5% to be absorbed in the thermal shield, biological shield,
and structural material in the cells. (About 5% of the energy of
fission escapes in the form of neutrinos and never produces any heat;

this energy is not included in the above balance.)
Approved byfi%fl{ % 2B-12

10/19/65

2.] Overall Temperature. Distribution’

The overall temperature distribution in the fuel is determined by

the spatial distribution of the power and the flow rate of the salt.

At 10 Mw the nominal temperature rise of the fuel from reactor inlet

to outlet is SOOF. Since about 14% of the power is generated in the
upper and lower heads and other peripheral regions of the reactor vessel,
the average temperature rise as the fuel passes through the graphite
channels is only 430F. The fuel undergoes a 3.5O#temperature rise before
it reaches the graphite and anothexr 3.50 rise between the time it leaves
the graphite and the time it leaves the core. The temperaturesin the
upper and lower heads are expected to‘be more-or-less uniform because

of fluid mixing.

Since most of the heat of fission comes from the fission fragments,
the heat-source distribution is essentially the same as the fission
distribution which,in turn, has about the same shape as the thermal-
neutron flux. The fuel velocity is relatively unifrom over most of the
core, with a region of high velocity near the center. §Since the neutron
flux is depressed near the center of the core by the control rods and
thimbles, the temperature rise of the fuel in the central channels is
much lower than that in channels some distance out from the center.

The maximum temperature rise (~ 86°F) occurs in the channels about 8

in. from the core center line. The temperature of fuel in any channel
increases continuously from the inlet to the outlet. The rate of
increase is proportional to the heat production, or flux; low at the .
ends and high in the middle. Since the shape of the power distribution

along a channel follows approximately a sine curve, the axial temper-

ature distribution of the fuel (proportional to the integral of the

flux distribution) has the shape of the general curve (L - cos x).

The temperature of the graphite at any point in the core is higher
than that of the adjacent fuel because the heat produced in the graphite
must flow into the fuel. The maximum difference between the mean trans-
verse temperature in a graphite stringer and the mean transverse tem-

perature in a fuel channel is 61°F near the midplane of the core. Because

of the continuously rising fuel temperature, the absolute maximum graphite -

-
A

ey ary
Approved bx/¢%§;::? ‘W&ézg/kifibL 2B-13
T a4 . 10/19/65

temperature (~ l3OOOF) occurs considerably above the core midplane.
2.2 Local Temperature Effects
Local overheating is not likely in the MSRE because of the rela-

tively low power density. However, there are some areas in the reactor
vessel where local heating must be considered.

The INOR-8 structural parts of the reactor are subject to radiation
heating by gamma rays and fast neutrons. For the most part, this heat
1s efficiently removed by the salt flowing past the surfaces. However,
if solids were deposited from the salt, they could inhibit such heat
removal (and produce more heat if the deposits contain 23%U) and lead
to locally high temperatures. The reactor-vessel lower head and the
core-suppert ring above the inlet voiute are areas where solids couid
accumulate if they form in the fuel salt. The temperatures in these
areas are continuously monitored for evidence of local overheating.

The control-rod thimbles are subject to substantial radiation
heating because of their location near the center of the core. Under
normal conditions they are adequately cooled by the combination of
salt on the outside and rod-cooling alr on the inside.

Blockage of a fuel channel would require that the heat produced
in that channel be transferred through the graphite stringers to the
fuel in adjacent channels. The temperatures resulting from this con-
dition would not damage the reactor.

3. Instrumentation

The nuclear instrumentation is described in detail in the MSRE
Design and Operations Report - Part IT, Nuclear and Process Instru-
mentation, ORNL - TM - 729. A brief summary is given here of the
operating principles and functions of those instruments which respond
to neutrons or the nuclear power of the reactor. |

3.1 Non-fission Neutron Sources

Neutrons are of course produced by the fission process at a rate
proportional to the power-level. But neutrons are also produced in
the reactor by other processes. The strength of this fission-independent
neutron source is related to safety. It is also closely related to the

neutron instruments because whenever the fission rate is very low, it
Approved byws,;fiw' i 229fll¢4h4 2B-14

” -~ ~ | 10/19/65

provides most of the neutrons that are counted by the detectors. Thus
the selection of the source and detectors must be ‘'coordinated to provide
the necessary information for reactor opei"ation°

The prime safety function of a neutron source is to guarantee a
sufficiently high neutron population so the statistical nature of the
neutronic processes is maintained. In addition the source supports a
certain minimum fission rate, or power level, in the suberitical reactor.
Since the size of the power excursion for a given reactivity ramp .
generally increases as the initial power decreases, this minimum level
tends to limit the severity of some accidents. Another useful, but not
safety, function of an independent neutron source is that it permits
monitoring the subcritical multiplication in the reactor as criticality
is approached. This is particularly important in the MSRE where keff
in the empty reactor starts at zero and each fill with fuel salt is
essentailly a new critical experiment.

Three types of non-fission neutron sources are important in the
MSRE: 1) the inherent alpha-n source in the fuel salt, 2) the external
(Am-Cm-Be) source in the thermal-shield source tube, and 3) the photo-
neutron (r,n) source which results from the interaction of fission
product gammas with beryllium.

3.1.1 Inherent Source

The alpha particles emitted by the various uranium isotopes
in the fuel interact with the Li, Be, and F to produce neutrons.
The alpha particles from 234U acting on Be and F produce about 96%
of these neutrons. With the reactor full of fuel salt at the nor-
mal operating concentration, the internal source releases about :
b x 10° n/sec in the core. This source is adequate for all the
safety requirements of the system. However, since the source is
absent when the reactor is empty, it does not meet the requirement
for monitoring suberitical multiplication during a fill.
3.1.2 External Source

Neutrons are produced in this source by the action of alpha

particles from 24%am and 242Cm on ®Be. The source was produced

by mixing 0.6g of 24lAm with Be and irradiating the mixture in the

Ve
R d

; a%?pf
Approved by .~ Lo L2 2B-15
Cdl ..v g

10/19/65

ORR to transmute some of the Am to 24Cm. When fresh, this source
emitted sbout 1.2 x 10®8 n/sec but, since it is installed in the
thermal shield, only a fraction (<25%) of these neutrons actually
enter the core. More than 99% of the external-source neutrons come
from the Cm alphas so the effective half-life of the source is that
of 242Cm, 160 days. Thus the intensity of the external source will
decrease with time unless the neutron flux from the operating reactor
is high enough to keep the Cm concentration high.

Since the external source i1s independent of the fuel location,
these neutrons and their progeny are counted when the reactor is
empty and during the initial stages of a fill when the internal
source is insignificant.

3.1.3 Photoneutron Source

Gamma rays with energies greater than 1.7 Mev are capable of
producing neutrons from ®Be. Since a number of 35U fission pro-
ducts emit gammas with energies above this threshold, the MSRE
will have a substantial internal photoneutron source after an
inventory of fission products has been established. This mechanism
will provide at least 107 n/sec in the core for 100 days after the
reactor has operated at 10 Mw for 30 days. The photoneutron source
is subject to decay and is not very effective after long shutdowns.
Furthermore, it has the same disadvantage as the (o,n) source - it
is observable only when the fuel is in the reactor.

3.2 Neutron Detectors

Radiation d.etectors in general consist of a chamber filled with
an ionizable gas and devices for collecting the ionic charges. When a
particle of ionizing radiation passes through the gas, positive ions and
electrons are formed which flow to oppositely charged electrodes producing
a small electric current. These small pulses of current can be amplified
and registered as discrete events or can be "smeared out" and measured
as an average current.

Since neutrons are uncharged, they do not produce any direct ion-
ization in passing through matter. Thus, neutrons as such cannot be

detected by ionization chambers. To circumvent this, neutron chambers
=y
Approved}fifii;;}izz£2£ZEfi¢hm\§_ 2B-16
” ~

10/19/65

contain a material that will interact with neutrons and produce ionizing
radiation. This secondary radiation then produces ionization in the
chamber which is detected and registered as a neutron event.

The neutron detectors in the MSRE are located in the nuclear instru-
ment shaft some distance from the reactor core. However, the neutrons
that leak out of the operating reactor produce a significant neutron flux
in and around the various detectors. ©Since the shape of the neutron flux
in the core of the critical reactor is essentially independent of power
level, a nearly constant fraction of all the neutrons produced by fissions
in the reactor escapes. The fraction of escaped (leakage) neutrons that
reaches a given location in the instrument shaft is also independent of
the neutron population density. Thus, a neutron detector with a fixed
detection efficiency at a fixed location will register neutron events
at a rate that is directly proportional to the neutron level (or fission
rate, or power level) in the reactor. The conversion factor between
neutron-chamber output and reactor power can be established only if the
absolute reactor power can be measured by an independent method. The
method that is used to measure absolute reactor power is a system heat
balance. Thus, once accurate heat balances have been obtained, it will
be possible to read absolute power directly from the nuclear instruments.

Four types of neutron detectors are in use in the MSRE. These are
fission chambers, BFs pulse counters, compensated ion chambers, and
boron-coated safety chambers. The basic features of each are described
below.

3.2.1 HFission Chambers

A fission chamber makes use of the very intense ionization
produced by fission fragments to register the passage of neutrons.
Some of the interior surfaces of the MSRE fission chambers are
coated with @35U (other fissionable materials may be used in other
applications) which undergoes fission in a neutron flux. Most of
the time at least one of the primary fission fragments escapes from
the surfaces and produces a very large pulse of ionization. These
pulses are amplified and counted as individual events. Alpha

particles from the radiocactive decay of the uranium in the chamber

e
o

S

and gamma rays from outside also produce ionization in a fission
chamber but the associated pulses are very much smaller than those
from fission fragments. Thus with an electronic circuit which counts
only the largest pulses, a fission chamber can be made to discrimia.
nate against nearly all radiation effects other than from neutrons.
The two fission chambers in use in the MSRE will produce a
counting rate of about 0.4 counts/sec in a neutron flux of 1 n/cm?—
sec. The normal useful range of a fission chamber is about k4
decades in counting rate. Below about 2 c/s the time response of
the count-rate circuitry is too slow to be very useful; above
about 20,000 c/s coincidence losses begin to be observable. The
useful range of the MSRE chambers has been greatly extended by
equipping them with servo-operated positioning devices. BSince the
neutron flux in the instrument shaft decreases approximately expo-
nentially with distance from the reactor, the logarithm of the
ratio of the flux at one point to that at some reference point
(say, the bottom of the shaft) is proportional to the distance
between the points. That is

toe [%g_z)} "o [X - XJ-

Or
log é(x,) = log &(x) + a(x - x5).

Thus, .%he log of the count rate or flux (and hence the actual count
rate) at some reference point, where it is too high to be measured
accurately, can be obtained from the log of the count rate at some
other point by adding to it a number proportional to thé distance
between the points. If the correlation between flux at the ref-
erence point and reactor power is known, this approach can be used
to indicate the log of the reactor power directly.

The above principle is used to extend the useful range of the
MSRE fission chambers to about 10 decades. The chamber travel to

accomplish this is about 90 in. This allows them to cover a power
Approved by/jgfiéfz%izégfi:%/lzéfl@\ 2B-18
T ~ 10/19/65

range from well below critical (0.0lw) to well above full power

(100 Mw). Since the exponential decrease of flux with distance

is only approximate, electronic corrections are applied to improve

the correlation between log power and the sum of log count rate and

position. Even so, these instruments do not give the most precise

indication of nuclear power that is available.

3.2.2 BF4 Pulse Counters

A BF5 chamber is simply a vessel equipped to collect ionization

pulses and filled with boron trifluoride gas. This gas, in addition
to being ionizable, contains *°B which interacts with neutrons to
produce alpha particles. Since the ionization pulses from alphas
are large, this chamber can be made relatively insensitive to

gamma, radiation (but less so than a fission chamber). It also

has a high neutron-detection efficiency.

It was originally expected that the fission chambers described
above would have sufficient sensitivity to give significant counting
rates (>2¢/s) with the reactor vessel empty and only the external
source present. This was not achieved because of physical limjita-
tions on the source intensity and the unfavorable location of the
source with respect to the detectors. Therefore, detectors with
higher sensitivity were provided for this condition and to monitor
the early stages of a reactor fill. (The fission chambers provide
a useful indication before the reactor is completely filled with
fuel salt.) The chambers used in this application are two BFs
chambers with sensitivities of ih c/sec per unit neutron flux
(1 n/em®-sec). Because of their high sensitivity, these chambers
are subject to rapid depletion of the 108 in high neutron fluxes
and must be retracted to a low-flux region when the reactor is in
operation.

3.2.3 Compensated Ion Chambers

This type of device measures the average current produced by
ionizing radiation rather than discrete pulses. The neutron-
sensitive portion of a compensated ion chamber is a vessel, fitted

with charge-collecting electrodes, filled with an ionizable gas,

“‘
It

B
——

zfiggfixfk‘
Approved pyfi£§?z y%gficyflhffix_ 2B-19

10/19/65

and coated on the inside with boron enriched in *°B. Since the

gas is ionized by gamma rays as well as by the alphas from the OB
(4,) 7Li reaction, the output of this subchamber is proportional

to the total radiation level. When a reactor is operating at

power, the contribution to the chamber current from gamma radiation
is relatively low and the output of the boron-coated chamber is
essentially proportional to the neutron flux (power level). However,
when the reactor is shut.down, .the neutron flux drops to a very low
level while the gamma radiation from the fission products remains
high. Thus, the indicated current is high relative to the actual

power level. In order to compensate for this high reading at low

power, a second subchamber is used that is sensitive to gamma rays
only; that is, no boron coating is used. If this second chamber
has the same characteristics (volume, gas pressure, collection
voltage, etc.) as the boron-coated chamber, the currents induced
in the two chambers by gamma radiation will be equal. The outputs
of these two chambers are connected with opposing polarities
(bucking each other) so that the two gamma-induced currents cancel
each other and the net current flow is due to neutron-induced ion-

ization. The combination of two subchambers and connecting wiring

constitute a single compensated ion chamber. In practice the two
subchambers rarely have identical characteristics so one of the
chamber volumes is made adjustable so the degree of compensation
can be tailored to exactly cancel the gamma ionization currents.

The two compensated ion chambers are used to provide linear
indications of the power level. The chamber that feeds the linear
power recorder also supplies the flux signal for the control-rod
servo mechanism. These chambers have a useful range of about 6
decades and indicate power from a few watts up to 150% of full
power (15 Mw). Linear output over this span is achieved by 15
stages of range switching in the output amplifier. The position
of the chambers is selected to provide maximum accuracy in the

normal power range, 1-10 Mw.
Approved b ”fcw 2B-20
| ~ 10/19/65

3.2.4 Safety Chambers

The principal requirement of neutron detectors in the safety

system is high reliability so a relatively simple device is indicated.

The chambers in use on the MSRE are uncompensated, ionization
chambers utilizing boron for neutron sensitivity. A chamber consists
of several concentric cylinders with some of the internal surfaces
coated with boron enriched in *°B. The ionizable gas is dry nitrogen
at 1 atm pressure. Each chamber is equipped with two high-voltage
leads and two independent signal leads. The chamber output is read
as a continuous current rather than individual pulses.

The output from these chambers has a useful range of about 2
decades and the normal readout is 1-20 Mw. The MSRE installations
have a special switching arrangement that increases the amplifier
output by a factor of 10> when the fuel pump is off. Under these
conditions the instrument range is 1-20 Kw. Since the safety
chambers are uncompensated, they are not highly accurate at very
low powers, but accuracy at low power is not a regquirement of
the safety system.

L. Kinetics and Safety

There are several facets to the interest in the kinetics of the

MSRE. Is it stable, i.e., do small disturbances cause oscillations
which don't die out? Does it respond quickly and smoothly to the con-::
trols? Could damaging nuclear excursions result from any conceivable
incident?

The dynamic behavior of the MSRE is shaped largely by 1) circulating
fuel, 2) separate moderator, 3) ‘negative temperature coefficients of
reactivity, 4) relatively low heat generation rate, and 5) loose coupling
to the heat sink (air). Circulation of the fuel reduces the delayed
neutron fraction, which makes the reactivity-period relation significantly
different. This effect is important in the "zero-power” kinetics (where
temperature feedback is negligible) and in rapid nuclear excursions.

In power excursions, the negative temperature coefficient of the fuel
acts promptly as an inherent shutdown mechanism, but.the graphite con-

tributes little. Normal power operation reflects primarily the rather

s
4%

Approved by %fir 1rf ) . 2B-21
/ 10/19/65

sluggish temperature response. The graphite responds slowly to power
changes: a 1-Mw change in reactor power changes the graphite heat
generation by only 0.06 Mw and the heat capacity of the graphite is

3.6 Mw—sec/OF, giving an initial rate of change of lOF/min. Further-
more the heat transfer to the fuel takes effect slowly: the transfer
amounts to 0.02 MW/OF, giving a time constant for the graphite of |
3.6/0.02 = 180 sec. The transfer of heat through a considerable resis-
tance to a low-temperature heat sink makes for sluggish response. Some
indication of this is the time constant which is the ratio of reactor
heat capacity, 12 Mw-sec/oF, to the heat transfer in the radiator. At
10 Mv the heat transfer is 10 Mw/1000°F = 0.010 Mw/°F and the time
constant is 1200 sec. (20 min.). At 1 Mw, the heat transfer area is
reduced, giving a time constant of almost 3 hours.

L.l Stability and Transient Response

The MSRE is stable under &ll conditions. At low power, however,

the margin of stability is not great and low-frequency oscillations
tend to die out slowly if no external reactivity control is applied.
This "wallowing" has a characteristic period of several minutes, so
it is easily flattened out by movements of the regulating rod.
Without any rod control, the negative temperature coefficient of
reactivity causes the nuclear power to follow changes in heat removal
rate and eventually level off at the same value. The servo control
system "tightens up" the response causing the nuclear power to follow
more dquickly with little or no overshoot or undershoot.
4.2 Potential Accidents

There are several more or less concelivable incidents in which

nuclear heating could produce undesirably high temperatures and pressures
inside the fuel salt system. These are described and discussed in de-
tail in ORNL TM-732, The MSRE Safety Analysis Report.

4.2.1 Uncontrolled Rod Withdrawal

Perhaps the most severe reactivity excursion which could be

considered credible is simultaneous and continued withdrawal of all
three rods past the criticel positions. If this happened under

the worst conditions and there were no corrective action, the
Approved. bYflVé ‘\/ff:f-/ W 2B-22
v )

10/19/65

power would surge to between 400 and 500 Mw for a fraction of a
second, then drop back to around 50-100 Mw. The fuel temperature
would rise very rapidly; within 6 sec. after the peak power, the
maximum fuel temperature in the core would be above l8OOOF. The
core would see a pressure surge of about 20 psi. Rod scram on
either l-sec. period or 15-Mw power would limit the excursion to
tolerable proportions even if one of the three rods failed to
drop.

4.2.2 "Cold-Siug”

This is a postulated accident in which the mean temperature of

the core decreases rapidly because fuel is injected at an abnor-
mally low temperature, creating a reactivity excursion by virtue

of the negative temperature coefficient of reactivity. The most
likely way in which such an accident could happen would be for the
fuel external to the reactor vessel to be cooled off while the

fuel pump is stopped; starting the fuel pump would then inject

the cooler fuel. All concern over this kind of cold-slug accident
was eliminated by requiring that the control rods be fully inserted
before the fuel pump can be started. With the rods down, no possible
cold slug could make the reactor critical, much less cause an
excursion.

4.2.3 Filling Accident

The reactor could go critieal. with the core only part full of
fuel if: (1) the control rods were withdrawn too far, (2) the
core temperature were too low, or (3) the fuel were abnormally
concentrated in uranivm. The position of the control rods will
be prescribed for each fill, and it is up to the operator to see
they are not withdrawn too far. Administrative control is also
used to assure that the temperature is high enough. A control
interlock requires that the rods be withdrawn part way before a
£ill starts. Should the reactor go supercritical during a fill,
the rods would scram either on a l-gec. period or at 15 Kw. This
will stop the excursion and if the reason for criticality was

either high rods or low temperature, the reactor will not go

4
Approved b¥¢fi§;%?;43£:flkwn\_ 2B-23
" Y

10/19/65

critical again. Abnormal concentration of uranium is extremely
unlikely, but separation by selective freezing in the drain tank
is theoretically possible even to a degree that would make the
reactor critical with the rods in. Thus in order to prevent
undesirably high core temperatures in the third type of filling
accident, safety interlocks stop the fill when the rods drop.
4.2.4 UO, Precipitation

Separation of uranium from the circulating fuel could lead to

local overheating under deposits or reactivity disturbances if the
uranium shifts position. The only known way for uranium to become
concentrated in the loop is by gross contamination of the salt
with moisture to form UOs,. Precautions against moisture, backed
by the presence of ZrF,, make UO, precipitation extremely unlikely.
Nevertheless, the operation will be watched carefully for possible
signs of such a condition: temperature differences between the
reactor vessel and incoming salt is one indication, another is the
reactivity balance which would show the loss of uranium. Rod
scram at 15 Mw would protect against excursions caused by fast
recovery of up to 700 g of uranium or more. The l-sec. scram
gives protection against even larger excursions by starting the
rods dropping earlier in the excursion.
4.2.5 Others

If the fuel pump stops, the reactivity tends to increase, but
the change is slow and is easily controlled by the temperature
interlocks and the 15-Kw scram with the pump off. Afterheat
problems are moderate in the MSRE because the power density in the
fuel is low. If the fuel were stopped in the core the temperature
rise would increase only l5OOF over about 20 hours. Fuel in the
drain tanks could increase much more, were it not for the heat
removal by the thimbles. Criticality in the drain tanks could
occur only if the uranium were concentrated near the center of the
tank by more than a factor of four. This is very unlikely, if not
impossible. However, should such occur, the chain reaction would

level off at heat-loss power without causing damage.
Approved by .=

h 9/7/65

SECTION 3

OPERATION OF AUXTILIARY SYSTEMS

In the normal operation of the MSRE practically all of the installed
equipment must function in an integrated manner, with a high degree of
interdependence. It is convenient, however, to regard the reactor com-
plex as an assembly of individual systems. The central part of the
MSRE operation consists of transferring the fuel salt, circulating it
through the core, sustaining a fission chain reaction in the core and
removing the heat from the fuel — all under controlled conditions. This
rart of the operation requires not only the primary components, but
absolutely depends upon the operation of the so-called "auxiliary"
systems. (These are auxiliary in the sense of being subservient to,
or supporting, the primary systems, not in the sense of substitute or
reserve. Only a few components are auxiliary in the latter sense.)

The startup and operation of each of these systems are described

in this section.
Approved bx)?ég%iéfifggféflflmgha 3A-1

10/4/6
3A ELECTRICAL SYSTEM

The 7503 Area 1is supplied from the ORNL substation by either of two
13.8 kv TVA power lines, a preferred line or an alternate. These are
separated by two interlocked pole mounted motor operated line switches.
Automatic transfer is provided from the preferred line to the alternate
line. Both transfer switches can be operated remotely from the auxiliary
control room.

The normal AC power enters the 7503 area from the 13.8 kv feeder
(between the transfer switches) through two transformer substations.

A 1500 kva, 480v, 3-phase substation serves the process equipment, and

a 750 kva, 480v, 3-phase auxiliary station is for building services, that
is, lighting, ventilation, etc. The auxiliary substation has no emergency
source, but the process station has three diesel-generators for emergency
AC use. Some of the process area lights can be supplied from either
substation,

There are two separate area IC systems, 250v system and a 48v system.
These are normally operated by AC-IC motor-generator sets and have battery
supplies for emergency use.

This section will cover operation of all equipment from the two 13.8 kv
power supply lines to, but not including, the breakers for individual
equipment. These breakers will be covered with the equipment involved.,

1 SYSTEM STARTUP
1.1 Alternating Current System

Normal power is supplied to the area by closing motor-
operated pole line switch 129 in the preferred feeder, ORNL
Circuit 23L4. This switch can be closed remotely from ACR
Panel 11 in the auxiliary control room or manually at Pole B -
north of Building T7503. An indicating light on ACR Panel 11
indicates when voltage is available on ORNL Circuit 234, and
lights above the control switch indicate whether switch 129 is
open or closed. The manual-automatic selector switch should be

placed in the automatic position.
3A-2
10/ /65

1.1 (continued)

Power is supplied to the T750-kva auxiliary power substation

for building services by closing the manual pole switch located
at the sub-station east of Building T7503.

Next, close the manual breakers to the L80v, 3-phase Distri-
bution Panels 1 and 2, which are located at Column D4 on the
8L0-ft level of the building, this will bring service power into
the building. Distribution Panels 1 and 2 breakers can then
be closed as required to put equipment in service as indicated in
Tables I, II, & ITI.

Power is supplied to the 150C kva process power switchgear
by closing the manual primary disconnect switch located at the
substation west of Building T7503.

The process equipment switchgear and motor control centers
are located in the switch house which is west of the main
building and south of the process power substation. This room
contains most of the breakers for energizing the process equip-
ment. The buses for the process equipment are energized by
closing the following breakers from the 1500 kva switchgear
in the switch house except as noted below:

1.1.1 Breaker R brings power from the substation to 1500 kva
switchgear bus. (TVA BUS)
1.1.2 Breakers S and Breaker A-1 energizes Bus No. 3. Close

Breaker A-1 from DP-3 or DMP-3. (A-1 is interlocked not

to close before S.)

1.1.3 Breaker T and Breaker A-2 energizes Bus No. 4. Close

Breaker A-2 from DP-4 or DMP-k4, (A-2 is interlocked not

to close before T.)

1.1.4% Breaker Z energizes Bus No. 5. (Close Breaker from

DP-5.)

The motor control centers (MCC) can be energized by closing
the foliowing breakers:

1.1.5 Breaker L for MCC-G3.
1.1.6 Breaker F for MCC-Gk.
A
Approved byfi %‘:}fz-fflf«
4—4\/ g

3A-3
10/4 /65
TABLE T
DISTRIBJTION PANEL NO. 1
Breaker Load
Circuit Equipment Fuse (HP) Remarks
10-ton crane TOA/9OA 15 Both cranes on same
fuse and breaker
3-tone crane T 1/2
1 Spare TOA Two 30A fused switches
2 Fused Sw., 852 L 254 Two 30A fused switches
3 Spare 25A
L Change House Vent Fan 15A 1/2, 3/4 Vent fan interlocked
& 840 level htr. fan with Circuit 5
5 8521 Htr. Fan 15A 1-1/2
6 Spare 15A
Two 3 ¢ Receptacles TOA (1) High Bay A-4
(2) North ESA
8 C. R. Air Cond 100/60A 15 Time delay and two
pressure switches
9 225 KVA Lighting LOOA AY, 480/120/208v,
Transformers 3¢, Uw
(See Table IIT)
10 Spare LOoA
11 Spare L4ooA

A e
Approved bwai;?'/;gggiifiyflflgfiz( /ifiéh
10 5

TABLE TT
DISTRIBUTION PANEL NO. 2

Breaker Load

Circuit Equipment Fuse (HP) Remarks
1 Two, L80v, 3¢ 50A In Service Area
Receptacles
2 Spare 50A
3 Spare 100A
Y Spare 100A
5 Spare 100A
6 Spare 100A
7 Two, 480v, 3¢ TOA Switch house, Blower
Receptacles House
Spare 100A
Spare TOA
10 Spare 100A
11 Rollup doors 30A 2 Top, bottom limit
switch
12 Spare 30A(F)
13 Two fans, 1 heater 30A(F) ' South high bay
1k Spare 30A(F)
15 Spare 30A(F)

16 Spare < 30A(F)

3A-5
10/4 /65

jffi;;7 “
Approved by :z:;;f“ flwzfyfiflfifh

- TABLE III

BUILDING LIGHTING FROM DISTRIBUTION PANEL 1 - CIRCUIT 9

Distribution Panel 1A located 8LO' level, Col. 4, 5-C

Circuit Light Pan,. Location Emergency* Lighting Area
0 Pnl. 1 MCR-852 No Maint. Control Room & RC &
’ Pnl. 2 MCR-852 Yes DIC Recept.
1 K TR Yes TR-S. ESA, W. Tunnel,

Blower House,Vent House,
Switch house, C.D. Cell,

. Waste Fan,
2 C Comp. R No Spare
H 840, Col. 1-C No 840' heater distribution
B 852, Col. 4-D Yes area, No ESA 852' hall,
Hi Bay, outside E & SE
of Building
b D 840, Col. 4, 5C No Spare
J 852, Col. 2D Yes Locker room, Instrument
Office & Shop, Hi Bay
6 A 852, Col. 2D Yes Computer Room, CR, Offices,
Outside No. & West
- 7 G Hi Bay Col. 5C No Hi Bay
8 AB 840, Col. 4, 5-C.  Yes Bat. Room, 840O' Maintenance

Area, East of TR

Distribution Panel 1A1 - located 8L40' - outside NE door to TR

1-6 Spare
7 Comp House Comp H Yes Store Room (Comp House)
T Diesel H Yes Diesel H.
8 S SR No Service Room & Tunnel

¥
Emergency Supply from Breaker M - Gen. Bus No. 3, through lighting
transformer and "B" position switch at each light. panel.
Approved by széjizjgésézg;fiflfig%fi

l.2

345
10/4/65
1.1.7 Breaker CC for MCC-G5-1. (This breaker also can be

operated from Panel DPM-5, ACR.) -
1.1.8 Breaker AA for MCC-G5-2. (This breaker also can be
operated from Panel DPM-5, ACR.)
1.1.9 Breaker X for MCC-T-1.
1.1.10 Breaker Y for MCC-T-2.
These additional breakers should be closed.
1.1.11 Breaker BB for Heater Distribution Panel G5-BB.
1.1.12 Breaker M should be closed to supply power for emergency

AC lighting. This includes Maintenance Control Room

Panel No.2, Lighting Panels K, A, AB, B, and T. Each of
these has a selector switch with an A and B position. The "

A position powers the lights from the auxiliary substation, -

and the B position powers lights from DG No. 3 Bus. These

lighting panels should be operated in the B position.

Direct Current System

Before starting the IC systems, turn on the battery room
ventilating fan. Check to be sure that all battery cells are
filled with electrolyte to the top of the stippled windows.
Measure the specific gravity of each cell. The specific gravity
of a fully charged cell is 1.210.

1.2.1 To start the 250v IC system:

1.2.1.1 Close Switchgear Breaker W, from switch gear panel, :

to supply power to MG-1. Start MG-1 from MG-1 control

panel as follows:

1.2.1.2 Set auto-manual voltage switch in auto position.

1.2.1.3 Push "AC" start button.

'1.2.1.4 Adjust generator voltage to 260v (floating voltage)
if batteries are charged, or to 280v (recharge voltage)
if batteries need charging, by use of the auto field
rheostat. (Left side) After completing Step 1.2.1.5
and 1.2.1.6 adjust charging rate. Charging rate should
not exceed 56 amperes. After batteries are recharged,

adjust generator voltage to 260 v.
= ? ,/"A
Approved bygéj?;iZ@Vé;?i)(pwfifi) /E?é?
; 10 5

- 1.2.1.5 Close the reverse power trip breaker.
1.2.1.6 Push "IX" start button.
1.2.1.7 Close the 250v distribution switches. (BMO—ft
level north)
(a) emergency lights
(b) breaker trip power

(e) MG-L
(d) 13.8 kv transfer control power.
. 1,2.1.8 Start the 25 kw DC to AC MG-4 from control panel

in MG room as follows: Note; MG-4 will not start if
MG-1 voltage is above 270v.
i () Set auto-manual selector switch in "auto"
position.
(b) Press "start" button.
(c) Set the generator voltage to 120v by ad-

r

justing the "generator" voltage rheostat.
(d) Set the AC frequency to 60 cycles by adjusting

motor rheostat. Any change made in MG-1
voltage also changes frequency of MG-14.
Note: After loading,readjust frequency
to 60 cycles.

. (e) Set MG-4 main contactor in "on" position.

(f) Push reset on throwover switch to transfer
instrument power from TVA to MG-k.
1.2.1.9 Close breaker MCC GL4-31 to energize the alternate
power supply for AC instruments.

1.2.2 To start the 48v IC system and charge batteries

In Switch Room:

1.2.2.1 Close MCC G3 Breaker 9 to MG-2.

1.2.2.2 Close MCC GU4 Breaker 9 to MG-3.

At 48v IC Panel, 8LO-ft level:

1.2.2.3 Open generator output contactors for Generator No. 2

and Generator No. 3.
Approved by~

F

l.2.

Aty g | 34-8
vV 10/k /6

1.2.2.4 Push motor start buttons to start MG-2 and MG-3.

1.2.2.5 Adjust both generators to 51.6v with field rheo-
stat. (large dial is for coarse adjustment; small
dial is for fine adjustment.)

1.2.2.6 C(Close equalizer contactor and both Generator No. 2
and No. 3 output contactors.

1.2.2.7 Adjust battery charging rate not to exceed 69 amps
with field rheostats.

1.2.2.8 After batteries have been recharged (i.e., when
specific gravity of each cell isiztluElO),copenvequalizer
contactors and standby generator output contactors.
Stop standby MG-2.

1.2.2.9 If necessary, adjust operating generator voltage
to 51.6v, using field rheostat. The charging rate of
each generator is limited to 54 amperes.

3 Startup 48v IC System with Batteries Charged

In Switch Room:

1.2.3.1 Close breakers MCC G3-9 (or G4-9) at L48v. IC
Panel on 84O-ft level.

1.2.3.2 Push start button for MG-2 (or 3).

1.2.3.3 Adjust operating generator voltage to 51.6v.

1.2.3.4 Close the operating generator output contactors.

1.3 Heater System Preparation

Before starting the reactor or a section of the reactor

system, the heater power supply must be checked to be sure all

breakers are closed and the heaters are ready to be turned on.

1.3

1.3

1.3

" The general procedure will be as follows:

.1 Tabulate all heaters already in service. Have shift
supervisor approve this list before proceeding.

.2 All manual powerstats that are not in service should be
set at zero.

.3 Regulator motor power and control circuit power should

be turned on. (See section LA.3.1.)
/4
Approved by ’J//fi"%f/’/‘: et 34-9
( 10/4/65
. 1.3.4 All motor-operated powerstats that are not in service

should be set at zero.

1.3.5 All induction regulators that are not in service should
be lowered to minimum setting and turned off.

1.3.6 All heater breakers except breakers tagged open for
repairs should be closed. (See section LA.3.1.) The
breakers are:
1.3.6.1 Heater panel breakers, north end 840-ft level.

- 1.3.6.2 Transformer breakers on transformer platform,
over 830-ft pit.
- 1.3.6.3 Distribution panel breakers, north end 8LO-ft
level. |
1.3.6.4 Heater switch gear and MCC breakers in switch house.
1.3.7 All ten induction regulator blowers should be on.
Switches are at each blower.
During and for two hours following the heater startup,
a periodic check of all system heater temperatures should
be made to ensure that no operating heaters were turned off
and no heaters not needed were turned on. The heaters will
- be turned on as part of the reactor startup, Section 5C and
5F. This can be accomplished from the heater contfol panels.
. 2 NORMAL OFPERATION

2.1 Alternating Current and Direct Current Systems

Normal operation of the AC system involves the occasional
use of the switchgear and MCC breakers for testing the emergency
equipment (Section 3A.3), which is not normally in operation,
or for isolating sections of the electrical system for
maintenance.

Periodically the 48v and 250v IC battery banks should be
checked for dead cells by checking the liquid specific gravity
and proper liguid level.

After excessive use of the 48v DIC bvattery, or when a cell
unbalance is indicated by variation in specific gravity of the

cells, the battery will be given an equalizing charge as follows:
Approved byszz;;zégzééza;fiaé 3A-10
e i 10/1/65

2.2

V

2.1.1 Using the field rheostat, slowly increase the operating
generator voltage to 55.9 volts (2.33v/cell) and hold for
eight hours, or until successive readings of specific
gravity (over two-hour periode) show no increase.

2.1.2 If generator amps exceed 5k, operate both generators
in parallel per Battery Charging Procedure given below:

At L4L8v IC Panel, 8LO-ft level:
2.1.2.1 Push motor "start" buttons to start both MG-2.
- and 3. -

2.1.2.2 Adjust both generators to 55.9 with field rheo-

stat. (Large dial is coarse adjustment; small dial is

for fine adjustment.)
2.1.2.3 Close equalizer contactor and both generator No. 2

and No.3 output contactors.
2.1.2.4 Adjust battery-charging rate not to exceed

69 amps with field rheostats.
2.1.2.5 After battery has been recharged (i.e., when

specific gravity of each cell is 2'}1;2100, open

equalizer contactors and open standby generator output

contactors. Stop standby MG set No. 2. .
2.1.2.6 If necessary, adjust operating generator voltage

to 51.6v, using field rheostat.

2.1.3 If only one generator is used, upon completion of
equalizing, slowly lower voltage to 51.6v. -

Heater System - Normal Operation

Except during reactor system heatup when a higher load is
required, most of the heaters will be operated at system heat-
loss power.

Periodic checks will be made of the current drawn by each
heater circuit to be sure there are no heater failures., When
circulating salt, pipe temperatures will not indicate heater
conditions. Ground detection meters will be checked once per

shift on the normally ungrounded induction regulator circuits.
Approved b - 3A-11
10/4 /65

) 3 EMERGENCY AND SPECIAL QPERATIONS
" 3.1 Alternate Feeder Operation

In the event that electrical power is lost on the preferred
feeder, ORNL Circuit 234, and if there is still voltage on the
alternate line, ORNL Circuit 294, after a preset time of
1 to 10 sec, switch 129 will open and 229 will close. Switch
129 will not open during an outage of <6 sec. Table IV lists
breakers and starters which need to be reclosed after a momen-
tary power outage that cannot be closed from the main control

” board. Start Equipment listed in Tables V and VI that was
operating before the momentary loss of TVA power. DNote: TUse

* control room and walking logs to determine equipment to be

. restarted. The starters and breakers will have to be reclosed
after momentary outages, or when TVA power is resumed.

Since there is no automatic feature for transferring from
the alternate feeder back to the preferred line, this becomes
a manual procedure, and should be done as soon as Clircuit 23&
has been restored. (See section 3A.3.3.2.)

3.2 Complete TLoss of TVA Power ‘
When voltage is lost on both TVA feeders or if the fault
B is between switch 129 and 229, switch 129 will open and 229

will not close. Alternating current must then be supplied by
- the diesel generators. ©OSwitch 129 will have to be closed manu-
ally when TVA power is restored.

3.2.1 Diesel Startup Procedure

- 3.2.1.1 Dispatch an operator to the diesel house to start

at step 3.2.1.8 below, meanwhile:
3.2.1.2 Push "start" button for Diesel Generator No. 3

on DPM-3, Generator voltage increase on DPM-3 will
indicate when unit starts. The diesel will crank
for 10 seconds and if not started will repeat after
10 seconds for up to 3 attempts. If diesel fails to
start, open fuel ignitor valve and turn on fuel ig-
nitor pump motor switch (both located on west side of

diesel) and repeat start.
Approved by ead| 3A-12
10/4/65
Table IV
BREAKERS AND STARTERS NOT OPERATED
from
MAIN CONTROL BOARD
BREAKER- EQUIPMENT »
STARTER CONTROLLED BREAKER /STARTER 1OC. TVA or DG
Reverse
Power
Breaker 250 v DC MG-1 MG-1 in MG Room TVA
Starters MG-1 MG-1 in MG Room TVA
Starters H-200-13, H-201-12,
H-202-2 Htrs. HCP-1, 8L0O' level TVA-MCC-T-1
Starters RCH-1, RCH-2, RCH-3,
RCH-L4 Htrs. HCP-6, 8LO' level TVA-MCC-T-1
Starters RCH-5, RCH-6, RCH-T,
H 102-2 Htrs.
HX-1, HX-2, HX-3, .
FP-1, FP-2 Htrs. HCP-T, 840' level TVA-MCC-T-1
Starters R-1, R-2, R-3 Htrs. HCP-T, 8L0' level TVA-MCC-T-2
Starters FFT-2, FD1-2,
FDe-2 Htrs. HCP-8, 8LO' level TVA-MCC-T-1
Starters MG-2, MG-3 Motor 48v Panel, 8LO' level G-3, DG-h
Starters MG-2, MG-3
Gen. Output L8v Panel, 8L40' level DG-3, DG-L
Starters Waste Tank Vent Fan Switch in Remote Maint.
Processing Cell G-k
Breaker AA | MCC G5-2 DPM-5 in Aux. C.R. DG-5, Bus #5
Breaker CC | MCC G5-1 DPM-5 in Aux. C.R. DG-5, Bus #5
Starters H-103 Htr. HCP-8, 84o' level DG-5, MCC G5-2
Starters FFT-1, FD1-1,
FD2-1 Htrs. HCP-8, 8L0' level G-5,

3

!
s
I
!

Bus #5

3A-13

10/4 /65
Table V-
EQUIPMENT SUPPLIED FROM DIESEL GENERATOR No. 3
MCC-G3
Motor Operating TVA | Breaker |Switch-
Rating Load Load | No | Sizejgear
Equipment Description (hp) (hp) (kw)  |(xw) Amps| Breaker
Inst. Power Panel #5( 30 kva 15 15 70
e’ 30-ton Crane Lo 37 31.5 100
SP Sump Pump L.6 30
PP Pit Pump 4.6
e Drain Tk Cell Cooler| 10 ? ? 5 ?
Be Sampling #1 .5 7 15
Exhauster #2 .5
CCP-3 Aux. FV Blower T.5 7. 4.6 4.6 30
MG-2 48v DC generator 5 5 L.6 15
RCC-1 Reactor Cell Cooler 10 ? ? ? 10 ?
FOP-1 FP Lube 0il Pump 3.5 L L 11 20
TF-1 Cooling Tower Fan 5 4.6 L6} 12 15
HCV-930A |[Vent Valve 0.75 .75 .66 13 30
HCV-930B |Vent Valve 0.75 .75 .66 14 30
AC-1 Inst. Air Compressor| 40 40 33.4 33.41 15| 100
* Diesel Aux. Power 12.2kw 12.2 16{ 100
ccc-1 Coolant Cell Cooler 2 2 1.8 1.84 17 15
Inst. Power Panel #4| 10 kw 6 13 30
TWP-1 Treated Water Pump 20 20 15 15 19 50
CTP-1 Cooling Tower Pump [ 20 20 17.2 | 17.2! 20| 50
MB-4 Annulus Blower 10 10 8.8 8.8] 23 30
SF-1 Stack Fan 50 50 41.8 41.84 24 100
CCP-1 Component Cooling
Pump 75 T0 58 H
CP Cooclant Pump 5 L6 39 39 K
Lighting Transformer|100 kva 33 33 33 M
Total 344,32 [252.6
*Transfer switch to DG No. L
‘**Breakers No. Lk, 6, 21, 22 are spares.

Approved by

10/L4/65
TABLE VI
EQUIPMENT SUPPLIED FROM DIESEL GENERATOR No. L
{ Mcchu***
Motor Operating TVA | Breaker [Switch-
1 Rating Load Load | No |Size | gear
Equipment|  Description (hp) (hp) (kw) (kw) Amps {Breaker
c1* 30-ton crane Lo 37 31.5 31.5] 2 | 100
ICC* Drain Tk cell cooled 1.5 1.5 1.k 1.4i 5 15|
MG-3 U8v IC power 5 k.6 L6| 9| 15
COP-1 CP lube oil pump 3.5 L L 11 20
TF-2 tooling tower fan 5 4.6 h6]12 | 15
IR-1 He' 0> Remover 1. 13 30
Preheater .6
Dryer .6
* Diesel Aux. Power 12.2 12.2 16 | 1001
CCC Coolant Cell cooler | 2 2 1.8 1.81 17 15
CTP-2 Cooling tower pump 20 20 17.2 20 50
TWP-2 Treated water pump | 20 20 15 2l 50
WP Waste Pump 10 10 T+5 T.51 23 50:
RCC-2 Reactor cell cooler | 10 ? ? ok ? 3
MB-2 Annulus 10 10 8.8 8126 30
DR-2 He Oz remover 1 27 30
Preheater .6 .6
Dryer .6 .6
Trnsfrmr. Spect. Rm | 25 kva 15 =15 29 30
*x Inst Panel #2 & 3 25 kva 13 31 | 100
AC-2 Inst air compressor | 4O 40 33.4 32 | 100
AC-3 Ser. air compressor | 4O 40 33.4 33.4 133 | 100
FP Fuel Pump 75 L5 38.2 38.2 D
CCP-2 Comp. cooling pump | 75 70 58 58 E
SF-2 Stack Fan 50 50 41.8
Total | 212.7
¥Transfer switch from DC No. 3
*¥Transfer from MG No. 4 (250v IC supply)

¥*¥Breakers #1, 3, &, 6, 7, 8,

10, 1k, 15, 18, 19,

22, 25, 28, 30 are spares

3A-15

Approved by /h/6
10 5

3.2.1.3 After diesel starts and voltage reaches 480v,
open Breaker A-1 and with key close Breaker A-5 from
DPM-3. Get OK from technician at diesel generator unit
before adding load.

3.2.1.4 Start diesel generator No. 4 by Step 2, observing
generator volts on DPM-L.

3.2.1.5 When generator No. 4 voltage reaches L480v, open
Breaker A-2 and with key close Breaker A-3 from DPM-k.
Get OK from technician at diesel generator before adding
load.

3.2.1.6 Start diesel generator No. 5 by pushing "start"
button on DPM-5, observing generator No. 5 voltage on
DPM-5. ©Start switch automatically opens after 10 sec;
release to reset.

3.2.1.7 When generator No. 5 voltage on DPM No. 5 reaches
480v, open Breaker 7 and with key close Breaker A-L
from DPM-5. Breaker BB load is on line. Get OK from
technician at diesel generator before adding load.
(See section 3A.3.2.2.)

3.2.1.8 After each diesel starts, check the following items
in the diesel house and switch house area.
(a) Louvers are open to each unit;
(b) No obstructions are in cooling air path to diesels;
(¢c) No unusual noises from DG sets;
(d) Annunciators on Diesel panels are clear;
(e) Fuel oil level in day tank "50%;

DIESEL GENERATOR 3 or 4

(f) Lube oil pressure >20 psi (normal is 30-40 psi);

(g) Check that diesel generator 3 and L fuel ignitor
motor switch is off and fuel ignitor valve is
closed;

(h) Water temperature <180°F;
A
Approved by Mfl{{;{/ At 3A-16

10/k4 /65
DIESEL GENERATOR 5 .

(1) Lube oil pressure - normal operating range;

(j) Water temperature - normal operating range;
(k) Fuel pressure - normal operating range;
(1) Speed - 1200 rpm;
(m) Starting air pressure - 225 psig;
(n) Items "e" through "1" should be checked every
30 minutes. '
(o) Keep each generator at 480 volts and 60 cps.
3.2.1.9 After diesel generators 3 and 4 reach speed, check
load limit at 5 and diesel generator 5 load limit at 10,
NOTE: If diesel 3 or 4 is heavily loaded or starts to decrease in speed,
set load 1limit at 10. Reduce to 5 when diesel is shut down.
After diesels are started, close the following breakers:
(a) Breaker AA on DPM-5, Auxiliary Control Room;
(b) Breaker CC on DPM-5, Auxiliary Control Room.
Restart the following heaters supplied from DG-5:
(c) Heaters FFT-1, FD1-1, FD2-1, H-103 on HCP No. 8;
Start the motorized equipment listed on Tables V and
VI, using the following guide:
With both diesel generators 3 and 4 running, start X
equipment with loads listed under column "TVA Load"
in Tebles V and VI. If diesel generator 3, 4, or 5
cannot be started or fails during operation, the operator
should proceed as outlined in section 9A. .
3.2.1.10 Call a power house operator to operate diesel
units until they are shut down.
After TVA power has been re-established, the power
supply should be returned to normal as described under
Section 3A.3.3.1.
3.2.2 Heater System - Emergency Operation - Complete Loss of
TVA Power

When diesel generator No. 5 is started and switched on

to Bus 5 by opening Breaker Z and closing Breaker A-k, the
) 3.2,

3.2,

3A-17
10/4 /65

2 (continued)

radiator circuits CR-1 through 4 are automatically energized
through Breaker BB. Power is on to the heater control cir-
cuits and the radiator induction regulator blower for CR-1
through k.

When Breaker AA from the auxiliary control room is
closed, the radiator circuits CR-5 through 8 and the in-
duction regulator blower for CR-5 through 8 on the same cir-
cuit are on. When Breaker CC is closed, heaters on all
freeze valves, drain lines, except L-103 are in operation.

To turn on heaters FFT-1, FD1-1, FD2-1, the three drain
tank lower heaters, push the start buttons. Line 103 heater
can be turned on by pushing its start button.

3 Emergency Lighting, 250v DC

There is 4 kw of emergency IC lighting located through-
out Building 7503. There are twenty-eight 250v DC lights

varying from 100w to 300w capacity, distributed as follows:

No. Location Watts /bulb
13 8L0-ft level and ESA 100

3 High-Bay Area 300

3 Control Room 200

5 852-ft level, offices and hall 100

1 Service Tunnel 200

1 Vent House 100

1 Switch House 100

1 Diesel House 100

These lights are supplied from the 250v DC panel
Breaker 21 on the 8L0-ft level through a switch and an AC
operated relay. Loss of AC power to the relay automatically
energizes the DC lights.

The AC relay is fed from the switch adjacent Lighting
Panel H on the north end of the 84O-ft level.
e / '
Approved by - 7Sy pme ;i;gs
10 5

3.2.3 (continued)
After the emergency AC lights, which are supplied from
diesel generator No. 3 come on (see Section 3Al.l), the
DC lights should be turned off at the 250v DC distribution
panel to lower the load on the 250v battery.
3.3 Special Operations

3.3.1 Return from Diesel to TVA Power Supply

3.3.1.1 As soon as TVA power is restored, start up the
250v IC system by the Startup Procedure, (Section 3A.1.2).
3.3.1.2 Start up equipment from MCC T-1 and T-2 as required.
See Table IV for heater induction regulator starter.
3.3.1.3 Parallel diesel generator 3 (or 4) with TVA, and
transfer load without interrupting operations as
outlined below.
NOTE: Never opera‘teé  with generator 3 and 4 in parallel with TVA at the
same time.
Make transfer in switch house as follows:

Generator No. 4 items are listed in parenthesges.

(a) Breakers A-1 (A-2) opened, green lights indicating
on Panel DP-3 (DP-4);

(b) Breaker A-5 (A-3) closed, red light indicating on
Panel DP-3 (DP-L4).

(c) With removable handle, close Al-SS (A2-SS) on
DP-3 (DP-4).

(d) Set governor speed droop at 50 on DG-3 (DG-4).

(e) Adjust "running voltage" (generator) to agree with
"incoming voltage" (TVA) on Panel DPS by raising
or lowering VAR-3 (&) on DP-3 (4) with regulator
transfer switch in automatic position. If on
manual, use EFR-3 (4).

(f) Adjust generator speed with GS-3 (GS-4) switch
until synchroscope pointer is rotating clockwise

at 3 to 10 sec per revolution.
10/4/65

Approved b%@%{ )fifl 3A-19

(g)

(h)

(1)

(3)

(k)

(1)

Close Breaker A-1 (A-2) when synchroscope pointer

is 5 degrees before "12 o'clock." Red light will

come on, and the green light will go off.

Turn GS-3 (GS-4) to lower and hold until generator
wattmeter on DP-3 (DP-4) drops to a low value.
Open A-5 (A-3). Green light will come on and red
light will go off.

Turn off Al-SS (A2-8S). Operate diesel unloaded
for 5 min before stopping.

Press diesel stop button, DP-3 (DP-L4), and hold
until diesel stops.

Go through startup check list. (Section LA.2).

3.3.1.4 Transfer the load from generator 5 to TVA as

outlined below.

NOTE: Generator 5 cannot be paralleled with TVA. Therefore, during the

transfer from generator 5 to TVA, the heaters supplied by generator 5

have to be off for a short time. Also, all induction regulators will

be off because their control voltage is supplied from BUS No. 5.

(a)
(b)
(c)
(a)
(e)
(f)

(&)

(h)

Transfer load from Generator 5 to TVA as follows:

Open AA and CC, on DPM-5, to partially unlocad
diesel.

Open A-4 to disconnect diesel from Bus 5. Operate
diesel for 5 min. at no load before stopping.

Stop Diesel No. 5. Push button on DP-5 or DPM-5.
After shutdown of diesel, check that governor has
reset. Reset marker should be at white mark.

use mirror mounted on manifold.

Close Breaker Z to tie Bus 5 to TVA bus.

Close Breaker AA and CC on DPM-5 to restore
heater voltage.

Cleose all induction regulator heater starters (see
Table IV) and reset to walking log settings prior
to power outage. '

Go through startup Check List (Section LA.2).
10/1/65.

Approved b¥f:::§§;2%4$a;(}y;fl 3A-20

3.3.2 Return to Preferred Feeder from Alternate Feeder Without

Loss of Power to Bus No. 3 and No. L

3.3.2.1 If load on either Bus No. 3 or No. 4 exceeds 300 kw

as indicated on bus wattmeter on DPM-3 and L4, adjust

loads by starting up some standby equipment on the least

loaded bus and by stopping the duplicated equipment on

the more loaded bus. See Table V and VI for rating of

duplicate equipment and supply bus.
NOTE: The diesels can stand 10% overload for two hours.

3.3.2.2 Start up Diesel No. 3 per Emergency Startup Pro-
cedure, Steps 3.2.1.1, 3.2.1.2, and 1.2.1.8.

3.3.2.3 Synchronize, parallel, and transfer load from

alternate TVA feeder to generator No. 3 in the switch

house as follows:

(a)

(b)

(c)

(a)

(e)

(£)

(g)

(h)

Breakers S and Al are closed, red lights indicating
on DP-3.

Breaker A-5 is opened, green light indicating

on DP-3.

With removable handle, close switch A5-8SS5 on DP-3,
Set governor speed droop to 50 on DG-3. _
Adjust "incoming voltage" (generator) to agree

with "running voltage" (TVA) by raising or lowering
VAR-3 (4) on DP-3 (4), with regulator transfer
switch in automatic position. If on manual,

use EFR-3 (L4).

Adjust generator speed with GS5-3 switch until
synchroscope pointer is rotating clockwise at

3 to 10 sec per revolution.

With key, close breaker A-5 when synchroscope
pointer is 5 degrees before "12 o'clock." Red
light will come on and the green light will go off.
Turn GS-3 to "raise" and hold until wattmeter
TVA-A1l on DP-1 drops to a low value. Set lcad

limit on governor to 10 if required.
Approved by/%m ;fi}gl
10/4 /65

(i) Open Al; green light will come on, red light will
go off.

(3) Turn off A5-85 on DP-3.

3.3.2.% Start up Diesel No. 4 per Emergency Startup Pro-
cedure, Steps 3.2.1.1, 3.2.1.4, and 3.2.1.8.

,3.3.2;5 Synchronize, parallel, and transfer load from
alternate TVA feeder to Generator No. 4 in the switch
house as follows:

() Breakers T and A-2 are closed, red lights indicating
on DP-L.

(b) Breaker A-3 open, green light indicating on DP-L,

(c) With removable handle, close switch A3-SS on DP-L.

(d) Set governor speed droop at 50 on DG-L.

(e) Adjust "incoming voltage" (Generator) to agree
with "running voltage' (TVA) on panel DPS by
raising or lowering VAR-3 (4) on DP-3 (4) with
regulator transfer switch in automatic position.
If on manual use EFR-3 (L).

(f) Adjust generator speed with GS-4 switch until
synchroscope pointer is rotating clockwise at
3 to lO_sec per revolution.

(g) With key, close breaker A-3 when synchroscope
pointer is 5 degrees before "12 o'clock.” Red
light will come on and the green light will go off.

(h) Turn GS-4 to "raise" and hold until wattmeter
TVA~-A2 on DP-1 drops to a low value. Set load
limit on governor to 10 if required.

(i) Open A-2; green light will come on, red light will
go off.

(j) Turn off A3-SS on DP-L.

NOTE: Never operaté with generator 3 and 4 in parallel with TVA at the

same time.
ey
A a b <fi2§?f53é5%5;kflz
pproved by =y Afef e\

NOTE :

NOTE :

3A-22

1074 /65

3.3.2.6 Transfer from alternate TVA bus to preferred TVA

bus as follows:

(a)

(b)

(c)

(a)

(e)
(£)

(g)

The equipment on

the switching from

(h)

3.3.3 Weekly

Turn the manual-sutomatic selector switch to the
manual position, ACR Panel 11.
Open switch 229 and close switch 129 from ACR
Panel 11 to transfer to preferred feeder.
Turn the manual-automatic selector switch to the
automatic position ACR Panel 11. .
Close the following breakers to restore TVA power
to Bus 5:
Breaker AA on DPM-5
Breaker CC on DPM-5
Start MG set #1 per section 3A.1.2.1.
Transfer load from generator No. 3 to TVA by
special operations, Section 3A.3.3.1.
Transfer load from generator No. 4 to TVA by
special operations, Section 3A.3.3.1.
the following buses will be without power during
ORNL Circuit 294, alternate, to 234, preferred:
TVA Switchgear Bus
Switchgear Bus No. 5
TVA MCC-T1 and T2
MCC G5-1 and G5-2
Auxiliary Substation )
Restart all equipment as required having combination
starters on thé buses noted in the above note.
(See Table IV)
Test Loading of Diesel Generators

3.3.3.1 Diesel Generators No. 3

Generator No. 4 items are listed in parentheses.

(a)

Start up Diesel Generator No. 3 (4) as follows:
1. Follow steps 3.2.1.1, 3.2.1.2 (3.2.1.4) and -
3.2.1.8 of this procedure.
Approved by 3A-23
;; g é 5%% N 10/4 /65

3.3.3.1 (continued)

2.

L.

After unit starts, run at half throttle for
15 min by setting governor load limit to 5
(located at diesel).

Notify Shift Supervisor before paralleling
with TVA.

Set load limits on governor to 10 if required.

(b) Parallel diesel generator 3 (4) with TVA and

transfer load to diesel generator 3 (4) without

interrupting operations as outlined below.

Transfer must be made in switch house.

l.

Breaker S(T) and A-1 (A-2) closed, red light
indicating on DP-3 (DP-L4).

Breaker A-5 (A-3) opened, green light indicating
on DP-3 (DP-4).

With removable handle, close switch A5-5S
(A3-83) on DP-3 (DP-L4).

Set governor speed droop at 50 on DG-3 (DG-L4)
(located on diesel).

Adjust "incoming voltage" (generator) to agree
with "running voltage," (TVA) on panel DPS

by raising or lowering VAR 3 (4) on DP-3 (4)
with regulator transfer switch in automatic
position. If on manual use EFR 3 (4).

Adjust generator speed with GS-3 (4) switch
until synchroscope pointer is rotating clock-
wise at 3 to 10 sec per revolution.

With key, close breaker A-5 (A-3) when synchro-
scope pointer is 5 degrees before "12 o'clock.”
Red light will come on and the green light
will go off.

Turn GS-3 (GS-4) to "raise" and hold until
wattmeter TVA-Al (TVA-A2) on DP-1 drops to a

low value. Set load limit to 10 if required.
Approved by

3A-2k
10/4/65

3.3.3.1 (continued)
9. Open A-5 (A-3); green light will come on, red
light will go off. )
10. Turn off Al-SS (A2-SS) on DP-3 (DP-4)
Operate Diesel Generator 3 (4) under load for
30 minutes, then return to TVA power as follows:
(¢) Parallel Diesel Generator 3 (4) with TVA, and
transfer load without interrupting operations as

outlined below.

NOTE: Never operate with Gen. 3 and 4 in parallel with TVA at the same

time.

Make transfer in switch house as follows:

Generator No. L items are listed in parentheses.

1. Breakers A-1 (A-2) opened, green lights indi-
cating on Panel DP-3 (DP-4).

2. Breaker A-5 (A-3) closed, red light indicating
on Panel DP-3 (DP-4).

3. With removable handle, close Al1-SS (A2-SS)
on DP-3 (DP-4).

4. Set turbine governor speed droop at 50 on
DG-3 (DG-4).

5. Adjust "running voltage" (generator) to agree
with "incoming voltage" (TVA) on Panel DPS
by raising or lowering VAR-3 (4) on DP-3 (4) with
regulator transfer switch in automatic position.
If on manual, use EFR-3 (k).

6. Adjust generator speed with GS-3 (GS-4) switch
until synchroscope pointer is rotating clock-
wise at 3 to 10 sec per revolution.

7. Close Breaker A-1 (A-2) when synchroscope
pointer is 5 degrees before "12 6'clock."

Red light will come on, and the green light
will go off.

8. Turn GS-3 (GS-4) to lower and hold until gene-
rator wattmeter on DP-3 (DP-4) drops to a low

value.,
Approved by % z */flz PN 3A-25
) 10/k4/65

3.3.3.1 (continued)

9.

10.

i1.

12.

Open A-5 (A-3). Green light will come on and
red light will go off.

Turn off Al-SS (A2-SS). Operate diesel un-
loaded for 5 min before stopping.

Press diesel stop button, DP-3 (DP-4) and
hold until diesel stops.

Complete Diesel Startup Check List. (Section
La.2)

3.3.3.2 Diesel Generator No. 4

Repeat 3.3.3.1 using values in parentheses.
3.3.3.3 Diesel Generator No. 5
Check that the governor load limit knob is set
at 10.

Start diesel generator No. 5 as follows:

(a)

(b)

(c)

()

(e)

1.
2.

Check that the starting air supply is normal.
Crank the engine by pushing the start button
on DPM-5 in Auxiliary Control Room.

Check to see that there is oil pressure indi-

cated on the lubricating oll pressure gauge.

Allow the engine to run for five minutes without

changing the control settings.

Vary the engine speed by turning the governor

synchronizer knob clockwise until the engine runs

at approximately full governed speed. This will be

when the fregquency meter indicator on the control

panel starts to move,

Turn the governor switch control handle to vary the

engine speed to obtain a 60-cycle reading on the

frequency meter.

NOTE: The governor speed droop knob will never e used in a single unit

application, so the indicator on this knob should remain pointing

at "0".

The governor synchronizer indicator merely indicates how many turns

of the synchronizer knob have been made.
, o
Approved ’oy{(fivz/é]z&m 3A-26
10/L4 /65

3.3,

3.3.3.37 (continued)

(f) The control panel volitmeter must indicate correct
generator terminal voltage (480v) with the engine
operating at rated speed. To establish the correct
voltage reading, turn the adjusting rheostat con-
trol knob to left of the voltage regulator. Do not

change this setting or the position of the exciter

field rheostat after the proper voltage (L80 volts)

reading is obtained.

(g) Open Breaker 7 and with key close Breaker A-4 to
tie Diesel No. 5 to Bus No. 5.

(h) Close Breakers AA and CC (DPM-5) to restore power
to heater, MCC's ‘G5-1 and G5-2.

(i) Close all induction regulator heater starters (see
Table IV) and reset to walking log setting.

(j) Operate Generator No. 5 under load for 30 min.

(k) Transfer back to TVA as follows:
1. Open Breaker AA, CC, and A-L in this order.
2. Close Breaker Z.

(1) Repeat Steps (i) and (j) to restart heaters.

(m) Stop the engine by pushing the stop push button in
and holding it in until the engine has stopped.

(n) After shutdown of diesel, check that governor has
reset. Reset marker should be at white mark. Use
mirror mounted on manifold.

3.3.3.4 After the weekly test loading has been completed -
recheck startup list to be sure diesels are ready for
emergency start. (see Section LA.2)
4y Test of 13.8 KV Automatic Transfer

These tests can be made without interrupting operation.
However, a power faillure during the test would require that
the switch 229 be closed manually at the pole to put the
alternate line in operation. OSwitch 129 should be opened
manually and a check be made to insure that there was no
fault in the area before closing Switch 229.

Bach month P & E Electrical Department will be requested

to perform the tests outlined below. The schematic diagram,

dc-47278 shows the switch identification.
Approved by *Mam ;fi}g?
10 /4 /65

3.3.4,1 Routine Testing Procedure, Automatic Operation

(a) Decouple motor operators #129 and 229 from line

(b)

(c)

switches by means of decoupler assembly between

mechanism and vertical operating pipe at each pole.

To simulate loss of potential on preferred line

(Emergency line energized):

l.

3.
L.
p)
6

Open Switch A and B on TD-1 with S5-1 set on

automatic.

Automatic operation -- preferred line switch

opens after time delay, emergency line switch
closes.

Reclose Switch A, B, on TD-1

Set S-1 to mamual.

Open Switch 229. Close Switch 129.

Switch S-1 to auto.

To simulate loss of potential of preferred line,

(Emergency line Not energized):

l’

Open Switches A, B, and J on TD-1 and A on
TD-2 with S-1 on automatic.

Automatic operation -- none.

Reclose Switches A, B, J, on TD-1 and A on
TD-2.

To simulate overlocad through CT's, followed by loss

of potential on preferred line: (Emergency line

energized).

1.

Open switch poles D, E, F, G, H, and I on TD-1
with 5-1 on automatic.

Manually close overcurrent relay 50-1, 50-2, or
50-3.

Immediately open Switches A and B on TD-1.
Automatic operation -- preferred-line switch
opens, lockout light remains illuminated.

Reclose all switches A through I on TD-1.
Approved by(/jzé?éfifék§<2;/fi¢¢fi4 3A-28

L

10/4 /65

3.3.4.1 (continued)

(e) To simulate loss of potential on emergency line

after transfer to emergency line:

1.
2.

L.
5.

Repeat step @4 (b)-1

Open switch poles J on (TD-1) and A on (TD-2)
only.

Automatic operation -- emergency line switch
opens after time delay.

Rectose J on TD-1 and A on TD-2.

Repeat steps @D(¥)Lclose switeh 129, 6.T.

(f) To simulate overcurrent surge through CT's without

subsequent potential loss on preferred line:

l.

3.

Open switch poles D, E, F, G, H, and T on
TD-1 with S5-1 on automatic.

Manually close overcurrent relay 50-1, 50-2,
or 50-3. Automatic operation: no operation -
lockout resets after time delay.

Close switch D, E, ¥, G, H, and I on TD-1.

(g) Recouple motor operators 129 and 229 after comple-

tion of the above tests.

Approximately every 12 months, P & E Electrical Depart-

ment will test the overcurrent relay settings of 50-1, 50-2,
and 50-3 and the undervoltage relay settings of 27-1, 27-2,
27-3, and 27-4. These will be set by standard ORNL procedures.

When these relays are being tested, the automatic transfer

system will be deenergized by opening switch 108 on ACP #11

and opening 250v IC supply breaker (13,8Krtransfer control)
in the 250 v IC supply panel (840' level). If possible the

test should be made when the reactor is not in operation.

NORMAL SHUTDOWN

L.,1 Alternating Current Systenm

4.1.1 Shut off load on electrical bus to be shut down — see
Process Distribution Drawing D-KK-C-41152.
Approved by"’ffi:i;zég?%i?’flbffh 3A-29

10/4/65
- 4.1.1 (continued)
. NOTE: If this is a shutdown of MCC No. G-3 or MCC G-4, or Bus No. 3 or L,
start up duplicate equipment on bus to be left in operation, see
Table V and VI, Section 3A.3.2. Equipment which can be operated from
either bus should be transferred to the operating'bus.
4.1.2 Open breaker supplying bus (or buses) being shut down.
Tag breakers that are opened on the supply side of equip-
mént to be repaired to prevent them from being closed by
7 others during maintenance. |
- L.2 Direct Current Systems
A shutdown of either the L8v IC systems or 250v DC systems

requires that emergency loads supplied from these systems are
not required during the shutdown.
4.2,1 UBv System

To shut down the 48v system, first open the generator

load breaker at the 48v panel outside the battery room.
Second, open the battery bank safety switch in the battery
room. Then turn off the operating MG set, and open
Breakers MCC (G3-9 and MCC G4-9 to isolate the supply system.
Either 48v MG set can be shut down for normal maintenance

- by using the alternate unit to keep the control circuits in
operation.

. h.,2.2 250v DC System

To shut down the 250v IC system, open the load switches

in the 250 v distribution panel outside the battery room;
turn off the 250v MG set No. 1 and then open breaker W in the
switch house.

The 250v battery has a two-hour life at full load, but
without any other 250v emergency supply this is just
sufficient capacity to shut down the reactor any time the

MG No. 1 set is off.
Approved by j%Z;é; Ve ?fi}go
& ;3 10/4 /65

k.3 Heater System Normal Shutdown

Normal shutdown of all heaters can be made at the heater
control panels.

Manual powerstats on the panels are turned to zero. The
heater ammeter should read zero amps. Motor-operated power-
stats are turned off by holding the "lower'" push button until
the ammeter reads zero and then 10 additional seconds. The
induction regulators are turned off by holding "lower" push
button until the minimum ammeter reading and then are turned
off by pushing the "off" button. Fill line heater H-103 is
turned off by turning manual powerstat to zero and then pushing
the "off" push button.

Induction regulator blowers and control power to the panels

should not be turned off on a normal shutdown.
Approved by 4 / g?él
’ 10/2 5

3B INSTRUMENT AIR AND SERVICE AIR SYSTEMS

The instrument air system supplies clean, dry, compressed air for
pneumatic instruments and other special uses. Two Joy compressors ACL
and AC2 are used to compress the air, which then passes through an
aftercooler and entraimment separator to a common line supplying two
parallel receiving tanks. From the receiving tanks, the air passes
through one of two parallel drying stations containing Trinity heatless
dryers. The dry ailr is distributed through headers to locally mounted
filter and reducing stations. Two nitrogen cylinder banks provide
emergency gas pressure to headers serving the more important equipment.

The service air system supplies air for pneumatic tools, etc.

One Joy air compressor and receiver tank are provided. The compressed
air without drying is distributed to stations located in various parts
of the building. Service air can also be used for emergency cooling
of freeze valves normally supplied by component cooling pump No. 3
(see 3D) and can be valved into the instrument air system upstream at
the receiver tanks if required.

1 STARTUP

l.1l Instrument Air Compressors

1.1.1 Check that the cooling tower water system is in opera-
tion and water flow is adequate to each compressor head
and after-cooler.

1.1.2 Check the oil level in each air compressor crank case.

1.1.3 Check that the electrical and control power is on to
each compressor.

1.1.4 Check the air valving. Open the valves in the com-
pressor discharge lines and the supply and discharge lines
t0 both receiver tanks. (Both instrument air receiver
tanks will be left on-stream.)

1.1.5 Check tfié drain-valves. Open valves in the drain lines
from the entraimment separator, receiver tanks, and line
filters downstream of the receiver tanks. Close valves

in the lines, bypassing the drain line traps.
Approved by _

1.2

3B-2
10/26/65

1.1.6 To start compressors ACL or AC2, set compressor selector
switch (on MB12) to the compressor being started, and push
start button for the selected compressor. (The standby
compressor will start automatically if the instrument air
pressure drops below the setpoint.)

Instrument Air Dryer

1.3

1.2.1 Close the discharge valve and discharge filter drain
valves of both dryers.

l.2.2 Open dryer purge valves and humidity indicator bleed
valves.

1.2.3 Turn on power to dryers and slowly open valves in air
supply lines to dryers.

1.2.4 Adjust purge flows and moisture indicator bleeds to
both dryers.

1.2.5 Let dryers operate until desiccant in indicator window
turns blue or through one complete cycle.

1.2.6 Close the inlet and filter drain valves of the standby
dryer.

l.2.7 Slowly open the valve in the discharge line from the
dryexr which 1s to be operated.

1.2.8 Check the instrument air header moisture analyzer.
It should read <10% of scale.

Instrument Air Headers

1.4

1.3.1 Open all header block valves and set all pressure-
reducing valves to the proper discharge pressure. At
the reducing stations which have duplicate reducing valves,
the valves must be closed which isolate the standby-
reducing valves.

1.3.2 Open all valves to instruments, and close all spare
valves to prevent excessive use of air.

Emergency Instrument Air Supply

1.4.1 Check that both banks of 6 nitrogen cylinders are full
and. all cylinder: valves are open.
1.4.2 Set PIC 9006-1 at 65 psig, so that nitrogen will be

used only on loss of normal instrument air pressure.
Approved by

1.5

3B-3
10/26/65

1.4.3 Open the block valve for one bank and close the block
valve in the standby bank.

Service Alr Compressor

1.5.1 Check the cooling water flow.

1.5.2 Check the 0il level in the crank case.

1.5.3 Check the air valving. .

1.5.4 To start the motor, switch the electro-pneumatic
selector switch to the "hand" position. The compressor
will load up and will subsequently unlcad and load auto-
matically to maintain the set pressure. If usage is small
it may be desirable to set the selector switch to "Auto.”
The compressor will then start and stop to maintain the

desired pressure.

2 NORMAL OPERATION

2.1

Instrument Air Compressors

28

One instrument air compressor is normally in operation with
the other in standby. Periodic checks should be made to
assure that there is adequate cooling water flow to the com-
pressors and aftercoolers, and that the water traps are oper-
ating properly. Any abnormal vibration or noise should be
investigated.

Instrument Air Dryers

2.3

One of the instrument air dryers is normally in operation.
The other should be in standby with the power off and valves
closed. Periodic checks should be made to see that the purge
and dryer bleed flows are adequate, the dryers are cycling,
and the air is dry.

Instrument Air Distribution

2.4

Periodic checks should be made of the air flow rate and header
pressures. The filters will be periodically blown down.

Imergency Instrument Air Supply

The two six cylinder banks of nitrogen cylinders will be full
at all times. ©One bank will be connected to the emergency

air headers through PCV 9006, which will be set to open at 65
o
Approved by &Q%f 55%%f2;gg&zfim 3B-4
) v 10/26/65

2.4  (continued)
psig. The other will be valved off and in standby. All
cylinder valves on both banks will be open.

2.5 Service Air Compressor

The service air compressor is not normally in operation unless
needed for pneumatic tools or emergency cooling for freeze
valves in the coolant cell or fuel processing cell.. When in
service, periodic checks should be made as described in 2.1
above. |

3 EMERGENCY OR SPECIAL OPERATIONS

3.1 Loss of Instrument Air Pressure

Abnormal air usage or compressor troubles could cause the
instrument air pressure to drop. Alarms will occur and the
standby compressor will start. If the pressure continues to
drop, the critical air headers will be supplied with nitrogen
from the emergency nitrogen banks. When the on-stream bank
pressure drops to approximately 100 psig, this bank should be
isolated and the standby bank put on stream. Cylinders should
be replaced as used. Any unnecessary usage should be reduced
while operating on emergency supply. When the compressors
are put back on stream, normal usage can be resumed. Pipes
and valves are provided for cross-tieing the service air
compressor with the instrument air compressors upstream of
the dryers.

