ORNL-TM-0908B.txt

 

ATI

i

LAB

ATORY LIBRARIES

1L

 

 

 

 

I

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

- R
OAl 3 4456 O549451 4 . LABORATORY
e operated by
UNION CARBIDE CORPORATION

for the
U.S. ATOMIC ENERGY COMMISSION

ORNL- TM - 908,

Volume I

MSRE DESIGN AND OPERATIONS REPORT
PART VIII, OPERATING PROCEDURES

R.H. Guymon

 

ey m -

 

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

 
 

l This report was prepored as an account of Government sponsored work, Neither the United States,

nor the Commission, nor any person acting on behalf of the Commission:

| A,

B,

‘ As used in the above, ‘‘person acting on behalf of the Commission

Makes any warranty or representafion, expressed or implied, with respect to the accuracy,
completeness, or usefulness of the information contained in this report, or that the use of
any information, apparatus, method, or process disclosed in this report may not infringe
privately owned rights; or

Assumes any liabilities with respect to the use of, or for damages resulting from the use of
any infarmation, apparatus, method, or process dis~losed in this report.

' includes any employee or

contractor of the Commission, or employee of such contractor, to the extent that such empleyee

or contraector of the Commission, or employee of such contractor prepares, disseminates, or

provides access to, any information pursuant to his employment or contract with the Commission,

or his employment with such cantractor.

-~ - LEGAL NOTICE — — = oo oo o o

| g
ORNL-TM-908,
Volume |l

MSRE DESIGN AND OPERATIONS REPORT
PART VIII, OPERATING PROCEDURES

R.H. Guymon

JANUARY 1966

OAK RIDGE NATIONAL LABORATORY

Oak Ridge, Tennessee
Operated by
UNION CARBIDE CORPORATION

for the

UNITED STATES ATOMIC ENERGY COMMISSION

ATIONAL LABORATORY LIBRARIES

T

3 4456 0549451 4

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
iii
PREFACE

The report on the Molten-Salt Reactor Experiment (MSRE) has been
arranged into twelve major parts as shown below. FEach 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. Each of the major divisions of
the report contains the bibliographical and other appendix information
necessary for that part.

The final volumes of the report, Part XII, 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 III,
Nuclear Analysis, by P. N. Haubenreich,
J. R. Engel, B. E. Prince, and H. C. Claiborne

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

 

*
Issued.
iv

ORNL-TM-"732% MSRE Design and Operations Report, Part V,
Reactor Safety Analysis Report, by S. E. Beall,
P. N. Haubenreich, R. B. Lindauer, and
J. R. Tallackson

ORNL-TM-T733% MSRE Design and Operations Report, Part VI,
Operating Safety Limits for the Molten-Salt
Reactor Experiment, by 5. E. Beall and
R. H. Guymon

ORNL-TM-907* MSRE Design and Operations Report, Part VII,
Fuel Handling and Processing Plant,
by R. B. Lindauer

ORNL- TM- 908 MSRE Design and Operations Report, Part VIII,
Operating Procedures, by R. H. Guymon

ORNIL-TM=-909 MSRE Design and Operations Report, Part IX,
Safety Procedures and Emergency Plans,
by A. N. Smith

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

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

MSRE Design and Operations Report, Part XII,
Iists: 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 ORNIL 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 NUCLE%R,ASPECTS OF OPERATION
- zA Simplified Reactor Theory

1

£ W m

[ ]
-

2B MBRE

= w M

3 OPERATION

Glossary

Atomic Structure

Radloactivity and Radiation

The Figsion Process

Cross Sections and Reaction Rates

The Fission Chain Reaction in an Infinite Reactor

Effect of Neutron Leakage

Criticality

Extraneocus Neutron Scurces and Subcritical Multiplication
Reactor Kineticé

Nuclear Instrumentation

 Reactor Control

Xenon and Samarium

NMuclear Characteristics

Core Reactivity Factors

Heat Generation and Temperature Distributions
Instrumentation

Kinetics and Safety
OF AUXILIARY SYSTEMS

3A Electrical System

oo

=~ W

System Startup
Normal Operation
Emergency and Special Operations

Normal Shutdown
3B

3C

3D

3B

viii

Instrument Air and Service Air Systems

1
a

3
L

Startup

Normal Operation

Emergency or Special Operation
shutdown

Water System

1
a

3
b

Startup
Normal Operation
Emergency Operation

Normal Shutdown

Component Cooling Systems

wvi & Ww o

Startup

Normal Operation
Emergency Operations
Special Operations
Shutdown

Shield and Containment

1

Reactor and Drain Tank Cells

1.1 Startup

1.2 Normal Operation

1.3 Emergency or Special Operation
1.4 Shutdown

Vapor Condensing System

2.1 Startup

2.2 Normal Operation

2.3 Emergency and Special Operations
2.4 Shutdown Operation

Coolant Cell and Coolant Drain Tank Cell
3.1 Startup

3.2 DNormal Operation

3.3 Emergency or Special Operations
3.4 Shutdown
3F

3G

30

31

ix

L Special Egquipment Room

5 West Tunnel and South Electric Service Area
6 Charcoal Bed Pit

7 Filter Pit

8 Auxiliary Cells
Ventilation System

1 Startup

2 Normal Operation

3 Operation during Maintenance
L Special Operations

5 Shutdown

Leak-detector System

1 Startup

z Normal Operation

3 Location of Lesking Flanges
L Shutdown Procedures
Instrumentation

1 Controllers and Indicators
2 Scanner

3 Computer

L Annunciators

5 Jumper Board

6 Other Instruments

6.1 FqI-569-A
6.2 AO5-566-A
6.3 PAE-RC-E
6.4 ABe-A-AD3
6.5 A0,-548
6.6 AH,0-5L8

Freeze Valves

1
2

3

Definitions and Criteria
Basic Operation and Interlocks

Operatidn 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

Bulilding Sump Operation

Pit Pump Operation

Treatment and Disposal of Waste Contents

~N O\ &= W v K

Clarification of Decontamination Tank or Decontamination
Cell Liguid

8 Backwash of the Waste Filter

9 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

L Coolant System Stack Be Monitoring Unit

AUXILIARY SYSTEMS STARTUP CHECK LISTS

La
LB
Le
4D
LE
LF
LG
Nt
ht

Electrical System

Instrument Air System

Cooling Water Systems
Component Cooling Systems
Shield and Containment Systems
Ventilation System
Leak-detector System
Instrumentation

Freeze Valves

Volume II1

REACTOR STARTUP

54
5B
5C
5D
5E

5F
5G
S>H

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-oil Systems for the Fuel and Coolant Pumps
Heatup of Fuel and Coclant Systems

Prepare Drain Tank Systems for Reactor Startup

Routine Pressure Test
51

5K

xi

I1lling the Fuel and Coolant Systems

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

Normal Operating Conditions

SAMPLING AND ADDITIONS

64

6B

6C

6D
6

Fuel System Sampling and Enriching

1 General Description of Sampling the Fuel System

2 General Description of Adding Enriching Capsules to the
Fuel System

3 Fuel System Sampling Check List

L Fuel System Enriching Check List

5 Fuel. System Sampler Startup

6 Fuel System Sampler Shutdown

7 Unusual Operating Conditions for the Sampler Enricher

Coolant System Sampling

1 General Description of Sampling the Coolant System

2 Coolant System Sampling Check List

3 Coolant System Sampler Startup

4 Coolant System Sampler Shutdown

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

-~ Oy 1 oW

PH Measurement

Cell Air

Lube Oil System

1 Sampling of New Oil as Received

o Sampling at 01l Packages

3 Addition of Lube 01l to 0il Packages
xXii

6F  Cover Gas
6G  Offgas System
HEAT BALANCE
TA  General Description
7B Computer Heat Balance
7C Manual Heat Balance
PERTODIC INSTRUMENT CALIBRATION AND CIRCUIT CHECKS
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
2 Radiation Monitor 557 (Offgas from Charcoal Beds)
3 Radiation Monitor 528 (Cooclant System Offgas)
L Radiation Monitor 565 (Cell Offgas)
5 Radiation Monitor 500 (Main Helium Supply)
6 Process Monitor 596 (Outside Transmitter Room)
7 Process Monitor 827 (Treated Water)
8 0il System Process Monitors (Service Tunnel)
8C Calibration of Personnel Monitors and Stack Monitors
1 Routine Source Check
2 Alarm Matrix Check
3 Evacuation Alarm Test
L Containment Stack Monitor Tests
8D Safety Circuit Checks

Fuel Pump and Overflow Tank Pressure
Helium Supply Pressure

FP and OFT Bubblers

Rod Scram Circuits

Emergency Fuel Drain

High/Low Reactor Cell Pressure

Cooclant Pump Speed and Coolant Salt Flow

Sampler-Enricher

W @O 1 Oy o o

Exercise Control Rods
xiii

9 UNUSUAL OPERATING CONDITIONS

OA

9B

9C

Ob

OF

oF

COH

o1
9J
9K

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 Outage

Failure of DG-5 during a TVA Power Outage

Failure of DG-3 and L4 during a TVA Power Outage

Failure of DG-3 and 5 or 4 and 5 during a TVA Power Outage
Loss of 250v DC Systems

O L -1 Oy B W

Loss of Instrument Power

Loss of Cooling Water

1 Treated Water System.

2 Cooling Tower Water

Loss of Fuel or Coolant Pump

1 Loss of Fuel Pump

z Loss of Coolant Pump

Loss of Instrument Air

1 Air Compressor Electrical Difficulties
2 Other Air Compressor Difficulties

3 Effects of Loss of Instrument Air
Radlation Increases

1 Personnel Monitorsg

2 Process Radiation Detectors

3 High Spack Activity

Control-rod Drive Difficulty

Loss of Computer

Lube-01l System Difficulties

L Coolant Salt Pump Lube System Failure
2 Fuel Salt Pump Iube System Failure

3 Total 01l System Faillure
ol Excess 0il Seal Leakage

Salt in Overflow Tank
Loss of Helium Purge to the Circulating Pumps

Loss of Component Cooling Blowers
10

11l

Xiv

OL  Removal of Water from the Steam Domes

9M  Regeneration of Helium Dryer

ON High Cell Leak Rate Indication

1
2
3
L

REACTOR SHUTDOWN

Salt Leaking into the Cell

Water Leaking into the Cell

Loss of Reactor or Drain Tank Space Coolers

Actual

digh Cell Leak Rate

10A Normal Shutdown

1

2
3.
L
>

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

1
2

3

Power Reduction and Going Subcritical

Draining and Flushing the Fuel System .

Shutdown of Remalning Equipment

SHUTDOWN OPERATIONS

11A Fuel or Flush Salt Transfers
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-2
Transfer from FST to FFT
Transfer from FD-1 to FD-2
Transfer from FD-2 to FD-1

O O 1 O F oW

= e
= N H O

Heatup
Heatup
Heatup
Heatup

Heatup

of FST

of Line 111

of Waste Line 112
of Fill Line 203

of" Transfer and Salt Addition Freeze Valve Assemblies
iz

13

11B

11¢
11D

XV

Opening Reactor Cell, Drain Tank Cell, and Coolant Cell Shields

O O 1 0w oW

.
O

Reactor Cell Heater Shutdown Check List

Drain Tank Cell Heater Shutdown Check IList

Coclant Cell Heater Shutdown Check List

Cocling Water Shutdown Check List

Freeze Valve Shutdown Check List

Component Cooling Air to Components Shutdown Check List
Component Cooling Pumps Shutdown Check List

Electrical Breakers Shutdown Check List

Opening Reactor Cell and Drain Tank Cell

Opening the Coolant Cell

Graphite Sampling

Routine Inspection and Testing of Equipment

1
2
3
L
5

6

Process Systems

Auxiliary Systems

Pressure Relief Valves

Rupture Discs

Reactor Cell and Drain Tank Cell Contaimment Vessels

Secondary Containment Vessels

ROUTINE OBSERVATIONS

1zA
1zB
12C
12D
12E

Logs

Check Lists

Recorders and Indicators

Computer

Tags

and Signs

MAINTENANCE AND CHANGES

13A
13B
13C
13D
13E

Msintenance

Modifications

Changes in Operating Procedures

Changes in Computer Program

Revisions of Approved Documents
9/7/65
SECTION 5
REACTOR STARTUP

After the auxiliary startup check lists have been completed, there
i1s still a considerable number of operations to be done prior to power
operation. The details of these are given in this section in chrono-
logical order. In each section a general description is given as to
what 1s to be done, what precautions are necessary and suggests corrective
action in case of difficulty.‘ This 1s followed by detailed check lists.
Section 5K describes the normal operation of the plant. Information
is given as to what equipment should be operated and in general how it
1s to be operated. The operational limits are covered by the Building

Tog. (12A-2A or 124-2B)
 
 

6/26/6M4 Aj%?f’ ,z/ 54-1

S5A PURGIfi%vOXYGEN AND MOISTURE FROM THE SALT SYSTEMS

 

After any appreciable amount of atmospheric contamination has occurred, as
when & system is opened for meintenance, it will be fiecessary to purge out most
of the oxygen and moigture befcre heat-up.

By evacuation and refilling the coolant system with helium, the oxygen and
moisture content can be reduced to a tolerable (~100 ppm) level. However, evacu-~
ation cannot be used on the fuel or fuel drain tank systems because fission gases
would be released from the charcoal beds. Oxygen and moisture will be removed
from the fuel system by purging a sufficlent amount of heliumffifiilé mixing with
the fuel pump. Since mixing during a continuous purge is not possible in the

fuel drain tenks, alternate pres jure-vent cycles will be used.

1  PURGING THE FUEL SYSTEM Init. Date & Time

Purging of the fuel system after maintenance will

 

consisgt of introducing helium into as many openings
as possible, circulating it with the fuel pump, and
venting continuously through the main charcoal beds.
A minimum of 9 fuel system volumes (~675 ft3) of helium
will be required to lower the oxygen concentration from
atmospheric to < 100 ppm. Details are given below:
1.1 Cleose or check that the following valves are
closed:
(High Bay Area)
Sampler-enricher coperational wvalve s
(Main Board)
F P vent HCV 533
Bypass valves HCV 54k |
HCV 5hs
HOV SBS
(Vent House)
Sample Station ¥ 518A‘___*H, and V-518E
(Coolant Drain Cell)
WOR V 7204 and V 20B __ _ ,

V 525A and V 525B ,

TX- 3545
(7-64)
  

Approved by ..~

(Electric Service Area)

V-519A

Init.

S5A-2
8/3/65

Date & Time

 

1.2 Check that freeze valves 10k, 105, and 106

are deep frozen

 

1.3 Set up maximum helium flows through the four
bubble tubes and the pump (FP) as follows:
(Diesel House)
1.3.1 Check helium supply of 40 psig on lines
501 and 516 _

 

(Main Roard)
1.3.2 Bet PCV-522 to 5 psig.

 

1.3.3 Set FP bubbler selector switch S-36
"voth bubbler" position

 

(Vent House)
1.3.4% Open V-522B and V-557B

 

1.3.5 Open two of the following pairs of

valves and close the other two pairs:

V-620 _ and V-624 5
V-621 _ and V-625 )
V-622 _ and V-626 5
V-623 _ and V-627

 

1.3.6 Open or check open the following:
(Special Equipment Room)

v-52ha

(Transmitter Room)
V-592A ., V-600A |
V-596A ___ , V-599A _
V-5938 _, V-5809A

 

1.3.7 Adjust bubbler throttle valves to ob-
tain flows as given in building log.
(Transmitter Room)
FP bubblers:
V-592B for FI-592
V-5968 for FI-596
V-593B for FI-593
5A-3
8/3/65
Init. Date & Time

 

 

OFT bubblers:

V 600B for FI 600

V 599B for FI 599

V 589B for FI 589 .

NOTE: The CFT bubblers may be plugged because

 

of a frozen heel of salt. This will be indicatead
by a high pressure on FI 599 and FI 600 (alarms

on XA 4006-6) and a false high level indication

on LI 599 and LI 600 (alarm on XA 4007-2). In

this event close block valves HV 599 and HV 600.

It would then be necessary to relieve the pressure
by turning test switch S-38 momentarily to
"equalizer No. 1" and then to "equilizer No. 2"
positions. Wait until the OFT temperature is

above salt liquidus before placing plugged bubblers

back ito service. Indicate condition of bubblers:

 

 

 

1.3.7 Set FIC 516 to maximum flow (~5 1/m).

 

1.4 In preparation for running the fuel pump to aid
in mixing the purge gas, check the following:
(Control Room)
1.4.1 0il level on LI-OT-1>50%
PIC 513 set for 7T psig
F.0 PNo. running
Shield oil flow 8 gpm on FI TOL s
Seal oil flow of L4 gpm on FI 703
(Water Room)
1.4.2 Motor cooling water 5 gpm on FI 830

 

 

(Control Room)
1.4,3 Start fuel pump.

 

1.5 Determine the required purge time required

before heat up is begun as follows:
3

 

A-L
8/3/65

Init. Date & Time

 

1.5.1 Determine total helium flow being intro-

duced into the fuel system. Refer to calibration

curves availsble to convert indicator readings

to l/min.
(Transmitter Room)
FI 592  psig= ____ 1/m,
FI 596  psig=__ 1/m,
FI 593 psig=__ _ 1/m,
FI 600 psig = __ 1/m,
FI 599 _____ psig = ___1/m,
FI 589 psig = ____ 1/m,
(Main Beard)
FI 516 % = 1/m,
Total Flow ___ 1/m.

 

1.5.2 Determine time required to purge 7 system

volumes at the flow established in step 1.5.1 by:

75 ft3/vol x Tvol 248
Flow l/m X Eggg Flow 1/m

 

Time (hrs) =

Purging helium at the rate in 1.5.1 while mixing
with the fuel pump, for the time sbowe should

reduce oxygen contemination to < 500 ppm.

hrs.

 

1.6 After purging for the length of time determined
above (approx 30 hrs), reduce the purge to normal

flow rate (see secticn 5.I1.2.8 and 5.1.2.9).

 

1.7 Continue the normal purge rate (total approx
.2 1/m) during reactor startup to further
reduce oxygen concentration in the gas to below
10C ppm which would represent < 1 ppm oxide in
8,800 1bs of salt.

 

2  PURGING THE FUEL DRAIN TANKS

 

Purging of a fuel system drain tank after it has been
opened to atmosphere for any reason consists of alter-

nately pressurizing and venting of helium. Pressure
DA-5
8/3/65
Init. Date & Time

Approved by

 

 

changes of 5 psi will be made by alternately pressurizing
to T psig and venting to 2 psig. To reduce the oxygen
concentration from atmospheric to < 500 ppm before heat
up is begun will require 24 cycles. An additional 6
cycles will be performed during heat up to lower oxygen
concentration to < 100 ppm. Each pressure cycle will
regquire in excess of an hour due to flow limitations

of FE 517. The theoretical number of AP cycles to

reduce oxygen concentration to any desired value may be

determined by:

 

1n Lo
C
N =
P
2
lnfi—
1
where N = number of pressure cycles purge gas required
Co = beginning concentration O2 in ppm
C = desired or end concentration O2 in ppm
Pl = end vent cycle pressure, psia
Pé = end pressure cycle, psia.

2.1 Check that the cover gas system is in operation.
2.2 Check that the drain tank, associated fill and

 

transfer piping, and freeze valves, to be purged
are at room temperature (Mark through tank(s)

not to be purged).

 

 

 

 

FDL FD2 FPT
Line 109 Line 108 Line 107
FV 109 : FV 108 : FV 107 :
Line 106 | Line 105 | vine 104 -
FV 106 ___ |® 105 | Fv 10k

 

 

 

 

 

 

(Control Room)
2.3 Close the bypass valve(s).
HCV 5kl HCV 545 HCV 546

 

 

 

 

|
|

 

2.4 Close the vent valve(s).
HCV 573 HCV 575 HCV 577

 

 

 

 

 

 

 
 

2

2

no

™

¢ 1)

Init.

5A-6
8/3/65
Date & Time

 

.5 Set PIC 517 to 8 psig. DNote that fuel system

pressure must be < 2 psig for this valve to open.

 

.6 Open tark supply valve by checking that:

5.6.1 Receiver selector S-4 in FST position

 

0.6.2 FV 111, ¥V 107, FV 108, ¥V 109 are

frozen

 

2.6.3 Two jumpers placed in circuit 115

 

Permission to insert jumpers
2.6.4 Request open valve:

rficv 572 JHCV 5Th JHCV 576

 

 

 

 

.7 Completzs pressure-vent cycles of T psig to 2 psig
ags follows:
2.7.1 When pressure in tenk reaches 7 psig, close

supply valve and open vent valve.

 

 

Open HCV 573 | Open HCV 575 | Open HCV 577

Close HCV 572 | Close HCV 5Th Close HCV 576

 

 

 

 

 

2.7.2 When pressure in tank reaches 2 psig, close

vent valve and open supply valve:

 

 

Open HCV 572 | Open HCV 574 | Open HOV 576

 

 

 

Close HCV 573 | Close ICV 575 Close HCV 577 _

 

 

.8 FRepeat sbove cycle {(step 7) 2L times before heat

up is tegun. Record data in Table HA-1.

 

.9 Continue above during reactor atartup (Sections
5A and 5B). There should be a total of at least
30 cycles. Record data in table 5A-2.

 

.10 Remove Jjumpers in circuif 115

 
* ~ '
- 8/3/65

TABLE 5A-1 DRAIN TANK PURGE CYCLES BEFORE HEATUP

 

Pressure Cycle, Step 2.7.1 Vent Cycle, Step 2.7.2

 

Date and Time Max. Pressure Date and Time Min. Pressure

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
 

  

 

 

J»:. g
Approved bYfif :) AL £ oA~
8/3/65
TABLE 5A-2 DRAIN TANK PURGE CYCLES DURING HEATUP
Pressure Cycle Step 2.7.1 Vent Cycle Step 2.7.2
Date and Time { Max. Pressure | Ave. Temp. | Date and Time | Min. Pressure | Ave. Temp.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
£

Approved by?ZZfiffi%fééE%;fx%%vwl 5A-9

3

8/3/65
PURGING OF THE COOLANT PTPING AND DRAIN TANK

~ Purging of the coolant piping system and coolant drain

tank will consist of evacuation of 0.5 psia or less

and refilling with helium. Provisions will be made

for the prevention of beryllium contamination from

the vacuum system.

If the coolant system or coolant drain tank system

are to be purged separately, the applicable portions

of this procedure will be used.

3.1 Check that the entire coolant system, coolant Init. Date & Time
'drain.lines, FV 204 and FV 206 are at room

 

temperature.
3.2 Check that the drain tank (CDT) is:
emptied of salt and cold

 

o ————

or, full of frozen salt

C—C—————r—

 

(Vent House)

3.3 Install a vacuum pump at V 560A. The vacuum
pump is to be either fitted with an absolute
filter on the exhaust or connected to building
exhaust. Tag the pump as being beryllium
contaminated. Include a vacuum gauge to

indicate system pressure.

 

(Control Room)

3.4 Turn the CP bubbler selector $-39 to "off."
(This closes HCV 595 BL, B2, B3 and opens
HCV 595 B4 and B5.)

3.5 Close or check closed the following valves:

e vt

 

(Coolant Drain Cell)

V 511A , vV 770 ,
VvV 512 5 V 529 ’

(Transmitter Room)

V 59ka ; V 595A s V 598A s

(High Bay)

Coolant sampler valve HCV 998

 
 

Init.

5A-10
8/3/65

Date & Time

 

(Special Equipment Room)
3.6 Check that line 203 is blanked.

 

3.7 Open the following valves:
(Coolant Drain Cell)

V511B V526

(Control Room)
HOV 511A  , FIC 512 _ , HOV 527 __
HCV 511B  , Pcvse8  , HOV 536
HCV 547 .

 

(Vent House)
3.8 C(Close V 560B

 

(Vent House)
3.9 Turn on vacuum pump and throttle open V 5604
according to capacity of the pump. As pressure

drops, open valve completely.