3.2 Loss of Cooling Tower Water to the Compressors

Cooling tower water is normally used to cool the compressors
and aftercoolers. However, connections are provided for the
emergency use of process water. Hand valve 880 must be closed
and 872 opened.
4 SHUTDOWN
L.l Header Shutdown

Shutdown of any header can be accomplished by closing the
header supply valve. The equipment affected should be checked

prior to shutdown to be sure that a needed air supply is not
>

Approved by ZF / 2?&
10/2 5

4.1 (continued)
terminated.
4.2 Shutdown of Entire Instrument Air System

A shutdown of the instrument air system should be made in the

following order:

4.2.1 Shut off emergency header block valves if emergency
alr is not needed during the down period.

* ‘ 4.2.2 Stop air compressors. Open electrical supply breakers

if maintenance work is to be performed on the compressors.

4.2.3 Close supply discharge and filter drain valves to air
dryers to keep desiccant dry during down period. Allow
dryers to operate through one complete drying cycle to
remove pressure from both drying columns, and then close
dryer purge block valve and indicator bleed valve. Turn
off the electrical power to both dryers.
Approved bgfigflfigjikg%5;6&4fla\5 3C-1

7/23/65

3C WATER SYSTEM

Potable water as supplied to the MSRE from the X-10 water system is
used for drinking and sanitary purposes and for fire protection. After
passing through a backflow preventer, the water is called process water
and is used in the liquid waste system, in the vapor-condensing system,
for general clean-up of equipment, as makeup for the cooling tower water
system, and for cooling of the charcoal beds. Two 520-gpm centrifugal
punmps are provided for circulating cooling tower water, which is cooled
by a two-fan induced draft cooling tower. The cooling tower water is
used for air compressors, air conditioners, in the chemical plant, for
the lube-oil systems, in the charcoal beds, and for condensing steam
from the drain tank steam domes. (Process water can also be used for
this.) Cooling :tower water is also used in a shell-and-tube heat
exchanger to provide cooling for the treated water system. Two 230-gpm
centrifugal pumps circulate treated water in a closed loop to cool in-
cell components. Makeup water is supplied by condensing building steam
in a shell and tube heat exchanger using cooling tower water as the
coolant. Treated water is also used to fill the Nuclear Instrument
penetration. This water is continucusly recirculated through a closed
loop by a 5-gpm pump to maintain uniformity of the water condition
throughout the penetration. The water is treated with 2000 ppm of a
mixture of 25% potassium tetraborate and 75% potassium nitrite to mini-
mize corrosion. Steam condensate is also used to supply water to the
feedwater tanks. Thiskuntreated water is used in the drain tank bayonets
to remove decay heat from the reactor fuel after the reactor has been
drained.

1 STARTUP
1.1 Potable Water System
This system is started by opening the main supply valve
located north of the 7503 building.

l.2 Process Water System

l.2.1 Open the malin supply valve.
1.2.2 Put the process water backflow preventer into service
and check that it is functioning properly as indicated by

little or no leakage from the drain line. Every six months
»
Approved byzfié?i;Z?/Lffi7’;umflh_, 3C-2
14 .

1.3

7/23/65

1.2.2 (continued)

a complete checkout of the backflow preventer should bhe
made by Inspection Engineering per ORNL Standard Practice
Procedure No. 1k.

1.2.3 Put the liquid waste backflow preventer into service
and check that it is functioning properly as indicated by
little or no leakage from the drain line. Every six months
a complete checkout of the backflow preventer should be
made by Inspection.Engineering.

1.2.4 Check that the cooling tower makeup valve is operating
properly.

Cooling Tower Water Systéem

1.4

1.3.1 Check that the cooling tower basin is full of water and
is clean.

1.3.2 Open the supply and discharge valves from both cooling
tower pumps.

1.3.3 Start each pump individually and check for leaking - .
packing or hot bearings. Leave'ghe pump running.

1.3.4 Start the cooling tower fans.

1.3.5 Adjust all flows and set the temperature controller
as indicated on the building log.

Treated Water System

1.4.1 Check that the level in both condensate storage tanks,
and the surge tank are as indicated in the building log.

1.4.2 Open the supply and discharge valve from both treated
wéter pumps .

1.4.3 Start each pump individually and check for leaking
packing or hot bearings. Leave one pump running.

1.4.4 Open the valves at the treated watercooler, and adjust
all flows as indicated on the building log.

NOTE: The design pressure of the thermal shield is <O psig. Extreme

caution should be taken to avoid overpressurizing it. Before opening

the inlet valve, all valves in the outlet lines must be tagged open.

1.4.5 Check that pressure drop across the filter in the
diesel house is less than 10 psi.
Approved by 452;5222/€§%;*%f1\\_ 3¢-3

: 1.4

7/23/65
Treated Water System (con't)

1.5

1.4.6 Check that the pressure drop across the strainer in the
| water room is less than 8 psig. Switch to other side of
the strainer and check that pressure drop is less than
8 psig.

Condensate Makeup

Condensate is made up by opening the steam and cooling water
supply valves to the makeup condenser and by opening the valve to
the desired condensate storage tank.

Decay Heat Removal System

1.6.1 Add condensate to each feedwater tank (FWT-1 and FWT-2)
until the total volume in each system is approx. L0 gal.

1.6.2 After a fuel drain the heat removal will start automatically
by opening ESV 806 or ESV 807 if the fuel drain tank temper-

ature reaches l3OOOF.

2 NORMAIL OPERATION

2.1

Potable Water System

2.2

No operator action is required for the normal operation of the
potable water system other than to prevent freezing. It should
be noted.that'this system_ié never to be confiécted to equipment
which might be contaminated or which might contain chemicals.
Process water should be used for this purpose and for all cleaning
and flushing operations.

Process Water System

2.3

During normal operation, a periodic check should be made to deter-
mine that the main backflow preventer and the waste system back-
flow preventer are operating properly. Water flow from the

drains greater than 1 ce/min would indicate malfunctioning of the
backflow preventers.

Cooling Tower Water System

In normal operation the supply and discharge valves from botbh
cooling tower pumps should be open. One pump should be in operation
with the other in standby. The operating pump should be checked

periodically for leaking packing. The flow and temperature
Approved oy, - 3C-4
7/21/65

controller should be set as indicated on the building log. Both
cooling tower fans will be operated in the summer; however, in

cold weather only one may be needed. Alternating the fans will

Tn normal operation the supply and discharge valves from both
treated water pumps should be open. One pump should be in operatio
with the other in standby. The operating pump should be checked
periodically for leaking packing. The flows should be set as

To avoid rupture of the thermal shield, the pressure should
not exceed 20 psig. This is equivalent to 12 psig in the water
room (PT 84L) with no flow or 13 psig on PI 84k at design flow..
The treated water filter in the diesel house should be bypassed
and cleaned when the pressure drop exceeds 5 psig. The strainer
in the water room should be switched to the clean side when the
inlet pressure exceeds 8 psig. The treated water should be sampled
periodically, and a mixture of 25% potassium tétraboratg and 75%

potéssium nitrite added to keep the concentration greatéf’than

After each condensate storagé tank has been filled, it should be
sampled. If analysis indicates that it is not within limits
specified in Section 6C, it should not be used in the treated

water system or the steam drums. Water from the alternate tanks

2.3 Cooling Tower Water System (con't)
help prevent excessive icing of the towers.
2.4 Treated Water System
indicated on the building log.
2000 ppm.
2.5 Condensate Makeup
should be used while waiting for analytical results.
2.6 Decay Heat Removal System

During normal operation of the reactor, the steam drum level
and drain tank temperatures should be checked periodically to
insure that there is no water leakage to the steam drums.

To remove decay heat from fuel salt, this system will be
operated intermittently. The block valves (ESV 806 and 80T)
in the water supply to the steam drums will open when the drain-

A
Approved mm 3C-5
=<7

- 2.6

7/23/65
Decay Heat Removal System (con't)

tank temperature rises to l3OOOF and will close when the tempera-
ture drops to 9500F. The water level must be kept above the top
water inlet to the bayonets, approx. 5 in., and below the steam
outlet at 7-in. elevation. Other water levels can be used by
controlling the water inlet flow using the ICV 806 or ICV 807.
However, this increases the stresses and might shorten the life of
the bayonets. If the ICV's are used the water flow must be stopped

manually when the fuel temperature reaches approx. 95OOF.

- 3 EMERGENCY OPERATION

3.1

Potable and Process Water

3.2

No emergency operations are anticipated for these systems.

Cooling Tower System

3.3

Iow cooling tower water pressure will switch the supply to
the drain tank steam drum condensers from the cooling tower water
to process water (HCV 882C1). Process water can be turned on
manuvally to the instrument air compressors by opening V 872
and closing V880. q
Treated Water System.

Nuclear contamination of the treated water system, monitored
by RIA 827, will close block valves in all the discharge water
lines from the reactor and drain tank cells. Then high pressure
will close HSV 844 in the supply line to the thermal shield. All
inlet water lines into the reactor cell and drain tank cell
contain check valves which prevent backleakage of activity.

If activity in the cooling water is the only (or most
critical) incident at the time, dispatch an operator and H. P.
representative to the water room to survey the water piping for
activity. Check the common return lines. If radioactive, check
the return lines from the RC and DTC space coolers. If one or more
are free of activity, close HV's in the supply to and the return
from all dther in-cell eguipment. Then raise the setpoint on the
activity monitor (RIA 827) to open the block valve in this line,

which will allow space coolers to be operated and prevent buildup
Approved b@m_ . 37(7263 /65

- Expansion of water after the block valves close is released
through 100 psi pressure relief valves which discharge to the
waste tank except in the case of the thermal shield. Rupture
disks in 1855 from the thermal shield water lines 8Lk4 and 845
relieve at 18 psi to the vapor~condensing system. Also, to
prevent damage to the thermal shield if the inlet block valve
(Fsv 84k4) leaks, a flow-limiting orifice in L 84k has sufficient
AP to carry the entire water capacity at full pump head.

All water lines which can be exposed to subfreezing
temperatures will be winterized and insulated. This winterizing

will consist of tracing pipes with either electric heaters or

3.3 Treated Water System (con't)
of cell pressure.
- 3.4 Winterization
‘steam lines.
3.5 Decay Heat Removal System

If loss of water from the system indicates a steam or water
leak, the fuel can be transferred to the other drain tank where

heat removal can be continued.

4  NORMAL SHUTDOWN

L.1

Cooling Water Systems

4.2

Normal shutdown of an entire cooling water system requires
that there be no demand on that system during the down time.
The circulation of either the CTW system or the TW system can be
stopped by stopping the circulating pump on MB No. 2. The cooling
tower fans can also be shut off from MB-2.

Any of the parallel paths of the cooling watér systems can
be isolated by closing supply and discharge hand valves. This

allows the rest of the system to continue operation.

"Decay Heat Removal System

When the fuel drain tank temperature drops to approx.
9500F, the water control valve, ESV 806 or ESV 807, will chose
automatically and remain closed until the fuel temperature increases

to 1300°F. The water in the steam dome will then be boiled out and
Approved b&;fi?zgégééflw%O\ 3¢

v | 7/23/65
4.2 Decay Heat Removal System (Con't)
stored in the feedwater tank until needed. The fuel drain tank -

temperature should be observed to insure that it does not continue

1o cool and to freeze the fuel salt.
3D COMPONENT COOLING SYSTEMS

Cooling is needed to prevent overheating of the reactor neck, control
rods, and ffiél pump, and for freezing the freeze valves.

Components located in the reactor and drain tank cells are cooled by
the primary component coolant system which circulates reactor and drain
tank cell air, using rotary type positive displacement blowers. Two
blowers (CCP' No., 1 and No, 2) are installed, but only one is used at a time.
The other serves as an emérgency standby unito

Freeze valves located in the coolant drain tank cell and fuel proceésing
cell are cooled by a secondary system using atomspheric air. The prime mover
is another rotary type positive displacement blower (CCP No. 3). Emergency
backup is provided by air from the auxiliary air compressor.
1l STARTUP

l.1 Primary System

l.1.1 Check that the treated water system is in operation and

| cooling water flow is adequate on the gas cooler and oil
coolers.

1.1.2 Check that the instrument air system is in operation and air
is on to the control valves in the component cooling system.

1.1.3 Open the large suction and discharge valves to both blowers
and backseat each of them, This forms part of the reactor
-cell containment.

l1.1.4 Open the valves which allow gas circulation past the cell
radiation monitor and O, analyzer.

1,1.5 Close the valves in the cell evacuation lines and sample
lines.,

1.1,6 Start CCP No, 1 or No. 2 by pushing "start' button on MB No. 3.
Observe that the system pressure increases and is controlled
by PAIC 9604, @ 8.1 psig.

1l.1.7 Leak check the bonnets of the blower discharge valves. These
must not leak.

l.1.8 5Start flows to components to be cooled as required and

evacuate cells through line 565,
Approved 9%51?552‘%%2;/gg¢fl\_ 3D-2

VvV 7/26/65

1.2 Secondary System
1.2.1 Check the 0il level in the blower (CCP No. 3) and add oil

if necessary, ‘ _

1,2,2 Visually check the suction filter and replace the element .
if necessary. |

1.2.3 Set PICA 906B to zero, Open V-906A.

1.2.4 Start CCP No, 3 by pushing“the button on MB 12,

1.2.5 Adjust PICA 906B to 8 psigland observe that PCV 906B con-

7 trols properly. |

1,2,6 Adjust flows to freeze valves as required for their operation.

1.2.7 Start the service air compressor. | |

1.2.8 Set PCV 967 to control at 8 psig and close the valve up-
stream from PCV 967, '

1.2.9 Stop the service air compressor if it is not needed for other

purposes.,

2 NORMAL OPERATION
2,1 Primary System

Normal operation consists of periodic observation of the temperatures
at the gas cooler, water flows, and the differential pressure as
indicated by PdIC 960A. A low oil pressure alarm, PA 791 (or 795)
monitors the blower lubricating system,' During an extended run,

when one blower has operated for 4000 hr, it should be put in
standby service, and the other blower shofild_be put into operation
until the end of the run.

2.2 Secondary System

The secondary system blower, CCP No, 3, should be - checked peri-
odically for proper oil level, unusual noise, and hot bearing

housings. PIC 906 should be checked for proper pressure control.

3 EMERGENCY OPERATIONS
3.1 Primary System

Upon annunciation of low oillpressure (PA 791 or 795) on either
CCP No. 1 or No. 2, low system pressure (PdA 960A) or low cooling
water flow (PA 875) to the oil cooler, the condition should be im-

mediately remedied, or the operating blower should be stopped
Approved bgzé;zq:2‘§§§;04h’%\ 3D-3

3.1

7/26/65

Primary System (continued)
(if still running). The standby unit should be started by push-
ing the start button on MB No. 3. It is then an administrative
decision whether the reactor should continue to operate without
a standby blower available.

cecondary System

Loss of CCP No. 3 for any reason is indicated by a low pressure
alarm, PICA 906B. Emergency cooling can be provided to the
freeze valves by starting the service air compressor and opening
hand valves V-96TA and V-967C and closing HV-906A in the blower
hourse. PCV-967 should be checked and adjusted to 8 psig if

necessary.

i SPECIAL OPERATIONS

L.1

Reactor Cell Evacuation

4.1.1 Initial or Periodic Cell Evacuation - The reactor and
drain tank cells can be evacuated at ~100 cfm using CCP
No. 1 or CCP No. 2 by opening V-565C in the vent house. The
periodic evacuation should be started when the cell pressure
is —1.8 psi (3.6 in. Hg vacuum), and should be stopped at a
—2.2 psi (.4 in. Hg). If the component cooling system
pressure starts to drop during evacuation, throttle V-565C
to get PAIC-960A to control. To stop evacuation, close
V~565C.

4.1.2 Continuous Cell Evacuation - If desired, the reactor cell
can be kept at a constant vacuum by continuvally bleeding
off gas through line 569. Open V-569A and throttle V-569B
until "FI 569 indicates a flow equal to the inleakage to the
reactor cell plus the N» purge rate into the cell through
the reactor cell and drain tank cell sump bubbler lines,

FI RCC-A and FI DTC-A. FqI 569 will summarize the flow.
4.1.3 Inspection of Primary System Blowers - Since CCP No. 1 and
CCP No. 2 are located inside tanks which are part of the

reactor cell containment, routine inspection of these
blowers should only be made when the reactor is shut down.

Valves are provided for isolating each tank and minor repairs
Approved byfififig%azifi%%/wfi%fi o ‘ : 3D=4
b v R _ ) S

T/26/65

can be made under admlnxstratlve control. -
~Plugging of the oil filter appears to be the most likely
' failure in the system. . However, with a clean gas system
the oil filter shqfildzlast >4000 hr. At this time the oil
‘level should be chéckedfland 0il should be added if neces-
sary. The filter element and oil should be changed if the
.blbwer has operated >2000 hr since the last change, or if an
extended run is planned. Inspection and maintenance of the
oil system can be made by opening the 12-in. flanged in-
spection port on the blower containment tanks. The drive

belts should also be examined at this time.

5 NORMAL SHUTDOWN

When cooling air is no longer needed, the operatlng blowers can be

shut down by pushing the "stop" button on MB No, 3.
If maintenance is to be performed on part of the system, valves

should‘be closed to isolate that part of the system.
Approved byfl“@é«—/mm 3E-1

8-16-65

3E SHIELD AND CONTAINMENT

The detailed steps in getting the reactor shield ready for operation
and checking containment are covered in the Startup Check List, Section
4E. HoWever, the general plan to be followed, reasons for actions taken,
ete., are given below for each area.

The maximum credible accident for the MSRE consists of a simultaneous
rupture of a molten-salt line or vessel and the presence of the proper
amount of water, presumable due to a rupture of one of the ccooling-water
lines or the thermal shield. In this case the pressure could rise to
110 psig if it were not for the vapor condensing system, which will limit
the rise to 39 psig. The maximum allowable leak rate from the reactor
and drain tank cells when they are pressurized to 39 psig is 1% of their
volume in 24 hours (180 ft3/day). This is checked at a positive pressure
(20 psig) after each time the reactor or drain tank cells have been Opened
for maintenance or inspection. Vapor condensing system is tested simul-
taneously, but separately, with reactor and drain tank cells. The cells
are operated at 12.7 psia, and the leak rate is continuously monitored
while the reactor is in operation.

Since any line in the cell could rupture during the maximum credible
accident, containment must be provided for each. These are checked peri-
odically as indicated in the Startup Check list, Section L4E.

1 REACTOR AND DRAIN TANK CELL

1.1 Startup

After all maintenance in the cells is finished, install

all lower blocks, weld the seal pans in place, check the seal
pans with the cells at 2 psig, and alternate top blocks in
place. Maximum spacing between blocks is 24 inches.

Since the air line block valves close at a cell pressure
of 2 psig, careful consideration should be given to the condi-.
tion of the reactor and drain tank system before starting the
cell pressurization. If there are no leaks in the air lines
to the air operated valves, they will not change position during
the period that the block valves are closed. Therefore, all

vent valves from, and equalizing valves between, the reactor
Approved by flxfififiz/t}fiicxaazn4 e
= g/ 8"16 "65

and drain tanks should be opened at the time the block wvalves

close. The drain tank and reactor systems should be vented to
atmospheric pressure before closing the block valves. Jumpers
in Circuits 33, 3&, and 35 will prevent the block valves from

closing.

As an added precaution against unintentional transferring
of salt, “the transfer and fill freeze valves should be frozen.
Since the component coolant pump will not be in operation, power
to the heaters on the freeze valves should be shut off, and the
power to the adjacent line heaters should be reduced.so that
the freeze valves remain frozen without coolant air.

When no pan leaks are visible at 2 psig, install all top
blocks and pressurize the cell to 20 psig, hold the cell temper-
ature constant, and check the leak rate by observing the cell
pressure. (For calculation of leak rate, see Section 3E.l1.Z.,
Part VIII, MSRE Operating Procedures). The space coolers should
be on at this time if possible.

If the leak rate is above the specified limit (see Table
3E-1 this section), all block and check valves and rupture disks
in the lines connecting the cell atmosphere will need to be tested.
It may be necegsary to retest the seal pans.

When the leak rate is satisfactory, reduce the pressure in
the cells to -2 psig, and again check the leak rate. The pressure
should not normally be reduced lower than —2;1/2 psig. An alarm
will occur at -3 psig, and the block valve (HCV-565) will close.
At -4 psig the component coolant pump will automatically be shut
off. (The space coolers and component coolant pump should be in
operation).

If this leak rate is satisfactory, the pressure will be main-
tained at -2 psig, and the cell wili be purged with nitrogen until
the oxygen content is less than 5%.

The procedure outlined above tests only the contaimment of
penetrations directly into the cell atmosphere. It is also nec-

essary to test each line which connects with the reactor or drain-
’ Approved byfififififiez/ ‘Ut e o , 3E-3
~ 8-16-65

tank system and extends outside of contaimment. Also since

during an accident any of the service lines entering the re-

actor or the drain tank cell could be ruptured, it is nec-

essary to provide contaimment for these lines and to periodi-

cally check the adequacy of each of these. The general method
: of containment is described below. Details of the methods

used for checking the containment are given in Section LE.

TABLE 3E-1
ALLOWABLE LEAK RATE
at .
VARIOUS PRESSURES AND TEMPERATURES

Cell Pressure Cell Temperature Allowable Leak Rate
(Ft3/Day)
Psig (Psia) Op °r STP* At Cell Pressure
and Temperature
39 53.7 285 THS o L3L 180
20 34,7 70 530 222 101
) > 19.7 70 530 5245 Lh.6
) -2 12.7 70 530 22 27. 4
-2 12.7 150 610 22 31.6

*The allowable leak rate at standard condition of temperature and
pressure is assumed to be directly proportional to the pressure differ-

ential. Standard T & P are 32°F and 1L4.7 psia.

All cover gas lines which enter the system contain a mini-
mum of one soft-seated check valve to prevent backflow. Also,

v the supply header pressure is maintained higher than could con-
ceilvably be developed in the system. These are tested by gas

pressurization.
Approved by /figflf%«wflm 3E-L
| </ 8-16-65

All the off-gas lines are blocked by a common block valve
which is closed on high activity in the line upstream of the
absolute filters in the ventilation system. In addition, those
lines which normally contain fission gases are jacketed (double
pipe) upstream of the charcoal beds. This is tested by gas
pressurization.

The cell evacuation line contains a radiation block wvalve
prior to the absolute filters. This is tested by gas pressuri-
zation (see Section 4E, Part VIII, MSRE Operating Procedures).

All cooling water lines which enter the cell have soft-
seated check valves to prevent backflow. The cooling water
lines which leave the cell contain radiation block valves.

Taps are provided to enable pressurization of the in-cell
equipment to test the check valves and block wvalves.

The surge tank also contains a block valve on the vent and
a spring closed valve on the chemical gddition line. These are
tested by alr pressurization.

The oil systems are closed systems. They are checked leak-
tight periocdically by pressurizing the entire systems, and ad-
ministrative control is used to assure that no changes are made
during operation which might violate containment.

The steam condensing system for the drain tank coolers is
a closed system except for the water supply lines which contain
soft-seated check valves and the vent line which goes to the
vapor condensing system. These check valves are tested during
testing of the vapor condensing system.

The coolant salt system is a closed system. Auxiliary
lines connected to this system have similar contaimment to the
fuel system. These are tested in place by gas pressurization
wherever possible; otherwise, they are removed from the system
and bench tested.

The cell sump jet supply lines contain-soft-seated check
valves, and the discharge lines contain two valves in series
which close on high cell pressure. The check valves are tested

when the cell is at pressure. A test line is provided for
Approved by wfi’@/\/cf;//ufl .
-16-65

testing the block valves.

All lines to the fuel sampler contain soft-segted check
vaives, and the supply header pressure is maintained higher
than the pressure which could be developed in the sampler.
These are tested by gas pressurization.

The leak detector system is a closed system which is oper-
ated at a higher pressure than could conceivably be developed
in the reactor. Administrative control is used to assure safe
operation and maintenance.

The helium supply lines to the fuel pump, fuel overflow
tank and fuel and flush salt drain tanks are provided with
secondary containment to a point upstream of the check valves
in these lines. The containment enclosures are connected to
the RC or DIC but sealed off from them. These are leak tested
by gas pressurization.

All instrument air lines and valve operator vent lines
contain block valves which close on high cell pressure. These
are tested by gas pressurization.

When the containment of all the penetrations is known to
be satisfactory, the cell leak rate is below permissible limits,
and the O, content of the RC and DIC atmosphere is less than 5%,
the RC and DIC are ready for operstion.

1.2 Normal Operation

- The reactor and drain tank cell will be operated at -2 psig.
This is accomplished by throttling V 569A. The evacuation rate
is measured by FyI 569 downstream of V 569A. A nitrogen purge
will be maintained at a rate such that the oxygen content of
the cell does not exceed 5%, as indicated by sampling cell air
or use of a continuous Os analyzer. The purge nitrogen enters
the cells at the sumps and provides the gas for the bubbler
level indicator. A probe type level alarm is also installed

r in each sump. These are tied into a common annunciator. Water
cannot be tolerated in either cell and should be jetted immedi-
ately. Continued buildup of water will necessitate shutting
down and repairing the leak. The procedure for sampling and

jetting the sump is given in Section 3J.
Approved by fl. Zd/% / Mgy

The cell leakage should not exceed 1% of the cell volume
in 24 hr at 39 psig and 285°F. The rate of inleakage to the

3E-6
8-16-65

cell can be calculated from (l) the change in cell pressure

and temperature or (2) the change in oxygen content. Several

temperature-compensating-reference-volume tanks are located in

the cells which when used as references for differential-

pressure-measuring instruments eliminate the need for adjusting

indicated-cell-pressure changes due t0 temperature changes.

The leak rate formulas are as follows:

Fl and Fo

T, and T

Tare

1

i

0o analyzer readings at beginning and
end of test (fraction of O, in contain-
ment atmosphere).

Nitrogen purge rate (SCFH).

Leak rate (standard cu ft per day).
Absolute pressure in containment at the
beginning and end of the test (psia).
Change in pressure during the test (in
of H0).

Time duration of test (hrs).

Average cell temperature at beginning and
end of test (°R).

Average cell temperature during test

(T + T2) (°R).
a

Volume of containment (£t3) (18000 cuft).
Gas evacuated at FqI 569 (SCF).

A - When pressure testing the cell, there will be no evacuation and

.l . no nitrogen purge.

(1) The leak-rate out of the cell in standard cu ft per day

based on pressure and temperature measurements would be:
Approved by _j?pfizQfié?zmnq : : 3E-7
V4 8-16-65

_14.5x%108 B, P»
IR=""% (7 )

(2) When the temperature-compensating drum is used and the
time is short, the leak-rate out of the cell in standard cu ft

per day based on the differential-pressure instrument would be:

5
- 5.25 X lO (AP )

Lr t Tare

B - When the cell is less than atmospheric pressure, there may be a

qI 569.

(1) The leak-rate into the cell in standard cu ft per day based

nitrogen purge and/or evacuation at F

on pressure and temperature measurements would be:

_ 14,5 x 10 P, P, 2LW
Ly = < (Tg - /Tl) + < - 2N

. (2) When the temperature compensating volume is used and the
time is short, the leak-rate into the cell is standard cu ft

per day based on the differential pressure instrument would be:

_ 5.25 x 105 AP 2UW

Lr t Tare Tt ° 2h

(3) If the leak rate is constant and the evacuation rate at
FqI 569 is constant, then the lesk-rate into the cell in standard
cu ft/day based on oxygen analysis readings would be:
Approved by;fifiéé%ZpQ§Z;/finfinq 3E-8
V

1.3

8-16-65

538 3~ (Fo - F1) + 12 WFy
Ly = — % (.2 - Fo)

(4) If there is no evacuation at Fol 569, the leak-rate into
the cell in standard cu ft/day based on oxygen analysis readings
would be:

538 £+ (F2 - F1)
Ly = =
R t (02 - Fa)

During operation the average temperature of the cells is
maintained at lBOOFJ or less by controlling the water flow to
the three space coolers.

The cell air activity and oxygen concentration is monitored
in the component coolant system, line 565, and therefore the
pump must be in operation at all times.

Fmergency or Special Operation

Cell air activity will stop the cell evacuation by closing
HCV-565, and will give an emergency fuel drain. A rupture of
in-cell piping or the loss of cooling water to the space coolers
will cause the cell pressure to rise. When the pressure reaches
16.7 psia, all block valves will close. No automatic blocking
action occurs on the valves in the cell ventilation lines, _
HCV-930A, HCV-930B, V-955A, or V-955B, and therefore these are
tagged closed at the start of each run. It is highly important
that they never be opened during operation.

If the pressure rises to 15 psig, the 3" rd ruptures and at
~ 20 psig the 12" rupture disc to the vapor condensing system
will break, relieving the cell pressure.

Residual air activity in the cells can be purged through

the auxiliary charcoal beds by opening V-571A and V-571B.
—_y
Approved by:,fléfigg%g/gépffl¢¢w1 3E-9

. 1.4

8-16-65

Shutdown

Shutdown of the reaétor and drain tank cells consists essen-
tially of shutting off the cell evacuation valves and venting
the system to atmospheric pressure. This is best done by opening
HV-955A and B, which bypass the 30 inch motor-operated valves
(HCV-930A and B) in the cell ventilation line. When the cell
has been vented, the motor-operated valves can be opened to pro-

vide ventilation for maintenance operations.

. 2. VAPOR-CONDENSING SYSTEM

2.1

2.2

Startup

Putting the vapor-condensing system in condition for opera-
tion consists of filling VI 1 two-thirds full of corrosion-
inhibited water, checking that the rupture disk bypass valve,
V-980Q, the vent valve, V-98kL, are tagged "closed'.

Normal Operation

The wvapor-condensing system should require lLititle or no
attention during operation. Should the water level in VI 1
drop below the lower intermediate probe, it should be replen-
ished.. Approval of the operations chief should be obtained
before filling. If the level continues to drop, it will be
necessary to shut down the reactor and determine the source of
leaks. (See Section 3E.2.4 Part VIII, MSRE Operating Procedures).
If the system pressure rises above 15 psia as indicated by PIA
VI 2, the system should be vented to the stack through HV-98L.
This valve should not be opened without the shift supervisor's
permission and should be closed and tagged after venting.

Emergency and Special Operations

If the pressure in the reactor cell has increased to 15
psig, the 3" rupture disc will break, and at 20 psig the 12"
rupture disc will break. Vapors from the reactor and drain
tank cells will be discharged into VI 1, where the gases will
be scrubbed and any steam condensed; the noncondensables will
be retained in VI 2 and the vapor space of VI 1. The activity

in the viecinity of the vapor condensing system may be as high
2.4

3E-10
8-16-65
as 100 rads/hr at this time.

As the reactor cell cools, its pressure will decrease, and
the gases will be pulled back into the cell through CV's 980A
and 980B. Any remaining pressure in VT-2 can be vented to the
stack through V-984. However, any gas pressure remaining in
VT-2 will be disposed of after the situation has been carefully
reviewed. ©Special instructions will be issued at the time
covering any other operations.

Shutdown Operation

A periodic leak test of this system will be performed and
the leak-rate shall not exceed 1% of the volume in 24 hours
at 39 psig and 140°F. The leak test when performed will be
performed simultaneously with the RC and DIC leak test but as
a separate test.

For this operation V-980 shall be opened when pressurizing
the RC and DIC and then closed for the leak tests. The detailed
steps for the leak test are given in Section UE, Part VIII,

MSRE Operating Procedures. The allowable leak rate 1is given
in Table 3E-2.

Ieak rate formuias are as follows:

Ip = Leak rate (scfd)
Py & P> = Absolute pressures at beginning and end of
test (psia).
T, & To = Absclute temperatures at beginning and end of

test (°R).
t = Time duration of test (hrs)

_ 3.T20 s (B1 _ Pz
Ip = =%~ x 10° {E — 3
Approved by,//%ét?{%/ AN

3E-11
8-16-65
TABIE 3E-2
VCS ALIOWABIE LEAK RATE
VARTOUS TEMPERATURES AND PRESSURES
X System Allowable Leak Rate
Pressure Temperature At System
Psig Psia °F °R STP#* Temperature & Pressure
39 53.7 140 600 139 L6
20 34,7 70 530 71 32
P 19.7 T0 530 18 17
-2 12.7 70 530 T 6.7

* The allowable leak rate at standard condition of temperature and

pressure is assumed to be directly proportional to the pressure

different

jal.

Standard T & P are 32°F and 14.7 psia.
Approved b

eet) g 3E-12
8-16-65

3 COOIANT CELL AND COOIANT DRAIN TANK CELL

3.1

Startup

3.2

Preparation for operation consists of installing blccks
on the top of the penthouse; closing the doors between the
coolant drain tank cell and the west tunnel, between the
coolant drain tank cell and the blower house and between the
coolant cell and the blower house (These doors should be
locked and signs should be installed to prevent entry by
personnel during operation.); putting the two coolant cell
space coolers in operation; and providing adequate ventilation
as described in 3F.

Normal Operation

3.3

In normal operation the radiation level in these areas
will be too high for personnel entry. The cell temperature
should be maintained at 150°F, or less, with the space coolers.

Water leaking into the cell will flow by gravity to the
sump pump pit and will be automatically pumped to the catch
basin.

Emergency or Special Operation

A leak of salt from the coolant or coolant drain tank
systems into the cell would probably be detected by losses
in coolant salt inventory. Air samples taken from the ventila-
tion duct may show an increase in beryllium concentration.
In case of a rupture of a salt line, it would be possible if
water were present to develop a slight pressure and release
some beryllium to the high bay, blower house, west tunnel or
special equipment room. However, since these areas are vented
to the containment stack, the amount of atmospheric contami-
nation would be small. In case of an accident of this nature,
gas masks should be worn until the conditions have been

adequately analyzed.
Approved by'5$§7 GV VPN 3E-13
| < ' 8-16-65

3.4  Shutdown

After the reactor has been shut down for 15 minutes, access

to the area is possible before the coolant salt is drained.
Adequste health physics and beryllium surveys sould be made
before entry.

SPECIAL EQUIPMENT ROOM

The special equipment room may be entered from the coolant
drain tank cell or by removing blocks from above. During ocperation
at power the radiation level is too high for continued occupancy;
however, by entering through the top, short term operations or main-
tenance jobs can be done. A health physics survey ié necessary be-
fore entry.

WEST TUNNEL AND SOUTH ELECTRICAL SERVICE AREA

These areas are not accessible during operation of the reactor,
but they may be entered when the reactor is drained. Positive per-
sonnel barriers and warning signs must be provided before startup.
A health physics survey is necessary before entry after shutdown.

CHARCOAL BED PIT

The shielding blocks on the charcoal bed pit should not be re-
moved without administrative approval. Air leakage into this pit
is vented to the ventilation stack. An inleakage will be limited
by caulking around the blocks.

FILTER PIT

The ventilation system filters are installed in a pit south of
the building. Top shielding is provided by means of concrete blocks,
which are caulked to prevent air or rain leaking in.

Entry should be necessary only for maintenance and should be
done with administrative approval.

AUXILIARY CELLS

The liguid waste cell, remote-maintenance practice cell, fuel
storage cell, decontamination cell, equipment storage cell, and a
spare cell are located below the 852 ft level in the high-bay area
north of the drain tank cell.

The activity levels in these cells are independent of the re-
actor operation. Entry should be made only after a health physics

survey.
SF-1
Approved by ’%@W\ 7/21/65

3F VENTILATION SYSTEM

The ventilation system provides ventilation to all areas where
radioactive contamination or beryllium dust is likely to occur. The
relative pressures are maintained so that the flow of air is from the
less hazardous to the more hazardous areas. Dampers are provided in the
discharge ducts from each area to enable balancing the flow for the
specific operation in progress. Ailr flows from the ducts to a header
which feeds three filter banks connected in parallel. Suction to the
filter banks is provided by either of two parallel 19,000-cfm stack
fans which discharge to a 100-ft high containment stack.

1 STARTUP
1.1 Stack Fans and Filters
1.1.1 Open all inlet and outlet dampers to the three filter

banks .

1.1.2 Start stack fan No. 1 by pushing the start button in
the control room.

1.1.3 Push the start button for the No. 2 stack fan. (The
No. 2 stack fan will start automatically on high pres-
sure at the suction of the filters.)

1.1.4 Check that the discharge damper from stack fan No. 1 is
open and from No. 2 is closed.

1.2 Ventilation Distribution

1.2.1 Open the damper in the duct that supplies air to the
high bay from the inlet air filter house.
o 1.2.2 Check that the supply air filters are in good condition.
| 1.2.3 OStart steam to the coils in the supply air if heating
is required.
1.2.4 Adjust dampers to the various areas to minimize possible
spread of contamination and start waste blower. (See
Normal Operation and Special Operations.)
2 NORMAT, OPERATTION

Normal operation of the ventilation is considered to be when the

reactor and drain tank cells are closed and the reactor is in operation.
| | | N 3F-2
Approved by,.«flA%//Mm | 7/21/65

2.1

Stack Fans and Filters

2,2

Stack fan No. 1 will normally be in service with No. 2 in standby
ready for automatic stértupo._NOTE: Stack fan No, 1 will not start
automatically. All three filters should be operated in parallel,
Periodic checks should be made of the stack flow, suction pressure,
filter pressure drop, and stack:rédiation monitor. Any abnormal
vibration or noise should be investigated.

Ventilation Distribution

The reactor and drain cellé will be sealed and held at a negative
pressure (=12.7 psia) using the component coolant pumps. The two‘
block valves in the 30-in. reactor cell ventilation line will be
closed. The coolant cell, coolant drain tank cell, spécial equip-
ment room, south electric service area, fuel processing cell, and
liquid waste cell will normally be closed énd caulked. The de-
contamination cell, equipment storage cell, and spare cell may be
open or closed depending upon conditions in that cell. The high-
bay supply air damper should be open and doors to the high-bay
closed. HCV 935A in the discharge ffom the high-bay area should
be open. The high-bay area will be maintained at a negative pres-
sure of -0,1 to-0.3 in. of water. The dampers in the exhaust lines
frbm the coolant cell, coolant drain tank cell, special equipment
room, fuel processing cell, and liquid waste cell will be open'to
maintain these at a lower pressure than the high bay. The waste
blower should be in operation. The dampers to the decontamination
cell, equipment storage cell; and spare cell will be adjusted to as-
sure a flow of air from the high bay into these cells if they con-
tain potentially hazardoué material., Normally the dampers in the
exhaust ducts from the transmitter room and north electric service
area éhould be closed and the dampers in the duct from the south
electric service area should be open, This will cause the air to
flow from the 840-ft level to the transmitter room, then to the
north electric service area, then to the south electric service
area and subsequently to the stack. The dampers in the ducts

from the service tunnel and vent house will be adjusted to keep
Approved by :;%?fgpt)g%;/ngmp\_ 3F-3

2.3

7/21/65

them at a lower pressure than atmospheric. There are no dampers

or valves in the ventilation lines from the off-gas containment

boxes or charcoal beds.

Periodic checks should be made of the relative pressures
and air flows. Due to possible cave-in of the high bay, the
vacuum should not exceed —0.3 in. of water.

Other areas and equipment are ventilated by separate ventilating

fans in the respective locations. They are as follows:

2.3.1 The "Sump Room" is ventilated by means of an exhaust
blower. The on-off switch is located at the entrance to
the sump on the 852 level. The blower should run con-
tinuously and should be checked on before entering sump
roonm.

2.3.2 An exhaust fan mounted in the west wall of the MG #1
and #4 room provides ventilation for the motor generator
sets. This fan should run at all times. The off-on
switch is located at the fan.

2.3.3 The induction regulators of the salt piping heaters
are ventilated by blowers which are to run continuously
during operations. Groups of four or six induction
regulators are each ventilated by a blower in conjunction
with a small duct system. The on-off switches for these
blowers are located at the respective blowers. There is
a total of nine (9) blowers located in the induction
regulator area just north of the "Heater Control Panel”
on the 840 level.

2.3.4 The battery room is ventilated by an exhaust blower in
the east wall. Continuous ventilation in this room is
mandatory because of the evolution of hydrogen from the
batteries. The on-off switch for this blower is located
in Panel H switch #18 on the north wall of the 840 level.

2.3.5 The remote maintenance area is ventilated by a small

exhaust blower in the west wall of the room. This blower
3F-L4
Approved bm s 7/21/65

should be operated when needed. The on-off switch is
located at the blower.

2.3.6 The main disconnect panel in the motor control center
is ventilated by means of an exhaust fan. The fan is
located in the south wall of the motor control center
room with the off-on switch located in the southwest
corner of the room. This fan should be maintained running

at all times.

3 OPERATION DURING MAINTENANCE

The flow of air should continue to be from the less hazardous to

the more hazardous areas as described in 2.1 and 2.2 of this section.

Many different damper settings may be required, depending upon the

operating conditions. When increasing the air flow from one area,

caution should be used not to decrease it below tolerance in another

area .

3.1

Several anticipated conditions are described below.

Maintenance in the Reactor and/or Drain Tank Cells

Before opening either cell a check should be made of the cell

air activity, Monitor RE-565. During maintenance, both valves

in the cell exhaust line 930 will be open, and the velocity
through any opening will be maintained at no less than 100 ft/min.
When the openings into the cell are large, the high bay exhaust
valve HCV-935A will be closed. With smaller openings, it will

be necessary to open HCV-935A to provide necessary ventilation

in the high bay and maintain the high-bay pressure at —0.1 to
—0.3 in. of water.

Maintenance in the Coolant or Coolant Drain Tank Cells

Direct maintenance is possible in equipment located in these
cells. A check of the radioactivity should be made by the
health physicist, and a check of beryllium contamination should
be made by the industrial hygienist before entering the cell.
The dampers in line 933 and 934 should be opened to provide

maximum ventilation.
3F-5
Approved by MW 7/21/65

3.3 Maintenance in Auxiliary Cells, South Electric Service Area,

and Special Equipment Room

Normally the dampers or valves in the exhaust lines from these
areas will be fully opened before opening the area for entrance.
A check must be made and approval given by the Health Physics

group before anyone enters these areas.

b SPECTAL OPERATIONS

L.l Failure of Stack Fans

h.2

Should fan No. 1 stop due to mechanical or electrical fallure,
fan No. 2 controls are designed to start it automatically.

The discharge damper from stack fan No. 1 will close and the
damper from stack fan No. 2 will open. Should this fail or
should No. 2 stack fan fail while running and before No. 1
has been repaired, all personnel will be evacuvated from the
high-bay area and other limited access areas until proper
ventilation is restored. The areas should be kept closed as
much as possible when the ventilation is lost. If both blowers
stop, the waste blower will also stop and will have to be
restarted after either fan is in operation.

Replacement of Exhaust Filters

4.3

Whenever the stack filter pressure drop exceeds L in. of water,
the filters will be replaced one bank at a time while the fan
continues to operate. The auxiliary cells and other limited
access areas will be closed with their shield blocks and doors
to assure sufficient exhaust from the high-bay area while re-
placing the filters. The inlet and outlet dampers of the bank
to be replaced will be closed. The filter will be replaced
with filters which have already been subjected to the Laboratory
standard DOP smoke test, and the DOP smoke test will be re-
peated on the installation. See paragraph L.L.

Ixcess Stack Activity

If the stack instrumentation indicates excess stack activity,
the source of which is not indicated by other radiation de-

tectors, a survey of each branch of the duct work and piping
3F-6
Approved by,{‘é iz_’%/m 7/21/65

L. L

leading to the fans will be made with portable instruments to
locate the source. Gas masks should be worn. Inlets to all
areas should be closed to reduce the release of activity out
of the stack.

Test of the Filters by the DOP Smoke Test

The filters will be tested to determine their efficiency for
removing particulate matter by the ORNL standard DOP smoke

test (see ORNL 3442, "Tests of High Efficiency Filters and
Filter Installations at ORNL"). The test will be performed

by the Inspection Engineering Department on replacement filters
before they are installed in the system and the installation
will be observed by Inspection Engineering personnel. The
complete filter bank will be tested after each filter change
and annually if the filters were not replaced during the pre-
ceding twelve months. They will also be tested at any time

the efficiency of the filters is suspected to be less than
99.95%. The test on the system will be conducted with a flow
of ~20,000 cfm with only one fan operating and the dampers to
all filters open. This test will be performed by the Inspection
Engineering Department and they will determine the amount of
dioctyl phthalate required for the test. The smoke will be
introduced into the system at the high-bay area exhaust duct.
Samples will be taken from the sample ports in the three filter
inlet ducts and the three filter outlet ducts. A photometer
analysis will be performed on each filter bank and should

indicate a filtering efficiency of =99.95%.

5 SHUTDOWN

Depending on conditions at the time of shutdown, it may be necessary

to close and caulk some of the auxiliary cells. After this is

complete, the waste blower in the remote maintenance cell will be

stopped and the stack fans stopped.
- Approved by, o7 ] 3G-1
7/26/65

- 3G LEAK-DETECTOR SYSTEM

This systefi is a pressurized helium system consisting of eight valve
manifolds or headers supplied from a common helium pressure~-reducing station.
Each header has from 4 up to 10 leak detector lines which serve in-cell
flanges. Each leak detector line monitors from one to . four pairs of ring-
joint flanges.

A reference tank and sensitive DP cell are connected through appropriate
valves to the eight headers so that small leaks from any one header can be
- measured.

Flange leakage can be tolerated at a rate of 6 cc/min for all inter-
- connected flanges (all headers connected). This is equivalent to a 0.66 psi
per hour pressure drop (see Sect., 11,3 of the Design Report, Part I),
All data calculations and leak rates should be recorded in the leak-

detector log.

1  STARTUP
As each leak-detector flange or group of flanges are tightened, the

leak-detector line monitoring that flange, or group of flanges, should
be purged of air and put into service by the following procedure:
Note: Leak detector line 420 serves two flanges in line 516 and it is
used as an example (numbers in parenthesis),

l.l Purging O, From Leak-Detector Headers

‘ Headers containing oxygen should be purged as outlined below
before being put into normal service.
l1.1.1 Before opening the supply valves to the leak-detector lines,
- open the helium supply valves and the valve to the header
to be purged.
1.1.2 Pressurize the header to 100 psi and close the valve upstream
of 0, contaminated section (V 514C or header supply valve),
l.1.3 Vent the header into the containment cell by opening a spare
leak-detector line valve (L 430 on header 403 is a spare until
the thermal shield water piping is cut and flanged).
l.1.4 After venting, close the valve in the spare leak-detector

line,
Approved by.%/ ’ 6“‘,‘7%&1«_, 3G=2

1.2

lolos

l.1.6

1.1.7

7/26/65

To complete the purge, repeat the pressurizing and venting
three times,

Then pressurize the header and, leaving the header supply
valve open, open all leak-deteétor line valves except spares.
Open the supply valve to all other leak-detector headers,

restoring them to normal service.

1.3

Purge Leak-Detector Lines as follows:

l.2.1

l.2.2

1.2,3

l.2.4

1.2.5

1,2,6

1.2.7

Make up all flanges served by the leak-detector, but do not
tighten bolts. (On leak-detector line 420, this is two
flanges in line 516,)

Close all "A" leak-detector valves on the header (420A
through 4294).,

Isolate all other headers from the pressurizing line (close
V 401A and 403A through 408A),

Pressurize header being tested to 100 psig, then close header
supply valve, (PI 402 reads 100 psig--V 514C, 514D open,

and V 402A closed).

Open or check open the "B" (maintenance valve) to the flanges
being made up (V 420B),

Slowly open the "A'" valve to the flanges being made up until
the header pressure drops 1 to 5 psi per min. This is equiv-
alent to a purge of 100 to 55 cc/min,

Open header supply valve to purge line while all flanges are
tightened (open V 402A while two flanges in line 516 are
tightened).

Leak Check Flanges as Follows:

1.3.1

1.3.2

1.3.3

1.3.4

Close all "A" leak-detector valves on the header except for
line to be checked. (Close V 421A through V 429A, and open
V 420A)

Isolate all other headerslfrom the leak test DP cell (Close
V 401B and 403B through 408B).

Set valves to connect header to DP cell, and open equaliz-

ing valve (V 400) at DP cell. (Open V 402B)

Pressurize header (Open V 402A)
Approved byggggzzéégé%%ZhMfiww 3G-3

7/26/65
- 1.3.5 When header pressure is at 100 psig and steady, isolate
’ header (Close V-402A).
1.3.6 Put DP cell in service by closing equalizing valve (V-400).
.7 Unless gross leakage is indicated, record PAI 400 at

Lo

10-min intervals until leak rate is established. Record
at least three 10 to 15 minute checks without equalizing.
Acceptable leak rate is 107> cc/sec. which is approximately
equivalent to a change in PAI 400 of 7% in 10 min.
1.3.8 If leak rate is not satisfactory, open the DP cell
- equalizing valve (V-400) and re-pressurize header (Open
V-4024).
- 1.3.9 After retorquing flange, test as per 1.3.4 through 1.3.8.
1.3.10 If leak rate is satisfactory, open DP equalizing valve,
V-400, and all "A" leak-detector valves on the header ex-
cept spares. (Open V-L20A and L422A through 429A and close
V-L4214).
1.3.11 Isolate header from DP cell (Close V-402B).
1.3.12 Repressurize header to 100 psig and put in normal opera-
tion. (Open V-402A until PI-402 indicates 100 psig.)
1.3.13 Close supply valve and tie all headers together. (Close
. V-514D and open V-LO1lA through L4O8A.)
2 NORMAL, OPERATION
- During normal operation the DP equalizing valve (V-400) is open.
All headers are isolated from the DP cell (V-LO1B through LO8B closed).
All headers are tied together (V-LOlA through 4O8A open). A1l "A"

and "B" leak-detector-line valves 410 through 489 (except spares)
are open. The pressure drop of PIA 514 is an indication of the leak
rate of the total leak-detector system. PIA 51k annunciates at 90
and 110 psig.

When low annunciation occurs, the system pressure (PIA 51L)
should be recorded in the leak detector log and the leak rate calcu-
lated. If leak rate is normal (<0.66 psi/hr pressure drop) repres-

i surize system (V—SlhD) and record time and pressure.
If calculated pressure drop is greater than 0.66 psi/hr, de-

termine the location of leak as described in Section 3.
Approved by AN  3G-4

7/26/65

3 LOCATION OF LEAKING FLANGES

3.1
3,2

3.3
3.4
3.5
3,6

Pressurize all headers to 100 psig.
Open DP equalizing valve and open V 40l1B to
connect header 40l to the DP cell.
Close all header supply valves (V 401A through 408A).
Close V 400 to put DP cell in service on header 401,
Record all header pressures, |
Determine which header is leaking, based on decrease in header

pressures or from DP cell measurements. (DP instrument can be

- switched from one header to another.)

3.7

3.8

3.9

3,10

When leaking header has been located, put other headers in normal
service,

Close off half of the valves on the leaking header, and using DP
cell determine which half the leaking flange is on.

Determine leaking flange by checking each individual line on the
leaking half of the header.

Determine leak rate on the leaking flange using the DP cell.

The corrective action which will be taken when a leaking flange
is located will be an administrative decision, depending on the
rate of leakage, and the system into which the leakage occurs,
Until a decision is made, open all valves on the header and keep

pressurized above 50 psig,

4. SHUTDOWN PROCEDURES

qol

Reactor Shutdown

During a reactor shutdown the leak-detector system will remain in
operation as described in Section 2,

Leak~-Detector Header Shutdown

A header may need to be shut down to repair an item connecting
directly to the header, that is, a damaged valve, leaking fitting,
etc. To shut down and vent a header, proceed as follows:
4,2,1 With the system at pressure and the header supply valves
open, close all valves to the header except the valve needing

repairs.,
e y :
Approved p;ZZjfi;;zz;é;//azn\ 3G-5
| . 14 - T/26/65

4,2.2 Close the header supply valve if this will isolate the
secfion to be maintained from the helium supply. If a
header supply valve needs repairing, close all other header
supply valves ("A'" wvalves) and open the "B" valves to L 400
for all headers except the one to be repaired.

4,2,3 Close V 514B and C,

Note: If repairs are being made during reactor operation,
they should be completed before L 400 pressure drops to the
90 psi alarm point.

4.2.,4 Vent the header to be repaired by opening a spare leak-

- detector line into the contained cells, When the header
pressure reaches zero, close the spare leak-detector line
valve.,

4.,2,5 After repairs have been completed, flush the section con-
taminated by oxygen by procedure given in 1.1'& 1l.2.0f this

4,3 Shutdown of One Leak-Detector Line section.

To shut down one leak-detector line, close valve supplying that line,
The leak-detector line will vent as the flanges being monitored are
opened. Note: The maintenance personnel should be informed that
there is pressure on the flange being disconnected. When the flange
joint is reconnected, the lines should be purged and leak checked

per 1.1 and 1.2 of this Section.
Approved byifi€§;7é<fléfifif¢y 3H-1
| V 10/4/65

3H INSTRUMENTATION

Many instruments at the MSRE are the same or similar to those used
in other plants and loops. The operation of these is common knowledge
of operating personnel and is not described here. This section describes

the operation of the more complicated or less commonly used instruments.
'l‘

» _‘,/:; o :
Approved by _ ) /‘)/*%‘f://f"fi] 3H1-1

8/k/65

3H INSTRUMENTATTION

1 CONTROLLERS AND INDICATORS

There are a number of different types of recorder/indicator con-

trollers at the MSRE. The maintenance and adjustment of these is the
responsibility of the instrument department. Changing of control action
settings will not normally be done by the operations personnel. If it is
necessary to make changes these should be noted in the console log and
punch listed for the instrument department to check.

The following is a brief description of the primary functions,
means of adjustment and method of setting the variables. The Foxboro
Company Consotrol Stabilog and Hyper-Reset Type as used on the drain
tank recorders is used as an example.

1.l Types of Control Action

Automatic process control functions may be enumerated as follows:
1) On-0ff, 2) Proportional Band (throttling range), 3) Reset

Action, and 4) Derivative Action (rate action). One or more of

these functions may be combined in a single controller to produce a
desired control action, and this action (input to output) may be
reversed as required. Whether these functions are accomplished
manually or automatically will depend upon the frequency of the
process change and the speed and dexterity of the operator.

1.2 Reversal of Control Action

Item 1 of Fig. 2 indicates the desired controller output (V
port) for a given controller input (El port). As shown, for an
increase in element (signal transmitter) pressure there will be a
corresponding increase in controller output pressure. As an example,
this mode known as "direct" action, is desired in the case of the
pressurizer level control. As the level increases it is necessary
to increase the pressure applied to the "air to open' letdown valve
in order to reduce the sure applied to the "air to open' letdown
valve in order to reduce the level. Likewise, the opposite mode
(reverse action) is required to decrease the heater on-time when the

fuel pressure increases.
Approved byéizfiéigkaggrvhkflq 8?5}%2
p)

Before describing the control actions, it is necessary to
define an "errcr signal' as that change in relation between the
pen (Ttem 1, Fig. 1, Input Signal) and the setting index (Ttem 3,
Fig. 1).

1.3 ON-OFF

This action may be described as a 100% change in output for an

incremental error signal either positive or negative.

1.4 Proportional Band

Items 2 and 3, Fig. 2, show the proportional band scale and
adjustment 1ever; respectively. Proportional action may be defined
as the change in controller OUTPUT air pressure proportional to the
amplitude of the error signal within the 1limits of the measurement
scale range.

Figure 3 shows graphically the relation between the INPUT signal
and the OUTPUT pressure (valve position, Item 2, Fig. 1), assuming
that the setting index is at 50% scale range and the action of the
controller is "direct." The intersection of the curves at the output
scale midpoint is attributable to the fundamental design of the
proportioning mechanisms.

The 100% curve requires the pen to move over its entire range
to produce a 100% change in output pressure. The 0% curve indicates
that an infinitesimal error signal will produce a 100% change in
output, i.e., on-off control. A study of the 200% curve indicates
that the output pressure will not reach its minimum or maximum even
with a 100% change in pen position. Observe the indicated range of
the letdown valve. With a proportional band setting of >P00%, the
valve would never full close (or open) and with 50% the error signal
need be only 1.5 psi (12.5%) to full close (or open) the valve.

Figure L4 shows the same relationship with the set point at 25%
scale range. Note now, with a proportional band >100%, the valve
would never full close even with the maximum negative error signal of
3 psi (25%).

Figure T indicates schematically the floating disk action of the
controller proportional adjustment. An increasing back pressure on

the nozzle, by closing the air gap, is amplified in the relay for

1IN
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Approved bxfffi?‘#Wéfié%géxhflq ' 3H1-3
4 | 8/4/65

for final control element operation, and is also fed back to the pro-
portional bellows. A total air gap change of .0006" is sufficient

to produce the 3-15 psi change in output pressure. Assuming the con-
troller to be in equilibrium with 9 psi set and input pressures with

a 100% proportional band setting, the output and proportional

" bellows will be at 9 psi. The balance spring will be exerting a

force equivalent to the 9 psi in the P bellows. If a sudden
pressure increase in M occurs, the nozzle bleed will temporarily

be restricted and the output will increase to meet the demand.
However, the output pressure will increase along the 100% propor-
tional band curve because of the feed back to P which is opposing
the action of M about the fulcrum. A decreasing measurement signal
will likewise cause a decrease in output. Note that if the pro-
portional band setting were 0% any feed back to P would have a very
limited effect on the back pressure at the nozzle. The converse is
true if the band setting were 500%. Reversal of control action is
accomplished by interchanging the signals to the set and measure-
ment bellows.

The proportional band adjustment is made by moving the level
horizontally to the desired point on the scale which‘is graduated
from O to 500, indicating the proportional band width in percentage
range of the recorder scale, Item 4, Fig. 1.

1.5 Reset Action (+ Proportional Band)

Ttems 4 and 5 of Fig. 2 show the reset scale and adjustment
screw, respectively. Reset action may be described as a shift of
the proportional band position with regards to the original set
point and is a function of the elapsed time and amplitude of the
error signal. '

Figure 5 indicates graphically a specific action of the reset
control. Again using the let down valve as an example, assume that
the pfimping rate has siowly increased to such a value as to require
the valve to be some 92% open to maintain control and would thus

stabilize the measurement pen at 60% of scale when following the
Approved Tz 3H1-L4

8/4/65

original set point 50% proportional band curve. The addition of
the reset action produces the effect of shifting the proportional
band to such an extent that with the new requirement of valve
position, the measurement pen will remain in alignment with the set
point index. The opposite reset action will occur if the pumping
rate were to decrease. The reset action is not a result of the fact
that the valve requirement is now 92% open, but is a result of the
amplitude of the error signal produced by the pen movement and the
time required for this movement, which in turn produces the new
valve position. If reset action 1s present during startup, while
the measurement pen is at or near 0%, the proportional band will
be shifted until it rests entirely above the 50% set point, and
there will be no control action until the pen reaches set point.
Excessive reset will cause an overshoot of the pen in the opposite
direction. Reset action is considered a slow type action of control
and will have little or no effect on rapid process oscillations.

Figure 8 shows the addition of the reset bellows to the floating
disk mechanism along with the reset capacity tank and restrictor
valve arrangement. The feed point of the reset network is in
parallel with the proportional bellows but its action is in oppo-
sition. Assuming that there exists a pressure balance between the
four bellows, the action may be described as follows for a specific
measurement increase condition; an increase in M pressure will pro-
duce an increased output pressure which will follow the preset
proportional band range but will be shifted to an even greater
output by the RC time controlled increase in pressure in R. The
resulting action of a pressure rise in R will produce the same
proportional band shift as would a decrease of pressure in the set
point bellows S. In some controllers the reset action is not auto-
matic, but once a process is stable, the measurement may be brought
into alignment with the set point by a mechanical adjustment of
the balance spring, shown in Fig. T.

The reset action adjustment screw is rotated CW for maximum

control effect and CCW for minimum to the desired setting on the

[ 1Y
.-

Approved b@)@ ' . ?b,Hl/éB
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rotating scale which is graduated from .1 to 50, indicating the
reset time constant in minutes. With a setting of .1 minutes (re-
strictor valve full open), the reset bellows will essentially cancel
out the action of the proportional bellows, and the control will

be on-off.

1.6 Derivative Action (+ Proportional Band)

Ttems 6 and 7 of Fig. 2 show the derivative scale and adjustment
screw, respectively. Derivative action may be described as an
automatic proportional band range adjustment which temporarily
narrows the band and depends upon the rate of change of the error
signal. This action may also be considered as maintaining a linear
relationship between the first derivative of the error signal and
the output signal.

Figure 6 shows graphically a transient condition for a specific
derivative action. The 200% proportional band setting is chosen
to show more clearly the resulting action when considering the
letdown valve. If a positive error signal of 5% were to arise as
a result of an increase 1n measurement, the valve would only open
some 2% along the 200% curve with no derivative action. Introduction
of the derivative action produces a fast response narrowing of the
proportional band to some temporary range, which in this case will
open the valve wide (+ 12 psi output), thus attempting to restore
the process to normal by fast letdown before the error signal
becomes excesgive. The derivative control is sometimes called
"anticipatory control.” A loss of measurement signal will cause
a like narrowing of the proportional band in an attempt to close
the valve rapidly.

The above description concerns only "direct" derivative action
which ismost often used with a relatively long process lag, and which
allows the use of a wider proportional band for stability and still
retains the advantage of narrow band control for sudden process
upsets. ''Inverse" derivative has the opposite action in that it

automatically widens the throttling band in proportion to the rate
Approved by Wwff woy 3H1-6

8/k4/65

of change of the error signal. It is most often used in a short
time-constant process in allowing narrow proportional band action
for good control and wide band action for stability.

The derivative action adjustment screw is rotated CCW for maxi-
mum control effect and CW for minimum to the desired setting on the
rotating scale which is graduated from .1 to 50, indicating the
derivative time constant in minutes. A setting of 50 will introduce
such a long time lag into the proportional bellows that the control
action will be essentially on-off.

Note that the error signals do not achieve the magnitude as
depicted graphically in Figs. 5 and 6, but are limited immediately
by the reset action sensing the amplitude and elapsed time and de-
rivative action sensing the rate of change.

1.7 Foxboro Hyper-Reset Control Adjustment Procedure

1) Adjust the reset time to its maximum value and the deriva-
tive time to its minimum value.

2) Set the proportional band at some high value (+ 100%)
and then reduce it in successive steps, leaving the pointer at
each setting long enough to observe the resulting control. Continue
to reduce the proportional hand until cyeling is Jjust perceptible.

3) 1Increase the derivative time until this cycling is removed.
Narrow the proportional band slightly, and again increase the de-
rivative time until cycling is removed. Repeat until further in-
crease of derivative time fails to eliminate the cycling introduced
by the narrowing of the proportional band. Maintain this setting
of derivative time and widen the proportiocnal band until the cycling
is removed.

L) Set the reset time to the same value as the derivative time.

For controllers with reset only, follow steps (1) and (2) but -
leave the proportional band position in a stable and not a cycling
condition. Then reduce the reset time in steps, watching the error
signal decrease to zero. Too much reset will cause a cycling

action, and therefore should be set above this value.

e
EL ]

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Approved Ly.—57 i ey 3H1-7

Y 8/1/65

1.8 Frequency Response

Figure 10 shows graphically the theoretical frequency response
of a typical controller., Curve "A" indicates the gain vs frequency
of a proportional controller with a proportional band setting of
100%. The gain will be linear with frequency up to about 100 cycles/
min. Curve "B" indicates the theoretical response of a proportional
+ reset + derivative controller with a proportional band setting
of 50%, a reset time of .1 min and a derivative time of .0l min.

The actual curve "C'" follows the general slope of the reset and
derivative, but changes slope about the intersecting time-constant
points and follows the proportional band. The roll-off at high
frequencies is a function of the limiting mechanical components

of the controller.

Curve "A" of Fig. 11 shows the phase angle vs the frequency of
a proportional controller. As would be expected, the output lags
the input at the higher frequencies due to mechanical limitations.
Curve "B" is a typical theoretical phase shift curve with a reset
time of .1 min and a derivative time of .0l min. Curve '"C" is a
more likely actual phase shift picture in that the change of slope
is not as sharply defined. The change in slope at the higher
frequencies will finally achieve a 180° phase shift which will induce
a positive feedback oscillation in the controller.

The response and phase shift curves shown here are, of course,
for a controller only. In order to obtain a complete picture of
automatic process control action, it is necessary to have the ampli-
tude and phase characteristics of the process system, as well as

the established response of the controller.
244
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2 SCANNER

The scanner system, made up of five "scanners," provides alarm moni-

toring and readout for groups of thermocouples. The system consists of

rotating mercury switches through which combinations of thermocouples

are compared with a reference thermocouple and read out on an oscilloscope.

The block diagram, figure 3Hz-1 shows the various components of this sys-
tem and thelr relationship to each other. ‘

Since portions of the salt system must remain heated at all times,
the scanners will be in continuous operation except for necessary shut-
downs for repairs. Due to the many possible operating conditions of the
salt system, considerable flexibility was built into the scanners which
allow easy changing of inputs. Whenever a portion of the salt system
is cooled, the associated thermocouple signals should be removed from
the scanner so that the alarm feature will not be inactivated. It is
necessary that all points on all operating scanners be connected to a
thermocouple or millivolt signal. Noise from a disconnected point can
completely saturate the amplifier and make the channel inoperable and
can damage the amplifier. When changes of input are made, these should
be logged in both sections of the thermocouple log.showing swinglink
connections, multipoint connections, etc. (See details below.)

The spare to the reference thermocouple for scanners A, B, and C
should always be connected to a temperature recorder and point 100 on
each scanner should be jumpered at the scanner panel to the reference
thermocouple. The scanner gain should always be set as high as possible
to increase the readability of temperatures and narrow the range in which
an alarm will occur. After heatup the gain can usually be set at 100
which will give a reading of 5OOF per inch and will alarm at * 15OOF
from the reference.

The reference signal for scanner D and E will be from a potentio-
meter located at the scanner panel. During heatup this is varied by a
vernastat knob, and the equivalent temperature in °F can be read out
from the vernastat setting. During coolant salt circulation, the switch
should be in the position to give a constant 11.00°F input signal. The
gain should be set at 100 (50°F per inch).
Approved by %—‘ o 3I612é2
-26-65

An alarm should occur at 950°F and 1250°F.

Periodic calibrations should be made of each scanner to assure that
there has been no change in the gain or vertical size of the scope. This
is accomplished by plugging a known EMF signal into a point of the scan-
ner and comparing it with the reference as indicated by point 100. The
vertical multiplier on the scope and the fine gain on the differential
amplifier should be adjusted to alarm at £ 3 inches from the reference

line on any gain setting and indicate on the scope as follows:

Gain OF/inch

25 200
50 100
100 50
250 20

In order to increase the life of the mercury jet scanning switch,

a continuous purge of nitrogen should be maintained as indicated on the
building log.

There are only a few adjustments.of the scanners necessary for rou-
tine operations. These are: dc amplifier, course gain, oscilloscope
vertical and horizontal position, focus, brightness and point locator.

The thermocouple input to the scanner system is from 314 plug-ins
on pyrometer panels#l and#8, and 120 coolant cell thermocouples which
are permanently tied into the scanner system. The 314 pyrometer panel
plug-ins provide an input of 300 thermocouples, 9 duplicated thermocouples,
and 5 reference thermocouples. The following is a detailed description
of each component of the scamner (see figure 3HZ-1 and drawings D-HH-B-41658,
D-HH-B-41659, D-HH-B-41660, D-HH-B-41661, D-HH-B-41662, E-HH-B-41663,
E-HH-B-41664, E-HA-B-41665, E-HH-B-L1666).

2.1 909 thermocouples terminate with plug-in receptacles at "thermo-

couple jack panel#" located in the auxiliary control room on
the 852 level. Hand plug-in leads are used to continue all of

these thermocouples to the scanner system.

s
¥

Approved by % : 3;61223
-26-65

2ed

2.3

"Pyrometer panels ¥l and #2," also located on the 852 level
Just below the thermocouple jack panel, provide 300 scannef\
input receptacles, 100 each to scanners A, B, and C, to receive
hand plug-in leads from the "thermocouple jack panel." A ther-
mocouple log is necessary at the pyrometer panel.

"Thermocouple scanner panel #1" is located on the 840 level

Just southeast of column C-3. The thermocouple leads from the

pyrometer panel route to the "thermocouple scanner panel #1."

The following is the sequence circuit routing of the leads and

a description of the components within the "thermocouple scan-

ner panel #."

2.3.1 The 300 thermocouple leads enter the "scanner panel 4"
by connection to three terminal strips with "swing links."
See table 3Hz-1 for lead identification on the terminal
strips.

A terminal strip is a strip of insulation through which
two parallel rows of screw terminals have been mounted and
which will accommodate 103 leads. Swing links are metal
bars which permit circuit continuity between terminal strip
terminals. Normally the thermocouple leads connect to
one row of screw terminals and continue the circuilt by
the "swing links" across the terminal strip to the other
row of screw terminals. There are 300 leads leaving the
three terminal strips which provide circuitry to the remain-
der of the scanner system. The "swing links" can be rotated
90 degrees in order to couple the scanner terminals together,
thus paralleling two or more of the scanner leads on a given
terminal strip. A thermocouple log is necessary at the
terminal strip.

The "swing link" terminal strips are constructed as shown
on drawing E-HH-B-41663, "detail B." The swing link con-
ductor bars are held in place by the terminal nuts, tThus

requiring a tool to rearrange them.
TABLE 3HZ-1

| | Scanner Panel #1
| ) Scanner Panel #1 Scanner Panel #1  Scanner Panel #1 25 Iead Polarized
Pyrometer Panel Scanner Termimal Strip No. Terminal Strip No. Terminal Strip Connector Receptacle

Receptacle No. + Pole - Pole Terminal No. No.
421 through L45 A TSPI-F TSPI-F 1 through 25 J-A-1"
446 through 470 A TSPI-E ISPI-F 26 through 50 J-A-2
471 through 495 A TSPI-E TSPI-F 51 through T5 - CJ-A-3
496 through 520 A TSPI-E TSPI-F 76 through 100 J-A-4
521 through 545 B =TSPI—C TSPI-D 1 through 25 J-B-1
546 through 570 B ToPI-C ™SPI-D 26 through 50 J-B-2
571 through 595 B TSPI-C TSPT-B 51 through 75 F-B-3
596 through 620 . B TSPI-C TSPI-D 76 through 100 J~B-4

- 621 through 645 C TSPI-A TSPI-B 1 through 25 J-C+1
656 through 670 c TSPI-A TSPI-B 26 through 50 J-C-2
671 through 695  C TSPI-A TSPT-B 51 through 75 - F-C-3
696 through 720 C TSPI-A TSPI-B 76 through 100 J-c-b

59-9¢-9
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Approved by%§?§5326§a29@%454 3Hz-5
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8-26-65

2.3.2 The 300 scanner leads from the terminal strips are then
routed to twelve 50-point connector receptacles to form
group connectors accommodating 25 leads each.

The connector receptacles are the polarized multipoint
type, and are rectangular in shape. Two rows of 25 con-
nector points make up the two major sides of the rectangle
receptacle. The scanner leads are connected to the recept-
acle in sequential order with the plus pole on one side and
the minus pole on the other side. See table 3H2-1 for lead
identification to the 25 lead polarized receptacles.

2.3.3 The circuitry is then continued from the lead polarized
receptacles by means of polarized connector plug-ins to
another group of twelve 50-point connector receptacles as
listed in table 3Hz2-Z2.

2.3.4 Any of the connector plug-ins as listed in table 3H2-2,
"scanner panel #1 25 lead polarized connector plug-in” can
be inserted into the connector receptacles listed in table
3H2-1. It is important to maintain a record of the effects
of any changes made of these plug-ins in both sections of
the thermocouple log.

This second group of receptacles are identical in con-
struction to the ones described in 2.3.2 above, except all
50 points of each receptacle are connected to the same pole
of 50 scanner leads. This segregates the 300 scanner leads
into six 50-pcint receptacles of plus polarity and six 50-
point receptacles of minus polarity. See table 3HZ2-2 for
lead identification to the scarner lead segregated pole
receptacles.

2.3.5 The scanner leads continue by means of the 50-point con-
nector plug-ins to 3 rotating mercury switches of the scan-
ner system. A rotating mercury switch is a device for cyc-
lic switching of the signal from 100 thermocouples. A
mercury stream rotating at 1200 rpm serves as a brush to

perform the switching of each lead at a rate of 20 times
Approved byazé%fj%é%%?czuwv\ | 3H2-6
' 8-26-6

TABIE BH2-2
Scanner Panel #1 Scanner Panel #1 Scanner Panel #1
25 Lead Polarized 50 Pt. Segregated Pole 50 Pt. Segregated Pole
Connector Plug-in Connector Receptacles . Connector Receptacles
+ Pole — Pole
F-A-1 ~ J-A-8 J-A-10
P-A-2 J-A-8 J-A-10
P-A-3 J-A~9Q J-A-11
P-A-L J~-A-9 J-A-11
P-B-1 J-B-8 J-B-10
P-B-2 J-B-8 N J-B-10
P-B-3 J-B-9 J-B-11
P-B-k J-B-9 | J-B-11
P-C-1 J-c-8 J-C-10
P-Cc-2 J-Cc-8 - J-C-10
P-C-3 J-C-9 o J-C-11

P-C-4 | J-C-9 J-C-11

-~ -

Approved by - T Mzm 3H2-7
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2.4

8-26-65

2.3.5 (continued)
per second. Each rotating mercury switch has two separate
switch sections which are synchronized by the same motor
shaft. This provides switching for both the plus and minus
pole of the thermocouple lead. Both the plus and the minus
switch bank are each lead adapted by two 50-point connector
plug-ins of the rectangular type. §See table 3HZ2-3 for lead
identification to the mercury switch. The connector plug-
ins from the lower section of each rotating mercury switch
are Tor the negatlive pole and the plug-ins from the top
section are for the positive pole. All the connector plug-
ins of table 3HZ2-3 are identical so they can be plugged
into any of the receptacles of table 3HZ-3. It is imper-
ative that the plug-ins of table 3HZ2-3 be oriented such that
polarity and synchronization are not disrupted. This is
done by pairing the even or the odd numbered plug-ins of a
given mercury switch and then plugging into receptacles
listed in table 3HZ2-2 that have been grouped similarily.
It is further necessary to maintain pole continuity by
noting polarity listed in tables 3H2-2 and 3HZ2-3. Any even
or odd numbered pair of plug-ins may be plugged into any
even or odd numbered pair of connector receptacles as long
as the above mentioned paliring and polarity of each has
been complied with.