 

3.10 Evacuate the system to ~0.5 psia and hold for
4 hours. Record time L-hour period

started ) stopped

 

(Diesel House)
3.11 Check or install a temporary line from V 500C
to V 597B to bypass FCV 500 if fast purge is

desired.

 

3.12 Start coolant pump, cover gas purge and coolant
drain tanks, purge as follows:
(Coolant Drain Cell)

3.12.1 Open V 512 and V 511 A

 

(Control Room)
3.12.2 Set FIC 512 to 0.6 1/m.

 

3.12.3 Throttle HCV 511B open slightly (there
is no flow indicator on this line) so that

there is a small purge through the drain tank.

 

3.13 Purge for two hours, then close V 560A

and stop vacuum pump

 

 
-

«fl"'(‘ ;
Approved bwgfiazsz 855%31
% 3/65

Init. Date & Time

 

3.14 Continue purge during remainder of reactor startup.

3-15

Remove bypass around FCV 500 . Open V 560B

when system reaches atmospheric pressure

 

Remove vacuum pump from vent house. Handle as
if it were beryllium contaminated equipment
until it has been cleared by Industrial Hygiene.
Drain the oil and have a sample analyzed for
beryllium content. Flush out the pump with
clean oil. Dispose of all used oll in approved
beryllium containers marked for burial.

0il sample contains ug/cc beryllium.

 
”g? * NPV 5B-1
T/26/65

Approved by Ji
L

5B STARTUP OF COVER GAS AND OFFGAS SYSTEMS

 

The cover and offgas systems may remasin essentially in full operation
during shutdown periods. However, they are important enough that at
each startup all valves, equipment, and instrumentation will be checked.
The following detailed procedure is designed to provide a supply to all
necessary locations and put each system in a standby condition.
NOTE: Position of valves marked "*" may depend upon conditions of the
system. If possible, set these as indicated. If not, shift super-
visor should approve deviation.

Tnit. Date/Time

 

1. Put two sections of the main charcoal beds on
stream. Shift supervisor should decide which two
are to be used.

1.1 Open two of the following pairs of valves and
close the other two pairs. Tag all eight
valves and note their position.

(Vent House)

V-620 and 624
V-621 and 625
V-622 and 626
V-623 and 627

 

1.2 Set the following valves as shown:

V-522A tag open V-518C2 tag closed
V-522B tag open V-518C3 tag closed
V-518A tag closed V-518D tag closed
V-518G tag open V-518E tag closed

V-518Bl tag closed __ V-518F tag closed

V-518B2 tag closed _  V-55TA tag closed

V-518B3 tag closed ___ V-55T7B tag open

V-518C1 tag closed V-537 tag closed

V-524B tag closed V-538A and B tag closed

V-566A and D tag closed

 
Approved b A*h’11,

2 Put the auxiliary charcoal bed on stream by setting

hand valves as follows:
V-561A Tag open
V-571A Tag closed
V-571B Tag closed
V-562A Tag open
V-562B Tag closed
V-562C Tag open

3 Set up valves for the coolant system and oil

systems as follows:
V-560A Tag closed
V-560B Tag open
(Service Tunnel)
V-534A Tag open
V-534B Tag open
V-535A Tag open
V-535B Tag open
*#V-513A Closed

5B-2
7/26/65
Date/Time

 

 

V-513B
*V-510A
V-510B

NOTE: The setting of all evacuation valves in line

Tag open
Closed
Tag open

565 are covered in Section L4E.

b Check to see that the offgas monitor RIA-557 and

stack monitor RIA-S-1 are in service.

5 Set the fuel drain tank valving as follows:

 

 

(WESA)
V-519A Closed
*¥HCV-5T73 Closed
(Main Control Room)
*¥HCV-5T75 elosed
*¥HCV-577 closed
"HCV-54l closed

e —
 

5 (continued)
*HCV 545 closed
*HCV-546 closed
*HCV-5T72 closed
¥HCV-5T4 closed
*¥HCV-5T6 closed
*HCV-533 closed

Init.

5B-3
7/26/65

Date/Time

 

V-572, 574, and 576 are opened on containment

NOTE :
check list,
6 Set fuel system valves as follows:

*FCV-516 closed
PCV-522 closed
(Special Equipment Room)
V-524A tag open
V-500J tag open

V-554 tag closed and cap line

(Transmitter Room)

 

*V-592A closed V-589B open

V-592B open V-599A closed
*¥V-593A closed V-599B open

V-593B open V-600A closed
¥V-596A closed V-600B open

V-596B open V-501 tag open

V-580A closed

NOTE: V-516, V-592C, 593C, 596C, 589C, 599C, 600C,

and 519B are opened on containment check list.
V-523 is in the reactor cell and should be opened
before cell is sealed.

T Set coolant system valves as follows:

*¥V-594A closed

V-594B
*V-595A
V-595B
*7-598A
V-598B

open
closed
open

closed

open

 
Approved by MW 5B-L
| 7/26/65

T (continued) Tnit. Date/Time
(Coolant Cell)
V-594C tag open
V-595C tag open
V-598C tag open
V=512 tag open
V-511A tag open
V-511B tag open
(Main Control Room)
¥HCV-511A closed
*¥FCV-512 closed
¥HCV-527 closed
*HCV-536 closed
¥HCV-547 closed

 

8 Valves to fuel sampler enricher should be set as
follows:
(High Bay)
V-509 tag open V-650 closed
*¥V-672 closed V-6L5 closed
*¥V-664 closed V-6L46 closed
*¥V-666 closed V-655 open
V-671 closed V-668 open
*¥V-657 closed V-670 open
*¥V-683 closed V-669 open

v-64L closed

 

9 Set valves to coolant system sampler as follows:
V-515 open and tagged
VC-650 closed
VC-651 closed
VC-670 closed

 
Approved by 5B-5
T/26/65
Init. Date/Time
10 Set chemical processing valves as follows:
V-530 open
PCV-530 set at 20 psig
*¥V-611 closed
*V-607A closed
*¥V-607C closed
*V-608A closed
¥V-610A closed
V-603A closed
(Main Control Room)
HCV-530 closed
*HCV-692 closed

 

11  Valves in supply to leak-detector system are set
as follows:
(Diesel House)
V-51L4A tag open
(Transmitter Room)
V-514B tag open
*¥V-514C closed
PCV-51L set at 100 psig

 

12 Connect helium trailer ta line 500.%

Open all valves on trailer,

 

13 Set valves in helium supply headers as follows:
V-FHS open
V-5004A open
V-500D open
V-500E tag open
*V-500F closed
*¥V-59TA closed
V-597B tag closed
*¥V-549 open
*¥V-605A closed
V-500 N-1 closed

 

lgelium Trailer license number - USN 120761
 

Approved b weer) 5B-6
7/26/65
Tnit. Date/Time
13  (continued)

1h

15

16

17

V-500 N-2 closed
V-500 N-3 closed

 

Check to see that helium dryer and oxygen removal
unit No. 2 are ready to operate but valved off and
in standby.

V-500B open

V-504 tag closed

V-503A tag open

V-503B tag closed

V-503C tag closed

TIC-DR2-1 set at zero

TIC-PH2-1 set at 800°F

TIC-0sR2-1 set at 800°F

 

Put helium dryer and oxygen removal unit No. 1
in service.
15.1 Set valves as follows:

V-500C tag closed

V-500D tag open

V-505A tag closed

V-505B closed

 

15.2 Set heater controllers as follows:
TIC-DR1~-1 set at zero
TIC-PHL-1 set at 800°F
TIC-0zR1-1 set at 1200°F

 

15.3 Periodically open V-549 to vent pressure.

 

Check to see that all emergency cylinders are
connected to headers and headers are above 1500 psig.

Tag closed V-502A and V-502B.

 

Check to see that the pressure in the normal
helium supply header is above 500 psig and is in

service (PI-500F).

 
Approved byfifffg%éggéf“%fl“\ 5B-7
7/26/65

18
19

20

21

22
23

2k

25
26

Tnit. Date/Time
Set PCV-500G at 250 psig (PI-SO0H).

 

cet FIC-500 at 0.35 c¢fm., This will limit the
helium flow to the capacity of the dryer and

O2 removal units.

 

Continue to purge through line 549 until the
moisture content is less than 1 ppm Oz and

6 ppm H20. Set flow to oxygen and Ho0O analyzers
at 100 cc/min.

 

When the No. 1 dryer and Oz removal units are
functioning satisfactorily, set up remaining
valves as follows:

V-59T7TA tag open

V-605A open

V-605B open

V-500F closed

V-500H tag open

 

Set PCV-605 at 35 psig.

 

Tf PCV-605 does not function properly, have it

repaired and recheck operation.

 

When PCV-605 does function properly, set valves
as follows:

V-605A tag closed N

V-605B tag closed

V-500F tag open

V-500G tag open

 

Set PCV-500C at 35 peig.

 

Check to see that RIA-500D is in service.

 
Approved by %flm 5C-1
9/7/65
5¢  HEATUP OF DRAIN TANK SYSTEM

This section covers the heatup of ¥FD-1, FD-2, FFT, and asscciated
lines. In general, whenever a tank is heated, the lines will be heated
and kept hot from this drain tank to the first freeze valves. From this
point the lines can be heated or cooled depending on the operation in
progress. Heatup of lines necessary for salt addition will be covered in
5D; heatup of the fuel and coolant systems and the £ill lines will be
covered in 5F, and heatup of the transfer lines and fuel storage tank
will be covered in 11A.

In this procedure, the details of the heatup of each tank are listed
separately; however, all can be heated simultaneously if desired. When
possible the TE's on lines and vessels which are being heated should be
monitored continuocusly. Equipment previously heated should be monitored
at least ftwice per shift tec prevent overheating or freezing.

In normal operation FD-1, FD-2, FFT and CDT will be maintained at
1100 to 1200°F. The FST may be cooled if desired. The transfer freeze
valves and other pockets of salt located in a high gamma field shall be
maintained at 4OO°F to 600°F to prevent the excessive evolution of Ffluorine.
The empty lines may be cocled to ambient temperature.

It is assumed that the tanks and lines being heated may contain salt.
To prevent rupture due to the expansion of the salt as it is heated, the
tank will be heated first followed by the section of pipe next to the tank
and continued in this order until the line is heated to the freeze valve.
The maximum permissible heatup or cooldown rate is 100°F per hour.

1 HEATUP OF FD-1 AND ADJACENT LINES
This section covers the heatup of FD-1, line 106 to FV-106, and
line 109 from FD-1 to the surge pot nearest FD-1.
Init. Date/Time
1.1 Check that the following FV's are switched to
freeze and that temperatures indicate that

they are frozen.

 

Fv-104 _ FV-107 __  FV-110 _
FV-105  FV-108 _ FV-111 _
FV-106

FV-109 -
Approved by _zfiff?ngg%;cbarn

1.2

1.3

1.4

1.5

1.6

1.7

Init.

Unplug the thermocouples listed in Table 5C-1
and plug them into the special recorders so
the heatup may be clesely followed. TFinish
filling out Table 5C-1. Swing link the
scanner ''C" points which are removed and plug
different thermocouples into the recorders

in place of the ones put on the special re-
corders. Keep the thermocouple tabulations

up to date.

5¢-2
9/7/65
Date/Time

 

Close the following valves.

HCV-5Lk HCV-5T72

Depending upon operation, it is possibile
that jumpers may be needed in circuits 20
and 21 in order to close HCV-5L4L. Approval

to ingert jumpers

 

 

As the tank heats up, keep a careful watch
on PR-5T72B to prevent overpressurizing the
tank. Periodically vent through HCV-573

when necessary to keep the pressure between

3 and 7 psig.

 

If they are not on, push the "start'" button
on the following induction regulator blowers.
G5BB-2 T1B-1

 

If FD-1 is already hot, start heating up

lines 106 and 109 by turning onh H-106-1 and
H-109-1 to give a heatup rate of 100°F/hr on
TE-106-~1 and TE-109-1 then skip to step 1.8.
If the tank is cold, turn on heaters FD1-1 and
FD1-2 to T5% of their 1200°F current setting

(amperage) and continue with step 1.7.

 

The tank temperature should be followed
primarily by watching the points listed in
Table 5C-1. Additional tank temperatures are

indicated on scanner '"C". When the tank
 

1.7

1.8

1.9

1.11

5C-3
9/7/65

Tnit. Date/Time

 

 

(continued)

temperature is approximately 4OO°F, turn on
H-106~1 and H~109-1 to 50% of their 1200°F
current setting. After they are turned on,
make any adjustment necessary to keep the
pipes under these heaters lagging the tank
by ~ 200°F until the thawing temperature is
exceeded (850°F). H-FD1-1 and H-FD1-2 should
be increased to their 1200°F setting when
the tank gets to 600°F or whenever the heat-

up rate starts leveling off.

 

When TE-106-1 reaches 4O0°F, start filling
out Table 5C-L4 and turn on heater H-106-2.
Keep TE-106-2 about 200°F less than TE-106-1.
Algo set H-FD1-1 and H-FD1-2 to their 1200°F

settings.

 

When TE-109-1 reaches 400°F, turn on heaters
H-109-2 and H-109-3. Due to the heater
arrangement on line 109, it will be impos-
sible to heat it up in a step-wise manner.
Keep all of the thermocouples under heaters
H-109-2 and H-109-3 as close together as
possible and lagging TE-109-1 about 200°F.

 

Continue the procedure of turning on successive
heaters on line 106 out to the freeze valve.
The last heater turned on should be H-FV-106-3,
Keep the temperature under each successive
heater about 200°F lower than the adjacent
heater to it on the tank side until 850°F

is exceeded.

 

ILevel the temperatures out between 1100°F
and 1200°F.

 
Approved byé? _3_ fié @M 5C-4

9/7/6
Tnit. Date/Time

 

1.12 After the lines are heated, place the thermo-
couples listed in Table 5C-1 back on their
normal readouts. Keep the thermccouple logs

up to date.

 

1.13 If jumpers were inserted in step 1.3,

remove them,

 

2 HEATUP OF FD-2 AND ADJACENT LINES
This section covers the heatup cf FD-2,
line 105 to FV-105, and line 108 from FD-2 to the
surge pot nearest ¥D-Z.
2.1 Check that the following FV's are switched
to freeze and that temperatures Indicate that

they are frozen.

Fy-104 Fy-108
FV-105 FY-109
FV-106 Fy-110
FV-107 _ FY-111

 

2.2 Unplug the thermocouples listed in Table
5C-2 and plug them into the special recorders
80 the heatup may be closely followed. Finish
filling out Table 5C-2. Swing link the
scanner "C" points which are removed and
plug different thermoccuples into the recorders
in place of the ones put on the special
recorders. Keep the thermocouple tabulations

up te date.

 

2.3 Close the following valves.
HCV-545 HOV-5Tk
Depending upon operation, it is possible
that jumpers may be needed in cilrcuits 20 and
21 in order to open HCV-545. Approval to

insert jumpers

 

 
Approved byfi%w .
9/7/65

2.4

2.5

2.6

2.7

2.8

Init. Date/Time

 

As the tank heats up, keep a careful watch
on PR-5T4B to prevent overpressurizing the
tank. Periodically vent through HCV-575
when necegsary to keep the pressure be-

tween 3 and 7 psig.

 

If not already on, push the "start" button
on following induction regulator blowers.
G5BB-2 T1B-1

 

If FD-2 is already hot, start heating up
lines 105 and 108 by turning on H-105-1 and
H-108-1 to give a heat-up rate of 100°F/hr on
TE-105-1 and TE-108-1 then skip to step 2.8.
If the tank is cold, turn on heaters FD2-1
and FD2-2 to 75% of their 1200°F current

setting (amperage) and continue with step

2.7.

 

The tank temperature should be followed
primarily by watching the points listed in
Table 5C-2. Additional tank temperatures
are indicated on scanner "C”. When the tank
temperature is approximately LOO°F, turn on
H-105-1 and H~108-1 to 50% of their 1200°F
current setting. After they are turned on,
make any adjustment necessary to keep the
pipes under these heaters lagging the tank
by ~ 200°F until the thawing temperature is
exceeded (850°F). H-FDe-1 and H-FDe-2 should
be increased to their 1200°F setting when

the tank gets to 600°F or when the heat-up

 

rate starts leveling off.

When TE-105-1 reaches L400°F, start filling
out Table 5C-5 and turn on heater H-105-2.
Keep TE-105-2 about 200°F less than TE-105-1.
Also set H-FD2-1 and H-FD2-2 to their 1200°F

settings.

 
Approved b;4aéf£5232%%z;g@¢a

Init.

5C-6
9/7/65

Da.te/Time

 

2.9 When TE-108-1 reaches LOO°F, turn on heaters
H-108-2 and H-108-3. Due to the heater
arrangement on line 108, it will be impossi-
ble to heat it up in a stepwise manner. Keep
all of the thermocouples under heaters E-108-2
and H-108-3 as close together as possible and

lagging TE-108-1 about 200°F.

 

2.10 Continue the procedure of turning on successive
heaters on line 105 out to the freeze valve,
The last heater turned on should be H-FV-105-3.
Keep the temperature under each succegsive
heater about 200°F lower than the adjacent
heater to it on the tank side until 850°F

is exceeded.

 

2,11 Level all temperatures out between 1100°F
and 1200°F.

 

2.12 After the lines are heated, place the thermo-
couples listed in Table 5C-2 back on their
normal readouts. Keep the thermocouple

logs up to date.

 

2.13 If jumpers were inserted in step 2.3, remove
them.

 

3 HEATUP OF FFT AND ADJACENT LINES
This section covers the heatup of FFT,

line 104 to FV-10L, and line 107 from FFT to the

 

surge pot nearest FFT.
3.1 Check that the following FV's are switched
to freeze and that temperatures indicate that

they are frozen.

FV-10L FV-108
FV-105 FV-109
FV-106 FV-110

Fv~-107 Fv-111

 
Approved byfi{%izm 5C-1
9/7/65

3.2

3.3

3.h

3.5

3.6

3.7

Init. Date/Time

 

Unplug the thermocouples listed in Table

oC-3 and plug them into the special recorders
sc the heatup may be closely followed. Finish
filling out Table 5C-3. Swing link the
scanner "C" points which are removed and plug
different thermocouples into the recorders

in place of the ones put on the special re-
corders. Keep the thermocouple tabulations

up to date.

 

Close the following valves.

HCV-546 HCV-576
Depending upon operation, it is possible
that jumpers may be needed in circuits 20
and 21 in order to open HCV-546. Approval

to insert jumpers

 

 

As the tank heats up, keep a careful watch
on PR-5T6B to prevent overpressurizing the
tank. Periodically vent through HCV-577

when necessary to keep the pressure between

3 and T psig.

 

If not already on, push the "start'" button
on the following induction regulator blowers.

G5BB-2 T1B-1

 

If FFT is already hot, start heating up line
10k by turning on H-104-1 and H-107-1 to give
a heat-up rate of 100°F/hr on TE-104-1 and
TE-107-1 then skip to step 3.7. If the tank
is cold, turn on heaters FFT-1 and FFT-2 to
T5% of their 1200°F current setting (amperage)

and continue with step 3.7.

 

The tank temperature should be followed
primarily by watching the points listed in
Table 5C-3. Additional tank temperatures

are indicated on scanner "C". When the tank
 

Approved by/fifii?eaé$§%yflfl%9n

3.7

3.8

3.9

3.10

3.11

Init.

(continued)

temperature is approximately L4O0°F, turn on
H-106-1 and H-109-1 to 50% of their 120C°F
current setting. After they are turned on,
make any adjustment necessary to keep the
pipes under these heaters lagging the tank by
~ 200°F until the thawing temperature is
exceeded (850°F). H-FFT-1 and H-FFT-2 should
be increased to their 120C°F settings when
the tank gets to 600°F or when the heatup

rate starts leveling off.

5C-8
9/7/65

Date/Time

 

When TE-104-1 reaches LOO°F, start filling
out Table 5C-6 and turn on heater H~-104-2,
Keep TE-10L-2 about 200°F less than TE-104-1.
Also set H-FFT-1 and H-FFT-2 to their 1200°F
settings if the tank is not already hot.

 

When TE-107-1 reaches LOO°F, turn on heaters
H-107-2 and H-107-3. Due to the heater
arrangement on line 107, it will be impossible
to heat it up in a stepwise manner. Keep

all of the thermccouples under heaters

H-107-2 and H-107-3 as close together as
possible and lagging TE-107-1 about 200°F.

 

Continue the procedure of turning on
successive heaters on line 107 out to the
freeze valve. The last heater turned on
should be H-FV-107-3. Keep the temperature
under each successive heater about 200°F
lower than the adjacent heater to it on the

tank side until 850°F is exceeded.

 

Level off all temperatures between 1100°F
and 12C0°F,

 
Approved bym/ %/WV\ 5C-5

9/7/65

 

Init. Date/Time

3.12 After the lines are heated, place the thermo-

couples listed in Table 5C-3 back on their
normal readouts. Keep the thermocouple

logs up to date.

 

3.13 If jumpers were inserted in step 3.3,

remove them.

 

L HEATUP OF CDT

line

L.1

h.2

b3

L.L

h.5

This section covers the heatup of CDT and
204 to the shoulders of FV-204 and FV-206.
Check that freeze valves 204 and 206 are
switched to freeze and that temperatures

indicate that they are frozen.

 

Unplug the thermocouples listed in Table

5C-7 and plug them into a special recorder so
the heatup may be closely followed. Finish
filling out Table 5C-7. OSwing link the scan-
ner "C" points which are removed. Keep both

thermocouple logs up to date.

 

Close the following wvalves.

HCV-511 HCV-547
Depending upon operation, it is possible
that jumpers may be needed in circuits 140

and 141 in order to close HCV-54T7. Approval

 

to insert jumpers .

As the tank heats up, keep a careful watch
on PR-511D to prevent overpressurizing the
tank. Periodically vent through HCV-527

when necessary to keep the pressure between

3 and T psig.

 

If the CDT is already hot, start heating up
line 20k by turning on H-204-2 to give a
heat-up rate of ~ 100°F/hr on TE-204-8A and
TE-204-B7A then skip to step 4.7. If the tank
Approved by%f?z%%%éiézfi¢flvL

L.5 (continued)
is cold and empty, turn on heaters CDT-1,

2, and 3 to 75% of their 1200°F current
setting and continue with step L4.6.

4.6 The tank heat-up may be followed by watching
the points listed in Table 5C-T7. Additional
tank temperatures may be observed on scanner
"C". When the tank temperature is approxi-
mately LOO°F, turn on H-204-2. Keep the line
temperature less than the tank temperature.

4.7 When the temperature under heater 204-2
reaches ~ LOO°F, turn on heater FV-204-3.
Keep the temperature of the freeze valve pot
about 200°F less than the temperatures under
H-204-2 until the pot exceeds 850°F.

L.8 The coclant drain tank heaters should be
set to their 1200°F settings when the coolant
drain tank heat-up rate begins to level off.

4.9 Turn on H-FV-204-2 when TE-FV-204-5B reaches
LOO°F. Keep TE-FV-20L-5B at least 200°F
above TE-206-7 until TE-206-7 exceeds 850°F.

4.10 Make adjustments necessary to level the
temperatures out at 1200°F. However, do
not exceed the 1200°F setting on H-FV-204-2.
Since this heater is next to a section of
frozen salt, it may not reach 1200°F until
the freeze valve heaters are turned on.

%¥,11 If jumpers were inserted in step 4.3, re-
move them.

L.12 After the tank and lines are heated, place
the thermoccouples listed in Table 5C-7 back
to their normal readout., Keep the thermo-

couple logs up to date.

5C-t0
9/7/65
Tnit. Date/Time

 

 

 

 

 

 

 

 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Approved byrfl/yag/w\ 511
< 9/7/65
TABLE 5C-1
HEATUP OF FD-1, LINE 106 to FV-106
and
LINE 109 to FV-109
NORMAL, TEMPORARY
READOUT READCIT
TE No. Heater No. Readout Pt. Recorder Peoint
FD1-1B rpl-2 Scanner "g" 1
FD1-3B FDI-1 " 14
FD1-5 FDL-1 " 13
FD1-6 FD1-2 " 3
FD1-9 FDl-2 " 6
FD1-18B FD1-1 & FD1-2 None None
106-1 106-1 Scanner "C" 15
106-2 106-2 " 16
106-3 106-3 " 17
106-4 FV-106-3 " 18
FV-106-5B FV-106-3 TR-3300 oh
109-1 109-1 Scanner "C" 20
109-2 109-2 " o1
109-3 109-2 " 2P
109-4 109-3 " 23
109-FL 109-3 " ol
109-5 109-3 " 25
109-6 109-2 " 26

 

 

 

 

 

 
Approved by@m\ 9?0 -fég
/05

TABLE 5C-2
HEATUP OF FD-2, LINE 105 TO FV-105
and.

LINE 108 to FV-108

 
 
 
  
   
 
       
  
 
 
 

 

   
  
 

 

    
  

    

    

   

NORMAT, TEMPORARY
READOUT T
TE No. Heater No. Readout Pt. Recorder Point

          
       
      

   

Lo
41
1
L

FD2-1 Scanner ''C"
FD2-1
Fie-2
De-2
PD2-1 & FD2-2
105-1
105=-2
10
105-4

FD2-
FD2-
FD2-6
FD2-
FD2-183
105-1
f105-2
105-

 

     

  

   

   

    
    

 

 

None

      
 

  

 

   

     
 

Scanner "C"

 

       
     
      

  

 

  
 

 

    
9/7/65

TABIE 5C-3
HEATUP OF FFT, LINE 104 to FV-10k
and
LINE 107 to FV-107

 

NORMAT, TEMPORARY
! READOUT READOUT
Heater No. ' eadou . Recorder Point

 

FET-1 Scanner '"C"
-l FFT-1
6 FET-2
FFT- FFT-2
11 f FFT-1
104-1 | 104-1
oh-2 104-2
104- 104-
104-Ak 104-4
104-B4 FV-104-
FV-104-58 | FV-104- TR-3300
107-1 107-1 Scanner "C"
107-2 s 107-2
107- 107-
107-FL | 107-
107-14 . 107-
107- : 107-2

 
 

 

 

Approved by%m__ 5C-1;
9/7/65
TABLE 5C-L
RECORD THE FOLIOWING THERMOCOUPIES TEMPERATURES
WHEN TE-106-1 IS AT THESE TEMPERATURES
TE-106-1 ‘ LoO°F 600°F B800°F 1000°F 1200°F

TRE-106-2

TR-106-
TE-106-14
TE-FV-106-5B8

 

TABLE 5C-5
RECORD THE FOLIOWING THERMOCOUPLE
TEMPERATURES WHEN TE-105-1 IS AT THE INDICATED TEMPERATURES

 

TE-105-1 LOO°F 600°F 800°F 1000°F 1200°F

 

TE-105-2
TE-105-3
TE-105-4
TE-105-5 é
TE-FV-105-58 |

 

 

 

 

 

 

 

 

 

 

 

TABLE 5C-6
RECORD THE FOLIOWING THERMOCOUPLE TEMPERATURES
WHEN TE-104-1 IS AT THE INDICATED TEMPERATURES

TE-104-1 LOOC°F 600°F 800°F 1000°F

TE-104-2
TE-104-
TE-104-Ak
TE-104-BL
TE-FV-104-5F

 
 

toprovea vy LI B anaon o
’ 9/7/65

TABLE 5C-T7
HEATUP OF CDT AND LINE 204 to FV-20L4 and 206

  
  

   
   
     
   
     
    
  

 
    
 

NORMAT,
READOUT
Readout

TEMPORARY
READOST
Recorder

    
 

      

TE No. Heater No. Point

 

 
 
 
 
 
 
 
  
 

  

204 -2 Scanner "C"
CDT-1
CDT-
CDT-2
CDT-1
204-2
204-2
FV-204-
FV-204-
FV-204-2

CDI-1
CDT-4
CDT-
CDT-6
CDT-2B
204-8A
204 -BTA
20h-ATA
FV-204-5B
206-T

 

 

1t

 

        

     

None

 
  

B

      

      
 

Scanner 'C"

    
  

      
     
  
    
     

    

 

    
  
 
- Approved by 5D-1

7/29/65

  

 

5D ADDITION OF FUEL,‘FLUSH'AND COOLANT SALT
TO THE DRATN TANKS

 

 

NOTE: If no salt is to be added, section 5D can be ommitted.

Fuel, flush, and coolant salt will be prepared by the Reactor Chemistry Division
and will be stored as a solid under a helium blanket until it is charged to the system,
Nonuranium salt will be handled in cans holding 250 to 300 1lb each. Uranium will be
charged as the UF
50 1b.

Two portable furnaces and control units furnished by the Reactor Chemistry Divi-

4'Lin eutectic (27 mole % UFu) from smaller cans containing 30 to

sion will be used for heating the salt. Each can will be weighed, heated, pressur-
ized to the system, cooled and reweighed.

Fuel or flush salt can be charged directly to the fuel drain tanks, fuel flush
tank, or to the fuel storage tank from the charging station in the high bay. Charg-
ing after criticality will be done via the fuel storage tank to provide an additional
freeze valve between the reactor and the charging station. The charging line will be
blanked off at the 852-ft elevation when not in use. To minimize intermixing of
different salts, lines to all other tanks will be prefilled before addition and will
be emptied afterward. Special instructions will be issued when needed. .

Coolant salt will be charged directiy to the coolant drain tank from the coolant
salt charging station, located above the special equipment room. The same furnaces
and control units used for charging fuel will be used for the coolant salt. The
charge line will be blanked off at the coolant drain tank when not in use.

Details of both charging operations follow,

Fuel and Flush Salt Charging (Fig, 5D~1)

 

(Note: This procedure assumes that the freeze valves have been filled with
salt and oxygen has been purged from the system.)

1,1 Set up two portable furnaces and control units Init. Date and Time

 

at the fuel-charging station,

 

1.2 Check that receiving tanks, transfer lines, salt
addition lines and purge line 610, are heated

above 1000°F (Section 5C, 11Al and 11Al5).

 

1.3 Prefill salt lines as required. (Special

instructions will be issued.)

 

l.4 Place a weighed salt can in each furnace. Check
that all openings on the can are plugged when

recelved,

 

1.5 Connect helium jumpers between the control unit

(Al and A2) and a vent connection on the top of

TX-3554
(7-64)
   

A
Approved by/,;?r-’f"'f' NS 1 o 5D-2
7/29/65

FIG. 5D-1 SALT ADDITION STATION

HELIUM SUPPLY

Voll

D * D,
: !

i
Q—#PCV 612

PCV 6l
)

A, XvelB  XVENA

—
V6138 VOI3A

JI
C
VAC
- g (BK 5
& @ G2

|

|

l

|

l

 

 

A, vel2B Velz2 A
— Jz
V6148 Vei4 Al VENT

 

 

 

 

 

 

 

 

T

 

 

51~|- F B2 -!—H .l.

A

 

 

 

 

 

 

TO TANK
Approved byfiéézzyifazguyzf 5D~3
___.,_7 - { -

1.6

1.7
1.8
1.9
1.10
1.11

1.12

1.13
1.14

7/29/65

each can (Bl and B2). These jumpers should con- Init. Date and Time

 

tain an electric insulating section so that the

salt can is not grounded through control units

 

Connect a KOH bubbler and a back siphon relief

trap to the control unit as shown at C.

 

Close HV 611A, 611B, 613A, 612A, 612B and 61uA.

 

Open HV 613B and 614B.

 

Connect helium supply to control unit at D1 and D2.

 

Open V 611 and set PCV 611 and 612 at 8 psig.

 

Set furnace temperature controllers at 1300°F,
and heat up the salt. ({Temperature controllers
and thermoccuples are integral parts of the

charging unit.)

 

Attach a Y-in, dia. flexible hose to V 978 in

the absorber cubicle for use as a portable vent.
Turn on the adsorber blower at the fuel processing
control panel., Always have the suction of this
hose near any salt containing lines which are

open.

 

Check that FV 111 is frozen,

 

Set PCV 604 at 2 psig and open V 610A and 610B.
Flow should be stopped by FV 111

 

GAS MASKS ARE REQUIRED FOR MOST OF THE FOLLOWING OPERATIONS.
BERYLLIUM SAMPLER SHOULD BE IN OPERATION,

1.15

1.16

1,17

1.18

1.19

1.20

1.21

Remove the blank from line 111 and install

weighed adapter flange at E,

 

Install weighed salt addition jumper at F.

 

Purge jumper, thru L610 and then cap line at Gl,

 

Attach resistance heater lugs to heat salt
addition jumper. Ground connection should be

at F.

 

Install purge jumper at Jl, crack open V 611A

and purge air from line and then cap line at Hlo -

 

When salt can in furnace No. 1 is at 100C to 1200°F,
and can is at atmospheric pressure (PI SCl), remove

blanks at H-1,

 

Install weighed dip tube to bottom of can and
attach to purge jumper at H-1,

 
Approved byzflgfj;yééééyflfi%\ 5p-L4

7/29/6.
1.22 Open V 611A and bubble helium through the salt Init. Date and Time
in Can No. 1 for approximately 5 min at a rapid
rate as indicated by the KOH bubbler. This
mixes the salt and assures that it is completely
melted.
1.23 Close V 611A,

1.24 Check that pressure in selected receiver tank is

 

 

equal to or less than atmospheric.

 

1.25 Record drain tank inventory (FD-1, FD-2, FFT, and
FST).

1.26 At G-1; remove cap from salt addition jumper (purge

 

will be provided by line 610), remove control unit
purge line, Jl1 to Hl, and attach dip tube to salt
addition jumper (H1l to Gl).

 

1.27 Using resistance heater, heat salt addition jumper
to cherry red.

1.28 Thaw FV 111 and FV to selected receiver tank.

 

 

1.29 Open vent valve on selected receiver tank.

1.30 Close V 613B and open V 611B to transfer salt

 

in furnace No., 1l.

 

1.31 When transfer is complete as indicated by PI SC1
and receiver tank weight, close V 611B., NOTE:
Record weight indication when probe light level

indicator or receiver tank comes on,

 

1,32 Turn off heat to salt addition jumper.

 

1.33 When receiver tank pressure is equal to or is less

than atmospheric, open V 613B.

 

1.3% When PI SCl is at approximately atmospheric

pressure, close V 613B and disconnect vent at B-1,

 

1.35 Disconnect salt addition line at G-1 and plug ends

at G1, Fa and Fbo
1.36 Remove salt can from furnace No. 1. Reweigh when

 

cool. If dip tube is removed before weighing, be

sure to note this and record its weight also.

 

1.37 Place a new weighed salt can in furnace No. 1 and
connect to vent line at B-1. |

1.38 Open V 613B.

 

 
—

Approved by .-

1.39

1.40

l.41

1,42

1l.43
l.u4

1.45

1.46

1.47
1.u8
1.49
NOTE:
1.50
1.51

1.52

1.53

1.55

  

ot D i i | 5D-2
| | 7/29/65
Connect purge jumper at J2 and crack open V 612A Init. Date and Time

 

to purge line.

 

When salt can in furnace No. 2 is at 1000 to 1200°F
and can is at atmospheric pressure (PI SC2), remove
blank at H-2, | |

Install weighed dip tube to bottom of can and attach

 

to purge line at H-2.
Open V 612A and bubble helium through the salt in

 

can No. 2 for approximately 5 min at a rapid rate
as indicated by the KOH bubbler, This mixes the
salt and assures that it is completely melted.
Close V B61l2A,

 

 

Check that pressure in selected receiver tank is
less than atmospheric,

Record drain tank inventory (FD-1, FD-2, FFT, and

 

FST). (Check List 12B5)

At G-1, remove cap from salt addition jumper and

 

remove control unit purge line, Attach dip tube

to salt addition jumper (G-2 to H-2).

 

Using resistance heater, heat salt addition Jjumper

to cherry red.

 

Close V 614B and open V 612B to transfer salt can

in furnace No. 2.

 

When transfer is complete as indicated by PI SC2

and receiver tank weight, close V 612B.

 

Record weight indication when probe light level indicator changes.

Turn off heat to salt addition jumper.

 

When receiver tank pressure is equal to or less than

atmospheric, open V 614B,

 

When PI SC2 is at atmospheric pressure, close V 614B

and disconnect vent at B-2.

 

Disconnect salt addition line at G-2 and plug ends

(G and Fa Fb)°

 

Remove salt can from furnace No. 2. Reweigh when cool.,
If dip tube is removed before reweighing, be sure to

note this and record its weight also.

 

Place a new weighed salt can in furnace No., 2 and

connect to vent line at B-2.

 
5D-6
o 7/29/65

Init., Date and Time

Approved

 

 

1.56 Open V 614B.
1,57 Repeat Step 1,10 to Step 1.56 until all

 

 

salt has been added.

 

1.58 After last salt has been added, turn off heat

to furnace and salt addition line.

 

1.59 Remove salt addition line at G-1 (or G-2) and
F, and reweigh,

1.60 Cap line 111 at T or E.

1.61 Turn off V 610A and B.

1,62 Flush the salt addition line. (A special

 

 

 

procedure will be issued.)

 

1,63 Turn off helium supply to charging unit and dis-

connect unit,

 

1.64 Have area smeared for beryllium contamination.

 

1.65 Blow out transfer lines per Section 5G.

Coolant Salt Charging (Fig. 5D-1)

 

 

(Note: This procedure assumes that the freeze valves have been filled with salt
and oxygen has been purged from the system,)

2.1 Set up two portable furnaces and control units Init, Date and Time

 

at the fuel-charging station.

 

2.2 Check that salt addition lines, purge line 630,
and coolant drain tank are connected and heated
above 1000°F (Section 5C and 11Al17).

2,3 Place a weighed salt can in each furnace. Check

 

that all openings on the can are plugged when

received,

 

2.4 Connect jumpers between the control unit (Al and
A2) and a vent connection on the top of each can
(Bl and B2). These jumpers should contain an
electric insulating section so that the salt can

is not grounded.

 

2,5 Connect a KOH bubbler and a back siphon relief trap
to the control unit as shown at Cl,

2.6 Close HV 611A, 611B, 613A, 612A, 612B and 614A.

2.7 Open HV 613B and 614B,

 

 

 

2,8 Connect cylinder helium supply to contrel unit at
Dl, D2, and D3,
2.9 Open V 615 and set PCV 611 and 612 at 8 psig.

 

 
 

Approved by 5D=7
7/29/65
2.10 Set furnace temperature controllers at 1300°F, and Init. Date and Time

 

heat up the salt., (Temperature controllers and
thermocouples are integral parts of the charging
unit.

2.11 Attach a 4-in, flexible hose to L9934 outside build-

 

ing for use as a portable vent. Always have the
suction of this hose near any salt containing lines
which are open.
2.12 Check that IV204 and 206 are frozen.
2,13 Check . B 60. TFlow should be stopped by FV 1ll1.
GAS MASKS ARE REQUIRED FOR MOST OF THE FOLLOWING OPERATIONS.
BERYLLIUM SAMPLER SHOULD BE IN OPERATION.,
2.14% Remove the blank from line 203 and install weighed

 

 

 

adapter flange at E.

 

2.15 Install weighed salt addition Jjumper at F.

 

2.16 Purge jumper thru L 630 and cap jumper line at Gl.

 

2,17 Open vent valve on selected receiver tank.

 

2,18 Attach resistance heater lugs to heat salt
addition jumper. Ground connections should

be at F.

 

2.19 Install purge jumper at J-1, crack open V 611A

and purge air from line and then cap line at Hlo
2,20 When salt can in furnace No, 1 is at 1000 to 1200°F,

 

and can is at atmospheric pressure (PI SCl), remove
blanks at H-1,
2.21 Install weighed dip tube to bottom of can and

 

attach to purge jumper at H-1l.
2.22 Open V 611A and bubble helium through the salt in

 

Can No, 1 for approximately S min at a rapid rate

as indicated by the KOH bubbler, This mixes the

salt and assures that it is completely melted.
2.23 Close V 611A,

 

 

2.24 Check that pressure in selected receiver tank is

equal to or less than atmospheric,

 

2,25 Record CDT inventory.

 

2.26 At G~1; remove cap from salt addition jumper (purge
will be provided by line 610), remove control unit
purge line, J1 to Hl, and attach dip tube to salt
addition jumper (H1l to G1).

 
Approved by4¢7?6?k%2§y#u5%1

2.27
2.28

2,29

2.30
2.31

2,32
2,33

2,34

2.35

2,36
2,37

2,38

2,39

2,40
2,41
2.42

2,43

Using resistance heater, heat salt addition jumper
to cherry red.

Close V 613B and.open B 611B to transfer salt in
furnace No., 1. |
When transfer is complete as indicated by PI SC1
and recelver tank weight, close V 611B. NOTE:
Record weight indication when probe light level
indicator CDT comes on.

Turn off heat to salt addition jumper.

When receiver tank pressure is equal to or less

than atmospheric, open V 6138,

When PI SCl is at approximately atmospheric pressure,
close V 613B and disconnect vent at B-1.

Disconnect salt addition line at G-1 and plug

ends at G1, Fa and Fbo
Remove salt can from furnace No. 1. Reweigh when
cool, If dip tube is removed before reweighing, be
sure to note this and record its weight also.
Place a new weighed salt can in furnace No, 1 and
connect to vent liné at B-~1l.

Open V 613B,

Connect purge jumper at J-2 and crack open V 612A
to purge line, When salt can in furnace No. 2 is
at 1000 to 1200°F and can is at atmospheric pres-
sure (PI SC2), remove blank at H-2,

Install weighed dip tube to bottom of can and
attach to purge line at H-1,

Open V 612A and bubble helium through the salt in
can No. 2 for approximately 5 min at a rapid rate
as indicated by the KOH bubbler. This mixes the
salt and assures that it is completely melted.
Close V B12A.

Record CDT inventory.

At G=1, remove cap from salt addition jumper and
remove control unit purge line., Attach dip tube
to salt addition jumper (Cneck GW to HZ).

Using resistance heater, heat salt addition jumper

to cherry red.

5D-8
7/29/65 :

Init. Date and Time

 

 

 

 

 

 

 

 

 

 

 

-

 

 

 

 

 

 

 
4 -
Approved byfifif?féié{f#fl\ | 7%20?g§9

20“"‘

2,45

NOTE:

2.U46
2.47

2.48

2,49

2,50

2,51

2.52
2,53

2.54

2,55

2,56

2.57

2.58

2,59

2,60
2,61

2.62

2.63
2.64

Close V 614B and open V 612B to transfer salt , Init., Date and Time

 

can in furnace No, 2.

 

When transfer is complete as indicated by PI SC2

and receiver tank weight, close V 612B,

 

Record weight indication when probe light level indicator changes.

Turn off heat to salt addition jumper.

 

When receiver tank pressure is equal to or less than

atmospheric, open V 614B,

 

When PI SC2 is at atmospheric pressure, close V 614B

and disconnect vent at B-2.

 

Disconnect salt addition line at G-2 and plug
ends (G and Fan)o

 

Remove salt can from furnace No. 2, Reweigh when
cool., If dip tube is removed before reweighing,

be sure to note this and record its weight also.

 

Place a new weighed salt can in furnace No., 2

and connect to vent line at B-2,

 

Open V 614B,

 

Repeat Step 2.9 to Step 2,52 until all salt has
been added.

 

 

After last salt has been added, turn off heat to

furnace and salt addition line.

 

Remove salt addition line at G-1 (or G-2) and F,

and reweigh,

 

Cap line 203 at F or E,

 

Turn off V 630,

 

Flush the salt addition line., (A special procedure

will be issued.)

 

Turn off helium supply to charging unit and dis-

connect unit,

 

Have area smeared for beryllium contamination,

 

Turn off heaters on L 203 and CTD, Table 5C4 and
tag off.

 

Disconnect L 203 from CDT and install blank flange
on CDT. Blank off each end of L 203,

 

Leak check flange on CDT with portable LD unit.

 

Remove tag on CDT heaters Table S5C4 and turn

heaters on.

 
 

Approved by "%2/€%E%/#¢fh 5E-1

9/16/65

5E STARTUP OF LUBE OIL SYSTEMS
for the
FUEL AND COOLANT CIRCULATING PUMPS

The lube o0il systems must be in operation before the fuel and cool-
ant pumps are started and/or heated. The pressure on the lube 0il stor-
age tank should be maintained at 2 to 8 psi above the pump pressures.
Normally, FOP-2 and COP-2 will be in operation with FOP-1 and COP-1 in
standby. The lube cil systems are congidered to be closed systems, and
therefore, have no block valves to isclate them from the cell. There-
fore, no valve from the 0il systems to the atmosphere should be opened
while the reactor is in operation without written approval of the opera-
tion chief.

To start up the lube oil systems, oil is added to the supply tank,
the tanks are purged and pressurized with helium, the valves are set,
the pumps started and flows adjusted. It may be also necessary to drain
the oil from the oil-catch tanks.

1 DETAILS FOR STARTUP OF LUBE OLL SYSTEMS

 

Init. Date/Time

 

(Auxiliary Control Room)
1.1 Check both OCT levels:
LI-52h %,
LI-526 _ %.
(Coolant Drain Tank Cell)
1.2 Drain oil from OCT-1 and OCT-z into WOR-1
or 2 until the level ig 5 to 10%.

 

 

(Auxiliary Control Room)
1.3 Record LI-52h %,
LI-526 %.

1.4 Calculate and record in console log and on

 

WOR-1, WOR-2 inventory cards the amount of
0il drained from OCT-1 to WOR-1 and
from OCT-Z2 to WOR-2

1.5 Drain oil from syphon pot into WOR-1

 

 
Approved bym Pt

NOTE:

1.6

1.7

Do
1.9

1.10

Calculate the amount of oil drained from

syphon pot to WOR-1l. Record this on syphon

pot and WOR-1 inventory cards and in console

log.

Isolate WOR-1 and Z by tagging the following

valves closed:

V-7204 V-5254
v-529 V-T20-2A
V-720B __ , V-525B

v-770 V-720-2B .
(Service Tunnel)
1.8 Fill the oil supply tanks (OT-1 and OT-2)

with Gulfspin-35 oil through V-711l and T761.

Normal starting level as indicated by

LI-07-1-A3 and
lines are full
empty. Record
LI-OD-1-A3
LI-0T-2-A3
LI-0T-1-A3
LI-0T-2-A3

LI-0T-2-A3 is 55 to 60% if
and 80 to 90% if lines are
the following:

before filling
before filling

after filling

after filling ,

O0il added to OT-1 (measured) ,
0il added to OT-2 (measured) .

not allow alr to get into the oil catch tanks.

Check that all

flanges removed for mainte-

nance are leaktight and all leak-detector

lines are capped.

Remove cover from the oil filters, CF-1

and OF-2; turn

handle three full turans,

then replace cap.

OF-1 ;
OF-2

5E-2
9/16/65

Init. Date/Time

 

 

 

 

 

 
o o s
Approved by*5§€2¢i2%?fzuyw~
3

S5E-3
9/16/65

Iniz. Date/Time

 

1.11 Leak check flanges by pressurizing leak

detector to 100 psig.

Allowable pressure

drop is 1 psi per hour for an 8-hour

period.

Time start

Pressure start

Time stop

Pressure stop
Pressure drop, psi/hr

IKD line capped

1.12 Set oill valves as follows:
V-TlzA tag closed
V-601A tag closed
V-T62A tag closed

V-T762B tag closed

V-762C tag closed ,

FTuel Oil System
V-TO3A tag open
V-70z2 tag open o
V-701 tag open
V-713 tag open
V-71k tag open
V-715 open
V-703B closed
V-704 closed
V-703C tag closed .
V-703D tag closed s
V-590 tag open
V-T706 tag open
V-711 tag closed
V-716 tag closed

e

 

OF-1  QF-2

S—" ———

 

A et

r——————

 

Coolant Oil System
V-753A tag open
V-752 tag open

V-T51 tag open

V-763 tag open

V-764 tag open

V-765 open

V-753B closed

V-754 closed

V-753C tag clcsed ___'
V-753D tag closed
V-591 tag open

V-756 tag open

V-761 tag closed
V-766 tag closed

 

 
A7,
Approved by/aé§?53£f§%5144¢zL_

1.13

Pressurize the systems with helium as follows:
V-513A tag open _ V-510A tag open L
V-513B tag open __ V-510B tag open
V-513C tag open ___ V-510C tag open
V-513D tag open ___ V-510D tag open
V-535A tag open _ V-534A tag open
V-535B tag open  V-534B tag open
V-531 tag open  V-551 tag open
V-532 tag open __ V-552 tag open

5E-L

9/16/65

Init.