The mercury switch motors are energized by plugging into
the 120v AC outlets Al5, Bl5, Cl5, D15, E15, located next
to each mercury switch motor on "scanner panel #1." The
mercury switches are purged by nitrogen continuously to
prevent oxidation of the mercury.

The output leads of the mercury switches each route to a sepa-
rate signal bucking network located on scanner panel# 2. The
rotating mercury switch signal is bucked against a reference
thermocouple signal to give a difference signal output. The

difference signal output routes to individual "D.C. gmplifiers.”
Approved by ‘Efi:f’??/\/{‘f vl 3H2-8
74 8-26-65

TABLE 3H2-3

Scanner Panel #1 Scanner Panel #1 Scanner Panel #1

50 Pt. Connector Plug-In 50 Pt. Connector Plug-in Mercury Switch
— Pole ' + Pole
P-A-10 P-A-8 A )
P-A-11 P-A-9 A
P-B-10 P-B-8 B
P-B-11 P-B-9 B .
P-C-10 P-Cc-8 C
P-C-11 P-C-9 C -

FELY

Approved by',f’:ff’;?' ) )/ @4/ DL 3H2-9

8-26-65

The D.C. amplifier outputs each route to an "alarm discrimina-
tion" and also parallel to a selector switch called "selector
scanner."

The "alarm discriminators” and the "selector scanner! switch
are located on "scanner panel #2." "scanner panel 72" is lo-
cated next to "scanner panel #L."

The selected signal from the selector switch is routed to
an oscilloscope. The light beam across the face of the oscil-
loscope made up of 100 incremental steps displays the visual
readout of a scanner within the scanner system. The amplitudes
of the increments represent the temperatures based on a refer-
ence thermocouple. The following is a more detailed descrip-
tion of the "alarm discriminator," D.C. amplifier, and the
oscilloscope.

2.4.1 The "alarm discriminators" of "scanners A, B, C, D,

and E" are located on "scanner panel #2."

An "glarm discriminator" is an electronic device for
triggering an alarm if the temperature difference between

a reference thermocouple and a thermocouple exceeds a pre-

set limit. This limit is preset by adjusting the "amplifier

gain" knob of the "D.C. amplifier.” It should be noted
that false alarm will occur for a given scanner if there

is not full circuit input to the mercury rotating switch.

The alarm discriminators have individual scanner annun-
ciators located in "scamner panel #L" on the 840'level.

The annunciation is by individual light indicators and a

common alarm. An acknowledgement button is provided on

"scanner panel #2" to silence the alarm, but the light

indicator remains on until the out-of-limit temperature

is corrected.

A Scanner System annunciator is provided in the main
control panel on the 852'level. This provides a general
alarm and general light indication at the main control

panel on the 852' level for an out-of-limit thermocouple
Approved by/dfigfigézégéafif)vfipy\ 3H2-10
V4

8-26-65

2.4.1 (continued)
within the scanner system. This annunciator is also pro-
vided with an acknowledgement button to silence the alarm
which is located on the main control console on the 852
level.

2.4.2 The "D.C. amplifiers,"” located on 'scanner panel #2,"
amplify the difference signal from the "alarm discrimina-

t

tors.” The oscilloscope readout is calibrated by adjust-
ing the "amplier gain" knobs on the "differential D.C.
amplifiers" and the vertical multiplier on the oscilloscope
to give the beam amplitude corresponding to a Known ther-
mocouple input to the scanner system. Adjustment should

be as follows:

Oscilloscope Scanner
Gain Reading Alarm
(°F/in) (°F)
25 200 + 600
50 100 + 300
100 50 + 150
250 20 * 60

2.4.3 There are two oscilloscopes within the scanner system;
one on the 840'level at scanner panel #2, and the other is
on the 852'level in the main control panel. The oscillo~
scope on the 840 level is a console unit and plugs into the
two receptacles on "scanner panel.#z." The oscilloscope
on the 852' level is mounted in the main control panel.
Both oscilloscopes are provided with a "thermocouple iden-
tification marker." This is controlled from the 8LO' level
and can be used on the 852' level oscilloscope only when
both oscilloscopes are set on the same scanner position.

The six (6) control knobs located on the front of the
oscilloscope to control the display of the light beam are

as follows:
e iy
Approved by-”?fgguia/\/fl;/Vfizm) 3Hz2-11
DZ 8-26-65

2.4.3.1 '"Vertical adjustment'--used to move display up or
down for centering reference line.

2.4.3.2 Horizontal adjustment--used to move display to
either side for centering.

2.4.3.3 Focus adjustment--used to adjust the display to
maximum sharpness.

2.4k.3.4 Intensity--used to vary the light intensity of
the display. This should be maintained at a good low
intensity to minimize burning the cathod ray tube
phosphorescent coating.

. 2.4.3.5 Thermocouple identification marker--the "thermo-

couple identification marker" serves to identify the

incremental section of light beam on the oscilloscope

corresponding to each of the programmed input thermo-

couples. The marker is a dot of light that appears

just in the increment in question. The position of

the marker dot is identified and controlled by a heli-

pot selector switch called "thermocouple identifica-

tion marker." The switch indicates the positions

. from 1 to 100, position 1 is the extreme left incre-

ment on the face of the oscilloscope and position 100

- is the extreme right increment on the face of the
oscilloscope.

2.4k.3.6 Light beam amplitude control--normally this con-
trol is set to read a full scale amplitude with an
input signal of £ 1 volt. This contrel is used when
it is desired to change the calibration of the scope
without changing the alarm calibration. (Refer to
alarm discriminator for alarm calibration, section

2.4.2).

2.5 Reference thermocouples are thermocouples that have a known
) readout and are introduced into the scanner system to provide
a datum temperature. Thermocouples are then readout by com-

parison with a reference thermocouple.

FILN
8-26-65

Approved by 45553i22/w?cafi/n4;wq 3H2-12
> V4

2.6

Each scanner has an input receptacle for a reference ther-
mocouple..at the "pyrometer panel." The circuitry of the ref-
erence thermocouple lead routes from the pyrometer panel to
a terminal strip in "scanner panel #." Then the reference
thermocouple lead continues to the signal hucking network where
the signal is bucked against the analytical thermocouples sig-
nal as previously described.

The reference thermocouple input can be simulated with an
external electronic source and coupled into the scanner system
at the pyrometer panel.

Table 3H2-4 details the routing of the reference thermo-
couple leads within the scanner system.

The scanner system has designed within circiutry that permits
single input thermocouple signal to be read out on 25 consecu-
tive increments of the oscilloscope display. This permits a
more accurate examination of an individual thermocouple. Again
it should be noted that false alarm will occur if the 100 points
of a given scanner are not activated. Signal input can be
either four (4) 25 duplicated thermocouple inputs or 100 single
thermocouple inputs, or any combination thereof.

There are nine duplicated thermocouple input receptacles
on the pyrometer panel as listed in table 3H2-5; 3 each to
scanners #, B, and C.

The thermocouples to be read out on the duplicated scanner
are introduced at the pyrometer panel by jumper leads from the
"patch panel" as previously described. The leads from the
pyrometer panel then proceed to the terminal strips with swing
links in "scanner panel #1."

The swing links permit the paralleling of duplicated leads
at the terminal strips.

The leads then continue from the terminal strips of "scan-
ner panel #1" to the nine 25-point connector receptacle of
"scanner panel #1." Each lead connects to all 25 points of a

connector receptacle.
an

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Approved by yffiZZ/iérhtfn 3H2-13 -
14 8~26-65
Table 3H2-4
REFERENCE THERMOCOUPLES
Scanner Scanner
Panel #2 Panel #2
Pyrometer Scanner Terminal Terminal
Strip Strip Alarm
Panel Panel 7#2 Terminal Terminal
Terminal . N
Receptacle Strip No. No. Discriminator
No. No. + Pole ~ Pole
56 TSP2-C 1 2 A
o7 TSP2-C 3 4 B
58 T8P2-C 5 6 C
59 TSP2-C T 8 D
60 TsP2-C 9 10 E

TABLE “3H2-5
DUPLICATED THERMOCOUPLES

Scanner Panel #1

£q poarocaddy

L 4

Pyrometer Panel Norme.l Scanner Panel #1 Scanner Panel #1  Scanner Panel #1 Duplicate
Duplicate Scanner Terminal Strip Terminal Strip Terminal Strip Thermocouple N
Thermocouple Designation No. No. With Swing ILengths 25 Point Polarized
Receptacle No. No. + Pole =~ Pole Terminal No. Connector
Receptacle No.
172 A TSPI-E TSPI-F 101 J-A-5
173 A TSPI-E TSPI-F 102 J-A-6 §
174 A TSPI-E TSPI-F 103 J-A-T
175 B TSPI-C TSPI-D 101 J=-B-5
176 B TSPI-C TSPI-D 102 J-B-6
177 B TSPI-C TSPI-D 103 J-B-7
178 C TSPI-A TSPI-B 101 -J=C-5
179 C TSPI-A TSPI-B 102 J-c-6
180 C TSPI-A TSPI-B 103 J-C-T7

G9-92-8
HT- CHE
FEs

Approved by %%‘7"% | 3H2-15
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2.7

8-26-65

The connector receptacles are identical to the others pre-
viously described so any scanner connector plug-in can be cou-
pled into them. Table 3Hz-5 details the circuitry of the dupli-
cated thermocouple facility.

The radiator temperature control is of crucial importance so
scanners D and E are semi-permanently connected to 120 radiator
thermocouples.

The thermocouple circuitry of scanners D and E is similar
to that of scanners A, B, and C except that the 120 thermocou-
ples couple directly into the terminal strips on "scanner panel
#1" of scanner D and E.

Scanners D and E each readout 60 thermocouples, the first
4O of which are duplicated to activate all 100 points of the
scanner.

The thermocouple leads route from their origin within the
radiator section of the project to two terminal strips in "scan-
ner panel #1." A parallel lead for each thermocouple also
routes to the "patch panel" to provide duplicate readout. The
terminal strips are equipped with swing link conductors so
that one thermocouple lead can be paralleled into more than
one scanner readout circuit within a given terminal strip.

When swing lengths are used, sections of the thermocouple log
should be corrected to indicate this.

The leads continue within the "scanner panel #1" from the
terminal strip in sequence to eight 50-point pole segregated
connector receptacles which are the same rectangular type that
was explained in Section 2.3.2. The leads are pole segregated
into four 50-point plus pole and four 50-point negative pole
receptacles. Table 3H2-6 details routing of the radiator
thermocouple'leads within the scanner system.

Scanner mercury switches D and E "located on scanner panel
#1" are plugged in at this point and are identical as described
in Section 2.3.5. Again it is emphasized that the mercury

switch connector plug-ins be paired by even or odd numbers and
TABLE 3H2-6

Scanner Panel #1 Scanner Panel #1 Scanner Panel #1 sy
Thermocouple Scanner Terminal Strip No. Terminal Strip 50 Pt. Connector H
Nos. No. + Pole — Pole Terminal No. + Pole —Pole . 9
§)]
CR- 1 D TSPI-G TSPI-H 1& 61 JD1 & JD2 JD4 & JDS z
CR- 3 D TSPI-G TSPI-H 2 & 62 JDL & JD2 JDh & JD5 3
CR- 5 D TSPI-G TSPI-H 3 & 63 JD1 & JD2 JD4 & JD5
CR- T D TSPI-G TSPI-H b & 64 - JDL & JD2 JDk & JD5 B I
CR- 9 D TSPI-G TSPI-H 5& 65 . JDL & JD2. JDh & JD5 N
CR- 11 D TSPI-G TSPI-H 68& 66 JDL & JD2 JD4 & JD5 Q N
CR- 13 D TSPI-G TSPI-H T & 67 JD1 & JD2 JD4 & JD5 '
CR- 15 D TSPI-G TSPI-H 8 & 68 JDL & JD2 JD4 & JD5 §
CR- 17 D TSPI-G TSPI-H 9 & 69 JD1 & JD2  JDh & JDS
CR- 19 D TSPI-G TSPI-H 10 & TO JDl & JD2 JD4 & JD5
CR- 21 D TSPI-G TSPI-H 11 & 71 JD1 & JD2  JD4 & JD5
CR- 23 D TSPI-G TSPI-H 12 & 72 JD1 & JD2 JD 4 & JD5
CR- 25 D TSPI-G TSPT-H 13 & 73 JD1 & JD2 JD4 & JDS
CR- 27 D TSPI-G TSPI-H 1k & T4 JD1l & JD2 JD4 & JD5
CR- 29 D TSPI-G TSPI-H 15 & 75 JD1l & JD2 JD4 & JD5
CR- 31: D TSPI-G TSPI-H 16 & 76 JD1 & JD2 JD4 & JDS
CR- 33 D TSPI-G TSPI-H 17T & 77 JD1 & JD2 JD4 & .JDS
CR- 35 D TSPI-G TSPI-H 18 & 78 JDL & JD2 JD4 & JD5
CR- 37 D TSPI-G TSPI-H 19 & 79 JDL & JD2 JD4 & JDS
CR-39 D TSPI-G TSPI-H 20 & 80 JD1 & JD2 JD4 & JD5
CR- 4l D TSPI-G TSPI-H 21 & 81 JDl & JD2 JD4 & JD5
CR- 43 D TSPI-G TSPI-H 22 & 82 JD1 & JD2 JDh & JD5
CR- L5 D TSPI-G TSPI-H 23 & 83 JD1. & JD2 JD3 & JDk
CR- LT D TSPI-G TSPI-H oL & 84 JDl & JD2 JD3 & JDk |
CR- 49 D - TSPI-G TSPI-H 25 & 85 JDL & JD2 JD3 & JD4 P
CR- 51 D | TSPI-G TSPI-H 26 & 86 JDL & JD2 JD3 & JDk4 R
CR- 53 D TSPI-G TSPI-H o7 & 87 JDL & JD2  JD3 & JD4 é\g\
CR- 55 D TSPI-G TSPI-H 28 & 88 JDl & JD2 JD3 & JD4 e
CR- 57 D TSPI-G TSPI-H 29 & 89 JD1 & JD2 JD3 & JDL

L

TABLE 3H2-6.. (Continued) -

Scanner Panel #1

Scanner Panel #1

Scanner Panel #1

Thermocouple Scanner Terminal Strip No. Terminal Strip 50 Pt. Connector
Nos. No. + Pole - Pole Terminal No. + Pole —Pole
CR- 59 D TSPI-G TSPI-H 30 & 90 JD1 & JD2 JD3 & JDL
CR- 61 D TSPI-G TSPI-H 31 & 91 JDL & JD2 JD3 & JDh4
CR- 63 . D. TSPI-G TSPI-H 32 & 92 JD1 & JD2 JD3 & JDh
CR- 65 D TSPI-G TSPI-H 33 & 93 JD1 & JD2 JD3 & JDh
CR- 67 D TSPI-G TSPI-H 34 & 94 JD1 & JD2 JD3 & JD4
CR- 69 D TSPI-G TSPI-H 35 & 95 JDL & JD2 JD3 & JD4
CR- 71 D TSPT-G TSPI-H 36 & 96 JD1 & JD2 JD3 & JDh4
CR- T3 D TSPI-G TSPI-H 37 & 97 JD1 & JD2 JD3 & JDh
CR- T5 D TSPI-G TSPI-H 38 & 98 JD1 & JD2 JD3 & JD4
CR- 77 D TSPI-G TSPI-H 39 & 99 JD1 & JD2 JD3 & JDh
CR- T9 D TSPI-G . TSPI-H 40 & 100 JD1 & JD2 JD3 & JDk
CR- 81 D TSPI-G TSPI-H b1 J-D-1 J-D-3
CR- 83 D TSPI-G TSPI-H Lo J-D-1 J-D-3
CR- 85 D TSPI-G TSPI-H 43 J-D-1 J-D-3
CR- 87 D-- TSPI-G TSPI-H LY J-D-1 J-D-3
CR- 89 D TSPT-G TSPI-H L5 J-D-1 J-D-3
CR- 91 D TSPI-G TSPI-H L6 J-D-1 J-D-3
CR- 93 D TSPI-G TSPI-H L7 J-D-1 J-D-3
CR- 95 D TSPI-G TSPI-H 48 J-D-1 J-D-3
CR- 97 D TSPI-G TSPI-H 49 J-D-1 J-D-3
CR- 99 D TSPT-G TSPI-H 50 J-D-1 J-D-3
CR-101 D TSPI-G TSPI-H 51 J-D-2 J-D-U
CR-103 D TSPI-G TSPI-H 52 J-D-2 J-D-4
CR-105 D TSPT-G TSPI-H 53 J-D-2 - J-D-4
CR-107 D TSPI-G TSPI-H 54 J-D-2 J-D-k
CR-109 D TSPI-G TSPI-H 55 J-D-2 J-D-4
CR-111 D TSPT-G TSPI-H 56 J-D-2 " J-D-k
CR-113 D TSPI-G TSPI-H 57 J-D-2 J-D-h
CR-115 D TSPI-G TSPI-H 58 J-D-2 " J-D-L
CR-11T7 D TSPI-G TSPI-H 59 J-D-2 J-D-4
CR-119 D TSPI-G TSPI-H 60 J-D-2 J-D-4

éqéfifi’”fiq psaocaddy

527 e

Wit
WI’Z//My\-

¢9-92-3
)T~ "ZHE
TABEEf3fiéIE (Continued)

Scanner Panel #1 Scanner Panel #1 Scanner Panel #1
Thermocouple Scanner Terminal Strip No. Terminal Strip 50 Pt. Connector
Nos. No. + Pole — Pole Terminal No. + Pole —Pole
CR- 2 E TSPI-J TSPI-K 1 & 61 JE1 & JE2'. JE3 & JE4
CR- L E TSPI-J TSPI-K 2 & 62 JE1 & JE2 JE3 & JE4
CR- 6 E TSPI-J TSPI-K 3 & 63 JE1 & JE2 JE3 & JE4
CR- 8 E TSPI-J TSPI-K 4 & 6k JE1 & JE2 JE3 & JEL
CR- 10 E TSPI-J TSPI-K 5 & 65 JE1 & JE2 JE3 & JEL
CR- 12 E TSPI-J TSPI-K 6 & 66 JE1 & JE2  JE3 & JEL
CR- 14 E TSPI-J TSPI-K T & 67 JE1 & JE2 JE3 & JEL
CR- 16 E ESPI-J TSPI-K 8 & 68 JE1 & JE2 JE3 & JE4
CR- 18 E TSPI-J TSPI-K 9 & 69 JE1 & JE2 JE3 & JE4
CR- 20 E TSPI-J TSPI-K 10 & T0 JE1 & JE2 JE3 & JEL
CR- 22 E TSPI-J TSPI-K 11 & 71 JE1 & JE2 JE3 & JEk4
CR- 24 E TSPI-J TSPI-K 12 & 72 JE1 & JE2 JE3 & JE4
CR- 26 E TSPI-J TSPI-K 13 & 73 JE1 & JE2 JE3 & JE4
CR- 28 E TSPI-J TSPI-X 1k & 7h JEL & JE2 JE3 & JEb
CR- 30 E TSPI-J TSPI-K 15 & 75 JE1 & JE2 JE3 & JE4
CR- 32 E TSPI-J TSPT-K 16 & 76 JE1 & JE2 JE3 & JEk
CR- 34 E TSPI-J TSPI-K 17 & 77 " JE1 & JE2 JE3 & JE4
CR- 36 E TSPI-J TSPI-K 18 & 78 JE1L & JE2 JE3 & JE4
CR- 38 E TSPT-J TSPT-K 19 & 79 JEl & JE2 JE3 & JEL
CR- Lo E TSPI-J TSPI-K 20 & 80 JE1 & JE2 JE3 & JE4.
CR- kL2 E TSPI-J TSPI-K 21 & 81 JE1 & JE2 JE3 & JE4
CR- L4 - E TSPI-J TSPI~-K 22 & 82 JE1 & JE2 JE3 & JEk4 w
CR- L6 E TSPI-J TSPI-K 23 & 83 JE1 & JE2 JE3 & JEL PE
CR- 48 E TSPI-J TSPI-K - 2k & 84 JEl & JE2 JE3 & JEb R,
CR- 50 E TSPI-J TSPI-K 25 & 85 JE1 & JE2  JE3 & JEk oG
CR- 52 E TSPT-J TSPI-K 26 & 86 JE1 & JE2 JE3 & JEb4 b
CR- 54 E TSPI-J TSPI-K 27 & 87 JE1 & JE2 JE3 & JE4
CR- 56 E TSPI-J TSPI-K 28 & 88 JEL & JE2 JE3 & JE4
CR- 58 E TSPI-J TSPI-K 29 & 89 JE1 & JE2 JE3 & JEkL
CR- 60 E TSPI-J TSPI-K 30 & 90 JE1 & JE2 ~JE3 & JE4

TABLE. 3H2-6. (Continued)

Scanner Panel #1

Scanner Panel #1

Scanner Panel #1

Thermocouple Scanner Terminal Strip No. Terminal Strip 50 Pt. Connector
Nos. No. + Pole — Pole Terminal No. + Pole -~ Pole

CR-62 E TSPI-J TSPI-K 31 & 91 JEl & JE2 JE3 & JE4
CR-64 E TSPI-J TSPI-K 32 & 92 JE1 & JE2 JE3 & JE4
CR-66 E TSPI-J TSPI-K 33 & 93 JE1 & JE2 JE3 & JE4
CR-68 E TSPI-J TSPI-K 34 & ok JEL & JE2 JE3 & JEb
CR-T0 E TSPI-J TSPI-K 35 & 95 JEl & JE2 JE3 & JE4
CR-T72 E TSPI-J TSPI-K 36 & 96 JEL & JE2 JE3 & JEk
CR-Th E TSPT-J TSPI-K 37 & 97 JEL & JE2 JE3 & JE4
CR-T6 E TSPI-J TSPI-K 38 & 98 JE1 & JE2 JE3 & JEU
CR-78 E TSPI-J TSPI-K 39 & 99 JE1 & JE2 JE3 & JEL
CR-80 E TSPI-J TSPI-K 40 & 100 JE1l & JE2 JE3 & JEL
CR-82 E TSPI-J TSPI-K b1 J-E-1. "J-E-3
CR-84 E TSPI-J TSPI-K Lo J-E-1 J-E-3
CR-86 E TSPI-J TSPI-K 43 J-E-1 J-E-3
CR-88 E TSPI-J TSPI-K Ll J-E-1 J-E-3
CR-90 E TSPI-J TSPI-K L5 J-E-1 J-E-3
CR-92 E TSPI-J TSPI-K L6 J-E-1 J-E-3
CR-94 £ TSPI-J TSPI-K W1 J-E-1 J-E-3
CR-96 E TSPI-J TSPI-K 48 J-E-1 J-E-3
CR-98 E TSPI-J TSPI-K 49 J-E-1 J-E-3
CR-100 E TSPI-J TSPI-K 50 J-E-1 J-E-3
CR-102 E TSPI-J TSPI-K 51 J-E-2 J-E-14
CR-10k E TSPI-J TSPI-K 52 J-E-2 J-E-4
CR-106 E TSPT-J TSPI-K 53 J-E-2 J-E-4
CR-108 E TSPI-J TSPI-K S5k J-E-2 J-E-4
CR-110 E TSPI-J TSPI-K 55 J-E-2 J-E-4
CR-112 E TSPI-J TSPI-K 56 J-E-2 J-E-L
CR-11k4 E TSPI-J TSPI-K 57 J-E-2 J-E-4
CR-116 E TSPI-J TSPI-K 58 J-E-2 J-E-L
CR-118 E TSPI-J TSPI-K 59 J-E-2 J-E-4

E TSPI-J TSPI-K 60 J-E-2 J-E-4

CR-120

7 Rq paroaddy

’,t'/’
-
Ed

‘P‘;__.o

a’

\, / )
18 Fif L2ty St

$9-92-8
6T~ THE
_,‘i' 4 »
Approved'%y?fi;fi%;éVZé/florh = 3H2:20

e |74 8-26-65

plugged into receptacles that are paired similarly. It is also
imperative that polar continuity is maintained. Table 3HZ-T7

describes the connector plug-ins of mercury switches D and E.
=)
Approved by 37’%214¢y7ufl%\ 3H2 =27
Y 8-26-65

TABLE 3IH2-7

Connector - Conneetor Mercury

Plug-In Plug~-In Switeh
No. No. No
Negative Pole Plus Pole )
P-D-3 P-D-1 D
P-D-4 P-D-2 D
P-E-3. P-E-1 E
P-E-U4 P-E-2 E

Approved by -7 | P ; 3H3-1
o 4 | 8/30/65

3H INSTRUMENTATION

3. COMFUTER

The operation of the computer for collecting, recording, and pro-
cessing reactor data is largely automatic and will require 1ittler-
attention, However, there are a few functions that must be perfofmed
by the reactor operators on a routine basis to keep the computer system
operating properly under normal conditions. In addltion, special
operator actlons are required when computer failures occur.

° A large amount of published information is availlable which describes
the computer and its operation at all technical levels. The principal
documents and their general contents on these subjects are listed
below for reference.

1) MSRE Design and Operations Report, Part II, Nuclear and
Process Instrumentation, by J. R. Tallackson, ORNL-TM-729.
Thils document contains a description of the hardware and
the system capability, along with information concerning its
use on the MSRE.

2) MSRE Reactor Operators' Computer Manual, by C. D. Martin, et al.
This contains all the information normally required by reactor
operations personnel to make full use of the computer. Be-
cause of its bulk and specific applicability, this document

- 1s separated from the rest of the reactor operating manual.

Since the signal tabulations and other detailg within the
computer are subject to change, an up-to-date copy of this

" report 1s kept at the computer console,

3) MSRE Computer System Report, by C. D. Martin, et al, This
report 1s a complete description of the application of the
computer to the MSRE. It includes engilheering descriptions
of the calculatlons as well as computer flow charts and
progrem listings,

4)  BR-340 System Marnual, supplied by Bunker-Remo Corporation. This

L is a highly detailed description of the entire 340 computer
system. It is intended for use primarily by the computer

programmers and maintenance personnel,

-
Approved by,¢f; fx: P | 3H3-2

v . - 8/30/65

Sinee there is a separate opervating menual for the computer {Com-
puter Manusl, item 2 above), the purpose of this part of the reactor
operators! manual is to emphasize those functions that must be performed

routihely.

381

342

Tog Forms

The routine-logs typéwriter, Typer No. 2, uses & pre-
printed form which is completed each shift. The £irst infor-
mation 1s typed on this form 15 minutes after the start of a
shift and the laet informmiion appears about 15 mirutes before
the emd of the shift. A new form must be inserted in this
typer shortly after the staxt or shortly before the end of each
shift. Detailed ingtruetions for inserting and aligning the
Porms are glven in the Computer Mamal. |
Calendar Date

Although the computer containg an internal deviece for

generating elock time, there i1g no proviglon for ealeulating
the calendar date. BSilnce the computer makes freguent use of
the date in storing date, this information must be mpnuelly
entered each day shortly after midnight, Detailed instructions
for entering "Dnte" are givem in the Computer Mamual,

The calendsr date in the computer is typed automatiesally
as part of the routine logs on Typer No. 2. Tt is NOT typed
ankomatically by the other 3 typers. Therefore, the procedure
for typing the date on each of Typers Na, 1, 3, and 4 must
be executed nesr the beginning of each ghift. This procedure
15 detalled in the Computer Menual.

Magnetie Tape

During normal operation, the computer will store data
on ‘the m&gmetid tape on one of the two dpive units; the second
unit will be in standby with a full reel of blank tape. When
the first reel is filled, the computer will mutomatically
switeh to the standby unit and armounce the fect on Typer No. 1.
When this occurs, a reactor operator will rewind the completed
tape and replace it with enother reel of blank tape.
Approved

3.4

K 5533

8/30/65

Geeaslonally 1% will be éeairable to remove a tape before it
ig completely filled. On these oecasions; the operator will
manually switch to the sgtandby unit before rewinding and
removing the "in-use" reel. Detailed procedures for switch-
ing tape units and for rewinding and changing tape reels
are glven in the Camputer'Manualf‘ The handling and storage
of new and completed magnetic tapes is deseribed in 12D of
this manual,
Computer Failure

There sre two areas which will require special attention
in the event of & fallure of the computer. Thege are {1) the
continued operation of the reagtor system without dats from the

N
[

computer and {2} the restoration of computer operation.

When the computer is out of* serviee, 1t will be necessary
to colleet a large amount of data manually in order to main-
tain adequate survelllance of the reactor systems. The
changes in resctor operation for this condition are desceribed
in 6G of thils mehual,

Restouration of computer operation will usually require
the attention of & programmer (ORNL) and/or a computer
maintenence engineer (Bunker-Ramo). Once the computer is
again operational, the way in which it is put in service de-
pendg on the condition of the reactor system and the duration
of the outage. If no power change has occurred during the
owtage and the down time is less than 30 minutes, all the com-

puter functions will be reactivated. TIf the reactor was in

"steafly state with regard to xenon and samarium transients

prior to ‘the outage and no power changes occurred, all the com-
pfiter funetions will be reactivated even if the down time is
greater than 30 minutes, Tf a xenon or samarium transient

was in progress prior to an outage of morve than 30 minutes or

lif'a power change occurred, only part of the computer functions

will be activated. The notable exception in this case is the
Approved. 'b,'y‘/f%> b%g 2 1L | H3-4
| Vo 8/3 30/65

the reactivity balance which must be corrected for changes
during the outage. The details of restarting the computer
under various circumstances are described in the Computer

Manual.

3.5 Procedure.for Changes

One of the feétures which makes the computer so useful is
its flexibiiity, Changes can be made in the form of calcu-
lations, thé coné%ants which are used, the form of output, and
so on, to meet the changing needs of reactor operations and
analysis or to improve the performance of the computer.
Changes in such a complex system must be handled carefully,
however. It is imperative that proposed changes be reviewed
thoroughly before they are made and that changes be properly
documented when they are made. To this end the following
procedures will be adhered to.

Recommendations for changes will normally originate within
the MSRE Operations Department, in either the operations
group, the analysis group or the computer group. Any recom-
mended change will be described by the person originating it
on a Change Request Form. Changes originating in the opera-
tions group must be approved by the Operations Chief or Assistant
Operations Chief. The head of the nuclear.and mechanical
analysis group, J. R. Engel, will evaluate and screen recom-
mended changes and will coordinate computer changes and reactor
operation. All changes must be approved by Engel and by the
head of the MSRE Operations Department. The computer group
will advise on the amount of effort involved in proposed
changes afid will make those changes which have been approved.

Requests originating in the operations group will go first
to the Operations Chief (or Assistant Operations Chief). If
he considers the change desirable, he will forward the request
to Engel. Requests originating in the Analysis group will
go directly to Engel. After he has evaluated the usefulness

and desirability of any requested change from the standpoint
Approved by A7 iy se m 3H3-5
" 4 8/30/65
- of operations and analysis, Engel may return a request to the
originator with an explanation of why it should not be made.
Other requests he will pass on to the computer group for an
estimate of the effort required to maké the change. Recom-
mendations for changes may be originated in the computer
- group. These will generally be of such a nature as to make
more efficient use of the computer or to improve the accuracy
of a particular calculation. They will submit their recom-
mended changes with an estimate of the effort and improvement
to Engel. After receiving an estimaté from the computer
group, Engel will evaluate the utility and cost of the change.
If he decides the change is not worthwhile, he will file the
Change Request, the estimate of effort, and pertinent notes
and will notify the originator. If he approves the change,
it will go to the department head for approval. If he approves
the change, it will be sent to the computer group for action.
Upon receiving an approved Change Request, the computer
group will proceed as follows:
1. Program the recommended change if applicable. If the
change involves only altering a constant or similar word

> in the computer skip steps 2 and 3.

2. Assemble/compile the program on line and execute through

- On~Line Program Development.

3. Completely de-bug the program exercising all program
options and check for correct answers.

- L, Advise J. R. Engel when the change is ready for inclusion
in the system and inform him of the amount of time the
computer will have to be off line to incorporate the
change.

5. Engel will give the go-ahead to take the computer off
line to make the change or he will advise to wait until
the next scheduled reactor shut-down or computer routine

! maintenance shut-down to make the change.

6. Make the change when advised by Engel.
Approved bygfifigfl%gz;tffizzmx 3H3-6
4 8/30/65
T. Correct the master cop& of the Reactor Operator's Com-
puter Manual (on computer.console) to reflect the change.
8. Enter time, date, and nature of the change in the computer
log and the reactor log.
9. Enter the change in the master copy of the Computer
System Report and list on the running list of changes to
the computer system report for periodic publication.
10. Notify operations and the analysis group of the fact that

the change has been made in the system.

There are certain constants (thermocouple bias corrections)
which may vary from time to time requiring changes in the A
conversion-equation table code words to reflect the current
bias. Certain other constants of similar nature may also need
to be changed from time to time. Minor changes of this type
will be verbally referred to J. R. Engel (if not originated
by him) for approval to make the changes without following
the above procedure. The only documentation required is that
outlined in steps 7, 8, and 9 above.

If there 1s any doubt as to whether a change may be
made following the abbreviated procedure, J. R. Engel will

decide which procedure is to be used.
[ ]

Approved by s ;4¢Q3i70/99\ 3H4-1
~ 9/24/65

3HL ANNUNCIATORS

Visible and/or audible annunciators are provided to alert the
operator when any of the important parameters are out of the prescribed
limits.

In general, when a variable deviates from the normal value, an
alarm first occurs on the computer and its value is typed on the alarm
typewriter. If the variable deviates further from the normal, a con-
ventional alarm will occur which will be indicated by a light above the
main beoard and an audible signal. If the variable deviates still further,
control action will occur.

There are fifteen different types or combinations of annunciators
at the MSRE., These are outlined in Table 3 HA4-1 and Fig. 3H4-1 and
described in the following pages.
| Table 3IH4-2 is a list of each annunciator. The cause of the annun-
ciation is described, the automatic control actions which are initiated
by the condition causing the annunciation are enumerated and suggested
remedial actions to be taken by the operator are given. Table 3HL-3
gives similar information for the Electro-system Temperature switches
and alarms. It should be emphasized that the suggested operator action
does not always apply. Consideration should be given to the condition
of the system, what tests are in progress, and other pertinent information.

Table 3IHL-L describes the various audible alarms.

4.1 Type I - Annunciations coming Direct to the Control Room

These may contain one or more switches in series or parallel
which will actuate the system. During normal operation the
red and white lights above the main control board will be on
dim indicating that the bulbs are good. There will be no
audible alarm.,

When a sustained abnormal condition occurs there will be
an audible alarm in the main control room and the associated
red and white lights above the main board will be on bright.

Pushing the acknowledge button on the console will turn off
Approved by 2 /4Z%é§;7hw&\\ 3HL-2

h.2

4.3

9/2k/65

the white light and audible signal. The red light will remain
on. If the condition clears the red light will go off and the
white light will come on.. If the condition reoccurs the
lights will come on bright and there will be an audible signal.
If the reset button on the console is pushed before the con-
dition reoccurs, the white light will go off.

Type II - Annunciators coming direct to the Auxiliary Control

Boards with no Common Visual Alarm on the Main Control Board.

These may contain one or more switches in series or parallel
which will actuate the system. During normal operation the
white lights above the auxiliary control board will be off and
there will be no audible alarm.

When an abnormal condition occurs there will be an audible
alarm in the auxiliary control room. Both of the white lights
above the auxiliary control board will be flashing. Pushing
the acknowledge button on the auxiliary control board will turn
off the:'flasher and audible signals. Both white lights will
remain on if the abnormal condition is sustained. If the con-
dition clears both of the white lights will go off. If the con-
dition reoccurs the lights will flash and there will be an
audible signal.

The lamp test button will turn all lights on to periodi-
cally test that they are operable,

Type ITT Annunciators Coming Direct. to the Auxiliary Control

Board with a Common Visual Alarm on the Main Control Board.

These may contain one or more switches in series or parallel
which actuate the system on the sampler panel or on the auxiliary
control board. Any one of several alarms will annunciate on a
common annunciator in the main-control room. During normal
operation the white lights above the suxiliary-control board
will be off and the red and white lights above the main-control

will be on dim indicating that the bulbs are good. There will

r

be no audible alarm.
Approved byzfigéégzz%fi%g;Ofiwfit 3HL4-3

L.h

9/2k /65

When an abnormal condition occurs there will be an audible
alarm in the main control room and in the auxiliary control
room. The associated red and white lights above the main board
will be on bright and the associated white lights above the
auxiliary control board will be flashing. Pushing the acknow-
ledge button on the console will turn off the main-control
board white light and audible signal. The red light on the
main-control board and the audible alarm and flashing lights
on the auxiliary control board will remain on. Pushing the
acknowledge button at the auxiliary control board will turn off
the flasher and the audible signal but will leave both white
lights on at the auxiliary control room. The associated main-
control board lights will change from red to white. Pushing
the reset button on the console will cilear the main board.

If, at any time after the auxiliary control board acknow-
ledge button has been pushed, the condition clears and reoccurs
or another abnormal condition occurs the lights will flash
and there will be an audible signal in both the main control
room and the auxiliary control board. When the condition has
cleared, the white lights will be off above the auxiliary
control board.

Tvpe IV Annunciators Coming Direct to the Sampler, Scanner,

Vapor Condensing System, or Chemical Processing Panel with a

Common Visual Alarm on the Main Control Board.

These may contain one or more switches in series or paral-
lel which actuate the system on the sampler, scanner, vapor con-
densing system, or chemical processing panel. Any one of
several alarms will annunciate on a common annunciator in the
main control room. During normal operation the red and white
lights above the local panel, main control board will be on
dim indicating that the bulbs are good. There will be no audi-
ble alarm.

When an abnormal condition occurs there will be an audible

alarm in the main control room and at the local penel. The
?/ ER

, 'y
Approved by £ 7?-*1.;;9*/;.-/;”\ /31;:?
~ 9/214/65

associated red and white lights above the main board will be

on bright and the associated red and white lights above the
local panel will be on bright. Pushing the acknowledge button
on the console will turn off the main control board white light
and audible signal. The red light on the main control board
and the audible alarm and red and white lights on the local
panel will remain on. Pushing the acknowledge button at the
local panel will turn off the white light and the audible sig-
nal but will leave the red light on at the local panel. The
associated main control board lights will change from red to
white. Pushing the reset button on the console will clear the
main board.

If, at any time after the sampler, scanner, vapor condensing
system, or chemical processing board acknowledge button has
been pushed, the condition clears and reoccurs or another ab-
normal condition occurs the red and white lights will come
on and there will be an audible sighal in both the main control
room and at the local panel. After acknowledgment and when
the condition has cleared, pushing the reset button on the
local panel will clear the white light.

The vapor condensing panel differes from the others in
that it has a test button which, when pushed, will cause an
annunciation in the MCR.

4.5 Type V - VIT Annunciators Coming Through The Auxiliary Control

Room Temperature Modules

A number of temperature signals are connected to Electro
System temperature switches. These are used to initiate annunci-
ations or in some cases are in control circuits. The power sup-
ply switch should be on at all times as indicated by the amber
light at the upper left hand corner. The manuval-~auto switch at
the right hand side of the panel should be in the manual posi-
tion. Some power supply panels have red lights, the red light
will go on when an associated alarm module is actuated. All
power supplies have reset buttons. Some not needed for present

assignment of modules but would be needed if an alarm module
Approved by éffiigzqzéégééé;fiwyfiw\__ 3H4-5
Y

9/2k/65
(Type ET-L200) were added. There are several variations in the
way that this alarm system operates. These are described
below:

With the exception of TS FD-1-19B and TS FD-2-19B which
do not alarm, the operation of TX-3001L and TS-AD3-5B and AD3-TB
is as follows:

Type V

During normal operation the power supply amber light is on
and the red (alarm) light is off. The red lights on the modules
are on dim. When an abnormal condition occurs there will be
an audible alarm in the main control room and the associated
red and white lights above the main bhoard will be on bright.
The red light on the power supply and the red light on the
module will be on bright. Pushing the acknowledge button on
the console will turn off the white light and audible signal in
the main control room. The red light on the main control board
will remain on and the lights in the auxiliary control room will
not change. If another abnormal condition occurs, the associ-
ated module light will come on but there will be no audible or
visual alarm in the main control room. When the abnormal con-
dition clears, nothing will happen. Pushing the reset on the
power supply will turn off the red lights on the module and
switch from red to amber on the power supply. The red light
on the main board will go off and the white light will be on..
Pushing the reset on the console will clear the main board.
Type VI

With the exception of TS FD-1-20B and TS FD-2-20B which do
not alarm, the operation of TX-3002 1s as follows:

During normal operation the module red lights are on dim.
When an abnormal condition occurs there will be an audible
alarm in the main control room and auxiliary control room. The
associated red and white lights above the main control board
will be on bright and white lights above the auxiliary control
board will be flashing. The red light on the module will be

on. Pushing the acknowledge button on the console will turn off
Approved by 7 7% e‘td/ dduly 3HL-6
-V R 9/2k/65

the white light and audible signal in the main control room.
The red light on the main control board and the audible alarm
and flashing lights and module red lights in the auxiliary con-
trol room will remain on. Pushing the acknowledge button in
the auxiliary control room will turn off the flasher and audi-
ble signal but will leave the white light above the auxiliary
board and red module light on. The associated main control
board light will change from red to white. Pushing the reset
button on the console will clear the main board. If another
abnormal condition occurs on TX-3002 or if the condition clears
and reoccurs, or if an abnormal condition occurs on TX-3002
and an obnormal condition already exists (for that particular
FV) on TX-3003 through TX-3010, the associated module light
will come on but there will be no audible or visual alarm in
the main control room.

When the abnormal conditions clear nothing will happen.
Pushing the reset on the power supply after the abnormal con-
dition has cleared will turn off the red lights on the module
and turn off the white light above the auxiliary control board.
Type VIT

The remaining Klectro System temperature switches are as-
sociated with freeze valves. Kach temperature module has 2
lights. A Dbright amber light indicating that the temperature
is in alarm and a green light indicating that the temperature
is normal. Depending on the requested condition of the valve
(frozen or thawed) either light could be on under normal
conditions.

These temperature switch signals are included in an alarm
(and control) circuit and will alarm if the temperature is out-
side the limits set for the selected condition of the freeze
valve. Operation would be as follows:

During normal operation the main control board and auxiliary
control board lights would be off and there would be no audible
annunciation. When an abnormal condition occurs there will be

an audible alarm in the main controcl room and auxiliary control
'/‘ .
Approved bycjé%;¢55é5”fi¢9fi4n¢&&& SHL-T
Ve 9,/2L /65

’ room. The associated red and white lights above the main con-
trol board will be on bright and the white lights above the
auxiliary control board will be flashing. To determine the
switch module causing the alsrm it will be necessary to con-
sider all associated switches (i.e. all on FV-104) and the
requested condition of this particular freeze valve. Pushing
the acknowledge button on the console will turn off the white
light and audible signal in the main control room. The red
light on the main control board and the audible alarm and
flashing lights in the auxiliary control room will remain on.

Pushing the acknowledge button in the auxiliary control
room will turn off the flasher and audible signal but will
il leave both white lights above the auxiliary board on. The
module lights will not change. Pushing the reset button on
the console will clear the main board. If another abnormal
condition occurs on the same freeze valve there will be no
audible or visual alarm in the main control room. If the alarm
clears the module lights will change and the white light above
the auxiliary control board will go off. Another annunciation
will then give an audible and visual alarm in the main control
roomn.

An alarm on another freeze valve while the initial alarm
condition exists will alarm in the normal manner.

4.6 Type VIIT Annunciators Coming Through Rochester Alarm Substation

Modules
- A number of signals are connected to Rochester substations
modules in the auxiliary control room and have common annunci-
ators in the main control room. Operation of these are as
follows:

During normal operation, the module selector switch should
be in the operate position. The module light will be on. When
an abnormal condition occurs there will be an audible alarm 1in
the main control room and‘the associated red and white lights

, above the main board will be on bright. The light at the module
-

Py
Approved by./%gy';Ffi<:§;€%7flahn /3E?é8
= 9/2k /65

will go off. DPushing the acknowledge button on the console will

turn off the white light and audible signal in the main control
room. The red light on the main control board will remain on.
If another abnormal condition occurs there will be no visual

or audible alarm in the main control room. Switching the module
switch to "disable" will turn the module light on dim and will
change the lights above the main control board from red to
white. Pushing the reset button on the console will clear the
main board. Other Rochester units on the same common annunci-
ator can now cause an annunciation.

If the abnormal condition clears and the switch is on
"disable'" the module light will turn from dim to bright.
Switching the module switch to operate prepares the module to
cause an annunciation should another abnormal condition occur.

h.7 Type IX Annunciators Coming Through Personnel Radiation Monitors

to the Main Control Board

During normal operation the annunciator lights will be on
dim. There will be no audible alarms in the main control room
or at the personnel radiation alarm center in the auxiliary con-
trol room. When an abnormal condition occurs there will be an
audible alarm in the main control room and the associated red
and white lights above the main control board will be on bright.
There will be an audible alarm at the personnel monitor center
in the auxiliary control room and one of the three lights on
the personnel monitor module will be on bright. The three lights
indicate high level activity, intermediate level activity and
trouble with the instrument. Pushing the acknowledge button
on the console stops the control room audible alarm and turns
off the white light. Pushing the buzzer reset button will stop
the instrument audible alarm and change the associated main
control board lights from red to white. Pushing the reset
button on the console will clear the main board. If the con-
dition causing alarm clears and reoccurs nothing will happen.

If another condition occurs (another monitor) there will be an
3HL-9
9/2k /65

audible signal in the main control room and the associated red

and white lights above the main control board will be on
bright. One of the three lights on the associated personnel
monitor module will be on bright.

When the alarmed condition clears, nothing will happen.
Pushing the reset button at the personnel radiation module will
clear the bright lights on the module and reduce them to dim.

If 2 out of 6 monitrons or 2 out ot U CAM's alarm, the
group light on the personnel monitor panel will go on and the
plant evacuation sirer will be actuated.

4.8 Type X Annunciation coming from Process Monitor to the Auxiliary

Control Board and Subsequently to the Main Control Board.
(GM Tubes on Q-1916 Indicators)

During normal operation the power light on the unit and the

reset light on the reset panel will be on. When an abnormal
condition occurs there will be an audible signhal in the main
control room and auxiliary control room. The red and white
lights above the main control board will be on bright and the
white lights above the nuclear panel will be flashing. The
reset light will be off and the alarm light on the module will
be on. Pushing the acknowledge button on the console will

turn off the white light and audible signal in the main control
room. The red light will remain on.

Pushing the acknowledge button on the auxiliary control
board will turn off the flasher, and the audible signal at the
guxiliary control board. The associated main control board
lights will change from red to white. Pushing the reset button
on the console will clear the main board. If the abnormal con-
dition returns to normal and thenreoccurs the only indication
will be on the dial indicator on the process radiation panel.

If another @Q-1916 unit monitoring the same process point
exceeds the setpoint there will be nd alarm. Other monitors
will alarm in the main control room and the nuclear panel be-

cause they are connected to different nuclear panel alarm units.
7

T
g /

e 4 ‘r .
Approved by#-/ T\ en 3H4-10

4.9

9/2k /65

When the condition clears, the only indication will be on
the dial indicator on the process radiation panel. Pushing the
reset button on this panel will turn on the reset light, turn
off the alarm light on the instrument panel and turn off the
white light above the nuclear panel.

Type XI Annunciation coming from the Process Monitors to the

Auxiliary Control Board and Subsequently to the Main Control
Board. (Ton Chambers and 202 Electrometer.)

During normal operation the power light will be on. When
an abnormal condition occurs there will be an audible signal
in the main control room and auxiliary control room. The red
and white lights above the main control board will be on bright
and the white lights above the nuclear panel will be flashing.
Pushing the acknowledge button on the console will turn off the
white light and audible signal in the main control room. The
red light will remain on.

Pushing the acknowledge button in the auxiliary control
room will turn off the flasher, and the audible signal at the
auxiliary control board. The associated main control board
lights will change from red to white. Pushing the reset button
on the console will clear the main board. If the condition
clears and reoccurs nothing will happen.

If another electrometer unit monitoring the same location
exceeds the setpoint there will be no alarm. Other monitors
will alarm in the main control room and the nuclear panel be-
cause they are connected to different nuclear panel alarm units.

When the condition clears, nothing will heppen. Pushing the
reset button on the process radiation panel will turn off the

white light above the nuclear panel and release the pointer.

4.10 Type XITI Diesel Annunciators

There will be no annunciation indicating loss of TVA or
that the diesels are in operation.

When an abnormal condition occurs while operating a diesel,
there will be an audible alarm in the main control room and the

associated red and white lights above the main board will be on
.11

Lt o 2 ;Hh-ll
9/2k/65

bright. A light indicating which diesel has an abnormal con-

dition will be actuated on the diesel panels in the auxiliary
control room and an annunciator flag will be showing on the
diesel panels in the switch house. There will be an audible
alarm in the switch house. Pushing the acknowledge button on
the conscle will turn off the main control board white light
and audible signal. The red light on the main control board
will remain on.

Actuating the signal reset on the diesel panels in the
switch house will turn off the audible alarm in the switch
house and the light in the auxiliary control room. The light
above the main board will change from red to white. Pushing
the reset button on the console after the alarm has been acknow-
ledged at the diesel panel or after the abnormal condition has
cleared will clear the main board. If the condition clears and
reoccurs nothing will happen. If another abnormal condition
occurs there will be an audible signal in the main control room
and the lights above the main control board will be on bright.
The light on the diesel panel in the auxiliary control room
will be on. Another annunciator flag will be showing on the
diesel panel in the switch house and there will be an audible
alarm in the switch house.

When the condition has cleared, actuating the drop reset in
the switch house will reset the flags. If the condition has
not cleared, actuating the drop reset will initiate another
annunciation at all locations.

Type XITI Annunciation Coming from Computer to the Main Control
Board

During normal operation the main control board lights will

be on dim, indicating that the bulbs are intact and there will
be no audible annunciation. When an abnormal condition occurs
there will be an audible signal in the main control room and
the red and white lights above the main control board will be

on bright. The data point or condition which is out of limits
Approved by.~Zr”

L.1o

,fijijbf’zf' |
N © 3Hk-12
Vv 9/2L /65
will be typed out in red on the "out of limits" typewriter.
Pushing the acknowledge button on the console will turn off

-

s

the white light and audible signal in the main control room;

the red light will remain on. If the alarm condition clears

and realarms or if another point goes out of limits, each will
be annunciated on the main control board visually and audibly;
each out of limits condition will also be typed out in red on
Typewriter No. 1. If the alarm condition clears, the data

point or condition will be typed out in black on Typewriter No.l.
The red light above the main control board will go off and the
white light will come on. Pushing the reset button on the
console will clear the main board.

Type XIV Annunciation Coming from Nuclear Power Panel to the -

Auxiliary Control Board and Subsequently to the Main Control

Board (Wide-Range Counting Channel to Fast Trip Comparators).

During normal operation, the normal light (white or green)
will be on bright at the Fast Trip Comparators (Q 2609-1).
When an abnormal condition occurs, there will be an audible
alarm in the main control room and auxiliary control room.
The associated red and white 1lights above the main control
board will be on bright and the white lights above the auxiliary :
control board will be flashing. The normal light will go off
and the Trip and Latch lights will come on at the fast trip -
comparator module. Pushing the acknowledge button on the
console will turn off the white light and audible signal in the
main control room. The red light on the main control board and -
the audible alarm and flashing lights in the auxiliary control
room will remain on. Pushing the acknowledge button in the
auxiliary control room will turn off the flasher and audible
signal but will leave the white lights above the auxiliary
board on. Pushing the console reset button will clear the main
board.
When the alarm condition clears the Trip and ILatch lights -

will go off and the normal light will come on at the modules;
e
Approved byfi/v 'fifé??flwflhw 3H4-13

.13

9/24/65

this will also clear the white lights above the auxiliary
control board. On the Scram Module only, the lateh light will
remain on while the trip light will clear and normal light
will come on. The latch light will remain on until the reset
button is pushed. If the alarm condition clears, and re-
appears or if another alarm condition in the same group occurs,
then another audible and visual annunciation will be generated
at the auxiliary and'main control boards.

Type XIT Annunciation Coming from Computer to the Computer

Console

During normal operation the computer will be on constantly
and perform its programmed functions. It will annunciate
on the main board and type out on Typewriter No. 1 any ab-
normal reactor condition (See Type XITI alarm). 1In addition,
the computer also checks its own internal timer and circuitry
every 1/k second. An abnormal condition in the computer per se
will be annunciated in the computer room by a flashing red
alarm light - push button combination on the computer console
and a repeating-gong audible alarm. Pushing the alarm light
button combination will silence the audible alarm but leave a
steady red alarm 1ight on at the computer console. The computer
will not perform any more of its programmed functions until
restarted. When the computer malfunction is corrected and

restarted the alarm light will clear.
(2

LIGHTS ABOVE MCB

RED
| WHITE

‘2N )
3 ~ MC8
AUDIBLE SIGNAL
© LIGHTS ABOVE SAMPLER,| RED )
(5) |SCANNER, CHEM. PROCESS WHITE
® p — (8) FLASHER
| | @ UACK.

O LAMP TEST
Q ACK
SCANNER, SAMPLER, AND

CHEMICAL PROCESSING AUX . CONTROL BOARD

HTS 'ABOVE
ACB

PERSONNEL
ROCHESTER UNITS O gMH?N'TORS
® I M AD DI INTER. ®
® X {fi I A 81X TRoUBLE &< RpseT
DS ATE W[® reser o
RESET GROUP LIGHT

. ()2 0UT OF 6 MONITRONS
i9) 20UTOF 4 CAMS
DIESEL ALARMS

| 1]

DROP SIGNAL
-9 -
RESET RESET

FLAG

&

COMPUTER

'COMPUTER CONSOLE
Iolarm[ g |

@ AUDIBLE ALARM =
IN DIESEL HOUSE

ALARM TYPEWRITER
@4 Y LIGHT ON DPM IN ACR RED TYPE-OUT OF LIM..

BLACK TYPE-IN LIM..

V) —

i @ RESET

‘8 e I ACKNOWLE DGE
CONSOLE

ELECTRA MODULE ET 4300

9 T3 r

ELECTRA MODULE
ET 4200

jeggegegeget
jegsgefishe

RED
RED

NUCLE AR
POWER
PANEL

¢ €

TRIP LATCH

NORMAL RESET
@ L °

TRIP_TEST
=
Q- 2609-1

MSRE ANNUNCIATORS
Fig. 3H4-)

ALARM

fiTIAMBER-
W W I_ZIII { XY BREEN L

ELECTRAE1E’O4VIJOE£\’ SUPPLY
POWER ON7 @/-RED HIGH

I""T Q AMBER
/ /AMAN

ON RESET AUTO

©B ®

ELECTRA POWER SUPPLY
ET 4101

s MAN.
s AUTO.

®

POWE ®
(ALWAYS ON) O/I: RESET

PROCESS MONITORS
E LECTROMETER

Xie}-POWER

(ALWAYs ON)

-METER_AND
SET PT.

RESET
/ L @ onF
RANGE SELECTOR

NOTES. LETTERS = SWITCHES
NUMBERS = LIGHTS,FLAGS,
OR AUDIBLE ALARMS

Lgq paroxddy

R,

G9/L2/6
HT-HHE
TARLE 3H L.1 SEQUENCE OF ANNUNCTIATORS

3H4-15

NO ABNORM COND.

AENORMAL CONDITION
OTHER ACKNOWLEDGEMENT

AENORMAL COND. CLEARED

.
MCB (A) ACT IF ALRM |
TYPE DESCRIPTION SWITCH | ACK B PUSH COND AFT CTEARS CLEARS & ACT ON ANOTHER AIRM ACTION ON TO CLEAR ALL
No. SETTING LTS. | AN ON AIM COND| CLEARS| BUTICN| ACTION MCB REATARMS i T SAME GROUP* CLEARING INDICATORS
T Direct to MCB None ' 1,2,3 2,3 None No 1-93,2,3 1-2 Push A
IT Direct to ACB None 7,8,9 None F Clear T—clear—7,8,9 T—clear None
I1T To ACB — MCB None 1,2,3,7,8,9 2,3 F 2,7 Yes 7 - clear 1,2, 1,2,3,7',8',9',7 7— clear None
IV To Sampler 3,7,8,9
To Scanner ,
To Chem Processing — MCB| None . 1,2, 3’)4’ 5’6 253 D 2)L" Yes t” 55 l: 25 3, 1,2, 3)}_,_1’51,6r’5 )'L""'5 2 )4'—5 Push C
To Vapor Condensing Syste@) »25
v Electra Mod. ET4200 — | Pwr. On 1,2,3,12,14 2,3 None 1,12,14 No None 14! None Pugh G & A
ETL4104— MCR H-Man
VI Electra Mod. ETL200 — Pwr. On 1,2,3,7,8,9,14 | 2,3 F 2, 7,14 Yes None 1,2,3,7',8',9,1k4", None Push G
ET4L101 — MCB H-Man 14,7
VIT FElectra Mod. ETL300 — Pwr. On 10 on 1,2,3,7,8,9,10 | 2,3 F 2,7,10 Yes 7,105 clear— 10! 10 - 11 None
(ET4101 or ETL1OL) — MCB H-Man 11 1,2,3,7,8,9,14
VITT Rochester Mod to MCB T in 15 on 1,2,3, 15 off 2,3 None 1, 15 off | No None 15" off None I > Reset -
Operate Oper & Push A
TX Personnel Mon. to MCB None 1,2,3 2,3 K 2, (16,17, Yes None 1,2,3(16', 17', or None Push J
1&16’17’ or 18) or 18) 18') 19" (16,17,0r 18)
X Process Rad, CM or Q1916 - None 21 1,2,3,7,8,9,20, 2,3 F 2,7,20,21 | Yes Dial Change 1,2,3,7',8',9,20',20 |Dial Change| Push L
— MCB 21 off of f
XT Process Rad, Ton Ch, 202 None 1,2,3,7,8,9 2,3 F 2,7 Yes None None None Push M
Elect-NP-MCB
XIT Diesel Alarm-DPM(ACR)-MCR Pwr. On 1,2,3,22,23,24 | 2,3 P 2,22 Yes None 1,2,3,22,23,24 None Switch N
XIIT Computer —s MCB None 1,2,3,26 red 2,3 None 1,26 red No 1, 26 red -2, |1,2,3,26"' red 1,26 red- Push A
26 black- 1,2, 2,26 black
3, 26 red
XTIV Nuclear Power Panel — ACB-MCB 27 1,2,3,7,8,9, 2,3 F 2,7,28,29 | Yes 7,28,29,- clear| 1,2,3,7',8',91,28", 28, 29 27 Push Q (On
28,29 -1,2,3,7,8,9, 29! Scram Module
28, 29 Only)
XV Computer (Computer Room) 25,R None R R, Clear Restart
Computer

1

]

TABLE 3HA4.2 ANNUNCIATORS

b
Location E
and Annunciates on 3
Annunciator Actuated (for setpoints o
Number by see Switch Tab) Control Action¥ Operator Action Zj
MCB-1 0
XA L000-1 XA 4029 Sump levels (Common) Note 1 Note 1 Check XA L4029-1 to 8 in '
ACB 3
XA L000-2 XA 4030-31 Instrument Air Note 1 Note 1 Check XA 4030-1 to 11 & )
(Common) XA 4031-1 to 12 on ACB 4
XA 4000-3 XA 4026-27 Cooling water Note 1 Note 1 Check XA L026-1 to 12 &
(Common ) XA 4027-1-9 on ACB 3 ‘SQ:
XA 400O-k PS k0O or Hi Lo Leak Detector None Repressurize or vent & hunt <}\\
514 Pressure for leaks
XA 4000-5 XA-4019, TVA Electrical power None Note 1 Check XA-4019. Check 3
Feeder, (Common ) and restart electrical
Diesel Pnl.. . equipment
XA L0O00-6 K 1073A on Containment Air Note 1 Note 1 Check XA L401T7-1 to 5
XA Loi7 (Cormon ) on ACB 2
MCB-2 '
XA L0oo1-1 K-1072A on  Misc. Aux. Bd. Note 1 Note 1 Check XA L4016, XA L018
XA 4016, Alarm
L018
XA hool-2 PA 9006-1 Lo Ns Pressure None Change banks and replace used
Initial cylinders
(Instrument Air) :
XA L4001-3 PA 9006-2 Lo No Pressure Final None Change banks, replace cylinders
(Instrument Air) & prepare to drain
XA L40ool1l-L Selected Drain None Check that (1)FV 105 & 106 are
tank not ready thawed & FV 104 frozen (if FFT
selected, FV 10k thawed & 105,
106frozen) (2) selected DT \O W
equalizers are open =R
XA Lo01-5 K-1028A Chem process common Note 1 Note 1 Check XA 4051 and XA 4052 i
on Chem processing panel EQPL

Note 1: See individual Annunciators (Aux. C. R., Sempler, Chem. Plant, Etc.)

*
Annunciation and control action do not necessarily occur at the same time.
TABLE 3H4.2 (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
MCB-2

XA 4001-6 A-Be S1010-Al1 Hi Be in radiator None Evacuate vicinity of monitor -
stack when in Consult industrial hygienist
operation. Hi
local Be during

' shutdown
MCB-

XA LOO2-1 PaA 960A1 Lo differential None Stop running CCP, start alter-
pressure. CCP 1 nate CCP & check PAIC 960A
or 2 : ' :

XA 4002-2 PS 906B Lo discharge pres-  None Check PC 906B in blower house
sure CCP 3 ‘ or valve in auxiliary air

compressor

XA 4002-3 PS 791B and Lo oil pressure Stops CCP Start alternate CCP

T95B . CCP 1 or 2 :
XA 4002-4  SS CP G-1 Lo coolant pump Stops FP - It & Low - Restart CP, stop radiator
or 2 speed Coolant flow scrams blowers & start up per pro-
‘ radiator doors cedures '

XA Loo2-5 PS 9013-2 Lo pressure to Blocks lines to cells Check cell pressure

block valves causing start of
drain, etc.
PSRCA-~1 or 2 Li-Lo R. C. pressure At 12.2 psia closes Check cell pressure & tempera-

XA L4002-6

K-98C KC 8iG
K-30, K-31
K-32, KB3LG
KA8LG

HCV 565. At 16.7 psia
2 out of 3 PSS closes
Lig. waste Block
valves and inst. air
to Penetration block
valves

ture. If Hi pressure, open
V-565C; check RCC-1,2

) A

£q pasoaddy

e

-l

S

/

c9/Llz/6
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TABLE 3H4.2 (continued)

Annunciates on
(for set points
see Switch Tab)

Control Action

Operator Action

TLocation
and
Annunciator Actuated
Number by
MCB-U4
XA L0OO3-1 RS-ST Al
RS-ST Bl
RS-ST C1
XA L00o3-2 TX 3003
XA L4003-3 TS 202-4,
B, or C
XA L0O3-k PS 510 A-1
or 2
XA L4003-5 ISOT 2-A3
XA L003-6 PS 751Bl &
75281
MCB-5
XA hook-1 TSCOP-1 or 2
XA LOOok-2 K-3504
XA LOook-3 FS-5124A

Hi containment air
Stack activity

Hi radiator annulus
temperature

Lo radiator outlet
temperature

Hi To coolant oil
tank pressure

Lo coolant oil tank
level

Lo coolant oil pump
pressure

Hi motor tempera-
ture COP 1 or 2

Coolant sampler
conmmon

Lo cover gas flow
to CP

None

None

If lo cell pressure - close 565C
& V-569A, determine source &
shut down system involved

Note 1 Check TX 3003-19 & 20
on ACB-5

2 out of 3 scrams radi- Increase heat to radiator &

ator doors & starts

coolant drain

None

coolant system. Close radi-
ator doors & stop radiator
blowers. A coolant drain
may be necessary. If FV-20L4
or 206 do not thaw, turn off
CCP 3.

Check PIC-510A & ECC-45 & Th

Close FSV T53A-1 (Cool- Check 0il tank (0T-2) & oil

ant lube oil)

Starts alternate pump

None

None

None

catch tank (0OCT-2) levels.
Pump seal leakage may neces-
sitate a drain. Alarm set-
point may need changing.

Start alternate pump - check &
stop defective pump.
to tie in fuel lube oll sys-
tem (Section 6D)

Investigate and consider
switching to alternate pump.

Check buffer header & glove
box pressures. Adjust as
necessary.

Check supply pressure.
& ECC-128

FIC 512

A
vaz/%i$7fizdészfiq pasrocaddy

Be p‘repa}f‘ea_

G9/Le/6
2k
TABLE 3H4.2 (continued)

1A-1B Tevel

Iocation
and Annunciates on
Annunciator Actuated (for setpoints
Number by see Switch Tab) Control Action Operator Action
MCB-5
XA LOook-4 FS 526C Lo upper gas flow None Check CP pressure. Plugged
o from CP line may be opened by in-
creasing CP pressure. Shut-
: down may be necessary.
XA Look-5 - WSCDT-C1 Lo CDT wt. None Check WR-CDT-C. Adjust alarm
(adjustable) set point.
XA L4OOk-6 PS-511-D1. Hi-Io CDT pressure Hi closes He supply Check PIC-511C. For Hi pres-
or D2 (HCV-511A) & opens sure, vent CDT. For Io
vent (HCV-SLTA). pressure, add helium.
MCB-6 ,
- XA L005-1 FS-T53A or Lo lube or coolant  Prevents starting CP Check lube-oil pumps & adjust
T54A oil flow to CP flows. See Section 6D.
XA L005-2 PS 508 A-1 Hi-Lo CP pressure: Hi closes supply Check PRC-528, FIC-512A,
or A-2 valve FCV-512 A-1 and FI-526C
XA LO05-3 1S5-595 C-2 Hi-Lo CP level Hi opens CDT vent & Check all level instruments.
or C-3 (Bubblers or float) closes He supply valve. Lo level may indicate salt
Lo stop CP leak & necessitate drain
XA L0oo5-L PS-594-A1,A2 Hi-Io gas flow %o None Adjust flows & check ECC-T5,
505-A1, A2 CP bubbler T6, & T7, check that lines
598-A1, A2 are not plugged.
XA L4005-5 FS-201-A Lo coolant salt Stops FP. 2 out of 2 Restart CP - Stop radiator
or B flow Lo flows or one lo flow blowers & start up per
& one Lo speed scrams procedures
radiator doors -
XA L005-6 XpS 201-A Hi reactor power None Check nuclear power. Close
at radiator radiator doors if in doubt.
MCB-8
XA L0OO6-1 RS-8100- Hi-Io Idinear Power None Change ranges on. selector

switch

— £q psaroxddy
SHE

A
2

q9/12/6
-3 " HHE
TABLE 3HL4.2 (continued)

Tocation
and
Annunciator
Number

Actuated
by

Annunciates on
(for set points
see Switch Tab)

Control Action

Operator Action

MCB-8

XA Loo6-2

XA 4006-3
TS-100-1
TS-100-A1
TS-100-A2
TS-100-A3

XA Looé-L4

XA hO06-5

XA L0oo6-6

MCB-9
¥A LOOT-1

XA LOOT-2

XA LooT7-3

SSIFPE-1
or -2

LS 593-C2
or C-3

PS 522 Al
or A2,
589A or
592B

PS 592-600

FS T02A or
TOLA

LS-599B or
6008

WO FDL Ch

or FD2 Ck

Lo FP speed

Hi reactor outlet
temperature

Hi-Io FP level
(bubblers)

Hi Lo FP pressure

Hi, o gas flow to
FP & overflow
tank bubblers

Lo Inbe or coolant
0il flow to FP
Hi level in FP

overflow tank

Hi £111 rate from
FD-1 or FD-2

Switches from run,
lowers heat & nuc-
lear power to
<1.5 Mw

Rod reverse on 2 out
of 3 channels

Hi opens FD-1, FD-2,
& FFT vents and
closes supply valves
Control Rod reverse
Io stops ¥P

Opens FP vent, FDT
vents, equal. valves
otarts drain

None

Prevents starting FP
Emergency drain
Stops He addition

& opens vent from
FD-1 or FD-2

Insert rods, lower heat load
and start up per procedures

Insert rods

Check Lo-Hi level instruments.
Lo level may indicate salt
leak & necessitate a drain,
or indicate a fuel system
temperature decrease

Check FP pressure. Determine
cause of pressure

Adjust flows & check ECC-63-68
Check that lines are not
plugged

Check lube-o0il pumps & adjust
flows. See Section 6D

Check P and OFT levels.
Section 6D.

Stop He addition, vent DT or
open equalizing valve if
necessary

See

G

%

q9/le/6
§?é°fié€
TABLE 3HL4.2

(continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
MGB-9
XA LOOT-4 ws ¥D-1, C5 Lo FD-1, FD-2, or None Check WRFD-1, FD-2 & FFT - Ad-
FD-2 C5 or FFT wt. (adjusta- just alarm setpoint
FFT C1 ble)
XA L0OT-5 FS-516B Lo cover gas Tlow None Check supply pressure, FIC 516
to FP & ECC-129
XA LOOT-6 FS-52LB Lo upper gas flow None Check FP pressure. Plugged
from FP line may be opened by in-
creasing FP pressure. Shut-
down may be necessary
MCB-10
XA L0oo8-1 K-149C Safety Circuit Prohibits Operate Mode . »:. .« . =0 x 5y “p o0
jumpered o Ll s T
XA Loo8-2 KC-881A Fuel Sampler Note 1 Note 1 Check XA-4035 to 37 - 1
(common) to 4 at SE panels I to 3
XA 4008-3 TS FOP 1 Hi motor tempera- None Tnvestigate and consider
or 2 ture. FOP 1 or 2 switching to alternate pump
XA L008-4 PS 513A-1 Hi-Lo fuel oil tank None Check PIC 513A & ECC L4k & 73
or A-2 pressure
XA 4008-5 IS OTL A-3 1o fuel oil tank Closes FSV-703 (fuel Check oil tank (0T-1) & oil
level lube 0il) catch tank (OCT-1) levels.
Pump seal leakage may neces-
sitate a drain. Alarm set-
point may need changing
XA 4008-6 PS 701B2 & Lo FOP discharge Starts alternate pump Start alternate - check & stop
PS 702 Bl pressure defective pump. Be prepared

to tie in coolant lube oil
system (Section 6D)

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TABLE 3HL.2 (continued)

Tocation
and

Annunciator Actuated

Annunciates on
(for set points

Number by see Switch Tab) Control Action Operator Action
MCB-11
XA 4009-1 PS 5T4BL Ii Lo FD-2 pressure Hi closes He supply Check PIC-517A. For Hi pres-
or B2 (HCV-5T7L4) & opens sure vent FD-2. For Lo
vent (HCV-575) pressure add He
XA 4009-2 PS-572 BL Hi Lo FD-1 pressure Hi closes (HCV-572) Check PIC-517A. For Hi pres-
or B2 & opens vent (HCV sure vent FD-1. For Lo
573) pressure add He
XA L4009-3 PS-576 Bl Hi Lo FFT pressure Hi closes (HCV-S5T76) & Check PIC-517A. For Hi pres-
or B2 opens vent (HCV 577) sure vent FFT. For Lo
pressure add He '
XA L4009-4 PS 608 B2 Hi Lo FST pressure Hi closes (HCV 530) & Check PIC-530. For Hi pres-
or B3 opens vent (HCV 692) sure vent FST. For Lo pres-
add He
XA L009-5 WS FST-C1 Lo FST Weight None Check WR FST - Adjust alarm
(adjustable) set points
XA 4009-6 XA L4028 Cover gas system Note 1 Note 1 - Check XA 4028-1 to
(common) 10 on ACB 3
MCB-12
XA L0O10-1 RS-7023 Hi activity - Note 1 Note 1 - Check CAM & Monitron
personnel modules on NP 5
monitors
XA 4010-2 K-1060A Hi activity - pro- Note 1 Note 1 - Check XA 4043 on NP L
cess monitors
XA L010-3 K-10TLA on  Freeze valve tem- Note 1 Note 1 - Check XA L4020 to 22-1
XA Lo20-22  perature. to 4 on ACT 5 to T also
(common) TX 3002 through TX 3010
XA L010-4 TX 3001 Freeze Flange Note 1 Note 1 - Check TX 3001 on
temperature ACB-5
(common )

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TABLE 3H4.2 (continued)

Location
and

Annunciator Actuated

Annunciates on
(for set points

Number by see Switch Tab) Control Action Operator Action
MEB-12
XA 4010-5 K 10364 Scanner (common) None Check XA L053-1 to 6 on
, Scanner Panel (840 level)
XA L010-6 Computer Computef (common) None Note 1.
MCB-6
XA 4011-1 KB 139H ¢ >1.5 Mw in Control rod reverse Check Nuclear Panel. Adjust
RXS-NCC1 ABB  start mode ' flux
RXS-NCC2 A8B '
XA Lo11-2 KA 1048A ¢ > 12 Mw common Two out of three chan- Adjust flux -
| nels give control '
rod reverse
XA L011-3 KB 1048B Period < 10 sec Control rod reverse Adjust control rods
' .if not in Run Mode
XA 40o11-L4 KB 161C Load set back Lowers radiator doors, Check radiator outlet tempera-
decreases AP set- ture. Check NP(¢ >12 Mw)
point and stops one’ Adjust load. ’ '
matn:blower: per pro-
_ grammed: sequence.
XA L4011-5 KB 11D Load scram Scrams both radiator Check radiator outlet tempera-
KB 12D doors. Stops MB-1 ture, CP speed & coolant
& MB-3 salt flow
XA L011-6 KA 140D Emergency coolant Opens CDT vent and by- Check radiator outlet tempera-
KA 141D salt drain pass valve. Closes ture

CDT He supply valve.
Scrams both radiator

doors. Stops MB-1
& MB-2. Thaws
FV-20k & 206

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TABLE 3H4.2 (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
MCB-8
XA-4012-1 KA 18G Emergency fuel salt Opens all vent and by- Reduce power to zero, reduce
KA 19G drain pass valves & closes heat load to zero. Check
all He supply valves Tro, FP pressure, OFT level,
to FD-1, FD-2, FFT. RE-565, RE-528
Thaws FV-103, 105,
106.
XA-L0o12-2 K2L8E Control Rod Scram Two out of three safety Lower radiator doors and re-
K2oLoR channels scrams all start per procedure. Checks
K 250% rods. Opens DT vent for circuit trouble in flux
valves. channels, 7 <1l sec, Tro,
¢ >15 kw, ¢ >15 Mw, reset
latch on rod scram module
XA-4012-3 K 207D T, demand rod set Group insert of control Check TSS-100A1-2, TSS-100A2-2
back rods TSS-100A3-2
XA-Lolo-L K-186E Control Rod Group insert of control Check ¢ >1.5 Mw, T <10 sec
reverse rods
XA-L4012-5 K-204D T, > 1275°F Two out of three ther- Lower reactor temperature
K-205D mocouples gives rod demand setpoint if in temp.
K-206D reverse and decrease servo. 1f not, lower flux.
reactor temp. demand
XA-4012-6 K-241B Reg. Rod @ L.L. Prevents transfer to Lower reg rod limit switch.
Run Mode if servo is If servo is on, lower rods
is on 2 & 3
MCB-
XA-4013-1 K-1054A High temperature None Shut down and drain reactor
control rod
housing
XA-4013-2 TS-0FT-64 Low Temperature None Check TE-OFT-6B, Scanner A, ad-

FP OFT

Jjust heaters, consider a
reactor drain

vy
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N A\O
TABLE 3H4.2 (continued)

Location
and Annunciates on
Anmunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
MCB-9
XA-4013-3 Spare
XA-4013-4 Spare
XA-4013-5 Spare
XA-4013-6 Spare
MCB-5 |
XA-LO1k-1 Spare
XA-hOlH—Q Spare -
XA-4O14-3 XA-4032 Low air flow, Bat-  None "~ Note 1. Check fans, switches

XA-hLo1k-k

XA-LO1k-5 K-111LkA

XA-L401L-6 K-85A

ACB-1

XA-4016-1 TS-3100

tery room exhaust ' and power supplies
Induction Regula- ' -
tor Cooling Air

24v DC power off HP None Check instrument power panel
Radiation Monitor #5

Vapor Condensing None Note 1. Check XA-4O5k out
Tank Common JB #151 at Vapor Condensing

Tank area

Low, Pressure Reactor Closes HCV-565. Stops Check to see that HCV—565,
cell. Safety CCP-1 & 2 thus initi- V-571, V-569 are closed.
Interlocks ating reactor drain Tnerease No to RC (sump

bubblers) and possibly add
air via 342 & 332. Restart
CCP-1 & 2 as soon as possible

Hi miscellaneous None Check TR-3100 on MCB-12 - Ad-
temperature just heat

TRA-3100

c9/Lz/6
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TABLE 3H4.2 (continued)

Location g
and Annunciates on 'S
Annunciator Actuated (for set points >
Number by see Switch Tab) Control Action Operator Action o
o'
ACB-1 <
XA-L016-2 TS-3400A1 Hi-Lo coolant salt  None Check TR-3400 on SP-2 (840
or 2 flow meter tem- level) Adjust heat.
perature. TR-3400
XA-L4016-3 P5-5-X10 Lo steam supply None Condensate make-up rate may be
pressure too high. Check gage on
steam header north of T503.
Call Utilities Dept. :
XA-L4016-L4 TS-3500A1 Hi-TLo drain line None Check TR-3500 or ACB-2. Ad- ’?
or 2 temperature just heat. Prepare to drain N
TRA-3500 system before salt freezes. &
XA-L4016-5 K 2A Hi-Temp sample None Check to see that computer is
surveillance test in operation. Adjust heat
if necessary.
ACB-2
XA-LO1T7-1 PS-HB-Al or Hi-Io High Bay None Check doors and dampers
A2 pressure
XA-L01T7-2 PdS-936A Lo auxiliary cell None Check auxiliary cell pressures
ventilation duct & adjust dampers
Diff.
XA-L017-3 PAS-927B Hi filter pit Diff. DNone Check dampers - filter replace-
pressure ment may be necessary.
XA-L017-4 FS-S1-A Lo ventilation None Check dampers, filters, AP etc.
stack flow
XA-L017-5 PS-927-A1 Containment air Starts stand-by con- Switeh to alternate stack fan
or A2 Duct 927 Vacuum tainment air fan blower. Check blowers, motors,
pressure <1.5" (sF-2) and dampers
H=0

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TT-2°* HHE

TABLE 3H4.2 (continued)

Annunciates on
(for set points
see Switch Tab)

Control Action

Operator Action

Location
and
Annunciator Actuated
Number by
ACB-3
XA-4018-1 TS-705
TS-T07
XA-4018-2 TS-T755
TS-T757
XA-14018-3 PS-9012-1A
1B, 1C-
XA-4018-L4 PxS-579,
580,581,
582, 58k,
586
XA-4018-5 PS-918-A1
ACB-4
XA-4019-1  UVR(48v IC)

Hi fuel pump oil
temperature

Hi coolant pump
oll temperature

Lo Press. sump bub-
bler and scanner

No supply

Hi pressure
in PT reference

Graphite Sampler
blower inlet Hi
pressure

Lo voltage
48v IC bus

None

None

None

None

None

None

Check temperature on logger,
check flows, lower power 1if
necessary. Check cooling
water flow & temp. Possi-
bly increase by-pass oil
flow.