Date/Time

 

 

1.1L Check to be sure FI-821 and FI-823 read 7 to

10 gpm.

(Mein Control Room)

1.15 Start FOP No. 2, and note that discharge pres-

1.16 Start COP No. 2, and note that discharge pres-

Set PIC-513 on Auto at 7 psig ,
Set P1C-510 on Auto at 7 psig __ .

sure (PI-702) 60 psig.

sure (PI-752) >60 psig.

(Service Tunnel)

1.17
1.18

1.19

1.20
1.21

1.22
1.23

Open V-~T04 to full open position.

Throttle V-703B to give a flow of 3.5 gpm on
F1-703.

Simultaneocusly throttle V-T15 and V-703B to
give a flow of 3.5 gpm on FI-703 and 6.5 gpm
on FI-704k (as V-715 is throttled down, flows
on FI-703 and FI-704 will increase).
Readjust V-T03B if necessary.

Notify shift supervisor if V-715 needs to be
throttled down more than 3 3/4 turns from full
open position.

Open V-T54 to full open position.

Throttie V-753B to give a flow of 3.5 gpm on
FI-753. |

 

 

 

 

 

 
"/ :-' e -
Approved by 7 7 \'ury pt g SE-5
| Y - 9/16/65

. Init. Date/Time

 

1.24 Simultaneously throttle V-765 and V-753B to
give a flow of 3.5 gpm on FI-753 and 6.5 gpm
on FI-754 (as V-765 is throttled down, flow
on FI-753 and FI-T54 will increase).

1.25 Readjust V-753B if necessary.

1.26 Notify shift supervisor if V-765 needs %o be
throttled down more than 3 7/8 turns from full

 

 

open position.
1.27 Stop FOP-2 and COP-2 by opening breakers FOP-2

 

and COP-2 in the service tunnel and note that
FOP-1 and COP-1 start.
1.28 Reset and close breakers FOP-2 and COP-2.
(Switch House)
1.29 Stop FOP-1 and COP-1 by opening breakers G3-11
and G4-11 and note that FOP-2 and COP-2 start.
1.30 Reset and close breakers (3-11 and GL-11.

 

 

 

 

(Service Tunnel)
1.31 Readjust flows if necessary (Steps 17 through
24 ).
1.32 The oil supply tank levels should be 50 to 60%.

——————————

Record:
LL-0T-1-A3
LI-0T-2-A3
1.33 Set LI-OT-1-A3 and OT-2 to alarm at 1% below
the operating level and to close FSV-T703 and
FSV-753 at 1% below the operating level.

Record the followlng:

Level Alarm Valve Control
Reading Setpoint Setpoint

LI-0OP-1-A3 )
LI~0T-2-A3

 

 
Approved by 444?Za/%€2;4w4m~1

1.34 Check that the oil tank radiation
are in place and in operation:
RIA-OT-1
RIA-OT-2

5E-6
9/16/65

Init. Date/Time

 

monitors
s
Approved by/¢5€;;2%;42;6u¢n1 5F-1

9/9/65
5F HEATUP OF FUTT, AND COOLANT SYSTEMS

The heatup rabe of the fuel and coolant systems should not exceed
100°F per hour, and since the two systems are connected at the heat ex-
changer, the temperature range of all points on both systems should be
kept as close as is practical. The circulating pumps will run during
heatup, and the helium purge flow will be kept at the normal rate. This
is to aid in heating up the graphite and help purge out any remaining
OXygen.

To minimize thermal stresses, the component coolant alr flow should
be flowing to the control rods and reactof neck during the heatup.

Details of the operation are given below.

1 PREPARATTON FOR HEATUP
(Main Control Room)

 

Tnit. Date/Time

 

1.1 Open HOV-523, V-96l4,. and V-961B to pro-
vide a vent for the overflow tank and reactor

neck annulus.

 

1.2 Set FIC-516A and FIC-512 per building log

to purge system during heatup.

 

1.3 Set PRC-522A and PRC-528A on automatic at
5> psig.

 

(Coclant Cell)
1.4 Physically check that the radiator doors

are closed.

 

1.5 Physically check that the bypass dampers are
closed.

1.6 C(lose the hatch between the coolant drain

 

tank cell and the radiator duct (Downstream

of radiator).

 

1.7 Close both doors between the blower house
and the radiator duct. (Upstream of the

radiator).

 

(Main Control Room)
Approved b - AN 5F-2

7 9/9/65

Init. Date/Time

 

1.8 Perform operations necessary to make up
Circuit 134 (Prefill mode).

1.9 Check that No. 1 and No. 3 blowers are
off.

 

 

1.10 Fully insert all three control rods.
CR-1
CR-2
CR-3

 

1.1l Start the coolant pump while listening
Tor unusual noises on the mike (Xdb E CP D).
L.12 Record the following:
EiI-CP-D (should be 19 amps)
EwI-CP-D (should be 2 Kw)
SI-CP-G (should be 1750 rpm)
(Transmitter Room)
SI-CP-G1 (should be 1750 rpm)
SI-CP-G2 (should be 1750 rpm)
NOTE: Taps to the flow indicator FR-201 will be frozen,

 

 

and therefore, this instrument will not be in operation.
(Main Control Room)
1.13 Start the fuel pump while listening for
unusual noises on the mike. (Xdb E FPF).

 

1.14 Record the following:
EiI-FP-D (should be 19 amps)
EwI-FP-D (should be 2 Kw)
SI-FP-E (should be 1150 xpm)
(Transmitter Room)
SI-FP-Fl (should be 1150 rpm)
SI-FP-E2 (should be 1150 rpm)

 

1.15 Check that the thermocouples listed in
Table 5F-1, S5F-2, and 5F-3 are plugged
intc the readout ingtruments listed and

the instruments are in service.

 
  

Approved by =

?figkééf F-
=~ o/o/c

Init. Date/Time
1.16 Start the air flows to the conbtrol rods
and the reactor neck. Set as per the

building log.

Control rods HIC-G15
Reactor Neck HIC-961
HIC-962
HIC-963

 

1.17 Push the start buttons on all the induc-
tion regulator blowers and check to see

that they start.

TIC-1 TTC-2
TIA-1 TIA-2
TIB-1 TIB-2
G5-BB-1 ___ (5-BB-2
G5-27-2 T2-7-1

 

2 HEATUP
2.1 Set the reactor heaters (R-1, R-2, and
R-3) at 50% of their 1200°F current set-
ting.

 

2.2 The reactor vessel will be the most slovwly
heated component due to its large mass.
Turn on and adjust the remainder of the
heaters listed in Tables 5F-1, 5F-Z, and
SF-3 so as to keep the temperatures under
these heaters more than the reactor but
within 150°F of the reactor. The heater
calibration curves may be used as a gulde
in making heater adjustments.

NOTE: ©Part of the method of monitoring the radia-

 

tor heatup will be Scanners "D" and "E." Note
that these have variable references and will need

to be adjusted as the heatup progresses.
Approved by *233?%?763%27%«4fl1 SF-L
<

2.3

2.5

9/9/65

Init. Date/Time

 

Each time the reactor heatup rate begins
to slacken, increase the reactor heaters'
current settings. The settings should
be increased from 50% to 75%; from 75%
to 90%, and from 90% to 105% of their
1200°F amperage settings.
Init. Date/Time

Increased to 75%

Increased to 90%

Increased to 105%

 

 

 

 

As the heatup progresses, the temperature

of the penetrations should be given special
attention. Try to keep the piping tempera-
ture on both sides of the penetration as
close to the pipe temperature in the pene-
tration as is possible. Record the tempera-

tures as indicated in Table 5F-5.

 

When the temperatures indicated by TE-CR-124
and TE-CR-122 (points 34 and 35 on Scanner
B) are above 900°F, the flow element should
be heated. The following steps should be
used.

2.5.1 Record the following temperatures:
O

TE-CR-124 (Scanner B Pt.34) F
TE-CR-123 (T1-3200 Pt.7) O
TE-CR-122 (Scanner B Pt. 35) °F

 

2.5.2 If CR-124 and CR-122 indicate tem-
peratures above 9OOOF, turn on the
flow element heaters. These are listed

in Table 5F-4.

 

2.5.3 Adjust the heaters to give a heatup
rate of ~ 200°F/hr. Try to keep the

temperatures of the thermocouples
A
Approved byzwffzgfj \yé;g{xW¢m] SF-5
| < 9/9/65

Init. Date/Time

 

oo

.5.3 {continued)
listed in Table 5F-4 within % lOOOF

of each other.

 

2.5.4 When the temperature of the flow
elements reaches that of line 201,
level off the heatup rate of the
flow elements and keep at the same

temperature as line Z0L.

 

2.6 When the temperature indicated by
TE-103-13 is above 900°F, start
heating the short section of line
106 ag follows.

2.6.1 Plug the thermocouples listed
in Table 5F-6 into one of the
special recorders so heatup of this
section of line may be closely fol-
lowed. Finish filiing out Table
5F-6A. Keep thermocouple logs
up to date.

 

2.6.2 When TE-103-13 is above 900°F,
turn on H-106-4. Adjust to give a
heatup rate of flOOOF/hr. This
section of line must be heated very
carefully due to the likely pres-
ence of salt in the lines. Do not
allow the temperature of TE-106-5A
to exceed TE-FV-105-6B. Table 5F-T
should be filled in to aid the oper-
ator in keeping up with the tempera-

tures of the thermocouples.

 

2.6.3 Do not exceed the 1200°F setting
on heater 106-4. The temperatures
of TE-106-5A or TE-FV-105-6B may
Approved bywm SF-6
9/9/65

Init. Date/Time

 

2.6.3 (continued)

neither come up to their normal valve
until the freeze valve shoulder heaters
are turned on. Leave the thermocouples
listed in Table 5F-6 readingout on the
specilal recorder until the freeze valve
shoulder heaters are turned on and/or
the temperature of all thermocouples

in 5F-6 are above 1100°F. See Pro-

cedure 51 for freeze valve heatup.

 

2.7 Level all temperatures in the loops at 1100
to lZOOOF. Make heater adjustments neces-
sary to accomplish this (such as lowering
the reactor heaters from 105% to 100% of
their 1200°F setting).

 

GENERAL NOTE: The heatup of the drain tanks and lines
out to the freeze valves is covered in Procedure 5C.

Heatup of the freeze valves shoulders is covered in
the fill Procedure (5I).
 

 

  
 

 

TABLE SF-1 fi?
THERMOCOUPLES AND HEATERS FOR REACTOR CELL COMPONENTS 3
Page 1 of 5 é
OTHER HEATERS g
TE HEATER CONTROLLER CONTROL ON THIS
READCUT POINT NUMBER NUMBER NUMBER PANEL CONTROLLER 3&
Scanner "A" 1 R-1 R-2 R-2 HCP-7 -
o 2 R-3 R-1 R-1 HCP-7 <<:;3
s 3 R-4B HCP-7 u
o L R-5B R-1, R-2, R-3 R-1, R-2, R-3 HCP-7 X
e 5 R-6B HCP-7 S
! 6 R-11 R-2 R-2 HCP-T7
oy 7 R-12 R-1. R-1 HCP-~7
e 8 R-13 R-3 R-3 HCP-7
9 R-1k4 R-2 R-2 HCP-7
o 10 R-15B R-2, R-3 R-2, R-3 HCP-7
m 11 R-16 R-1 R-1 HCP-7
e 12 R-18B R-3 R-3 HCP-T7
o 13 R-19 R-2 R-2 HCP-T7
i 1h R-20B R-2 R-2 HCP-7
e 15 R-21 R-2, R-3 R-2, R-3 HCP-7
o 16 R-22 R-1 R-1 HCP-7
o 17 R-23B R-1 R-1 HCP-7 \O
i 18 R-2k R-3 R-3 HCP-7 %g}g
o 19 R-25B R-2 R-2 HCP-7 i

" 20 R-263 R-1, R-2, R-3 R-1, R-2, R-3 HCP-7

 
TABLE 5F-1 (continued)

 

i
3
H
o
2
(D
tof
C'
e

 

 

Page 2 of 5
OTHER HEATERS
TE HEATER CONTROLLER CONTROL ON THIS
READOUT POINT NUMBER NUMBER NUMBER PANEL CONTROLLER

Scanner "A" 21 R-27B R-1, R-2, R-3 R-1, R-2, R-3 HCP-T
e 22 R-28B R-1, R-2, R-3 R-1, R-2, R-3 HCP-7
e 23 R-29B R-1, R-2, R-3 R-1, R-2, R-3 HCP-7
n 2l R-30B R-1, R-2, R-3 R-1, R-2, R-3 HCP-7
n 25 R-31B R-1, R-2, R-3 R-1, R-2, R-3 HCP-T7
o Reference R-32B R-1, R-2, R-3 R-1, R-2, R-3 HCP-7
e 26 100-1B
n 27 100-2B H 100-1 H 100-1 HCP-5
nh 28 100-3B E 100-2 H 100-2 HCP-6
o 29 100-4 FP-1, FP-2 FP-1, FP-2 HCP-T
n 30 100-5 FP-1, FP-2 FP-1, FP-2 HCP-7
e 31 FP-7B FP-1, FpP-2 FP-1, FP-2 HCP-7
e 32 ¥P-8B FP-1, FP-2 FP-1, FP-2 HCP-7
o 33 OFT-2A FP-1, FP-2 FP-1, FP-2 HCP-T7
n 34 OFT-3 FpP-1, FP-2 FP-1, FP-2 HCP-T7
. 35 OFT-5 FP-1, FP-2 FP-1, FP-2 HCP-T7
n 36 101-1 H 101-1 RCH-7 HCP-7 H-102-3 o
nr 37 101-2B H 101-2 H-101-2 HCP-6 §§}g
n 38 101-3B H 101-3 H 101-3 HCP-6 &
n 39 HX-3B H 101-3 H 101-3 HCP-6

n Lo EX-6 HX-1 HX-1 HCP-T7

 
TABLE 5F-1 (continued)

 

 

 

 

g
Page 3 of 5 §
OTHER HEATERS -
TE HEATER CONTROLLER CONTROL ON THIS g
READOUT POINT NUMBER NUMBER NUMBER PANEL CONTROLLER
Scanner "A" 41 HX-7B HX-1 HX-~1 HCP-T7
e L2 HX-8 HX-2 HX-2 HCP-7
" b3 HX-9B HX-2 HX-2 HCP-T7
e Wi HX-10 HX-2 HX-2 HCP-T7
e L5 HX-2B HX-3 HX-3 HCP-7
" 46 HX-5 HX-3 HX-3 HCP-T
e L7 102-1B H 102-1 H 102-1 HCP-TA
"" L8 102-A2 H 102-2A H 102-2 HCP-7
e e 102-B2 H 102-2B H 102-2 HCP-7
nh 50 102-3B H-102~3 RCH-7 HCP-T7 H-101-1
n 51 102-A4B H-102-4 H-102-4 HCP-TA
n 52 102-BL4B H-102-5 H-102-5 HCP-TA
n 53 102-5B
m 54 200AS-A1A H-200-16 H-200-16 HCP-TA
i 55 200-A0A H-200-1, 16 H-200-1, 16 HCP-5, TA
m 56 200-BoA H-200-1 H-200-6 HCP-5
o 57 200-10 H-200-2 RCH-1 HCP-6 o
o 58 200-11A H-200-3 RCH-1 HCP-6 §§}§
i 59 200-12 H-200-4 RCH-1 HCP-6 IO
" 60 200-13 H-200-5 RCH-2 HCP-6 H-201-8

 
TABLE 5F-1 (continued)

Page 4 of 5
OTHER HEATERS

 

TE HEATER CONTROLLER CONTROL ON THIS
READOUT POINT NUMBER NUMBER NUMBER PANEL CONTROLLER

Scanner "A" 61 200-14B H-200-6 RCH-3 HCP-6

n 62 200-15 H-200-7 RCH-3 HCP-6

! 63 200-16A H-200-8 RCH-3 HCP-6

e 6l 200-A17 H-200-9 RCH-4 HCP-6 H-201-k

e 65 200-B17 E-200-9 RCH-4 HCP-6 H-201-4

n 66 200-18 H-200-10 RCH-5 HCP-T7 H-201-3

n 67 200-19B H-200-11 H-200-11 HCP-5

n 68 200-20B H-200-12 H-200-12 HCP-5

n 69 HX-1B HX-1 HX-1 HCP-7

m 70 HX-4B

nh 71 201-1A H-201-1 H-201-1 HCP-5

n 72 201-2A H-201-2 H-201-2 HCP-5

m 73 201-3 H-201-3 RCH-5 HCP-T H-200-10

i 4 201-Ak H-201-L4 RCH-4 HCP-6 H-200-9

n 75 201-Bh H-201-4 RCH-L HCP-6 H-200-9

e 76 201-5B H-201-5 RCH-6 HCP-T

m 77 201-6 H-201-6 RCH-6 HCP-7

"o 78 201-7A H-201-7 RCH-6 HCP-7

e 79 201-8 H-201-8 RCH-2 HCP-6 HE-200-5

n 80 201-A9A H~201-9 H-201-9 HCP-5

 

s
o
g
H
Q
2
®
o
o’
L

 

Gs/6/6
OT-44
TARLE 5F-1 {continued)

Page 5 of 5
OTHER HEATERS

 

TE HEATER CONTROLLER CONTROL ON THIS
READOUT POINT NUMBER NUMBER NUMBER PANEL CONTROLLER
Scanner "A" 81 201-BYA H-201-9, 1L H-201-9, 1k HCP-5, TA

" 82 201AS-A1A H-201-14 H-201-14 HCP-TA

o 83 103-A1A H-FV-103 H-FV-103 HCP-8

! 8L 103-Bl H 103 H 103 HCP-8

e 85 103-2 H 103 H 103 HCP-8

' 86 103-3 H 103 H 103 HCP-8

n 87 103-k4 H 103 H 103 HCP-8

e 88 103-A5 H 103 H 103 HCP-8

e 89 103-B5 H 103 H 103 HCP-8

o 90 103-7 H 103 H 103 HCP-8

n 91 103-9 H 103 H 103 HCP-8

m 92 103-10 H 103 H 103 HCP-8

o 93 103-A11 H 103 H 103 HCP-8

no ol 103-12

e 95 103-13 H 104-7 H 10h4-7 HCP-10

n 96 103-1LA H 104-7 H 104k-7 HCP-10

e o7 104-B6 H 104-7 H 104-7 HCP-10

e 98 - 10hk-46 H 10Lk-6 H 104-6 HCP-9

e 99 104-5A H 104-5 H 104-5 HCP-9

" 100 R-32B R-1, R-2, R-3 R-1, R-2, R-3 HCP-T7

Reference

 

£q psaroxddy

)gé‘

69/6/6
TT-d6
 

 

 

TABLE 5F-2
T/C's AND HEATERS FOR COOLANT SYSTEM OUT OF REACTOR CELL
Page 1 of 4
TE HEATER CONTROLLER CONTROL
READOUT POLNT NUMBER NUMBER WUMEER PANEL

Scanner "B" 1 CP-6B CP1 CP1 HCP-4

" 2

n 3 CP-9B CP2 CP2 HCP-4

n L LE-AL LECP-2 LECP-2 HCP-3

n 5 LE-A3 LECP-1 LECP-1 HCP-3

i 6 200-1 H-200-13 H-200-13 HCP-1

" 7 200-2 H-200-13 H-200-13 HCP-1

" 8 200-3 H-200-13 H-200-13 HCP-1

" 9 200-4 H-200-13 H-200-13 HCP-1

" 10 200-5 H-200-13 H-200-13 HCP-1

n 11 200-6 H-200-13 H-200-13 HCP-1

" 12 200-ATA H-200-1k H-200-14 HCP-2

o 13 200-B7A H-200-1k H-200-14 HCP-2

nh 14 200-CTB H-200-14 H-200-1kL HCP-2

nh 15 200-DTA H-200-1L H-200-14 HCP-2

n 16 200-A8A H-200-15 H-200-15 HCP-2

nh 17 200-R8A

" 18 200-C8A

" 19 201~-A10A

e 20 201.-B10OA

 

/=
h4“4JE’$¢aZ;ugz/’ £q poaoaddy

 

69/6/6
ST-46
 

 

 

TABLE 5F-2 (continued) %)

Page 2 of 4 §

TE HEATER CONTROLLER CONTROL A

READOUT POINT NUMBER NUMBER NUMBER PANEL g

Scanner "B 21 201-C10A H-201-10 H-201-10 HCP-2 \
e 22 201-A11A H-201-11 H-201-11 HCP-2
e 23 201-Bl1A H-201-11 H-201-11 HCP-2
e 2L 201-C11A H-201-11 H-201-11 HCP-2
e 25 201-D11A H-201-11 H-201-11 HCP-2
! 26 201-12 H-201-12 H-201-12 HCP-1
e 27 201-13 H-201-12 H-201-12 HCP-1
e 28 201-14 H-201-12 H-201-12 HCP-1
" 29 201-15 H-201-12 H-201-12 HCP-1
n 30 201-16 H-201-12 H-201-12 HCP-1
e 31 201-17 H-201-12 H-201-12 HCP-1
n 32 205-1 H-205-1 H-205-1 HCP-3
e 33 205-2 H-205-1 H-205-1 HCP-3
e 34 CR-12L H-201-13 H-201-13 HCP-2
e 35 CR-122 H-201-13 H-201-13 HCP-2
nu 36 CR-128 CR-7 CR-T HCP-1
e 37 CR-129 CR-T CR~7 HCP-1
" 38 CR-126 CR-1, 2, 3, 4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1 ©

m 39 CR-127 CR-1, 2, 3, 4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1 gifg

e 40 CR-130 CR-8 CR-8 HCP-1 NATY
m 41 CR-131 CR-8 CR-8 HCP-1

 
TABLE 5F-2 (continued)

 

~ £q paroxddy

 

Page 3 of U
TE HEATER CONTROLLER CONTROL

READQUT POINT NUMBER NUMBER NUMBER PANEL
Scanner "B" L2 CR-125A H-202-1 H-202-1 HCP-3
o L3 CR-132 CR-1, 2, 4, 5, 6 CR-1, 2, L, 5, 6 HCP-1
' nn CR-133 CR-1, 2, L4, 5, 6 CR-1, 2, 4, 5, 6 HCP-1
™ L5 CR-13k CrR-1, 2, 4, 5, 6 CR-1, 2, 4, 5, 6 HCP-1
" L& CR-135 CR-1, 2, 4, 5, 6 CR-1, 2, 4, 5, 6 HCP-1
nn L7 CR-136 CR-1, 2, 4, 5, 6 CR-1, 2, 4, 5, 6 HCP-1
m L3 CR-137 CR-1, 2, 4, 5, 6 CR-1, 2, 4, 5, 6 HCP-1
e Lo CR-138 CR-1, 2, 3, L4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
" 50 CR-139 CR-1, 2, 3, 4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
nn 51 CR-140 CR-1, 2, 3, L4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
o 52 CR-141 CR-1, 2, 3, &, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
n 53 CR-1k2 CR-1, 2, 3, 4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
e 5k CR-143 CR-1, 2, 3, 4, 5, 6 CR-1, 2, 3, 4, 5, 6 HCP-1
" 55 CR-144 CR-1, 3, 4, 5, 6 CR-1, 3, 4, 5, 6 HCP-1
" 56 CR-145 CR-1, 3, 4, 5, 6 CR-1, 3, 4, 5, 6 HCP-1
" 57 CR-146 CR-1, 3, L, 5, 6 CR-1, 3, 4, 5, 6 HCP-1
e 58 CR-1L7 CR-1, 3, 4, 5, 6 CR-1, 3, b4, 5, 6 HCP-1
m 59 CR-148 CR-1, 3, 4, 5, 6 CR-1, 3, 4, 5, 6 HCP-1
”" 60 CR-149 CR-1, 3, 4, 5, 6 CR-1, 3, 4, 5, 6 HCP-1
" 61 202-A2 H-202-2 H-202-2 HCP-1

n 62 20z2-B2 H-20z-2 H-202-2 HCP-1

€9/6/6
7T-d6

 
TABLE 5F-2 (continued)

 

 

Page 4 of L

TE HEATER CONTROLLER CONTROL

READOUT POINT NUMBER NUMBER NUMBER PANEI,
Scanner "B" 63 202-3 H-202-2 H-202-2 HCP-1
" 64 202-Ak H-202-2 H-202-2 HCP-1
m 65 202-A5 H-202-2 H-202-2 HCP-1
i 66 202-6 H-202-2 H-202-2 HCP-1
TRA-3500 1 204-1B 204 -1 204 -1 HCP-4
o 2 20L-2B 204 -1 204L-1. HCP-4
e 3 204-3B 20k -1 20k-1 HCP-4
o b 204 -4B 204-1 204 -1 HCP-4
e 5 204 -5B 204 -1 204-1 HCP-4
e 6 204 -6B 204-1 204-1 HCP -4
e 9 206-1B 206-1 206-1 HCP-4
e 10 206-2B 206-1 206-1 HCP-k
" 11 206-3B 206-1 206-1 HCP-k4
" 12 206-4B 206-1 206-1 HCP-4
' 13 206-5B 206-1 206-1 HCP-L
nn 14 206-6B 206-1 206-1 HCP-L4

 

Q

W £q paroaddy

 

My

59/6/6
QT-44
Approved by Mfiw\ SF-16
-9/9/65

TABLE 5F-3
T/C's AND HEATERS AT RADIATOR RISERS

 

 

Page 1 of 8
SCANNER TE HEATER CONTROLLER CONTROL
LOCATION POINT NUMBER NUMBER WUMBER PANEL
Riser-15 D-1, D-61 CR-51 CR-8% CR-8% HCP-1
e D-2, D-62 CR-53 CR-8% CR-8% HCP-1
m D-3, D-63 CR-55 CR-&% CR-8% HCP-1
i D-4, D-6kL CR-57 CR-8% CR-8% HCP-1
nr D-5, D-65 CR-59 CR-8% CR-8% HCP-1
Riser=-16 D-6, D-66 CR-61 CR-8% CR-8% HCP-1
n D-7, D-67 CR-63 CR-8% CR-8#% HCP-1
n D-8, D-68 CR-65 CR-8% CR-8% HCP-1
e D-9, D-69 CR-67 CR-8% CR-8% HCP-1
" D-10, D-70 CR-69 CR-8% CR-G% HCP-1.
i D-11, D-T1 CR-T1 CR-8% CR-8% HCP-1
Riser-17 D-12, D-T2 CR-T3 CR-8% CR-8% HCP-1
m D-13, D-73 CR-T75 CR-8% CR-8% HCP-1
" D-14, D-Th CR-T7 CR-8% CR-8% HCP-1
o D-15, D-75 CR-T9 CR-8% CR-8% HCP-1
o D-16, CR-81 CR-8% CR-8% HCp-1
" D-17 CR-83 CR-8% CR-8% HCP-1
Riser-18 D-18 CR-85 CR-8% CR-8% HCP-1
n D-19 CR-87 CR-8% CR-8% HCP-1
m D-20 CR-89 CR-8% CR-8% HCP-1
n D-21 CR-91. CR-8% CR-8% HCP-1
e D-22 CR-93 CR-8% CR-0% HCP-1
n D-23 CR-95 CR-8% CR-0% HCP-1
Riser-19 D-24 CR-97 CR-8% CR-8% HCP-1
m D-25 CR-99 CR-G% CR-8*% HCP-1
Riser-11 D-26, D-86 CR-1 CR-G% CR-G% HCP-1

 

*¥Although Heater H-CR-8 will be most important, the other heaters on the
radiator will have a significant effect on the temperatures of the thermo-

couples listed in this Table.
Approved by"ffg;kégéfwwgn« 5F-17

. 9/9/65

TABLE 5F-3 (continued)

 

 

Page 2 of 8
SCANNER TE HEATER CONTROLLER CONTROL
LOCATION POINT NUMBER NUMBER NUMBER PANEL
Riser-11 D-27, D-87 CR-3 CR-8% CR-8% HCP-1
n D-28, D-88 CR-5 CR-8% CR-8% HCP-~1
n D-29, D-89 CR-T7 CR-8% CR-8% HCP-1
n D-30, D-90 CR-9 CR-8% CR-8% HCP-1
n D-31, D-91 CR-11 CR-8% CR-8% HCP-1
Riser-12 D-32, D-92 CR-13 CR-8% CR-8% HCP-1
Y D-33, D-93 CR-15 CR-8% CR-8% HCP-1
m D-34, D-94 CR-17 CR-8% CR-8% HCP-1
" D-35, D-95 CR-19 CR-8% CR-8% HCP-1
m D-36, D-96 CR-21 CR-8% CR-8% HCP-1,
n D-37, D-97 CR-23 CR-8% CR-8% HCP-1
Riser-13 D-38, D-98 CR-25 CR-8% CR-8% HCP-1
" D-39, D-99 CR-27 CR-8% CR-8% HCP-1
o D-40 CR-29 CR-8% CR-8% HCP-1
n D-41, D-51 CR-31 CR-8% CR-8% HCP-1
" D-42, D-52 CR-33 CR-&% CR-8% HCP-1
n D-43, D-53 CR-35 CR-8% CR-8% HCP-1
Riser-1h4 D-Lk, D-5k CR-37 CR-5% CR-8% HCP-1
Y D-45, D-55 CR-39 CR-8% CR-8% HCP-1.
n D-46, D-56 CR-41 CR-8% CR-8% HCP-1
" D-47, D-57 CR-43 CR-8% CR-8% HCP-1
' D-48, D-58 CR-h45 CR-8% CR-8% HCP-1
n D-49, D-59 CR-47 CR-8% CR-8% HCP-1
Riser-15 D-50, D-60 CR-49 CR-8% CR-8% HCP-1
Riser-13 D-51, D-4l CR-31 CR-8% CR-8&% HCP-1
m D-52, D-h2 CR-33 CR-8% CR-8% HCP-1
" D-53, D-43 CR-35 CR-8% CR-8% HCP-1

 

*¥Although Heater H-CR-8 will be most important, the other heaters on the
radiator will have & significant effect on the temperatures of the thermo-

couples listed in this Table.
 

 

 

Approved bxg?€?;5343£;7fl4jfi 5F-18
V 9/9/65
TABLE 5F-3 (continued)
Page 3 of 8
SCANNER TE HEATER CONTROLLER CONTROL

LOCATTON POLNT NUMBER IUMBER NUMBER PANEL
Riser-13 D-54, D-Lk CR-37 CR-8% CR-8% HCP-1.
Riser-1k D-55, D-45 CR-39 CR-8% CR-8% HCP-1
" D-56, D-U6 CR-41 CR-8% CR-8% HCP-1

m D-57, D-47 CR-43 CR-8% CR-8% HCP-1

" D-58, D-48 CR-45 CR-8% CR-8% HCP-1

m D-59, D-49 CR-47 CR-8% CR-8% HCP-1
Riser-15 D-60, D-50 CR-49 CR-8% CR-8% HCP-1
n D-61, D-1 CR-51 CR-8% CR-0% HCP-1

" D-62, D-2 CR-53 CR-8% CR-8% HCP-1

" D-63, D-3 CR-55 CR-8% CR-8% HCP-1

n D-64, D-k CR-57 CR-8% CR-8% HCP-1

" D-65, D-5 CR-59 CR-8% CR-8*% HCP-1
Riser-16 D-66, D-6 CR-61, CR-8% CR-8% HCP-1
o D-67, D-T CR-63 CR-8% CR-8% HCP-1

o D-68, D-8 CR-65 CR-8% CR-8% HCP-1

" D-69, D-9 CR-67 CR-8% CR-8% HCP-1.

m D-70, D-10 CR-69 CR-8&% CR-8% HCP-1

n D-71, D-11 CR-T1 CR-8% CR-8% HCP-1
Riser-17 D-72, D-12 CR-73 CR-8% CR-8% HCP-1
n D-73, D-13 CR-T75 CR-8% CR-8% HCP-1

n D-74, D-1k CR-T7 CR-8% CR-8% HCP-1

n D-75, D-15 CR-T9 CR-8% CR-8*% HCP-1

o D-T76 CR-101 CR-8% CR-8% HCP-1

" D-77 CR-103 CR-8% CR-8% HCP-1

" D-78 CR-105 CR-8% CR-8% HCP-1

o D-79 CR-107 CR-8% CR-8% HCP-1
Riser-20 D-80 CR-109 CR-8% CR-8% HCP-1
" D-81 CR-111 CR-8% CR-8% HCP-1

o D-82 CR-113 CR-0% CR-8% HCP-1

 

¥Although Heater H-CR-8 will be most important, the other heaters on the

radiator will have a significant effect on the temperatures of the thermo-

couples listed 1in this Table.
 

 

 

Approved by &§£?i2<éé;h¢¢yL 5F-19
v 9/9/65
TABLE 5F-3 (continued)
~Page 4 of 8
SCANNER TE HEATER CONTROLLER CONTROL

LOCATION POINT NUMBER NUMBER NUMBER PANEL
Riser-20 D-83 CR-115 CR-8% CR-O% HCP-1
" D-8L CR-117 CR-8% CR-8% HCP-1

" D-85 CR-119 CR-8% CR-8% HCP-1
Riser-11 D-86, D-26 CR-1 CR-8% CR-8% HCP-1
" D-87, D-27 CR-3 CR-8% CR-8% HCP-1

" D-88, D-28 CR-5 CR-8% CR-8% HCP-1

n D-89, D-29 CR-T7 CR-8% CR-8% HCP-1

e D-90, D-30 CR-9 CR-8% CR-8% HCP-1

e D-91, D-31 CR-11 CR-8% CR-8% HCP-1
Risér-12 D-92, D-32 CR-13 CR-8% CR-8% HCP-1
o D-93, D-33 CR-15 CR-8% CR-8% HCP-1

" D-94, D-34 CR-17 CR-8% CR-8% HCP-1

" D-95, D-35 CR-19 CR-8% CR-&% HCP-1

”" D-96, D-36 CR-21 CR-8% CR-&% HCP-1

n D-97, D-37 CR-23 CR-8% CR-8% HCP-1
Riser-13 D-98, D-38 CR-25 CR-8% CR-8% HCP-1
m D-99, D-39 CR-27 CR-8% CR-8% HCP-1

nh D-100 Reference CR-8% CR-8% HCP-1
Riser-15 E-1, E-61 CR-52 CR-0% CR-8% HCP-1
" E-2, E-62 CR-54 CR-8% CR-8% HCP-1

e E-3, E-63 CR-56 CR-8% CR-8% HCP-1

' E-L4, E-64 CR-58 CR-8% CR-8% HCP-1

" E-5, E-65 CR-60 CR-8% CR-8% HCP-1
Riser-16 E-6, E-66 CR-62 CR-8% CR-&% HCP-1
m E-7, E-67 CR-6L CR-8% CR-8% HCP-1

e E-8, E-68 CR-66 CR-8¥% CR-8% HCP-1

" E-9, E-69 CR-68 CR-8% CR-B8% HCP-1

n E-10, E-70 CR-70 CR-8% CR-8% HCP-1

 

¥Although Heater H-CR-8 will be most important, the other heaters on the

radiator will have a significant effect on the temperatures of the thermo-

couples listed in this Table.
z

e

   
 

 

 

 

Approved by,fifififir fify&flg?) 5F-20
7 9/9/65
TABLE 5F-3 (continued)
Page 5 of 8
SCANNER TE HEATER CONTROLLER CONTROL

LOCATION POINT NUMBER NUMBER NUMBER PANFL
Riser-16 E-11, E-T1 CR-72 CR~8% CR-8% HCP-1
Riser-17 E-12, E-72 CR-Th CR-8% CR-8% HCP-1
o E-13, E-73 CR-T6 CR-8% CR-8% HCP-1

o E-14, E-Th CR-T8 CR-8% CR-O% HCP-1

n E-15, E-75 CR-80 CR-8% CR-8% HCP-1

m E-16, CR-82 CR-G#% CR-8% ACP-1.

e E-17 CR-8kL CR-8% CR-0% HCP-1
Riser-18 E-18 CR-86 CR-8% CR-5% HCP-1
o E-19 CR-88 CR-8% CR-8% HCP-1

" E-20 CR-90 CR-8% CR-8% HCP-1

n E-21 CR-92 CR-8% CR-8% HCP-1

e E-22 CR-9k CR-8% CR-8* HCP-1

e E-23 CR-96 CR-8% CR-8% HCP-1
Riser-19 E-2L CR-98 CR-8% CR-8% HCP-1
e E-25 CR-100 CR-8% CR-8% HCP-1
Riser-11 E-26, E-86 CR-2 CR-8% CR-8% HCP-1
e E-27, E-87 CR-4 CR-8% CR-8% HCP-1

e E-28, E-88 CR-6 CR-8% CR-8% HCP-1

n E-29, E-89 CR-8 CR-8% CR-8% HCP-1

n E-30, E-90 CR-10 CR-8% CR-8% HCP-1

e E-31, E-91 CR-12 CR-8% CR-8% HCP-1
Riser-12 E-32, E-92 CR-1kL CR-8% CR-8% HCP-1
e E-33, E-93 CR-16 CR-8% CR-8% HCP-1

n E-34, E-OL CR-18 CR-8% CR-8% HCP-1

n E-35, E-95 CR-20 CR-8% CR-8% HCP-1

" E-36, E-96 CR-22 CR-8% CR-G% HCP-1

' E-37, E-O7 CR-24 CR-&% CR-8% HCP-1

 

"Although Heater H-CR-8 will be most important, the other heaters on the

radiator will have a significant effect on the temperatures of the thermo-

couples listed in this Table.
Approved by Aaff?i}é?%E7Lq»@,yq S5F-21

9/9/65

TABLE 5F-3 (continued)

 

 

Page 6 of 8
SCANNER TE HEATER CONTROLLER CONTROL
LOCATION POLNT NUMBER NUMBER NUMBER PANEL
Riser-13 E-38, E-98 CR-26 CR-8% CR-8% HCP-1
n E-39, E-99 CR-28 CR-O% CR-8*% HCP-1
n E-40, CR-30 CR-8% CR-8% HCP-1
nh E-41, E-51 CR-32 CR-8#% CR-8% HCP-1
! E-42, E-52 CR-3k CR-8% CR-8% HCP-1
" E-43, E-53 CR-36 CR-8% CR-8% HCP-1
Riser-1k E-4k, E-5k CR-38 CR-8% CR-8% HCP-1
n E-45, E-55 CR-LO CR-8* CR-8%* HCP-1
' E-L6, E-56 CR-42 CR-8% CR-8% HCP-1
"o E-L7, E-57 CR-44 CR-8% CR-8% HCP-1
A E-L3, E-58 CR-46 CR-8% CR-8% HCP-1
m E-49, E-59 CR-48 CR-8% CR-8% HCP-1
Riser-15 E-50, E-60 CR-50 CR-8% CR-8% HCP-1
Riser-13 E-51, E-L1 CR-32 CR-8% CR-8% HCP-1
e E-52, E-L2 CR-34 CR-8% CR-8% HCP-1
" E-53, E-U43 CR-36 CR-8% CR-8% HCP-1
Riser-1lk E-5k, BE-kh CR-38 CR-8% CR-8% HCP-1
n E-55, E-L5 CR-LO CR-8% CR-8% HCP-1
n E-56, E-L6 CR-42 CR-8% CR-8% HCP-1
e E-57, E-LT CR~LL CR-8% CR-8% HCP-1
o E-58, E-48 CR-L46 CR-8% CR-8% HCP-1
" E-59, B-49 CR-48 CR-8% CR-8% HCP-1
Riser-15 E-60, E-50 CR-50 CR-8% CR-8*% HCP-1
m E-61, E-1 CR-52 CR-8% CR-8% HCP-1
m E-62, B-2 CR-54 CR-8% CR-S%* HCP-1
m E-63, E-3 CR-56 CR-8% CR-8% HCP-1
" E-6l, BE-b CR-58 CR-8% CR-8% HCP-1
" E-65, E-5 CR-60 CR-8% CR-8% HCP~1
Riser-16 E-66, E-6 CR-62 CR-8% CR-8% HCP-1

 

%¥Although Heater H-CR-8 will be most important, the other heaters on the
radiator will have a significant effect on the temperatures of the thermo-
couples listed in this Table.
Approved by A s 11 s e 5F-22

 

 

 

</ 9/9/65
TABLE 5F-3 (continued)
Page 7 of 8
SCANNER TE HEATER CONTROLLER CONTROL
LOCATION POINT NUMBER NUMBER NUMBER PANEL
Riser-16 E-67, E-T CR-64 CR-&% CR-8% HCP-1
mn E-68, E-8 CR-66 CR-8% CR-8% HCP-1
n E-69, E-9 CR-68 CR-8% CR-8% HCP-1
o E-70, E-10 CR-70 CR-8% CR-8% HCP-1
nh E-71, E-11 CR-T72 CR-8% CR-8% HCP-1
Riser-17 E-72, E-12 CR-T4 CR-&% CR-8¥% HCP-1
" E-73, E-13 CR-76 CR-8% CR-&% HCP-1
Y E-7k, E-14 CR-T78 CR-8*% CR-8% HCP-1
o E-75, E-15 CR-80 CR-&% CR-8% HCP-1
Riser-19 E-T76 CR-102 CR-8% CR-8% HCP-1
nn E-77 CR-104 CR-8% CR-8% HCP-1
' E-78 CR-106 CR-8% CR-8% HCP-1
m E-79 CR-108 CR-8% CR-8% HCP-1
Riser-20 E-80 CR-110 CR-8% CR-8% HCP-1
e E-81 CR-112 CR-8% CR-8% HCP-1
n E-82 CR-114 CR-8% CR-8% HCP-1
o E-83 CR-116 CR-&% CR-8% HCP-1
i E-84 CR-118 CR-8% CR-8% HCP-1
! E-85 CR-120 CR-8% CR-8% HCP-1
Riser-11 E-86, E-26 CR-2 CR-8% CR-8% HCP-1
" E-87, E-27 CR-k CR-8% CR-8% HCP-1
' E-88, E-28 CR-6 CR-8% CR-G¥% HCP-1
n E-89, E-29 CR-8 CR-8% CR-8% HCP-1
" E-90, E-30 CR-10 CR-8% CR-8% HCP-1
" E-91, E-31 CR-12 CR-8% CR-8% HCP-1.
Riser-12 E-92, E-32 CR-14 CR-8% CR-8% HCP-1
" E-93, E-33 CR-16 CR-8% CR-8% HCP-1

 

*Although Heater H-CR-8 will be most important, the other heaters on the
radiator will have a significant effect on the temperatures of the thermo-

couples listed in this Table.
‘ 9/9/65

TABLE 5F-3 (continued)

 

 

Page 8 of 8
SCANNER TR HEATER CONTROLLER CONTROL
LOCATION POLNT NUMBER NUMBER NUMBER PANEL

Riser-12 E-Ok, E-34 CR-18 CR-8% CR-8% HCP-1
e E-95, E-35 CR-20 CR-8% CR-8% HCP-1
o E-96, E-36 CR-22 CR-8% CR-8% HCP-1
' E-97, E-37 CR-2k CR-8% CR-8% HCP-1
Riser-13 E-O8, E-38 CR-26 CR-8% CR-8% HCP-1
e E-99, E-39 CR-28 CR-8% CR-8% HCP-1
' E-100 Reference CR-8% CR-8% HCP-1

 

*¥Although Heater H-CR-8 will be most important, the other heaters on the
radiator will have a significant effect on the temperatures of the thermo-

couples listed in this Table.
 

 

Approved by'égféizz%gfééfififlarfih SF-2L
9/9/65
TABLE S5F-k
THERMOCCOUPLES AND HEATERS
HEATUP OF THE COOLAggRSYSTEM FLOW VENTURI

TR-3400 TE HEATER CONTROLLER CONTROL
LOCATION POINT NUMBER WUMBER NUMBER PANEL
Stem 1 FT-201A-1A *
Body 2 FT-201A-2A FT-201A-1 FT-201A-1 HCP-3
Body 3 FT-201A-3A FT-201A-2 FT-201A-2 HCP-3
Stem b FT-201A-LA * :
Body 5 FT-201A-5A FP-201A-3 FT-201A-3 HCP-3
Body 6 FT-201A-6A FT-201A-4 FI-201A-4 HCP-3 ’
Stem T FT-201B-1A * .
Body 8 FT-201B-24 FT-201B-1 FT-201B-1 HCP-3
Body 9 FT-201B-3A FT-201B-2 FT-201B-2 HCP-3
Stem 10 FT-201B-4A *
Body 11 FT-201B-5A FT-201B-3 FT-201B-3 HCP-3
Body 12 FT-201B-5A FT-201B-4 FT~201B-4 HCP-3

 

*The thermocouples located on the stem are heated by both H-201-13-1
(controller no. H-201-13) and the body heater nearest them.
Approved by‘ZE;EZ%nggjzvun\ oF-25
< 9/9/65

TABLE 5F-5

RECORD THE TEMPERATURE OF THE THERMOCCUPLES LISTED BELOW
AT THE
TEMPERATURES OF THE REACTOR VESSEL AS INDICATED.

IMPORTANT: The following data is taken at only two temperatures during
heatup, but the operator should continually check the penetration tempera-
tures (at least every 30 minutes).

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

REACTOR VESSEL
TEMPERATURE |
TE | THERMOCOUPLE HEATER
NUMBER 500°F | 1000°F g READOUT CONTROLLER

201-A9A | _Scanner "A" = Point 80 H-201-9
'201-BOA !  Scanner "A" % Point 81 H-201-14
201AS-ALA | Scanner "A" | Point 82 | H-201-1l
201-A10A Scanner "B Point 19 H-201-14 and 10
201-B10A Scanner "B" ! Point 20 | H-201-11

201 ~C10A Scanner "B" Point 21 E~-201-11
201-B11A Scanner "B" | Point 23 | H-201-11
EZOl-DllA Scanner "B" | Point 25 | H-201-11
201-12 “ Scanner "B" Point 26 H-201-12
EEOO—B9A Scanner "A" Point 56 H-200-1
izoo-AgA { Scanner "A" Point 55 H-200-16
|2004S-A1A | Scanner "A" | Point 54 | H-200-16 |
1200-B34A | Scanner "B" | Point 17 | H-200-15 and 16
200-A8A j Scanner "B" | Point 16 | H-200-15 :
200-C7B § Scanner "B" Point 1b H-200-1L4
200-ATA : Scanner "B" Point 12 H-200-14

200-6 i Scanner "B" | Point 11 | H-200-13

 

 

 

 

 
 

Approved by./.% MINC '
T

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

5F-26
9/9/65
TABLE 5F-6
FOR HEATUP OF SHORT SECTION OF LINE 106
NORMAL READOUT TEMPORARY READCUT
TR READOLT POINT RECORDER =~ POLINT
ElOS—lB Scanner "A" 95 !
103-14B TRA-35C0 15 |
TV-105-6B Noze |
1 106-53 TRA-35C0 16 i
: T -
TABLE 57-7 ]
DATA ON HEATUP OF LINE 106
Recommended Recording Fregquency - 1 hour ’
DATE ;
AND | |
INITIAL TIME TE-103~13 TE-103-14B ~ TE-FV-105-6 . TE-106-5B
i
l .