Check temperature on logger,
check flows, lower power
if necessary. Check cooling
water flow & temp. Possi-
bly increase by-pass oi
flow. ' ‘ ‘

Check N2 supply press. at 840
level. OSwitch to alternate
bank. Change out empty
bottles

Consider draining fuel system
(violation of primary con-
ment)

Check Nz purge

Check MG sets. Check for
ground. Start alternate MG
possibly initiate emergency
drain

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TABLE 3H:.2 (continued)

Tocation
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
ACB-L4
XA-L019-2 MG #2 off 4L8v DC MG-2 or None Check MG sets. Start alternate
MG #3 off MG-3 off MG
XA-L4019-3 Position Reverse current None Check MG-1 and try to restart.
switch on trip breaker open If running, check reverse
reverse cur- current trip and reset. If
rent break- unsuccessful, shut down MG-4
‘'er handle (which transfers load to TVA)
XA-4019-k UVR MG-k Lo voltage MG-U4 None. However, if Check MG-U4 voltage, frequency,
(time voltage continues etc. Make adjustments if
delay) to drop, automatic necessary.
transfer to TVA will
occur
XA-4019-5 UVR open on Io voltage at any Would prevent 480v Check operation of MG-1. Check
low breaker of the 4 loca- equipment trip, or fuses and breakers at 250v
trip voltage tions in left prevent transfer to panel. Check condition of
UVR open on column AH feeder 250v batteries.
low 13.8 KV
feeder con-
trol voltage
250v batteries
low or breaker
"W" open.
ACB-5
XA-4020-1 TS-FV-103-1A2 FV-103 Hi & Lo Turns air on or off Check TX-3003-1-6, TX-300L,
KA-652C, “temp. for ‘thaw’& as required ECC- 1-6. Adjust air and see
TS-FV-103-3A2 freeze 650-660 Table 3H.L4.3-2, 3
(K-659A and a
K-660A)
XA-4020-2 KA-663C, KB- FV-10L4, Hi, Lo Turns air on or off Check TX-3002-1, TX-3005, 1-6,
663C, KG- temp. for thaw & as required. Per- 19, TX-3006-1-6. Adjust air
665D, (KA- freeze missive to thaw ECC- see Table 3H.4.3-2, 3, 4

670 & K-671) 661-671

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TABLE

3E4.2 (continued)

Location %?
and Annunciates on 'S
Annunciator Actuated (for set points 2
Number by see Switch Tab) Control Action Operator Action 3
o’
ACB-5 ;fi
XA-4020-3 KA-67LC, FV-105 Hi & Lo Turns air on or off as Check TX-3002-2, TX-3005 T7-12 \
KB-6T7L4C, temperature required. Permis- TX-3006 T7-12, TX-3005-20 \2§q
KA-675B, ‘ sive to thaw. See Table 3H.k.3-2, 3, L \
KB-675B, ECC-672-682 .
K-6814A% S
K-682A | < N
XA-L020-L4 KA-685C, FV-106 Hi & Io Turns air on or off as Check TX-3002-3, TX-3005 13-18 $~
KB-685C, temperature required, permissive TX-3006 13-18. See Table - g~
KA-686B, to thaw ECC-683-693 3H.4.3-2, L N
KB-686B, ~
KA-692A &
K-693A |
XA-4020-5 TS-3300 FV End None Check TR-3300. Adjust heat
Temperature Hi
XA-4021-1 KA-T762C, FV-204 Hi & Lo Turns air on & off, Check TX-3002-10, TX-3003, 7-12
KB-T762C, temperature permissive to thaw. TX-3004, T-12. See Table
K-T63B, ECC T60-T7T0 3H.4.3-2, 3
- K-T69A &
K~-TTOA
XA-4021-2 KA-T7T73C, FV-206. Hi & Lo Turns air on and off, Check TX-3002-10, TX-3003,
KB-TT73C, temperature permissive to thaw 13-18, TX-300L4, 13-18
K-TT4B ECC T71-781 See Table 3H.L.3-3
K-T80A and
K-T81A
XA-4021-3 KA-6963B, FV-107. Hi & Lo Turns air on & off. Check TX 3002-4, TX 3007 1-6
KB-696B, temperature Permissive to thaw TX 3008, 1-6. See Table w
KA-698D, ECC 69k4-T0k 3H.4.3-2, 4, 5 -fi;?fi
K-TO3A & Iw
K-TOLA oK

TABLE 3H:4.2 (continued)

Location %?
and Annunciates on ‘g
Anmunciator Actuated (for set points 9
Number by see Switch Tab) Control Action Operator Action o
ACB-5 g
XA-4021-1 KA-TOTB, FV-108. Hi & Lo Turns air on & off. Check TX 3002.5, TX 3007 T7-12
KB-T707B, temperature Permissive to thaw TX 3008, T-12. See Table
KB-T709D, ECC T705-T715 3H.4.3-2, 4, 5
K-T14A & :
K-715A
XA-4021-5 Spare <§
XA-Lpo2-1  KA-T18B, FV-109. Hi & Lo Turns air on & off, Check TX 3002-6, TX 3007 13-18 -
KB-T718B, temperature permissive to thaw TX 3008, 13-18. See Table X
KB-720D, ECC T16-726 3H.4.3-2, b, 5 >
K-T725A &
K-T726A
XA-L4022-2 KA-T29B, FV-110. Hi & Lo Turns air on & off, Check TX 3002-7, TX 3009, 1-6
KB-T29B, temperature permissive to thaw TX 3010, 1-6. BSee Table
KB-T731D, ECC T27-T37 3H.4.3-2, 5
K-T36A &
K-T3TA
XA-4022-3 KA-TLOB, FV-111. Hi & Lo Turns air on & off. Check TX 3002-8, TX 3009, T7-12
KB-T40B, temperature Permissive to thaw TX 3010, T7-12. See Table
KB-742D, ECC T738-748 3H.4.3-2, 5
K-TL47A &
K-T48A _
XA-Lo22-4 KA-T51B, FVv-112. Hi & Lo Turns air on & off. Check TX 3002-9, TX 3009, 13-18
KB-751B temperature Permissive to thaw TX 3010, 13-18. See Table
KB-753D, ECC Th9-T759 3H.k.3-2, 5
K-758A &
ACB-3 N
XA-4026-1 FS-8LLA. Lo water flow to None Adjust flow, check ECC 56, 58, ..
thermal shield & 475 & TE 845, May be neces- VIV

sary to drain & cool reactor

TABLE 3H4.2 (continued)

Location
and
Annunciator Actuated
Number by

Annunciates on
(for set points
see Switch Tab)

Control Action

Operator Action

ACB-3
XA-L026-2 FS-8104A

XA-L4026-3 FS-812A
XA-40o6-k TS~-826

XA-L026-5 K-113 from
FS-830A

XA-L026-6 K-114 from
FS-832A
XA-LO26-T FS-836A
XA-L026-8 FS-8384A
XA-L026-9 FS-8LOA
XA-4026-10  PS-829B
XA-L4026-11  PS-851R2
K-143

XAfh026-12 PS-882B

XA-hooT-1 Fs-851C

Lo water flow to
DT condenser #1

Lo water flow to
DT condenser #2

Hi treated water
temperature

Lo water flow to
FP motor

Lo water flow to
CP motor
Lo water flow to
DT space cooler
Lo water flow to
RC space cooler 1
Lo water flow to
RC space cooler 2
Lo T™W pump dis-
charge pressure

Lo CTW pump dis-
charge pressure

Lo process water
pressure

Lo CTW flow to
treated water
cooler

None
None
None

Time delay to stop FP

Time delay to'stop CP
None
None
None

None (Check Inst.
Ap. ECC)

Switches DT steam dome
condensors from CTW
to PW

None

None

- Adjust flow, check ECV-56, 58,

Adjust flow
Adjust flow

Check CTW flow, TIC-858, CT <
fans, etec.

17327 Ao

& 475 & TE 831-1. May be
necessary to stop FP

Adjust flow, check TE 833-1,
may be necessary to stop CP

Adjust flow, check cell tem-
perature & pressure & ECC 53

Adjust flow, check cell tem-
perature & pressure & ECC 53

Adjust flow, check cell tem-
perature & pressure & ECC 53

Start alternate pump. Check
flows. Check ECC (TS
pressure)

Start alternate pump & check
flows

Check back flow preventer, cur-
tail unnecessary water usage
so that cooling tower can be
kept in operation

Adjust flow, start alternate
CIW pump

¢9/l2/6
9T-2° HHE

=
TABLE 3H4.2 (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
ACB-3
XA hooT-2 FS-873A Lo TW flow to com-  None Adjust flow, start alternate
ponent gas cooler TW pump
XA-4027-3 FS-875A Lo TW flow to CCP None Adjust flow, start alternate
1 & 2 oil coclers TW pump
XA-L027-4 FS-821A Lo CTW flow to oil  None Adjust flow, start alternate
supply of fuel oil CTW pump
system
XA-4027-5 FS-823A Lo CTW flow to oil  None Adjust flow, start alternate
supply of coolant CTW pump
oil system
XA-4027-6 LA FWT-1A Lo feed water tank  None This may indicate that drain
or 2A 1 or 2 level tank steam domes are in service.
Check temperatures. If not,
add condensate to prescribed
level .
XA-4027-7 LA ST-A Lo treated water Condensate will be Check condensate tanks levels
surge tank level added from conden- and valving
: sate tanks.
XA-4027-8 PSS-8LLmp Hi H=0 Pressure Re- C(Closes TS cooling Check that FSV 847 is open also
actor Thermal water inlet block check rupture discs and reset
Shield valve FSV-84L
XA-4027-9 IS NP Io nuclear instru-  None Physically check level & add
ment penetration water through line 848
water level
XA-4028-1 P5-500k Lo He storage None Check He traller-valve in
tank pressure emergency cylinders
XA-4028-2 PS-500B1 Hi-I.o He header None Check PRV 500G
or B2 pressure
XA-4028-3 F5-500J Hi He flow None Check FIC 500J - Curtail
unnecessary usage
XA-L028-L PS 500K Lo treated helium None Check FIC 500J - Curtail

surge tank pressure

unnecessary usage

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LT-2 HE
TABLE 3Hk.2  (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
ACB-3 |
XA-4058-5 PS 500 L-1 Hi-Lo regulated None Check PCV-500C (or 605A).
or L-2 He pressure Change to alternate regula-
: tor. Curtail unnecessary
usage
XA-4028-6 PS-508A Hi rupture disc dis- None " Excess He leakage through re-
charge pressure lief valve may necessitate
(Line 508) a shutdown
XA-4028-7 PS-506 Hi pressure at Op None Relieve pressure. Replace
removal No. 2 rupture disc if necessary
(Line 506)
XA-4028-8 PS-50T7 Hi pressure at Op None Relieve pressure. Replace
“removal No. 1 rupture disc if necessary
(Line 507) '
XA-14028-9 K-L46F, Lo He supply pres- Closes all He Sup- Check He surge tank pressure,
‘ K-47F, sure safety ply block valves FIC-500F, He trailer sup-
K-L48F channels ply pressure valve in
Emergency He cylinders
XA-4028-10 K-L4OOB Hi Heater temp. or Turns heater off and Adjust heaters or repair
K-40LB open thermocouple prevents restarting thermocouple. Consider
K-L408B at He treating heater at He pre- changing helium treating
K-412B station heater, dryers, station
K- 4168, K=420B or 0o removers
XA-4029-1 LS-RC-C Hi level RC sump None Jet to liguid waste tank.
IS-RC-D Determine source and leak
rate. Prepare for reactor
shutdown
XA-4029-2 IS-DTC-A Hi Level DIC sump None Jet to liquid waste tank.
L5-DIC- Determine source and leak

rate.
shutdown

Prepare for reactor

Lg psaocaddy

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TABLE 3H4.2 (continued)

Location
and

Annunciator Actuated

Annunciates on
(for set points

pressure trans-
mitter room
20 psig

Number by see Switch Tab) Control Action Operator Action
ACB-3
. XA-4029-3 IS-FRT Hi Level Pump None If radioactive, pump to liquid
Room Tank waste storage tank. Other-
wise pump to catch basin.
XA-4029-4 IS-FSC-A Hi Level FSC Sump None - Jdet to Liquid waste
storage tank
XA-L4029-5 I.5-PRS-C Hi Ievel PR & Operates jet syphon Check sump pumps 1 & 2.
' CDC sump in CDIC sump Check 60# steam supply
‘ header in filter house
XA-L029-6 LS-SC-A Hi Level Euipment None Jet to 1liquid waste storage
: storage cell sump tank
XA-4029-7 IS-TC-A Hi Level spare cell None Jet to liquid waste storage
tank
XA-L4029-8 LS-WIC-A Hi Level waste tank None Jet to Liquid waste storage
cell sump tank
ACB-4
XA-4030-1 PS 9001-1 Lo Instrument air None Check pressure reducing valve
pressure - MCB- and usage
, 20 psig
XA-4030-2 PS 9002-1 Lo instrument air None Switch to alternate PCV if
pressure trans- possible
mitter room
30 psig
XA-4030-3 PS5 9002-3 Lo instrument air None Switch to alternate PCV if
pressure trans- possible
mitter room
20 psig
XA-4030-4 PS 9002-4 Lo instrument air None Switch to alternate PCV if

possible

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TABLE 3H%.2 (continued)

Location %?
and Annunciates on "
Annunciator Actuated (for set points | 2
Number by see Switch Tab) Control Action Operator Action 3
o'
ACB-L _\“
XA-4030-5 PS 9003-1 Lo instrument air None : Switch to alternate PCV if o
pressure mainte- possible :\\
nance control ' _
room 20 psig Hdr _
XA-4030-6 PS 9004-1 Lo instrument air None Switch to alternate PCV if
pressure service possible )
room 20 psig Hdr _ P BN
XA-4030-7  PS 9005-2 Lo instrument air  None Switeh to alternate PCV if N
pressure water possible \g
room 20 psig Hdr ' X
XA-4030-8 PS 9005-1 Lo instrument air None Switch to alternate PCV if %;
pressure water possible ™~
room 60 psig (Sup-
plier WR, Filter
Pit, & Chem.
Processing)
XA-4030-9 PS 9000-1 Lo instrument air Starts alternate Check air compressors &
pressure Main compressor air usage
' Supply 80 psig Har |
XA-4030-10 PS5 9013-1 Lo instrument air None, however low Check air compressors &
pressure block pressure (<20 psig) emergency nitrogen
valve Hdr. causes block valves
80 psig to fail in closed
position
XA-4030-11 K-302 & AC-1, AC-2 permis- Hi Comp. temperatures, Check AC cooling water, oil
| K-307 sive Hi tempera- Lo oil pressure. level S-53 not manual %
ture. Lo oil Stops compressor ~F
pressure Iy
- 8

TABLE 3H4.2 (continued)

TLocation
and

Annunciator Actuated

Number

by

Annunciates on
(for set points
see Switch Tab)

Control Action

Operator Action

ACB-4
XA-L4031-1

XA-4031-2

XA-L031-3

XA-L031-k

XA-4031-5

XA-4031-6

XA-L4031-7

XA-1031-8

PS

PS

PS

PS

PS

9007-3

900T-1

9007-1

9008-1

9009-1

9010-1

9010-2

9011-1

Lo instrument air
pressure MCB &
Transmitter room
<18 psig

Lo instrument air
pressure, trans-
mitter room, 30
psig Hdr

Lo instrument air
pressure, trans-
mitter room &
MCR 60 psig Hdr

Lo instrument air
pressure, MCR &
transmitter room,
20 psig Hdr

Lo instrument air
pressure, Sampler
Enricher 30 psig

Lo instrument air
pressure service
room 30 psig Hdr

Lo instrument air
pressure service
room 20 psig Hdr

Lo instrument air
pressure water
room, service
room & filter pit
- 60 psig

None

None

None

None

None

None

None

None

Check pressure, reducing valve

& alr usage.

Switch to al-

ternate PRV if possible

Check pressure,
& alr usage.

alternate PRV

Check pressure,
& air usage.

alternate PRV

Check pressure,
& air usage.

alternate PRV

Check pressure,
& ailr usage.

alternate PRV

Check pressure,
& air usage.

alternate PRV

Check pressure,
& air usage.

alternate PRV

Check pressure,
& air usage.

alternate PRV

reducing valve
Switch to
if possible

reducing valve
Switeh to
if possible

reducing valve
Switch to
if possible

reducing valve
Switch to

if possible
reducing valve
Switch to

if possible
reducing valve
Switch to

if possible
reducing valve
Switch to

if possible

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TABLE 3H4.2 {continued)

=
Location E
and Annunciates on 2
Anmnunciator Actuated (for set points g
Number by see Switeh Tab) Control Action Operator Action o
[
ACB-L |
XA-4031-9 PS-9011-2 Lo instrument air None Check pressure, reducing valve I
: pressure water & air usage. OSwitch to jij
room. 30 psig alternate PRV if possible 5\;
XA-4031~10 PS-9011-3 Lo instrument air None Check pressure, reducing valve “\Q
pressure water & air usage. OSwitch to <<f}v
. _ room. 20 psig alternate PRV if possible N
XA-L031-11 PS-9011-4 Lo instrument air None Check pressure, reducing valve }5
pressure water & air usage. OSwitch to 'Q
room. 30 psig alternate PRV if possible —
XA-4031-12 P5-9011-5 Lo instrument air None Check pressure, reducing valve
pressure filter & air usage. Switch to
pit. 20 psig alternste PRV if possible
X4-4032-1 PS-9011-6 Chem. process. None Switch to alternate PCV
Emergency instru-
ment air header,
lo pressure
XA-4032-2 Spare S
XA-4032-3 Spare
XA-Lh032-L4 Spare
XA-4032-5 Spare
XA-4032-6 Spare
XA-4032-7 Spare
XA-4032-8 Spare %
~ F
XA-4032-9 Spare g
~. |
XA-4032-10 Spare an

TARLE 3H4.2 (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
ACB-4
XA-4032-11 S Lo flow, Battery None Check blower switch & power
Room Exh
XA-4032-12 FS Lo flow, Induction None Check blower switch & power
Regulator
SAMPLER-ENRICHER
ok-1 _
XA-4035-1 PS-5904A Lo pressure He None Check main He supply
supply
XA-4035-2 PS-650C Hi rupture pressure None Set PV-650A to 80 psig;
access port Replace rupture disc
supply
XA-4035-3 PS-509D Lo Pressure Regu- None Check main He supply and
lated He header PV-509B setting
XA-4035-4 PS-6TLA Hi rupture pressure None Set PV-509B to LO psig.
Regulated He Replace rupture disc
header
XA-4035-5 PS-664B Lo pressure leak None Repressurize through HV-66L

detector Header

#1

If pressure fails to rise,
find leak

C2-2 HHE

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no
~1
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N1

TABLE 3HL.2 (éontinued)

Iocation
and

Annunciator Actuated

Annunciates on
(for setpoints

Number by see Switch Tab) Control Action Operator Action
SE-1
XA-4035-6 PS-6L4LB Lo pressure leak None Repressurize through HV-6kh,
detector header If pressure fails to rise,
#o find leak
SE-2
XA-4036-1 K-360D Lo buffer pressure Prevents opening access If not caused by opening
to removal valve port, operating valve valve, find leak and
or maintenance valve correct
XA-4036-2 K-369D Lo buffer pressure Prevents opening ope- If not caused by opening port,
to access port rating valve, find leak and correct
maintenance valve,
or removal valve
XA-4036-3 K-363D & Lo buffer pressure  Prevents opening access If not caused by opening
K-366D to operating & port, removal valve, valves, find leak and
maintenance valve or offgas lines correct
XA-4036-4 K-393B Hi Boot Pressure Closes HSV6TT-A If pressurizing, throttle HV-663
XA-4036-5 PdS-1Ce Area 1C pressure Prevents opening access Acknowledge alarm. No action
greater than port unless 1C pressure rising
Area 3A rapidly
XA-4036-6 PS-683A Lo pressure None Open HV-683, check He supply,
buffer header 1look for leak
SE-3
XA-4037-1 P5-1CE Hi pressure Area 1C None Vent pressure to offgas system
Find leak causing pressure
rise
XA-4037-2 PS-AR3A Hi pressure Area 34 None Vent pressure to offgas system

Find leak causing pressure
rise

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TABLE 3H:).2 (continued)

Tocation

and

Annunciator Actuated

Annunciates on
(for set points

load set back &
rod reverse

Number by see Switch Tab) Control Action Operator Action
SE-3
XA-4037-3 PS-659A Hi Pressure Area 2B None Find leak causing pressure
. rise
XA-4037-4 PS-522A3 Hi pressure fuel Closes HSV-680E, Acknowledge alarm. Do not
pump bowl HSV-668B, HSV-655B, sample
HEV-657D. Prevent
opening access port,
operating valve, or
maintenance valve
XA-L4037-5 RS-675A or Hi activity con- Close HSV-6T78A, 678B, Reset the radiation indicator.
RS-675B tainment areas HSV-6T7TA, ESV-5L42A, Locate source of activity.
HSV-6T75A, HSV-659B,
HSV-657D, HSV-668B,
and HSV-655B
XA-L403T7-6 RS-678C or Hi activity offgas  None Acknowledge alarm. Determine
RS-678D reason for high activity
MB #11 &
NBL
XA-LoLko-1 K-200C ¢ >12 Mw Channel None, however two out Check RSS-NSCl1l-A2
#1 of 3 channels give load
set back & rod
reverse
XA-40ho-2 K-201C ¢ >12 Mw Channel None, however two out Check RSS-NSC2-A2
#2 of 3 channels give load
set back & rod
reverse
XA-40LO-3 K-202C ¢ >12 Mw Channel None, however two out  Check RSS-NSC3-A2
#3 of 3 channels give

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TABLE 3H4.2 (continued)

Location
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
MB #11 &
NB-1
XA-4OLO-k4 RXS-NCC-1-A3B Period <10 sec Rod reverse if not in Insert control rods
Run Mode
XA-L4OLO-5 RX5-NCC2-A3B Period <10 sec Rod reverse if not in Insert control rods
Run Mode
NB-2
XA-4OL1-1 TS-NRR1-Al  Hi-temperature None Shut down and drain
TS-NRR1-A2 Control Rod #1 reactor
XA-Loh1-2 TS-NRR2-A1  Hi-temperature None Shut down and drain
TS-NRR2-A2 Control Rod #2 reactor
XA-Lolh1-3 TS-NRR3-A1  Hi-temperature None Shut down and drain
TS-NRR3-A2 Control Rod #3 reactor
XA-4Oh1-4 Spare
XA-LOL1-5 Spare

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TABLE 3HL.2 (continued

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Iocation
and Annunciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
NB-3
XA-4olho-1 RS-827-A2 Cooling H-0 Hi Closes in-cell cooling Locate & isolate source, open
RS-827-B2 Activity water block valves block valves if necessary.
RS-827-C2 Initiate a drain
XA-Lok2o-2 RS-0T1-B Fuel & coolant salt None Violation of primary contain-
R5-0T2-B pump oil supply ment. Reduce power to zero
Hi Activity
NB-4
XA-LoU3-1 RS-596-A2 FP bubbler He Closes He supply line Reduce power to zero and
RS-596-B2 supply to in-cell bubblers and consider draining
RS-596-C2 Hi Activity
XA-4oh3-2 RS-500D Helium gas supply None Determine source. Consider
Hi Activity reducing power to zero
and draining reactor
XA-40L3-3 RS-55T7-A2 Fuel salt system Closes block valve 1in Determine source and reduce
R5-557-B2 offgas Hi main offgas line power if necessary
Activity to stack
XA-LOk3-)k RS-528-R2 Coolant salt system Reactor Drain & Check RS-528 to drain
RS-528-C2 offgas Hi Stop FP
Activity
XA-L4OL3-5 RS-565-B2 Reactor cell air Reactor Drain. Initiate a drain
RS-565-C2 Hi Activity Closes cell evacu-

ation block valve

¢9/.1z/6
l2-2' HHE

TABLE 3Hk.2 (continued)

Location
and
Annunciator Actuated
Number by

Annunciates on
(for set points

Operator Action

CHEMICAIL PROCESSING
Panel #l

XA-4051-1 Spare
XA-L4051-2 PS-604C

XA-4051-3 PS-608A1

XA-4051-4 PS-608B1

XA-L051-5 PasS-694-A2

XA-L0O51-6 FS 940

CP Panel #o
XA-L0O52-1 PS-690B

XA-4052-2 (Remote)
PS-696-A

XA-4052-3 TS HFH
TS SOP
Ts FLP

see Switch Tab) Control Action
Helium supply to None

Line 111 Lo

pressure

Helium to top of FST Closes HCV-690
Low Flow

FST Hi pressure Opens FST vent valve
Closes FST He supply
valve

Lo pressure Opens HCV-694

Line 690
Offgas low flow Close HCV-692
Fo supply Hi None

Pressure

HF Supply Hi None

pressure

HF heater Lo None

SOz pre-heater Hi
F» pre-heater Hi

Check He supply valve and
and He supply pressure

Check He supply pressure
and valves

Determine cause of Hi pres-
ure. Check HCV-692

Check flow from GSS

Turn off Hs supply valve.
Check fans, duct flow, and
940 Qamper

Check FST and CS pressure.
Check for restriction down-
stream of PS-690 and that
HCV-694 is closed

Check temperature of water
bath. Turn off steam
supply at GSS

Check power to HF heater.
Check SOz and Fo flow, check
for excessive power to
heaters

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TABLE 3HL.2 (continued)

Location
and Annuvnciates on
Annunciator Actuated (for set points
Number by see Switch Tab) Control Action Operator Action
CP Panel #2
XA-L4052-4 PS SFA-C1 Hi pressure instru- None Check to see that V979 is open.
PS CP3-B1 ment cubicle Hi Check to see that cubicle
pressure absorber blower is on and V-978 is
cubicle open
XA-4052-5 PS-CS-Al Hi pressure caustic None Check for restriction in line
scrubber 628. Check No flow to
bubbler
XA-4052-6 RS-9LoG Hi activity in fuel- None Check for source of activity
RS-CP3-A processing system and prepare for possible
RS SFA-A shutdown
RS-994
SCANNER PANEL
XA-4053-1 TS-5001-A Hi-Lo temperature None Check Scanner A temperature
R Scanner A trace
XA-L4053-2 TS-5002-A Hi-Lo temperature None Check Scanner B temperature
Scanner B trace
XA-4053-3 TS-5003-A Hi-Lo temperature None Check Scanner C
Scanner C
XA-4053-4 TS-5004-A Hi-Io Temperature None Check Scanner D
Scanner D Lower load
XA-4053-5 TS-5005-A Hi Lo temperature None Check Scanner E
Scanner B Lower load
XA-4053-6 PS-5000-A N> supply pressure None Switch supply banks and change

Lo tc scanner

out empty cylinders

q9/)z/6
62-2 " HHE
TABLE 3H4.2 (continued)

TIocation
and Annunciates on
Annmunciator  Actuated (for setpoints
Number by see Switch Tab) Control Action Operator Action
JUNCTION BOX
#151
XA-L40O54-1 LS-VT1-Bl Lo-water level None Prepare to shut down reactor
Vapor Condensing and add water
Tank. FINAL
XA-LO5k-2 LS-VT1-B2 Lo-water level None Punch list for water addition
Vapor Condensing during next shutdown
Tank. INITTAL
XA-LO54-3 IS5-VT1-B3 Hi-water level None Check thermal shield rupture
Vapor Condensing disc
Tank. INITTAL
XA-4osk-L ILS-VT1-B4 Hi-water level None Prepare to shut down and remove
Vapor Condensing water
Tank. Final
XA-Lo5h-5 Spare
XA-4054-6 PS-VT1-C Hi pressure None Release excess pressure through

Vapor Condensing
Tank

V-98L.

open

Do not leave wvalve

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=7,
Approved by;zfigaigjfltigékhbflm____,,_ 3H4.3-1

10/4/65
CODE FOR TEMPERATURE SWITCHES, TABLE 3HL.3

The code letters or numbers listed describe the automatic control

action and Operator action to be taken when a module alarm condition

exists.
CONTROL ACTION DESCRIPTION

A Air Off

B None unless 1A1 or 341 exceeds setpoint at which time interlocks
(1) shuts off FP and (2) precludes start mode.

C High air and green flashing light on at Freeze Valve switch when
valve is in the freeze position.

D None

E Red flashing light on at freeze valve switch when valve is in thaw
position.

B Prevents closing of cooling-air control valve thus prevents thaw of
freeze valve

G Center Heater and red flashing light on at freeze valve switch when
valve is in thaw position.

Opens ESV-806A -- Water to Steam Dome of FD-1
I Opens ESV-80TA -- Water to Steam Dome of FD-2
OPERATOR ACTION DESCRIPTION

1 Increase hold air (decrease heat as last resort).

2 Check air off (raise shoulder heater as last resort).

3 Lower hold air (increase heat as last resort).

Y None

5 Turn on or raise line-heater power. Check adjacent line temperatures.

6 Check other thermocouples of freeze flange. Possibly adjust heat
on adjacent heaters.

il Check other thermocouples on reactor ne¢k. Possibly adjust coolant
air flow.

8 Check Drain Tank temperature, possibly turn off heaters or lower
setting.

9 Chéck lube oil cooling water, lube oil flows. Lower reactor power if
necessary.

10 Check that MB-2 and MB-4 are on.

11 Increase FP heaters or prepare to shut down reactor.
TABLE 3 H.4.3 TEMPERATURE SWITCHES

Module Light

Kq parcaddy

/,

s

w4

{0

Approximate Control Operator
Nuzber TE-To. bescription Above  Below  Set Point®  Action Action
Set Set (°F)
Point Point
TX 3001-1 FF 100-1 Freeze Flange Temperature Red - Hi 975 B 6
-2 FF 100-3 Freeze Flange Temperature - Red. Lo 700 B 6
-3 FF 101-1 Freeze Flange Temperature Red -—- Hi 975 B 6
-4 FF 101-3 Freeze Flange Temperature - Red Lo 700 B 6
-5 FF 102-1  Freeze Flange Temperature Red -—- Hi 1050 B 6
-6 FF 102-3  Freeze Flange Temperature -—- Red Lo 700 B 6
=7 FF 200-1 Freeze Flange Temperature Red -—- Hi 975 B 6
-8 FF 200-3  Freeze Flange Temperature - Red Lo 700 B 6
-9 FF 201-1-  Fréeze Flange Temperature Red --- Hi 975 B 6
-10 FF 201=3 = Freeze Flange Temperature -—- Red Lo 700 B 6
-11 R 42 B Reactor Neck Temp. (lower) Red ——— Hi 800 B 7
-12 R 45 B Reactor Neck Temp. (upper) Red - Hi 400 B 17
-13 R-33 Reactor Neck Temp. (lower Red - ‘Hi 300 B 7
-14 R 46 B Reactor Neck Temp. (upper). Red = =--- Hi 40O B 7
"15& 16  FD-1-19B Bayonette Temperature ‘ Red -——— Hi 1300 H 8
17 & 18 FD-2-19B Bayonette Temperature Red - Hi 1300 I 8
-19
-20

®3ee Switch Tabulatiofi‘for cfirfent“setzpéint. Switches with two temperatures alarm at the high
temperature and clear at the low temperature, ’

Vil 7

$9/4/01
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TABLE 3 H.4.3 (con't)

—- R pasroxddy

Module Light’

Approximate
Number TE-No. Description Above  Below o itpiinga  Control  Operator
‘ Set Set (°F) Action Action
Point Point
TX 3002-1 FV 104-5A  Freeze valve pot temperature -——- Red Lo 900 F 5
-2 FV 105-5A Freeze valve pot temperature - Red Lo 785 F 5
-3 FV 106-5A Freeze valve pot temperature -——- Red Lo 900 F 5
-4 FV 107-5A  Freeze valve pot temperature --- Red Lo 900 F 5
-5 FV 108-54 TFreeze valve pot temperature - Red Lo 900 F 5
-6 FV 109-5A Freeze valve pot temperature - ‘Red Lo 900 T 5
-7 FV 110-5A Freeze valve pot temperature - Red - Lo 900 ' F 5
-8 FV 111-5A TFreeze valve pot temperature - Red Lo 200 F 5
-9 FV 112-5A Freeze valve pot temperature -——- Red Lo 900 F 5
~-10 FV 204-5A  TFreeze valve pot temperature -——- Red "Lo 900 F 5
11 & 12:. FD-1-20B FD-1 Bayonette temperature Amber Green Hi 1300 H 8
13 &-1L FD-2-20B FD-2 Bayonette temperature Amber Green Hi 1300 I 8
=15 705-1B FP lube oil return | Red -—-- Hi 150 B 9
.16 707-1B . FP coolant 0il return Red -— Hi 150 B 9
.17 '755-1B CP lube oil return Red -—— Hi 150 B 9
.18 1757-1B CP coolant oil return Red -—- Hi 150 B -9
19 & 20 OFT-6A Temperature at Bottom of Green Amber D 11
- Overflow tank
ol w
TX 3003-1 FV 103-1A1 ©Shoulder temperature, outside Yellow Green Hi 960- C 1 o
&-2 box, Reactor side gl0 S
-3 FV 103-2A1 C(Center temperature in air box  Green Yellow Lo 900~ B 2 di(o
&t S

at equilibrium.

bYellow light is alarm condition for freeze valve modules. Take operator action if alarm persists

TARLE 3 H.4.3 (con't)

£q paacaddy

Module Lightb

Above Below gfifirggiizge Control Operator
Number TE-No. Description Set Set P Action  Action .
X ; (°F)
Point Point
TX 3003-5&6 FV 103-3A2 Shoulder temperature,outside Greem  Yellow Lo 620 A 3 D
Lo o T cbox DT side : <i§}\
=788 FV 204-1A1 Shoulder temperature, coolant Yellow Green Hi 800-750 C 1 N
| system side N
-9810 FV 204-2A1 Center temperature Green Yellow Lo 1000 E 2 .%
-11&12  FV 204-3A2 Shoulder temp., C.D.T. side Green Yellow Lo 650 A 3
-13814  FV 206-1A1 Shoulder temperature, coolant Yellow (Green Hi 800-750 C 1
system side
-15816  FV 206-2A1 Center temperature Green Yellow Lo 1000 E 2
-17818 FV 206-3A2 Shoulder temp., C.D.T. side Green Yellow Lo 650 A 3
-19 AD3-5B Radiator duct temperature Red -—- Hi 1000 B 10
-20 AD3-7B Radiator duct temperature Red -— Hi 800 B 10
TX 3004-18&2 FV 103-1A2 OShoulder temp. — Reactor side Green Yellow Lo 675 A 3
-384  FV 103-2A2 Center Temp., in air box Yellow  Green Hi 550% - B 1
- -586  FV 103-3A1 Shoulder temp., DT side Yellow Green Hi.765-715 C 1
-788 FV 204-1A2 Shoulder temp., Coolant system Green Yellow Lo%@EO A 3.
-9810  FV 204-2A2 Center temperature Yellow Green  Hi:550:- _ D L
-11812 FV 204-3A1 Shoulder temp., C.D.T. side Yellow Green Hi *800-750- C 1
-13&14  FV 206-1A2 Shoulder temp., Coolant Green Yellow Lo 650 A 3
system side
-15816  FV 206-2A2 Center temperature Yellow  Green Hi 550~ D 1.
-17818 FV 206-3A1 Shoulder temp. C.D.T. side Yellow Green Hi 800-750 C 1
TX 3005-18&2 FV 104-1A1 Shoulder temp. F.F.T.side Yellow Green  Hi 645-595 c 1 o
- -3&4 PV 104-2A1 Center temperature Green Yellow Lo 925 | E 2 = N
-68&6  FV 104-3A2 Shoulder temp. — Reactor side Green  Yellow Lo 700 A 3 24
-78&8 TV 105-1A1 Shoulder temp., F.D.T. side  Yellow Green  Hi 900-850 C 1 I
-9810 FV 105-2A1 Center temperature Green Yellow Lo 825 E 2 A
-11812 FV 105-3A2 Shoulder temp. Reactor side Green Yellow Lo 845 A 3

%
TABLE 3 H.4.3 (con't) 2
2
Module Light’ E’:
Above Below gfifrgiifiige Control Operator c
Number TE-No. Description Set Set o Action Action o
: ; (°F)
Point Point
TX 3005-13 FV 106-1A1 BShoulder temp., F.D.T. side Yellow Green Hi T750-700 C 1 §E§
&14 |
-15816 FV 106-2A1 Center temperature Green Yellow Lo 950° E 2
-17818 FV 106-3A2 Shoulder temp. reactor side Green Yellow Lo T65 A 3 ‘Q;
-19 TV 104-6A Vertical line temperature Red Lo 900~ F 5 ‘A§?
Reactor side §
-20 FV 105-6A Vertical line temperature Red Lo 900" F 5
Reactor side p§
TX 3006-1&2 FV 104-1A2 Shoulder temp., F.F.T. side Green Yellow L&t 520 A 3
-384  FV 104-2A2 Center temperature Yellow  Green Hi 550° D 1
-586  FV 104-3A1 Shoulder temp. reactor side  Yellow Green Wi T95-Th5 C 1
-788 FV 105-1A2 Shoulder temp. FD2 side Green Yellow Lo 820 A 3
-9810 FV 105-2A2 Center temperature Yellow  Green Hi 550° D 1
-11&12 FV 105-3A1 Shoulder temp., Reactor side Yellow Green  Hi 930-880 C 1
-13814  FV 106-1A2 Shoulder temp., FD 1 side Green  Yellow Lo 670 A 3
-15816 TV 106-2A2 Center temperature Yellow  Green Hi 5507 D 1
-17818 FV 106-3A1 Shoulder temp., Reactor side Yellow Green Hi 865-815 9! 1
TX 3007-18&2 FV 107-1A1 Shoulder temp., F.F.T. side Yellow  Green Hi 800-750 C 1
~-3&%&  FV 107-2A1 Center temperature Green Yellow  ILg 1000 E 2
-586  FV 107-3A2 Shoulder temp. L 110 side Green Yellow Lo 600 D 3 W
-7&8  FV 108-1A1 Shoulder temp. FD 2 side Yellow Green Hi 800-750 C 1 -
-9810 FV 108-2A1 Center temperature Green Yellow Lo 1000 E 2 tS}x
-11812 FV 108-3A2 Shoulder temp. L 110 side Green Yellow Lo 600 D 3 :;i»
-13814  FV 109-1A1 Shoulder temp. FD 1 side Yellow  Green Hi 800-750 C 1 ?pr
-15816  FV 109-2A1 Center temperature Green Yellow Lo 1000 E 2 b
-17818 FV 109-3A2 Shoulder temp. L 110 side Green Yellow Lo 600 D 3
TX 3008-1&2 FV 107-1A2 Shoulder temp. FFT side Green Yellow Lo 600 D 3
-3&4  FV 107-2A2 Center temperature Yellow Green Not in Use D 4

TABLE 3 H.4.3 (con't)
Module Lightb A i mat ,
Above Below Spprox%m ae Control Operator
et Point . .
Number TE-No. Description et Set (°F) Action Action
Point Point
TX 3008-5&6 FV 107-3A1 Shoulder temp. L 110 side Yellow Green  Hi 800-750 C 1
-7&8 FV 108-1A2 Shoulder temp. FD 2 side Green Yellow Lo 600 D 3
-9810 FV 108-242 Center temperature Yellow  Green Hi Not Used D 4
_-11812 FV 108-3A1 Shoulder temp., L 110 side Yellow Greem  Hi 800-750 C 1
-13814  FV 109-1A2 Shoulder temp., FD 1 side Green Yellow Lo 600 D 3
-15&16 FV 109-2A2 Center temperature Yellow Green . Hi Not Used D A
-17818 FV 109-3A1 Shoulder temp., L 110 side Yellow Green Hi 800-750 C 1
TX 3009-1&2 FV 110-1A1 Shoulder temp., L 110 side Yellow Green Hi 800-750 ¢ 1
‘ -3&4 FV 110-2A1 Center temperature Green Yellow Lo 1000 B 2
586 FV 110-3A2 Shoulder temp., F.S.T. side Green  Yellow Lo 6§00 D 3
-7&8  FV 111-1A1 Shoulder temp., Add. side Yellow Green Hi 800-750" C 1
-9810 FV 111-2A1 Center temperature Green Yellow - Lo 1000 E 2
-11&12 FV 111-3A2 Shoulder temp., L 110 side Green Yellow Lo 600 D 3
-13%14  FV 112-1A1 Shoulder temp., L 110 side Yellow Green Hi 800-750 C 1
-15816  FV 112-2A1 Center temperature Green Yellow Lo 1000 E 2
-17818  FV 112-3A2 Shoulder temp., Waste side Green Yellow Lo 600 D 3
TX 3010-1&2  FV 110-1A2 Shoulder temp.,.L 110 side Green  Yellow Lo 600 D 3
~3&4  FV 110-2A2 Center temperature ~ Yellow Green Hi Not Used D 4
-586 FV 110-3AL Shoulder temp., F.S.T. side Yellow Green Hi 800-750 C 1
-788 FV 111-1A2 Shoulder temp., Add. side Green  Yellow Lo 600 D 3
-9810 FV 111-2A2 Center temperature Yellow Green Hi Not Used D 4
-11812 FV 111-3A1 Shoulder temp., L 110 side Yellow Green Hi 800-750 c 1
-13814 FV 112-1A2 Shoulder temp., L 110 side Green Yellow Lo 600 D 3
-15816  FV 112-2A2 Center temperature Yellow Greén Hi Not Used D 4
-17818 FV 112-3A1 Shoulder temp., Waste side Yellow Green Hi 800-750 C 1

A

—1

7~ £q psaoxddy

S9/t/0T
9-"¢'%'H €

'fim%mv/%%A A
»
Approved bx;?’féfig4éfiffitfl4\ 3H5-1

8/6/65

5 JUMPER BOARD

On the MSRE there are many interlocking features of control circuits

and safety circuits to prevent undesirable and dangerous events from

taking place.

To provide for necessary flexibility under other-than-

normal operating conditions, provisions are made to by-pass certain

interlocks under strict administrative control. The jumper board provides

this flexibility along with a visual indication of the condition of all

circuits represented thereon. The location of the Jjumper board in the

main control room provides both accessibility and ease of administrative

control of any jumpers used.

5.1 Design Criteria, from operations standpoint, are as follows:

5.1.1 Bafety circuit isolation 1s maintained by means of by-

passing relays. Instead of insertion of a Jjumper pin
directly into the circuit, as with non-safety circuits,
the safety jumper pin operates a relay which indirectly

by-passes the circuit function.

5.1.2 The jumper board displays the condition of circuits by

means of indicating lamps. These lamps (white) are placed
between the schematic contacts of the circuits and will
indicate whether the circuit to this point is energized

or de-energized. A brief notation of the condition re-
quired to energize the circuit is given at each schematic

contact.

5.1.3 All jumper board safety circults are designed so that

failures of jumper board components will not jeopardize
operation of the circuits. The indicator lamps described
above are connected with diodes in series so that current
cannot "back feed" through the lamps to maintain a circuit.
For further information on the hookup of these diodes

(or check valves) see the maintenance elementary drawings
of jumper board safety circuits. Note that all circuits

are not thus provided.

5.1.4 Jumper pin openings in safety circuits are distinguished

by their red color. The presence of a safety system (red)
A
Approved by~4¢7é%/L¢£%/”%W\,, 3H>-2
. —~ 8/6/65

5.1.4 (continued)
jumper is annunciated (MB-10, XA L4008-1) and also will
prevent entry into "operate' mode. If system is already
in "operate” mode, the insertion of a safety jumper will
cause system to go to "off." Other jumpers (block openings)
will not give an annunciation when inserted.

5.2 Use of Jumper Board
5.2.1 Although the jumper board is provided for flexibility

of operation it must be remembered that the use of Jumpers
violates the normal designed operational interlock func-
tions. The use of jumpers is under strict administrative
control. No jumper should be inserted without the per-
mission of the Operations Chief or Operations Department
Head.

5.2.2 To determine the condition of the circuits shown
schematically on the jumper board observe the white lights
located between contacts. The notations at all of the
contacts down to a particular lamp give the conditions
which must be met for the lamp to be on. If all white
lamps in a circuit are on the end condition lamp {(red,
green, or amber) will be on to signify the action or
condition notation at the bottom of the circuit. OSome
circuits give condition when de-energized — e.g. circuits
20 and 21 indicate fill restrict condition when de-ener-
gized. The color of indicating lamps is also of signifi-
cance. During power operation in RUN mode all RED lights
will be OFF, all GREEN lights will be ON, the AMBER
lights may be ON or OFF as required.

5.3 Other information displayed on the jumper board involves freeze
valves and instrument power circuits.

5.3.1 The freeze valve permissive lights on the lower jumper
board C#h) give indication of system conditions which would
allow thawing of the particular valve. Note that these
lights do not indicate permission to thaw from the stand-

point of the valve itself — i.e temperature of pot or
Approved by /Zgji&é2é?/rufi?\b 3H5-3

8/6/65

5.3.1 (continued)

5e3.

shoulders. For example — a permissive light on Jjumper
board for fill valves (FV-104, FV-105, FV-106) requires
that all transfer freeze valves be frozen and the AP
between tank and the FP be low. For a permissive light on
transfer valves requires that all fill valves be frozen,
the tank pressure low, and the reactor system be empty of
salt. For details on FV permissive lights see block
diagram D-HH-B-57331 or circuit diagrams for the individual
freeze valves.

2 The IPP (instrument power) lights on the lower board (#4)
indicate whether or not power is available to certain
circuits in IPP-1, IPP-2, and IPP-4. See Table 3H5.1

for listing of these circuits and what is supplied by them.
For details on these and other instrument power circuits

see Drawing E-HH-Z-41695.
Approved by _- s b “‘J:‘:tf.t./ M'h\,_ T
N able 3H5-1

8?6{?%?

INSTRUMENT POWER CIRCUITS INDICATED ON JUMPER BOARD #4

Panel No.

Fed by

Circuilt

Equipment On Circuit

IPP-1

IPP-2

IPP-4

4L8v oC

Y
MG- k4

or
TVA BUS 4

TVA BUS 3

N 2 o ©O© 31 O Fw oo

H W 0 3 v = w

Safety Circuits

Safety Circuits

Safety Circuits

Safety Circuits

Safety Circuits

Safety Circuits, Channel #3
Control Circuits

Control Circuits

FV-103, FV-104, FV-105, FV-106

FV-107, FV-108, FV-109
FV-110, FV-111, FV-112

FV-20k4, FV-206

AC#1, FORH#L, COPHL

AC #2, FOP#2, COP#2

Safety Circuits, Channel #1
Radiator Ioad Control
Control Rod Drives

Safety Circuits, Channel #2

Approved byfizfgzkéaé;/fiafivt 3H6-1
a4

9/14/65

6 OTHER INSTRUMENTS
6.1 Fql-569-A, Reactor Cell Air Bleed Line Flow Totalizer (Wet Test
Meter)

This instrument will be used to measure the amount of reactor

cell and drain-tank cell in-leakage by bleeding it off to the
containment stack. It is connected in parallel with line 565
which connects the component coolant pump discharge to the con-
tainment stack inlet. After the reactor and drain-tank cells
have been brought to the desired operating pressure, HV-565-C
will be closed and flow established through FgI-565-A to main-
tain the contaimment cell pressure within proper limits.

The instrument is an American Meter Controls, Inc. standard
precision,positive displacement, wet test meter with a capacity
of 5¢/min.

Tnit. Date/Time

6.1.1 Preparing the meter for use:
6.1.1.1 Level the meter by adjusting
the leveling screws at the base
until the bubble in the spirit
level 1s exactly in the center.
6.1.1.2 Fill the meter with distilled

water until the water level is
slightly above the tip of the

pointer in the gage glass.

6.1.1.3 Make sure all connections are
tight.
6.1.1.4 After the reactor cell leak

rate has been determined, open
HV-569-A  and HV-569-B

and close HV-565-C __ . Throttle
HV-569-B until the flow rate through
rotameter FI-569 is equal to the
Approved bx,422¢523f<fi%;¢£n¢n /ifi?éz
9 5

Init. Date/Time

6.1.1.4 (continued)
cell leak rate plus the cell nitro-
gen-purge rate. Cell leak rate
+ cell nitrogen-purge rate
= £/m through FI-569.

Pass the gas to be measured through

the wet test meter until the water
is saturated. At normal rates of
flow and room temperature, the
approximate time required is one
hour for a meter in which the

water or gas has been changed.

6.1.1.5 Disconnect the tubing leading
to the meter so that both inlet
and outlet are under atmospheric
pressure. Draw off water through
the small pet cock at the base of
the water line gage until the
center of the concave meniscus in
the gage glass coincides exactly
with the tip of the pointer. Usu-
ally this may best be accomplished
by viewing the pointer through a
magnifying glass from below with
the aid of a flashlight, if neces-
sary. The image of the pointer
will be visible on the underside
of the meniscus and the tip of
the image should just touch the
tip of the pointer when suffi-
cient water has been withdrawn.

6.1.1.6 Reconnect the tubing.

6.1.1.7 Place meter in service.

Approved by 4£é5;”

WK g pirn, 3H6-3
v of14/65

Init. Date/Time

6.1.1.8 For extended runs, the gas enter-
ing the meter should pass through a
saturator to prevent a change of lig-
uid level in the meter during the run.

Fill saturator with distilled water.

6.1.2 Reading the instrument:
6.1.2.1 One revolution on the large dial
is 1 liter. ©Subdivisions are 0.0l
liter. The totalizing dials read
10,000 liters, maximum.

AO,-566-A, Reactor Cell Oxygen Analyzer

The purpose of this instrument will be to monitor the oxy-
gen concentration in the reactor and drain-tank cell atmosphere
and to provide a means for calculating the containment cell
in-leakage. A bypass flow will bé circulated through the ana-
lyzer which is connected in parallel with line 566, the return
line from the reactor cell air-bleed line to the component
ccoling pump suction.

The instrument is a Beckman Instruments, Inc., model F3,
oxygen analyzer that continuously measures oxygen concentration
in gaseous streams based on the magnetic susceptibility of the
gas being analyzed. Two ranges, O to 10% and O to 25% are
provided; and the accuracy is claimed to be * 1% of full scale.

The general formula for calculating the leak rate is taken

from Section 3E 1.2 B(3) of the Operating Procedures:

Ty
_ 538 Py (Fo - F1) + 12 WFy |
Ly = £ (0.5 - Fa) £3/day

Y
Approved by agf”“?b/\/?tgffiffixfimh 3H6-k
i v 9/14/65

Fl and F2

il

oxygen analyzer readings at beginning and end of
test (fraction of oxygen in containment atmosphere)
L_ = Leak rate, ft3/day
P, = absolute pressure in containment at beginning of
test, psia
t = time duration of test, hrs
T, = absolute temperature at beginning of test, °r

W = evacuated gas rate at FqI-569-4, £t3/hr

6.2.1 Operating Controls
The instrument is provided with three operating con-
trols: the Range Switch, the Zero Control, and the Span
Control. The Range Switch sets the zero point of the
scale and the Span Control sets the span point, a reference
point at the opposite end of the scale from the zero point.
The setting to which the operator must turn the Zero Con-
_trol in order to establish a correct zero point (down scale
standardization point) depends on several factors, two of

the most important of which are the particular response
Approved byfiwg s
~ 9/14/65

6.2.1 (continued)
characteristics of the individual instrument and the mag-
netic susceptibilities of the various background gases in
the sample.

Similarly, the setting to which the operator must turn
the Span Control in order to establish a correct span point
(up scale standardization point) depends on several factors,
of which the one most subject to change is the pressure in
the analysis cell. This pressure can vary because of a
change in elther the pressure at which the incoming sample
enters the instrument or the pressure against which the
outgoing sample is discharged. If both Span and Zero Con-
trol adjustments are to be made, the zero adjustment must
be made first.

6.2.2 Reference Gases

For calibration, the instrument redquires two reference
gases -- a zero gas and a span gas -- each of accurately
known oxygen content.
6.2.2.1 Zero Gas

The terms "zero point” and "zero gas" as applied
to the analyzer, are used in a specialized sense. The

two terms, which relate to the electronic circuitry,

refer to the potential on the suspension. The zero
point is a reference point on that end of the readout
scale which corresponds t0o a potential of zero on the
suspension; the zero gas is a reference gas, the oxy-
gen content of which is such that this gas can be used
to establish the zero point. Note that the term "zero
point” is not synonymous with "zero-percent oxygen
point." Although in some instruments these two points
coincide, in others they do not. In this instrument,
zero voltage on the suspension corresponds to a read-
ing at the low endpoint of the scale.

The zero gas (nitrogen) used with this instrument

has an oxygen content of zero, or very nearly zero.
Approved byfli %‘;{Wflflg 3H6-6
</ 9/14/65

6.2.2.2 The Span Gas
The span point is set with a gas having a known
oxygen content. Clean dry air, which contains 20.93%
oxygen, is a convenient span gas; however, the span
gas that will be used was specially made up and ana-
lyzed spectrographically. This gas, which contains
4.82% oxygen, will be used to set the span point of
the analyzer.
6.2.3 Preliminary Procedure
Supply power to the instrument for 24 hours before
standardizing it. This warm-up period 1s necessary because
a reliable calibration can be obtained only after the ana-
lyzer has reached a stable operating temperature. Moreover,
the resultant elevated temperature will help to prevent
moisture from condensing in the analysis cell and damaging
it. After the instrument has reached operating temperature,
run gas through it until the reading ceases to drift.
Ordinarily, approximately one hour will be required.
Init. Date/Time

6.2.3.1 Close or check closed the follow-
ing valves:
HV-566-A1
HV-566-A2
Zero gas valve

Span gas valve

6.2.3.2 Instrument turned on at

6.2.3.3 At least 24 hours after the instru-

ment was turned on and with CCP No.

1 or No. 2 running, open or check open

the following valves:
HV-566-A1  HCV-566-A2
HV-566-A2  HCV-566-A3
HCV-566-A1  HCV-566-Ak%

Approved by/?%?fi%;;ééaéfguéw1
- v

Init.

3HG-T7
9/14/65

Date/Time

6.2.3.4 Set back-pressure regulator to

control at 1 atmosphere.

6.2.3.5 Close or check closed zeroc gas

and span gas valves.

6.2.3.6 Open or check open sample valve
_____, amalyzer bypass valve
and turn the 3-way valve (ahead of
analyzer FI) to sample gas position
Using sample valve and ana-
lyzer bypass valve, adjust flow of
sample gas to analyzer to 250 cc/min.

and 22 psia.

6.2.3.7 Pass gas through the analyzer
until reading ceases to drift, but
for at least one hour before taking

readings.

6.2.4 Calibrating Instrument
Calibration of the instrument con-
sists. of "two procedures, the zero-point
adjustment and the span-point adjustment.
6.2.4.1 Zero Adjustment
6.2.4.1.1 Close HV-565-A1 _ , the
sample gas valve  , and the

analyzer bypass flow valve

6.2.4.1.2 Set the range switch to

the lower range.

6.2.4.1.3 Open or check open
HCV-566-A3 , and -Ah
and HV-566-A2

6.2.4.1.4 Set back-pressure regula-

tor to control at 1 atmosphere.

6.2.4.1.5 Turn the 3-way valve to

the zero gas position , open
Approved by £2?¢524Céé;9n¢m_ 3H6-8
fi/

9/14/65

Init. Date/Time

6.2.4.1.5 {(continued)
the zero gas valve and
set the zero gas flow to 250

cc/min. at 22 psisa .

6.2.4.1.6 Allow zero gas t0 purge
the anelyzer for & minimum of
three minutes.

6.2.4.1.7 Set zero control so that

reading shown by recorder or
indicator is equal to oxygen
content of zero gas.
6.2.4.1.8 Close the zero gas valve.
6.2.4.2 Span Adjustment
6.2.4.2.1 Set the range switch to

the upper range if air is used
as the span gas, or to the lower
range if the special span gas is
used.

6.2.4.2.2 Turn the 3-way valve to

the span gas position __ , open
the span gas valve  and set

the span gas flow to 250 cc/min.
at 22 psia __

6.2.4.2.3 Allow span gas to purge
the analyzer for a minimum of
three minutes.

6.2.4.2.4 Set span control so that

reading shown by recorder or
indicator is equal to oxygen
content of span gas: 20.93 if
air is used, or 4.82 if special

span gas 1s used.

Approved by - Ay I /35?é9
M 9/14/65

Init. Date/Time

6.2.4.2.5 Close span gas valve.

6.2.5 Routine Operation
After standardizing the instrument,

run the sample gas through it at the same
flow rate at which the zero and span gases
were admitted. The instrument will auto-
matically and continuously record the oxygen
content of the sample:

6.2.5.1 Open or check open the following

valves:
HV-566-A1 _ HCV-566-A2
HV-566-A2 _ HCV-566-A3
HCV-566-A1  HCV-566-Ak

6.2.5.2 Close or check closed the zero
gas and span gas valves
6.2.5.3 Turn the 3-way valve to the

sample gas position , Open the
analyzer bypass flow valve y

and open the sample gas valve

6.2.5.4 Set the back pressure regulator

to control at 1 atmosphere.

6.2.5.5 Using the analyzer bypass valve
and the sample gas valve, adjust
the flow of gas through the analyzer
to 250 cc/min. at 22 psia.
6.3 PAE-RC-E, Reactor Cell Differential Pressure
Element (Hook Gage)

This instrument will be used to measure the differential

pressure between the reactor and drain tank cell and the four
reference volumes located in the cells for determining the
containment cell in-leakage. It 1s identified as an F. W.
Dwyer Mfg. Company No. 1420 transparent Hook Gage.

The general formula for calculating the leak rate is

taken from Section 3E 1.2 B(2) of the Operating Procedures:
i
Approved by 42552;/\f“fififiwfl1—'
~

_5.25 x 105 AP , 2k
R~ t T avg. t

short test time, where

L

L, = leak rate, £t3/day

= time duration of test, hrs

= nitrogen purge rate, £t3/hr

X 2k N £t3/day

3H6-10
9/1k /65

R
t
AP = change in pressure from beginning to end of test, psi
N
W

= evacuated gas rate at Fql-569-4, £t3/nr

T avg = average cell temperature, °R

Init. Date/Time

6.3.1 Close the valves to the reactor cell

and to the reference volumes.

6.3.2 Open the equalizing valve between

the two columns of the gage.

Be certain

no air is contained in the connecting

tube between the wells. Bleed by slightly

loosening the machine screw plug if nec-
essary.

6.3.3 Check level before using. Set both
micrometers at zero position.

6.3.4 Loosen both zero adjustment locking
rings and turn hook handles until both
hooks just dimple water suxrface.

(observing from below, the bright

Approved by { 2 %%mm ?Hi)él
O/14/65

6.4

init. Date/Time

6.3.4 (continued)

mirror-like surface of the water will

slightly distort at the moment of con-
tact, or the image of the pointer will
be visible on the underside of the me-
niscus and the tip of the image should
just touch the tip of the hook). Lock
zero adjustment rings, making sure both

micrometers still read zero.

6.3.5 Close equalizing valve and open the
valves to the reactor cell and refer-
ence volumes. Turn both micrometers
until each hook again dimples the water
surface. Read each micrometer, and add

the readings together:

left micrometer in.
right micrometer in.
total in.

A-Be-A-AD3, Beryllium Monitors

There will be two beryllium monitors in use, one in the
vent house, and one in the high bay. Although these will be
their normal locations, the monitors can be moved to other
areas if desired. The instrument located in the vent house,
designated the ORNL beryllium monitdr model 1, will be used
to monitor the air in the radiator stack when the reactor is
operating, and the coolant-cell atmosphere during maintenance
periods. This is a spectrographic monitor in which the air
being sampled is drawn through a spark which excites any
beryllium atoms whiéh are present. The resulting ultraviolet
radiation that is emitted is spectrographically analyzed for
the characteristic beryllium wavelength. The beryliium con-
centration in the air is displayed on a strip chart on the

instrument.
Approved by,¢¢??;524%22;/¢4fi,,\_ 3HH-12

7 9/14/65

The other beryllium monitor, a model Sa-103 made by the

National Spectrographic Laboratory, will normally be used in

the southeast corner of the high bay. Air is drawn into the

unit through

a filter paper tape that moves under the arc of

a spectrograph which analyzes the light emission for the char-

acteristic beryllium wavelength. The beryllium concentration

s integrated and recorded on a strip chart on the instrument.
6.4.1 ORNL Beryllium Monitor Model 1

6.4.1.1

General Precautions

6.4.1.1.1 Always assume that the air sampling sys-

6.4

6.k.

6.4,1.2

6.k,

6.4

6.k,

tem is beryllium contaminated. Use appropriate
caution.
1l.1.2 To avoid blowback of beryllium dust in
the piping system, never operate the auxiliary
air blast unless the sampling blower is on.
1l.1.3 Never leave the spark supply voltage on
unless spark discharges are occurring, as the
spark transformer may be destroyed.

Init. Date/Time

Operation
1.2.1 Check sample piping connec-
tions and exhaust piping connec-

tions for tightness.

.1.2.2 Connect the power cord to

a suitable source of 115 volt 60

cycle ac.

1.2.3 Check for adequate air
pressure by adjusting the regu-
lator to the rear of the right-
hand side of the left-hand cabi-
net. An indication of 1 - 2
scale divisions on the air pres-
sure gage above the regulator is
satisfactory. Use a mirror to

read the gage if necessary.

Approved by fla@,

Init.

3HH6-13
9/14/65

Date/Time

6.4.1.2.4 Turn "Power" switch on.
"Power On'" light comes on, samp-

ling and cooling blowers start.

CAUTION: Do not leave ailr on unless blowers are running.
6.4.1.2.5 Turn "Spark Power" switch
on. Spark starts, "Spark On"
light comes on, "Spark Transformer
Primary Current" meter indicates

3.0 to 3.5 ampeies.

6.4.1.2.6 Recorder starts inking.

6.4.2 National Spectrographic Laboratory
Model S2-103 Beryllium Monitor
6.4.2.1 Check tape mechanism to be sure

paper is not fouled.

6.4.2.2 Check sample piping connections
for proper installation, especially
the slipjoint above the tape advancing

mechanism.

6.4.2.3 Connect the power cord to a
suitable source of 115 volt 60

cycle ac.

6.4.2.4 Turn both standby switches to
"on" position, and turn master

switeh to "on" position.

6.4.2.5 After allowing the electronic
circuits to warm up (~ 2 minutes),
zero the instrument:
NOTE: If spark light is on, wait until it goes out
before proceeding to zero the lanstrument.
6.4.2.5.1 Turn black knob to "cali-
brate” position and zero the
meter with the potentiometer

marked "calibrate."

Approved by4?¢%§?%§?;/¢QW4 3H6-1h
& _fi/

6.5

9/114/65

Init. Date/Time

6.4.2.5.2 Depress zero check and
adjust meter to zero with
potentiometer marked "zero."

6.4.2.5.3 Reset black knob to

"integrate' position.

6.4.2.6 If filter-paper tape runs out,
place both standby switches in
"standby"” position.

6.4.2.7 If reload light is on, check

condition of filter-paper tape.
Reset by momentarily turning off

the master switch.

Cover Gas Oxygen Analyzer

A 100 cc/min. stream of helium cover gas is passed through
a Lockwood and McLorie, Inc. model 0-1000 oxygen analyzer to
determine the oxygen concentration in the cover gas. The
analyzer electrolytically determines the oxygen in the sample
stream by first reducing it according to the equation
Os + 2Hop + 4 e » LOH',
and then measuring the electrolysis current. The amount of
current is directly proportional to the oxygen concentration
in the sample and is indicated on a meter on the instrument.
6.5.1 General Precautions
6.5.1.1 The potassium hydroxide used in the various cells
of the analyzer should be handled carefully. After
the analyzer is in operation, the reagent is in a
pressurized system making the caustic even more
hazardous. Do not disconnect sample lines, cells,
or any fittings in the analyzer without first depres-
surizing the analyzer. Wear goggles or safety glasses
when handling the caustic. Flush with copious
amounts of water any areas of the skin, clothing,

or working spaces accidently brought into contact
Approved by zZEZQngfia,/finflzLi 3fi6-15

74 9/14/65

6.5.1.1 (continued)
with the reagent. Follow with a dilute acetic acid
or vinegar rinse.

6.5.1.2 The 1lid on the reagent tank should be kept on at
all times. The valve with the red handle at the
base of the prescrubber should never be opened when
the prescrubber is under pressure.

6.5.2 Operation
Init. Date/Time

6.5.2.1 Prescrubber Cell
6.5.2.1.1 Fill the stainless steel
reagent reservoir with about
1000 cc of 25% KOH solution.
6.5.2.1.2 Open toggle valve with
white handle. Then open toggle

valve with red handle. Observe
drain at bottom of analyzer case
or transparent plastic section

in drain line. When reagent is
observed flowing down the drain,
close valve with red handle, then
valve with white handle in that

order.

6.5.2.1.3 To change reagent after
analyzer has been in operation,
shut down analyzer by closing
off both the sample and reference
gas lines. Depressurize the sys-
tem by opening valve on the trap
at the lower left-hand side of
the analyzer. Open toggle valve
with white handle slowly, then
open valve with blue handle.

When the cell has been completely
Approved by 3H6-16
¥ - 9/14/65

Init. Date/Time

6.5.2.1.3 (continued)

6.5.2.2

drained, close valve with blue
handle. To refill, repeat pro-
cedure in above paragraph.

Set Up

After the performance checks have

been carried out as per the following

instructions, the analyzer can be

switched to the unknown sample gas.

6.5.2.2.1 Make certain drain valve

st the bottom of the 1/4" pipe
nipple trap on the left side

of the analyzer is closed.

6.5.2.2.2 Open valve in sample line

or reference gas line, if used,
on right-hand side of case. Open
this valve slowly. If the valve
is opened rapidly, the solution
in the cell may be blown forward
into the connecting lines and
flow control system creating a

maintenance problem.

6.5.2.2.3 Adjust the gas flow through

the analyzer to 300 cc/minute.

6.5.2.2.4 The recorder will be

reading off scale at this point
due to the high concentration

of oxygen in the analyzer. Reduce
the "Span Adjust" setting until

the recorder just comes on scale.

6.5.2.2.5 As the analyzer is gradu-

ally purged of air, the recorder

reading will decrease. The "Span
Approved by /fi_@%m_ ?HE;%7
9/14/65

Init. Date/Time

6.5.2.2.5 (continued)
Adjust" setting may at the same
time be increased if it is
desired.

6.5.2.2.6 After a period of time,

the recorder indication will
level out at some value repre-
senting the oxygen content of
the sample.

6.5.2.2.7 Reduce flow rate to 100

cc/minute and wait until recorder

again levels out.
6.5.2.3 Performance Check

Since under normal operating conditions, the ana-

lyzer performs in accordance with Faraday's law, the
following sensitivities can be expected at 1 atmos-

phere at 2500.

Flow Rate Sensitivity per ppm O
50 cc/min 13.15 Microamps

100 cc/min 26.3 Microamps

150 cc/min 39.45 Microamps

200 ce/min¥ 52.6 Microamps

250 ce/min¥ 65.75 Microamps

300 ce/min* 78.9 Microamps

*For samples containing more than 100 ppm Os, the ana-

~lyzer should not be operated at flow rates greater than
150 cc/minute in order to avoid appreciable deviation
from quantitative behavior. On occasion, certaln silver
electrodes may also deviate somewhat from gquantitative
behavior at lower concentrations with flow rates over
200 ce/min. while others will perform well up to 40O

cc/min. In a properly functioning analyzer, all
Approved bygfifiaf%éza}égfinmnx, 3E6-18
~N

9/1k4/65

6.5.2.3 (continued)
electrodes exhibit good quantitative behavior up to 200
cc/min. with gases below 100 ppm.
6.5.2.3.1 Span Adjustment

After the recorder has leveled out, the span
may be adjusted in accordance with the above sen-
sitivities.

Mo illustrate, if the flow rate is 100 cc/min.,
the sensitivity of the analyzer will be 26.3 micro-
amps per ppm Os.

With a 5 mv recorder and a desired full scale
range of 20 ppm, the adjustment of the span adjust-
ment pbtentiometer may be calculated as follows.
Substitute in Ohm's Law.

Where E = Recorder full scale range in volts
R

I = Desired full scale range in amps,
SmV__p oy (20 ppm x 26.3 microamps)
1000 1, 000, 000

or R = 9.5 ohms.

Resistance in analysis cell circuilt

Therefore

Since the span adjustment potentiometer is
25 ohms with a dial of 1000 divisions, 380 divi-
sions on the dial would be equivalent to 9.5 ohms
(0.380 x 25 = 9.5) or the resistance required to
give a full scale range of 20 ppm at a flow rate
of 100 cc/min. Similar calculations can be made
for other ranges and flow rates or see Appendix

II for different ranges. Therefore,

ua = bscale L o 103

span
6.5.2.3.2 Zero Check

The above span adjustment does not take into
account the zero or background current of the

instrument. Normally, this zero or background
Approved by %/M— 3IH6-19
V 9/14/65
6.5.2.3.2 (continued)
amounts to about four to six microamps and may be
disregarded except in the most critical applica-
tions.
The zerc or background of the instrument may
be checked as follows:
The method is based on the fact that when
no gas is flowing through the instrument, there
should be no output from the cell. When no gas
is flowing, any reading on the recorder then is
the zero or background of the instrument.
Init. Date/Time

6.5.2.3.2.1 Set the recorder
span adjustment at 380 (20
ppm, or 760, 10 ppm).

6.5.2.3.2.2 Place a tubing cap
over the vent of the ana-
lyzer or close shut-off
valve in the vent line if

provided.

6.5.2.3.2.3 Even through the
flowmeter reads zero,
there still may be appre-
ciable flow through the
electrode to give a false
zero. Sufficient time
should be allowed for the
pressure to equalize on
both sides of the silver
electrode.

6.5.2.3.2.4 Leaks may also

cause false or high zero
readihgs in that they will
permit a flow through the
Approved byf/‘/’%'%/mm - 3H6-20

9/14/65

-

Init. Date/Time

6.5.2.3.2.4 (continued)
analysis cell even though
the analyzer is apparently
shut down.