 

 

 

 

 

 

 

 

 

 

 
Approved by p 5G-1
8-13-65

5G PREPARE DRAIN TANK SYSTEMS FOR REACTOR STARTUP

Before starting to fill the fuel or coolant system, the gas valving
and freeze valves in the drain tank systems should be checked. All
Treeze valves in the fuel drain tank transfer lines will be deep frozen
during operation. Normally FD-1, FD-2, FFT and CDT will be maintained
at 1000 to 1200 degrees F, the equalizing valves (HCV-5ik, HCV-545 and
HCV-546) will be open, and the vent valves on the tanks (HCV-573, HCV-575
and HCV-577) will be closed.

Details of startup preparations are given below:

1 Blow Salt OCut of Transfer Lines as Follows:
NOTE: If transfer lines are known to be free of salt, proceed to step
5G-2.

Init. Date/Time

 

1.1 Vent FST to 15.7 psia (PR-608) through
HCV-692 and leave the valve open.
1.2 Close the following hand valves in the fuel

 

processing system:
V-6084
V-607A
V-609
V-610B
V-690B
1.3 Blank line 111 or have a charging can attached

 

and valved off.

1.4 Check to see that the salt in the transfer

 

lines is molten and FV-10L , FV-105
, FV-106 , IV
Fv-108 , FV-109 , FV-112
are frozen.
1.5 Thaw FV-110 and FV-111
1.6 Close PCV-60L.
1.7 Open V-610B to blow out lines 110 and 111

 

 

 
Approved byj;;%5§;%%%Z2%/}¢wm oG-z

1.7

1.8

1.9

8-13-65

Init. Date/Time

 

(continued)
by increasing PCV-604. PI-60L4 and PR-608
should be observed to determine when lines

are free of galt.

 

Close V-610A. Increase pressure on FST

~ 1/2 psi and freeze FV-110.

 

Vent FD-1 , I'D-2 , FET and

 

FST to less than 15 psia by opening
HCV-573 , HCV-5T75 HCV-5TT , and

 

HCV-692 . Leave these valves open.

1F FUEL HAS BEEN TRANSFERRED PRIOR TC STARTUP PROCEED AS

 

FOLLOWS :

1f flush salt has been transferred, use the

alternate plan below.

1.10

1.11
1.12

1.16
1.17

Thaw FV-108 or 109 to allow the salt to be
blown from the lines to the tank containing
fuel salt (i.e. FD-1 or FD-2).

 

Close PCV-60lk,

 

Open V-610B to blow out line 108 or 109
by inecreasing PCV-60L.

 

Close HV-610B. Increase pressure on FD-1
or FD-2 ~ 1/2 psi and freeze FV-108 or 109.

Jumpers approved

 

Thaw freeze valve to other drain tank

(FV-109 or 108).

 

Repeat steps 1.11 through 1.1h.

 

 

Open V-610B and adjust PCV-60L
to blow out line 107. PI-604 and FFT
pressure (PI-576B) should be observed to

determine when the line 1s free of salt.

 

Close V-610A and B. Increase pressure on

FIT ~ 1/2 psi and freeze FV-107.

 
Approved by % ' L oG-3
8-13-65

Init. Date/Time

 

1.19 Pressurize through V-610 to determine that

FV's are frozen.

 

1.20 Freeze FV-111l.
IF FLUSH SALT HAS BEEN TRANSFERRED PRIOR TO THE STARTUP,-
USE THE ALTERNATE PROCEDURE GIVEN BELOW:

1.10

1.11
1.12

1.1h
1.15

1.19
1.20

 

Alternate: Thaw FV-107 to allow salt to be
blown from the lines to the fuel flush tank.
Alternate: Close PCV-60L.

 

 

Alternate: Open V-610B and adjust PCV-60L
to blow out line 107. PI-604 and FET
pressure (PR-576B) should be observed to
determine when the line is free of salt.
Alternate: Close V-610B. Increase FFT
pressure o~ 1/2 psi and freeze FV-107.
Jumpers approved .

Alternate; Thaw FV-108.

AMternate: Close PCV-60L..

Alternate: Open V-610B and adjust PCV-60L
to blow out line 108. PI-60L4 and PR-574B

 

 

 

should be observed to determine when the

line is free of salt.

 

Alternate: Cloge V-610B. Increase FD-2

pressure ~ 1/2 psi and freeze FV-108.
Jumpers approved

Alternate: Thaw FV-109.

Alternate: Close PCV-60L.

 

 

 

Mternate: Open V-610B to adjust PCV-60L

to blow out line 109. PI-604 and PR-572B
should be observed to determine when the line
is free of salt.

Alternate: (lose V-610A and B. Increase

 

pressure on FD-1 ~ 1/2 psi and freeze FV-109.

Jumpers approved

 
Approved by ,fi%{fim . 50215;
-13-

Init. Date/Time

 

1.22 Alternate: Pressurize through line 610 to

test FV's are frozen.

 

1.23 Alternate: TIreeze FV-111.

 

2 Deep freeze the transfer freeze valves and lines.
Switch FV-1C7, 108, 109, 110, 111, 112 to freeze.
Turn off all heaters that are given in Tables 11A
1 to L.

 

3 Check to see that FD-1, FD-z2, FFT and CDT are at
1000 to 1200 degrees F and that the TE's given in

Tables 5C 1, 2, 3 and 4 are being scanned.

 

L The thermocouples in Table 5GL monitor portions of
the lines which are filled with salt during operation
and also are needed to drain the fuel or coolant
systems. Do not allow these to cool below 950
degrees F at any time during operation. Check that
the thermocouples are plugged into the readout
instrument listed. The bypass switch on TRA 3500
should be tagged open.

 

5 The fuel storage tank may bte cooled and put into
deep freeze condition (i.e., all heaters off) or
it may be heated. FIFV-110 and 112 should ve frozen.
The lines between the tank and these freeze valves
should be maintained at approximately the same
temperature as the tank. If the tank is to be
heated the thermocouples listed in Table 11AZ

should be monitored.

 

6 Close or check closed helium supply valves HCV-572
s 5T, 576 ,end 511 . If
FST is not being used,close V-608B , 609B ,

and 690B . Indicate condition

 

T To prevent possible back diffusion of oxygen into
the salt, all vents on the tanks should be closed.
Close HCV-573  , 575 and 577 . If FST
is not belng used, close HCV-692.

—_—

 
 

8-13-65

Approved'byfiffié?gifiégPh¢¢n oG=-5

TABLE 5G-1
THERMOCOUPLE READOUT FOR DRALN LINES

 

 

TE TE Jack Panel Pyrocmeter Panel Instrument and
No. No. No. Point No.
204-1B 830 207 TR 3500-1
204k -2B 832 208 TR 3500-2
204 -3B 834 209 TR 3500-3
204-4B 836 210 TR 3500-4
204-5B 838 211 TR 3500-5
204 -6B 840 212 TR 3500-6
204-B7B 927 213 TR 3500-7
204-8B 8h2 21k TR 3500-8
206-1B 8L6 215 TR 3500-9
206-2B 848 216 TR 3500-10
206-3B 850 217 TR 3500-11
206-LB 852 218 TR 3500-12
206-5B 85k 219 TR 3500-13
206-6B 856 220 TR 3500-1k4
103-14B Loz 221 TR 3500-15
106-5B 420 222 TR 3500-16
FV-105-Ak 274 27 TR 3300-3
FV-105-Bk4 275 28 TR 3300-k
FV-106-Ak 286 29 TR 3300-5
FV-106-Bk 287 30 TR 3300-6
FV-204-Ak T13 42 TR 3300-18
FV-20L4-BL 714 43 TR 3300-19
FV-206-AL 723 Ly TR 3300-20

FV-206-BL 724 L5 TR 3300-21

 
- et

Approved by %fl 5H-1
7/29/65

5H ROUTINE PRESSURE TEST

The fuel'system will be periodically tested (approximately every
year) at 65 psig and 1200°F and after opening any system. The coolant
system will be tested at 65 psig and 1200°F. The test procedure is de-
signed to provide (1) a strength test of the reactor piping and equipment,
(2) a rough indication of any leakage from the reactor piping, and (3) an
operating check of préssure switches which are actuated during the course
of the test.

In order to thoroughly test the heat exchanger, the fuel system will
be pressurized to 65 psig with the coolant system at essentially atmos-
pheric pressure, and the cooclant system will be pressurized to 65 psig
after the fuel system is at atmospheric pressure. Since FD-1, FD-2, and
FFT will Dbe connected to the fuel system during operation, they will be
included in the test. The FST will not be included but will be tested
prior to any chemical processing. The CDT will be included when the
coolant system is tested. To avoild excessive pressure on the pump seals,
the lube oil systems will be pressurized. Valves will be closed in the
offgas lines upstream of the charcoal beds, thus isolating them from the
test. The fuel and coolant samples will be tested during the sampler
startup.

Prior to starting the test, the salt piping and equipment must be at
1200°F, the reactor and drain cell must be sealed and evacuvated to 12.7 psia.
To prevent transfer of salt, the necessary freeze valves will be frozen,
and the gas spaces of the various systems will be interconnected. The
test may be run with the systems empty or with coolant salt in the coolant
system and flush salt in the fuel system.

Details of the procedure are given below:

1. Check that all auxiliary systems startup operations listed in

Sections LA through 4T have been completed, or the Operations
Chief has approved items omitted.
Operations Chief's approval to proceed with system empty or

with salt circulating.

 

Date

 
Approved by, AP

Init.

5H-2
7/29/65
Date /Time

 

(Main Control Room)
2. Open the following valves to equalize pres-
sure between the fuel and FDT systems.
HCV-54L _ , HCV-545 _ , HCV-546 .

 

3. Open HCV-527 to equalize pressure between the
coolant system and the CDI system.

 

4, Close the following: PCV-517, ,
HCV-572 , HOV-57h , HCV-5T6 .

 

5. (Close V-605A and 605B8. Replace PCV-605 with
a PCV with at least 65 psig capacity and a
7O psig relief valve downstream of the PCV.

 

6. Set the new regulator at 40 psig and start
regulating through it.

 

(Water Room)
7. Remove cap from line upstream of PX-508 and
attach a helium cylinder with low-pressure

regulator. BSet the pressure at zero.

 

8. Close the following to prevent helium addition
to the coolant system,
(Transmitter Room)
vV-50h
V-595A
V-598A
(Coolant Drain Cell)
V=512
(Main Control Room)
HCV-511A
FCV-512

 

(Vent House)
9. Close HCV-547 and HCV-536 to prevent moisture

from OT-1 or 2 getting into coolant system.

 
1h.

 

 

 

 

Approved b My 5H-3
7/29/65
Init. Date/Time
’ 10. Close the following:
V-561 _ V-522V
V-534A _ V-535A
V-518A
(Special Equipment Room)
V-524A
) (Main Control Room)
11. Check that FV-103 is frozen.
If test is to be made with salt circulating
(See Step 1) it will be necessary to install
v clip lead jumpers around the following points:
. SC1C3 to SC1D3 and SC2E3 to SC2F3., Permission
to insert Jumpers . This will
prevent emergency drain on high pump bowl
pressure (25 psig) from thawing FV-103.
12. Check that the following freeze valves are

deep Trozen.

FV-107 ___ FV-109
FV-108 _ TV-110
Fy-111
Fy-112

 

(Diesel House)

13.

Increase the back pressure on the rupture
disc in line 508 to 35 psig. It will be
necessary to increase the flow until the ex-

cess flow valve 508 closes.

 

Tncrease PCV-605 to 65 psig.

 

(North Electric Service Area)

15.

If the test is to be made with salt circu-

lating (See approval at step 1) check that FP

 

is on and coolant pump is off.

Approval to insert prefill jumper in ECC-1L47.

 
Approved b%

NOTE:

NOTE:

16. Start adding helium to the fuel system at
maximum rate through ILine 519 and the fuel
bubblers. Set 5-36 on Position 2. Open
V-592, 593, 596, 589, 599, and 600 A and B.

Do not allow PI-500M to drop below 30 psig.
Throttle HV-519A if necessary. Keep OT-1 less
than fuel system (within 5 psig), keep the fuel
system pressure (PRC-522), and the drain tank
pressures (PR 572, 574, and 576) within 5 psi of
each other. WNeither coolant pressure (PR-528)
nor FST pressure (PR-608) should increase. It
may be necessary to close V-510A to keep OT-2
from pressurizing.

17. Record alarms and control actions that occur
as indicated in Table 5H-1.

When pressure gets to 45 psig stop pressurizing
and put a 20 psig back pressure on PT-522. This
will give PR-522 a range of 20-70 psig. Tag
PR-522 with Caution Tag. This will also feed a
false signal to all 522 Pressure switches. How-
ever action of all switches should have been
checked in Table LH-1 before 45 psig is reached.
Do not check further switch action until back
pressure is removed.

18. When pressure reaches 63-65 psig, in all

systems, close off helium supply. Close

 

 

V'519A -3 V=-502A —_— V‘593A 3
V-596A _ , V-589A » V-B99A
and V-600A

(If necessary to vent V=561 or V-522B will

need to be opened.)

SH-L

7/29/65

Init.

Date/Time

 

 

 
Approved by MAN_

Date/Time

 

 

 

 

 

 

Init.
19, Record time and pressures at 5-min intervals
as follows:
*¥PI-T01
INTERVAL | TIME PR-522 PI-500M or INITIAL
PI-T702
START
5 min
10 min
15 min

 

 

 

 

 

 

 

*
Record Discharge pressure of pump which is not in
service.

 

 

20. Data is satisfactory. Shift Supervisor's

initials:

 

21. Lower the pressure in the fuel system; set
valves as follows:
(Vent House)
V-561 Tag open
V-522B Tag open
(Special Equipment Room)
V-524A Tag open
Throttle V-535A to keep OT-1 pressure 5 psig
Jless than fuel system.
NOTE: Keep pressure on OT-1, fuel system (PR-522),
and FDT system (PR-572, 57k, and 576) within 5 psi
of each other. When pressure gets to 45 psig
remove the back pressure from PR-522. This should
cause 522 pressure switches to go into alarm

condition.
Approved b&’”‘”’l

NOTE :

22,

23.

2,

25.

Init.

As pressure decreases from this point on,
record alarms and control actions that occur

as indicated in Table 5H-1. When 20 psig

is reached remove jumpers if they were inserted

in step 11.

5H-6
7/29/65
De.te/Time

 

When fuel system reaches 5 psig stop venting
fuel system. Close operational and mainte-
nance valves at sampler, and lower '1C"
pressure to O psig. Turn off permissive

switch in control room.

 

If the tesgt is to be made with salt circu-
lating (see approval at step 1) turn the FP
off and start the CP.

 

Close Valve 560B, start pressurizing coolant
system at maximum rate through PCV-511,
FCV-512, and the coolant bubblers. ©Set 5-39
to Position 2. Open V-594, V-595, and V-598A
and B, and V-512.

 

Do not allow PI-500M to drop below 30 psig.
Throttle FCV-512 and HCV-511B if necessary. Keep
OT-2 pressure, coolant system pressure (PRC-528),
and the coolant drain tank pressure (PR-511D)

within 5 psi of each other.

26,

27,

Record alarms and control actions that occur

as indicated in Table 5H-2.

 

When coolant system pressure gets to 30 psig,
HCV-511 will close due to action of PS5-511DI1.
After this action has been verified, have
instrument mechanic increase gcetting on this
pressure switch. This will reopen HCV-511.
Continue adding helium until pressure

reaches approximately L0 psig.

 
S5H-T
7/29/65
Init, Date/Time

Approved by A

 

28. When LO psig is reached, FCV-512 should close.
At this point stop adding pressure and put a
back pressure of 30 psig on PT-528. This
will give PR-528 a range of 30-80 psig and
allow the system pressure to be monitered all
the way to 65 psig. Attach caution tag to
PR-528. DNote that all 528 pressure switches
will see a false sighal and no actions need
be recorded until the back pressure is re-
moved from PT-528. Instrument mechanic may
need to continue increasing set point on

P55-511D1 to allow flow through HCV-511.

 

29. When coolant system pressure reaches 65 psig,
close off helium supply. Close PCV-511 ,
FCV-512 _, V-512 __ , V-59hA
V-59SA _ , V-598A .

(Do not overpressurize due to heatup of

helium., If necessary to vent, use V-560B.)

 

30. Record PR-528 at 5-min intervals for

 

15 minutes.

 

*
Clock PI-T751 Initials

 

 

 

 

Interval . PR-528
Time or
PT-752
Start
5 min
10 min
15 min

 

* - -
Record discharge pressure of pump which is not
in service.

31. Data is satisfactory. ©Shift supervisor's initials.

 
Approved by P

(Vent House)

32.

33

3k,

32,

36,
37.

38.

39.

Lo,

Start lowering the coolant system pressures
by opening V~560B (Tag open). Keep pressure
on 0T-2, coolant system (PR-528) and CDT
(PR-511D) within 5 psig of each other.
Throttle through V-535A to lower OT-2
pressure.

As coolant system pressure is lowered, lower
the setting on PSS-511D1 until 40 psig is
reached. Reset the pressure switch at 40O
psig by alternately raising and lowering the
pressure in the coolant system until a

40 psig setting is obtained.

When pressure gets to L0 psig, remove back
pressure from PT-528.

Receord alarms and control actions which occur
as indicated in Table 5H-2 until 5 psig is
reached.,

Start CP and remove jumper in ECC-147.

Lower setpoint on PCV-605 to 40 psig as indi-
cated by PI-S500M.

Remove helium cylinder from PA-508 and rein-
stall PX-508. (Check PX-508 and XA-4028-6
before reinstalling.)

Replace PCV-605 with original PCV and put
spare parts in spare parts cabinet.

Open bubbler valves, A and B.

V-589 ____, V=593 ____, V-598 ;
V-592 5 V-59k ____, V-599 ____ _,
vV-595 __ , V=600 __ , V-596 __ .

5H-8
T/29/65
Tnit. Date/Time

 

 

 

 

 

 

 

 

 

 
Approved by(%/ E?{”‘fl'\ >H-9
7/29/65

41,

L2,

Tnit. Date/Time
Check that V-53LA and V-535A have been

opened.

 

Reset pressures and flows in all systems to
values which are compatible to the present

situation.

 
Table S5H.1 FUBL SYSTEM ANNUNCIATIONS AND

CONTROL ACTIONS

 

TNDICATTON OR OPERATOR CHECK POTNTT

 

 

CAUSE CIRCUTIT ACTION AND AFFECTED CIRCUIT PRESSURE TNCREASTNG PRESSURE DECREASTNG
Fuel Pump >2 psig 20 Open HCV 5hk, 545, Sh6. Close PCV 517, HCV 572, 57h, 576  In Circuit 20 light on Jumper Board off __ _ Light on
Overflow Tenk >2 psig 21 Circuit 131, 132, 133, 127, 115, and 116 Tn Circuit 21 light on Jumper Board off ___ Light on
FD 1 »5 psig 89 Closes HCV 572, FV 109 permissive off, Circuit 115, A-T20 In Circ. 115 light FD 1 Press. Light off _ Light on
FD 2 »5 Dpsig 90 Close 2 of 3 HCV 57k, FV 108 permissive off In Circ. 115 light FD 2 Press. Light off__  Light on
Circuit 115, A 709
FFT > psig g1 Close 2 of 3 FV 107 permissive off, Circuit 115, A-698 Tn Cire. 115 light FPT Press. Light off ___  Light on
FDT 1 >30 psig 109 Close HCV 572, Open HCV 573, In Cire. 117 FD1 Press. light off Light on
Circuit 115, 117 In Cire. 115 FD1 Press. light off
FD 2 >30 psig 110 Close HCOV 57&4. Open HCV 575 Tn Circe. 118 FD 2 Press. light off Light on
Circuit 115, 118 In Cire. 115 FD 2 Press. light off Light on
FET >30 psig 111 Close HCV 576. Open HCV 577 In Cire. 119 FFT Press. light off Tight on
Circuit 115, 119 In Cire. 115 FFT Press. light off Light on
Fuel Pump >4O 129 Close FCV 516. Circuit 129 In Circ. 129 He Press. light off Light on
Hi Press RD-1508 AOR3 ¥Ah028-6 ~ 10 psi Common on MB-2 XA-4001-1  Alarm Audio and light on Ann. clear
Hi-Lo Fuel Pump Press. MB 8 XA-LO06-5 ~ 1 - 10 psi Alarm Andio and light on high Alarm lo
Hi-Lo OT-1 Press. MB 10 XA-L4008-L4 ~ 5 - 15 psi Marm Audio and light on high Aarm lo
Hi FD 1 Press MB 11 XA bL00g-2 25 psig Alarm fndio and light on High Amn. Clear
Hi ¥D 2 Press MB 11 XA %009-1 25 psig Alarm Audio and light on high Ann. Clear
Hi FFF Press. MB 11 XA 4009-3 25 psig Alarm Audioc and light on high Ann. Clear
Cover Cas Pressure MB 11 XA 4009-6 Common - from Aux. Bd. 3 XA 4028 Alarm Audio and light on high Ann. Clear
Lo He Treated Pressure AB-3 XA 4028-4 (100 psig) Alarm Audio and light on
Ei Lo He Pressure AB-3 XA h028-5 (PA 500L) (30 - 41 psig) Alarm Audio and light on high
FP >25 psig 20 & 23 Cause Emergency Drain, opens HCV 533 Al Tn eircuits 22 & 23 light on, Ann. Clear
Jumper board off
L Where possible, record pressure at which action oceurs. Increasing Decreasing
Sampler Common
P3-1C-E 35 psia ALARM CLEAR
Pas-10-3 Press in 1C >3A (AP = 1 psig) ALARM CLEAR
« e

1
T
R
O
2
D)
o
o'
<

Go/62/L
OT-HS

 
Table 5H.2 COQLANT SYSTEM ANNUNCIATOR AND CONTROIL ACTION

 

CFERATOR CHECK1

 

CAUSE CIRCUTT CONTROL ACTTON
PRESSURE INCREASTING PRESSURE DECREASING
CDT >30 psig 107 Open HCV sht In Circuit 121, CDT Press. light off In Circuit 121 CDT Press. light on
Close HCV 511 Tn Circuit 126 CDT Press. light off In Circuit 126 CDT Press. light on
CP >L0 psig 128 Close FCV 512 In Circuit 128 He Supply light off In Circuit 128 He Supply Light on

CP Hi-Io Press.
Ann.

CDT-Hi Press

Ann,

* When possible

FCY 512 closed
XA LOO5-2  Hi alarm 10 psi  Annunciation
Lo alarm 2 psi
MB6
XA 40OL-6  Hi alarm 25 psi  Annunciation
Io alarm 1 psi
MBS

record pressure at which action occurs.

FCV may open, operator should close

Annunciation

No snnunciation

>
g
g
R
Q
<
@®
ol
o
e

 

co/6z/L
TT-HSG
5I-1
10/1/65

 

51 FILLING THE FUEL AND COOLANT SYSTEMS

When the coclant system temperatures reach 1000 to llOOOF, it will
be filled with salt, the freeze valves will be frozen, and circulation
of coolant salt will be started. When the fuel and coolant system
temperatures reach 1150 to lZOOOF and the graphite temperatures are
above llOOOF, the fuel system will be filled with either flush salt or
fuel salt depending on condition of the system. t is estimated that
heatup should take about 36 hours which is sufficient time to heat up
the graphite. The outlet gas temperature is essentially the same as the
top graphite temperature and therefore could be a good indication of
graphite heatup rate. However, the installed thermocouples will probably
be affected more by the heater temperatures than by the gas temperature
in the system.

After the fuel system has been filled with flush salt, FV-103 will
be frozen, the reactor access nozzle freeze joint will be established,
and the fuel pump will be started. The flush salt will be circulated
for at least two hours and sampled prior to draining to the fuel flush
tank.

The fuel system will then be filled with fuel salt. The filling
will be done with all three control rods withdrawn to the prefill
elevation. The reactor will be filled in several steps, with sufficient
time delay between steps for neutron multiplication to be determined.
If'criticality appears feasible, filling will be discontinued.

When the proper level is reached in the pump bowl, FV-103 will be
frozen and the fuel pump started.

Details of the operations are given below:

1 FILLING THE COOLANT SYSTEM

(Main Control Room)

 

Init. Date/Time

 

1.1 When coclant system temperatures are above
1000°F, stop the coolant pump.
1.2 Check that the coolant drain tank salt

o
temperatures are between 1100 and 1200 F.