6.5.2.3.2.5 The analyzer should
not be left without gas
flowing through the analysis
cell for any appreciable
length of time as the silver
electrode may become plugged.
The flow should only be closed
off sufficiently long to
accomplish a suitable no-
flow zero and then returned
to normal operating condi-

tions.

6.5.2.3.2.6 Occasionally, after
the zero has been checked
by the no-flow method, the
analyzer will become noisy
when returned to its normal
operating conditions. This
noise can usually be removed
by setting the flow rate to
a maximum for a short period
and then returning it to its
normal flow rate. 1If the
noise does not disappear,
after several hours, it means
the electrode has become
plugged and will require

cleaning or replacing.

9/14/65

Approved'byhgzéfiéigéiéfifgfiaafln 3E6-21

Init. Date/Time

6.5.2.3.2.7 If a suitable zero
is not obtained, consult
the procedures to follow
under trouble shooting,
Section 6 of the manufac-
turer's instruction book.
6.5.2.3.3 Sensitivity Check

The sensitivity of the ana-

lyzer may be checked by use of
the coulometric generator which
will add oxygen to the sample
stream.
6.5.2.3.3.1 The span of the ana-
lyzer should be adjusted so
that the full-scale range
of the instrument is at
least 10 ppm greater than
the oxygen content of the
sample or reference gas.
It is preferable to use a
reference gas of stable
oxygen content rather
than the sample. Set
flow rate at 100 cc/min.

6.5.2.3.3.2 Turn coulometric
generator switch to the

on position.

6.5.2.3.3.3 Set the coulometric
generator adjustment so
that the meter on the con-
trol box reads 263 micro-
amps, the equivalent of

10 ppm.

Approved by&§;25;5%¥§%294%qfih
Vv .

6.5.2.4
6.5

6.5.

Init.

3H6-22
9/1L4/65

Date/Time

6.5.2.3.3.4 Within a minute
the reading on the recorder

will begin to rise.

6.5.2.3.3.5 Allow the recorder
to level off.

6.5.2.3.3.6 The point at which
the recorder levels off
should represent about 80%
of the calculated amount
of oxygen that was added
by the generator. In
other words, the recorder
will only increase about
8 ppm above the analysis
of the sample or reference

gas.

6.5.2.3.3.7 If the recorder
shows only a corresponding
rise of less than 5 ppm or
50%, see Section 6, on
trouble shooting, and Sec-
tion 6.2, Loss of Sensitivity,
of the manufacturer's instruc-

tion book.

Analysis of Sample Gas

.2.4,1 After the above zero and

sensitivity checks have been per-
formed and familiarization is
gained with the operation of the
analyzer, the analyzer may be

shifted over to the sample line.

2.4.2 The reference gas valve
should be shut off and the wvalve

in the sample line opened slowly.

TRy s
Approved by 7 =fl;{¢y;%fl% ?Hfi;é3
» 9/14/065

- - Init. Date/Time
6.5.2.4.3 Even though the sample

may contain & low amount of

oxygen, chances are the ana-
lyzer will run off scale
because of atmospheric oxygen
in the sample line. This will
eventually purge out of the

- system and the recorder will
level out at a point representing
the analysis of the sample stream.

6.5.2.4.4 The span of the recorder

should be set at the desired

level following the procedure
outlined in Step 6.5.2.4 or by
refering to the table in Appendix
IT of the manufacturer's instruc
tion book. In critical applica-
tions, the zero can also be
compensated for either by deducting
the zero from the final analysis

or by compensating for the zero

in making the span adjustment.

6.6 Cover Gas Moisture Analyzer

A 100 cc/min. stream of helium covergas is passed through
fi Manufacturers Engineering and Equipment Corporation (Meeco)
model W electrolytic moisture analyzer to determine the mois-
ture concentration in the cover gas. The moisture 1s absorbed
from the gas stream flowing through the electrolytic cell and
an electrolytic current is established. This current depends
on the rate of absorption of moisture and 1s directly connected
with decomposition of this moisture. The decomposition prod-
ucts, hydrogen and oxygen, are carried off in the gas system.
The metering circuitry is arranged so that the meter reads

in parts per million by volume of moisture in the gas stream.
Approved byz;?fiizééfiiyffikmq 3H6-24

9/14 /65

Init. Date/Time

6.6.1 Operation

6.6.

6.6.1.1 Adjust the sample flow depending

on which meter is in use as follows:

Meter Sample Inlet Flowvmeter
Number Pressure, psig Setting
157 ---- 95
1764 0 102
1764 10 70
1764 20 53
176k 30 43

6.6.1.2 Turn the analyzer power switch
on and set the range switch to the
maximum range position. For standard
range operation, this is 1000 ppm.
An off-scale indication will occur
during the initial dry-down period.
This is normal. Leave the power

switch on.

6.6.1.3 Depress the power check test
button and note that the power
supply is 70 £ 5 volts.

6.6.1.4 Depress the cell check test
button and note that the cell

voltage is >2 volts.

2 Reading the Instruments

Since the analyzers are presumed to
operate in accordance with Faraday's law,
the reading is directly proportional to
the mass of water passing through the
cell per unit time. If C = concentration

of water, F = sample flow, and I = current
Approved by%{({bfip&. 3H6-25

9/14/65

6.6.2 (continued)
or meter reading, the I = KCF, where K incorporates all
necessary conversion factors. If F, sample flow, is main-
tained constant, the reading is directly proportional to
the concentration. This is the normal mode of operation
since concentration in ppm H-O may be read directly only
when a constant flow is maintained. The range of the
meter may be varied by varying the sample flow rate:
assume the moisture level 1s constant at 500 ppm with the
range set on 0-1000 and a normal flow of 100 cc/min.;
the reading would be 50% of full scale. Now assume that
the flow is cut to 50 cc/min. The throughput of water
would be 1/2 as much and the reading should drop to 25%
of full scale. Since the moisture content of the gas
did not change, the full scale range would then be four
times 500, or 2000 ppm. Thus, the actual full scale

range is inversely proportional to the fiow rate:

100
actual flow rate’

actual range = indicated range x

where indicated range means the range at 100 cc/min.
For example, if the range is set at 1000 an d the flow

is set at 10 cc/min., the actual range would be
100
1000 x 0 = 10, 000.

Changes in ambient temperature usually affect the reading

because of disturbance of the absorbed moisture eguiiibrium.
Approved by af'yfiwjflyiigf P b, ‘ 3I-1
v 10/18/65

31 FREEZE VALVE OPERATION

Isolation of the salt in the MSRE drain, circulating, and process-
ing systems is controlled by freezing a short plug of salt in a flattened
section of 1 1/2" pipe called a "freeze valve." A combination of cool-
ing air piped to a shroud attached to the flattened section of pipe and
electrical heaters adjacent to the freeze valve is used to freeze or
thaw the valve. Siphon break pots are provided on one or both sides of
the freeze valves to prevent blowing all the salt out of the valve
during transfers and drains.

The electrical heat is manually controlled for the desired condi-
tion. The coolant air is automatically switched between "off," "hold"
and "blast" condition by temperature moduler or switches which obtain
signals from thermocouples attached to the center or either shoulder
of the freeze valve, In the "thaw" condition, all air is turned off.
In the hold condition,sufficient air is supplied to the valve to keep
it frozen. On FV's 104 and 107 through 112, the amount of air is manu-
ally adjusted using HIC's which throttle the cooling air valves. On
FV's 103, 105, 106, 20k and 206, temperature indicator controllers are
provided which regulate the "hold" cooling air to maintain a constant
freeze valve shoulder temperature. The temperature setpoint is manually
adjustable. When the temperature controller is in the manual position,
it functions like the HIC's on the other freeze valve.

1 DEFINITIONS & CRITERIA

1.1l Deep Frozen

When a freeze valve is deep frozen, the cooling air will
be turned off and the salt frozen by lowering or turning off
the electrical heaters.

Fluorine evolution can occur if salt which is in a high
radiation field is cooled below L00°F. Therefore FV 10k
through 109 will be maintained above this temperature. The
upper limit has been arbitrarily set at about 600°F.

Freeze valve 103 is emptied completely during a drain and

therefore can be cooled to ambient temperature. Freeze valves
Approved by ,;fifir”jV,%/QifhbmuMM 31-2
W/

-
Teenth

2

10/18/65

1.1 (continued)
110, 111, 112, 204 and. 206 can also be cooled to ambient
temperature since they are located in cells having less
radiation.

l.2 Frozen

Freeze valves are considered frozen when the heaters,

cooling air and temperature controllers have been adjusted S0
that a frozen plug exists and turning off the cooling air
will thaw the valve. Freeze valves 103, 204 and 206 have an
additional requirement that they must thaw within 15 minutes
if electrical power fails.

1.3 Thawed

A freeze valve is considered thawed when all portions of

_it are.above the freezing poiht of the salt. 1In general, the

heaters will be on and the cooling air off.

BASIC OPERATION. AND INTERLOCKS

2vi---Ereeze

On each freeze valve, modules 1Al, 1AZ2, 3A1 and 3AZ are
in circuits which control the cooling air flow to the valve.
If the freeze valve is in the normal thawed condition and
the manually operated valve switch is set to freeze, the green
light at the switch on the main control board will start
flashing. The red light will also be on until the center
valve temperature drops to Module 2A1 setpoint (~ 1000°F).
Whefi switched to freeze blast air flow will come on and stay
on until £he both shoulder temperatures drop to Module 1Al
and 3Al setpoints (~ 7509F). At this point Module 1Al and
3A1 open circuits which stops the high air flow but lets the
hold air flow to continue. The green light will be on steady.

- As each shoulder temperature decreases below 85OOF, its module

green light comes on and the amber light goes off. Hold air
flow will be automatically regulated to maintain the preset
temperature on FV 103, 105, 106, 204 and 204. On other freeze

valves, the hold air is adjusted manually.
Approved by __ ;?ifi%%%§?17324afi\ 31-3
" 10/18/65

2.1 (continued)

If the valve shoulder temperatures continue to decrease
to ~ 6500F, either module 1A2 or 3A2 with either 1Al or 3Al1
will stop all air flow, and the amber module light will be on
until the temperature increases to above this setpoint.
Temperature above ~ BOOOF will actuate the 1AL or 3Al module
and turn on the high air to prevent valve melt-out. The
green light will start flashing. Either module can actuate
the high air mechanism and the air will continue on until both
shoulder temperatures decrease to normal conditions.

Modules 1Al and 3A1 have ~ 50F hysterisisj;and therefore,
if the air flow is adjusted to hold the shoulder temperatures
between ~ 650 and 800°F, no alarm or control action should
occur. For a control action to be initiated by a freeze valve
requires that a combination of 2 modules be in alarm - either
3A1 and 1Al, 3Al and 2AZ2, or 1Al and 2AZ.

2.2 Thaw Operation

When the manual operating switch is turned to thaw, all
air to the valve is cut off, the red indicating light starts
flashing, and the green light is on until both shoulder tem-
peratures reach approximately 8OOOF (Modules 1Al and 3A1).

When the 2A1 module thermocouple reaches the setpoint
(~ 1000°F), the red light at the freeze valve switch will
stop flashing and be a steady red.

. 2.3 Additional Interlock

In addition to the FV control modules, interlocks are

provided to prevent thawing when the syphon break (pots) or
vertical pipe on either side of the freeze valve are below
lOOOOF and when there is excessive AP between the drain tank
and the circulating system.
3 OPERATION OF FREEZE VALVES
3.1 Adjustment and Startup
A1l freeze valves can be adjusted so that turning the

freeze valve switch on the main board is all that is necessary

Approved by ffifjfiffigqflw,wzmfim 31-4

Vi 10/18/65

3.1 (continued)

3.2

to change from normel thawed to normal frozen position or
from normal frozen to normal thawed position. To accomplish
this, the heaters are first adjusted to obtain desired tem-
peratures with the freeze valve in the thawed position, The
freeze valve control is then switched to the freeze position
and the air flow controllers set to control the desired tem-
peratures. (For details see L4I.) |

Normal Operation of Freeze Valves.

During reactor shutdowns, salt transfers or additions may
be made. The transfer freeze valves, FV 107 through 112,
will be adjusted as described in 3.1. Thawing or freezing will
be done using the freeze valve switch. After a transfer and
prior to freezing a walve, it will be necessary to adjust
differential pressures to assure that salt is in the flat
portion of the freeze valve. Detalls of this are covered in
other sections of this report. During shutdown periods,
FV 103 through 106 and 204 and 206 will be deep frozén,

During a startup, F¥ 103, 104, 204 and 206 will be thawed
to allow filling the reactor and coolant system. FV 105
through 112 will be deep frozen. During circulation of flush
and coolant salt, FV 103; 204 and 206 will be in the normal
frozen condition. After the.flush salt is drained, FV 10k
will be deep frozen. FV 105 or 106 will be thawed to fill
the fuel system with fuel salt. After filling and during all
fibfié£ p§éfétions; FV 103, 204 and 206 will be normally
frozen, FV 105 and 106 will be thawed, and FV 107 through
112 will be deep frozen.
Approved by M@m 37-1
7/27/65

3J LIQUID WASTE SYSTEM

The liquid waste system is designed to accumulate and dispose of
radicactive aqueous waste material, Facilities are provided for sampling,
diluting, neutralizing, and transferring these to the Melton Valley waste
handling system. This system is also used for clarifying the shielding
water used in the decontamination cell and tank.

Waste handling procedures are given in the following sections.

1 JETTING REACTOR CELL AND DRATIN TANK CELL SUMPS

Any water which accumulates in the sumps of the reactor or drain tank
cells is removed by air jets which discharge to the liguid waste storage
tank. These jets are permanently mounted in the drain tank cell. Pumping
is started by simultaneously opening the air supply valve and alr operated
discharge valves. The operation must be well coordinated because opening
either air supply or jet discharge valves prematurely allows air to be
blown or sucked into the cells which are normally below atmospheric
pressure.

The sumps would be jetted as part of the reactor startup procedure
if there is any liquid in them and during operations whenever a high
gump level is indicated. The procedure requires two technicians. Details
are given below:

1.1 To Jet the Reactor Cell Sump to the Waste Tank

Init. Date/Time

(Transmitter Room)

i1.1.1 Record sump level, LIA-RC

1.1.2 Record waste tank level LI-WT

(Remote Maintenance Practice Cell)

1.1.3 Check that waste blower is on.

(Water Room)
1.1.4 Open block valve, V-332A.

1.1.5 Adjust PCV-332 to 30 psig.

1.1.6 Open V-332C and blow out any accumu-
lated moisture. Close V-332C.

-2
7/27/6

Init. Date/Time

1.1.7 Jet sump by simultaneously opening
V-332B (water room) and FCV-333A1 and A2
(HS-333A1 in Pos' 4. TB 9). . = The two
operators should be in contact by the
intercom system and should notify the
control room when jetting is started and

stopped.

1.1.8 Stop jetting when LIA-RC reads zero or
when PI-332 pressure drops or fluctuates,
indicating loss of liquid suction. Close
V-332B and then immediately close FCV-333A1
& A2 (HS-333A1 in Pos. 2 TB 9).

(Transmitter Room)
1.1.9 Record levels LIA-RC , LI-WT

1.2 To Jet Drain Tank Cell Sump to the Waste Tank

(Transmitter Room)
1.2.1 Record level of LIA-DIC

1.2.2 Record level of LI-WT

(Remote Maintenance Practice Cell)

1.2.3 Check to be surerwaste blower 1is on.

(Water Room)
1.2.4 Open valve V-3324.

1.2.5 Adjust PCV-332 to 30 psig.

1.2.6 Open V-332C and blow out any accumu-
lated moisture. Close V-332C.

1.2.7 Jet sump by simultaneously opening
FCV-343A1 & A2 (HS-343 Al pos ‘4 TR Panel
9) and V-342 (in water room). The two
operators should be in contact with each
other on the intercom system, and should
notify the control room when jetting is

started and stopped.

2 Ve
Approved byfl«f Ve

Init.

3J-3
T/27/65

Date/Time

1.2.8 When pump is empty, as indicated by
zero level on LIA-DTC, or fluctuation in
pressure of PI-332 (PCV), stop jetting
by closing V-3L2 and immediately close
FCV-343A1 and A2 (HS-343 Al Pos. 2).

(Transmitter Room)

1.2.9 Close air supply valve, V-332A

1.2.10 Record time and level of
LTA-DTC.

1.2.11 Record level of LI-WT

2 SAMPLING REACTOR AND DRAIN TANK CELL SUMPS

The reactor and drain tank cell sumps are sampled

during Jjetting by bypassing the flow from the jets

through a sample bomb attached to lines 334 and 3hbL.

Details are given below:

NOTE: Protective clothing, rubber gloves, and a face
shield shall be worn during the sampling. All
sampling operations shall be monitored by In-
dustrial Hygiene and Health Physics personnel.

(Remote Maintenance Practice Cell)

2,1 Attach a liquid waste sampling bomb between
lines 334 and 34k.

2.2 Open V-334 and 34k,

(Transmitter Room)
2.3 Set valves to sample sumps as follows:

2.3.1 To sample Reactor sump, open FCV-333A1
and close FCV-33342 (HS-333A Pos. 1) and
open FCV-343A2 (HS-343A1 Pos. 3) and keep it
open while jetting reactor cell sump as

given in 3J-1.1.

Approved pyzgfifjéafigfiééz)zay 3J-4

7/27/6
Tnit. Date/Time

2.3.2 To sample drain tank sump, open FCV=343A1
und ; close FCV-34342 (HS-3L43 A-1)Pos 1 and
open FCV-333A42 (HS-333 A-1 Pos 3)and keep it
open while jetting Drain Tank cell sump

as given in 3J-1.2.

(Remote Maintenance Practice Cell)
2.4 When jetting is complete close V-334 and 3kk,

and bomb. valve.

2.5 Cautiously remove sample bomb. Catch drip-
pings and put these into the liquid waste

~storage tank. Have Health Physics coverage.

3 JETTING AUXILTIARY CELL SUMPS

The sumps in the fuel processing cell, equipment

storage cell, liquid waste cell, and spare cell have steam
jet pumps for the transfer of liquid to the waste tank.
Each of these sumps will be emptied when a high level
for that sump is annunciated. All process cell sumps
have a common annunciator on the main control board
(XA 4000-1) and individual indicator lights in the
auxiliary control room (XA 4029) which can be deacti-
vated to clear the common alarm. Details of jetting
these sumps are given below.
(840 Level)

3.1 Open V-311 at the 60-psi steam heagder.

3.2 Record name of cell sump level
and liquid waste tank level (see
table below).

3.3 Open jet supply valve (see table below).

3.4 When jetting is complete, close jet supply

valve.

3.5 Record sump level and liquid waste

tank level
:,’J e ’ ///, .
Approved bxfigfigfi”fi/\g;i}f”fifl\

3J-5
7/27/65
Cell Level Indicator Jet Supply Valve
Fuel Processing LIA-FSC V-321
Equipment Storage LIA-SC V=317
Liquid Waste LIA-WTC V-315
Spare LIA-TC V-319

Y BUILDING SUMP OPERATION
The main building sump, with a bottom at the 812-ft level, is

accegsible from the pump room located below the Special Eguipment™
Room. The sump serves the building floor drains and French drains.
There are two 1-1/2 hp sump pumps which are started and stopped auto-
matically by integral float level switches. One starts pumping when the
water level reaches 815' 8" and the other 816 ft. elevation. A start
switch located at Col. C-9, 852-ft level, must be on to activate both
sump pumps. Normally no operator action is reguired. A high sump level
will be alarmed, IA-PRS-A, at 818 £t 6 in. elevation. This alarm can
indicate pump trouble, pumps off or just insufficient pumping capacity.
The sump alarm is connected to the common alarm, XA L000-1, on the main
control board with the cell sumps and individual indicator module on
XA 4029 in the ACR. A switch activates a high coolant cell sump level
alarm and energizes a solenoid valve, ICV 809 to a 1 in. steam jet lo-
cated in the coolant drain cell at elevation 818' 6". This jet takes
suction from coolant drain cell sump which has a bottom elevation of
817 ft., and is connected to the building sump at the 818 ft. elevation.
The float level switch turns off jet when level drops to the 818 foot
elevation.

The steam supply is through V-309 at the 100 psi steam reducilng
station, north of the filter house. The Jjet discharges to the sewer in

the west tunnel. No level indicator is provided.
Approved by,fgéffizigéééfifl““”\ ) 3ié6
/27

5 PIT PUMP OPERATTION

The pit pump, located inlthe pump room, is used to transfer water

from the 55-gal. tank in the pump room to the waste tank. The 55-gal.
drum receives water from the ventilation stack and filter pit, and may
be contaminated. A transfer should be made whenever an alarm occurs on
LAPRT (XA 4029). To transfer, open valves V-SD and V-326 in the pump
room and close V-325 and V-330. Start the pump from Col. C-9 on the
852-ft level. The pump should be stopped when the transfer is completed.
If a large quantity of water accumulates in this tank and a radiation
survey indicates no activity, the water can be pumped to the catch basin
by closing V-326 and opening V-330. If activity is found in the main
building sump, the pit pump can be used to pump from the sump to the
waste tank by closing valve V-SD and opening V-325 and V-326. The pit
pump can be used to empty the reactor cell annulus or the charcoal bed
cell into the catch basin by V-330 and either V-329 (RC annulus) or V-328
(CB cell).

If the water is contaminated 1t éan be pumped to the waste tank by
opening V-326 and closing V-330.
6 TREATMENT AND DISPOSAL OF WASTE TANK CONTENTS

The general procedure for handling the contents of the waste tank

will be to circulate and sample contents, dilute if activity is too high
(>5 curies/gal.), adjust pH to >T by caustic addition, mix thoroughly,
resample, and transfer to Melton Valley Waste Station.

| Tnit. Date/Time

6.1 Circulation and Sampling of Waste Tank Contents

(Remote Maintenance Practice Cell)
6.1.1 The following valves should be closed
or checked closed.
Vv-302 , V-305A ___, V-303B
V-305B ____, V-307

6.1.2 The following valves should be opened
or checked open.
V-300 , V-301

6.1.3 Check waste blower on

Approved by4§5¢32flgé%7fl”H7VL 307

7/27/6
Init. Date/Time

6.1.4 Start waste pump . Check waste

pump area for radiation.

6.1.5 Throttle V-301 until PI-305 reads
35 psi.

NOTE: Operator should wear protective clothing and face
shield and have a health physics survey during
sampling. |

6.1.6 After circulating the waste tank con-
tents for one hour or more, carefully
flush 1 liter through the sample line,
and take two 200-cc samples at V-305B.
Take samples approximately 30 minutes

apart.

6.1.7 Submit to the laboratory for total
activity (millicuries/cc), pH, and vol
of 0.1N NaOH to neutralize 100 cc of

sample.

6£.1.8 Put flush back into the waste storage

tank via the caustic addition funnel.

6.2 Dilution of Waste Tank Solution

If the waste tank sample analysis for total
activity is >1.3 millicuries/cc, dilute the con-
tents by the following procedure.

(Transmitter Room)

6.2.1 Record LI-WT level,  ft =V,

gal.

6.2.2 Calculate final vol = Va(ft) =

V,C, {analysis)
1.3 millicuries/cc

Vo = ft.

(Remote Maintenance Practice Cell)

6.2.3 Stop waste pump.

Approved byzflgégggzgg%éy@flflml ) 3§é8
1/27/65

Init. Date/Time

6.2.4 Close the following valves:
v-300 _  , V=302 ____, V-303B ___ ,
V-305A , V-305B ____, V-306

6.2.5 Open the following valves:
V-306A ., V=307 = , V-301

(840 Ievel, North End)
6.2.6 Open V-819 to start process water

addition.

6.2.7 Close V-819 to stop water addition
when LI-WT indicates the proper increase

in level,

(Transmitter Room)
6.2.8 Record LI-WT = ft. (Vo).

6.3 Neutralization of Waste Tank Solution

If neutralization is necessary, proceed as

follows:

6.3.1 From sample analysis, calculate pounds
of NaOH to neutralize contents of waste
tank as follows: 3.5 x 107% XY = 1b of
NaOH to add. Y = vol of liquid in waste
tank, gal. X = vol of 0.1 NaOH to

neutralize 100-cc sample.

(High Bay)

6.3.2 Dissolve NaQH calculated above in
water and add to waste tank through funnel
in the high bay (L-339). Wear face
masks, rubber gloves, and rubber apron

while handling caustic,

6.3.3 Rinse out line 339 with water fol-

lowing caustic addition.

6.4 Resampling

If neutralization is not necessary circulate

and sample waste tank per Section 6.1.

Approved by Wm / 3:} é9
T7/27/65
Tnit. Date/Time

6.5 Transfer to Melton Valley Waste System
6.5.1 Call Melton Valley Waste Station

(Telephone ) and report

activity, pH, and volume to be pumped.

6.5.2 When permission to transfer is ob-

tained, set valves as follows:
(Remote Maintenance Practice Cell)

V-300 open
V=301 closed
V-302 closed
V-303B closed
V-305A closed
V-305B closed
V~-307 closed

(Transmitter Room)
6.5.3 Record WT level

(Remote Maintenance Practice Cell)

6.5.4 Start the waste pump.

6.5.5 Throttle V-305A to give flow acceptable
at Melton Valley Waste Station. PI-305
should not exceed psig. OSee curve

in calibration book.

6.5.6 When desired amount has been trans-

ferred, stop pump.

6.5.7 Close V-300 and 305A.

(Transmitter Room)

6.5.8 Record waste tank level

7 CLARIFICATTION OF DECONTAMINATION TANK OR DECONTAMINATTION CELL LIQUID

A waste filter has been provided to clarify the water in the decon-

tamination tank (or cell) to improve visibility for inspection or under-

water repairs.
NOTE: This is a sand and gravel filter and should not be used to filter

acid solution.
Approved bxfi¢£?fi2%5€%%? re

Init.

3J7-10
7/27/65

Date /Time

To clarify water in the Decontamination Tank (Decon-

tamination Cell valves in parentheses) proceed as

follows:

(Remote Maintenance Practice Cell)

f.1
7.2

(High Bay)

Check that the waste pump is off.

Check valves as follows:

306C (or 306D) closed
3034 (or 304) closed
306D (or 306C) open
30k ( or 303A) open

(Remote Maintenance Practice Cell)

7.3

7.4

7.5

7.6

301 closed

300 closed

305A closed
305B closed
302 closed
306A open
307 copen
306B open
303B open

Start waste pump. Adjust flow to 30 gpm
on FI-306 by opening V-302 and throttling
V-307. (Check periodically and keep flow
adjusted to 30 gpm.)

Record pressures of PI-302 PI-306
Record AP (PI-302 minus PI-306)

(<5 psi).

Upon completion of filtration or when filter

AP 2 5 psi, stop the waste pump.

Close the following valves:
V-302 _ , V-303B _____, V-306B ____
V-306A , V-307

Approved b)fl&%fi,w 37-11
7/27/65

Init. Date/Time

(High Bay) |
T.7 Close V-306D , (Vv-306C),
v-304 (V-3034)

8 BACKWASH OF THE WASTE FILTER

Use process water to backwash filter to waste
tank. Proceed as follows:
(Remote Maintenance Practice Cell)

8.1 Close the following valves:

V-300 , V-305A , V-305B s
V- 306A , V-307 , V-308
8.2 Open V-302 , V=301

(Transmitter Room)

8.3 Record LI-WT.

(841 Level, North end)
8.4 Open V-819 very slowly (2 to 5 min) until
PI-819 reaches 15 psi. Check AP of PI-306-
PI-302 <6 psi = (~ 140 gpm).

(Transmitter Room)

8.5 Check rate of level increase on LI-WT

(Remote Maintenance Practice Cell)
8.6 Catch a sample at V-305B every 5 minutes.
(Flush sample line before sampling. Add
flush to waste tank via the caustic

addition funnel in high bay.)

(840 Level, North End)
8.7 When sample is clear, or after 15 minutes
of flushing, start closing V-819. Take 2
to 5 minutes to close V-819 to allow filter
bed to settle slowly.

(Remote Maintenance Practice Cell)

8.8 Close V-302 , V-301

Approved by fi\%:k.fl. /w}%e
T/27/605

9 GENERAL DECONTAMINATION AND CLEAN UP
Periodically the building should be checked for contamination by

health physicists and industrial hygienists. When radiocactive contami-
nation or beryllium is found, the area should be isclated and marked.
A survey should be made to determine source of contamination or beryl-
lium. A cleanup should be started as soon as practical. Where water
will not demage equipment in the area, plenty of hot water, detergent,
scouring powder or soap should be used to scrub the area. Then the
area should be rinsed. This procedure should he repeated as necessary
until the area is approved by health physics.

Caution should be used to prevent spread of the contamination.
Contaminated or beryllium containing water should be put into the
liquid waste storage tank through the caustic addition funnel in the
high bay.

Electrical equipment, instruments, and panels containing equipment
which cannot be wetted, should be wiped clean with damp sponges and
detergent or scouring powder and followed by a damp sponge rinse. Many
repetitions of washing and rinsing may be required. Used sponges, etc.
should be put into the hot Dempster Dumpster or hot cans provided.

Equipment having porous coverings, such as insulation which would
absorb moisture should be cleaned, using an approved vacuum cleaner.
When possible the air from the vacuum cleaner should be discharged into

a ventilation duct.
Approved by _ 7 ':-'-‘,;{"’f;\, J:"-/«M/z‘.-fi\\_ 3K-1
9/28/65

3K Be MONITORING SYSTEM

The Be Monitoring system consists of four units which take air
samples from various areas of the MSRE facility and the Be concentration
in the sample is determined. The operation and maintenance of this
system is the responsibility of the IH (Industrial Hygiene) Department;
however, the operations group will provide assistance as described in
the following parts of this procedure.

1 GENERAL BUILDING AIR SAMPLING SYSTEM

1.1 One of the units consists of two alr pumps, only one of which

is in operation at any one time, with 15 sample points connected
to it. The sample points are located as shown on dwg. D-ZZ4-Z
56399. Each has a paper-type filter which removes the par-
ticulate matter from the air sample drawn through it. The
filter is removed and analyzed for Be periodically by the IH
Department. The MSRE Operations personnel will check the air
pumps periodically to assure that one is operating and pulling
a vacuum of ~ 1.8" Hg. If the pump has stopped, the standby
pump will be started and the IH Department informed of the
failure. A low vacuum (<1.8" Hg.) would indicate an open
line on the pump suction side or the pump is not operating
properly. In this event the operating pump will be stopped,
the standby pump started and the IH Department notified. If
the trouble can be corrected by personnel available when it
is discovered, it will be done. This pump becomes the standby
pump when the trouble is corrected.

2 VENTILATION SYSTEM AIR SAMPLING

2.1 The second unit consists of a small air pump with the single

sample point. It also uses g paper-type filter to collect

the particulate matter and takes the air sample from the main
building ventilation duct upstream of the filter pit. It is
operated in essentially the same manner as the 15 sample point
system. Since there is no standby pump, any trouble developing

will be corrected as soon as it is practical. The IH Department
”

0}
Approved by ;i;;%éé&’yfiV}%bfifi 3K-2
| v

9/28/65

2.1 (continued)

will be notified of any difficulties developing.

3 NSL Be AIR MONITORING UNIT

3.1

The third unit consists of an NSL. Be Air Monitor. This instru-
ment collects an air éample from the duct upstream of the venti-
lation filter pit and makes an éhalysis for Be concentration
once per:fiour automatically. fl.local alarm occurs if the Be
concentrétion is >2 ug/m3. fi%erations personnel will check
the instrument periodically énd inform the IH Department as
soon as possible if an alarfirhas occurred due to a Be level.

If the alarm is due to insqfument trouble and the shift instru-
ment mechanic cannot correét it, the IH Department will be
informed as soon as possibie if it occurs between the hours

of 0800 and 1@%0. Otherwgse, it will be put on standby and
the IH Department informed at 0800. Operations personnel will
check and service the instrument in accordance with the in-

structions of the IH Depértment.

L COOLANT SYSTEM STACK Be MONITORING UNIT

4.1

The fourth unit is an Atomic Instrument Co. Be Air Monitor
which normally monitors the air in the coolant system stack.
The instrument is located in the vent house and takes its air
sample through a tube connected to the stack. During shutdown
operations it can be connected to tubes which take the air
sample from the coolant cell. This will be done during
maintenance operations which require that the salt containing
pipe and equipment be opened. Air samples are taken and
analyzed on a continuous basis. A high Be level (>2 ug/m3)
or instrument trouble will give an alarm in the CR. If it is
due to instrument trouble which the shift instrument mechanic
cannot correct or a high Be level, the IH Department will be
notified as soon as possible regardless of the time when the
alarm occurs. The instrument will be checked and serviced

by the operations personnel as instructed by the IH Department.
Approved by %/)/ f;//wfn 8/3/65
SECTION k4

AUXTLTARY SYSTEMS STARTUP CHECK LISTS

Successful operation of the reactor depends upon all essential
equipment and instrumentation functioning properly. Prior to each
startup all equipmentlis checked to assure that it is in the proper
operating condition, all necessary motors are started, all valve and
breaker positions are set and operational tests are made on all
esgsential instrumentation.

The check lists covering these operations are given in this section.
Items are listed by systems rather than chronologically and except where
there is interdependence these can be completed in any order. Where
possible items are grouped by areas to facilitate completion of the lists.

All operations listed must be completed before each reactor start-

up unless their deletion is approved by the operations chief.
Y W
Approved by,ffif‘f{; &g/)/ \gfi//ffi’L / i%%
10/1

YA FELECTRICAL STARTUP CHECK LIST

The purpose of this section is to prepare the electrical sysitem
for startup, that is; motors are ready to be turned on, diesel ready
for remote start and heaters ready to be turned on from hegter control

panel.
Init. Date/Time

1 ELECTRICAL CHECK LIST (EXCLUDING HEATERS)
1.l Main Control Board

Note that breakers are energized as
indicated by lights at push buttons.
Stack Fan 1 and 2 (SF 1 and 2)

Component Coolant Pump 1 and 2 (CCP 1 and 2)
HCV 930A (BKR G3-13)% and HCV 930B (BKR G3-1k4)*
HCV 935% (T-2-8)

Coolant 0il Pumps 1 and 2 (COP 1 .and 2)
Radiastor Blowers MBl and MB3

Duct Annulus Blowers MB2 and MBL

Radiator Bypass Damper

Coolant Pump

Fuel Pump

Fuel 0il Pumps 1 and 2 (FOP 1 and 2)
Treated Water Pumps 1 and 2 (TWP 1 and 2)
Cooling Tower Pumps 1 and 2 (CTP 1 and 2)
Tower Fans 1 and 2 (TF 1 and 2)

Coolant Cell Coolers 1 and 2 (CCC 1 and 2)
Reactor Cell Coolers 1 and 2 (RCC 1 and 2)
Drain Tank Cell Cooler {DCC 1)

Component Coolant Pump No. 3 (CCP 3)

Instrument Air Compressor No. 1 and No. 2
(AC 1 and 2)

1.2 Console Control Power Breakers
Control Rod Drives 1, 2, and 3

*1f breaker lights are not on, check closed
breakers at switch house.

S
Approved bx£g$§:22;4§z354/}%¢¢9zL LA-2
. 7 5

L.2

1.3

10/14/65

Init. Date/Time

(continued)

Radiator Door Drive Motor

Radiator Door Brake

Radiator Door Clutch

13.8 kv Panel (Auxiliary Control Room)

1.4

Note that circuits are energized by lights.
Pref. Line Potential
Switch 129 Closed and Energized
Emergency Line Potential
Switch 229 Open and Energized
Manual, Auto Switch set to automatic
Breaker 108 On and Tagged On
TD-1 - Switches A through J closed
TD-2 - Switches A, B, D through J closed
Lock out Light Off
North of Building
Motor to Switch 129 connected
Motor to Switch 229 connected
Diesel Panel (Auxiliary Control Room)

1.5

DPM3 S Closed _ A-l Closed ___ A-5 open

DPM4 T Closed ___ A-2 Closed ___ A-3 open

DPM5 Z Closed __ AA Closed ___ BB closed_
CC Closed _ A-h Open

48v System (840 ft. level, north)

1.5.1 Check MG No. 2 energized.
1.5.2 Check MG No. 3 energized.
1.5.3 DNumber of MG set running

1.5.4 Check running MG set Generator Switch
closed.

1.5.5 Check ground detector lights dim.

1.5.6 Check low dc voltage light dim.

In Battery Room:
1.5.7 Check L48v battery switch closed and
tagged.

Approved bynggzgggfi%fié;qffiaéa4 LA-3
| </ o 10/14/65

1.5

1.6

Init. Date/Time

(continued)
1.5.8 Check all battery cells electrolyte

level.

1.5.9 Check specific gravity of each cell
to be 1.210. Give cells balancing charge
if necessary.

250v DC System

1.7

At 250v DG Panel (840 ft. level North)

check the following switches closed.

1.6.1 250v Panel Supply Switch

1.6.2 MGL4 Supply (25 kw Gen.)

1.6.3 13.8 kv Control Power

1.6.4 FEmergency Lights

1.6.5 Breaker DC Trip Power (480v Swgr.
trip) |

In Battery Room
1.6.6 Check Battery Cells electrolyte level.
1.6.7 Check Cell Specific Gravity = 1.210.

Give cells equalizing charge if necessary.
In MG Room
1.6.8 MG-1 Running (Breaker "W" closed)

1.6.9 Generator switch (Reverse power trip)
closed.

1.6.10 MG-4 running

1.6.11 MG-4 generator breaker closed.

1.6.12 Instrument Panel No. 2 and 3 Disc.
Switch closed.

1.6.13 Process Power Panel No. 2 disconnect

switch closed.

1.6.14 Diesel No. 5 control power disconnect

closed.

Switch House

Close the following breakers:
Approved by %7:‘5\%1[ At LA-L

10/1k/65

Init. Date/Time

1.7 (continued)
MCC -G -4
l.7.1 DBreaker 13, Panel DR-2

1.7.2 Breaker 16, Diesel Auxiliary
Transfer Switch Supply _ (G3 or Gk)
l1.7.3 Breaker 27 - Panel DR 1
1.7.t Breaker 29 - Spect. Room Transformer
l.7«5 Breaker 31 Inst. Power Trans. No. 1
1.7.6 Breaker 33 - Air Compressor No. 3
MCC-G3
1.7.7 Breaker 3 - Sump Pump and Pit Pump
1.7.8 Breaker 16 - Diesel Auxiliary Power
1.7.9 Breaker 18 - Inst. Panel No. 2
Switch Gear Bus 3
1.7.10 Breaker M - Lighting Transformer
TVA Switch Gear
1.7.11 Breaker MB-1l closing coil breaker
1.7.12 Breaker MB-3 closing coil breaker
1.7.13 Breaker FP closing coil breaker
1.7.1h4 Breaker CP closing coil breaker
1.7.15 Breaker CCP-1 closing coil breaker
1.7.16 Breaker CCP-2 closing coil breaker
1.7.17 Breaker MB-1 trip coil breaker
1.7.18 Breaker MB-3 trip coil breaker
1.7.19 Breaker FP trip coll breaker
1.7.20 Breaker CP trip coil breaker
1.7.21 Breaker CCP-1 trip coll breaker
1.7.22 Breaker CCP-2 trip coll breaker

NOTE: These control power breskers are ingide the main

breaker compartment.
1.8 FEmergency ac Lighting
The following Lighting Panels should be

supplied from Process Power Transformer (M).
Approved by_fififififiig?gfiéfi;gxéqgux LA-5S
g 4 : 10/14/65

. Init. Date/Time

1.8 {(continued)
Switch each to B Position,
1.8.1 Panel 2 (861 ft level in maintenance
C. R.)
1.8.2 Lighting Panel K (840 ft level, TR)
1.8.3 1Lighting Panel B (852' level, Hall)
1.8.4 Lighting Panel A (852' level, Hall)

1.8.5 Lighting Panel AB (840' level outside
T. R.)

1.8.6 Lighting Panel T (Switch House)

1.9 Emergency D€ Lighting
1.9.1 Tag switch adj, lighting panel H closed,
North end, 840 ft level.

1.9.2 Tag DC light switch, 250v DC Dist.
Panel closed. (CKT No. 21)

2 DIESEL STARTUP CHECK LIST (This prepares the
diesels for quick startup.)
2.1 Fuel Supply (See Figure 4A.2-1)
2.1.1 Check all fuel oil valves open as
listed below:
Supply Valve at Storage Tank VS

v3-1 __ , V32 _ , V33 ___
Diesel No. 3 oil system.
Vil  , vk 5, vVh3
Diesel No. 4 oil system. |
V5-l _ , V52, V53 ___
Diesel No. 5 oil system.
2.1.2 Check 0il Storage Tank lLevel
_____gal. (>1000)
2.1.3 Close and tag P-3 Switch __
Close and tag P-4 Switch
Close and tag P-5 Switch _

2.1.4 Check and Record 0Oil Level in Day Tanks
w3, DT Y s, Dr5

Approved by ,J;fi/ “\%//fii;fl% La-6

10/1L/65

Init. Date/Time

2.1.5 Drain sludge and water from Fuel Oil
Supply Filters on DT 3 and DT L

’ DI 5 L]
Cooling Water

2.3

2.2.1 Check Radiators level of D3 ,
Dk , D5 .
2.2.2 Check specific gravity for antifreeze.

Note: If water is added, add antifreeze.

2.2.3 Close Heater Switch to all three Diesels:

Diesel 3 , Diesel L , Diesel 5.

2.2.4 Check Diesel water temperature Gauge
>90°F on Diesel 3 , Diesel k4 ,
Diesel 5 .

2.2.5 Check to see there are no obstructions

nath of diesel units outside building.
2.2.6 Check that air inlet louvers south side

of building can be opened. (Open these

louvers when diesels are running.)

Batteries on Diesels No. 3 and No. 4

2.4

2.3.L Turn on battery chargers D3 ;___ and
Db .

2.3.2 Check and record electrolyte in
Battery D3 _ and D4 .

2.3.3 Check for dead cells in each battery.

Local Manusgl-automatic Switch on Diesel

2.5

No. 3 and No. L4
2.4.1 Turn switch to automatic position and

tag. D3 D4

Air System on Diesel No. 5 (See Sketch 4A-2.1)
{
2.5.1 Open or check open and tagged:
V 5-4 and V 5-5 .

2.5.2 Close or check closed starting switch

to compressor C 5 .

Approved byfi%zm, ]
10/1 5

Init. Date/Time

2+¢5.3 Check PI discharge of air receiver
>150 psi.
Diesel Units (See Diesel Operation Manual)

2.7

2.6.1 Check crank case oil level D3 |,
Dby , D5 . should be full (or
above).

2.6.2 Check or fill Fuel Injection Pump.

D3 , Dh , D5
2.6.3 Check o0il level in air cleaners.
Check

D3 __, D+ , D5 .

governor oil level

D3 ___, D+, D5 .
2.6.4 Set the Diesel Governor settings as

follows: Speed droop = O

D3 , Db , D5 .
Load Limit , Setpoint and Dial indicator

approximately as follows.
D3=5__, Dk = 5 , D5 = 10 .
Synchronizer Indicator at Scribed Mark.

D3 , Dk , D5 .
Additional Checks for Diesel No. 5

2'8

2.7.1 Check 0il level in oiler of airstarting

motor.

2.7T.2 O0il pressure alarm switch should be in

the "on" position.

2.7.3 Check that governor has reset. Reset
marker should be at white mark. Use minor

mounted on mgnifold.

Diesel Auxiliasry Panel (Diesel Room)

Close or check closed the following
breakers:
2.8.1 Bkr. No. 1 Gen. No. 5 Fuel pump and

heater.

Approved by}zfi?’zigi;é%ynufh La-8
V

2.9

10/14/65

Init. Date/Time

2.8.2 Bkr. No. 2 Gen. No. 4 Fuel pump and

heater.

2.8.3 Bkr. No. 3 Gen. No. 3 Fuel pump and

heater.

2.8.4 Bkr. No. 6 Gen. No. 5 air compressor.

Lighting Panel T

Close or check closed the following
breakers:
2.9.1 Bkr. No. 7 and No. 9. Cen No. 4
battery charge.
2.9.2 Bkr. No. 11 and No. 13. Gen. No. 3

battery charge.

3 HEATER PRESTARTUP CHECK LIST

This section is to be completed to ensure the

following objectives:

(1)

(2)
(3)
(L)
3.1

that all heater controllers are at the lowest
setting before breakers are closed;

that all breakers are closed;

that induction regulator blowers are on;
heaters are ready when required.

Procedure for Completing Heater Check List

3.1.1 Check all heater controllers on Heater
Control Panels. Circle in Red all heaters
(in tables) which have amps indicated on
the ammeters. These heaters should be
left on during completion of the check
list.

3.1.2 Have Shift Supervisor approve list

before proceeding.

3.1.3 Set all manual powerstats to zero
that are not cireled in red. Circle
each heater number as the controller is
checked at or set to zero using black

pencil. Note: Check with Shift Supervisor
/},:f:j ]. '_ -
Approved by f;fifii;f/{>駣%§/k¢gy\\ y 2?89
' 10/1 5

- | - Tnit. Date/Time
3.1.3 (continued)

before turning off any heaters (not
checked in No. 1) which show current

on ammeters.

3.1.4 Check that heater control power and
induction regulator motor power is on;
. that is, the following breakers are
. L. closed:
3.1.4.1 Switch gear Breaker No. Z
3.1.4.2 Switch gear. Breaker BB
3.1.4.3 Safety Switch G 5-1-D (adj.
transformer GS-1-D)
3.1.4e4h Heater Panel Breakers G5-1-D3-
1, 2, 4, 5, 6, 8, 9, 10, 12.
3.1.4.5 Heater Panel Breakers G5-1-Di-
1, 2, 5, 6, 9, 10.

NOTE: Circle heater panel breaker numbers which are

closed or as they are closed.
. Check that all induction regulators and
motor operated powerstats are at the
lowest setting before closing the heater

breakers.

Approved by ,/f52??3¥4§23;</#@¢4 4A-10
e AV4 10/14/65

G5-1-A CIRCUITS

HEATER HEATER

CONTROL PANEL

HEATER CONTROL* PANEL BREAKFRS INIT: DATE/TIME

FV 103 P 8 G5-1-Ak-2 L
H 103 P 8 G5-1-Ab-k L
H 104-1 P 8 G5-1-Al-1 L
FV 10k-1 P 9 G5-1-A1-9 ,___
FV 104-1A P G5-1-Ak-1 S
FV 104-3 P 9 G5-1-A1-11 L
H 104-5 P 9 G5-1-A1-3 L
H 104-6 P 9 G5-1-A1-5 L
FV 105-1 P 9 G5-1-A1-6 L
FV 105-1A P G5-1-A1-10 .
FV 105-3 P 9 G5-1-A1-8 L
H 105-1 P 9 G5-1-Al-2 L
H 105-k4 P 9 G5-1-Al-L L
FV 106-1 P 9 G5-1-A2-5 -
FV 106-1A P G5-1-Ak-3 -
FV 106-3 P 9 G5-1-A2-7 L
H 106-1 P 9 G5-1-A2-1 L
H 106-4 P 9 G5-1-42-3 ”*__
H 107-1 P 10 G5-1-A2-2 L
H 107-2 P 10 G5-1-A2-4 L
H 107-3 P 10 G5-1-A2-6 L
FV 107-1 P 10 G5-1-A2-8 .
FV 107-3 P 10 G5-1-A2-12 .
H 108-1 P 11 G5-1-A3-1 L
H 108-2 P 11 G5-1-A3-3 L
H 108-3 P 11 G5-1-A3-5 L
FV 108-1 P 11 G5-1-A3-11 .
FV 108-3 P 11 G5-1-A3-7 L
H 109-1 P 11 G5-1-A3-2 -
H 109-2 P 11 G5-1-A3-L L

) Yy
Approved by %j Z/«‘é/élf/ wiem La-11
- v 10/14/65
G5-1-A CIRCUITS (continued)
HEATER HEATER
CONTROL PANEL
HEATER CONTROL* PANFL BREAKERS INIT. DATE/TIME
H 109-3 P 11 G5-1-A3-6
FV 109-1 P 11 G5-1-A3-12
FV 109-3 P 11 G5-1-A3-8
H 110-1 P 11 G5-1-A2-9
RAN-1. P TA G5-1-45-1
RAN-2 P TA G5-1-45-2

Breaker G5-1-A

*P = Powerstat
) /7,
Approved by¢;$55;224;4?9641/m
b4

La-12
10/14/65
G5-1-C CIRCUITS
HEATER HEATER
CONTROL PANEL
HEATER CONTROL* PANEL BREAKERS INIT. DATE/TIME
H 104-2 P(m) 10 G5-1-C1-1
H 104-3 P(m) 10 G5-1-C1-3
H 10k-k4 P(m) 10 G5-1-C1-5
H 105-2 P(m) 10 G5-1-Cl-k
H 105-3 P(m) 10 G5-1-Cl-6
H 10k-7 P(m) 10 G5-1-C1l-7
H 110-2 P(m) 10 G5-1-Cl-2
H 110-3 P(m) 10 G5-1-C1-8
H 203-1 P(m) L G5-1-C2-8
H 204-1 P(m) L G5-1-C2-6
H 206-1 P(m) L G5-1-C2-5
CDT-1 P(m) L G5-1-C2-4
H 106-2 P(m) 10 G5-1-C2-2
H 106-3 P(m) 10 G5-1-C2-7
H 204-2 P 3 G5-1-C3-5
FV 204-1 P L G5-1-C3-5
FV 20k-1A P 3 G5-1-C3-9
FV- 204-2 P L G5-1-C3-k
FV 204-3 P 3 G5-1-C3-6
FV 206-1 P L G5-1-C3-1
FV 206-1A P L G5-1-C3-3
Receptacles HCP-1-TA G5-1-C3-8
Receptacles HCP-8-12 G5-1-C3-7

Breaker-GS-l-C

¥P(m) Motor operated powerstat.
b}
Approved by?fiézgzgk;?é@064¢4fl1
' L4 fl.\/

G5-BB CIRCUITS

LA-13
10/1k/65

HEATER CONT.* HCP

HEATER PANEL  TRANSFORMER DIST. PANEL

BREAKERS BREAKERS

. BREAKERS  INIT. DATE/TIME

CRL I
CRz 1
CR3 i
CRL 1
FFT-1 L

¥FD1-1 I

FDz-1 i

Ind. Regulator
Ind. Regulator
Ind. Regulator

Motors

Ind. Regulator
Cont. Circuits

Powerstat = .

Motor

Motors

©® H PR

CRL - 1,2,3,4,5 CR1L
CR2 - 1,2,3,4,5 CR2
CR3-- 1,2,3,4,5 CR3
CRk - 1,2,3,4,5 CRkL
FFT-1-1,2,3,4,5 FFT-1
6,11,12
FDL-1-1,2,3,4,5 FD1-1
6,7
FD2-1-1,2,3,4,5 FD2-1
6,11,12

Blower Started
Blower Started

1
6

89)

= O~ O B

10
Ind. Regulator

N

7

G5-1-D3-1
G5-1-D3-5
G5-1-D3-9

G5-1-D3-2
G5-1-D3-k
G5-1-D3-6
G5-1-D3-8
G5-1-D3-10

G5-1-D3-12

G5-1-Dh-1
G5-1-D4-2
G5-1-Dh-5
G5-1-Dk-9
G5-1-Dk-6
¢5-1-D4-10

G5-BB-3

G5-BB-5

G5-BB-T

G5-BB-9

G5-BB-6

G5-BB-10 __

G5-BB-8

G5-BB-1

G5-BB-2

¥1 - Induction Regulator

NOTE: Circle heater panel breaker numbers which are closed or as they

are closed.
/
Approved by.. = il /ufi_;éu
; AV 10/14/65

G5-2-Y CIRCUITS

HEATER PANEL. TRANSFORMER DIST. PANEL

HEATER CONT. HCP BREAKERS  BREAKERS BREAKERS INIT. DATE/TIME
CR5 I 1 CR5-1,2,3,4,5 CR5 G5-2-Y 3
CR6 I 1 Cr6-1,2,3,4,5 CR6 __ G5-2-Y b
CR7 I 1 CR7-1,2,3,4,5 G5-2-Y 5
CR8 I 1 CR8-1,2,3,4,5 G5-2-Y 6
Induction Regulator Blower Started G5-2-Y-1

Breaker G5-2-X
Breaker G5-2-Y

NOTE: Circle heater Panel breaker numbers which are closed or as they
are closed.
) / e
Approved byigfifi%“jgg‘vf%?7y%@9¢\ YA-15

10/14 /65
T-1~-A AND T-1-B CIRCUITS
HEATER PANEL TRANSFORMER DIST. PANEL
HEATER CONT. PANEL BREAKERS ' BREAKERS ~ BREAKERS INIT. DATE/TIME
HZ200-13 I 1 H200-13-1,2,3 H200-13 __ T-1-A-5
k,5,6
H201-12 I 1 H20l-12-1,2z,3 Hz-1-12  T-1-A-7
4,5,6
Hz202-2 I 1 Hz202-2-1,2,3 H202-2 T-1-A-9
h,5,6
RCH-3 I RCH-3-1,2,3 - T-1-A-6
FP-1 I FP-1-1,2,3 FP-1 T-1-A-10
4,5
FP-2. I 7 Fp-2-1,3,4,5 FP-2 T-1-A-8
| 6
Induction Regulator Blower Started _ T-1-A-1
Induction Regulator Blower Started T-1-A-2
RCH-L I 6 RCH-4-1,2,3 T-1-B-6
I
A I 7 HX1-1 T-1-B-9
HX2 I 7 HXZ2-1 T-1-B-10__
HX3 I 7 HX3-1 T-1-B-8
FFT-2 I 8 FFI2-1,2,3,4 FFT-2 T-1-B-7 __
5,6,7,8
FD1-2 I 8 FDl-2-1,2,3,4 FD1-2 T-1-B-3
5,6,9
FD2-2 I - 8 FD2-2-1,2,3,4 FD2-2 T-1-B-5
5.’ 6) 7}8
Induction Regulator Blower Started T-1-B-1
Induction Regulator Blower Started T-1-B-2

Breaker T-1-A
Breaker T-1-B

NOTE: Circle heater panel breaker numbers which are closed or as they
are closed.
Approved.by&gffigég%zsgpffifififii LA-16

10/14/65

T-1-C CIRCUITS

HEATER PANEL. TRANSFORMER DIST. PANEL
HEATER CONT. PANEL. =~ BREAKERS BREAKERS BREAKERS  INIT. DATEVTIME

RCH-1 I & RCH-1-1,2,3 T-1-C-7 __
RCH-2 I 6 RCH-2-1,2 T-1-C-9
RCH-5 I 7  RCH-5-1,2 T-1-C-10__
RCH-6 I 7 RCH-6-1,2,3 T-1-C-8
RCH-7 I 7  RCH-7-1,2 T-1-C-5
H102-2 I 7 H102-2-1,2 T-1-C-6
Induction Regulator Blower Started T-1-C-1
Induction Regulator Blower Started T-1-C-2 __

Breaker T-1-C

NOTE: Circle heater panel breaker numbers which are closed or as they
are closed.
z5:3252;2é97g
Approved by. =7 N/ L21) At i LA-17
s Froa B ll--v

10/14/65

T-2-V AND T-2-Y CIRCUITS

HEATER PANEL. TRANSFORMER DIST. PANEL

HEATER CONT. HCP  BREAKERS BREAKERS  BREAKERS INIT. DATE/TIME
H200-15 P 2 T-2-V1-22

H200-16 P TA T-2-V1-17 __

H201-10 P 2 T-2-V1-18

H201-14 P 7A T-2-V1-19

CDT-2 P 4 T-2-Vi-2

CDT-3 p L4 T-2-v1-6

CP1 P 4 T-2-V1-10 __

CP2 P 4 T2-vi-1h

H100-1 P 5 T-2-V1-1

H100~2 P 6 T-2-V1-5

H101-2 P 6 T-2-V1-9 __

H101-3 P 6 T-2-V1-13

Rl I 7 R-,2,3 ___ Rl T-2-Y-3 __
R2 I 7 R2-1,2,3 ___ Rz T-2-Y-5 __
R3 I 7 R3-1,2,3 _ R3 T-2-Y-6 __
Induction Regulator Blower Started T-2-Y-1

Breaker T-2-V
Breaker T-2-Y

Approved by 1#EF;%%KJfiUy'A//7\ La-18
| S - 10/14/65
T-2-W CIRCUITS
HEATER HEATER
CONTROL PANEL
HEATER CONTROL PANEL BREAKERS INIT. DATE/TIME
H200-14 P 2 T2-Wl-2 .
H201-11 P 2 T2-W1-5 L
H201-13 P 2 T2-W1-9 -
H201-14 P L
H202-1 P 3 T2-W1-20 o
H205-1 P 3 T2-W1-18 L
FT201A-1. P 3 T2-W1-2 -
FT201A-2 P 3 T2-Wl-4 L
FT201A-3 P 3 T2-W1-6
FT201A-4 P 3 T2-W1-8
FI201B-1 P 3 T2-W1-10
FT201B-2 P 3 T2-W1-12
FT201B-3 P 3 T2-Wl-1k
FT201B-k4 P 3 T2 -W1-16
H 203-2% P 3 T2-W1-17
H200-1 P 5 T2-W2-2
H200-11 P 5 T2-W2-6
H200-12 P 5 T2-W2-10
H201-1 P 5 T2-W2-1k
H201-2 P 5 T2-W2-18
H201-9 P 5 T2-W2-17
H102-5 P TA T2-W2-13
H102-1 P TA T2-W2-5
H102-4 P TA T2-W2-9
Breasker T-2-W
LE-CP-1P P T2-W1-15
LE-CP-2P T2-W-19

*¥Fill line disconnected, leave heater off

All items on the Electrical Startup Check List are complete.

Shift Supervisor

Date

- )fififi
Approved by gfififig@fi;”VV“”M LA-19
Y 10/14 /65

.t L INSTRUMENT POWER PANEL CHECK LIST

This section is to be completed to ensure all instrument

power breakers are turned on.
Tnit. Date/Time

h.l Instrument Power Panel #1 (L8v IX)
4.1.1 Close breakers 1, 2, 3, 4, 5, 6, T,
8, 9, 10.

4.2 TInstrument Power Panel #A1 (L8v IC convertegd
to 120v AC)

4.2.1 Close breakers 1, 2, 3.

4.3 Instrument Power Panel #2 (115v AC)
%.3.1 Close breakers 1, 2, 3, 4, 5, 7, 8,
- 9, 10, 11, 12, 13, lh, 15, 16, 17,

18, 20.
4,4 TInstrument Power Panel #3 (115v AC)
4.4.1 Close breakers 1, 2, 3, 4, 6, 7, 8,
9, 10, 11, 13, 15.

4.5 Instrument Power Panel #A3 (Regulated 115v AC)
4.5.1 Close breakers 1, 2, 3, L.

L.6 Instrument Power Panel #L (115v AC-TVA Bus)
) | 4.6.1 Close breakers 1, 2, 3, 4, 5, 6, T,
8, 9, 10, 11, 16.
4L.7 Instrument Power Panel #Al4 (Regulated 115v AC)

- 4.7.1 Close breakers 1, 2, 3.
| 4.8 Instrument Power Panel #5 (120/208v AC 3¢-TVA)
4.8.1 Close breakers 1, 2, 3, 4, 5, 6, 7, 8,
9, 10, 11, 12, 13, 14, 15, 16, 17, 18,
19, 20, 21, 25, 27, 29.

1.9 Instrument Power Panel #6 (120/208v AC 3¢ - TVA)
L.9.1 Close breakers 1, 2, 3, 4, 5, 6, 9,
11, 12, 17, 18, 23, 24, 25, 26, 28.

All items on the Instrument Power Check List are complete.

) Shift Supervisor Date

*J;/,«'//f’ ,«fr‘g
Approved by =~ / \/m/ "
N

—

4A-20

FRCM
Ol
STORAGE

4000 GAL.

I—N-E

Lo

10/14/65

DG-DIESEL GEN.
P-0OIL PUMP

DT- OIL DAY TANK

C 5-AIR COMPRESSOR
() -HI -LO LEVEL 3W.
(P)-PRESS SW.

\/ENT’]

x| © UISIGHT GLASS

FIG. 4A2 -1

DG-4

DIESEL GENERATOR OIL AND AIR PIPING
& |
Approved Dby 4459;2%4;4??’”“4”\\ LB-1
7 v

10/25/65
4B INSTRUMENT AIR SYSTEM STARTUP CHECK LIST

The instrument air system will normally be operated with one instru-
ment air compressor, one air dryer and both air receivers in service,
with the second instrument air compressor and air dryer in standby.

This check list covers the startup of the instrument air system for
normal operation, and assumes that related portions of the electric
system check list have been completed. Some portions of the system may
already be in service; however, each item listed should be checked.

1 INSTRUMENT ATIR COMPRESSORS AND DRYERS

- (Diesel House)

Init. Date/Time

1.1 Close, or check closed the cooling water drain
valve, V-881-B.

l.2 Close, or check closed, the following valves

in the instrument air compressor and after
cooler cooling water circuits:
v-880-1C _ Vv-880-2C
v-881-1¢ _ v-881-2¢
1.3 Open, or check cpen, the following valves in

the instrument air compressor and after

cooler cooling water circuits:

v-881-A _ Vv-881-1A _ Vv-881-1B
) v-881-24  V-881-2B _ V-880-1B%
. v-880-2B% __ V-880-1A _ V-880-1D¥¥ _
V-880-24 _ V-880-2D%%

1.4 If the cooling tower water system is in oper-
ation, close, or check closed, V-872
If this system is not in operation, open,

or check open, V-872

NOTE: If the instrument air compressor is already in
operation, the valves marked * should be left throttled,
and the valves marked *¥ should be left closed.
10/25/65

Approved byfi%flm 4B-2
4 ~

Init. Date/Time

1.5 Check that the oil level is visable in the
bulls eye of both instrument air compressors.
No. 1 No. 2

1.6 Close or check closed, the following valves in

the air system:

V-9110-C _ V-9113-C ___ V-9113-E __
V-9113-F _ V-911k-c __ V-911k-E
V-9114-F  V-9115-E ___ V-9116 ___
V-9119%  V-9120-C ___ V-9123-C __
V-9123-E  V-9123-F __v-912k-C __
V-912L-E _ Vv-9124-F __ V-9l25-E __
V-9126 v-9129% _ V-9130 _
V-9132 __ V-9000-3 __ _ V-9000-4
V-9000-5

*¥NOTE: If an instrument air compressor and air dryer
are already in operation, either V-9119 or V-9129 will
be open, and should be left open.

1.7 Open, or check open, the following valves in

the air system:

V-ACl-A _ V-AC1-B ___ V-ACl1-C _
V-9110-A _ V-9110-B ___ V-9111 __
V-DL ___V-9113-A ___ V-9113-B __
V-9113-F __ V-911k  _ V-911hk-A
V-9114-B _ V-9114-D __ V-RL = ___
V-9115-A  V-AC2-A __ V-AC2-B ___
V-AC2-C __ V-9120-A __ V-9120-B __
v-9121 _ V-D2 ___Vv-9123-A
V-9123-B __ V-9123-D ___ Vv-912k
V-9l2k-A  V-9124-B __ V-9124-D
V-R2  _ V-9125-A __ V-9000
V-9000-1 __ V-9000-2 ___ V-9001

(Control Room)

1.8 Check that instrument air compressor
1/;’#fa
Approved by IQEE;;;%Li/4;;4k¢flM 4B-3
T 4 V \

1.8

10/25/65

Tnit. Date/Time

(continued)

selector switch (S-53) is set to the com-
pressor which is in operation, or to the

compressor to be operated and start-the’

compressor selected.

(Diesel House)

1.9

1.10

1.11

1.12

1.13

1.14

1.15

After the instrument air compressor has been
started, check that the cooling water flow
to the compressor has been established.
Close the temperature control valve by-pass
valves V-880-1D  and V-880-2D

Turn the electric power on to both air dryers

and note that both air dryers are cycling.
Lighting panel T, Bkrs. 15 and 17.

Adjust the purge flow through both air dryers
to 19 C F M (4.5 on rotameter).

Adjust the bleed, from the moisture indicator

petcocks, on both air dryers to a small bleed.

When the moisture indicators on both air
dryers are blue, open or check open valve
V-9119 to place air dryer No. 1 in service,
or V-9129 to place air dryer No. 2 in service.
Momentarily open valves V-9116 and V-9126 to

blow down the filters downstream of the air

dryers.
Close V-9129, V-9125-A if dryer unit No. 1 is

to remain in service, or close V-9l119, V-2115-4,
if dryer unit No. 2 is to remain in service.

Dryer unit No. is in service

Close bleed petcock on standby dryer

De-energize.standby dryer
Lighting Panel T Bkr. 15 for Dryer No. 1.
Lighting Panel T Bkr. 17 for Dryer No. Z.

e .
2 i ?
Approved Ufi%fi(};i2<;4;géa¢#k 4R-k
I V

10/25/65

Init. Date/Time

1.16 Check that moisture indicator XmI-9000 in
line 9000 is less than 20%.

1.17 Check that the instrument air pressure as
indicated on PI-ACl-K and PI-AC2-K is
between 70 and 85 psig.

2 TEST AUTOMATIC START OF STANDBY INSTRUMENT ATR
COMPRESSOR

(Diesel House)

2.1 With the instrument air pressure as indicated
on PI-ACl1-K and PI-AC2-K above 7O psig, open
the blow down valve at the separator outlet
of the operating instrument air compressor
(V-9110-C if instrument air compressor No. 1
is operating or V-9120-C if instrument air

compressor No. 2 is operating.)

2.2 Observe PI-ACL-K if instrument air compressor
No. 1 is operating, or PI-ACZ-K if instrument
air compressor No. 2 is operating. The standby
instrument air compressor should start and
XA-L030-9 should annunciate when the instru-
ment air pressure drops to 70 psig. Record
the instrument air pressure when the standby

instrument air compressor starts: psig

and when XA-4030-9 annunciates  psig.
NOTE: If the time required to decrease the instrument
air pressure to 70 psig is excessive, the operating
instrument air compressor may be momentarily stopped

from the control room and restarted after the standby

instrument air compressor starts.
2.3 Close valve V-9110-C or V-9120-C, which-

ever was opened in Step 2.1 above.

(Main Control Room)
2.4 After anmunciator XA-4030-9 clears, stop
Approved by

2.4

25

4B-5
10/25/65

Init. Date/Time

(continued)

the air compressor which had been selected
in Step 1.8, and change the instrument air
compressor selector switch (8-53) to the

other instrument alr compressor,

Start the selected instrumefit air compressor.

(Diesel House)

2.6 With the instrument air pressure as indicated

NOTE:

2.7

on PI-ACl-K and PI-AC2-K above 70 psig, open
the blow down valve at the separator outlet
of the operating instrument air compressor
(V-9110-C if instrument air compressor No. 1
is operating or V-9120-C if instrument air

compressor No. 2 is operating.)

Observe PI-ACl-K if instrument air compressor
No. 1 is operating, or PI-AC2-K if instrument
air compressor No. 2 is operating. The standby
instrument air compressor should start and
XA-4030-9 should annunciate when the instrument
alr pressure drops to TO psig. Record the
instrument air pressure when the standby
instrument air compressor starts: _ psig

and when XA-4030-9 annunciates psig.

If the time required to decrease the instrument

air pressure to 70 psig is excessive, the operating

instrument air compressor may be momentarily stopped

from the control room and restarted after the standby

instrument air compressor starts.

2.8

Close valve V-9110-C or V-9120-C, whichever

was opened in Step 2.6 above.

(Control Room)
2.9 Note that annunciator XA-L030-9 clears and

stop the standby instrument air compressor.

I
Approved by X 4/‘\’?’7 Jed 4B-6

10/25/65

Init. Date/Time

2.10 Note:the position of the instrument air

compressor selector switch (S-53) and which

instrument air compressor is in operation:

S-53 position:
TAC-1 MANUAL JAC-2

Operating instrument air compressor:

IAC-

1 IAC-2

3 INSTRUMENT AIR PRESSURE REDUCTION AND DISTRIBUTION

(Auxiliary Control Room)

3.1 Control Room Instrument Alir Reducing Station

3.1.1 Close or check closed the following

3.1.

valves:

Line 900Ll-1 vent wvalve

Line 9007-1 vent valve
PCV-9001-1 filter blow down valve
PCV-9001-2 filter blow down valve
PCV-9007-1 filter blow down valve
PCV-9007-2 filter blow down valve
PCV-9001-2 inlet valve __ and outlet valve

PCV-900T7-2 inlet valve and outlet valve

2 Open, or check open, the following valves:

Valve to PI-G0001-1 Valve to PI-9001-2Z

Valve to PI-9007-1 Valve to PI-9007-2

Valve to PI-9007-4 Valve to PI-9007-5

——

PCV-0001-1 inlet valve and outliet valve

PCV-9007-1 inlet valve and outlet valve
Approved by//zgifii84%7%5/7wwfl4 4B-7

3.2

10/25/65

Init. Date/Time

3.1.2 (continued)
PCV-9007-3 inlet valve and outlet wvalve

PCV-9007-5 inlet valve and outlet valve

P ——

Line 9001-1 shut off wvalve
Line 9007-1 shut off valve _
3.1.3 While observing PI-9001-2, slowly

increase PCV-9001-1 setting until HSV-9001-1

opens. (30 psig). Record PI-9001-2

psig.

3.1.4 Reset PSV-9001-1 at 20 psig as indi-
cated by PI-9001-2.

3.1.5 Set PCV-9007-1 at 60 psig as indicated
by PI-9007-2.

3.1.6 While observing PI-9007-4, slowly in-
crease PCV-9007-3 setting until HSV-9007-1
opens (30 psig). Record PI-9007-%

psig.

3.1.7 Reset PCV-9007-3 at 20 psig as indi-
cated by PI-9007-4.

3.1.8 While observing PI-9007-5, slowly in-
crease PCV-9007-5 setting until HSV-9007-2
opens (4O psig). Record PI-9007-5

psig.

3.1.9 Reset PCV-9007-5 at 30 psig as indicated
by PI-9007-5.

3.1.10 Check that the following annunciators

are clear:
XA-4030-1 XA-4031-1
XA-4031-2 XA-4031.-3

Control Room Instrument Air Distribution

Approved by éé?fieayg?§;§/2¢fifl LB-8
V

10/25/65

Init. Date/Time

3.2.1 Behind Main Panel 12, open, or check
open, all valves on the following headers
that are permanently connected to instru-
ment lines. .Header 9001-1 _ Header
9007-1 __ Header 9008-1 __

3.2.2 Behind Main Panel 11, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header 9001-1  Header
9007-1 - FHeader 9008-1 .

3.2.3 Behind Main Panel 10, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header 900l-1 __  Header
9007-1 _ Header 9008-1

3.2.4 Behind Main Panel 9, open, or check

open, all valves on the following headers
that are permanently connected To instru-
ment lines. Header 9001-1 _  Header
9007-1  Header 9008-1

3.2.5 Behind Main Panel 8, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header 9001l-1 __ Header
9007-1 _ Header 9008-1 __

3.2.6 Behind Main Panel 7, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header G00l-1 _ Header
9007-1 __ Header 9008-1

3.2.7 Behind Main Panel 6, open, or check

open, all valves on the following headers

that are permanently connected to instrument
Approved by /é;f 4B-9
' 10/25/65

Tnit. Date/Time

3.2.7 (continued)
lines. Header 9001l-1 _ Header
9007-1 __ Header 9008-1

3.2.8 Behind Main Panel 5, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header 9001-1  Header
9007—1 ____ Header 9008-1 __ .

3.2.9 Behind Main Panel 4, open, or check

open, all valves on the following headers
that are permanently connected to instru-
ment lines. Header 9001-1 _  Header
9007-1 __ Header 9008-1 .

3.2.10 Behind Main Panel 3, open, or check

ocpen, all valyes on the following headers

that are permanently connected to instru-
ment lines. Header 9001-1 Beader
9007 -1 Header 9008-1 .

(High Bay)
3.3 Sampler Enricher Instrument Air Reducing Station
3+3.1 Close, or check closed, the following

valves:

Line 9009-1 vent valve

PCV-9009-1 filter blow down valve
PCV-9009-2 filter blow down valve
PCV-9009-2 inlet valve

PCV-9009-2 outlet valve

3+3.2 Open or check open, the following valves:
Valve to PI-9009-1
Valve to PI-9009-z
PCV-9009-1 inlet valve __ and outlet valve

Line 9009-1 shut off wvalve

/«’
Approved b%?{fgg;;ZZ;?%kafiH
- \'

3.4

Init.

4B-10
10/25/65

Date/Time

3.3.3 While observing P1-9009-2, slowly
increase PCV-9009-1 setting until
HSV-9009-1 opens (4O psig).

Record PI-9009-2  psig.

3.3.4 Reset PCV-9009-1 at 30 psig as indi-
cated by PI-9009-2.

3.3.5 Check with the control room that

annunciator XA-4031-5 is clear. .

High Bay Area Instrument Air Distribution

NOTE:

3.4.1 Behind Sampler Enricher Panel 1, open,
or check open, the yellow-handled valves
that supply air to HSV-675 _ and
HSV-678 __ , and the black-handled valve

that supplies air to the removal valve

The startup of the instrument air system for

the Chemical Processing Plant is covered in the

Chemical Processing Plant Startup Procedure.
(Filter Pit)

3-2

Containment Air Panel 1 Instrument Alr

Distribution

3.5.1 Behind Containment Air Panel 1, open,
or check open, the valve on header 9005-3
that supply air to the following:
FCV-925-A  TFCV-926-A

3.5.2 Behind Containment Air Panel 1, open,
or check open, the valves on header 9011-5
that supply air to the following:

Line S1-A1 __ FCV-934-A

(Blower House)

3.6 Blower House Instrument Air Reducing Station

3.6.1 Close, or check closed, the following

valves:
Page (s) Missing
from

Original Document
4E3

Init.

Date & Time

(Main Control Room)

14, Stop the component cleant pumps .after the FV's

in_the DIC have cooled to the point where they
will not thaw on loss of air.

(High Bay)

15. Place the necessary masonite sheets in place for

alternate top shield blocks on both cells.

16. Place alternate top shield blocks in place on the

masonite, and bolt in place.

(Water Room)
17. Set the pressure control valve PCV 332 for 2 psig.,

18, Open V 332 A & B and V 342,

(High Bay)
19. When the cell pressure reaches 2 psig as indicated
by PI-RC-B, check all accessible membrane welds. with leak

detector solution,

(Water Room)
20. Close V 332 A

(Service Tunnel)

21. Open V 955 A & B

22. When the cell reaches atmospheric pressure as

indicated by PI-RC-B close V 955 A & B

(High Bay)
23 . Remove the top shield blocks and masonite sheets

put in place in steps 4E 14,

24, Place in their proper place the masonite sheets

not placed in step 4E 14,

25, Place the corresponding top shield blocks on

these sheets of masonite and bolt in place,

(Water Room)
26, Open V 332 A

(High Bay)

27.

28,

29,
30.

4E4

Date & Time

When the cell pressure reaches 2 psig check the
remaining membrance welds with leak detector

solution.,

When all leaks in the membrane have been repaired

place all masonite and top shield blocks in place.

Bolt down the upper shield blocks.

A leak rate test of the RC and DTC will be per-
formed at 20 psig prior to start-up after either
of the cells has been opened. A number of.the
valves will also be tested while the cells are

at 20 psig pressure. These are HCV's 930 A & B,
V 930 C, V's 955 A, B, & C, CV 332, CV 342, FCV's
333 A& B, FCV's 343 A & B, CV 965, and CV 966.

Open V 980 A & B before pressurizing,

There are numerous other valves, penetrations and
lines which require periodic leak testing at a

cell pressure of 20 psig. When these are to be
tested it will be done while the cells are at

20 psig for the leak rate test. Others requiring
the periodic leak test which can be performed with
the cells at 0 psig will be tested when the cells
are depressurized after the 20 psig leak rate test,
The penetrations and their locations are given in
tables 4.1 ahd 4.2 in the MSRE Design and Opera-
tions Report, Part VIII,.

The detailed steps for the leak tests follow. The
first group is tested each time a leak rate test

at 20 psig is performed. The second group is tested
periodically during one of the 20 psig leak rate
tests. The third group is tested periodically with
the second group following the 20 psig leak rate
test.

4E5
Check

¥

Init. Date & Time

31, HCV 930 A & B and V 930 C in the following
manner.
HP coverage and gas masks afe reduired.
(Control Room)
31.1 Check to see that the following freeze
valves are frozen, '

104

105

107

FV
FvV
FVv 106
Fv
FV

108

Fv 109

31,2 Check to see that the space coolers are

in operation.

31.3 Check to see that the component coolamt pumps

are stopped,

(Transmitter Room)
31.4 Check the drain tank weight indicators to see

that all the salt is in the tanks.

(Water Room)
31.5 Set PCV 332 for 20 psig.

31.6 Open V 332 A,

(Special Equipment Room)
31.7 Close V 980 A & B after the cell pressure

reaches 20 psig.

31.8 Close V 332 A,

(Service Tunnel)

31.9 Connect an instrument air line with a
pressure regulator having a gauge of 0 to
50 psi minimum range and a rotameter having

a range of 0-100 cc/min to valve 930 C.

31.10 Connect a 0-10 cc/min range. rotameter to

the lantern ring plug on HCV 930 A.

31.11 Connect é 0-10 cc/min range rotameter to the

lantern ring plug on HCV 930 B,

3l.12
31.13

31.14
31.15
31.16
31.17.

31.18

31,19
31.20

31.21

31.22

31.23

31.24
31.25

4E6

Init,.

Date & Time

Open V 930 C.

Pressurize the region between HCV 930 A

and HCV 930 B to 20 psig.

Check the external parts of V 930 C, HCV
930 A and HCV 930 B with leak detector

solution. No leakage acceptable.

Flow through V 930 C .

Leakage from lantern ring on HCV 930 A .

Acceptable leakage 5: scc/min

Leakage from lantern ring on HCV 930 B .

Acceptable leakage 5 scc/min

Subtract the sum of the leakage through the
lantern rings from the leakage through

V 930 C, This is the leakage through HCV
930 B, Leakage . The acceptable

leakage is 50 scc/min,

If the leakages exceed the acceptable values

make repairs and recheck as above.

Close V 930 C.

Disconnect the instrument air line and .
reverse the rotameter connection to V 830 C,

Do not reconnect the air line,

Connect a bleed line from V 930 C to exhaust

into line 931. Open V 930 C slowly to
relieve the pressure between HCV 930 A and
HCV 930 B.

With V 930 C open and pressure relieved read
the rotameter. This is the leakage through
HCV 930 A. Leakage . The acceptable

leakage is 50 scc/min,

Close V 930 C and cap,

If repairs on HCV 930 A are required which
necessitates opening the 30 in. duct (line

930) complete all other containment checks
32,

WET

Init.

Date & Time

31.25 (Continued)
required at a cell pressure of 20 psig before
lowering this pressure to make required

repairs.

31.26 If the leakage rates on HCV 930 A & B and
V 930 C are now acceptable tag the valves

closed.

Check V 955 A, B, & C in the following manner

after testing HCV 930 A & Band V 930 C. HP

coverage and gas masks are required.

(Control Room)

32.1 Check PI-RC-B to see that the cell pressure
is 20 psig.

32.2 Connect the instrument air line with a
pressure regulator having a gauge of 0-50
psi minimum range and a rotameter having

a range of 0-10 cc/min to valve V 955 C.

32.3 Open V 955 C.

32.4 Pressurize the line between V 955 A, V 955 B
to 20 psig with the air.

32.5 Leak test the exterior of V 955 A, B, & C
with leak detector solution. No leakage
acceptable.

32.6 If repairs are required on V 955 A the cell will
have to be vented to atmospheric pressure; All
other containment tests to be performed at
a cell pressure of 20 psig should be completed

prior to venting the cell.

32.7 When the no leak requirement of step 32.5
is satisfied read the rotameter. This 1is
the leakage through V 955 B.

32.8 Close V 955 C.

32,9 Disconnect the air line and reverse the
rotameter connection. Do not reconnect.

the air line.

4E8

Init.

Date & Time

32.10' Open V 955 B to relieve the pressure between
V 955 B and V 955 A then close V 955 B,

32.11 Slowly open V 955 C and read the rotameter.
This is the leakage through V 9355 A,
Leakage .. Acceptable leakage

2 cc/min,

32,13 Close V 955 C, cap and tag closed.

(Water Room)

33.

34.

35.

Check CV 332 in the following manner. HP coverage
and gas masks are required. The RC should be at
20 psig.

33.1 Close V 332B.

33.2 Connect a 0-10 cc/min rotameter to the tap
upstream of CV 332,

33.3 Read the leakage through CV 332, Acceptable

leakage 2 scc/min. Leakage .

33.4 Disconnect the rotameter and cap the tap.

Check CV 342 in the following manner. HP coverage
and gas masks are required. The RC should be at
20 psig.

34.1 Close V 342,

34,2 Connect a 0-10 cc/min rotameter to the tap

upstream of CV 342,

34.3 Read the leakage through CV 342, Acceptable

leakage 2 scc/min, Leakage .

34.4 Disconnect the rotameter and cap the tap.

Check FCV 333 Al & A2 and V 334 in the following

manner, HP coverage and gas masks are required,

The RC should be at 20 psig.

(Liquid Waste Cell)

35.1 Connect a 0-10 cc/min rotameter to V 334
(rotameters outlet to the valve and the

valve closed).

36.

4E9

(Transmitter Room)

35.2 Open FCV 333 A2

(Liquid Waste Cell)

35.3 Pressurize V 334 with air to 20 psig.
Leakage . Acceptable leakage
2 scc/min,

(Transmitter Room)

35.4 Close FCV 333 A2

(Liguid Waste Cell)

35.5 Open V 334, This pressurizes FCV 333 A2.
Leakage « Acceptable leakage
2 scc/min,

35 .6 Close V 334 disconnect the air line and
reverse the rotameter connection.,

35.7 Connect a 1/4" Copper tube to the rotameter
and extend it into the ventilation duct
pullout,

35.8 Slowly open V 334 to relieve the pressure
then read the rotameter for leakage through
FCv 333 Al. Leakage . Acceptable
leakage 2 scc/min,

35.9 Close V 334, disconnect the tube and rota-
meter and cap the valve tag FCV 333 Al &
A2 and V 334 closed.

Check FCV 343 Al & A2 and V 344 in the following

manner. HP coverage and gas masks are required.

The RC'should be at 20 psig.

(Liquid Waste Cell)

36.1 Connect a 0-10 cc/min rotameter to V 344
(rotameter outlet .to the valve and the
valve closed) .

36.2 Connect the instrument air line with a
pressure regulator having a gauge of

0-50 psi minimum range to the rotameter.

Init.

Date & Time

4E10

Init.

Date & Time

(Transmitter Room)

36.3 Open FCV 343 A?2.

(Liquid Waste Cell) ‘

36 .4 Pressurize V 344 with air to 20 psig.
Leakage . Acceptable leakage

2 scec/min.,

(Transmitter Room)

36.5 Close FCV 343 A2

(Liquid Waste Cell)
36 .6 Open V 344. This pressurizes FCV 343 A2,
Leakage . Acceptable leakage

2 scc/min.

36.7 Close V 344, disconnect the air line and

reverse the rotameter connection.

36.8 Connect a 1/4" copper tube to the rotameter
and extend it into the ventilation duct

pullout,

36.9 Slowly open V 344 to relieve the pressure
then read the rotameter for leakage through
FCv 343 Al. Leakage . Acceptable

leakage 2 scc/min.,

36.10 Close V 344, disconnect the tube and rota-.C .-

meter and cap the valve, Tag FCV 343, Al
& A2 and V 344 closed.

(West Tunnel)

37. Check CV 965 in the following manner. Check while
the RC is at 20 psig. HP coverage and gas masks
required. |
37.1 Connect a 0-10 cc/min rotameter to the tap

upstream of CV 965 with a tube leading from

the rotameter to the ventilation duct,.

37.2 Read the rotameter for leakage. Leakage

. Acceptable leakage 2 scc/min.

1

37 .3

37 .4

4E11

Init.

Date & Time

Disconnect the rotameter, 1/4" tube, and

cap the tap.

Check lines RCC-6, RCC-10, and LT RC-c
with leak detector solutions. No leakage

acceptable,

(Electric Service Area)

38, Check CV 966 in the following manner while the

cell is at 20 psig. HP coverage required.,

38.1

38.2

38.3

38.4

Connect a 0-10 cc/min rotameter to the tap
upstream of CV 966 with a tube leading from

the rotameter to the ventilation duct.

Read the rotameter for leakage. Leakage

. Acceptable leakage 2 scc/min.

Disconnect the rotameter, tube, and cap the

tap.

Check lines DTC-6 and DTC-10 and LT DTC
with leak detector solution., No leakage

acceptable,

39. The following lines, valves, and containment items

will be leak checked periodically with the RC and
DIC at 20 psig. (Par. 40 through Par, 51)

(Special Equipment Room)
40. Check CV's 516 A & B, ESV 516 Al, ESV 516 A2 and

Cont. Encl. No. 1 in the following manner. HP

coverage and gas masks required.

40.1

40 .2

Open V CE-1 and check the valve outlet
with leak detector solution. No leakage
acceptable. Leakage may come from the helium

supply or RC which is at 20 psig.

If leakage occurs open CE No. 1 and leak
check the valves fitting and connections
leading to the RC with leak detector solu-

tions.

40.3

4E12

Init.

Date & Time

Repair the Leaks.

(Diesel House)

40 .4

Close V 500 G and allow the pressure

downstream to relieve itself.

(Special Equipment Room)

40.5
40.6

40.7

40.8

40.9

40.10

Close V 516,

Remove CV's 516 A & B from the system
and bench test at 40 psig with He. Leakage

. Acceptable leakage 1 scc/min.

Reinstall CV's 516 A & B and break line 516
upstream of ESV 516 Al and downstream of
ESV 516 A2,

Connect a He ¢yl.. to the downstream side of
ESV 516 A2 with a regulator and 0-50 psi
minimum range gauge, and connect a 0-10 cc/min

rotameter to the inlet side of ESV 516 Al.

Pressurize downstream of ESV 516 A2 to 40 psig
and read the rotameter. Acceptable leakage .

1 sce/min, Leakage .

Reconnect all lines.

(Diesel House)

40,11
40,12

40.13

40,14
40.15

Open V 500 G.

Check to see that FCV 516:..is open or par-
tially open,

Check line 516 (all valves fittings etc.)
from ESV 516 Al to V 516 with leak detector
solutions. No leakage acceptable. The

cover gas supply must be in operation at this
time and pressure on this section of the line.
See Section 4.4 of the MSRE Operating Pro-

cedures,

Open V 516 and close CE No. 1,

Connect the helium line to V CE-1 and

pressurize CE No., 1 to 20 psig.

41,

4E13

Init.

Date & Time

40,16 Check the entire enclosure and V CE-1 with
leak detector solution° No leakage accep-

table.

40,17 Close V CE-1 while the enclosure is pres-

surized and disconnect the line,

40.18 Check the outlet of V CE-1 for leaks with
leak detector solutions. No leakage accept-

able.,.

40,19 Open V CE-1 to relieve the pressure. Close
V CE-1 and tag closed.

Check CV's 592 A & B, CV's 593 A & B, CV's 596 A
& B, CV's 589 A & B, CV's 599 A & B, CV's 600 A
& B, HCV's 593 Bl, 593 B2 and 593 B3, HCV's 599

Bl, 599 B2, and 599 B3 and Containment Enclosure

2
No, 2 which contains .the above valves, in the
following manner. HP coverage and gas masks are
required.

(Special Equipment Room)

41 .1 Open V CE-2 and check the valve outlet with
leak detector solution. No leakage accept-

able. Leakage may come from the helium

supply or RC which is at 20 psig.

41 .2 If leakage occurs open CE No. 2 and leak
check the valves, fittings, and connections
leading to the RC to locate the leaks with

leak detector solution,

41.3 Repair the leaks.

(Transmitter Room)

l.4 | Close V 501.
Special Faguipment Room

41.5 Close V 589 C, V 592 C, V 593 C, V 596 C,
V 599 C, and V 600 C.

(Control Room)
41.6 Close HCV's 593 Bl, B2, B3, and open HCV's
593 B4, and B5 (S36 in OFF position) .

4E14

Init,

Date & Time

(Special Equipment Room)

41 .7

41,8

41 .9

41.10

. 41,11

41 .12

41,13

41 .14

_the A & B valves,

Remove CV's 589 A & B, 592 A & B, 593 A & B,
596 A & B, 599 A & B, and 600 A & B from the

system but do not break the connection between

Disconnect line 593 at the upstream side of
V 593 C and connect the He (CYL., with regu-
lator and gauge used in step 40.6,to line

593.

Pressurize through line 593 to 20 psig. This
pressurizes..the downstream side of HCV 593 Bl,

B2, and B3,

Connect a short piece of plastic tube to the
upstream side of HCV 593 Bl and check the
open end of this tube with leak detector solu-

tion. No leakage acceptable,.

Repeat step 41.10 on HCV 593 B2. No leakage

acceptable.

Repeat step 41.10 on HCV 593 B3. No leakage
acceptable,
Disconnect the He cyl... from line 593 and

reconnect the line to V 593 C.

Disconnect line 589 upstream of V 589 C
and connect the He cyl. with regulator and

gauge to it.

(Transmitter. Room)

41 .15

Hold S38 in Ref. Block position.

(Special Equipment Room)

41 .16

41,17

Pressurize line 589 to 20 psig and repeat:
step 41,10 on HCV 599 B2, No leakage accept-
able LS

Disconnect the He cyl. and reconnect line
589, Disconnect line 599 upstream of V

599 C and connect the He «¢yl. to this line,

4E15

Init,

Date & Time

{Transmitter Room)

41 .18 Hold S38 in the No. 1 Block position.

(Special Equipment Room)

41,19 Pressurize line 599 to 20 psig and repeat
step 41,10 on HCV 592 Bl., No leakage accept-
able. ,

41 ,20 Disconnect the He ¢yl. and reconnect line

599. Disconnect line 600 upstream of V 599

C and connect the He ¢yl.. to this line.

(Transmitter Room)

41,21 Hold S38 in No. 2 Block position,

{Transmitter Room) |

41 ,22 Pressurize line 600 to 20 psig and repeat
step 41.16 for HCV 599 B3. No leakage

acceptable.

41,23 Disconnect the He cyl. and reconnect the

line.

41 .24 Check CV's 5389 A & B simultaneously by con- . .°
necting the He cyl. . with regulator and
gauge to the downstream side of CV 589 B
and pressurizing to 20 psig. Connect a
short piece of plastic tube to the upstream
side of CV 589 A, Check for leakage over
the entire assembly with leak detector solu-

tion. No leakage acceptable,

41 ,25 Check CV's 592 A & B in the same manner
as used on CV's 589 A & B, No leakage accept-
able. ,

4] .26 Check CV's 593 A & B in the same manner
as used on CV's 589 A & B, No leakage accept-
able,n

41 ,27 Check CV's 596 A & B in the same manner as
used on CV's 589 A & B,. No leakage accept-
able..

(N.
42,

41 .32 Set S38 in the OFF position.

4E16

Init. Date & Time

4] ,28 Check CV's 599 A & B in the same manner as
used on CV's 589 A & B, No leakage accepti-
able.,

41 .29 Check CV's 600 A & B in the same manner as
used on CV's 589 A & B. No leakage accepi-
gble. .

41.,30 Install the check valves tested in 41 .24
through 41.29 back in the containment en-

closure.

(Transmitter Room)

41 .31 Open V 301,

{Control Room)

41 ,33 Set S36 in the No, 1 position.

(Special Equipment Room)
41 .34 Leak test all valves, fittings, and con-
nections in CE No. 2 with leak detector

. solution. No leakage acceptable,

41,35 Open V 589 C, 592 C, 593 :.C, 596 C, 599 C,
and 600 C,

41,36 Close CE No. 2 and connect the He cy. 1
with regulator and gauge to V CE-2,

41 .37 Pressurize the CE No., 2 to 20 psig and check
all possible sources of leaks with leak

detector solution. No leakage acceptable,

41 ,38 Close V CE-2 while the enclosure is pres-
surized and disconnect the He cyl.. . Test
vV CE-2 iniet for leakage with leak detecfor

solution. No leakage acceptable.

41 .39 Open V CE-2 to relieve the pressure, reclose

and tag the valve closed.

Elec. Ser., Area)
Check CV's 519 A & B, HCV's 519 A & B and Contain-
ment Enclosure No. 6 in the following manner. HP

coverage and gas masks are required.
ho,1

ho.2

42,3
koL
42,5

LWELT

Init.

Date & Time

Open V CE-6 and check the outlet of this
valve with leak detector solution. DNo leak-
age acceptable. ZLeakage may come from the

helium supply or RC which is at 20 psig.

If leakage occurs, open CE No. 6 and leak
check the valves, fittings, and connection
leading to the RC with leak detector

solution.

Repair the leaks.

Close V 519 A and V 519 B.

Close HCV's 519 A and B.

(N. Elec. Service Area)

Lo.6

ho.7

42.8

42.9

Connect a He cyl. with regulator and &
gauge having a 0-50 psi minimum range to

the tap upstream of V 519 B.

Break line 519 at the downstream side of
HCV 519 B, at the upstream side of HCV 519 A
and between HCV 519 A and B.

Connect a small piece of plastic tubing to
line 519 coming from the check valves.
Pressurize the check valves to 20 psig and
check for leakage at the plastic tubing with
leak detector solution. Teakage

Acceptable leskage 1 scc/min.

Connect the He cyl. with regulator and
gauge to the downstream side of HCV 519 B
and connect the short piece of plastic
tube to the upstream side. Pressurize
HCV 519 B to 20 psig and check for leakage
at the plastic tube with leak detector

solution. No leakage acceptable.

L3,

L4E18

Init.

Date & Time

42,10 Connect the He cyl. regulator and gauge to
the downstream side of HCV 519 A and the
plastic tube with leak detector solution.

No leakage acceptable.

42.11 Reconnect all breaks in line 519 and cap
the tap. Open V 519 A.

42.12 Open HCV's 519 A and B.

(N. Elec. Service Area)
42.13 Check all connections, valves, and fittings
from V 519 A to V 519 B with leak detector

solution. No leakage acceptable.

ho.14 Close V 519 A, close HCV's 519 A and B,
open V 519 B, and close CE No. 6.

42,15 Connect the He cyl. with regulator and gauge
to V CE-6 and pressurize to 20 psig.

42,16 Check CE No. 6 for leaks with leak detector

solution. No leakage acceptable.

42,17 Close V CE-6 with the enclosure pressurized

and disconnect the He cyl.

42,18 Check V CE-6 outlet for leaks with leak

detector solution. No leakage acceptable.

42.19 Open V CE-6 to relieve the pressure, close
V CE-6 and tag closed.

Check CV's 572 A & B and CE No. 3 in the following
manner. HP coverage and gas masks required.
(Control Room)

43.1 Open HCV 573 Al and set PIC 517 A for

5 psig.

(N. Elec. Ser. Area)
43.2 Open V 517.

43.3 Open HCV 572 Al by operating HCV 572 A2 with
a jumper from the 48v IC supply 1P3. Leave

open for 5 minutes and then close.

43 .4
43 .5
43 .6

43,7

43 .8

43.9

4E19

-Close V 517.

Open V CE-3, CE No. 3 and close V 3572,
Disconnect PT 572 B and connect the He
¢yl. with regulator and gauge to line
572 at this point. Uncap the tap upstream
of CV 572 A,

Pressurize the line to 20 psig and check
for leaks at the tap with leak detector
solution. No leakage acceptable,
Disconnect the He ¢yl. and reconnect

PT 572 B,

Open V 517.

(Control Room)

43.10

Set PIC 517 A for 20 psig.

(N, Elec. Ser. Area)

43 .11

43,12

43 .13

43 .14

43 .15

43 .16

43 ,17

Open HCV 572 Al by operating HCV 572 A2
with a jumper from the 48 VDC supply IP3.
Check all valves and fittings from HCV 572
Al to V 572 with leak detector solution,
No leakage acceptable.,

Close HCV 572 Al, open V 572 and close the
containment enclosure.

Connect the He c¢yl. with regulator and
gauge to V CE-3 and pressurize CE No, 3

to 20 psig.

Check the CE with leak detector solution.
No leakage acceptable, «

Close V CE-3 while the CE is pressurized
and disconnect the He .¢yl.. Check the
outlet of VCE-3 with leak detector solu-
tion, No leakage acceptable,

Open V CE-3 to relieve the pressure then

- close and tag closed.

Init,

Date & Time

4E20

Init.

Date & Time

44, Check CV's 574 A & B and CE No. 4 in the following
manner. HP coverage and gas masks required.
(Control Room)

44,1 Open HCV 575 Al and setrPIC 517 A for 5 psi,

(N, Elec. Ser, Area)
44,2 Open V 517.

44 .3 Open HCV 574 Al by operating HCV 574 A2 with
a jumper from the 48 V DC supply 1P3. Leave

open for 5 minutes and then close.

44 .4 Close V 517.

44 .5 Open V CE-4, CE-'No. 4 and close V 574,

44 .6 Disconnect PT 574 B and connect the He
eyl.. with regulator and gauge to line
574 at this point, Uncap the tap upstream
of CV 574 A,

44 .7 Pressurize the line to 20 psig and check
for leaks at the tap with leak detector .

solution, No leakage acceptable.

44 .8 Disconnect the He cyl.  and reconnect PT

574 B.

44 .9 Open V 517.

(Control Room)
44,10 Set PIC 517 A for 20 psig.

(N, Elec. Serv. Area)
44,11 Open HCV 574 Al by operating HCV 574 A2
with a jumper from the 48V .DC supply 1P3,.

44,12 Check all valves and fittings from HCV 574
Al to V 574 with leak detector solution.

No leakage acceptable.

44.13 Close HCV 574 Al, open V 574 and close
CE No. 4.

44 ,14 Connect the He cyl. with regulator and
gauge to V CE-4 and pressurize the CE to
20 psig.

415,

44 .15

44,16

44,17

Check

4E21

Init.

Date & Time

Check the CE with leak detector solution.

No leakage acceptable,

Close V CE-4 while the CE is pressurized
and disconnect the He cyl.. Check the
outlet of V CE-4 with leak detector solu-

tion., No leakage acceptable,

Open V CE-4 to relieve the pressure then

close and tag closed.

CV's 576 A & B and CE No, 5 in the following

manner, HP coverage and gas masks required,

(Control Room)

45.1

Open HCV 577 Al and set PIC 517 A for 5 psi.

(N, Elec., Serv, Area)

45.2
45 .3

45 .4
45 .5
45,6

45,7

45.8

45.9

Open V 517.

Open HCV 576 Al by operating HCV 576 A2 with
a jumper from the 48V DC supply 1P3. Leave

open for 5 minutes and then close.

Close V 517,

Open V CE-5, CE No. 5 and close V 576,

Disconnect PT 576 B and connect the He cyl.
with regulator and gauge to line 576 at this
fioint. Uncap the tap upstream of CV 576 A,

Pressurize the line to 20 psig and check
for leak at the tap with leak detector solu-

tion., No leakage acceptable,

Disconnect the He cyl. and reconnect PT 576

Bo

Open V 517,

(Control Room)

453.10

Set PIC 517 A for 20 psig.

(N. Elec., Serv, Area)

45.11

Open HCV 576 Al by operating HCV 576 A2 with
a jumper from the 48V DC supply 1P3,

46,

47,

48,

4E22

Init,

Date & Time

45,12 Check all valves and fittings from HCV 576 .
Al to V 576 with leak détector solution. No

leakage acceptable, .

45.13 Close HCV 576 Al, open V 576 and close CE
No, 5.

45.14 Connect the He cyl. with regulator and
gauge to V CE-5 and pressurize the CE to
20 psig.

45,15 Check the CE with leak detector solution.

No leakage acceptable,

45,16 Close V CE~S while the CE is. pressurized
and disconnect the He : ¢yl. Check the
outlet of V CE-5 with leak detector solu-

tion, No leakage acceptable.

45,17 Open V CE-5 to relieve the pressure then

close and tag closed.

Tables 4.1 and 4.2 of the MSRE Design and Opera-
tions Report lists all the penetrations of the

RC and DTC., Using a copy of these tables as a
check sheet, check each line through these pene-
trations at the point where it leaves the penetra-
tion, except lines 200 in penetrations XII, and
201 in XIX, and check all accessible penetration
welds with leak detector solution while the cells

are at 20 psig for leak testing.

Check the blind flange on line 918 in the follow-
ing manner. Gas masks and HP coverage required.

(Special Equipment Room)

47 .1 With the RC at 20 psig check the flange with

leak detector solution. No leakage accept-

able,

Check HCV 565 Al in the following manner, HP
coverage and gas masks required. This test is

made while the RC is at 20 psig.

Lo,

50.

LE23

Init.

‘Date & Time

(Control Room) | |
48.1 Close HCV 656 Al by HS 565 A,

(Vent House)
4L8.2 Open V 566.

48.3 Connect a 0-10 cc/min rotemeter to V 565 B
(rotameter inlet to valve) and open V 565 B.
Read the rotameter. Acceptable leakage
5 scc/min. |
48.4 Disconnect the rotameter and cap V 565 B,
open V 566. |

Check CV's 802, 803 in the following menner when

the vapor condensing system is at 20 psig.

(Water Room)
49.1 Close V 802 A, 803, 883.

49.2 Open V 802 B.

49.3 Remove the cap on the tap upstream of V 803
and catch the leakage through CV 802. Accept-
able leakage 5 cc/min. Leakage

4o,k Close V 802 B and open V 803.

49.5 Catch the leakage through CV 803 at the
tap upstream of V 803. Acceptable leakage
5 ee/min. Ileakage

49.6 Close V 803, cap the tap and open V 802 A.
Check HSVRC E 1, BSVRC E 2, PT RC A, PAT RC E and
the equalizing valve across PAdT RC E in the follow-
ing manner. HP coverage and gas masks are required.
50.1 Open HSV RC E 1, HSV RC E 2 and the

equalizing valve across PdT RC E.

50.2 Check with leak detector solution all con-
nections in the piping connecting HSV RC E 1,
HSV RC E 2, PT RC A, PAT RC E and the equaliz-
ing valve across PdT RC E and check the above
item where leakage is possible. DNo leakage

acceptable.

S51.

52,

4E24

Check HV RC B, HV RC G, HV RC F the CV's in series
with these valves, PxM RC B, PxM RC F, PxM RC G,
PSS RC B, PSS RC F, PSS RC G, PI RC B, PI RC F, and
PI RC G in the following manner. HP coverage and
gas masks required,

51,1 Close HV RC B, HV RC G, and HV RC F.

Init.

Date & Time

51.2 Disconnect the lines to these valves at the
upstream side and check with leak detector

solution. No leakage acceptable.

Check leakage from the thermocouple pressuri-
zation headers when the reactor and drain tank
cells are at 20 psig. Proceéed as follows:

52.1 Close inlet wvalves to each header.

52.2 Open each vent to bleed off pressure.

52.3 Close vents and record pressure and time.

52.4 After 4 hours record pressures and calcu-

late leak rate.

3.

LE25

Init.

Date & Time

Check 9020-1 Block Valve in NESA and the vent lines
connected to it in the following manner. The fuel
system must be empty, HP coverage ?nd gas mask re-
quired.

(Control Room)

53.1 Jumper the block valve closed.

(NESA)

53.2 Connect an Nz cylinder to the tap upstream
of the block valve with a regulator and 0-50
psi minimum range pressure gauge and

pressurize the header to 20 psig.

53.3 Check the following lines with leak detector
solution from the header to the penetrations.
No leakage accéptable.

Line 5hl-k

Line 5hk5-L4

Iine 546~k

Line 573-L

Line 575-L4

Line 577-k

Line FFT C1 - 5

Line FFT C2 - 5

Line FD 1 C1 - 5

Line FD1 C2 - 5

Line FD2 C1 - 5

Line FD2 C2 - 5

53.4 Disconnect line 9020-1 where it joins the
ventilation duct and connect a 0-10 cc/min
rotameter to it with line 9020-1 at 20 psig

upstream of the block valve.

53.5 Read the rotameter. Acceptable leakage
10 scc/min, Ieakage

53.6 Disconnect the Nz cyl., cap the tap, and
reconnect line 9020-1 to the ventilation

duct.

5.

25

LE26

Init.

Date & Time

Check 9020-1 block valve in SESA and the vent lines
connected to it in the following manner. The fuel
system must be empty, HP coverage and gas masks
are required.

(Control Room)

54,1 Jumper (the block valve) closed.

(SESA)

54,2 Connect an Nz cylinder to the tap upstream
of the block valve with a regulator and 0-50
psi minimum range pressure gauge and

pressurize the header to 20 psig.

54.3 Check the following lines with leak detector
solution from the header to the penetrations.
No leakage acceptable,

Line 903-4

Line 915-L4

Line 523-L4

Line 956-L

Line 961-L4

Line 962-4

Line 963-4

54L.4L Disconnect line 9020-1 where it joins the
ventilation duct and connect a 0-10 ce¢/min
rotameter to it with line 9020-1 at 20 psig
upstream of the block valve.

54.5 Read the rotameter. Acceptable leakage

10 scc/min. Leakage

54.6 Disconnect the No cylinder, cap the tap and
reconnect line 9020-1 to the ventilation
duct.

Check the fuel pump and coolant pump oil system
for containment in the following manner. HP
coverage and gas masks are required.

(Service Tunnel)

55.1 Close V 513A, V 711, V TO3A, V 762 A, B, &

C, V 716, V 706, V 590, V 535.
25

25

2

3

LEDT

Init.

Date & Time

Connect a He cyl. with regulator and 0-50
psi minimum range pressure gauge to the tap
upstream of PCV 513 A2.

Connect a 0-10 cc/min rotameter to the tap

upstream of CV 513.

(Control Room)

55.4 Set PIC 513 A for 25 psig.

(Service Tunnel)

55
.6

55

55.

55,

55.

55.

55

25

p

T

9

10

11

'12

Open V 513 B and V 535 A.

Pressurize 0T-1 to 20 psig with the He.

Read the rotameter upstream of CV 513.
Acceptable leakage 5 scc/min. Leakage

Open V 71l and check the disconnect upstream
of CV 71l for leakage with leak detector
solution. No leakage acceptable.

Reclose V T11.

Check V 716, T03C & D, 762 B & C for visible
oil leakage. No leakage acceptable,

Connect a 0-10 cc/min rotameter to the tap

downstream of PCV 513 AZ2.

Read the rotameter. Acceptable leakage

5 scc/min. Leakage

Turn off the He, disconnect the rotameter
downstream of PCV 513 A2 and cap the tap.
Open V 535 B to relieve the pressure

and close V 535 B.

55.13 Disconnect the He cyl. and reinstall the

rotameter downstream of PCV 513 A2.

(Control Room)

55.14 Set PIC 513 A for O psig.

(Service Tunnel)

55.15 Open V 513 A, read the rotameter downstream

of PCV 513 A2, This is the leakage through
PCV 513 Al from the He supply line 510 at
95.15

55 .16

55 .17

55.18

35.19

4E28

" Init.

Date & Time

(Continued)

40 psig. Acceptable leakage 10 scc/min,

Leakage .
Close V 513 A, open V 535 B to relieve the

pressure then close V 335 B.

Close V 510 A, V 761, V 753, V 766, V 756,
vV 591, V 534 B.

Connect a He c¢yl. with regulator and a 0-50
psi minimum range pressure gauge to the tap

upstream of CV 510.

Connect a 0-10 cc/min rotameter to the tap

upstream of CV 510.

(Control Room)

55.20

Set PIC 510 A for 25 psig.

(Service Tunnel)

55.21
55.22
55.23

35 .24

55.25

95 .26

95.27

55.28

Open V 510 B and V 534 A,

Pressurize OT-2 to 20 psig-with the He.

Read the rotameter upstream of CV 510,

Acceptable leakage 5 scc/min. Leakage .

Open V 761 and check the disconnect upstream
of CV 761 for leakage with leak detector
solution. No leakage acceptable, Reclose

V 761.

Check V 766, V 753 D for visible oil leakage.

No leakage acceptable.

Connect a 0-10 cc/min rotameter to the tap

downstream of PCV 510 A2,

Read the rotameter, Acceptable leakage

5 scc/min. Leakage, .

Turn off the He, disconnect the rotameter
downstream of PCV 510 A2 and cap the tap.
Open V 534 to relieve the pressure and close

vV 535 B.

95 .29

4E29

Init,

Date & Time

Disconnect the He cyl. and reinstall the

rotameter downstream of PCV 510 A2,

(Control Room)

55 .30
55.31

55 .32

55 .33

Set PIC 510 A for O psig.

Open V 510 A, read the rotameter downstream
of PCV 510 A2, This is the leakage through
PCV 510 Al from the He supply at 40 psig.
Acceptable leakage 10 scc/min., Leave the
rotameter connected to check CV 534, Leak-

age .

Close V 510 A, open V 534 B to relieve the

pressure then close V 534 B,

Close V's 534 A & B and 535 A,

(Vent House)

55 .34

95.35

Close V 560 B, connect a He cyl. with
regulator and a 0-50 psi minimum range

gauge to V 560 A,

Open V 560 A and pressurize the line to
20 psig.

(Service Tunnel)

29 .36

595 .37

55 .38

55 .39

55 .40

Open V 534 B and read the rotameter downstream
of PCV 510 A2, Acceptable leakage 5 scc/nmin,

Leakage °

Close V 534 B disconnect the rotameter. Cap

the tap and open V 534 B,

Connect the rotameter to the tap upstream of

CV 535 and cpen V 535 B,

Read the rotameter for leakage through CV
535, Acceptable leakage 5 scc/min. Leak-

age .

Close V 3535 B, Disconnect the rotameter,

cap the tap and open V 535 B,

56.

58.

LE30

Init. Date & Time

(Vent House)
55.41 Close V 5604, disconnect the He eyl., cap
the valve outlet and open V 560 B.

Check the following valves, fittings, lines, etc.,

with the RC at atmospheric pressure.

. To check HSV FD1 C1 A and line to WT FD1 Cl the

fuel systems must be empty. HP coverage and gas

masks are required.

(ESA)

57T.1 Disconnect line FD1 Cl-27 at HSV FD1 Cl1 A
and plug the line temporarily to stop air

leakage.

(Transmitter Room)
57.2 Disconnect line FD1 Cl-1 at TB 3 x 30.

57.3 Connect a 0-10 cc/min rotameter and Nz
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD1 C1 A and pressurize to LO psig.

57.4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage

(ESA)

57.5 Reconnect line FD1l C1l-27 to HSV FD1 C1 A
while line FD1 Cl1l-1 is at 40 psig. Leak
check line FD1 Cl-1 from HSV FD1 C1l A to
the penetration with leak detector solu-

tion. No leakage acceptable.

(Transmitter Room)
57.6 Disconnect Nz cyl. and reconnect line FD1

Cl-1.

To check HS5V FD1 C1l B and line to WT FDL Cl the
fuel system must be empty. HP coverage and gas

masks are required.
4E31

Init, Date & Time

(ESA)
58.1 Disconnect line FD1 C1-28 at HSV FD1 C1 B
and plug the line temporarily to stop air

leakage,

8.2 Disconnect line FD1 Cl1-2 at TD3 x 29,

58.3 Connect a 0-10 cc/min rotameter and Ny
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD1 Cl1 B and pressurize to 40 psig.

58 .4 Read the rotameter. Acceptable leakage

4 scc/min., Leakage o

58 .5 Reconnect line FD1 Cl1-28 to HSV FDl1 Cl1 B
while Line FD1 Cl-2 is at 40 psig. Leak:
check line FD1 Cl1-2 from HSV ¥FD1 Cl B to
the penetration with leak detector solution.

No leakage acceptable.

(Transmitter Room)
58.6 Disconnect the N, cyl. . and reconnect line

Fbl C1-2,

59. To check HSV FD1 C1 C and line to FDl1 the fuel
systems must be empty. HP coverage and gas masks
are required,

(ESA)
59.1 Disconnect line FD1 Cl1-29 at HSV FD 1 C1 C
and plug the line temporarily to stop air

leakage.

(Transmitter Room)

59.2 Disconnect line FD1 Cl1-3 at TB3 x 28,

59.3 Connect a 0-10 cc/min rotameter and Nog
¢yl.  with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD1 C1 C and pressurize to 40 psig,

59 .4 Read the rotameter. Acceptable leakage

4 scc/min., Leakage R

60,

61,

4E32

Init,

Date & Time

(ESA)

59.5 Reconnect line FD1 Cl1-29 to HSV FD1 Cl1 C
while line FD1 C1-3 is at 40 psig. Leak
check line FD1 C1-3 from HSV FD1 Cl1l C to
the penetration with leak detector solution,

No leakage acceptable.

(Transmitter Room)
59.6 Disconnect the No ¢yl. and reconnect line

FD1 C1-3.

To check HSV FD1 C1 D and line to WT FD1 Cl the

fuel system must be empty. HP coverage and gas : ..

masks are required,

(ESA)

60,1 Disconnect line FD1 C1-30 at HSV FD1 C1 D
and plug the line temporarily to stop air

leakage.

60.2 Connect a 0-10 cc/min rotameter and N2 eyls -
with regulator and 0-50 psig minimum range
gauge to the outlet of HSV FD1 C1 D and

pressurize to 40 psig.

60,3 Read the rotameter. Acceptable leakage

4 scc/min, Leakage .

60 .4 Reconnect line FD1 Cl1-30 to HSV FD1 C1 D
while line FD1 Cl-8 is at 40 psig. Leak
check line FD1. Cl-8 from HSV FD1 Cl1 D to
the penetration with leak detector solution.

No leakage acceptable.

To check HSV FD1 C2 A and line to WT FD1 C2 the fuel
system must be empty. HP coverage and gas masks are
required.
(ESA)
61.1 Disconnect line FD1 C2-12 at HSV FD1 C2 A

and plug the line temporarily to stop air

leakage.

62.

Y

(Transmitter Room)
61.2 Disconnect line FD1 C2-1 at TB3 x 2L.
61.3 Comnect & 0-10 cc/min rotameter and Np
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the 1line to
HSV FD1 C2 A and pressurize to 40 psig.
61.4 Read the rotameter. Acce@table leakage
b sce/min. Leakage

(ESA)

61.5 Reconnect line FD1 C2-12 to HSV FD1 C2 A
while line FD1 C2-1 is at 40O psig. ILeak
check line FD1 C2-1 from HSV FDL C2 A to

the penetration with leak detector solution.

No leakage acceptable.
(Transmitter Room)
61.6 Disconnect Nz cyl. and reconnect line
FD1 C2-1.
To check HSV FDL C2 B and line to WT FD1 C2 the
fuel system must be empty. HP coverage and gas
masks are required.
(ESA)
62.1 Disconnect line FD1 C2-13 at HSV FDL C2 B
and plug the line temporarily to stop air
leakage.

4E-33
Date & Time

Init.

LE-34

' Init.' Date & Time

(Transmitter Room)

62.2 Disconnect line FD1 C2-2 at TB3 x 26,

62.3 Connect a 0-10 cc/min rotameter and N,
cyl.. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD1 C2 B and pressurize to 40 psig.

62.4 Read the rotameter. Acceptable leakage

4 scc/min., Leakage _ .

(ESA)

62.5 Reconnect line FD1 C2-13 to HSV FD1 C2 B
while line FD1 C2-2 is at 40 psig. Leak
check line FD1 C2-2 from HSV FD1 C2 B to
the penetration with leak detector solution,

No leakage acceptable.

(Transmitter Room)
62.6 Disconnect the N, c¢yl. and reconnect line
FD1 C2-2.

63. To check HSV FD1 C2 C and line to WI FD1 C2 the
fuel system must be empty HP coverage and gas masks
are required.,

(ESA)
63.1 Disconnect line FD1 C2-14 at HSV FD1 C2 C
and plug the line temporarily to stop air

leakage.

(Transmitter Room)

63.2 Disconnect line FD3 C2-3 at TB3 x 25.

63.3 Connect a 0-10 cc/min rotameter and Ny
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD1 C2 C and pressurize to 40 psig.

63 .4 Read the rotameter. Acceptable leakage

4 scc/min., Leakage

LE-35

Init. Date & Time

(ESA)

63 .5 Reconnect line FD1 C2-14 to HSV FD1 C2 C
while line FD1 C2-3 is at 40 psig. Leak
check line FD1 C2-3 . from HSV FD1 C2 C
to the penetration with leak detector solu-

tion. No leakage acceptable,

(Trahsmitter Room)
63 .6 Disconnect N2 ‘cyl. and reconnect line .-

FD1 C2-3,

64, To check HSV FD1 C2 D and lines to WI FD1 C2 the
fuel system must be empty. HP coverage and gas
masks are required.,

(ESA)
64.1 Disconnect line FD1 C2-31 at HSV FD1 C2 D
and plug the line temporarily to stop air

leakage.

64.2 Connect a 0-10 cc/min rotameter and N2 L
with regulator and 0-50 psig minimum range
gauge to the outlet of HSV FD1 C2 D and

pressurize to 40 psig.

64.3 Read the rotameter, Acceptable leakage

4 scc/min. Leakage

64.4  Reconnect line FD1 C2-31 to HSV FD1 C2 D
while line FD1 C2-8 is at 40 psig. Leak
check line FDl C2-8 from HSV FD1 C2 D to
the penetration with leak detector solu-

tion. No leakage acceptable.

65. To check HSV FD2 C1 A and line to WT FD2 4 the fuel
system must be empty. HP coverage and gas masks
are required,

(ESA)
65.1 Disconnect line FD2 Cl1-27 at HSV FD 2 C1 A
and plug the line temporarily to stop air

leakage.

66,

LE-36

Init. Date & Time

(Transmitter Room)

65.2 Disconnect line FD2 Cl-1 at TB3 x 24,

65.3 Connect a 0-10 cc/min rotameter and N2
cyl. . with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV .-
FD2 C1 A and pressurize to 40 psig.

65 .4 Read the rotameter, Acceptable leakage

4 scc/min., Leakage .

65.95 Reconnect line FD2 C1-27 to HSV FD2 Cl1 A
while line FD2 Cl-1 is at 40 psig. Leak
check line FD2 Cl-1 from HSV FD2 Cl A to
the penetration with leak detector solu-

tion. No leakage acceptable.

(Transmitter Room)
65.6 Disconnect the Np cyl;. and reconnect line

FD2 Cl-1.

To check HSV FD2 Cl B and line to WT FD2 Cl the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

66,1 Disconnect line FD2 C2-28 at HSV and plug

the line temporarily to stop air leakage.

(Transmitter. Room)

66 .2 Disconnect line FD2 Cl-2 at TB3 x 23.

66 .3 Connect a 0-10 cc/min rotameter and Ng
cyl.. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV

- FD2 C1 B and pressurize to 40 psig.
66 .4 Read the rotameter. Acceptable leakage

4 scc/min., Leakage .

66 .5 Reconnect line FD2 Cl1-28 to HSV FD2 Cl1 B
while line FD2 Cl-2 is at 40 psig. Leak
check line FD2 C1-2 from HSV FD2 Cl B to
the penetration with leak detector soiu—

tion. No leakage acceptable.

67.

68.

(Transmitter Room)

66.6 Disconnect N, Cyl. and reconnect line
FD2 Cl1l-2,

To check HSV FD2 C1 C and line to WI FD2 Cl the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA) _

67 .1 Disconnect line FD2 C1-29 at HSV FD2 C1 C
and plug the line temporarily to stop air
leakage.

(Transmitter Room)

67.2 Disconnect line FD2 C1-3 at TB 3 x 22,

67.3 Comnnect a 0-10 cc/min rotameter and N,
cyl... with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD2 Cl C and pressurize to 40 psig.

67 .4 Read the rotameter. Acceptable leakage
4 scc/min, Leakage .

(ESA)

67 .5 Reconnect line FD2 C1-29 to HSV FD2 Cl1 C
while line FD2 C1-3 is at 40 psig., Leak
check line FD2 Cl-3 from HSV FD2 Cl1l C to
the penetration with leak detector solu-
tion. No leakage acceptable.

(Transmitter Room)

67.6 Disconnect No ¢yl. and reconnect line

| FD2 C1-3.

To check HSV FD2 C1 D and line to WT FD2 Cl the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

68.1 Disconnect line FD2 Cl1-30 at HSV FD2 Cl1 D
and plug the line temporarily to stop air

leakage.

Init.

LE-37

Date & Time

69.

68.2 Connect a 0-10 cc/min rotameter and N, cyi.

with regulator and 0-50 psig minimum range
gauge to the outlet of HSV FD2 Cl D and
pressurize to 40 psig.

68.3 Read the rotameter. Acceptable leakage
4 scc/min. Leakage. -

68 .4 Reconnect line FD2 C1-30 to HSV FD2 Cl1 D
while line FD2 C1-8 is at 40 psig. Leak
check line FD2 C1-8 from HSV FD2 C1 D to

the penetration with leak detector solution.

No leakage acceptable,

To check HSV FD2 C2 A and line to WT FD2 C2 the

fuel system must be empty. HP coverage and gas ' -

masks are required.

(ESA)

69.1 Disconnect line FD2 C2-12 at HSV FD2 C2 A
and plug the line temporarily to stop air
leakage.

(Transmitter Room)

69 .2 Disconnect line FD2 C2-1 at TB3 x 21.

69 .3 Connect a 0-10 cc/min rotameter and
No ¢yli with regulator and 0-50 psig
minimum range gauge to the end of the line
to HSV FD2 C2 A and pressurize to 40 psig.

69 .4 Read the rotameter. Acceptable leakage
4 scc/min, Leakage °

(ESA)

69 .5 Reconnect line FD2 C2-12 to HSV FD2 C2 A
while line FD2 C2-1 is at 40 psig. Leak
check line FD2 C2-1 from HSV FD2 C2 A.to
the penetration with leak detector solu-
tion. No leakage acceptable.

(Transmitter Room)

69.6 Disconnect N2 ¢yl. and reconnect line

FD2 C2-1.

LE-38

Init. - Date & Time

70,

71.

To check HSV FD2 C2 B and line to WI FD2 C2 the
fuel system must be empty. HP coverage and gas
masks are required.

(ESA)

70.1 Disconnect line FD2 C2-13 at HSV FD2 C2 B
and plug the line temporarily to stop air
leakage.

{Transmitter Room)

70.2 Disconnect line FD2 C2-2 at TB3 x 20,

70.3 Connect a 0-10 cc/min rotameter and Ny
cyl. . with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD2 C2 B and pressurize to 40 psig.

70.4 Read the rotameter. Acceptable leakage
4 sce/min. Leakage .

(ESA)

70.5 Reconnect line FD2 C2-13 to HSV FD2 C2 B
while line FD2 C2-2 is at 40 psig. Leak
check line FD2 C2-2 from HSV FD2 C2 B to
the penetration with leak detector solu-
tion. No leakage acceptable.,

(Transmitter Room)

70.6 Disconnect Ng -¢cyl. and reconnect line
FD2 C2

To check HSV FD2 C2 C and line to WI FD2 C2 the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

71.1 Disconnect line FD2 C2-29 at HSV FD2 C2 C
and plug the line temporarily:to stop air
leakage.

{Transmitter Room)

71.2 Disconnect 1ine FD2 C2-3 at TB3 x 19.

Init.

LE-39

Date & Time

72.

71.3 Connect a 0-10 cc/min rotameter and N2
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FD2 C2 C and pressurize to 40 psig.

Init.

LE-40

Date & Time

Pl

71 .4 Read the rotameter. Acceptable leakage
4 scc/min. Leakage o

(ESA)

71.5 Reconnect line FD2 C2-29 to HSV FD2 C2 C
while line FD2 C2-3 is at 40 psig. Leak
check line FD2 C2-3 from HSV FD2 C2 C and

pressurize to 40 psig.

(Transmitter Room)
71.6 Disconnect N, ~¢yl. and reconnect line FD2

Cc2-3,

To check HSV FD2 C2 D and line to WT FD2 C2 the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

72.1 Disconnect line FD2 C2-31 at HSV FD2 C2 D
and plug the line temporarily to stop air

leakage.

72,2 Connect a 0-10 cc/min rotameter and Ng cyl...
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV FFT Cl1 A

and pressurize to 40 psig.

72.3 Read the rotameter, Acceptable leakage

4 sce/min, Leakage .

72 .4 Reconnect line FD2 C2-31 to HSV FD2 C2D
while line FD2 C2-8 is at 40 psig. Leak
check line FD2 C2-8 from HSV FD2 D to the
penetration with leak detector solution.

No leakage acceptable.

T3.

Th.

To check HSV FFT C1l A and line to WT FFT Cl1 the

4E-41

Init. Date & Time

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

73.1

| leakage.

Disconnect lina FFT C1-17 at HSV FFT C1 A
and plug the line temporarily to stop air

(Transmitter Room)

73.2
T3.3

73.b

3.5

73.6

Disconnect line FFT Cl1l-1 at TB 3 x 16.

Connect a 0-10 cc/min rotameter and Nz cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV FFT Cl A

and pressurize to 40 psig.

Read the rotameter. Acceptable leakage
4 scc/min. ILeakage

Reconnect line FFT Cl-17 to HSV FFT C1 A
while line FFT Cl-1 is at 4O psig. Leak
check line FFT Cl-1 from HSV FFT Cl A to
the penetration with leak detector solution.

No leakage acceptable.

Disconnect Nz cyl. and reconnect line FFT Cl-1.

To check HSV FFT C1 B and line to WT FFT Cl the

fuel system must be empty. HP coverage and gas

ma.sks are required.

(EsSA)

Th.1

Disconnect line FFT C1-18 at HSV FFT Cl B
and plug the line temporarily to stop air

leakage.

(Transmitter Room)

Th.2
Th.3

Disconnect line FFT Cl-2 at TB 3 x 18.

Connect a 0-10 cc/min rotameter and No
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV

FFT C1 B and pressurize to 40 psig.
5.

75.2 Disconnect line FFT C1-3 at TB3 x 17.

Init.

LE-Lk2

Date & Time

74 .4 Read the rotameter. Acceptable leakage
L sce/min. Leakage .

(ESa)

74.5 Reconnect line FFT C1-18 to HSV FFT C1 B
while line FFT Cl-2 is at 40 psig. Leak
check line FFT Cil-2 from HSV FFT C1l B to
the penetration with leak detector solution.

No leakage acceptable.

(Transmitter Room)
T .6 Disconnect N, cyl. and reconnect line FFT
Cl-1l.

To check HSV FFT C1 C and line to WI FFT C1,

the fuel system must be empty. HP coverage and

gas masks are required.

(EsA)

75.1 Disconnect line FFT Cl-19 at HSV and plug
the line temporarily to stop air leakage.

(Transmitter Room)

75.3 Connect a 0-10 cc/min rotameter and Ny
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FFT Cl C and pressurize to 40 psig.

75.4 Read the rotameter. Acceptable leakage
4 sce/min. Leakage .

(EsA)

75.5 Reconnect line FFT Cl1-19 to HSV FFT Cl C
while line FFT Cl-3 is at 40 psig. Leak
check line FFT Cl-3 from HSV FFT Cl C to
the penetration with leak detector solution.

No leakage acceptable.

(Transmitter Room)
75.6 Disconnect the Ny cyl. and reconnect line

FFT C1-3.

76.

77.

LE-L3

Init., Date & Time

To check HSV FFT Cl1 D and line to WT FFT Cl1 the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

76.1 Disconnect line FFT Cl1-20 at HSV FFT Cl1l D
and plug the line temporarily to stop air

leakage.

76.2 Connect a 0-10 cc/min rotameter and Ny cyl...
with regulator and 0-50 psig minimum range
gauge to the outlet of HSV FFT Cl D and

pressurize to 40 psig.

76.3 Read the rotameter, Acceptable leakage

4 scc/min., . Leakage .

76.4 Reconnect line FFT Cl- 20 to HSV FFT C1 D
while line FFT Cl- 8 is at 40 psig. Leak
check line FFT Cl- 8 from HSV FFT Cl D to
the penetration with leak detector solu-

tion. No leakage acceptable.

To check HSV FFT C2 A and line to WT FFT C2 the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

77.1 Disconnect line FFT C2-12 at HSV FFT C2 A
and plug the line temporarily to stop air

leakage.,

(Transmitter Room)

77 .2 Disconnect line FFT C2-1 at TB3 x 13.

77.3 Connect a 0-10 cc/min rotameter and N2
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to

HSV FFT C2 A and pressurize to 40 psig.

77 .4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage .

78,

(ESA)

77 .5 Reconnect line FFT C2-12 to HSV FFT C2 A
while line FFT C2-1 is at 40 psig. Leak
check line FFT C2-1 from HSV FFT C2 A to
the penetration with leak detector solu-
tion. No leakage acceptable.

(Transmitter Room)

77 .6 Disconnect the N2 c¥l. and reconnect line
FFT C2 1.

To check HSV FFT C2 B and 1line to WT FFT C2 the

fuel system must be empty. HP coverage and gas

masks are required.

(ESA)

78.1 Disconnect line FFT C2-13 at HSV FFT C2 B
and plug the line temporarily to stop air
leakage.

(Transmitter Room)

78.2 Disconnect line FFT C2-2 at TB3 x 15,

78.3 Connect a 0=10 cc/min rotameter and No
{cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FFT C2 B and pressurize to 40 psig.

78 .4 Read the rotameter, Acceptable. leakage
4 sce/min, Leakage .

(ESA)

78 .5 Reconnect line FFT C2-13 to HSV FFT C2 B
while line FFT C2-2 is at 40 psig. Leak
check line FFT C2-2 from HSV FFT C2 B to
the penetration with leak detector solu-
tion. No leakage acceptable.

(Transmitter Room)

78.6 Disconnect the N, ¢yl. and reconnect line

FFT C2-2.

Init.

YE-Lk

‘Date & Time

79.

80.

LE-U5

Init. Date & Time

To check HSV FFT C2 C and line to WI FFT C2 the

fuel system must be empty. HP coverage and gas

mgsks are required.

(ESA)

79.1 Disconnect line FFT C2-14 at HSV FFT C2 6
and plug the line temporarily to stop air

leakage.

(Transmitter Room)

79.2 Disconnect line FFT C2-3 at TB3 x 14.

79 .3 Connect a 0-10 cc/min rotameter and Nz'
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
FFT C2 C and pressurize to 40 psig.

79.4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage .

(ESA)

79.5 Reconnect line FFT C2~14 to HSV FFT C2 C
while line FFT C2-3 is at 40 psig. Leak
check line FFT C2-3 from HSV FFT C2 C to
the penetration with leak detector solu-

tion. No leakage acceptable.

(Transmitter Room)
79 .6 Disconnect N, ¢cyl. and reconnect line

FFT C2-3.

To check HSV FFT C2 D and line to WI FFT C2 the

fuel system must be empty. HP coverage and gas .

masks are required.

(ESA) ,

80.1 Disconnect line FFT C2-21 at HSV FFT C2 D
and plug the line temporarily to stop air

leaKage.

80.2 Connect a 0-10 cc¢/min rotameter and 0-50
psig minimum range gauge to the outlet of

HSV FFT C2 D and pressurize to 40 psig.

81.

80.3

80.4

Init.

LE-L46

_Date & Time

Read the rotameter. Acceptable leakage

4 sce/min. Leakage .

Reconnect line FFT C2 21 to HSV FFT C2 D
while line FFT C2-8 is at 40 psig. Leak
check line FFT C2-8 from HSV FFT C2 D to
the penetration with leak detector solution.

No leakage acceptable.

To check HSV 544- ‘A and lines to HSV 544 Al the fuel

system must be empty. HP coverage and gas masks

are required.,

(ESA)
8l.1

Disconnect line 544-3 at HSV 544 A and plug

the line temporarily to stop air leakage.

(Transmitter Room)

81.2

81.3

81 .4

(ESA)
81.5

Close the valve in line 544-1 off header
9007-4 and disconnect line 544-2 at SR x 26.

Connect a 0-10 cc/min rotameter and Ng cyl..
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 544 A

and pressurize to 40 psig.

Read the rotameter. Acceptable leakage

4 sce/min, Leakage .

Reconnect line 544-3 to HSV 544 A while

line 544-2 is at 40 psig. Leak check line
544-2 from HSV 544 A to the penetration with
leak detector solution. No leakage accept-

able.

(Transmitter Room)

8l.6

Disconnect the N, -cyl.., reconnect line
544-2 and open the valve in line 544-1 off
header 9007-4.

LWE-47

Init. Date & Time

82. To check HSV 545 A and lines to HCV 545 the fuel

83.

system must be empty. HP coverage and gas masks
are required.

(ESA)

82.1 Disconnect line 545-3 at HSV 545 A and plug

the line temporarily to stop air leakage.

(Trxansmitter Room)
82.2 Close the valve in line 545-1 off header
9007-4 and disconnect line 545-2 at SR x 29,

82.3 Connect a 0-10 cc/min rotameter and Ng cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 545 A

and pressurize to 40 psig.

82.4 Read the rotameter. Acceptable leakage

4 scc/min, Leakage . .

(ESA)

82.5 Reconnect line 545-3 to HSV 545 A while
line 545-2 is at 40 psig. Leak check line
545-2 from HSV 545 A to the penetration
with leak detector solution. No leakage

acceptable,

(Transmitter Room).

82.6 Disconnect N C¥l., reconnect line 545-2,

'~ and open the valve in line 545-1 off. header

9007-4

To check HSV 546 A and lines to HCV 546 Al the fuel
system must be empty. HP coverage and gas masks
are required.

(ESA)

83.1 Disconnect line 546-3 at HSV 546-'A and plug

the line temporarily to stop air leakage.

(Transmitter Room)
83.2 Close the valve in line 546-]1 off header
9007-4 and disconnect line 546-2 at SR x 23.

8k,

Init.

LE-48

Date & Time

83.3 Connect a 0-10 cc/min rotameter and N- cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 546 A

and pressurize to 40 psig.

83.4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage

(ESA)

83.5 Reconnect line 546-3 to HSV 546 A while line
546-2 is at LO psig. Leak check line 546-2
from HSV 546 A to the penetration with leak
detector solution. No leakage acceptable.

(Transmitter Room)

83.6 Disconnect the Ns cyl., recomnect line 546-2
and open the valve in line 546-1 off
header 9007-k.

To check HSV 573 A and lines to HCV 573 Al the fuel
system must be empty. HP coverage and gas masks
are required.
(ESA)
84.1 Disconnect line 573-3 at HSV and plug the
line temporarily to stop air leakage. |
(Transmitter Room)
84.2 Close the valve in line 573-1 off header
9007-4 and disconnect line 573-2 at
SR x 32.

84.3 Connect a 0-10 cc/min rotameter and Nz cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 573 A

and pressurize to 40 psig.

84.4  Read the rotameter. Acceptable leakage

L sce/min. Leakage

85.

86.

4E-49

Init., Date & Time

(ESA)

84 .5 Reconnect line 573-3 to HSV 573 A while line
573-2 is at 40 psig. Leak check line 573-2
from HSV 573 A to the penetration with leak

detector solution. No leakage acceptable,

84,6 Disconnect N, cyl.. Reconnect line 573-2
and open the valve in line 573-1 off header

9007-4,

To check HSV 575 A and line to HCV 575 the fuel
system must be empty. HP coverage and gas masks
are required,

(ESA)

85.1 Disconnect line 575-3 at HSV 575 A and plug

....theé line temporarily to stop air leakage.

(Transmitter Room)
85.2 Close the valve in line 575-1 off header
9007-4 and disconnect line 575-2 at SR x 35,

85.3 Connect a 0-10 cc/min rotameter and Ng cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 575 A

and pressurize to 40 psig.

85.4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage o

To check HSV 577 A and lines to HCV 577 Al, the
fuel system must be empty. HP coverage and gas
masks are required.

(£s4)

86,1 Disconnect line 577-3 at HSV 577 A and plug

the line temporarily to stop air leakage.

(Service Room)
86.2 Close the valve in line 577-1 off header
9007-4 and disconnect line 577-2 at SR x 38.

86,3 Connect a 0-10 cc/min rotameter and N, cyl. .

with regulator and 0-50 psig minimum range
87.

LE-50

Init. Date & Time

86.3 (Continued)
gauge to the end of the line to HSV 577 A

and pressurize to 40 psig.

86 .4 Read the rotameter., Acceptable leakage

4 scc/min. Leakage .

(ESA)

86.5 Reconnect line 577-3 to HSV 577 A while
line 577-2 is at 40 psig. Leak check line
577-2 from HSV 577 A to the penetration.
with leak detector solution. No leakage

acceptable,

(Transmitter Room)

86.6 Disconnect the N, ;Cylg, reconnect line
577-2, and open the valve in line 577-1
off header 9007-4,

To check HSV 903 A and lines to HCV 903 the fuel
system must be empty. HP coverage and gas masks
are required.

(SESA)

87.1 Disconnect line 903-3 at HSV 903 A and plug

the line temporarily to stop air leakage.

(Transmitter Room)
87 .2 Close the valve in line 903-1 off header
9008-2 and disconnect line 903-2 at TB6 x 6,

87.3 Connect 0-10 cc/min rotameter and No cyl..
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV-903-A

and pressurize to 40 psig.

87 .4 Read the rotameter., Acceptable leakage

4 scc/min., Leakage .

(SESA)

87.5 Reconnect line 903-3 to HSV 903 A while line
903-2 is at 40 psig. Leak check line 903-2
from HSV 903 A to the penetration with leak

detector solution, No leakage acceptable.

88.

89.

LE-51

Init. Date & Time

(Transmitter Room)

87.6 Disconnect Nz cyl., reconnect line 903-2;
open valve in line 903-1 off header 9008-2.

To check HSV 915 A and lines to HCV 915 A the fuel

system must be empty. HP coverage and gas masks are

required.
(EsSA)
88.1 Disconnect line 915-5 at HSV 915 A and plug

the line temporarily to stop air leakage.

(Transmitter Room)
88.2 Close the valve in line 915-1 off header 9008-2
"and disconnect line 915-3 at TB 6 x 12.

88.3 Connect a 0-10 cc/min rotameter and Np cyl.
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 915 A

and pressurize to 40 psig.

88.4 Read the rotameter. Acceptable leakage

4 scc/min. Leakage

(EsA)

88.5 Reconnect line 915-5 to HSV 915A while
line 915-3 is at 40 psig. Leak check line
915-3 from HSV 915 A to the penetration with
leak detector solution. No leakage

acceptable.

(Transmitter Room)

88.6 Disconnect Nz cyl., reconnect line line 915-3
and open the valve in line 915-1 off
header 9008-2.

To check HSV 956 A and line to HCV 956A the fuel
system must be empty. HP coverage and gas masks
are required.

(EsA)

89.1 Disconnect line 956-3 at HSV 956 A and plug

the line temporarily to stop air leakage.

0.

Init.

LRE-52

Date & Time

(Transmitter Room)

89.2 Close the valve in line 956-1

89.3 Connect a 0-10 cc/min rotameter and Nz cyl.
with regulator and 0-50 psig minimum
range gauge to the end of the line to

HSV 956 A and pressurize to 40 psig.

89.4 Read the rotameter. Acceptable leakage

L sce/min. Leakage

(ESA)

89.5 Reconnect line 956-3 to HSV 956-2 while
line 956-2 is at 40 psig. Ieak check line
956-2 from HSV 956 A to the penetration
with leak detector solution. No leakage
acceptable.

(Transmitter Room)
89.6 Disconnect Nz cyl. Reconnect line 956-2
and open valve in line 956-1 off header 9008-2.

To check HSV 960 Al, HSV 960 A2, FE 960 A and

line to these items, the fuel system must be

empty. HP coverage and gas masks are required.

(SESA)

90.1 Disconnect line 960-7 at HSV 960 Al and
plug the line temporarily to stop air

leakage.

90.2 Disconnect line 960-12 at SR x Tkh.

90.3 Connect a 0-10 cc/min rotameter and Np
cyl. with regulator and 0-50 psig minimum
range gauge to the end of the line to HSV
960 Al and pressurize to 40 psig.

9l.

LE-53

Init. Date & Time

90.4 Read the rotameter. Acceptable leakage
L sce/min. Leakage

(SESA)

90.5 Reconnect line 960-T7 to HSV 960 Al while
line 960-13 is at U0 psig. Ieak check line
960-12 from HSV 960 Al to the penetration

with leak detector solution. No leakage

xJ

acceptable.
90.6 While line 960-12 is at 40 psig, check line
960-9, FE 960 A, line 960-10 and line 960-8

with leak detector solution. No leakage

acceptable.
90.7 Disconnect the line from HSV 960 A2 to header
9020-1 at the valve and connect a 0-10 cc/min

rotameter to the valve while line 960-12 is
at L0 psig.
90.8 Read the rotameter. Acceptable leakage

4 scc/min. Leakage

(SESA and Transmitter Room)

90.9 Disconnect the Nz cyl. and reconnect lines
960-12 and the line from HSV 960 A, to header
9020-1 |

To check HSV 961 A and lines to HCV 961 Al the fuel

system must be empty. HP coverage and gas masks

are required.
(SESA)
91.1 Disconnect line 961-3 at HSV 961 A and plug

the line temporarily to stop air leakage.

(Transmitter Room)
91..2 Close the valve in line 961-1 off header
9008-2 and disconnect line 961-1 at TB 5 x 8.

92.

Init.

4E-54

Date & Time

91.3 Connect a 0-10 cc/min rotameter and Ng cylk..
with regulator and 0-50 psig minimum range
pressure gauge to the end of the line to HSV

961 A and pressurize the line to 40 psig.

91.4 Read the rotameter. Acceptable leakage

4 sce/min., Leakage .

(SESA)
91.5 Reconnect line 961-3 to HSV 961 A while line
961~-2 is at 40 psig.

91 .6 Leak check line 961-2 from HSV 961 A to the
penetration with leak detector solution. No

leakage acceptable,.

(Transmitter Room)

91.7 Disconnect NZ ¢y.l. . Reconnect line 961-2
and open valve in line 961-1 off header
9008-2.

To check HSV 919 Al, HSV 919 A2, FE 919 A, HSV
919 Bl, HSV 919 B2, and FE 919 B the fuel system
must be empty. HP coverage and gas masks are

required,

(Control Room)

92.1 Close the B port of HCV 919 A2,

(Transmitter Room)

92.2 Disconnect line 919-6 at TB7 x 3.

(SESA)
92.3 Disconnect line 919-7 at HSV 919 Al and
temporarily plug the line to stop air

leakage.

(Transmitter Room).

92 .4 Connect a 0-10 cc/min rotameter and N, eyl.
with regulator and 0-50 psig minimum range
pressure gauge to the end of“line 919-6 going

to HSV 919 Al and pressurize to 40 psig.

LE-55

Init, Date & Time

92.5 Read the rotameter. Acceptable leakage

4 scc/min; Leakage .

(Transmitter Room and ESA)

92,6 Relieve the pressure on line 919-6, reconnect
line 919-7 to the valve, and disconnect line
919-18 from HSV 919 A2, Cap the line tempo-

rarily to stop air leakage,

92.7 Pressurize HSV 919 A2 through line 919-6 to
40 psig. Read the rotameter, Acceptable leak-

age 4 scc/min, Leakage .

92,8 Check FE 919 A, lines 919-15, 919-16, 919-6
from HSV 919 Al to the penetration and 919-8
from HSV 919 A2 to the penetration with leak
detector solution while pressurized to 40 psig.

in step 92,7, No leakage acceptable.

92.9 Disconnect the N, ¢yl. and reconnect all

lines.

(Control Room)
92,10 Close the B port of HCV 919 B2 by setting

S3 in the drain position,

(Transmitter Room)

92.11 Disconnect line 919-10 at SR x 65,

(SESA)
92,12 Disconnect line 919-17 at HSV 919 Bl and
temporarily plug the line to stop air leak-

age.

(Transmitter Room)

92,13 . Connect a 0-10 cc/min rotameter and Ny eyi..
with regulator and 0-50 psig minimum range
pressure gauge to the end of line 919-10
going to HSV 919 Bl and pressurize to 40

psig.

LE-56

Init. Date & Time

92,14 Read the rotameter. Acceptable leakage

4 sce/min, Leakage .

(SESA & Transmitter Room)

92.15 Relieve the pressure on line 919-10, reconnect
line 919-17 to the valve, and disconnect line
919-19 from HSV 919-B2. Cap the line tempo-

rarily to stop air leakage.

(Transmitter Room)
92,16 Pressurize HSV 919 B2 through line 919-10 to
40 psig. Read the rotameter. Acceptable

leakage 4 scc/min. Leakage .

(SESA)

92.17 Check FE 919 B, line 919-13, 919-14, 919-11
from HSV 919 Bl to the penetration and 919-12
from HSV 919 B2 to the penetration with leak

detector solution, No leakage acceptable,

(Transmitter Room and SESA)

92.18 Disconnect the N, cyl.. and reconnect all
lines. To check HSV 962 A and lines to
HCV 962 A the fuel system must be empty.

HP coverage and gas masks are required.

(ESA)
92,19 Disconnect line 962-3 at HSV 962 A and plug

the line temporarily to stop air leakage,

(Transmitter Room)
92.20 Close the valve in line 962-1 off header
9008-2 and disconnect line 962-2 at TBS x 7.

92.21 Connect a 0-10 cc/min rotameter and Ng cyl.
with regulator and 0-50 psig minimum range
gauge to the .end of the line to HSV 962 A

and pressurize to 40 psig.

92.22 Read the rotameter. Acceptable leakage

4 scc/min, Leakage .

LE-57

Init. Date & Time

(ESA)

92.23 Reconnect line 962-3 to HSV 962 A while line
962-1 is: at 40 psig. Leak check line 962-2
at TB 5 x 6,

(Transmitter Room)
92 .24 Disconnect N2 cylinder. Reconnect line
962-2 and open valve in line 962-1 off
. header 9008-2,

93, To check HSV 963 A and line to HCV 963 A the fuel
system must be empty. HP coverage and gas masks
are required,

(ESA) |
93.1 Disconnect line 963-3 at HSV 962 A and plug

the line temporarily to stop air leakage,

(Transmitter Room)
93.2 Close the valve in line 963-1 off header
9008-2 and disconnect line 963-2 at TB 5 x 6.

93.3 Connect a 0-10 cc/min rotameter and N2 Cyk..
with regulator and 0-50 psig minimum range
gauge to the end of the line to HSV 963 A and

pressurize to 40 psig.

93.4 Read the rotameter. Acceptable leakage

4 scc/min, Leakage .

(ESA)

93.5 Reconnect line 963-3 to HSV 963 A while
line 963-2 is at 40 psig., Leak check line
963-2 from HSV 963 A to the penetration
with leak detector solution, No leakage

acceptable,

(Transmitter Room)
93 .6 Disconnect N2 cyl..., reconnect 962-2 and
open valve in line 963-1 of header 9008-2,

ok,

Init.

LE-~58

Date & Time

Check CV 524, CV 557 A & B, CV 560 D, CV 562,
HCV 557 C, V 557 C, CV 565, and CV 566 in the

following manner. HP coverage and gas masks

required.

(special Equipment Room)

ok.1

Close V's 500 J and V 524 A.

(Vent House)

ok.2
9%.3

ol L

k.5
ok.6

.7

ok.8
k.9

9k, 10

Close V's 522 B, 561, 620, 621, 622, 623.

Connect a 0-10 cc/min rotameter to the
sample pt. at V 524 B.

Connect a He Cylinder with regulator and
0-50 psi minimum range gauge to the sample

point at V 518 F.

Open V's 518 E, 518 D, 518 F, 524 B.

Slowly pressurize the line with He to 40 psig
while observing the rotameter. Constant
surveillance by the HP at the rotameter out-
let is required. If the activity reaches

2 mr/hr close V 524 B immediately. The
acceptable leakage is 5 scc/min at 4O psig.
If this limit is reached before the 40 psig
He pressure is reached discontinue the test.

Leakage

Close the valve on the He cylinder. Close
V 524 B. Disconnect the rotameter and cap

the valve outlet.

Open V's 620, 621, and 561.

Open V 522 B, V 500 J if it was open when
step 1 was performed and V 524 A,

Close V's 518 F, 518 D, and 518E. Dis-
connect the He Cyl. and cap the sample

point.

4E-59

Init, Date & Time

(Diesel House)

94,11 .Check to see if the He supply from line 500
to éil systems downstream of V 500 H may be
discontinued. When this condition is met

close V 500 H,

(Service Tunnel)
94,12 Close V 534 B and V 535 B.

(Control Room)

94,13 Jumper K4, K5, and K6.

94,14 Set S 95 in the no drain position.

94.15 Close HCV's 536 and 547 with HS 536 A and
HS 547 A respectively.

94,16 Set PRC 528 A for 5 psig.

(Vent House, Valve Pit)
94,17 Close V's 562 A, 624, 625, 626, and 627.