 

 
 Z
Approved by ;5:;§Eé;fi74:;4%%fflx\_ 51-2

10/4/65

Init. Date/Time

 

1.3 Adjust the CDI wt. alarm to annunciate when
1500 1b of salt have been transferred to the

coolant system.

 

NOTE: ©Step 2.1 can be done simultaneously with Steps
1.4 and 1.5 in preparation for adding flush salt to the

fuel system.
(Heater Control Panel)

1.4 With FV-204 and 206 in the freeze position,
heat up the shoulders to approximate operating
temperatures with heater settings as listed
in the building log. The heaters are con-
trolled by FV 204-1 and FV 20k-1A on HCP-2,

FV 206-1 and FV 206-1A on HCP-3. Temperatures

of TE FV 204-A4 and FV 204-B4t are recorded on
TRA 3300-18 and 19. Temperatures of TE FV 206-Ak
and FV 206-B4 are recorded on TRA 3300-20 and

21.

1.5 When FV-204 and 206 shoulder temperatures
have been adjusted, plug TE FV 204-5B into

Scanner ¢, Point 95.

 

 

1.6 Put coolant pump bubbler level instrument in
service as follows:
(Main Control Room)
1.6.1 Set selector switch (S-39) on Position
2 which is "Record LT-598, Bubbler No. 1,

and No. 2 on."

 

(Transmitter Room)
1.6.2 Check that test switch (8-40) is in
the "Off" position.
1.6.3 Open the following:
V-59hA
V-295A
V-5984

 

 
Approved by./zégz:zzkgé%gé/fiaifl\g 5I-3

1.7

10/ /65

Init. Date/Time

 

1.6.4 Adjust V-594B, V-595B, and V-598B so
that the following read 25 psig.

FI-sok

FI1-595 __

FI-598
Record CDT weight: on salt inventory and
transfer date sheet Table 12B-5. Attach
sheet to this procedure and identify data

 

per step number of this procedure.

 

(Main Control Room)

1.8
1.9

1.10

1.11
1.12

1.13

1.14

Set FCV-512 on auto at 0.6 1/m.
Thaw FV-204 and FV-206 and adjust FV heaters
to control TE 204-Ak, 20L-BL, 206-Ak, and
206-Bl at 1200 to 1225°F.
Set valves as follows:

Equalizer HCV-527 closed

CDT vent HCV-547 closed

CP vent HCV-536 open

CDT supply HCV-511A closed
Set PIC-511C on auto at 27 psig .
Stop the coolant pump (CP).
Adjust HIC-511B to approximately SO% and open
HCV-511A to begin filling coolant system.

 

 

 

 

Note coolant system calibration and dc not
stop £il1l at FF-200 or FF-201 (reasons of ther-
mal stress).

As system is filled, record WRCDT when the

 

upper tank probe light goes off and
when lower probe light goes off

Note time when salt Tfills FF-200. This will
be after approximately 1500 lbs. of salt have

 

been transferred. Reset CDT wt. alarm
to annunciate when 4800 1lbs. have been trans-

ferred to the coolant system.

 
'l
Approved by W%M@
v \

NOTE: The following components will be filled after
transfer of the following amounts of coolant salt
(approximate) (See coolant system calibration.) HX
~ 1200 1bs, CR ~ L4500 1bs entering CP at ~ L7700 1bs,
CP full at ~ 5300 lbs.

1.15 The desired operating level in the coolant
pump is 58% % 2% at 1060°F. To compensate
for level changes caused by trapped gas,
£11ling of pump internals and temperature
changes, estimate the initial fill level

as follows: {See also coolant pump levels

vs salt temperature in calibration note book.)

1.15.1 Desired operating level at

1060°F. +58%
1.15.2 Coolant system trapped gas

pocket (Consider if not previocusly

swept out.). + 9%
1.15.3 Filling internals of CP. + 49
1.15.4 Change in level due to

difference between average salt

temperature and 1060°F equals

0.07 x average salt temperature

(°F) - 1060°F) + 4
1.15.5 Desired fill level, CP off

(Total of items above. Note

correct sign on item 1.15.L4.) %

NOTE: Average salt temperature after fill (Estimate

from Scenner B.) must be between ~ 1000 and ~ 1140O°F.

5T -
10/4/65

Init. Date/Time

 

 

1.16 When desired level in coolant pump is approached,

close HCV-511A. Note that there may be coast
up of level cf from 4% 4o 6% on LR-595 after

BCV-511A is closed.

1.17 Record the following when desired level 1s

 
1.17

1.18

1020

 

oI-5
10/4/65

 

Init. Date/Time

 

(continued)

reached:
PR-511
PR-528
LR-595
WR CDT
Freeze FV-204 and FV-206 and record LR-595

 

 

 

 

Test TV's by venting CIDT about 1 psi. Open
HCV-547 momentarily while observing LR-595.
If level drops below minimum start level,

readjust level and refreeze.

 

After allowing ~ 1 hour for temperatures
to reach equilibrium, check the thaw time
of FV-204 and 206 as follows or obtain the

operations chief permission to omit the

 

 

test
1.20.1 Record the following temperatures
TE FV 204-1B  TE FV 206-1B __
TE FV 204-2B __ TE FV 206-2B
TE FV 204-3B  TE FV 206-3B
TE FV 204-AL  TE FV 206-A4
TE FV 20L-Blk _ TE FV 206-Bk
1.20.2 Record air loading to HCV-906
(TIC 906-A2)  and to HCV-907
(TIC 907-A2) .

 

1.20.3 Simultaneously turn off heaters
FV-204k-1, 20Lk-1A, 206-1, and 206-1A and
switch FV-204 and 206 to thaw. Record

time

 

1.20.4 Note time when the freeze valves thaw.
FV-20L FV-206

 

* NOTE: The CP level will decrease when the first FV thaws.
Approved by _.;

  

7 10/4/65

Init. Date/Time

 

Temperatures will be used to determine when the other

FV thaws.

l.Zl

1l.22

1.23

1.20.5 If thew time of either valve is longer
than 15 minutes, refreeze, adjust FV tem-
peratures and retest. See that new valves
of heater settings are added to building
log.

1.20.6 Refill and refreeze per steps 1.15 to
1.19.

 

 

Close HCV-536 and adjust coolant pump pres-
sure (PR-528) to 5 psig. Record LR-595

 

 

To lessen thermal stresses in FF-200 and
201, wait until 3 hours after Step 1.1k
before starting CP. While observing the
pump motor speed, amps, and watts, as well
as coolant salt flow meter FR-201 and loop
temperstures; start coolant pump (CP).
Check the CP level with salt circulating to
see that it i1s within limits of Step 1.15.
The calculated level at 1060°F should be
between 56 and 60.5% level at 1060°F =
IR-595 - .07 (% - 1060°F) where; LR-595

is present level in %, T is present

temperature of coolant salt. If not with-

in above limits, refill as follows:

1.23.1 Open HCV-536 CP vent.

1.23.2 Check that the AP (PR-511-PRC-528)
is less than at Step 1.17. (Vent CDT
slightly through HCV-547.) Record:

PR-511
PRC-528

1.23.3 While observing pump bowl level and

CDT wt., thaw FV-206.

 

 
1.24

1.25

Approved by ‘% /Z}é7
10/L /65

Init. Date/Time

 

1.23.4 Estimate new fill level according
to information in Step 1.15 except that
1.15.2 is disregarded. Fill level should
be %.

1.23.5 Readjust level by throttling HCV-511B
and opening HCV-511A to refill to above
level. Close HCV-511A

1.23.6 Record the following:

PR-511
PRC-528
LR-595 ___
WR-CDIC

1.23.7 Refreeze FV-206 and record LR-595

1.23.8 Test the FV's by venting the CIDT
and. observing LR-595.

1.23.9 Close HCV-536 and adjust the coolant

 

 

 

 

 

 

pump pressure (PRC-528) to 5 psig. Record
IR-595 ____ .

1.23.10 While observing the pump motor speed
(SICPG) amps (EiICPD) and watts (EwICPD)
as well as the coolant salt flow (FE-201)

 

and the loop temperatures; start the
coolant pump. Recheck the CP level. It
should be between 56 and 60.5% at 1060°F.
Level at 1060° = LR-595 - .07 (T - 1060°F)
where: ILR-595 = present level in %, T

I

= present temperature of coolant salt.

 

When the level is within limits with the pump
running, vent the CDT through HCV-547 to 5
psig.

Close HCV-547 and open HCV-527 to connect the
CDT to the coolant system. With this arrange-
ment, thawing FV-204 and 206 is all that is

 

necessary to drain the coolant system.

 
Approved byfiggfifigkfi

1.26

ey

  

o
7 5I1-8
fl/m 10/4/65

Init. Date/Time

 

Record the following:

IR-595
WRCIT

 

(Transmitter Room)

1.27

1.28

1.29

2 FILL
2.1

2.2

Record CDT inventory on salt inventory and
transfer data sheet Table 12B-5 attached.

 

If necessary, adjust the heaters to maintain
1175°F in the coolant system. Using the
heater calibration curves as a gulde, adjust
each heater by approximately the same %
change in current to avoid overheating any

one hesater.

 

Within cne hour after starting the CL sample

the coolant salt according to Procedure

6B3 and enter into salt sample log.

FUEL SYSTEM WITH FLUSH SALT

Set FV-104 in the freeze position, set HIC 908-AZ
at ~ 5 (Check building log.), and heat up the

shoulders to approximate operating temperature

 

with htr settings as listed on the building

log. The heaters are controlled by FV-104-1,
FV-104-14 on HCP-9. Temperatures of TE FV 104-Ak
and TE FV 10L-Bi are recorded on TRA 3300-1

and 2.

 

Set valves as follows:
FFT Vent HCV-577 closed
FFT Eg. HCV-546 open
FP Vent HCV-533 open
FFT gupply HCV-576 closed
FDI Eqg. HCV-544* open
FD2 Eq. HCV-5L45% open
Set PIC-51T7A on auto at 21 psig.

 

¥These can be left closed if conditions in

the tanks so dictate.
Approved by 2

2.3

2.4

2.5

2.6

2.7

2.8

51-9
10/4/65

 

 

Init. Date/Time

 

When the graphite temperatures are estimated
to be above 1100°F and all other fuel system
temperatures are above ll5OOF, switch drain
tank selected to FFT, start thawing FV-103
and FV-10k, and prepare for filling the fuel
system with flush salt.

 

Check that all the neutron instruments are in
service and that BFs chamber confidence contact
in circuit 174 has been satisfied. Observe

BF5 and other neutron instruments during the
£111. |

Check that all three control rods are at 24

 

inches.

Check that the FFT temperatures are all above
ll5OOF.

Check that FV-105, 106, 107, 108, 109, 110,
111, and 112 are deep frozen. This is to

 

 

prevent inadvertant transfer between tanks
or mixing of the fuel and flush salt through
the fill lines.

 

Set the FIT weight alarm to annunciate when
~ 9000 1lbs. have been transferred to the fuel

system.

 

Put fuel pump bubblers level instruments in

service as follows:

2.9.1 B8et the selector switch (8-36) on
Position 2 which is "Record LT-596 -
Bubbler No. 1 and No. 2 on."

 

(Transmitter Room)

2.9.2 Check that test switch (S8-37) is in
the "Off" position.
2.9.3 Open the following:

 
Approved by ,;fifi?fiézzéfigfifwwfin 5I-10

10/4/65

Tnit. Date/Time

 

2.9.3 (continued)
V-59z2A
V-5934
V-596A

2.9.4  Adjust V-592B, V-593B, and V-596B

so that the following read 25 psig:
FI-592
Fi-593 _
FI-5% ____
2.10 Put the overflow tank bubbler level instru-

 

 

ment in service as follows:
2.10.1 Check that the test switch (5-38) is
in the "Off" position.
2.10.2 Open the following:
V-589A
V-599A
V-600A
2.10.3 Adjust V-589B, V-599B and V-600 so that
the following read 2z5 psig:
FI-589A
FI-599A
FI-600A
2.10.4 Check that the OFT is empty as indi-
cated by LI-589 and LI-600.
(Main Control Room)
2.11 When FV-104 is thawed, push operate mode button.

 

 

 

 

Light will stay on. Adjust FV heaters to con-
trol temperatures to ~ lZOOOF.

 

2.12 Take a complete salt inventory (Check list
12B5.) attached.

 

2.13 When ready to begin fill, stop IFP, close
HCV-546, and open HCV-576.

 
Approved by /Zg;?zzé%%:;/‘%%”fl 5I-11

v * 10/4/65

Init. Date/Time,

 

NOTE: If a freeze joint is not already established on
the reactor neck it will be necessary to do so during
the filling with flush salt. To establish a freeze
Jjoint, cooling alr should be turned off at this time.
With shift supervisor's permission, close the following.
These should be left open if a freeze joint has already
been established.

(Transmitter Room)

HIC-961 _ inside 2" sample access (air
closes)

HIC-962 __ outside RAN (air closes)

HIC-963 _ inside RAN (air closes)

 

(Main Control Room)

2.14 As the system is filled, record WR-FFT when
the upper flush tank probe light goes off
and when the lower light goes off

NOTE: FE-517 will limit the flow to less than 22 scfh
with a 40 psi pressure drop. Filling of the fuel sys-

 

tem will take approximately 3 1/2 hours. Thermocouples
on piping and vessels may be helpful in following the
fill. Do not overfill the fuel pump. The fuel drain
tanks, fuel flush tank, and fuel storage tank weights
should be observed to assure that salt is not flowing
to them. The fission count rate should be observed to
be sure that fuel was not inadvertantly mixed with the
flush salt. The reactor neck flange temperatures TER-3k
and TER-35 should not exceed 4OO°F. Refer to fuel sys-
tem calibration curves to determine the pressure differ-
ential and/or welght of salt necessary to fill to various
elevations. Do not stop fill while salt is midway in
freeze flanges.

2.15 Determine the desgired FP fill level for nor-

mal operation at 59% % 3% as follows: Refer
 

Approved byféggfigi;é:;figé/¢‘yfiflv 5I-12

10/4/65

Init, Date/Time

 

2.15 (continued)
to the graph of "fuel system fill level"
in the calibration curve notebook. Estimate
the average salt temperature in the fuel
system from Scanner A _____?F. According
to the graph the desired fill level is
____%. Note that the fill salt temper-
sture should be between 1150°F and 1225°F.

2.16 As soon as LR-593 indicates salt has reached

 

FP bowl, turn on cooling air to FP shroud.
Adjust HIC-903A (TR) for 20 SCFM cooling
air as indicated on FI-903.

2.17 Note time that FF-101 is filled; ie when
level in FP reaches ~ 50% on LR-593.

 

 

2.18 Before desired level is reached, close
HCV-5T6. _ Allow for coast up of ~
5% on LR-593 after HCV-576 is closed.
NOTE: If salt inadvertantly overflows into the over-
flow tank, refer to Section OI.
2.19 Record the following:
(Main Control Room)
PR-5T6A
PRC-522
LR-593
WR-FEF'T

 

 

(Auxillary Control Room)
LI-599
LI-600
2.20 Freeze FV-103 and record LR-593 .

 

 

2.21 Test the freeze valve by venting FFI slightly.
Open HCV-577T momentarily while observing
LR-593. If the level drops too far according
to i1l level graph, readjust level and re-

freeze.

 
 

Approved by/zggfiigizigéé%yfl,fiffiux

5L-13
10/14/65

Init. Date/Time

2.22 If a freeze joint is to be established in the

reactor neck, proceed as follows; if not,

proceéd to Step 2.24,

2.22.1 Set PRC-522 at 15 psig.

2.22.2 Close HRC-533 and HCV-577.
2.22.3 Open HCV-54L, 545 and 546.

2.22.4 If the equilibrium pressure is less

 

 

than 10 psig, repressurize using PRC-522

or through line 510.

Set PRC-522 at the

final pressure (310 psig) and record

PRC-522

* 2.22.5 Open the following valves and establish

 

freeze joints. (This will take at least

30 minutes. )
HCV-962

HCV-961 HCV-963

(Main Control Room)

 

2.22.6 When frozen record the following tem-

. peratures:
TE R-TA
TE R-CA
TE R-9
TE R-10

A ey

TE R-33

T ——— e

TE R~34

TE R-44B

TE R-454

TH R-U6A

TE R-47

TE R-42A

TE R-43A

 

2.22.7 Reduce the pressure (PRC-522A) to 5

Set on auto at 5

psig using PCV-522.

psig.

 

2.23 When the fuel pump pressure (PRC-5224)

reaches 5 psig, record LR-593 .

 

2.24 If a freeze Joint does not need to be

established, proceed as follows.

* supervisor's permission

Shift

 
2
Approved bx,efi”52424§5(fl4’“ 5I-1k
- Vv

2

10/k/65

Init. Date/Time

 

2k.1 Vent FFT through HCV-577 to a pres-
sure such that when HCV-54L, 545, and
546 are opened, the equilibrium pres-

sure will be ~ 5 psig.

 

2.24.2 Close ECV-533 and 577.
2.24.3 Set PRC-522 at 5 psig.

2.

 

 

2.k Open HCV-5hh, 545 and 546.

 

2.25 Wait at least 2 hours after FF-101l was
filled with salt. Step 2.17 start

end
2.26 Fully insert all three control rods.

 

 

 

2.27 While observing the pump motor speed
(8I-FPE), amps (Eil-FPE), and watts
(EwI-FPE) as well as loop temperatures;

start the fuel pump.

 

NOTE: It is desirable to start the pump as soon as

possible to avoid freezing salt in a cold spot.

(Flectric Service Area)
2.28 Purge salt from line 103 as follows:

2.
2.

z

28.1 Check V-519A closed .
28.2 Push and hold in HS-519-A1

 

 

.28.3 Observe PI-519 (will be sub-

atmospheric if DT has been vented).

 

.28.4 Throttle open V-519A to introduce

small amount of helium into line 519.

Close to observe pressure on PI-519

 

 

.28.5 Repeat small additicns of helium and

observation of pressure changewith V-519A
closed. As soon as further additions fail
to show increagse in pressure, line 103

has blown through to the drain tank.

 

.28.6 Close V-510A . Release HS 519-Al

 

i t——
10/Lk/65

Approved by My%‘/ L 51-15

Init. Date/Time

 

2.29 Adjust heaters to maintain 11750F.
2.30 Take salt inventory {(Check list 12B5.).
2.31 Sample from FP (Check list 6A3) and make

 

 

entry in sample log.

 

3 DRALN OF FIUSH SALT

 

3.1

3.3

When flush salt operation is complete
(minimum of 2 hours of circulation) and
sample has been taken, check that FV-105,
106, 107, 108, 109, 110, 111, and 112 are
deep frozen, FV-104 is thawed, and drain
tank selector is to FFT position.

Teke a salt inventory - (Check list 12B5).
Check the thaw time of FV-103 as follows:

 

 

3.3.1 Record the following temperatures:
TE FV 103-13B
TE FV 103-2B
TE FV 103-3B
TE 102-5C (1170-="1180°F)
TE R-32 (1170 - 1180°F)
3.3.2 Record air loading to HCV-919 (TIC 919-42)

 

.

 

 

3.3.3 Simultaneously turn off reactor
heaters RL, R2, and R3, and switch the
fuel drain switch to drain. Record
time

3.3.4 Note time when FV-103 thaws

 

as indicated by FP level decrease.

 

3.3.5 If thaw time is longer than 15 minutes,
adjust FV temperatures, and retest.

3.3.6 Turn on heater RL, R2, and R3 at same
setting as 3.3.3.

 

 

NOTE: The bulk of the salt will drain in approximately

» 4O minutes. While the flush salt is draining, start
Approved by

heating FV-105 and 106 as given in 4.1 and 4.2 or
5.1 and 5.

3.4

3.2

3.6
3.7

3.8

3.9
3.10

 

Init.

51-16
10/4/65

Date/Time

 

2. Do not allow FV's to thaw.

 

When sait has left FP, turn off cooling air
to FP shroud with HIC-903.

 

When the bulk of the salt has drained, switch

fuel salt drain switen to "Off)

 

Open HCV-5TT.

 

Continue purging through FCV-516 and the
bubblers until all of the salt has been
blown down to the FIT as indicated by
WR-FFL~-C and by closing HCV-577 to note
pressure buildup in FFT.

 

When all salt has been drained, there will be
sufficient pressure on fuel gystem to bubble
through FEFT. Reduce fuel system thru HCV-533
by ~ 0.5 psi to position salt in FV-104.
Switch FV-104 1o freeze position.

Reduce HIC 908-A2 to zero.

——————
ree—————
S ——

(Heater Control Panel)

3.11

3.12
3.13
I FILL

Adjust heater controller FV-104-1 and FV-10L-1A
located on HCP-9 to deep freeze FV-104.

TE FV 104-AL and B4 should be maintained at
400 to 600°F.

Take a system inventory (Check list 12B5.).
Push prefill button, and start fuel pump.

 

FUEL SYSTEM WITH FUEL SALT FROM FD-1 (For

 

filling from FD-2, see Section 5.).

L.y

Check that heater H-106-4 iz on at normal
operation setting. Heatup Procedure S5F
calls Tor all drain line heaters being on,
with exception of the IV shoulders. Because
of the configuration of pipe and heaters in

this grea, this temperature is dependent also
Approved by

h.1

4.2

L.3

L4

oI-17
10/L4/65

 

 

Init. Date/Time

 

(continued)

upon FV-105 and FV-106 shoulder heaters. Note
that TS FV 105-6A (temperature at the "Tee"
must be above 9OOOF before valve can be thawed.
The temperature of the lower end of line 103
and the "tee" may be read out on special recorder.
See Procedure S5F, Step 2.6 and Table 5F-6 as
used for this heatup. As valve shoulders are
heated in the next step, check that temperature
gradient is such that the "Tee" reaches melting
temperature before the FV shoulders.

With FV-106 in the freeze position, heat up

 

FV-106 shoulders to approximate operating
temperatures with htr. settings as listed
in the building log. FV-105 and FV-104
will be kept in deep freeze above LOOCF.
FV-106 shoulder temperatures are controlled
by FV-106-1 and FV-106-1A on HCP-9 and
temperatures are indicated by TE FV 106-AhA
and TE FV 106-B4A on TR 3300-5 and 6. FV-10k4
and FV-105 will be kept in deep freeze but
above 4O0°F. While shoulder temperatures
are being adjusted, observe FV-106-5B on

TR 3300-24. Pot temperature must be up

to 900°F or value will not thaw.

 

When temperatures of line 103 and the "Tee"
are above low alarm setpcint of TR 3500,
connect TE's listed in Table 5F-6 of
Procedure 5F to their normal readout.

Check that FV-10k, FV-105, 107, 108, 109,
110, 111, and 112 are deep frozen. This

 

is to prevent inadvertant transfer between
tanks or mixing of the fuel and flush salt

through the fill lines.

 
Approved by (%

 

<

(Main Control Room)

4.5 Check that safety interlocks as follows:

4.5.1 Vent fuel system pressure by opening

4.5,

4.5,

k.5

L.o.

HCV-533.

2 As soon as lights go on in circuit

Add helium

20 and 21, close HCV-533-
pressure to fuel system via FCV-516

and bubblers. Note pressure on PI-589A

psig when light goes out in ckt. 21,

Note pressure on PIL-592 psig when

light goes out in ckt. zO.

3 Above pressures agree with switch

tabulation settings of PSS 589-A2
psig and PSS 592-B2 psig.

Open HCV-533

4 Prepare for thawing FV-106 by venting
fuel system and FD-1.

Open HCV-5T3 .

5 Check prefill rod position switches

in circuits 20 and 21 for each rod,and

record results in the table below.

pare results with switch tabulation.

Com-~

(BF= chamber confidence is required to

raise the rods.)

ZSS N RR1-Az
Z55 NCR 2-AZ

7SS NCR 3-A2

Raising rod lights
Z5S RR1-Al
73S CR2-A1l
7SS CR3-AL

Sw.

Tab.