(Vent House)
94,18 Close V's 557 B, 560 B, and 562 C,

(Control Room)
94,19 Close HCV 557 Cl1 with HS 557 C,

(Vent House)

94,20 Remove CV 557 B from the system and connect
a 0-10 cc/min rotameter to V 557 C (rotameter
outlet to valve). Connect a He cyl. with
regulator and a 0-50 psi minimum range gauge

to the rotameter,

94 .21 Open V 557 C and pressurize line 557 to
40 psig with the He cyl.. .

94,22 Read the rotameter, Practically all of this
leakage will be through HCV 557 C. Accept-

able leakage 10 scc/min, Leakage . o

94,23 Open V 557 B, Uncap the outlet on V 557 A
and open the valve, Read the rotameter at
V 557 C, Subtract the leakage in step 22
above. Acceptable leakage 10 scc/min,

Leakage through CV 557 A o

oL,24
9k.25

ol .26
oL.o27

ol .28

9k, 29
9kL.30

9L.31

Init.

4E-60

Date & Time

Close and cap V 557 A, close V 557 B.

Open V 560 B. Uncap and open V 560 A.
Read the rotameter at V 557 C. Subtract
the leakage in step 23. Acceptable
leakage 10 scc/min. Leakage thfough

CV 560

Close and cap V 560 A, close V 560 B.

Open V 562 C, uncap and open V 562 B. Read
the rotameter at V 557 C. Subtract the
leakage in step 23. Acceptable leakage
10 scc/min. Leakage through CV 562

Close V 557 C and read the rotameter.
Acceptable leakage 5 scc/min. Leakage
through V 557 C

Close and cap V 562 B, close V 562 C.

Close V 557 C and disconnect the He cyl.,
reinstall CV 557 B.

Connect the He cyl. with regulator, gauge
and rotameter to CV 557 B.

(Control Room)

9Lk.32
(Vent

k.33

ol .3l

ok.35
(Vent
9k .36

Open HCV 557 C1l by HS 557 C.

House )
Pressurize CV 557 to 4O psig and read the
rotameter. Acceptable leakage 5 scc/min.

Leakage

Disconnect the He cyl. and rotameter and

cap CV 557 B.

Open V's 557 B, 560 B, and 562.

House Pit)
Open V's 562 A, 624, 625,

(Service Tunnel)

ok.37

Open V 534 B and V 535 B.

(Diesel House)

9L .38

Open V 500 H.

95.

96,

LE-61

Init. Date & Time

(Control Room)

94,39 Stop the component cooling blowers.

(Vent House)
94.40 Close V's 565 A, 565 C, HCV 565 and V 566.

94.41 Remove CV's 565 and 566 from the system and
bench check at 20 psig. Acceptable leakage
5 scc/min, Leakage CV 565 .

Leakage CV 566 .
Check CV 511 and CV 512 in the folldwing manner.
HP coverage and gas masks required,
(Control Room)
95.1 Set FIC 512 A for 0 psig.

(Coolant Cell)
95.2 Close V's 511 A & B and V 512,

95 .3 Remove CV 511 and CV 512 from the system
and bench check at 40 psig. Acceptable
leakage 5 scc/min, Leakage CV 511 .

(Coolant Cell)
95.4 Reinstall CV's 511 & 512 and open V's 511
A& B and V 512.

95.5 Check the valves with leak detector solu-
tion (supply pressure must be on line 511).

No leakage acceptable.

Check CV's 594, 595, 598, and HCV's 939 Bl, B2,

and B3 in the following manner. HP coverage and

gas masks required, He supply pressure must be on . .
line 501, | |
(Transmitter Room)

96.1 Close V 594 A, 595 A, V 598 A,

(Control Room)
96.2 Set S 39 for LT 598 C.

(Coolant Cell)
96 .3 Remove CV 595 from the system and connect
a 0-10 cc/min rotameter to the upstream side

of HCV 595 B2,

(Transmitter Room)

96 .4

Open V 594 A,

(Coolant Cell)

96 .5

96 .6

Read the rotameter for leakage through HCV
595 B2, Acceptable leakage 2 scc/min.
Leakage .

Bench check CV 595 at 40 psig. Acceptable

Leakage 2 scc/min. Leakage .

(Coolant Cell)

96.7

Reinstall CV 595.

(Control Room)

96 .8

Set S 39 for LT 595 C,

(Coolant Cell)

96.9

96.10

96,11

96,12

Remove CV 598 from the system and attach
the 0-10 cc/min rotameter to the upstream
side of HCV 595 B3. |

Read the rotameter for leakage through

HCV 595 B3, Acceptable leakage 2 scc/min,
Leakage .

Bench check CV 598 at 40 psig. - Acceptable
leakage 2 scc/min. Leakage .

Reinstall CV 598,

(Transmitter Room)

96.13
96,14

Close V 594 A,
Open V 595 A,

(Control Room)

.96 .15

Set S 39 in LE CP A position,

‘(Coolant Cell)

96.16

96 .17

Check all connections from CV's 594, 595,
and 598 to V's 594 C, 595 C, and 598 C,.
No leakage acceptable,

Open V's 594 C, 595 C, and 598 C.

Init.

LE-62

Date & Time

L4E-63

Init, Date & Time

97 . Check CV's 830, 836, 838, 840, 844, 845, 846;
FSV's 837 Al, 841 Al, 844 Al, 846 Al, 847 Al,
in the following manner,

(Control Room)

97.1 Stop the TWP's No. 1 & 2,

(Water Room)
97 .2 Close V 830 A & B and V 844 A & B.

(Blower House)

97 .3 Close V 847 A,

97 .4 Open V 831 and V 845,

97.5 Close the valve in the air line to FSV
847 A2 which comes off air supply leader
9011-4.

97 .6 Break line 855 at the relief valve and
connect a small positive displacement pump
(Sprague or similar) to the end which leads
to line 847 with a 0-25 psi minimum range

pressure gauge.

97 .7 Pressurize to 15 psig with water from the

treated water system and hold this pressure.,

(Water Room)
97 .8 Open V 830 C and collect the leakage through
CV 830. Acceptable leakage 3 cc/min,

Leakage o

97.9 Close V 830 C, open V 844 C and collect the
leakage through CV 844, Acceptable leakage

3 ce/min, Leakage o

97.10 Close V 844 C, open V 847 B and collect the
leakage through FSV 847 Al, Acceptable

leakage 3 cc/min, Leakage .

(Blower House)
97.11 Disconnect the pressurizing pump..from line
855, leave the line open, and connect the

pump to V 847 B,

hE-6k

Init., Date & Time

97.12 .Open the valve in the air linetto FSV 847 A2
and check FSV 847 Al to see that it is open.

97 .13 Pressurize through V 847 B to 15 psig and
collect the leakage through CV 847 at the
relief valve in line 855. Acceptable leak-

age 3 cc/min., Leakage .

(Water Room)
97.14 Check to see that FSV 844 has closed due to

the pressure imposed on line 847,

(Control Room)
97.15 Start TWP No. 1.

(Water Room)
97.16 Open V 844 A & B and collect the leakage
through FSV 844 Al at V 844 C,

97,17 Acceptable leakage 10 scc/min., Leakage .

(Control Room)
97 .18 Stop TWP No, 1

(Water Room)
97 .19 Close V's 836 B and 837 B.

(Blower House)

97.20 Open V- 837 A,

97 .21 Connect the small positive displacement
pump to V 837 C, open V 837 C and pressurize
to 20 psig with treated water and hold the

pressure.

(Water Room)

97 .22 Open V 836 C and collect the leakage through
CV 836. Acceptable leakage 5 cc/min,
Leakage .

(Water Room & Blower House)
97 .23 Close V 836 C and disconnect the pump from

V 837 C, leave V 837 C open,

2

(Water Room)
97.24 Open V 836 A & B,

LE-65

Init. Date & Time

(Blower House)

97.25 Close the valve in the air line to FSV 837 A2
off header 9011-4 and check to see that FSV
837 Al closed.

(Water Room and Blower House)

97.26 Start TWP No. 1 and collect the leakage at
V 837 C. Acceptable leakage 20 cc/min
through FSV 837 Al. ILeakage

97.27 Close V 837 C and stop TWP No. 1.

97.28 Open V 837 A and the valve in the air line
to FSV 837 A2.

(Water Room)

97.29 Close V's 838 B and 841 B.

(Blower House)
97.30 Open V 841 A.

97.31 Connect the pressurizing pump to V 841 C,
open V 841 C and pressurize to 20 psig with

treated water and hold the pressure.

(Water Room)

97.32 Open V 838 C and collect the leakage through
CV 838. Acceptable leakage 4 cc/min.
Leakage

(Water Room and Blower House)
97.33 Close V 838 C and disconnect the pump from
Vv 841 ¢, leave V 841 C open.

(Water Room)
97.34 Open V's 838 A and B.

(Blower House)

97.35 Close the valve in the air line to FSV 841
A2 off header 9011-%4 and check to see that
FSV 841 Al is closed.

98.

Init.

LE-66

Date & Time

(Water Room & Blower House)

97 .36

97 .37

Start TWP No. 1 and collect the leakage at
V 841 C. Acceptable leakage 20 cc/min
through FSV 841 Al, Leakage .

Close V 841 C.

(Control Room)

97 .38

Stop TWP No, 1.

(Blower House)

97 .39

Open V 841 A and the valve in the air 1line
to FSV 841 A2,

(Water Room)

97 .40

Close V's 840 B and 846 B,

(Blower House)

97 .41

Close the valve in the air line to FSV 846 A2
off header 9011-4 and check to see that FSV
846 Al closes.

(Control Room)

97 .42

Start TWP No, 1

(Blower House)

97 .43

97 .44

Collect the leakage through FSV 846 Al at
V 846 C, Acceptable leakage 20 cc/min,
Leakage .

Close V 846 C, open V 846 A and open the
valve in the air line to FSV 846 Al.

(Control Roomn)

97 .45

Stop TWP No. 1.

Check CV 825, ESV ST A, and solution addition point

in the following manner,

(Control Room)

98.1

Stop the TWP's No. 1 and No. 2

(Water Room)

98 .2

Close V's 802 A, 825 A, 827 C, D, & E and
834,

98.3

98.4

98.5

98 .6

98,7

98,8

98.9

98.10

98 .11

Init.

LE-67

Date & Time

Open V's 802 B, 803, 825 B, 883, V ST D,
and LCV 825 by increasing the setting of
LC ST A, to drain lines 802, 803, 825, and
883.

Close V's 802 B, 803, 883, and ESV ST A by

disconnecting one lead wire,

Connect an ims trument air line with 0~30
psi minimum range pressure gauge and

pressure regulator to V ST A,

Pressurize the surge tank with instrument
air by opening V ST A and V ST C to 20 psig

and hold the pressure,

Connect a 0-10 cc/min range rotameter to the
tap upstream of V 803. Open V 883 and read
the rotameter for leakage through CV 825,

Acceptable leakage 5 cc¢/min, Leakage .

Close V 883 and cap the tap, connect the
rotameter to ESV ST A and read the rota-
meter to ESV ST A and read the rotameter
for leakage through this valve, Acceptable

leakage 2 scc/min, Leakage o

Move the rotameter to the solution addition
point and read the meter for leakage through
this valve., Acceptable leakage 2 scc/min.

Leakage °

Close V ST A and disconnect the air line.
Vent the pressure through ESV ST A by re-

connecting the lead wire to open the valve,

"Leave the valve open,

Open V's 802 A, 825 A, 827 C, D, & E and

reset LC ST to its original position,

4,
Approved by /fl @m LF-1

7/28/6

4¥  VENTIIATION SYSTEM
STARTUP CHECK LIST
The ventilation system provides adequate flow of air from the
less hazardous to more hazardous areas to prevent spread of radicactive
contamination or beryllium. This check list covers the valve and damper
settings normally used. Different auxiliary cell conditions may require
deviations from the procedure as written. All deviations should be noted
and approved by the shift supervisor.
Init. Date/Time

1 STACK FAN AND FILTERS
(Stack Area)
1.1 Tag the three dampers in the inlet and the

three dampers in the outlet of the stack
filters open (Line 927).

1.2 Check that top of filter pit is closed and
caulked.

NOTE: Caulking shall be done as follows: ©Set the
shield blocks so that the crevice between them is
1/2 inch or less. Caulk with a 5/8 inch dia.
nylon rope, inserting the rope 1 inch below the
block surface. Leave 12 inches of one end of
each rope extending out of the crevice. Fill
the crevice above the rope with "Atlas CK
Weatherproof Sealing Compound” or equal. Pour
hot and flush with the top of the blocks.
(Control Room)
1.3 Start stack fan No. 1 by pushing start button
on MB-3.

1.4 Place stack fan No. 2 in standby by pushing
start button on MB-3.

(Stack Area)
1.5 Perform standby fan operational check by
closing hand valve in line to P5-927, and

open vent to raise pressure indication.
w “.‘ : ;" -
Approved by ‘;QJ'”’z%{LM%&P/#&fiq\wv

Init.

Lp-2
7/28/65
Date /Time

1.5 (continued)
Check that PS-92T7A stops Fan No. 1, closes
FCO-925A completely, starts Fan No. 2, and
opens FCO-926A, all automatically. Record
PI-92T7TA at which fan switching occurs,
in H-0. Check that this agrees with switch

tabulation.

(Control Room)
1.6 Stop Fan No. 2.

1.7 Start Fan No. 1.

1.8 Place Fan No. 2 on standby by pushing start
button.

(Remote Maintenance Cell)
1.9 Start the waste blower in the remote mainte-
nance cell.
2 AREA PREPARATION
2.1 Shield blocks should be in place and caulked

on the following cells or areas:
(High Bay)
Coolant cell (penthouse)

Fuel processing cell

Tdiquid waste cell

Transmitter room (Between transmitter room

and high bay)

Special equipment room

(Transmitter Room)
South electric service (between south elec-

tric service area and transmitter room)

(Vent House Area)

Charcoal bed cell

2.2 Check that blocks are in place if needed for

existing conditions in the following areas:
Approved b)@ PPN

Init.

LP-3

T7/28/65

Date /Time

2.2 (continued)

(High Bay)

2.3

(High Bay)

2.4

Equipment storage cell

Remote maintenance cell

Decontamination cell

Spare cell

Vent house

(Coolant Cell)

All openings into the coolant and coolant drain
tank cell have been closed, caulked, and
tagged to keep closed during operation. Warn-
ings are posted of electrical power and for

presence of Beryllium or activity.

All doors and openings into the high-bay are
closed. EFach door except through the hot
change room has a sign on the outside and
inside, stating that it is an emergéncy exit
only. Entrance and exit should always be

through the hot change room.

3 VENTTTATTON DISTRIBITTON

- (Supply Air Filter House)

3.1

3.2

Tag open the damper in line 953 and check
that the two gravity dampers in the inlet

air filter house are free to operate.

Set the dampers or valves in the following

lines as indicated:

(Vent House Area)

933 Tag open.

934 Tag open.

(service Tunnel)

931 Tag open.

HCV-930A Tag closed.

HCV-930B Tag closed.

Approved bxfi~”2;9file¢ 27l
g : i

Init.

LF-14
T/28/65

Dete /Time

(Transmitter Room)

938 - 939 Tag open to south electric service

area.

(Control Room)

(High Bay)

3.3

3.k

3:5

(High Bay)

HCV-935A Tag open.

HCV-930A Tag closed.

HCV-930B Tag closed.

935 Diverter - Set to split flow approxi-
mately equal.

olky Tag open.
9LO Tag open.
937 Tag open.

Check that ventilation is adequate for existing
conditions in the following areas. Dampers in
exhaust lines should be closed and tagged as
far as possible to give additional ventila-
tion to other areas.

Equipment storage cell (Line 942)

Decontamination cell (Line 9L3)

Spare cell (Line 941)

Adjust damper in Line 953 at the inlet filter
house until the high bay pressure PI HBA is

0.2 in. of water.

Check that the following read less than at-

mospheric pressure and record reading:

PAT-9L6A - in. Hs0
PAI-945A - in. H0
PaI-g43A - in. Hz0
PAT-942A - in. H=0
PAI-9k1A - in. Hs0
PAT-9LOA - - in. Hs0
P4I FPC - in. Hz0

(Service Tunnel)

PT 5TD

in. Hgo

Approved b%ffigajéaég%;/fi¢flzL

3.5 (continued)

(Transmitter Room)

PAI-93TA - in. Hz0
PAI-938A - in. Hz0
(Vent House)
PAI 950A - in. Hg0
PAT VH A - in. Hz0
(Above SER)
) PAT SER A - in. Hz0
PAT 933 - in. Hz0

If any of the above pressures are greater
than —0.1 in. H20, list below and obtain
shift supervisor's approval of these.

Instrument No. S. 5. Init.

3.6 Check that stack flow FI S1A is greater than
19,000 cfm. Record FI S1A

N 3.7 Pressure drop through the roughing filter
) should be less than 1.0 in. Hs0. Record the
following:
. (Stack Area)
PAT FT Al in. Hz0
PaI F2 Al in. H=0
PAI P3 Al in. H20

3.8 Pressure drop through the absolute filters
should be less than 3.0 in. H-0. Record the
following:

Lp-5

T/28/65

Init.

Date /Time

Approved bY/fié;€%L<£$;flflflf?\ Wp-6

3.8

(Stack Area)

3.9

7/28/65
(continued) Tnit. Date/Time
PaI FI A2 in. H=0
PaI F2 A2 in. H=0
PaI P3 A3 in., Hz0

Over-all pressure drop through filters
should be less than 4.0 in. HzD. Record
the following:

(Stack Area)

PAIL 927 Bl in. Hg0

PaT 927 B2 in. Hz0

(Auxiliary Control Room)

3.10

3.11

3.12

3.14

3.16

Ventilation suction as indicated by PI-927A
(at stack area) should be greater than 1.5

in. H20. Record PI-92T7A in. Hx0.

If necessary to re-adjust flows, recheck

3.3 through 3.11.
Start the 10 blowers that ventilate the salt

piping electric power induction regulators.
Start the exhaust blower for the battery

room.

Start the exhaust blower that ventilates

the "Sump Room."

Start the exhaust fan that ventilates the
room that contains MG #1 and MG #L.

Start the exhaust fan that ventilates the
main disconnect panel in the "Motor Control

Center."

Start the exhaust fan that ventilates the

"Remote Maintenance Area."

ALL ITEMS IN VENTILATION SYSTEM CHECK LIST ARE COMPLETE.

shift Supervisor Date

Approved byggé?ffiggéggé;xwivx

4G LEAK-DETECTOR STARTUP CHECK LIST

he-1

7/28/6

Before the reactor is started, complete. the following check list

to ensure proper operation of the leak-detector system.

1 MATN LEAK-DETECTOR SYSTEM

1.1 Helium Supply

(Trensmitter Room)

1.2

1.1.1 Check V-51LB and V-514A open
1.1.2 Check closed: V-514C _ , V-51L4D ,
V-51LE , V-514E (capped)

1.1.3 Check PI-514 reading 100 psig.

Init.

Date /Time

PSV-514 if necessary.

Line L00

1.3

1.2.17 Check V-400 open. Open L403A and 4O3B.

1.2.1.A Check Ann. XA-LOOO-L clear.

1.2.2 Check the following valves closed:

v-401B , V-402B , V-ho3B _____,
V-L4OLB , V-hosB __, v-kooB ____,
v-LOTB , V-h08B ___ .

Headers - Front of Panels

1.3.1 Header 401l. Check V-L4LOlA open

1.3.

Check that PI-401 is between 90 and
100 psig. . Check all used LD line

valves open . Check all spare

LD line valves closed

2 Header 402. Check V-L4O2A open __
Check that PI-402 is between 90 and
100 psig _ . Check all used LD line

valves open . Check all spare LD

line valves closed

Adjust

bos
.
Il ya

Approved by .- / ' saiaL
v4

7/55??%

Init. Date & Time

1.3.3 Header 403. Check V 4O3A open.
Check that PI 403 is between 90 and 100 psig.
Check all used LD line valves open.

Check all spare LD line valves closed.

1.3.4 Header LOL. Check V LOLA open.
Check that PI 404 is between 90 and 100 psig.
Check all used LD line valves open.

Check all spare LD line valves closed.

1.3.5 Header 405. Check V 405A open.
Check that PI 405 is between 90 and 100 psig.
Check all used LD line valves open. '

Check all spare LD line .valves closed.

1.3.6 Header 406. Check V 4O6A open.

Check that PI 406 is between 90 and 100 psig.

Check all used LD line valves open.

Check all spare LD line valves closed.

1.3.7 Header 4O7. Check V LOT7A open.

Check that PI LO7 is between 90 and 100 psig.

Check 2ll used LD line valves open.

Check all spare ID line valves closed.

1.3.8 Header 408. Check V 4O8A open.
Check that PI 408 is between 90 and 100 psig.
Check all used LD line valves open.

Check all spare LD line valves closed.

Headers, Back of Panel

1.4.1 Header 402. Check all LD line "B" valves open.
1.4.2 Header 40O4. Check 2ll LD line "B" valves open.
1.4.3 Header 405. Check all LD line "B" valves open.
1.4.4 Header 407. Check all LD line "B" valves open.
-+1.45 Header; 401. .Check all LD line "B" valves open.

hG-3
7/28/65
Init. Date & Time

Approved by 4‘f¢;24%:?§7;¢hfl\_

2 LUBE OIL SYSTEM LEAK DETECTORS
2.1 Check the following LD lines capped and no indication

of oil leakage:'

Fuel Lube 0il Package Location
L 4100 L 71k
L 4101 FOP-1
L 4102 L 701
L 4103 L7153
L 4104 FOP-2
L 4105 I 702
L 4106 Inlet OF 1
L 4107 . OF 1
L 4108 Cap OF 1
L 4109 - Outlet OF 1
L 4110 FSV 703

Coolant Lube 0il Package Location

ARRRRRRREE RN AR

L 4150 Line 764
L 4151 COP-1

‘L 4152 - Lo

L 4153 L 763

L 4154 - COP-2

L 4155 L 752

L 4156 Inlet,OF 2
L 4157 OF 2

L 4158 Cap, OF 2
L 4159 Outlet,OF 2
L

4160 - FSV 753

ar i i
%), 1

P T
+
approved by 4 JYS

2.2

Init.

7/2

N
Yz
a

fe & Time

If any flanges in eithér lube oil system have been
opened, they should be leak checked as outlined below.
2.2.1 Connect the protable leak-detector rig
to the leak-detection nipple. (The rig
consists of a helium cylinder, pressure
regulator, Hoke type 482 block valve,
and O-to 100 psig pressure gauge connected
with 1/4-in., .035-in. wall tubing.)

2.2.2 Pressurize the leak-detector line to
100 psig.

2.2.3 Soap check leak-detector line connection.

2.2.4 Close block valve and check pressure

over an . 8-hour period.

2.2.5 Record initial and final pressure. A
pressure drop of < 1 psi/hr is acceptable
(.04 to .05 cc of He/min.).

2.2.6 Disconnect leak-detector rig and cap leak-
detector nipple.

ALL ITEMS ON THE LEAK-DETECTOR STARTUP CHECK LIST ARE
COMPLETE Shift Supervisor Date

4
Approved by , 7. & 7

V

s

, -?éfih¢pq WH-1
“~ . 9/17/65

4YH INSTRUMENTATION
STARTUP CHECK LIST

Detailed procedures are given in this section for testing each

instrument and each control circuit. Where possible, abnormal conditions

are simulated and the control or alarm action is allowed to occur. Some

of these tests can ohly be done at specific stages of operation, and this

fact is cross-referenced here and in other parts of the operating pro-

cedures:

a. Steps of this section (4H) which can be done at any time:

1, 2, 3, 4,
26, 27, 28,
Lo, 43, L5,
64, 65, 66,
86, 87, 88,

5 8, 9, 13, 14, 15, 16, 18, 19, 20, 22, 23, 24, 25,

29, 30, 31, 32, 33, 3k, 35, 36, 37, 38, 39, ko, 41,

ke, Lt, 48, 52, 53, 54, 55, 56, 5T, 58, 59, 60, 63,
e8, 69, 12, T6, 7T, 78, 79, 80, 81, 82, 83, 8L, 85,

89: 9O) 91) 925 93: 9)"': 95: 96: 97? 99

b. Steps of this section which can be done only after the reactor

and drain tank cells are sealed:

6, 7, 17, 21, 61, 62.

C. Steps which
10, 11, 75,
d. Steps which
ki, kg, 50,
e. Steps which
but empty:
12, 67, 70,
f. Steps which
T3, Th.
Not all portions
however, the need for
omission.

Details are also

should be done before systems are heated:
100

require Operations Chief approval before starting:

51, Th.

can be done with the salt systems at temperature

71, 98

can be done only with salt circulating:

of this check list will be done at each startup;

doing each one will be carefully considered before

given for putting each instrument into service and

assuring that the alarm and interlock setpoints are properly set,
Approved by _ -

Vv

Init.

bE-2
9/17/65

Date /Time

1 STEAM SUFPPLY

1.1 Close the 15 psig steam supply valve (3 in.

gate valve) to the water room located on the
8LO' level just west of column E-4 and note
that PS-SX10 annunciates on XA-4016-3 per
switch tabultion. (It may also be necessary
to open the condenser steam inlet valve.)
Open the 15 psig steam supply valve previ-
ously closed and note that annunciation

clears.

2 INSTRUMENT ATR SYSTEM

2.1 Check that the Instrument Department has

2.2

checked the following prior to placing the

alr compressors in operation:

Compressor No. 1 Unloading Valve
Compressor No. 1 Temp. Sw. AC1-A
Compressor No. 1 Temp. Sw. AC1-B
Compressor No. 1 0il Press. Sw. AC1-C____
Compressor No. 2 Unloading Valve
Compressor No. 2 Temp. Sw. AC2-A
Compressor No. 2 Temp. Sw. AC2-B
Compressor No. 2 Oil Press. Sw. AC2-C___
Compressor No. 3 Temp. Sw. AC3-A
Compressor No. 3 0il Press. Sw. AC3-B
Compressor No. 3 Unloading Valve AC3-C

With the instrument air system in normal
operation, close all HV's on the emergency
nitrogen cylinders. TIeave HV's in line 9006
open. While observing PI-9006-2, slowly
‘raise the setpoint on PIC-9006-1 and note that
PS-9006-1 annunciates on XA-4001-2 per Sw.
Tab. Record PI-9006-2

L

- g
Approved by 147////_14/.%#[

2.3

2.k

2.5

2.6

Init.

LH-3
9/17/65
Date /Time

Continue to relieve pressure and note that
PS-9006-2 annunciates on XA-L0O1l-3 per
Sw. Tab . Record PI-9006-2

Lower the setpoint on PIC-9006-1 to its

previous value., Open cylinder valves and
note that both alarms clear . Low
final clear psig, PI-9006-2. Low initial
clear psig PI-9006-2.

Close HV-9119 and/or HV-9129, whichever is
open, at the air dryer outlet filter and note
that PS-900-1 annunciates on XA-4030-9 and

XA-4000-2 per Sw. Tab ____ . Record

PI-9000 . ©PS-900-2 should start

standby compressor per Sw. Tab __ . Record
PI-9000 __ . Open HV-9119 and/or HV-9129,

previously closed. Reset Rochester alarm
units and note that annunciators clear.
Stop the standby compressor by pushing the
stop button on MB-12.

At the instrument air reducing station in
the transmitter room, close the HV in line
9013-1 upstream of PI-9013-1 . While
observing PI-9013-1 note that P5-9013-1
snnunciates on XA-4030-10 per Sw. Tab
Record PI-9013-1 _ . Allow the pressure
indicated on PI-9013-1 to continue to de-
crease and note that PS-9013-2 annunciates on
XA-4002-5 per Sw. Tab . Record PI-9013-1,
Open HV in line 9013-1 upstream of
PI-9013~-1 and note that both alarms clear.

NOTE: After closing HV in line 9013-1 upstream of

PI-9013-1, it may be necessary to crack the vent

by

HV in order to obtain a decrease in pressure in

line 9013-1.
.
Approved byfizfz;;zzézfiaffiymkfiwl LH-4
v 9/17/65
2.7 Close the HV ahead of the pressure-reducing
valve in each instrument air line and note
that alarms occur as indicated in Table L4H-1.
Open HV, reset Rochester alarm units and note
that annunciation clears. XA-4000-2 will also
annunciate and clear each time.
Table LH-1
LINE SERVICE SWITCH r%f_ ATARM ATARM AT | O |
IOCATION! No. (psig) No. [ 2 No. PI-No. | psig ffixnit.
Control [9007-1 | 20-Emerg | PS-9007-3 KA-4031-1 | PI-9007-4
Room 9007-4% | 30-Emerg | PS-9007-Lk XA-4031-2 { PI-9007-5

9007-1 | 60-Emerg | PS-9007-1 KA-4031-3 | PI-9007-2 3

9001-1 | 20-Norm | PS-9001-1 KA-L4030-1 | PT-9001~-2
Blower |9011-2 | 15-FEmerg | PS-9011-2 XA-14031-9 | PI-9011~3
House  19011-3 | 20-Emerg | PS-9011-3 A -4031-10] PT-9011-L

9011-4 | 30-Emerg ! PS-9011-4 ¥A-4031-11} PT-9011-5

9011-5 | 20-Emerg | PS-9011-5 kA-u031-12 PI-9011-6 ,

9011-1 | 60-Emerg | BS-9011-1 kA-u031-8 PI-9011-~2 %

19005-2 | 20-Norm ' PS-9005-2; ka-%030-7 | PT-9055-3

9005-1 | 60-Norm gPS—9OOS-l kA—u03o-8 PI-9005-2;

Trans- 9008-1 | 20-Emerg , PS-9008-1 XA-4031-4 | PT-9008-2
mitter (9002-4 | 20-Norm  PS-9002-4 KA-4030-4 | PI-9002-5:
Room 9002-3 | 20-Norm ' PS-9002-3 ka-L030-3 | PT-9002- k- :

19002-1 { 30-Norm ;PS-9002-1 ¥A-L030-2 | PT-9002-2
Service {9010-2 | 20-Emerg PS-9010-2 ¥A-L4031-7 | PT-9010-3 }

Room 9010-1 | 30-Emerg PS-9010-1 ¥A-4031-6 | PI-9010-2 %

%9004-1 20-Norm  PS-9004-1 KA-4030-6 | PT-9004-2 ! |
Eifi?ifigrggoog-l 30-Fmerg §P8-9009-1 ¥A-4031-5 |PT-9009-2 ‘ §
Maint. : E I
Control {9003-1 | 20-Norm 'PS-9003-1 ¥A-4030-5 |PI-9003-2 |
Room

1

Approved by

b,

. 4;! \

L

Init,

4H-5
9/17/65
Dete /Time

With No. 1 stack fan in operation and No. 2 stack
fan in "stand-by" (Start button depressed),
slowly close hand dampers on down-stream side of
filters and note that PdS-936-A annunciates on
XA-4017-2 per Sw. Tab. . Record PI-927-A
(located on Contaimment Air Panel 1). Note
that PS-HB-Al annunciates on XA-L017-1 and XA-L0O0O-6
per Sw. Tab. ___ . Record PI-HB-A __ (located
on Aux. Board 1) and PI-927-A _ (located on
Containment Air Panel 1). Note that FS-S1-A
annuncdétes on XA-4017-4 and XA-L000-6 per Sw. Tab.
Record FI-S1-A __ (located on Main
Panel 3). DPS-927-Al and A2 start No. 2 stack fan
and stop No. 1 stack fan per Sw. Tab.
Record PI-927-A _ when stack Fan No. 2 starts.
Note that PaS-927-B annunciates on XA-4017-3 and
XA-4000-6 per Sw. Tab. . Record PAI-927-B2
(on Containment Air Panel 1). Open dampers
Stop stack fan No. 2 _ . Start stack
fan No. I. . Place stack fan No. 2 iIn stand-

by by depressing start button.

Apply a slight vacuum to high bay tap of PT-HB-A
and note that PS-HB-A2 annuncaites on XA-4017-1
and XA-4000-6 annunciates per Sw. Teb. — .

Record PI-HB-A (located on Aux. Board 1).

Remove wvacuum and note that alarms clear.

At the containment block valve header (located in
the North Electric Service Area), note that PI-
9013-1A1 through 1A6 all indicate greater than
50 psi . Slowly open HV-RC-B to increase
pressure on PI-RC-B (do not exceed 5 psi) until
HCV-9013-1A1 and 9013-1A2 operate . Record
PI-RC-B ___ . Note that PI-9013-1A5 drops to

zZero and all other pressure gauges in the

A Lu-6
b ‘_' s S
Approved by 7 \ L / 9/17/65

Init. Date/Time

5 (continued)
9013 series do not change = . Close HV-RC-B _ and note
that all 9013 series pressure gauges are greater than 70 psi
_____ .« Slowly open HV-RC-F to increase pressure on PL-RC-F
(Do not exceed 5 psi) until ‘HCV-9013-1Bl and 9013-1B2 operate

Record PI-RC-F . Note that PI-9013-1A1 drops to
Zero __ and all other pressure gauges in the 9013 series
do not change . Close HV-RC-F and note that aill

O01l3 series pressure gauges are greater than 70 psi

Slowly open HV-RC-G to increase pressure on PI-RC-G
(do not exceed 5 psi) until HCV-9013-1Cl and 9013-1Cz operate

Record PI-RC-G . Note that PI-9013-1A4 drops to

zero . A}l other pressure gauges in the 9013 series do
not change

Slowly open HV-RC-B to increase pressure on PI-RC-B (do
not exceed 5 psi) until HCV-9013-1A1l and 9013-1AZ2 operate
____+ Record PI-RC-B __ . DNote that PS5-9013-2 annunciates
on XA-4002-5 per Sw. Tab. _____+ Recora PI-9013-146 at time
of alarm . Note that PI-9013-1A4, 1AS5, and 146 drop
to zero . Note that PI-9013-1A1, 1AZ, and 1lA3 do not
change ~ . Close HV-RC-B _;__. Note that annunciator
XA-4002-5 clears '

Slowly open HV-RC-F to increase pressure on PI-RC-F
(do not exceed 5 psi) until HCV-9013-1Bl and 9013-1B2 operate
- Record PI-RC-F . Note that P5-9013-2 annunciates
on XA-4002-5 per Sw. Tab. . -Record PI-9013-146 at time
of alarm . DNote that PI-9013-1A1, 1A3, 1Ak, 1A5, and
1A6 drop to zero . Note that PI-9013-1A2 does not
change. . Close HV-RC-G . Note that annunciator
XA-4002-5 clears

Slowly open HV-RC-B to increase pressure on PI-RC-B
(do not exceed 5 psi) until HCV-9013-1A1 and 9013-1AZ2 operate
____+ Record PI-RC-B . Note that P5-9013-Z annunciates
on XA-4002-5 per Sw. Tab. _____+ Record PI-9013-1A6 at time
of alarm . Note that PI-9013-1Al, 1Az, 1A3, 1Ak,
)

Approved by _ fifff’ V@ft@fill LE-7
9/17/65
Tnit. Date/Time
) 5 (continued)
1A5, and 1A6 all drop to zero . Close HV-RC-F

Note that annunciator XA-L4002-5 clears
Close HV-RC-B. . Note that all pressure

gauges in the 9013 series read about 50 psig

Slowly open HV~RC-K and raise the pressure
on PSS-RC-K. BSlowly open HV-RC-H and raise the
pressure on PSS-RC-H. Note that the following
actions occur:

XA-4002-5 alarms
- CCP #1 or CCP #2 stcps

Reactor cell evacuation valve HCV-565-A1

closes
Close HV-RC-H and note that XA-L002-5
clears . Start CCP #L or #2 . Slowly

open HV-RC-J and raise pressure on PSS5-RC-J.
Note that the following actions occur:
XA-L4002-5 alarms
CCP #1 or CCP #2 stops
Reactor cell evacuation valve HUV-565-Al

closes

. Close HV-RC-K and note that XA-L002-5
clears . Start CCP #1 or #2
Slowly open HV-RC-H and raise pressure on PS55-RC-H.
Note that the following actions occur:
XA-4002-5 alarms
CCP#1 or CCP #2 stops
Reactor cell evacuation valve HCV-565-A1

closes

Close HV-RC-J and note that XA-4002-5 clears
Close HV-RC-H

6 When the reactor and drain tank cells are pres-
a surized for leak testing:
Note that PS-RC-Al annunciates on XA-4002-6 per
e
Approved by ,<gz%?%3a’b/é%944fwn_
- :

NOTE :

LH-8
9/17/65
Init. Date/Time
(continued)
Sw. Tab. _____. Record PI-RC-A _____ (on Main

Panel 3). Check that FCV-333-Al, FCV-333-A2,
FCV-343-A1, and FCV-343-A2 can not be opened.
(This can be done in the transmitter room by
turning their switches to the "on" position, one
at a time and feeling the solenoid valve to de-
termine if they are energized.

Be sure all switches are returned to the "off"

position when check is completed.

When cell is evacuated, check that PS-RC-A2
annunciates on XA-4002-6 per Sw. Tab.
Record PI-RC-A (on main board 3).

EVACUATION ATARM

8.1 Announce a test of the building evacuation
alarm on the PA system, and notify plant
supervisor that tests are to be made on the

evacuation alarm system.

8.2 Close the nitrogen supply valves at all four

evacuation horn stations.

8.3 Operate building evacuation alarm using switch

109 on console.

8.4 Make sure all evacuation horn solenoid valves

are closed after above test.

8.5 Check that monitrons and CAM's actuate the
building evacuation alarm as follows:
8.5.1 Pressurize the lines up to the sole-
noid valves at each horn station by
opening the nitrogen supply valves momen-

tarily and then closing them.

8.5.2 Actuate the building evacuation sys-
tem with a radioactive source in the

following way: (See also Step U43.)
ra

| -“?‘/f
Approved byfifffigzzg%g€§;9fl¢m1

Init.

LH-9
9/17/65
Date /Time

8.5.2.1 Using the source, alarm the

monitron in the CR.

8.5.2.2 Acknowledge the alarm, but do
not reset the CR monitron alarm

module.

8.5.2.3 Using the source, alarm the moni-
tron in the HB (west). (This should

actuate the evacuation horns.)

8.5.2.4 Acknowledge the alarm, reset
the HB (west) monitron alarm module,
but do not reset the CR monitron

alarm module.

8.5.2.5 Check that the solenoid valves

at the horn stations are closed.

8.5.2.6 Repeat steps 8.5.1 through
8.5.2.5 substituting the following

combinations of monitrons and CAM's

for CR and HB (west).

MONTTRONS
CR and HB (south)
b. CR and HCP
c. CR and TR
d. CR and Horn Hall. (Reset CR module, but

not the Horn Hall module)

Horn Hall and IR

Horn Hall and HCP

Horn Hall and HB (south)

B R H o0

Horn Hall and HB (west) (Reset Horn
Hall module, but not HB (west). =~ .-

module).

i. HB (west) and TR

j. HB {west) and HCP

k. HB (west) and HB (south ) (Reset HB (west)
module, but not HB (south) module.)

Approvead byfl4:22222%§%%ggfivfl

MONITRONS (continued)

CAM's

l.

m.

.10

11

.12

HB (south) and TR

HB (south) and HCP (Reset HB (south) module,
but not HCP module.)

HCP and TR. (Reset both modules.)

CR (located in hallway of 7503 office area)
and 840 level (north).

CR and TR

CR and Service Tunnel (Reset CR module, but

not Service Tunnel module.)

Service Tunnel and TR

Service Tunnel and 840 level (north)

(Reset Service Tunnel module, but not
840 level (north) module.)
840 level (north) and TR (Reset both modules)

After the above tests have been completed,

check that all evacuation horn solenoild
valves are closed and that all alarm modules
have been reset.

Open nitrogen supply valves to all evacu-
ation horns.

Test building evacuation alarm system by
pushing button in ACR and allow cylinders to
completely run down. Check that alarm can
be heard in all areas.

Reset alarm and check that all solenoid
valves at horns are closed.

Replace nitrogen cylinders at all horn sta-
tions and check that supply valves are open.
Announce completion of test over PA system
and notify plant shift supervisor.

Announce a test of the bullding evacuation

siren over the PA system.

Init,

4H-10
9/17/65

Date /Time

-

Approved by_%;gf?

g prarm_
174

Init.

LH-11
9/17/65
Date/Time

8.13 Test evacuation siren by turning switch
111 on console to "On". Check that siren can

be heard in all areas.

8.14 Announce completion of test over PA system.

9 THERMOCOUPLE EIEMENTS

9.1 The instrument department will periodically

test the resistance to ground and to each lead
of all thermocouples. The results will be
kept in the instrument department Thermocouple
Resistance Log Book. This log should be
reviewed by the shift supervisor and any
thermocouple failures noted in the operations
department "Thermocouple Tabulation Log

Book." TInitial when this is complete.

9.2 Check that each thermocouple is plugged in as
indicated in the Thermocouple Tabulation Log
Book (both sections). Check that the listing
in the Thermocouple Tabulation Log Book has
been approved by the Operations Chief.

9.3 .Check that the Instrument Department has
checked out the temperature scanners and has
: completed the scamner check lists and set
the following switches per switch tabulation:
T5-5001-A
TS-5002-A
TS-5003-A
TS-5004-A
TS-5005-A

9.4 Check that the nitrogen flows to the scanner
swlitches are as indicated on the building

log.

9.5 Check that the proper range and alarm innts

have been selected for each scanner. (See

.2
Approved bymnffl/f%a’P;fiVU//fifl L4H-12
\V4 9/17/65

Init. Date/Time

9.5 (continued)
Shift Supervisor.} (Details of startup and

operation of the scanner are given in the

scanner Alignment and Calibration Procedures.)
9.6 The Instrument Department has checked out

the logger; all calibration and cross checks

have been made in accordance with the logger

check list. The readout and setpoints are

as given in the logger tabulation.

NOTE: The logger tabulation should be approved by the

Analysis Chief before starting the tests.

10 RADIATOR DOORS
With no salt in the coolant system and with

no heat on the radiator, perform the following

tests on the radiator doors:

10.1 Insert jumpers in circuits 162 and 16L4.
10.2 The door position indicators on MB-13

(Console Panel TIII) are as follows:

b ]
=

27
Approved by ,71;‘4044QW\
: \/ \

g 10.2 (continued)

~-Qutlet Door

Inlet Door

B1
(UL)

B2
(UL)

Bl B2 -
(ur) | (UL)
D1 Cl
(sv) | (1L)
- : Z2I-0D-
) 7,T-0D-A

7I-0D-A3

and on MB-4 are:

AY 7/
7 “~

)
. Z2I1-0D-B3
(UL)

AS ”
()
ZI-0D-D2
(LL)

LY

| par

AD2
Al
and
AP

Cl
(LL)

D1
(sL)

LH-13
9/17/65

]
ZI-0OD-A2
(UTL) (LIL)

Z2I-ID-

O,

ZI-ID-A
]

®,
V4 N

ZI-ID-A3

i
ZI-ID-A2
(LIL)

ZI-ID-D2
106.3

10.4 Slowly raise the inlet door and record ZI-ID-A when the following occur:

10.5

[

Check both doors closed:

10.3.1 Inlet Door
Switch No.
Z5-ID-D1 and D2
Z5-ID-C1 and C2
Z5-ID-D1 and D2
10.3.2 Outlet Door
Switch No.
Z3-0D-D1 and D2
Z5-0D-C1l and C2
Z5-0D-D1 and D2

Position Indicator Light

ZI-ID-D1 on
ZI-ID-C1 on
Z2I-ID-D2 on

Position Indicator Light

ZI-0D-D1 on
ZI-0D-C1l on
ZI-0D-D2 on

ZzI1-ID-A, in.

ZI-0D-A, in.

ZI-ID-A in.
Switch No. Position Indicator Light Raising Lowering
Z5-ID~D1 and D2  ZI-ID-Bl off
Z5-ID-C1l and C2  ZI-ID-C1 off
Z5-1D-D1 and D2  ZI-ID-D2 off-
ZS-ID-Al ZI-ID-A2 on
ZS-ID-A2 ZI-ID-A3 on
Z5-ID-B2 ZI-ID-B3 on
ZS5-ID-B1 ZI-ID-Bl on
Z5-1ID-B2 ZI-ID-B2 on

Slowly lower the inlet door and record ZI-ID-A (Above ) when position

indicator lights change aspect.

Init. Date/Time

a9/LT/6
WT-HY

\4¢¢y74§zsy%£;ggff;/fiq pasoxddy
11

Init.

Da.te/Time

10.6 Repeat Steps 11.4 and 11.5 for the outlet door:
ZI-0D-A, in.
Switch No. Pogition Indicator Light Raising Lowering
25-0D-D1 and D2 ZI-0D-D1 off
Z5-0D-C1 and C2 ZI-0D-C1l off
Z5-0D-D1 and D2 ZI-0D-D2 off
Z5-0D-Al ZI1-0D-A2 on
7S-0D-A2 7I-0D-A3 on
Z5-0D-B2 Z1I-0D-B3 on
ZS~0D-Bl ZI-0OD-Bl on
Z5-0D-B2 ZI-0D-B2 on

10.7 Leave doors closed.

BYPASS DAMPER

11.1 Check bypass damper closed:

owiteh No. Position Indicator Light PAM-AD2-AY, % PaT-AD2-A3, %
7S-AD2-A2 7I-AD2-A2 (green light) on
ZS-AD2-Al ZI-AD2-Al (red light) off

11.2 Slowly open bypass damper and record damper position when following

actions occur:

Switeh No. Position Indicator Light PAM-AD2-Al, % PAI-AD2-A3,%
Z25~-AD2~-Al ZI-AD2-Al comes on
Z3-AD2-A2 ZI-AD2-A2 goes off

11.3 Slowly close the bypass damper and record damper position when

following actions occur:

Switeh No. Position Indicator Light
ZS5-ADe-A2 ZI-AD2-A2 comes oh
Z3-AD2-Al ZI-AD2-Al goes off

PAM-AD2-A1,% PAT-ADP-A3, %

" £q paroxddy

¢9/L1/6
CT-HY

"Mwnwyégb

’

;%é;;ffff

e

g A
fpproved by"fj%*“"'\fi?fvfiflflfl LH-16
. . 9/17/65

Tnit. Date/Time

11.4 ZLeave bypass damper open. .-
12  CONTROL RODS
The following list should be done only when there

is no fuel or flush salt in the reactor and with the
nuclear instruments in service.
1l2.1 Check that all control rods are fully

inserted.

12.2 Slowly raise one rod and record rod posi- -
tions when upper and lower limit lights
change aspect. Lower the rod and again
record rod positions when the lights change. .
Repeat for the other two rods and enter
results in table below. The position indij .

cator locations are as follows:

MB-13 (Console Panel IITI)

A1 | A2 A1 | A2 N

(un) | (UL) (u1)| (VL) (UL) | (VL)

A3 | AL | A3 | Ak A3 | AL

(rm) | (1.L) (rr)| (LL) (1) (1L)

7I-NRR1-A6 7,T-NCR-2A 7.T-NCR3-A )
MB-T

O ®

ZI-NRR1-A5 ZI-NCR2-A5 Z2I-NCR3-A5

-
Rod Condition owiltch No. Position Indicator Light Rod Position, in.
1 Inserted Z5-NRR1-A1 ZI-NRR1-Al off ZI-NRR1-A5 _ , -A6
il " " -AD " -A2 off " A5 , A6
1 " " =A3 " -A3 on " ,
1 " " Al " AL on y , "
1 Raising " -A3 " -A3 off " P
1 " "ok " _Al off " , "
1 " To=A " -Al on " , "
1 " " -AP " ~A2 on " ,
1 Lowering "=Al " -Al off " s
1 " " -AD2 " =A2 off " y
1 " " =A3 " =-A3 on " P
1 " " -AL " -A3 on " ,
2 Inserted Z5-NCR2-Al ZI-NCR2-Al of £ ZI-NCR2-A5 , —A.
2 " " =A2 " =AD off " s
2 " " -A3 " -A3 on " ,
2 " " -Alb " -Al on " o,
2 Raising " -A3 " =A3 off " , "
2 " " -AL " -AL off " s
2 " " -Al " =Al on " s
2 " " -A2 " -A2 on " ,
2 Lowering "o=AlL " -Al off " ,
2 " " -A2 " -A2 off " s
2 " " -A3 " -A3 on " , "
2 " " Al " -Ak on " "

£q paroxddy

q9/L1/6
L 1T-HY

A
Av;?«tf-‘_?rfi'-:'

(e 1t

[ -

s
T A

-l
Rod Condition Switch No. Position Indicator Light Rod Position, in.
3 Inserted Z5-NCR3-Al ZI-NCR3-Al off ZI-NCR3-A5 _ , -A
3 " " -A2 " =A2 off " ,
3 " " -A3 " -Ahon " s
3 " T -Ab " -Abon ___ " ,
3 Raising " =A% " -A3 off " s
3 " " -Ab " -Ab off " s
3 " T =A1 " -Alon " s
3 " " -A2 " -A2on " ,
3 Lowering "-AY " =Al off " ,
3 " " =AD " =A2noff " ,
3 " " -A3 " -A3on " ,
3 " " -Ab " -Abon ____ " ,
12.3 Check that all rods are fully inserted when test Init. Date/Time

Elal

is complete.

A

v,

leo

Go/LT/6
ST-Ht

/figgjzfiEZVKq paacxddy

-

WAL
) L
Approved bxfijjg?:gzk;@%?”“fin 4H-19

9/17/65
12.4 Before filling system but after heat-up, raise Rod #1 until
o lights at bottom of ECC 20 and 21 on jumper board go on. Lower
rod until lights go out.
Repeat for Rod #2 and Rod #3. Record results in table

below and compare with switeh tabulation.

Rod Position When Rod Position When
Iight in Ckt. Goes Qut Light in Ckt. Goes on
Rod # | Sw. Tab. Actual Sw. Tab. Actual
) Ckt. Ckt. Ckt. Ckt.
¢ 20 21 20 21 Initial Date

Tnit., Date/Time

12.5 With the system hot, but before adding
salt, check the control rod reference loca-
tion. Check that cell air activity is not
high: record RM-565-3B and RM-565-C

Also check radiation level in TR:
record CAM and Monitron . Do
not proceed if cell air activity is >

- The two rods not being tested should be
above
- 12.5.1 GSet valves as follows:
HV-985-A2 open
HV-987-A2 open
HV-987-A3 closed
HV-986-A open

12.5.2 Open HV-986, 987, or 989. Throttle
HV-985-A1 and HV-989-A until ZI-987-A

indicates approximately 50%.

4
e Z
Approved bmfifif?fjgaf/fifwmffl 4H-20
4 9/17/65

Init. Date/Time

12.5.3 Establish communications between TR
and Control Room.
12.5.4 TInsert Control Rod and determine

control rod reference position.

Record rod position when maximum dp 1s obtained. Determine position

indications for each rod being inserted and for each being withdrawn.

CONTROL ROD POSITION
Valve Valves Actual
Rod #| Open Closed Should Be|Inserting |Withdrawing|Initial|Date

1 |986-4 |987-A1 |989-A

2 |987-A1 {986-A |[989-A s i

3 1989-A 1986-A |987-Al

12.5.5 Open HV-987-A3.
12.5.6 Close HV-985-A1, 989-A, 986-A, 98T7-A1,
and 989-A1.
12.6 After the system is hot and before adding

salt check the drop time of each rod.

12.6.1 Raise #1 rod to 50 inches above the
rod position where the first lower indi-
cator light 1it up. (13.5)

12.6.2 Plug in the rod drop timer and set to

zero.
12.6.3 Actuate the rod scram switch.
12.6.4 Repeat with Rod #2 and Rod #3 and

record results in table.

Approved byizffigzjgéigéffgflflzfl\ LH-21

9/17/65

Rod Drop Time
Rod # | Starting Position | Should Not Exceed 1.0 Sec. | Initial | Date

Init. Date /Time

12.7 Raise all three rods 12 to 15".

12.8 Push HS5-100-Al and A2 and note the kth
v light in ECC-1T74 goes out and first light in
ECC-183, 184, and 185 goes on and rods scram.

12.9 Reset and raise rods. Push HS5-100-Al and
A3 and note that Lth light in ECC-174 goes
out and first light in ECC-183, 184, and 185

goes on and rods scram. Reset and raise rods.

12.10 Push HS-100-A2 and A3 and note that Lth
light in ECC-174 goes out and first light in
ECC-183, 184, and 185 goes on and rods scram.

Regset and raise rods.

12.11 Push trip test switch on RSS-NSC1l-A2 and
‘ RSS-NSC2-A2 and note that 4th light in
ECC-1T7hk goes out and first light in ECC-183,
184, and 185 goes on.

12.12 Push trip test switch on RSS-NSCl1l-A2 and
RSS-NSC3-A2 and note that 4th light in ECC-
174 goes out and first light in ECC-183,
184, and 185 goes on.

12.13 Push trip test switch on RSS-NSC2-A2 and
RSS-NSC3-A2 and note that 4th light in
ECC-1T74 goes out and first light in ECC-183,
184, and 185 goes on.

Approved @xwizéfizgié;%%rk 4H-22

13

FUEL

""" B 9/17/65
Tnit. Date/Time

PUMP, FUEL PUMP OVERFIOW TANK AND COOLANT

PUMP

BUBBLER SYSTEMS FLOW ATARM CHECKS

13.1

13.2

13.3

On jumper boards 2, 3, and 4, check that
the green lamps are on in circuits 40 _
L1 , 128, and 129

On main panels 6 and 8, check that annunci-
ators XA-40O5-4  and XA-L4006-6

are clear.

Referring to the following tables, set the
fuel-pump selector switch (S8-36, on main
panel 8), coolant-pump selector switch
(5-39, on main panel 6), fuel-pump level
test switch (S-37, on transmitter panel 5),
fuel-pump overflow tank level test switch
(5-38, on transmitter panel 5) and coolant-
pump level test switch (S-40, on trans-
mitter panel 6) as indicated, open the indi-
cated supply valve and note when the low
flow (or high pressure) alarm occurs. Then,
while maintaining the test switch position,
close the supply valve. After the supply
valve has been closed, return the test switch
to the "off" position and note the time
required for the flow indicator to drop from
35 psi to 20 psi. Also, record the pressure
at which the high flow (or low pressure)

alarm occurs.

*a

Approved

by :,»”/’////\J m-«r’fK
an - . \/

Table 4H-2
FUEL PUMP LEVEL SYSTEM

MH-23
9/17/65

Hi & Low Flow Alarm XA-LO06-6

Time (sec.)

Selector Test |Supply Switch Hi {Flow Indicator| for FI to
Switch | Switch | Valve Set Point lor Alarm | drop from
S-36 S-37 |Number|Number|Per Sw Tab|Low|Number|Reading| 35 to 20

PS
Position|Position| HV |596-A2 {Low| FI
3 2 596-B PS 1 596-A
596-A1 | Hi
£ ;
Position|Position| HV |592-A2 Low| FI
2 4 502-B | FS ? 592-A
592-A1 {51
pS .
Position{Position| HV 593-A2 iLow FI
2 5 |593-A1| BS " [593-A
503-A1 cHi
Table L4H-3
FUEL PUMP OVERFIOW TANK LEVEI, SYSTEM
s i
Hi & Low Flow Alarm XA-L4006-6 Time (sec.) i
Test |Supply owitch Hi |Flow Indicatorf for FI to
Switch [Valve Set Point jor Alarm | drop from
S-38  [Number |Number |Per Sw Tab|Low|Number|Reading| 35 to 20
m B
Position| HV [|599-A2 Low; FI
2 599-B PSs 599-A
590-A1 Hi
PS
Position{ HV |[589-A2 Lowl FI
h 589-B PS 589-A
589-A1 Hi |
PS :
Position| HV |600-A2 Low: FI
5 600-B PS ; 600-A
600-A1 JHL -

- (./( 4

S A

Approved by, A" N s Y1

Y4

COOLANT PUMP LEVEL SYSTEM

Table LH-L

LH-2k

9/17/65

13.4 Set the fuel pump, fuel pump overflow tank

Supply Value

HV-596-B
HV-592-B
HV-593-B
HV-599-B
HV-589-B
HV-600-B
HV-598-B
HV-594-B
HV-595-B
1k

and coolant pump bubbler system gas flows as

given in the building log.

Actual Reading After Setting

Log Value

FI-596-A
FI-592-A
FI-593-A
FI-599-A
FI-589-A
FI-500-A
FI-598-A
FI-594-A
FI-595-A

FURL PUMP OVERFIOW TANK BUBBLER

Hi & Low Flow Alarm XA-L0O5-4 Time (sec)
Selector Test Supply Switch Hi |Flow Indicator: for I to
Switch | Switch Valve Set Point | or Alarm | drop from
S5=-39 S-40 Number|Number |Per Sw Tab| Low| Number! Reading { 35 to 20
PS
Position|Position| HV |598-A2 Lowi FI
b 2 598-B PS 598-A
598-A1 Hi
PS
Position |Position] HV |594-A2 Low| FI
L i 594-B PS 594-A
594~A1 Hi
PS
Position {Position Hv 595~A2 Iow| FI
2 5 595-B PS5 595-4A
595-A1 Hi
Init. Date/Time

SDYSTEM: TLEVEL

INDICATION AND INTERIOCK CHECKS

NOTE :

Enclosure 2 must be open.

In order to complete these checks Containment

o
Approved bygflfi%it%i;%;iigfiflflfifi1

Init.

LH-25
9/17/65
Date /Time

14.1 Check that annunciator XA-4O06-5 is clear.

14.2 Check that lights in Circuit 21 on jumper

board 2 are burning.

14.3 While observing PI-589-A (Aux Panel 8),
slowly close HV-589-C (Containment Enclosure 2)
and record PI-589-A and FI-589 when the fol-

lowing actions occur:

Switch No. Sw Tab Setting Action PI-589-A FI-589

PSS-5890-A2 Turn out
light in
) Ckt. 21
PSS-589-A2 Alarm
XA~L4006-5

*
NOTE: If alarm does not occur, check HV-589C closed

NOTE :

and slowly open HV-589B to increase pressure
on PI-589A.
144 Open HV-589C and note that the alarm and

circuit lights clear.

The action of PSS-589-A1 is checked during the
routine fuel system pressure tests.

14.5 Check that annunciator XA-4007-2 is clear.

1Lh.6 Check that the top light in circuit 19 on

Jumper board 2 is burning.

14.7 Close HV-599B (Transmitter Panel 5)

14.8 While observing LI-599-Bl (Auxiliary
Panel 8) and LI-599-B2 (Transmitter Panel 5)
slowly close HV-599-C and record LI-599-El
and LI-599-B2 when the following actions

oceur:
Swch. No. Sw. Tb. V1 Action LI-599-B1 LI-599-B2
I5-599-B Alarm XA-400T-2
1SS-599-B Turn out top

-

light in Ckt 19

Approved by - =%

Sweh.

af vt
ey s
,,/i;ij?fi%ffiflt

Init.

L H-26
9/17/65

Date /Time

14.9 Open HV-599-C and note that the alarm and

circuit light clear.

14.20 Check that the top light in circuit 18

on jumper board 2 is burning.

14.11 Close HV-600-B (Transmitter Panel 5).

14.12 While observing LI-600Bl (Auxiliary
Panel 8) and LI-600-B2 (Transmitter Panel 5)
slowly close HV-600-C and record LI-600-BL
and LI-600-B2 when the following actions
occur:

No. Sw. Tb. V1 Action  LI-600-Bl LI-600-B2

1LS-600-

B Alarm XA-40OT-2

1SS~600-B Turn out top

15

light in Ckt 18

14.13 Open HV-600-C and note that the alarm and

circuit light clear.

1L.14 Set HV-589-B, HV-599-B, and HV-600-B as
per building log. (See item 13.4 this

procedure. )

FUEL PUMP BUBBLER SYSTEM: TIEVEL, INDICATION AND

NOTE :

INTERIOCK CHECKS

In order to complete these checks Containment

IEnclosure 2 must be opemn.
15.1 Check that the lights in circuit 20 on

Jjumper board 2 are burning.

15.2 Check that the lights in circuit 129 on

Jumper board 2 are burning.

15.3 Check that there is cover gas flow to the
fuel pump as indicated by FIC-516-B (Main
Panel 9) and Record FIC-516-B

15.4 Check that annunciators XA-LO06-5
and XA-400T7-5 are clear.

RN
Approved hy45fi:?fii}£§%%7%%aq_

Init.

YH-27
9/17/65

15.5 While observing PI-522-A (Sampler Enricher
Panel 2), PRC-522-A (Main Panel 8), PI-592-B
(Auxiliary Panel 8) and FIC-516-B (Main
Panel 8) slowly close HV-592-C (Containment
Enclosure 2) and record the data in the
following table as the indicated action
occurs.:

Action Switech No. Sw Tab V1 Record

Turn ocut lights
in Circuit 20  PSS-592-B2 PI-522-A

PI-592-B
PRC-522-A
- Alarm XA-LOOB-5  PS-522-A2% PI-522-A
PI-592-B
PRC-522-A
PS-592-B¥. 8 PI-522-A
PI-592-B
PRC-520-A

Turn out lights
in Circuit 129 PSS-522-A PI-522-A

- | PI-592-B
PRC-522-A

Alarm XA-40OO7-5  FS-516-B PI-522-A

N PI-592-B
PRC-522-A

. FIC-516-B

Date /Time

*An instrument mechanic may be required to determine
that both switches cause the alarm.
NOTE: The action of PSS-592-Bl is checked during the
routing fuel system pressure test.
15.6 Check that FIC-516-B is indicating zero
flow __ and that FCV-516-B2 (on solenoid

LS

rack) is deenergized

A

B
Approved by -1'4;‘p¢?94yfyq

. 14

Init.

4H-28
9/17/65

Date /Time

15.7 ©Slowly open HV-592-C (Containment En-
closure 2) until XA-4OOT-5 clears and then
close HV-592-C _ . Note that the flow,
as indicated by FIC-516-B returns to

normal

15.8 While observing PI-522-A (Sampler Enricher
Panel 2) and PRC-522-A (Main Panel 8) open
HV-592-C just enough to produce a slow pres-
sure decrease, and when PS-522-A1 causes

XA-4006-5 to alarm record the following:

Switch Tabulation value for PS-522-Al s
PRC-522-A , PI-522-A
15.9 Open HV-592-C fully . Set HV-592-B

per building log (see item 1L.L4 this
procedure) . . Check that the annunci-

ators and circuit lights clear

15.10 Check that the Normal Fuel Drain Switch
(S-T) on console panel III, is in the "off"

position.

15.11 Check that the following freeze valves
indicate that they are frozen.
FV-103 FV-104
FV-105 FV-106

15.12 Set the fuel-pump selector switch (8-36)

on main panel 8, to position 2.

15.13 Check that the following circuits on Jjumper
panel 1 are as follows:
Ckt. 117: Top three (3) white lights burning

Ckt. 118: Top three (3) white lights burning

Ckt. 119: Top three (3) white lights burning

"‘
T

Approved by

Init.

LH-29
9/17/65

Date/Time

15.13 (continued)
Circuit 138: Top white light burning

(jumper "A" may be inserted if re-

gquired) and the second white light out.

15.14% Check that the top white light in circuit
147 on jumper panel 2 is burning (jumper "A"
may be inserted if required) and the second

white 1light is out.

15.15 Insert Jumper in top jumper of circuit 150
on jumper panel 4 and check that the first
white light 1s out.

15.16 Note that annunciator XA-LOO6-4 is in the

alarm condition.

15.17 While observing LR-593-C (main panel 8)
and LI-596-B (transmitter panel 5), slowly
close HV-596-C to allow the fuel pump level
indicator to increase very slowly and record
IR-593-C, LI-596-B and the switch tabulation
valves for the indicated switches as the

following actions occur:

Action

Second white 1light in
circuits 138 and 147
comes on and the first
white light in circuit
150 comes on.

Annunciator XA-L0O06-4
clears

Annunciator XA-LO0O6-4
alarms

Third white light in
circuits 117, 118, and
119 goes out.

LR-593-C LI-596-B

SW. No.

Sw.
Tab
Val

155-593-C1

L5-593-C3

L5-593-C2

155-593-C2

Approved byfl/ Q%T?/MM

15.18 While observing ILR-593-C (Main panel 8)
and LI-596-B (Transmitter panel 5) slowly
open HV-596-C to allow the fuel pump level

indication to decrease very slowly and record

IR-539-C, LI-596-B and the switch tabulation

values for the indicated switches as the

following actions occur:

Action LR-593-C LI-596-B ow. No. Sw. Tab V1

Init,

LH-30
9/17/65
Date/Time

Third white

light in Ckts.

117, 118, &

119 comes on 155-593-C2

Annunciator
XA-L0O06~k
clears 15-593-C2

Annunciator
XA-L0oo6-4
alarms | 1S5-593-C3

First white
light in ckt.
150 goes out
and the second
white light in

ckts 138 &
147 goes out. _ 188-593-C1
15.19 Open HV-596-C fully and set HV-596-B
per building log (see item 14.4 of this
procedure ).

15.20 Set the fuel pump selector switch (S-36)

on main panel 8 to position 3.

15.21 Check that the following circuits on jumper

panel 1 are as follows:

Top thiee (3) white lights burning in
circuits 117 _  , 118 ___ , and 119 __
Top white 1light burning _ (jumper "A"
may be inserted if required) and the second

white light out in circuit 138.

P
R P

At
Approved byL A sait Lol

Init.

LH-31
9/17/65
Date/Time

15.22 Check that the top white light in circuit
147 on jumper panel 2 is burnhing (jumper "A"
may be inserted if required) and the second

white light is out.

15.23 Check that the top white light in circuit
150 on jumper panel 4 is out (jumper "A"

may be inserted if required).

15.24 Note that annunciator XA-4006-k4 is in the

alarm condition.

15.25 While observing LI-593-C (transmitter
panel 5) and LR-593-C (main panel 8) slowly
close HV-593-C to allow the fuel pump bowl
level indication to increase very slowly and
record LR-593-C, LI-593-C and the switch
tabulation values indicated as the following
actions occur: S

Action IR-593-C LI-593-C SW. No. Tab.
Val.

Second white light in
ckts. 138 & 147 comes on
and the first white light

in ckt. 150 comes on. ISS5-593-C1
Annunciator XA-4006-L4
clears IS5-593-C3
Annunciator XA-L006-L4
alarms I5-593-C2

Third white light in
ckts. 117, 118, &
119 goes out. ISS-593-C2

15.26 While observing ILR-593-C (main panel 8) and
LI-593-C (transmitter panel 5) slowly open
HV-593-C to allow the fuel pump level indi-
cation to decrease very slowly and record
LR-593-C, LI-593-C and the switch tabula-
tion values for the indicated switches as

the following actions occur:

Approved by _-

o
.i;}/;%@&wl

Init.

LH-32
9/17/65
Date /Time

Sw.
Tab
Action ILR-593-C LI-596-B Sw. No. Val

Third white light
in ckts. 117, 118,
& 119 comes on. L55-593-C2

Annunciator XA-L4006-L
clears _ 15-593-C2

Annunciator XA-LOO6-L
alarms 15-593-C3

First white light in

ckt. 150 goes out and

the second white

light in ckts 138 &

147 goes out. I185-593-C1

15.27 Open HV-593-C fully and set HV-593-B
per building log (see item 1L.L this

procedure).

15.28 Remove the "A" jumpers from ckts 138, 14T,
and/or 150.

16 COOIANT PUMP BUBBLER SYSTEM: ILEVEL INDICATION
AND INTERIOCK CHECKS
NOTE: 1In order to complete these checks the coolant

cell must be open,
16.1 Set the coolant pump selector switeh (8-39)

on main panel 6 to position 2 (B2).

16.2 Check that the lights in circuit 128 on

Jumper panel 2 are burning.

16.3 Check that there is cover gas flow to the
coolant pump as indicated by FIC-512-A
(main panel 5) and record FIC-512-A

16.4 Check that annunciator XA-LOOL-3 is clear.

16.5 While observing FIC-512-A (main panel 5)
and PRC-528-A (main panel 6) slowly close
HV-594-C to allow the pressure indicated by

PRC-528-A to increase very slowly and record

F
P

s
Approved Q&;ifiggéaiié;wufls‘_

16.5

Action

Annunciator
clears

Apnunciator
alarms

Tnit.

Y H-33
9/17/65
Date /Time

(continued)
PRC-528-A, FIC-512-A and the switch tabu-
lation values indicated as the following
actions occur:

Switceh No. Sw Tab Val Record

XA-L4005-2

PS-528-A2 PRC-528-A

XA-14005-2

PS-528-A1 PRC-528-A

Lights in circuit 128

go out

Annunciator
alayrms

16.6

16.7

Action

Annunciator
clears

PSS~528-A PRC~528-A

XA-4004-3

FS5-512-A FIC-512-A

Check that FIC-512~A is indicating zero
flow and that FCV-512-A2 (on solenoid

rack) is de-energized

While observing PRC-528-A (main panel 6)
slowly open HV-594-C (coolant cell) to allow
the pressure indicated by PRC-528-A to de-
crease very slowly and record PRC-528-A,
FIC-512-A and the indicated switch tabulation
values as the following actions occur:

Switch No. Sw Tab Val Record

XA-LOo0k-3

PS-512-A FIC-512-A

Lights in circuit 128

come on

Annunciator
clears

Annunciator
alarms

16.8

PSS-528-A PRC-528-A

XA-L0O5-2

PS-528-A1 PRC-528-A

XA-4005-2

PS-528-A2 PRC-528-A

Note that the cover gas flow to the
coolant pump as indicated by FIC-512-A
returns to normal (see item 17.3) and

open HV-594-C (coolant cell) fully

Approved bf)%'{r;'g//fl”\

16.9 Set HV-594-B per building log (see item
1Lk.4 this procedure).

16.10 Depress the Off Mode button (S-8) on
console panel 1.

16.11 Check that the lights on circuit 142 on

Jumper panel 3 are off.

16.12 Check that the top white lights in circuits
121 and 126 on jumper panel 3 are

burning.

16.13 While observing LR-595-C (main panel 6)
and LI-598-C3 (transmitter panel 6) slowly
close HV-598-C to allow the level indicated
on LR-595-C and LI-598-C3 to increase very

slowly and record LR-595-C, LI-598-C3 and the

switch tabulation values indicated as the

following actions occur:

Action Switch No. Sw Tab Value Record
Annunciator
XA-4005-3 clears  IS-595-C2 LR-595-C
LI-598-C3

Top light in
circuit 142 comes

on 1S55-595-C1 LR~595-C
LI-598-C3

Annunciator

XA-4005-3 alarms  LS-595-C3 IR-595-C
LI-598-C3

Lights in circuits

121 & 126 go out  ISS-595-C2 IR-595-C
LI-598-C3

16.14 While observing LR-595-C (main panel) and
LI-598-C3 (transmitter panel 6) slowly open
HV-598-C (coolant cell) to allow the level
indicated on LR-595-C and LI-598-C3 to de-

crease very slowly and record LR-595-C and

Init.

LH-34
9/17/65

Date/Time

-
w7 2
Approved by’%)%’wfifli

Init.

LH-35
9/17/65

Date /Time

16.14% (continued)
LI-598-C3 and the switch tabulation values

as the following actions occur:

Action Switch No. Sw Tab Val Record

The top lights in
ckts. 121 & 126

Annunciator

Lights in c¢ircuit

Annunciator

come on. I55-595-C2 IR-595-C
LI-598-C3

XA-4005-3 eclears  IS-595-C3 LR-595-C
LI-598-C3

142 go out 1SS-595-C1 LR-595-C
| LI-598-C3

XA-4005-3 alarms  ILS-595-C2 LR-595-C
LI-598-C3

16.15 Open HV-598-C (coolant cell) fully
and set HV-598-B (transmitter panel 6) per
building log . (See item 1k4.k4 this

procedure. )

16.16 Set the coolant-pump selector switeh (S-39)

on main panel 6 to position 4. (BL)

16.17 Check that the top white lights in circuits
121 and 126 on jumper panel 3 are

burning.

16.18 While observing IR-595-C (main panel 6)
and LI-595-C3 (Transmitter panel 6) slowly
close HV-595-C to allow the level indicated
on LR-595-C and LI-595-C3 to increase very
slowly and record LR-595-C, LI-595-C3 and the
switch tabulation values indicated as the

following actions occur:
Approved by -

i

e
#“;“”jfififlfl

Action

Annunciator
XA-4005-3 clears

Top light in
circuit 142 comes
on

Annunciator
XA-4005-3 alarms

Lights in circuits
121 & 126 go out

V4

Switech No. Sw Tab Val

L5-595-C2

188-595-C1

L5-595-C3

1SS-595-C2

Record

LR-595-C _______
LI-595-C3

LR-595-C
LI-595-C3

LR-595-C

LI-595-C3

LR-595~C
LI-595-C3

16.19 While observing LR-595-C (main panel) and
LI-595-C3 (transmitter panel 6), slowly open
HV-595-C (coolant cell) to allow the level
indicated on ILR-595-C and LI-595-C3 to de-

crease very slowly and record LR-595-C,
LI-595-C3 and the switch tabulation values

indicated as the following actions occur:

Action

The top white
lights in circuits
121 & 126 come on

Annunciator
XA-L005-3 clears

Lights in circuit
142 go out

Annunciator
XA-4005-3 alarms

Switeh No. Sw Tab Val

L55-595-C2

L5-595-C3

I55-595-C1

L5-595-C2

Record
LR-595-C
LI-595-C3

LR-595-C
LI-595-C3

IR-595>-C ___
LI-595-C3

LR-595-C
LI-595-C3

16.20 Open HV-595-C (coolant cell) fully
and set HV-595-B (transmitter panel 6) per

building log (see item 1L.4 this procedure.)

Init.

LH-36
9/17/65
Date /Time

»
LH-37
9/17/65
Tnit. Date/Time

17 If the containment-startup-check-1list tests have
been completed, check that the following valves are
open and install the flanges on the containment
enclosures. Test the containment enclosure per

containment-startup-check list.

Valve Init. Valve Init.
HV-600C HV-5T7T2A
HV-599C ___ HV-5TWFA
HV-589C HV-5T6A
HV-592C HV-516
HV-596C HV-519B
HV-593C ___

18 TDRAIN, FIUSH AND STORAGE TANK PRESSURES

Check that the drain tank receiver selector

switeh (S-4) is not switched to FST __ and reactor
is in prefill mode = . Referring to Table LH-5,
one at a time close the listed HV in the helium
supply to the tank. Then slowly add pressure
through the listed supply HCV by adjusting the

PIC and note that the pressure switches listed
cause the control action or annunciation listed
per Sw. Tab. Record the pressure readings when
these occur. Insert jumper and change drain-tank
selector switch where indicated. Remove Jjumper
and change selector switch to the original posi-
tion before starting next test. Also open HV's in
the helium supply to the tanks that were initially

closed.

19 IOW PRESSURE ALARMS ON DRATIN TANKS, FUEL PUMP AND
COQIANT PUMP
The Instrument Department should apply pres-

sure on the reference side of the transmitters
listed in Table LH-6. The low pressure alarms
should sccur at an equivalent pressure to that given

in the Sw. Tab. As the test is made Fill out Table L4H-6.
Approved by _%%ML 4H-138
| 9/17/65
TABLE LH-5
TANK
FD-1 FD-2 FPT CDT
Close HV 572 -A 57k -A 576 -A 511-B
Open HCV 572-A1 5TL-A1 576-A1 511-A1
Adjust PIC 517A 51TA 51T7A 511-B
PAdsSS or PSS No. 1000-Al 1000-B1 1000-C1. 511-D1
Sw. Tab. Value
Turn out lights in circuit 687 676 665 121, 126
Pressure indicator PR-572-B  PR-574-B  PR-576-B PR-511-D
Pressure reading
Insert jumper "A" in circuit 115 115 115
PSS No. 572-B2 5Th-B2 576-B2
Sw. Tab. Value
Turn out lights in circuit 720 709 698
Pressure indicator PR-572-B PR-5TL-B PR-576-B
Pressure reading
Switeh DT selector (S-4) to FST
PS No. 572-8B2 57h-B2 576~ B2 511-D1
Sw. Tab. Value
Alarm on XA L00g-2 4009-1 4009-3 L4OoL-6
Pressure indicator PR-572-B  PR-574-B  PR-576-B PR-511-D
Pressure reading
PSS No. 572-BL 5Th-BL 576-Bl
ow. Tab. Value
Turn out lights in circuit 115, 117 115, 118 115, 119
Pressure indicator PR-572-B PR-574-B  PR-576-B
Open HV 572 -4 5L -a 576 - 511-B
Remove jumper "A" in circuit 115 115 115

.
- - #‘{!
Approved bM55;;;;%5§%if%;fiéq¢q

LH-39
9/17/65
Init. Date /Time
i TABLE LH-6
Pressure PS No.  Sw. Tab Val  Annunciator Pressure
Transmitter Reecorder
PT-522-4A 5o2-A1 XA-4006-5 PR-522-A
PT-572-B 572-Bl XA-4009-2 PR-572-B
PT-574-B 57h-B1 XA-4009-1 PR-5T74-R
; PT-576-B 576-B1 XA-L4009-3 PR-576-B
PT-528-A 508-A2 XA-L005-2 PRC-528-A
PT-511-D 511-D2 XA-LOOL-6 PR-511-D
20 The Instrument Department has checked that the

following rolling diaphragm seals on the trans-

mitter vents are properly set and alarm on XA-4018-L

and the test lines have been capped.

Alarm on

Diaphragm Seal Sw. No. Press. Transm. XA-4018-L4 Init.

21

22.

PAli- 580
PXM-5T9
PXM-581
PXM-582
PXM-58L
PXM-586

PX3-580
PXS-579
PXS-581
PXS-582
PXS-58Lk
PXS-586

PT-592-B
PT- 5001
PT-589-A
PT-572-B
PT-574-B
PT-576-B

Check that all contaimment enclosures opened for

the above tests have been closed and have been

tested as described in the containment startup
check lists.
Lower the getting of FIC-516-B and note that

FS-516-B annunciates on XA-4OOT7-5 per Sw. Tab.

Record FIC-516-B

FS-52L4-B should

also annunciate on XA-4007-6 per Sw. Tab.
Record FI-52L4-B

LH-40

Approved by
| 9/17/65

| Init. Date/Time
23 Lower setting on FIC-512-A and note that FS-512-A '

anaunciates on XA-4OOL-3 per Sw. Tab. . Record
FIC-512-A . FS5-526-C should also annunciate
on XA-LOOL-4 per Sw. Tab. . Record FIC-512-A

Reset FIC-516-B as found.
NOTE: It may be necessary to slowly close HV-512 to

get the desired actions. If so, be sure to open it

when check is completed.

24  Close HV-500-K and note that PS-500-E annunciates
per Sw. Tab. on XA-4028-1. . Record PI-500-Gl
_____+ Open HV-500-K.

25 Increase PCV-500-G and note that PS-500-Bz annun-
ciates on XA-4028-2,  , PS-506 annunciates on
XA-4028-7 _ , and PS-507 annunciates on XA-L028-8
as per Sw. Tab. _ . Record PI-500-GzZ __ . Re-
duce PCV-500-G and note that annuncilations clear
and PS-500-Bl reannunciates per Sw. Tab. on XA-4028-2

Record PI-500-G2 . Bet PCV-500-G as

found

26 Close HV-500-E and note that PS-500-K annunciates
on XA-4028-4 and PS-509-A annunciates on XA-4035-1
(at S-E panel) per Sw. Tab. . Record PI-500-A.

27 Note that PS-509-B anmunciates on XA-4035-3 (at
S-E Panel) per Sw. Tab. . Record PI-500-A
____+ Instell temporary pressure gages and hand
valves (per sketch below) on the vents of HV-500-N1,
Nz, and N3.

(LY
LH-41

Approved by / /6
/L7765

- Init. Date/Time

LINE S007

Purge out oxygen, then close HV-X1l, X2, and X3,

leave HV-500-N1, N2, and N3 open. Open X1 until

PI-N1 reads approximately 25 psig. Slowly open

temporary HV-X2 and note that PSS5-500-N2 turns

out lights on ECC-40 and 41 per Sw. Tab.

Record PI-Na _

Close HV-X2 and slowly open HV-X3. Note

. that PSS-500-N3 turns out lights in ECC-40 and.
L1 per Sw. Tab. . Record PI-N3.

. Close HV-X1 and slowly open HV-X1l. Note
that PSS-500-N1 turns out lights in ECC-40 and
41 per Sw. Tab. . Record PI-NL . Close
HV-L0O-N1, -N2, and -N3 and tag closed. __

28 Check that there is flow indicated on FIC-516-B
and 512-A and check that there is flow through
each bubbler. . Record PCV-500-C

Increase PCV-500-C and note that PS-500-L2
annunciates on XA-4028-5 per Sw. Tab.

Approved by AL L3 LH-42

- A4 9/17/65

Init. Date/Time

28 (continued)

NOTE:

Record PI-500-M

Decrease PCV-500-C and note that PS-500-L1
annunciates on XA-4028-5 per Sw. Tab. . Note
that lights are out in ecircuits 40, 41, 115, 116,
126, and 127. Use jumpers as necessary to check
this, then remove Jjumpers.

Note that flow has stopped on the following:

FIC-516-B ___ FI-599-A
FIC-512-A ___ FI-589-A
FI-596-A FI-600-A
FI-592-A FI-598-A
FI-593-A _ FI-595-A __

FI-594-A

Open HV-519-A and note that PI-519 rises.
Close HV-519-A and note that HS-519-A will not
open HCV-519-A and B as indicated by the pressure
remaining high on PI-519 . Close HS5-519-A.

Raise setting on PIC-510-A and PIC-513-A
and note that pressure does not increase.

Return to settings as found.

Raise PCV-500-C to wvalues fofind at start of
test. BSet FIC—516-B, 512-4A, and bubblers as found.
Increase FIC-500~Jd and note that FS-500-J annun-
ciates on XA-4028-3 per Sw. Tab. . Record
FIC-LOO-J .

PS-508-A annunciation on XA-4028-6 is tested

during routine system pressure test.

29

Adjust the pressure controllers on the oil supply
tanks and note that the alarms occur per Sw. Tab.

and record pressures in table below.
’ Approved by;/cigfizggéé%é?fikfiflnmqy 4H-43
v 9/17/65
- Init. Date/Time
TANK PIC  PRESSURE SW. TAB. ANNUN.
NO. NO. SW. NO. VALUE PRESSURE NO.
OT-1 513-4A 513-Az XA-4008 -4
Or-1  513-A 513-Al XA-4008-L4
- OT-2 510-A  510-A2 XA-4003-L
g OT-2  510-A 510-Al XA-4003 -k

- 30

31

32

Set TIC-PHL-1 and TIC-O5R1-1 (TIC-PH2-1 and TIC-0-R2-1)
to turn heat onto preheaters and O, removal units.
Adjust setpoint on TS-PHL-Z, TS-0-R1-2, TS-PHZ-Z and
TSO-RZ2-2 per Sw. Tab.

Lower HIC-915-A to zero, open HCV-565-A and note
that there is flow through FqI-569-A

Lower the setpoint on RS-565-B and note that
lights go out in ECC-18 and ECC-80  annun-
ciation occurs at XA-4010-2  , light comes on
at monitor panel HCV-565 closes as indicated
by light on MB-3 and flow stops through FqIl-569-A

While observing temperatures on control rods
(R36, 37, 38, 39, 40, or Ll), raise setpoint on
HIC-915-A. Valve should not open and temperatures
should not change. Raise setpoint of RS-565-B and
push reset button. . Valve should open and
temperatures change . Reset RS-565-B set-

point as found.

Open HCV-565-A1. Lower the setpoint on RS-565-C
and note that lights go out in ECC-19,
annunciation occurs on XA-4010-2  , and light
comes on at monitor panel . Raise setpoint
on RS-565-C and push reset button. Note that

conditions clear.

Approved by

33

3k
35

36

BH-4h
9/17/65

Init. Date/Time

Lower setpoint on RS-528-B and note that lights

in ECC-18 and 147 go out, ___, annunciation

occurs on XA-4010-2 ____, and light comes on at

monitor panel _ . Raise setpoint to value as

found and push reset button. . Note that

conditions clear.

Repeat with RS-582-C.

Check that there is flow indicated on FI-836-4,

FI-838-A, FI-8L0-A, FI-830-A, and FI-8LkL-A.
Lower setpoint on RS—827-A and note that

annunciation occurs on XA-L010-2 ___and light
comes on at monitor panel
Lower setpoint on RS-827-B and note that flows
on FI-836-4, 838-4, 840-A, 830-A, and 84k-A go to
zero, and ESV-ST-A closes (physically check).
Raise setpoint on RS-827-A and push reset. Note
that flows start but annunciator does not clear
Lower setpoint on RS-827-C and note that flows
stop . Raise setpoint on RS-827-B and note
that {lows start but annunciator does not clear
Lower setpoint on RS-827-A and note that
flows stop _ . Physically check that both
FoV-847-A1 and FSV-8LL-A2 are closed .
Raise setpoint on RS-827-A and push reset

button. Note that flows start but annunciators

do not clear. . Railse setpoint on RS-827-C
and push reset button. Note that annunciators
clear.

Check that HS5-557-C is open. Record alarm set-
point on RS-557-A . Lower the setpoint on

RS-557-A and note that annunciation occurs on
y
Approved bymyfl

36

37

LH-45
9/17/65
Init. Date/Time
(continued)
XA-4010-2 , light comes on at monitor panel
, and HCV-557-Cl closes as indicated by light
on main board and visual observation Visually

observe that HCV-510-AZ and HCV-513-A2 do not open

when PIC-510-A and PIC-531-A setpoints are lowered.

Raise PIC-510 and 513-A setpoint to values as found.
Reise RS-55T7-A getpoint to value as found and

note that conditions clear.

Repeat with RS-557—B,
Check that flow is indicated on FI-596, FI-592,

FI-593, FI-599, FI-589, and FI-600. Record alarm

setpoints on RS-596-A , RS-596-B and
RS-596-C .
Lower the setpoint on RS-596-A and note that

annunciation occurs on XA-4010-2 and light

comes on at monitor panel

Lower setpoint on RS-596-B and note that
flows on FI-596, FI-592, FI-593, FI-599, FI-589,
and FI-600 go to zero
RS-596-A and push reset. Note that flows start
but annunciation does not clear

Lower setpoint on RS8-596-C and note that

Raise setpoint on

flows stop (i.e. pressures increase) Raise
setpoint on RS-596-B, push reset and note that
flows start but annunciator does not clear

Lower setpoint on RS-596-A and note that
flows stop. Raise setpoint on RS-596-A and note
that flows start but annunciator does not clear

Raise setpoint on RS-596-C and note that

annuhciators clear.

- 2)./ L

I AP
Approved by,<gfi5f ,%fi(,fi/fi¢7[
Vv

39

Lo

41

42
43

Lk

Have the instrument mechanic complete the process
radiation instrument check list and check out all
alarms, setpoints, and control actions using a
source at each element.
The process monitors are in service, the primary
element is properly located and the setpoint
agrees with master copy of process radiation check
list. See Table L4H-T.
The Instrument Department has put the neutron
instruments in service and has completed the neu-
tron instrument check list.
High level gamme instruments are in service.
The Health Physics Department will check the
functioning of each personnel radiation monitor
with a source. When this check is made, complete
Table 4H-8, checking that each monitor gives a
local indication and alarm and causes an alarm
in the auxiliary and main control rooms.
NOTE: The following should be approved by the
Operations Chief before proceeding. Health
Physics personnel should monitor the operations.
Open FCV-703 and then drain the oil from OT-1.
Note that LS-0T1-A3 annunciates on XA-4008-5 and
that LSS-0T1-A3 closes FSV-T03 _ per Sw. Tab.
Record LI-OT1l-A for each action.

Completely drain tank.

Add a total of _ of oil and note that
LI-07-1 reads approximately 55%. Record level
or-1

If lines to the salt pump are empty, add
additional oil, which should bring level to 95%.

If lines are full, do not add more oil. Record

LWH-46
9/17/65

Init. Date/Time

Approved;bgjig;fzgzééé;%%”dfl

LhH-47
4 9/17/65
TABIE LH-T7
POSITION
CF .
NO. ‘ LOCATION MONITOR ; SETPOINT | READING ;?NIT. . DATE

RE-506-4 - 8L0' Level 1 | |
RE-596-B - 840' Level ; ' |
RE-596-C | 840" Level |
RE-528~B  Vent House !
RE-528-C  Vent House
RE-500-D Water Room g
RE-675-A  Sampler
_RE-675-B . Sampler |
'RE-DT-1B | Service Tunnel ;
RE-DT-2B ! Service Tunnel )
RE-565-B | Vent House 3 |
'‘RE-565-C  Vent House |
;RE-557-B ' Vent House %
gRE-557-C Vent House
IRE-678-A | Sampler
RE-678-B | Sampler
5RE~827-A Blower House
RE-827-B | Blower House }
RE-827-C | Blower House

Approved by/%m. HH-18
9/17/65
TABLE L4H-8
PERSONNEL, RADIATION MONITOR |
! LOCAL |T.OCAL |{AUX. CR.|MCR. AIM.

=
o

i

TYPE | LOCATION

ALARM { INDCT. | ALARM

XA-4010-1 |DATE

C.A.M. :Control Room

a ¥
:Monitron iControl Room

‘Monitron Hi Bay (West)

‘Monitron Hi Bay (South)

iC.A.M. Hi Bay (South)

|C.A.M. Hi Bay (West)

!

Monitron 840" Level (HCP)

Fe

‘ \ _
Monitron ;840" Level (Horn Hall)

C.A.M. ;840' Level

C.A.M. 4Transmitter Room

Monitron iTransmitter Room

Monitron jService Tunnel

(OANN FO el NI \G I =l Fo AN A0, B FAVINS Dol (US IR VIR F ol (U8

[
C.A.M. hService Tunnel

P Y S

Ll

k5

(continued)

Init. Date/Time

oil added gal and LI-OTL-A

Tag fill and drain valves closed.

With FOP-2 in operation, slowly close HV-T71l3 and
note that PS-702-B annunciates on XA-4008-6 and
FOP-1 starts per Sw. Tab. Record PI-T702-A .

Open HV-713. .

Slowly close HV-71l4 and note that PS-701-B
annunciates on XA-4008-6 and FOP-2 starts per

Sw. Tab. Record PI-T701l-A .

Open HV-T1lk

46 Slowly close HV-703-B and note that FS-703-A
annunciates on XA-4007-1 per Sw. Tab. Record
FIL-703-A . FS5-703-A should turn out lights

in ECC 147 per Sw. Tab. (Jumpers may be used

.
i
Approved gzéfégfjjf’ Yt

L6

b7

L8
49

50

4H-L9
9/17/65
Init. Date/Time
(continued)
where needed.) Record FI-T03-A . Readjust
flows and note that alarm clears. _ Remove
jumpers.

/Slowly close HV-704 and note that FS-70L-A annun-

ciates on XA-4007-1 per Sw. Tab. Record FI-7O4-A
FSS-704k-A should turn out lights in ECC 1L47.

(Jumpers may be used where needed.) Record FI-70k-A
Readjust flows and note that alarm clears.

Remove Jjumpers.

Repeat test for COP-1 and COP-2.

NOTE: Obtain Operations Chief's permission before

doing the following:

Remove temperature switches from all four oil
pumps (TS-FOP-1, TS-FOP-2, TS-COP-1, and TS-COP-2)
and immerse in an oil bath and check that TS-FOP-1,
TS-FOP-2, TS-COP-1, and TS-COP-2 annunciate on
XA-4008-3 or 4OOL-1 per Sw. Tab. Record tempera-
tures. TS-FOP-1 _ Ts-FOP-z _ Ts-COP-1
TS-COP-2

Reinstall temperature switches and seal.

The following should be approved by the Operations

Chief before proceeding.

Health Physics coverage should be provided.

Open HV-720-A, T720-B, 525-A and 525-B, and
drein OCT-1 to WOR-1

Close 720-B and 525—3. Disconnect 720 line
from WOR-1. Attach a temporary line to line 720
and add __ liters of oil to OCT-1. LI-524-C
should indicate %, and LS-524-C should cause
the light at OCT-1 on MB to burn. Record oil
added
Approved by_/gfifi%i§§§¥5;644¢n1 4H-50
Lo sne “

50

51
52

53

5h

25

9/17/65

Init. Date/Time

(continued)
Drain oil to WOR-1 until OCT-1 reads 5 to 10%.
Record initial and final levels on LI-524 to

Tag HV-720-A, HV-720-B, HV-525-A, and HV-525-B

closed.

Repeat test for the coolant oil package.
Close HV-825-B and note that LS-ST-A annunciates
on XA-4027-7 and XA-4000-3 per Sw. Tab. as level

is lowered by removing water from the system at

a sample point or other convenient location.

(Have HP check for activity in the water.) Re-
cord LI-ST-B . Close the valve used to lower
the level in CST and open HV-825-B. HCV-825-A
should close when surge tank level is approxi-
mately  %.

With No. 1 TW pump in operation, throttle HV-829-A
and note that PS-829-B annunciates on XA-4026-10
and XA-L00CO-3 per Sw. Tab. Record PI-829-A
Open HV-829-A.

Close HV-890-B and check that water is flowing
through FI1-810-A. Note that PS-882-B alarms on
XA-4026-12. With No. 1 CT pump in service,
throttle HV-851-A and note that PS-851-B2 annun-
ciates on XA-4026-11 and flow stops in FI-810-A,
indicating that PS-851-Bl has switched HCV-882

to process water. (If No. 2 CT pump is in service,
throttle HV-853 for above test).

Record PI-851-A . Open HV-890-B and note

flow is indicated on FI-810-A. Open HV-851-A.

With the cooling tower water system in opera-
tion, throttle HV-851-C and note that F§-851-C
annunciates on XA-4027-1 and on XA-4000-3 per
52

- 56

PR / “'i/’ g
Approved by ;éfi?’zggpffiy%fi%W\‘ LH-51
: \v4 )

9/17/65

Init. Date/Time

(continued)
Sw. Tab. Record FIL-851-C.
Continue throttling HV-851-C and note that

high treated water temperature TS-826 annunciates
on XA-4026-4 per Sw. Tab. Record TI-829-1
Open HV-851-C.

With TW system in operation, adjust fiows to the

following and note that annunciations cccur as

listed in Table 4H~9. Readjust flows as found

and note that alarms clear. XA-4L000-3 should

also alarm and clear each time.

56.1 While cbserving PI-844 to be sure that it
does not exceed 16 psig, close FSV-847 and
note that PSS-84L-Bl closes FSV-8ik, FS-84h-A
alarms on XA-L026-1 and PS-84L4-B2 alarms on
XA-L027-8.

56.2 Close HV-830~A and note that FS-830-A operates

time-delay relay K-113 to stop FP in circuit
147. Use jumper if necessary.

56.3 Slowly close HV-840-A and note that FS-8L0-A
alarms on XA-4026-9.

56.4L Slowly close HV-838-A and note that FS-838-A
alarms on XA-4026-8.

56.5 Close HV-832-A and note that FS-832-A operates
time-delay relay K-11lhk to stop CP in circuit

142. (Use Jjumper if necessary.)

56.6 Slowly close HV-836-A and note that FS-836-A
alarms on XA-L026-7.

56.7 Open HV-848-A and HV-848-B and slowly add TW

to the nuclear instrument penetration until

LS-NP alarms on XA-4027-9 . (Close both
wvalves and remove water from penetration until
LS-NP alarms on XA-4027-9. Refill pene-

tration.

Approved @y23:;2;%54%§;;77¢fi¢¢7 hE-52
|74 ) ‘

9/17/65
TABLE U4H-9
. SW. TO. SW. TAB. SETTING | ALARM | ALARMED AT | OTHER ACTION |
éPss-8u4-Bl Closes FSV-8hk
TS-84L -4 XA-4026-1
PS-844-B2 XA-4027-8
iFS-830-A | Stops FP (15 min
l time delay)
iFS-BuO-A XA-4026-9
§FS-838-A XA-4026-8
%FS-832—A | Stops CP (15 min
| time delay)
FS-836-A XA-4026-7
LS~NP - XA-4027-9 !
FS-873-A - XA-LO27-2 ¢
FS-875-A XA-4027-3 fi
LS-FWT-1A | XA-4027-6 |
IS-FWT-2A | XA-4027-6 |
F5-821-A | XA-hO2T-4
FS-823-A % XA-4027-5 %

Init. Date/Time

56.8 Slowly close HV-873-A and note that FS-873-A
alarms on XA-4027-2.

56.9 Slowly close HV-875-A and note that FS-875-A
alarms on XA-4027-3.

56.10 Close HV's between FWT-1 and LT-FWT-1A. Drain
water from LT and note that LS-FWT-1A alarms
on XA-4027-6. Record level . Close drain

valve and open HV's and note that alarm clears.
Record level

56.11 Repeat for FWT-2. Alarms at level

Clears at level

Approved by fl%é (2t

56.12 Slowly close HV-821-B and note that FS-821-A
alarms on XA-L027-L4.

56.13 Slowly close HV-823-B and note that FS-823-A
alarms on XA-4027-5.

56.14 Remove jumpers.

57  Check that LI-806-A and 807-A indicate that the
steam domes are empty. If not, add water to top
leg of each DP cell by opening HV-824 (or HV-828)
until level reads zero or until it stops changing,
indicating that leg is full.

NOTE: Indicated level will decrease as water level in-

creagses until the top leg overflows. The water will

then go into the steam dome proper and indicated level
will increase.

Close the hand valves in both legs of the DP
cells (LT-806 and 807) and open the equalizing
valve. These are located in the north electric
service area. LI-806 and 807 should indicate
that the steam domes are full. Record LIC-806-A
_____and LIC-807-A ___ .

Close the two equalizing valves and open the
four supply valves to LT-806-A and 807-A.

NOTE: Hold the following tests to a minimum to avoid

putting too much water in the steam dome. Have an

instrument mechanic apply a millivolt signal to

TS-FD1-19B and note that ESV-806-A opens per Sw. Tab.

as indicated by LI-FWT-1l or LIC-806-A. Record tempera-

ture equivalent to millivolt signal needed.

Remove millivolt signal and repeat, using
TS-FD1-20B. Record temperature equivalent
Remove millivolt signal and plug TE's back into
patch panel. Have a millivolt signal applied to
TS-FD2-19B and note that ESV-807-A opens per Sw.

Init.

hH-53
9/17/65

Date/Time

Approved byfiffia?zzizf/ y ddakilaag LH-5k4 '
&r o v L

o7

29

9/17/65

Init. Date/Time -

(continued)
Tab., as indicated by LI-FWT-2 or LIC-80T7-A. Re-
cord temperature equivalent to millivolt signal
needed.

Remove millivolt signal and repeat using

TS-FD2-20B. Record temperature equivalent

Remove millivolt signal and plug TE's back into -
patch panel. . Bhift supervisor should check

that the four TE's are properly installed at the

patch panel. ©Shift Supervisor's initials __ . ~
Raise the setpoint on LIC-806-A and note (physically

observe) that LCV-806-A opens. __ Lower the set-

point. Raise the setpoint on LIC-807-A and note

(physically observe) that LCV-807-A opens

Lower the setpoint.

58.1 With both component coclant pumps running,
lower the setpoint on PAIC-960-A and note
that PAS-960-Al alarms on XA-4002-1 per Sw.
Tab. . Record PaIC-960-A .

58.2 Check that PAS-960-A2 opens PACV-960-A2 per
Sw. Tab. by turning off both component cooling - .

pumps momentarily . Record PAIC-960-A

_____+ Reaise setpoint to value in building log.
58.3 Stop CCP-1 and note that PS-791-B alarms on

XA-4002-3 . Start pump and note that alarm

clears
58.4 Stop CCP-2 and note that PS-795-B alarms on
XA-4002-3 . Start pump and note that alarm

clears.
58.5 Leave CCP-1 running and put CCP-2 in standby.
Lower the setpoint on PIC-906-B on WP and note
that PS-906-B annunciates per Sw. Tab. on XA-4002-2. .

Record PI-906-B .  Raise setpoint to value given
29

60

61

Approved byréfiéggiaéz%%?egflf”L_

Init.

L4H-55
9/17/65

Date/Time

(continued)

in building log .

Reduce setpoint on PIC~514, and note that PS-51L-Al
annunciates on XA-LOCO-4 per Sw. Tab. Record

PIC-51k4 . Raise setpoint on PIC-514 and note
that PS-51L4-A2 annunciates on XA-4000-4 per Sw.
Tab. Record PIC-51k .~ Restore to normal

Reduce pressure on line 4OC and note that
PS-400-AL annunciates on XA-400O-U4 per Sw. Tab.
Record PI-401 . Raise pressure on line 40O
and note that PS-400-A2 annunciates on XA-4000-L
per Sw. Tab. Record PI-hOl'____. Restore to

normal.

With the reactor and drain tank cells at normal
operating pressure (12.7 psia), jet both sumps to
the waste tank . Close HV-332-B and 342, and
stop Ny flow to RC and DIC sump bubblers. Check
with Operations Chief before proceeding. Remove
the cap from line 332 west of the building. Add
water to the sump and note that LS-RC-D annun-
ciates on XA-4029-1 per Sw. Tab. Record water
added . Do not exceed ____ liters. Replace
cap and jet sump. Alarm cleared = . Check

with Operations Chief before proceeding.

Remove ‘cap from line 342. Add water to sump and
note that LS-DIC-B annfinciates on XA-4029-2 per
Sw. Tab. Record water added ___ . Do not exceed

liters. Replace cap and jet sump. Alarm
cleared

Increase flow on LI-RC-C or open HV-965 and
note that LS-RC-C annunciates on XA-4029-2 per
Sw. Tab. Record LI-DIC-A . Decrease flow to

normal.

62

63

6L

L4H-56
9/17/65

Init. Date/Time

If possible, add approximately 1 gal. of water to
lines 315, 317, 319, and 321, and note that alarms

clear.

Alarms Clears Sw. No. 8Sw. Tab.

Liquid Waste

Cell

Equipment  XA-4029-8 LS-WTC-A
Storage Cell XA-4029-6 LS-5C-A
Spare Cell  XA-4029-7 LS-TC-A
Fuel

Processing

Cell ' XA-4029-4 ILS-FSC-A

Turn off power to sump pump and pit pump in sump
room below special eguipment room.

Add water to sump drum and note that LS-PRT
annunciates on XA-4029-3. Turn power onto pit
pump and note that alarm clears

Add water to sump and note that LS-PRS-B annun-
ciates on XA-L029-5. Turn power onto sump pump and

note that alarm clears.

Check the adjustable low weight alarm by raising

the alarm setpoint and checking that XA-L4OOT7-L

alarms for FD 1, FD 2, and FFT at the indicated
tank weight, that XA-LOOL-5 alarms for CDT, and
XA-4009-5 for FST.

Check the high and low level probes vs the
indicated weight as salt is transferred to or
from a tank. Record results in Table LH-10 and
LH-11.
Approved by.:¢5§%;:52943;;_ Vi g , 4H-5T7

9/17/65

Init. Date/Time

TANK SW. NO. SW. TAB. WEIGHT AT ALARM
FD-1 WS-FD1-C2

FD-2 WS-FD2-C2 |

FET WS-FFT-C3

CDT WS-CDT-CL

FST WS-FST-CL

65 Remove lines FD1-Cl-14 and FD1-Cl-31 from output

side of WM-FD1-C5 on TB-3 and cap fittings on WM.
Tee lines FDL-Cl-14 and -31 together and connect

ramp generator to other side of tee. Introduce a

decreasing signal from ramp generator into system
and note that WS-FDL-Ck alarms XA-LOOT-3 at LL6%¢,
on WI-FD1-Cl on TB-3 ___ . (This corresponds to

a, dw/dt decrease of 95 lb/min) and that WS-FD1-C3
turns out lights in circuits 116 and 117 at L1%e

on WL-FD1-Cl

decrease of

(This corresponds to a dw/dt
140 1% /min. )

Restore lines as found.

Remove
output side
on WM. Tee
and connect
Introduce a

into system

lines FD2-Cl-14 and FD2-Cl-31 from

of WM-FD2-CT on TB-3 and cap fittings
lines FD2-C1l-14 and FD2-Cl-31 together
ramp generator to other side of tee.
decreasing signal from ramp generator

and note that WS-FD2-Ck alarms

XA-4007-3 at 46%«p on WI-FD2-Cl on TB-3 |
(This corresponds to a dw/dt decrease of 95 1b/min)

and that WS-

FD2-C3 turns out lights in circuits 116

and 118 at ”1%'%3? on WI-FD2-C1 . (This corresponds

to a dw/dt decrease of 140 1b/min).

Restore lines as found.

Approved by,zzjggggg%gfifé;’fiééfiq

Init.

4H-58
9/17/65

Date/Time

TABLE L4H-10

Record weight when high level light is actuated

on changing level.

FD-1 FD-2 T ST CDT

Recorder

Live Manometer

Tare Manometer

Decreasing or
Increasing Level

Date

Initial

TABLE LH-11

Record weight when high level light is actuated

on changirglevel.

FD-1 FD-2 FFT FST CDT

Recorder

Live Manometer

Tare Mancmeter

Decreasing or
Increasing Level

Date

Initial

66  Open HCV-5kl, 545, am 546. Switch HS-573-4, 575-4,

57T7-A to open.

Switch receiver selector to FD-1. Introduce a

false air signal to the input of WR-FD-1 and note
that WSS-FD1-Cl turns on light in ECC 115 per Sw.
Tab.  Record WR-FD-1 . Close HCV-54Lk and
note that ZS-544-A turns light out in ECC 115 and
9/17/65

Approved by 4465;;;§;%:§%%§’fl?#v\ 4H-59

66

67

Init. Date/Time

(continued)
turns light on in ECC 117 ___ . Open HCV-54L and
reset tare to normal

Switch the receiver selector switch to FD-2.
Introduce a false air signal into the input of
WR-FD2 and note that WSS-FD2-Cl turns on light in
ECC 115 per Sw. Tab. . Record WR-FDz
Close HCV-545 and note that Z8S-545-A turns light
out in ECC 115 and turns light on in ECC 118 _
Open HCV-545 and reset tare to normal.

Switch the receiver selector to FFT. Introduce
a false air signal into the input of WR-FFT and note
that WSS-FFD-Cl turns on light in ECC 115 per Sw.

Tab. . Record WR-FFT ___ . Close HCV-546 and
note that ZS-546-A turns light out in ECC 115 and
turns light on in ECC 119 . Open HCV-546 and
reset tare to normal. . Set HCV-5kk, 545, 5.6,

573, 575, and 577 as found.
With fuel pump on and no sait in fuel system, push

calibrate button on SIT-FP-EL and note that SS-FP-EL
annunciates on XA-4006-2 and SSS-FP-EL turns lights
out in ECC 139 and ECC 150, and turns one light on

in ECC 116 . Use jumper where required.

Release calibrate button and note that con-
ditions clear

Push calibrate button on SIT-FP-EZ and note
that SS-FP-E2 annunciates on XA-4OO6-2 and SSS-FP-E2
turns lights out in ECC 139 .

Release calibrate button and note that con-
ditions clear

Push both calibrate buttons SIT-FP-El and
SIT-FP-E2 and note that XA-L006-2 alarms and that
two lights come on in ECC 116 and lights are out
Approved by

67

68

69

70

Init.

LH-60
9/17/65

Date/Time

(continued)

in ECC 139 and 150 .  Remove jumpers.

Disconnect the FP's speed element input from
SIT-FP-El or E2 and connect it to an oscilloscope.
If the FP is rotating in the proper direction, the
pulses will appear in the following order: long,
medium, short.

Reconnect the input to SIT-FP-El or EZ2.

As various freeze valves are thawed and frozen,
note that the interlocks and position indicators
function as indicated in Table 4H-12 and Table
4H-12a. Indicate that the interlock functions by

the use of check marks.

Temperature Alarms -- The following tests will be

done in conjunction with the instrument department.
For each of the alarms listed in Table L4EH-13,
provide a millivolt signal at the patch panel and

note that annunciation occurs at the millivolts

equivalent to temperatures listed in the Sw. Tab.
Adjust the setpoints if they deviate more than *
2%. Be sure to plug TE back in when test is com-

plete. Shift Supervisor check TE's properly plugged.

When system is at temperature, activate test switch
HS-100-A1 under TI-100-Al and note that TS-100-Al
annunciates on XA-4006-3 per Sw. Tab. Record
TI-100-A1 . Also note that TSS5-100-Al-1 turns
out safety channel No. 1 light on MB-13 (console).
Record TI-100-Al.

Activate test switch HS-100-AZ under TI-100-Az
and note that TS-100-A2 annunciates on XA-4006-3
per Sw. Tab. Record TI-100-AZ2 . Also note that
TSS~100-AZ-1 turns out safety channel No. 2 light
on MB-13 (console). Record TI-100-AL
Y.
Approved by Efifirffiyfiffififi/w%aq LE-61
av4 9/17/65
TABLE L4H-12
Check that Listed
Circuit Lights ™ No.
Freeze Valve go out as FV Ts-
Other Conditions Required |completes thawing |[FV- Sw. Tab.
No.| Condition or freezing Value
103| Thawing In Operate Mode 1h7-1 1A1,242
& 371
Freezing |In Operate Mode 116-2 2A1
104} Thawing FV-107 & 110 frozen, 116-A2 & B2, 119-1]1A1,2A2
FV-105 & 106 thawed. 120-1, & 134-2 & 3A1
Freezing |FV-105 & 106 frozen and 116-Cl & 136-2 1A1,2A2
S-6 set to FFT & 3A1
105{ Thawing FV-104 & 106 frozen. 116-A1 & C1, 118-1}1A1,2A2 |
FV-108 & 110 thawed. 120-1 & 134-2 & 3A1 ;
Freezing |FV-104 & 106 frozen & S-6 |116-B2 141,242 |
FV-109 & 110 thawed. 120-1 & 134-2 & 3A1
106} Thawing FV-10L4 & 105 frozen, 116-B2 & C1, 117-11A1,2A2
| FV-109 & 110 thawed. 120-1 & 134-2 & 3A1 |
Freezing |FV-10Lk & 105 frozen & S-6 |116-A2 141, 2A2 5
set to FD-1 & 3A1 ;
i
107 | Thawing FV-108 & 109 frozen, 115-1, 119-1, 1A1,2A1 :
FV-104k & 110 thawed, S-L4 |120-1 & 136-1 & 341 '
or 5-5 set to FST
Freezing |S-4 set to FFT, FV-108, 115-3 1A1,2A1
109, 110, 111 frozen & 3A1
S-5 set to FFT & S-4 not |115-4
set to FFT. FV-108,109,
110,111 frozen
108{ Thawing FV-107 & 109 frozen, FV- |[115-1, 118-1, 120-1|1A1,2A1
105 & 110 thawed. S-4 or |& 136-1 & 3A1
S-5 get to FOT
Freezing |{S-4 set to FD-2, FV-107, [115-3 1A1,241
109,110,111 frozen & 3A1
S-5 set to FD-2 & s-4 not [115-4
set to FD-2. FV-107, 109,
110, 111 frozen

7P

Approved by Lu-62
9/17/65
TABLE 4H-12 (continued)
|Check that Listed '
! Circuit Lights ;TS No.
Freeze Valve ! go out as FV LTS
Other Conditions Required . completes thawing ,FV- Sw. Tab.
No. Condition or freezing Value
.109 {Thawing FV-107 & 108 frozen, . 115-1,117-1,120-1 {1A1,2A1
‘ FV-106 & 110 thawed. S-4 & 136-1 & 3A1
( or S5-5 set for FST o
Freezing |[S-4 set to FD-1. FV-107, {115-3 1A1,2A1
108, 110, 111 frozen. 3 & 3A1
S-5 set to FD-1 & S-4 not ,115-4
set to FD-1, FV-107, 108,
110, 111 frozen.
110 | Thawing FV-10k4, 105, 106, 107, .115-1 & 120-1 1A1,2A1
108, or 109 thawed. & 3AL
; Freezing |S-4 set to FST, FV-107,  115-3 1A1,2A1
; 108, 109, 111 frozen & 3A1
? S-5 set to FST & S-4 not  115-4
set to FST. FV-107,
108, 109, 111 frozen. ' !
'111 | Thawing FV-107, 108, 109, 111 115-2 1A1,2A1
‘ frozen. & 3A1
20k :Thawing 1ho-2 141,242,
| & 3L
206 |Thawing  |FV-20L4 frozen. 142-3 1A1,2A2
& 3AL

=2) /oot
Approved byugfiégzggyc;/z%%fdwém
1 4

TABLE L4H-121

LH-63
9/17/65

Color : :
Position of Temperature Sw. No. Sw. Tab. Value
Indicator Light
ZI-FV-206-2A Red TS-FV-206-2A1
-2B Green -1431, 3AL
204 -2A Red 20k-2A1
-cB Green -1A1, 3AL1
112-2A Red 112-2A%
-zB Green -1A1, 3A1
111-2A Red 111-2A1
-2B Green -1A1, 3A1
110-2A Red 110-2A1
-2B Green —lAl,'3Al
109-2A Red 109-2A1
-zB Green -1A1, 3A1
108-2A Red 108-2A1
-2B Green -1A1, 3Al
107-2A Red 107-2A1
-zB Green =1A1, 3A1
106-24A Red 106-2A1
-2B Green -1A1, 3Al1
105-2A Red 105-2A1
-2B Green -1A1, 3A1
10k-2A Red 104241
-2B Green -1A7, 3A1
103-24A Red 103-2A1
-2B Green -1A1, 3A%

Approved by,%%/ aal 4H-6L4
o 4 9/17/65
TABLE L4H-13
TE and Switch Alarm Alarm | Alarm
TS No. - Now & No. Point | Point Date | Init.
Reset to
'FF-100-1 |{TX-3001-1 ' XA-4010-k
éFF-lOO—3 -2 | XA-4O10-L
| FF-101-1 -3 XA-4010-4
;FF-lOl-3 -L XA-L4010-k
|FF-102-1 -5 XA-hO10-L | |
 FF-102-3 -6 XA-4010-4 fi
FF-200-1 -7 XA-L010-k ;
FF-200-3 -8 XA-4010-k |
FF-201-1 -9 | XA-4OLO-k |
FF-201-3 -10 | XA-LO10-b4
R-L2B -11? XA-4010-4
R-45B -12, XA-4010-L |
R-33 13 | XA-b010-L §
R-L6B 1k | XA-40L0-b ;
FDL-19B -15| | XA-4010-k ¢
_16° XA-4010-k |
FD2-19B | -17' XA-4010-k
~181 'XA-40O10-4
% -19 XA-4010-4
o -20 XA-4010-b
FV-104-5A |TX-3002-1 XA-L020-2
FV-105-54 -2 -3
FV-106-5A ° -3 o |
FV-107-5A ; -l g XA-h021-3 | ;
FV-108-54 -5 -k ;
FV-109-5A | -6 E XA-h022-1 ;
FV-110-5A | -7 ; | -2 \
FV-111-5A | -8 -3

i
:
|
4

bt

Wl
i
li}
i
i
i

|

!

Approved'bygflgsgiz%gizffl%rh 4H-65
Y 9/17/65
TABLE L4H-13
{continued)
TE and Switch Sw. Tab. Alarm Alarm Alarm ! t
TS No. No. Value No. Point | Point | Date} Init.
Reset to
FV-112-5A -9 -4
| FV-20k-54 -10 XA-4021-1
FD-1-20B | TX-3002-11 None
-12
{ FD-2-20B -13 None
=14
1 705 -15 XA-4018-1
(707 -16 XA-4018-1
755 -17 -2
757 -18 XA-4018-2
OFT-6A -19
-20
FV-103-1A1 | TX-3003-1 XA-4020-1
FV-103-2A1 -2 XA-4020-1
FV-103-3A2 -3 XA-4020-1
FV-20L4-1A1 | -4 XA-4021-1
FV-204-2A1 -5 XA-4021-1
FV-20L-3A2 | -6 NA-4021-1
FV-206-1A1 . -7 KA-4021-2
EFV-206-2A1 | -8 %A-L021-2
| FV-206-342 -9 A -1021 -2
!AD-3-5B i -10 gA-aoos-z
AD-3-7B | -11 KA-4003-2
|FV-103-1A2 %TX-3ooh-1 KA-L020-1
'Fv-103-2A2 | -2 A-4020-1
FV-103-3A1 | -3 XA-4020-1
| FV-204-1A2 | -4 fii-hozl—l

Approved byfl% LH-66
- 9/17/65
TABLE 4H-13
(continued)
TE and Switch Sw. Tab. Alarm Alarm Alarm
TS No. No. Value No. Point Point Date] Init.
Reset to
FV-20L4-2A2 -5 XA-L021-1
FV-20k-3A1 -6 XA-4021-1 !
FV-206-1A2 -7 XA-4021-2 |
FV-206-2A2 -8 XA-4021-2 :
FV-206-3A1 -9 XA-L021-2 |
-10 XA-4021-2
FV-10L-1Al | TX-3005-1 XA-4020-2
FV-10k-241 -2 XA-4O20-2 ;
FV-104-3A2 -3 XA-4020-2 E
FV-105-1A1 | TX-3005-4 XA-4020-3 i *
FV-105-2A1 -5 XA-L020-3
FV-105-3A2 -6 KA-L020-3
FV-106-1A1 | -7 KA-4020-4
FV-106-2A1 8 XA-4020-L ;
FV-106-3A2 % -9 K A-4020-L
iFV-th-éA ; -10 KA-L020-2 |
' FV-105-6A % -11 XA-4020-3 %
FV-10L-1A2 : TX-3006-1 XA-4020-2 ! §
FV-10L-242 2 1XA-4020-2 | |
%FV-104—3A1 | -3 ! XA-4020-2 ? |
'FV-105-1A2 -4 i XA-4020-3 ; i
| FV-105-242 5 XA-4020-3 | %
FV-105-3A1 -6 - XA-4020-3 ; {
FV-106-1A2 -7 | XA-LO20-4 f
FV-106-2A2 8 XA-4020-4
FV-106-3A1 -9 YA-L020-b | @ |
-10 ‘ 5 !

Approved by Z 57 gyl LE-67
< % 9/17/65
TABLE 4H-13
(continued)
TE and Switch | Sw. Tab.| Alarm | Alarm| Alarnm | |
TS No. No. Value No. Point Point Date { Init.
Reset to

FV-107-1A1 |TX-3007-1 XA-4021-3 :
FV-107-2A1 -2 XA-4021-3
FV-107-342 -3 XA-4021-3
FV-108-1A1 -l XA-L0O21-1
FV-108-2A1 -5 XA-4021 -4
FV-108-3A2 -6 XA-4021 -k
FV-109-1A1 -7 XA-h022-1
FV-109-2A1 -8 XA-4022-1
FV-109-3A2 -9 XA-4022-1

-10 \
FV-107-1A2 | TX-3008-1 XA-4021-3 ! 3
FV-107-242 -2 XA-4021-3 | ;
FV-107-3A1 -3 XA-4021-3 % g
FV-108-1A2 -l XA-LO21-4 f |
FV-108-242 -5 XA-4021-k : g
FV-108-3A1 -6 XA-4021-k | §
FV-109-1A2 | TX-3008-7 XA-L022-1 E
FV-109-24A2 -8 XA-Lo22-1 i
FV-109-3A1 -9 XA-Loz2-1"! | i

-10'} | E !
FV-110-1AL | TX-3009-1 | XA-1022-2 | ? :
FV-110-241 2 XA-L022-2 | Z |
FV-110-3A2 3 XA-4022-2 | |
FV-111-1A1 o XA-4022-3 | '
FV-111-241 5 XA-L022-3 | !
FV-111-342 6 i XA-4022-3 }
FV-112-1A1 7 XA-hoaz-L -
FV-112-2A1 g XA-ho22-l

and note that
per Sw. Tab.

TS-100-A3 annunciates on XA-L006-3

Record TI-100-A3 . Also note

that T55-100-A3-1 turns out safety channel No. 3
light on MB-13 (console).

and 176.

Record TI-100-A3
Check that lights are on in circuits 18, 19,

Approved by W/ ‘?W"’L LH-68
9/17/65
TABLE 4H-13
(continued)
, , _

i TE and Switch Sw. Tab. Alarm Alarm Alarm

. TS No. No. Value No. Point Point {Date{ Init.
! Reset to
,FV—112-3A2 -9 XA-4022-4

-10

FV-110-14A2{ TX-3010-1 XA-4022-2

FV-110-242 -2 XA-4022-2

FV-110-3A1 -3 XA-4022-2

FV-111-1A2 -4 XA-4022-3

FV-111-2A2 | -5 XA-4022-3

FV-111-3A1 -6 XA-4022-3

FV-112-1A2 -7 XA-L4022-4

Fv-112-2A2 -8 XA-4022-4

Fv-112-3A1 -9 XA-Lo22-4

-10 |
Init. Date/Time
70 (continued)
Activate test switch HS-100-A3 under TI-100-A3

Simultaneously push two of the test switches

and note in Table U4H-14 when the following actions

occur.

//__‘.«—: o Ve »

Approved by fz%7<z§;fézof4aam4 ,_AH-69

T Y ‘ 9/17/65

Init. Datg/Time
TABLE LEH-1k4
Test Temperature Turns out Lights| Temperature
Switches Switches |} in Circuit Ind.
Readings

‘HS-100-A1 TS8-100-Al-2 176

i
'HS-100-A2 TSS-100-A2-2

HS-100-A1 TS5-100-Al-1 18

: and 19 é
;HS-100-42  TS5-100-42-1 ;
;HS—lOO—Al TSS-100-A1-2 176 |
{HS-100-A3 TSS-100-A3-2 :
t ; !
iHS-lOO—Al% TSS-100-A1-1 18 and 19 |
HS-100-A3 | TSS-100-A3-1} P
HS-lOO—AZ{ TSS-100-A2-2 | 176 ]
HS-100-A3 | TSS-100-A3-2 P
HS-100-A2 | TSS-100-A2-1 18 and 19 _
HS-100-A3 | TSS-100-A3-1 |

TL

Unplug TS-100-1 at thermocouple patch panel, feed
in a false signal and record temperature when
XA-4006-3 alarms

With the coolant system at temperature, test the
low radiator temperature interlocks as follows:
Actuate the test switch HS5-202-A under
TI-20z2-A and note that TS-202-A annunclates on

XA-4003-3 per Sw. Tab. Record TI-202-A
Actuate the test switch HS-202-B under
TIL202-B and note that TS-202-B annunciates on
XA-4003-3 per Sw. Tab. Record TI-202-B
Actuate the test switch HS-202-C under
TI-202-C and note that TS-202-C annunciates on
XA-4003-3 per Sw. Tab. Record TI-202-C .

Approved by %@L /)-LH?EO
’ 917765

Init. Date/Time

71 (continued)
Check that lights are on in circuits 11, 12,
140, and 1k1.

Simultaneously push two of the test switches

and note in Table LH-15 when the following actions

occur:
TABLE L4H-15
Test f Temperature | Turns out Lights | Temperature
Switches ! Switches in Circuits Ind.
Readings
HS-202-4 ! T8S-202-~-Al 11 and 12
HS-202-B . TSS5-202-Bl
\HS-202-B | TS5-202-B2
i
HS-202-A } TSS-202-Al1 11 and 12
HS-202~C TS8-202-CL
HS-202-A | TSS5-202-A2 | 140 and 141
HS-202-C | TSS-202-C2 i
HS-202-B | TSS-202-B1 11 and 12
HS-202-C TSS-202-CL
gHS-BOZ-B TSS-202-B2 140 and 141
{HS-202-C | TSS-202-C2
i :

T2 The Instrument Department has checked that the
following are set per the Sw. Tab. and annunciation

occurs as indicated;

Switch Ann. At. Initial
FS-201-A XA-5005-5
FSS-201-A XX

XpS-201-A  XA-L005-6
FS-201-B XA-4005-5
,-»fi/' .
Approved bngfigfifjgg;?i;q/o¢fflvL_
<

T2

73

Th

(continued)

Switch
FSS-201-B
SS-CP-GL
S5-CP-G2
S85-CP-G1L
S58-CP-G2

Return all circuitry to normal.

Ann. At.
XX

XA-4002 -k

XA-4002 -4
XX

XX

Init.

LE-T1
9/17/65

Date/Time

Initial

With the coolant salt circulating, activate the

calibrate butbons in the following combinations

and note that the lights in the circuits listed

go out.

Calibrate Button

FSS-201-A,
FSS-201-4,
FSS-201-4,
FSS-201-B,
FSS-201-B
SSS-CP-G2

F85-201-B
S55-CP-Gl
S58~-CP-G2
S85-CP-G1
535-CP-Ga

11,
11,
11,
11,
11,
150

Return system to normal.

Clear circults between each test.

12
12
12, 1h7
12, 147
12

Disconnect the'CP speed element input from

SIT-CP-G and connect it to an oscilloscope. If

the CP is rotating in the proper direction, the

pulses will appear in the following order:
medium, short.

Reconnect the input to SIT-CP-G.

long,

The following requires permission of the Operations

Chief

With coolant salt circulating,

radiator doors a small amount.

and HS-201-B simultaneously.

Return conditions to normal.

raise both the
Actuate HS-201-A

Note that doors drop

Raise doors,
Approved bx»;gfii%ffi%é%é%é;fihfl?%fl%,

T4

5

76

Init.

YH-72
9/17/65

Date/Time

(continued)
actuate H5-201l-A and HS-201-B simultaneously and
note that doors drop . Return system to nor-

mal.

With no salt in system, have the instrument depart-
ment set ZS-ADZ2-Al and A2 per Sw. Tab. Note that
zI-AD2-Al (green light) is on . Open damper
and note that ZI-AD2-A2 (red light) comes on
and ZI-AD2-Al (green light) goes out

Close damper and note that ZI-AD2-A2 (red
light).goes out and ZI-AD2-Al (green light) comes
on . Open by-pass damper fully and adjust

APSP = 0. Note that sixth light in ECC 150 is on

, bottom light in ECC 151 is ocut , and tenth
light in ECC 139 is on . Increase APSP >0 and
note that there is no change in ECC 150 . In-
crease APSP = 100% and note that fourth light in

ECC 153 goes out.

5 AMPLER

76.1 Close HV-509-A  and PV-509-B
Open HV-672 and slowly open PCV-672-A (area
3A purge) and lower the pressure until PS-509-D
alarms on XA-4035-3 and XA-40OO8-2 per switch
tabulation. Record PI-509-C . Clear
XA-LOO8-2 . Also note that PS-683-A alarms
on XA-4036-6 and XA-4LO0OB-2 per switch tabulation.
Record PI-509-C . Clear XA-L008-2.
Slowly open PV-509-B until PS-509-A alaxrms on
XA-4035-1 and XA-L0OO8-2 per switch tabulation.
Record PV-L09-B . Close HV-672 ___
PCV-672-A  , and PV-L09-B . Open
HV-509-A . Reset PV-509-B to 40 psig

and clear alarms.

7 9 4E-T3
_. ; 9/1.7/65

Init. Date/Time

76.2 Check that the permissive lights in the main
control room and at the sampler enricher panel
are actuated by the permissive switch on MB-8.

Leave on. Check that sampler light works.

76.3 Close capsule access door (HS-651), removal
valve (HS-RV), operational valve (HS-OV), and
HCV-678. Maintenance valve should be open
and cable drive withdrawn. DBuffer pressure
should be applied to RV, OV, MV and AD.

T76.4 Note that removal valve motor will not operate

but that operational valve will operate.

76.5 Close operational valve. Note that main-
tenance valve will close. Leave closed. Note
that access port will open. Close door. Note
that there is a 15 second time delay on
HSV-652.

76.6 Insert capsule rod into sampler access tube
and open HCV-666. Note that removal valve

can be opened.

76.7 With removal valve open, note that access
port operational valve, and maintenance valve

will not open.

76.8 Close removal valve and note that access port’

will open. Leave open.

76.9 Check that removal valve, operational valve,

and maintenance valve will not open.

76.10 Close access port and note that operational
and maintenance valves will open. Leave both

valves open.

76.11 Check that removal valve, access port and
HCV-678 will not open. Cable drive motor
will operate. Withdraw cable.

.
Approved b ¢;%£:; A LH-Th

9/17/65

Init. Date/Time

76.12 Close maintenance valve and note that cable
will not operate but ECV-678 will open. Open
maintenance valve. HCV-678 should close.

76.13 Close operational valve and note that cable
will not operate but HCV-678 will open. Leave

cpen.

76.14 Open HCV-675, HSV-660, and HSV-659 and access
door. Activate RS-675-A and RS-675-B with a
source and note that HCV-678, HCV-679, HSV-660,
HSV-569, and access door close and XA-4037-2
and XA-L008-2 annunciate.

76.15 Remove source and note that none of the valves

reopened and access door remains closed.
76.16 Open HCV-6T78 and note that operational valve

will not open.

76.17 Close maintenance valve and note that it will
not open.
76.18 Close HCV-678 and open operational valve and

maintenance valve.

76.19 Insert cable 4" and note that neither the

operational valve ror the maintenance valve will

close.

76.20 Insert cable and note that drive automatically
stops and green light comes on.

76.21 Remove cable and note that it automatically

stops and red light comes on.

76.22 Close operational valve, open HV-657 and
pressurize Area 1C until XA-4037-4 alarms.

76.23 Open HCV-678 to relieve pressure.

76.24 Operate the following and note that indicator

lights are functioning properly:
HS-RV HCV-679
HS-0V HSV-678

Approved by e W T LH-T75
N 9/11/65
Init. Date/Time
76.24  {continued)
HS-MV ECV-677
HCV-666 HCV-667
HCV-675 EOV-678-2

76.25 With manipulator cover on, pressurize area
3A until PS-AR-3A alarms on XA-4037-1 and
XA-4008-2 per switch tabulation. Record
PR-AR-3A.

76.26 With access door closed, pressurize area 1C
until PS-1C-3 alarms on XA—MOBT—l and XA-L4008-2
ver switch tabulation. Record PR-1C-E

NOTE: Check with Operations Chief before proceeding.

76.27 Close HV-542 in area 3B, open HSV-6T78-A,
HSV-678-Bl, ECV-667-A, and ESV-542-A. Pressur-
ize area 1C and note that PSS-542-B and PSS-542-C
both operate to close‘ESV—ShawA. Record PR-1C-E

NOTE: Check with Operations Chief before proceeding.
76.28 Disconnect line 650 at FE-650-C and slowly
back pressurize line 650 until PS-650-C alarms
on XA-4035-2 and PS-674-A alarms on XA-4035-4
per switch tabulation. Use a temporary gage

and record pressures when above actlons occur.

76.29 Allow leak detector header No. 2 to decrease
in pressure until PS-655-B alarme on XA-4035-6
and XA-4008-2 per switch tabulation. Record
PI-644-B

76.30 Allow leak detector header No. 1 to decrease
in pressure untlil PS-664-B alarms on XA-4035-5
and XA-4008-2 per switch tabulation. Record
PI-664-B .

76.31 Make a temporary connection to HSV-659-B in

area LA and pressurize area 2B slowly until
Approved by iZZEEfié?ié%Z%;zfi&zzfim

I

76.31 (continued)
PS-659-A alarms on XA-4037-3 and XA-L008-2 per

switch tabulation.

Use a temporary gage and

record pressure when above action occurs

LS-FP-Al
LS-FP-A2
LS-FST
Z5-MBlL-Al
7ZS-MB1-A2
ZS-MB2-Al
7ZS-MB2-A2
ZS-MB3-Al
7S-MB3-A2
ZS-MBA-AL
Z3-MBL-A2
LS-0T1-A2
LS-0T1L-A3
LS-0T2-A2
LS-0T2-A3
LS-PRS-A
LS-PRS-CL
Ls-PRS-C2
ZS-511-A
Ls-524-C
LS-526-A
75-527-A
Z5-533-A
75-536-A

ANRRRRRREEEEY

a

75-930-A3

Init.

YH-T76

9/17/65

Date/Time

As various systems are put into service, check
that the following position switches actuate the
corresponding position indicators per switch

tabulation:

7S-841-A
7ZS-84h-A
Z5-846-A
78-8L47-AL
7ZS-8L47-A2
XSS-930-A1
X55-930-4A2
Z35-930-A1
75-930-A2

T

ZS-930-Ak
ZS-930-45
ZS-930-A6
Z8-930-A7
78-930-A3
X88-930-BL
XS8-930-B2
Z8-930-B1
7ZS-930-B2
78-930-B3
78-930-B+
75-930-B5
z8-930-B6
75-930-B7

NERENE
7/4,

r’d

Approved by et /)1 foi YH-TT
~ 9/17/65

Init. Date/Time

77  (continued)

zZs-547-A Z8-930-B8
Z5-557-C X55-935-A1L
ZS-565-A X88-935-A2
7Zs-572-A 28-935-A1
Z5-573-A 25-935-A2
ZS-5Th-A 75-935-A3
ZS-575-A 7S-935-Ak
Z5-576-A 7Z5-935-A5
ZS-5TT-A __ Z8-935-A6 _
Z5-837-AL __ Z5-935-AT
Z8-935-A8

78  SAFETY INSTRUMENTATION

Check all safety instrumentation per operating

procedure 8D.
79 TEMPERATURE RECORDER ALARMS
Check that the instrument department has set the

following switches per switch tabulation:

TS-3100
TS-3300
TS-3400-AL
TS-3400-A2
TS-3500-Al
TS-3500-A2
80  STACK MONITORS
Check that the stack monitoring group has set the

s

following switches per switch tabulation:

RS-SI-Al
RS-SI-A2 (spare)
Approved bmh LH-78
9/17/65
Init. Date/Time
80 (continued)
RS-SI-BL
RS-SI-B2 ____ (spare)
RS-SI-CL
RS-SI-C2 __ (spare)
81  HELIUM DRYERS
Set the following switches at the helium treatment
station per switch tabulation:
TIC-DR1-1
TS-DR1-2
TIC-DR2-1
TS~-DR2-2
82  FUEL STORAGE TANK
Have an instrument mechanic check the settings on
the following switches per switch tabulation:
PSS-608-Bl PS-608-C1
PSS-608-B2 PS-608-C2
83  COMPONENT COOQOLING SYSTEM
Have an instrument mechanic check the settings on
the following switches per switch tabulation:
PS-T91-A4 PS-795-A
84  THERMAL SHIFLD COOLING WATER
Close HV-855-A, open HV-855-B and slowly apply
pressure through HV-855-B and note that PS-855
closes FSV-8LkL per switch tabulation . Re-
cord PI-855 . Restore valves to proper
positions.
85 DRAIN TANK CONDENSER COOLING WATER

Slowly close HV-810 and note that FS-810-A alarms
on XA-4026-1 per switch tabulation ___ . Record
FI-810-A . Slowly close HV-812 and note that
FS-812-A alarms on XA-L026-2 per switch tabulation
Record FI-812-A . BSet flows per building
=~ A 7 &, '
Approved by?zfifjjé;£v¢£:g<my¢¢wt
’ ) V4

85

86

init.

hH¥79
9/17/65

Date/Time

(continued)

log.

SUMMATION OF DRAIN TANK WELGHTS

87

Raise tare settings on FD-1 and/or FD-2 and note
that WgSS-1002 turns lights out in ECC-134 per
switch tabulation . Record Wql-100Z located
behind TB-4 . Reset tares

SCANNER NITROGEN PURGE

88

Siowly close PCV-5000-A at scanner panel and note
that PS-5000-A alarms per switch tabulation
Record PI-5000-A . Readjust PCV-5000-A .

NORMAL (SCANNER) NITROGEN SUPPLY SYSTEM

89

Close off both nitrogen bank header valves and note
that PS-9012-1A alarms on XA-4018-3 per switch tabu-
lation ___ and that PS~9014 alarms on _ per

switch tabulaticn . Put one bank back in

service and clear alarm . Slowly close PCV-901lz-1A
and note that PS-9012-1C alarms on XA-4018-3 per

switch tabulation . Slowly open PCV-901z-1A

and note that alarm clears and that PS5-9012-1B alarms
on XA-4018-3 per switch tebulation . Readjust
PCV-9012-1A per building log . Alarm should

clear

Check that the following Foxboro recorders.are

inking and the settings are per switch tabulation:

Instru. No. Location Setting Record Set Point

PRC-528 MB-6 Auto _____psig

XpR-201 MB-6 KKK XXXX _

FR-201 MB-6 XKXX XXX

WR-CDT MB-6 Auto 1b. below
salt wt.

TR-100 MB-7 XXXX XXX
89  (continued)

Instru. No. Location Setting Record Set Point

PRC-522 MB-8
WR-FD-2 MB-8
WR-FET MB-9
WR-FDL MB-10
WR-FST MB-11

PR-669-B S-E
PR-3A S-E
PR-655-C S-E

Q0 Check that the following Brown recorders are
inking, the instrument power, chart drive and
light switches are on, and the battery is good.
The setpoint should be adjusted by the instru-

Auto
Auto

Auto

Auto

Auto

XXXX

XXXX

____psig
_____1b below
salt wt.

. . .1b below __
salt wt.

___ 1b below __
salt wt.

______1b below
salt wt.

KEXX

s v
B ]
L ——

XXXX

ment department per switch tabulation:

Init.

LH-80
9/17/65

Date/Time

Instru. No. Location Record Set Point
RR-8100 MB-T XXKXK o
RR-8200 MB-12 XXXX

TRA-3100  MB-12 ~ __ and ____°F
TRA-3500 AB-2 and °F
TR-3600 AB-3 XXXX L
A-Be-R-1010 VH XXXX .
LR-CP-A TB-8 XXX

TRA-3300 ACP ____and °F
TRA-3400 ACP ____and __°F
TR-CTSS HB °F

Approved beffi§§§?32?1;€%?¢fi4¢L

o

Init.

WH-81
9/17/65

Date/Time

Check that the following Foxboro indicators are

in service and set per switch tabulation:

Instru. No. Location §Setting Record Set Point

PAIC-960-A  MB-3 Auto psig

PIC-510-A MB-L4 Auto psig

FIC-512-A  MB-5 Per S.8.. _ _ 1/m

PIC-511-C MB-5 Auto psig

LIC-807-4 MB-8 Auto o % o

FIC-516-B  MB-9 Per 5.S. ___ 1fm

PIC-517 MB-9 Auto __ _pesig

PIC-513-A MB-10 Auto ___ _psig

LIC-806-A4  MB-10 Auto %

92  Check that all Rochester units on AB 3 and 4 are
in the operate condition. List those which are
not and have 5.5. approve these.

S.5. approval

93 Check that the power switch is on and the reset
selector switch on manual reset on all ten Electro
System power supply in ACR.

94 Check that there are no jumper pins in the Jumper
board other than those approved in the run or shift
instructions.

95 Check that all green lights on the Jjumper board

are on except those approved by the 5.S.
Circuit S.5. Approval Date

F

Approved by/gZ€;£;;Zz%§459fiUh¢?k
\ 4

Init.

LH-82

9/17/65

Date/Time

95  (continued)
Circuit S.S5. Approval Date
96  Check that the scanner is in operation and will
alarm.
97  Check that the logger is in operation and will
alarm.
98  CONTROL ROD DRIVE TEMPERATURES
With the fuel system at temperature but empty,
close HCV-915-A1 (HIC-915-4) and record the
length of time it takes for the control rod
drive temperatures to rise to the alarm point:
Time to Alarm
Rod  Annunciator Time tc Alarm gfi;fi?d be Less
1 XA-kokl-l : . min.
2 XA-Lok1 -2 min.
3 XA-4Oh1-3 min.
Each also annunciates on XA-4013-1
Reset HIC-915-A to its previous valwe
99  VAPOR CONDENSING SYSTEM LEVEL

Vapor.condensing tank VIl is equipped with a four-
point float-operated level switch. The water level
under normal conditions will be midway between the
two center switches which are 4 in. apart, and mid-
way between the other pair of switches which are

12 in. apart. Thus, the switches will give alarms
locally and on XA-4014-5 if the water level goes

2 in. above, 6 in. above, 2 in. below, or 6 in.
below normal. The tank also has a 1/8 in. NPS
level dip tube for determining the water level in

the tank, but this system will not normally be used.
-,

Approved by /A//’/ QJZW Ao LH-83
i Y 9/17/65
Init. Date/Time

99

(continued)
Water can be added to or removed from the
tank by removing the 6 in. blank flange next
to the instrument installation. The water will
have to be added with a hose and removed by
siphoning or by means of a self-priming pump.
Remove the 9/16 in. Autoclave plug from
the level diptube in the 6 in. instrument
installation flange and connect a temporary
alrline equipped with a U-tube manometer to the

level diptube:

water | ,
level ac least /6
3 .
line Tygon tubing

With the water in VTl at the normal lével of 14 ft.
11 in., add water to the tank and record the levels
when the upper level switches actuate the alarms.
Lower the level in the tank and record the levels
when the upper alarms clear, and the lower alarms
are actuated. Refill tank to normal level and

record levels when tower alarms clear.
Approved by _fffigizgézzé/xunak
Y

Adding or

Removing Water Switch

Adding

Adding

Removing

Removing

Removing

Removing

Adding

Adding

Remove temporary equipment, replace level diptube

plug, replace and leak check 6 in. blank flange.
100 Radiator Door Scram Time

LS. VI1-B3
Lower upper

LS VT1-Bh
Upper upper

LS VI1i-B4
Upper upper

LS VI1l-B3
Lower upper

LS VIl-Bz
Upper lower

LS VI1l-Bl
Lower lower

IS VI1-Bl
Lower lower

LS VI1-BZ
Upper lower

Alarm

Clear PRBubbler Level

Init.

L8l
9/17/65

Date/Time

£t

in.

With coolant system empty, check the scram time of the radiator

doors as follows:

100.1 Raise inlet door to upper limit.

Simultaneously start a stop

watch and turn switch S-2 (load scram) to scram position.

Stop the stop watch when lower limit lights come on.

time

100.2 Repeat with outlet door.

Leave doors closed.

Record time

ALL ITEMS ON THE INSTRUMENTATION STARTUP CHECK LIST ARE

COMPLETE.

Shift Supervisor

Date

Record

Approved by—zfigizE;LQVé:;/antfl77 LI-1
%

10/14/65
LT Freeze Valves

The following check list covers the complete startup of each freeze
valve and adjusting each so that freezing and thawing can be accomplished
using the freeze valve switch on the main control board. This does not
need to be done on each valve on each startup. If a number of transfers
or additions are to be made, it may be desirable to set up FV-107 through
112 in this manner. However, for a single transfer it may be easier to
go directly from deep freeze to the thaw condition using heaters and
manual control of the air. When transfers are complete, the valves will
be deep frozen.

During a normal startup, FV-10k through 106 will normally be either
deep frozen or thawed, and no extensive adjustments are required. The
thawing of these 1s described in Section 5I.

On each startup, FV-103, 204 and 206 must be set up so that they
will thaw when required. These are also covered in Section 51.

The setting of the temperature switches, and freeze valve HIC's
and TIC's are covered in Section 4H.

The following is a detailed description of the steps necessary in
setting up a freeze valve for automatic operation. Table 4I-1 and 2
should be used for recording the data obtained.

1 DETATILED PROCEDURE

1.1 Obtain shift supervisor's permission to proceed. (Column 1.1)

1.2 Check that the associated lines are heated. Thaw or check
that the freeze valve is in the thaw position (Check that
interlocks are clear). (Column 1.2)

1.3 Adjust plug control heaters to give the temperature listed.
Record final temperatures. (Column 1.3)

1.4 Check that pressure on both sides of FV is balanced. Switch
freeze valve fio freeze position and set blast air HIC to
value given. (Column 1.4)

1.5 When both shoulder thermocouples reach ~ TSOOF, the alarm will
clear and the cooling air will be reduced from blast to hold.

Set TIC's on automatic. Adjust hold air HIC or set TiIC to
Approved bz?/fiéfi%z/ P LI-2
i v T | 10/14/65

1.5 (continued)
give the shoulder temperatures listed. Record final HIC

setting and shoulder temperatures. (Column 1.5)

1.6 When the freeze valve is thawed, note time required for valve
to thaw. Accurate indication of thaw time can only be obtained
by salt flow as indicated by rapid change in FV temperatures.
Less accurate indications can be obtained from the thermo-

couples without salt flow. Record any results obtained

(Column 1.6).

ALL ITEMS ON THE FREEZE VALVES STARTUP CHECK LIST ARE COMPLETE.
Shift Supervisor Date

- 7 "’
B Approved by .2 4 “\//f yAL? L1-3
T 14 10/14/65
'
TABLE 4I-1
STARTUP OF FREEZE VALVES 103, 104, 105, 106, 20k, and 206
Step DESCRIPTION OF
No. DATA FV-103 FV-10k FV-105 FV-106 FV-204 FV-206
1.1 Permission to Start
(SS Initials)
1.2 Line Hot and FV in
“ Thaw Position
FV Shoulder Rg?;;cor Note 1 H-FV-104-1|H-FV-105-1 'H-FV-106-1 | H-FV-204-1 | H-FV-206-1
. i :
Heaters Dra;? dg‘ank Note 1 ' H-FV-104-1A H-FV-105-1A|H-FV-106-1A) B-FV-204-14| R-FV-206-14
¥ ; : i
| Adjust to Dralf_;Efifflde; 1200°F 1200°F 1200°F 1200°F 1200°F 1200°F
| Average i
i' Temp. Reactor Side ! c ; o a ) ° o
1.3 i | 1200°F | 1200°F 1200°F 1200°F 1200°F 1200°F
TE-AL |
FPinal TE"B’-I- i
Temp. i
with TE-1 '
Air ' .
off T2 i
TE-3 | i
1 i
Blast HIC No. | 919 A-1 _ 908 A-1 909 A-1 910 A-1 | 906 A-1 | 907 A-1
1.} Air Setting | 16 ; 20 20 20 20 1 20 “
T ; —
HTC Initial ! |
Controller TIC HIC TIC TiC TIC | TIC ;
. No.r 919 A-2 | 908 A-2 909 A-2 910 A-2 906 A-2 | 907 A-2 |}
! I oo ] ! o o O o om_ o O o E o °p
‘ : Shoulder! g, 10°F-992 Ff 800°F-850°F | 800°F-850°F 800°F-850°F! 850°F-950°F . 850°F-950°F
1.5] Hold | Temps. : -
| Adp : Note 2 { TE~-3 | TO0°F-T764°F. 800°F-850°F |800°F-850°F, 800°F-850°F| 850°F-950°F |350°F-950°F
e ‘g 3 i
!Controller i 3
! ' Controller | o ¢
' i H ° o o o o
| Setting i 960°F Note 3 825°F 825°F 825°F 25°F _
i ‘
f Tnitial j
f T
1.6 Thaw ‘ TE-1 f
| Pime (sec) | TE-2 i
- a
i ! When Temp E TE-3 5
- T
: ! reaches ! When salt ' ! |
' 850° ; :

Note 1:- FV-103 is heated by the reactor vessel heaters.

Note 2:- Record eguilibrium values for TE-1 and TE-3.

Note 3:- Record setting necessary to hold shoulder temperatures listed.
= e e——— s =

;1.63 Time (Sec)

,152//f
Approved byafig?fd \féi?ffl!fiv\\

TABLE 4I-2

STARTUP OF FREEZE VALVES 107, 108, 109, 110, 111, and 112

LI-
10/14/65

DESCRIPTION OF
DATA

Step
No.

FV-107

FV-108

FV-109

Fv-110

Fy-111

FVv-112

Permission to Start

1.1 (S8 Tnitials)

Line Hot and FV in

1.2 Thew Position

FV Shoulder Hester
Controls
Both Shoulders i

. H-FV-107-1

H-FV-103-1

B-FV-109-1

H-FV-110-1

H-FV-111-1

H-Fv-112-1

Adjust to Average
Temperature
TE-Al and Bh

1200°F

1200°F

1200°F

1200°F

1200°F

1200°F

¢
§
|
1
—_—

1.3 TE-Al

TE- Bl

Final

Temperature

With TE-1

Air

Off TR-2 !

TB-3

DI QO

HIC No.

912 A-1

913 A-1

969 A-1

929 A-1

924 A-1

Blast

1.k Alr

Setting

[P R

HIC

Initial

HIC No. ;

912 A-2

913 A-2

969 A-2

929 A-2

g2k A-2

TE-1;

1.5 Shoulder [

Hold
Air

800°F-850°F

800°F-850°F

800°F-850°F

800°F-850°F

£ 800°F-850°F; 800°F-850°F

Controller Temps

TE- 3.

1 H
. 800°F-850°F; 800°F-850°F

800°F-850°F

800°F-850°F

800°F-850°F

800°F-850°F

&

**
{ Controller
Setting

? Tnitial

| TE-1

Thaw
TE-2 :

When

| Temperature TE-3 §

When Salt
TFlows

850°F

f Reaches
{

i
4
;

NPT S

i

*
Record equilibrium values for TE-1 and TE-3.

Record setting necessary to hold shoulder temperatures listed.

%4
ot
1. R
2, T
3. 8.
L. N.
5. R.
6. G.
. 7. R.
8. J.
et 9. Jd .
10. E.
11. R.
Y 12. A,
13. E.
14-18. R.
19-23. P.
2L, C.
A.
R.
C.
C.
R.
W.

60. D.
6l. H.
62. R.
63. Bruce Deering, AEC

ORNL-TM- 908

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