 

 

5I-18
10/4/65

Init. Date/Time

 

 

 

 

 

 
. Approved by figflgggfi

    
 

7 et o1-19
</ lO/)-L/65

L : o+
—

Init. Date/Time

 

L.5.6 Check safety high sensitivity setpoint

h.5.

as follows:

4.5.6.1 The FP must be off, and all safety
channels in-tripped. Note that the
galloping safety lights on console are
green indicating high sensitivity
mode (15 KW).

L.5.6.2 Set the "current adjust" dial
to zero on the "test module” of
safety channel No. 1 (on NB2).

4L.5.6.3 Push "low current” push button
on the test module and hold in

 

 

while adjusting current adjust
dial.

 

L.5.6.4 Increase setting on current
adjust dial until flux amplifier
panel meter reads 150%. If it
will not go to 150%, it may
indicate that the safety flux
setting has not been switched
to the 15 KW range.

L.5.6.5 Check that the safety channel

 

scram occurs at above set point
+ 2%.
4L.5.6.6 Reset channel No. 1.
4.5.6.7 Repeat Steps 1 through 6
above for safety channel No. Z.
L.5.6.8 Repeat Steps 1 through 6

 

 

 

for safety channel No. 3.

 

7 Check file for last execution of
safety procedure 8A and 8D4. Record
dates: G8A 8Dk . Repeat

these if it has been longer than 1 month

 
s
#F z;/;,;

 

Approved by }ffif“'»’ A A1
Ve

4.5.7 (continued)
since 8A has been done or longer than 1
week since 8D4 was done.
4.5.8 Check rod &rop times as follows:
4.5.8.1 Raise No. 1 rod to 50 1ln above
the rod position where the first
lower indicator light 1it up.
4.5.8.2 Plug in rod drop times and set
to zero.
L.5.8.3 Activate rod scram switch.
4.5.8.4 Repeat for rods No. 2 and No.

3, and record results..

51-20

10/L/65

Init.

DatQ[Time

 

 

 

 

 

 

iRod

Start Position | Drop Time (<1 sec) | Init. Date

 

 

 

 

 

 

 

L.6

L.7

L.8

b.9

.10

 

4.5.9 Check the control rods fidacial zero
by procedure given in 4H-12.5.

Switch drain tank selector to FD-1 and start

thawing FV-106.

Check that FP and OFT bubblers are in service

per Step 2.9 and 2.10 and that OFT is empty

according to LI-589 and LI-600.

Check that all neutron instruments are in

service and the BFx chamber confidence inter-

lock in circuit 174 has been satisfied.

Check that all three control rods are at the

fill position specified by analysis group.

Position __ . Imitial

Check that FD-1 temperatures are all above

1100°F (average should be 1175 to 1225°F).

 

 

 

 

 

 
Approved by /fl/\%w Mo 5I1-21
vV 10/4/65

Init. Date/Time

 

4.11 Take a 1l0-minute count on the BFs chamber
and on both fission chambers. BFs should
be >10 cps and the fission chamber should
be >0.1 cps. Record data in Tables 5I-1i, 5I-2,
and 5I-3 at Step C.
NOTE: The ratio between the BFs count rate and the
fission chamber count rate should be about 100. All
nuclear instruments should be cbserved during the fill.
However, the BFs instrument will be the most useful
during this period. If the BFs instrument shows a
rapid increase or if the ratio between the BFs count
rate and the fission chamber count rate is greater
than 500 or less than 20, the £ill should be stopped.
4.12 When FV-106 is thawed, FP will stop. Push
operate button. Light will stay on.

 

4.13 Set valves as follows:
FD1 vent HCV-573 closed
FD1 FEq. HCV-544 open
FP vent HCV-533 open
FDL supply HCV-572 closed
FD2 Eq. HCV-545% open
FFT Eq. ECV-546% open
Set FCV-516 at 2.4 1/m on auto. ___
¥These can be left closed if conditions
in the tanks so dictate.
h,1k Take a complete inventory on check 1list 12B-5.

 

Identify inventory readings with this step
mimber.
.15 When ready to fill, set PCV-51T7A at 20 psig,
and close HCV-5Shi,
NOTE: FE-517 will limit the flow to less than 22 scfh

 

 

with a 40 psi pressure drop. Thermocouples on the

piping and vessels may be helpful in following the fill.
Approved by,;fizgzcgifyfn;/,ufiwl
) bv

Do not overfill the fuel pump. The other fuel drain
tank, fuel flush tank and fuel storage tank weights
should be observed to assure that no salt is flowing
to them. The reactor neck flange tvemperatures TE R-34
and TE R-35 should not exceed 400°F. To avoid unnec-
essary thermal stress on freeze flanges, do not stop
the fill midway of flanges.

4.16 As the system is filled, record WR-FD-1 when
the upper prove light goes ¢ff _ and when
the lower probe light goes off

The reactor will pe filled in steps as
given in Table 5I-1. (See fuel system cali-
bration curve for pressure differential vs
weight of salt necessary to fill to varilous
elevationg.) The drain tank weight alarm
should be set €0 ennunciate Just before the
required amount has been transferred. The
drain tank helium supply valve (HCV-572)
will then be opened for sufficient time to
fill to the required elevation. After
recording the data in Tables 5I-2 and 5I-3,
the next £i1ll step should be started as
described above.

Plot CR/CR vs. Salt level (ft) to aid in
assuring that the reactor will not go critical
during the fill.

L.17 After the reactor vessel is full, raise set-

point on PIC-517-A and continue filling.

51-22
10/4/65

Init. Date/Time

 

 

 

.18 Determine the desired FP £ill level for nor-
mal operation of 59% + 3% at 1200°F as follows:
Fefer to graph of "fuel pump fill and operate
level” in the FP sgection of calibration curve
notebook. Estimate the average salt temper-

ature in the fuel system from scanner A at
 
  

Approved by

v
o

 

Init.

5I-23
10/4/65

Date/Time

 

1.18 (continued)
OF. According to the graph the desired

 

£i11 level is %. Note that fill salt
temperature should be between llSOOF and
1225°F.

4.19 As soon as LR-593 indicates salt has reached
FP bowl, turn on cooling air to FP shroud.
Adjust HIC-903A (TR) for 20 scfm cooling air
as indicated on FI-903.

 

4,20 Note time that FF-101 is filled, ie when level
in FP reaches ~ 50% on LR-593.

 

4.21 Before desired level is reached, close HCV-5T2.
Alow for coast up of ~ 5% on LR-593 after
HCV-572 is closed .

 

NOTE: If salt inadvertantly overflows to the overflow
tank (epproximately 90% on LR-593), refer to Section 9I.
L.22 Record the following:
(Main Control Room)
PR-572
PRC-522
LR-593 _
WR-FDI
(Auxillary Comtrol Room)
LI-599B1
LI-600B1

 

LL,23 Freeze FV-103 and record LR-593 .

 

h.24h Test the freeze valve by venting FDL slightly.
Open HCV-573 momentarily, while observing
IR-593. If it drops too far according to fill

level graph, readjust level and refrecze.

 

4.25 Vent FD-1 through HCV-573 to a pressure such
that when HCV-5hk, 545, and 546 are opened,

the equilibrium pressure will be ~ 5 psig.

 
Approved by giigggzéé“

-
o=

  

4.26 Close HCV-573 and HCV-533.

L.27 Open HCV-54kh, 545, and 546 and set PCV-522
on auto at 5 psig.

4.28 Check that the fission chamber count rate
is >2 cps. (Should be 30 to 40 cps).

L.29 Fully withdraw the BF5 chamber.

4 .30 Note that lights in circuits 116 and 174
indicate FC confidence.

4.31 Wait at least 3 hours after FF-101 was
filled with salt. Step 4.20 Start
End

4.32 FPully insert all three control rods.

 

k.33 While observing the pump motor speed
(SI-FPE), amps (EiI-FPE), and watts
(EwI-FPE) as well as loop temperatures;
start the fuel pump.
NOTE: I% 1s desirable to start the pump as soon as
possible to avoid freezing salt in a cold spot. With
the fuel circulating at zero power, the calculated
level at 1200°F should be between 56 and 62%. See
chart in calibration curves notebook.

Level at 1200°F = LR 593% - .12 (T - lZOOOF)

where; LR-593 is present level in %

T is present reactor outlet in F.
1f not between these levels, consideration should be
given to adjustment of level.
(Flectric Service Area)

Purge salt from line 103 as follows:

4.34 Check V-519A closed

4.35 Push and hold in HS-519A1 .

4.36 Opbserve PI-519 (will be sub-atmospheric
if DT has been vented).

4.37 Throttle open V-519A to introduce small amount

of helium into line 519. Close to observe

5T-2k
10/4/65

Init. Date/Time

 

 

 

 

 

 

 
 

Approved b

h.37

L.38

4.39
L. Lo

hoL1
h.h2

h.43

L.l

4,45

NOTE: Whe

F Attt 414 oL-25
7 10/4/65

Init. Date/Time

 

(continued)

pressure on PI1I-519 .

 

Repeat small additions of helium and obser-
vation of pressure change with V-519A closed.
As soon as further additions fall to show
increase in pressure, line 103 has blown
through to the drain tank.

Close V-519A . Release HS-D1L9AL

1f necessary, adjust botg Tuel and coolant

 

heaters to maintain 1225 F.

Take salt inventory (Check list 12B-5.).
Sample from FP. (Check list 6A-3.) and
make entry in sample log.

With FV-105 in the freeze position, heatup
Fv-105 shoulders to normal approximate
temperatures with htr settings as listed
in the building log. FV-105 shoulder
temperatures are controlled by FV-105-1
and FV-105-1A on HCP-Q.. Temperatures

are indicated by TE FV 105-A4A and TE FV 105-BLhA
on TR 3300-3 and k4.

When shoulders are heated to normal temper-

ature, turn FV-105 to thaw.

————

Adjust FV heaters to contrel temperature at
~ 1200°F.
n FV-105 and FV-106 are thawed, an emergency

drain will drain to both FD1 and FD2. Therefore, if

sufficient time is availlable before a drain is necessary,

FV-105 should be frozen first.

L.46

Push the reset buttons (switches 121, 122,
and 123) on theconsole which change the
safety chamber control actions from kilowatts
to megawatts (ie they change the rod scram

setbings from 15 KW to 15 MW.)
vfl,f”fififvfifiéyuuza« 51-26
| Vv 10/4/65

 

Approved by

 

Init. Date/Time

 

NOTE: Whenever the FP stops, the safety interlock
settings are automatically lowered by a factor of
1000. When the pump is started, it is necessary to
push the mset buttons in order to change to the
higher settings. The lights on the console indicate
which settings are in service. (Green for kilowatt
andred for megawatt.)
5 FILL FUEL SYSTEM WITH FUEL SALT FROM FD-2 (For
filling from FD-1l, see Section 4.)
5.1 Check that heater H-106-4 is on at normal

 

operating setting. Heatup Procedure 5H5F
calls for all drain line heaters being on
with exception of the FV shoulders. Because
of the configuration of pipe and heaters in
this area, this temperature is dependent
also upon FV-105 and FV-106 shoulder heaters.
Note that TS FV 105-6A (temperature at the
"Tee") must be above 900 F before valve can
be thawed. The temperature of the lower
end of line 103 and the "Tee' may be read
out on special recorder. See Procedure

5F, Step 26 and Table 5F-6 as used for

this heatup. As valve shoulders are

heated in the next step, note that temper-
ature gradient is such that the "Tee"
reaches melting temperature before the

FV shoulders.

2.2 With FV-105 in the freeze position, heat up
Fy-105 shoulders to approximate operating temperatures
with htr settings as listed in the building
log. FV-105 shoulder temperatures are con-
trolled by FV-105-1 and FV-105-1A on HCP-~9
et g e o i e e w

5.2

53

5.k

 

Approved by,figggfifgévéfifidfiMfiA >I-27
' v

10/4/65

Init. Date/Time

 

(continued)

and temperatures are indicated by TE FV 105-AkA
and TE FV 105-BkA on TR 3300-3 and L. FV-106
and FV-104 will be kept in deep freeze but
above 400°F. While shoulder temperatures are
being adjusted, observe TE FV 105-5B on

TR 3300-23. Pot temperature must be up to
900°F or valve will not thew.

When temperatures of line 103 and the "Tee
are above low alarm setpoint of TR 3500,
connect TE's listed in Table 5F-6 of Procedure
5F to their normal readout.

Check that FV-104, 106, 107, 108, 109, 110,
111, and 112 are deep frozen. This is to
prevent inadvertant transfer between tanks

or mixing of the fuel and flush salt through
the fill lines.

(Main Control Room)

‘ 245

Check that safety interlocks in circuits 20

and 21 function properly as follows:

5.5.1 Vent fuel system pressure by opening
HCV-533.

5.5.2 As soon ag lights go on in circuit
20 and 21, close HCV-533. Add helium

 

pressure to fuel system via FCV-516
and bubblers. Note pressure on PL-5804
psig when light goes out in circuit

2l. DNote pressure on PI-592  psig
when light goes out in circuilt 20.

5.5.3 Above pressures agree with switch
tabulation settings of PSS-589A2
psig and PSS-592B2  psig.

 
 

Approved by - ;fl%fiflj%fik;¢:z/%fififirk 51-28
— 14 ‘ 10/&/65

Init. Date/Time

 

5.5.4 Prepare for thawing FV-105 by venting
fuel system and FD-2. Open HCV-533 .
Open HCV-575 .

5.5.5 Check prefill rod position switches
in clrcuits 20 and 21 for each rod, and
record results in the table below. Com-
pare results with switch tabulation.

Raising rod - lights ON in circuit 20
Sw.
Tab. Actual

 

Z58 N RR1-A2
Z55 NCRZ-AZ
Z55 NCR3-AZ
Raising rod lights ON in circult 21
Z85 RRL-AT
Z5S CRZ2-Al
255 CR3-AL
5.5.6 Check safety high sensitivity setpoint

 

———

 

 

 

as follows:

5.5.6.1 The FP must be off, all safety
channels in-tripped. Note that the
galloping safety lights on console
are green indicating high sensitivity
mode (15 KW).

5.5.6.2 Set the "current adjust" dial to

 

zero on the "test module" of safety
channel No. 1 (on NB2).
5.5.6.3 Push "low current’” push button
on the test module and hold in while
adjusting current adjust dial.
5.5.6.4 Increase setting on current
adjust dial until flux amplifier
panel meter reads 150%. If it
will not go to 150%, it may indicate
: Approved bngzééfifiééfifgiffiwfn_fl 5I-29

5.5.

10/k/65

Init. Date/Time

 

5.5.6.4 (continued)
that the safety flux setting has not
been switched to the 15 KW range.
5.5.6.5 Check that the safety channel

 

scram occurs at above setpoint % 2%.
.5.6.6 Reset channel No. 1.
.5.6.7 Repeat Steps 1 through 6 above

 

N

 

1

for safety channel No. 2.
5.5.6.8 Repeat Steps 1 through 6 for

 

safety channel No. 3.

 

T Check file for last execution of safety
procedure 8D. Date has been longer

than 1 week since this was done, repeat

 

 

 

 

 

 

 

 

 

 

Step 4 of 8D.
5.5.8 Check rod drop times as follows:
5.5.8.1 Raise No. 1 rod to 50 in. above
the rod position where the first
lower indicator light 1lit up.
N 5.5.8.2 Plug in rod drop times and set
to zero.
5.5.8.3 Actuate rod scram switch.
’ 5.5.8.4 Repeat for rods No. 2 and No. 3
and record results.
| ,
: i Rod |Start Position | Drop Time (<l sec) { Init. Date
1
3 —_—
. 5.5.9 Check the control rod fiducial zero

by procedure given in LH-12.5.

5.6 Switch drain tank selector to FD-2 and start

thawing FV-105. —_
3/
Approved by@fflézggékgéé;éfiMfitxka_ 5I-30
o Vv

10/4/65

Init. Date/Time

 

5.7 Check that FP and OFT bubblers are in
operation per Steps 2.9 and 2.10 and
that OFT is empty according to LI-599
and LI-600.

 

5.8 Check that all neutron instruments are in
service and the BFx chamber confidence
interlock in circuit 174 has been satisfied.

5.9 Check that all three control rods are st
the fill position specified by the analysis
group. Position . Initial

5.10 Check that ID-2 temperatures are all above
1150°F (average should be 1175 to 1225°F).

5.1l Take a 1O0-minute count on the BFy chamber

 

and on both fission chambers. BFs should
be >10 cps and the fission chamber should
be >0.1 cps. Record data in Tables 51-2
and 5I-3 at Step O.
NOTE: The ratio between the BFs count rate and the
fission chamber count rate should be about 100. All
nuclear instruments should be observed during the fill.
However, the BFs instrument will be the most useful
during this period. If the BFx instrument shows a
rapid increase or if the ratio between the BFx count
rate and the fission chamber count rate is greater
than 500 or less than 20, the fill should be stopped.
5.1z When FV-105 is thawed, FP will stop. Push
operate button. Light will stay on.
5.13 Set valves as follows:
FDz wvent HCV-575 closed
FD2 Eg. HCV-545 open

FP vent HCV-533 open

 

FD2 supply HCV-57h closed
FDL Eq. HCV-5Lix open
[Py ‘!_4
Approved byefggggzfiifé;gfiwffifkm‘ 5I1-31

10/4/65

Init. Date/Time
5.13 (continued)
FFT Eq. HCV-546% open
Set FCV-516 at 2.4 1/m on auto.
*These can be left closed if conditions
in the tank so dictate.
5.14 Take a complete inventory on Check List 12B-5

 

attached. Identify inventory readings with
this step number.
5.15 When ready to fill, set PCV-517A at 20 psig,
and close HCV-545.
NOTE: FE-517 will 1imit the flow to less than 22 scfh
with a 40 psi pressure drop. Thermocouples on the
piping and vessels may be helpful in following the
fill. Do not overfill the fuel pump. The other
fuel drain tank, fuel flush tank and fuel storage
tank weights should be observed to assure that no
salt is flowing to them. The reactor neck flange
temperatures TE R-34 and RE R-35 should not exceed
400°F. To avoid unnecessary thermel stress on
freeze flanges do not stop the fill midway of flanges.
5.16 As the system is filled, record WR-FD-2 when
the upper probe light goes off and when
the lower probe light goes off
The reactor will be filled in steps as
given in Table 5I-1. (See fuel system cali-
bration curve for pressure differential vs
weight of salt necessary to £ill to various
elevations.) The drain tank weight alarm
should be set to annuncaite just before the
required amount has been transferred. The
drain tank helium supply valve (HCV-572)
will then be opened for sufficient time to

111 to the required elevation. After
S
Approved by~ LY A A 5I-32
~ 7 % |; 10/4/65

Init. Date/Time

5.16 (continued)
recording the data in Table 5I-2 and 5I-3,
the next fill step should be started as
described above.

Plot CR/CR vs. Salt level (ft) to aid
in assuring that the reactor will not go
critical during the fill.

5.17 After the reactor vessel is full, raise set-
point on PIC-51T7A and continue filling.

5.18 Determine the desired FP fill level for
normal operation of 59% * 3% at 1200°F
as follows: Refer to the graph of 'fuel
pump £ill and operate level! in the FP
section of the calibration curve note-
book. Estimate the average salt tem-
perature in the fuel system from
Scanner A at ____?F. According to the
graph the desired fill level is ___ %.

Note that £ill salt temperature should
be between 1150 and 1225OF.

5.19 As soon as LR-503 indicates salt has reached
FP bowl, turn on cooling air to FP shroud.
Adjust HIC-903A (in TR) for 20 sefm cooling
air as indicated on FI-903.

5.20 Note time that FF-101 is filled; ie when level
in FP reaches ~ 50% on LR-593. L

5.21 Before desired level is reached, close HCV-57kL.
Allow for coast up of ~ 5% on LR-593 after
HCV-5Th4 is closed

NOTE: If salt inadvertantly overflows to the overflow
tank (approximately 90% on LR-593) refer to Section
9rL.
Approved by e

5.22

    
 

51-33
10/4/65

Init. Date/Time
Record the following:

(Main Control Room)

PR-57h
PRC-522
LR-593
WR-FD2 __

(Auxillary Control Room)

5.23
5.24

525

5.26

D2

5.28

229
5.30

LI-599 __

LI-600
Freeze FV-103 and record LR-593 o
Test the freeze valve by venting FDz slightly.
Open HCV-575 momentarily while observing
LR-593. If it drops too far according to fill
level graph, readjust level and refreeze.
Vent FD-2 through HCV-575 to a pressure such
that when HCV-54L, 545, and 546 are opened,

 

the equilibrium pressure will be ~ 5 psig.
Clogse HCV-575 and HCV-533.
Open HCV-5Lh, 545, and 546 and set PCV-522

 

 

on auto at 5 psig.

 

Check that the fission chamber count rate
is >2 cps. (Should be 30 to 40 cps).
Fully withdraw the BF3 chamber.

Note that lights in circuits 116 and 1Tk

 

 

indicate FC confidence.

 

5.31 Wait at least 3 hours after FF-101 was filled

5.32
5.33

with salt. See Step 5.26. Start .
End
Fully insert all three contrcl rods.

e ——

 

While observing the pump motor speed (SI FPE),
amps (Eil FPE), and watts (EwI FPE) as well

as loop temperatures; start the fuel pump.
Approved b MY

Vv

NOTE: It is desirable to start the pump as soon as
possible to avold freezing salt in a cold spot. With
the fuel circulating at zero power, the calculated
level at 1200°F should be between 56 and 62%. See
chart in calibration curves notebook.
Level at lZOOOF = LR-593% - .12 (T - 12OOOF),
where T 1is present reactor outlet temperature
(°F) and LR-593% is present level.
If not between these limits, consideration should be
given to adjustment of level.
(Electric Service Area)
Purge salt from line 103 as follows:
5.34 Check V-519A closed
5.35 Push and hold in HS-510A1
5.36 Observe PI-519  (will be sub-atmospheric
if DT has been vented).
5.37 Throttle open V-519A to introduce small amount
of helium intc line 519. Close to observe
pressure on PL-519 .
5.38 Repeat small additions of helium and obser-
vation of pressure change with V-519A closed.
As soon as further additions fail to show
increase in pressure, line 103 has blown
through to the drain tank.
2.39 Close V-519A . Release HS-510A1
5.40 If necessary, adjust fuel and coolant system
heaters to maintain 1225°F.
5.41. Take salt inventory (Check List 12B-5.).
5.42 Sample from FP. (Check List 6A-3.) Make
entry into sample log.
5.43 With FV-106 in freeze position, heat up FV-106
shoulders to approximate operating temperature

with hitr. set tings as listed in building log.

5I-34
10/4/65

Init. Date/Time

 

 

 
Approved byffigfifgzfigz%é%/ua/%, 51-35
- V 10/4/65

Init. Date/Time

 

5.43 (continued)
FV-106 shoulder temperatures are controlled
by FV-106-1 and FV-106-1A on HCP 9. Tempera-
tures are indicated by TE FV 106-A4A and
TE FV 106-BLA on TR 3300-5 and 6.
5.44 When shoulders are heated to normal tempera-
ture, turn FV-106 to thaw.
5.45 Adjust FV heaters to control temperatures of
~ 1200°F.
NOTE: When FV-105 and FV-106 are thawed, an emergency
drain will drain to both FDL and FDz2. Therefore, if
sufficient time i1s available before a drain is necessary,
FV-106 should be frozen first.
5.46 Push the reset buttons (switches 121, 122, and
123) on the console which change the safety
chamber control actions from kilowatts to
megawatts (ie they change the rod scram settings
from 15 KW to 15 MW.)
NOTE: Whenever the FP stops, the safety interlock

settings are automatically lowered by a factor of
1000. When the pump is started, it 1s necessary %o
push the reset buttons in order to change to the
higher settings. The lights on the console indicate
which settings are in service. (Green for kilowatt

and red for megawatt)
Approved by Leety 51-36 ’
s 10/4/65

51-1 RECOMMENDED STOPPING POINTS
FOR
ROUTINE FILL WITH FUEL SALT

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

o STOPPING POINT
: Weight i Salt
Step* |Transferred 'Z/H Location Level | Initial {Date and Time
1 (1bs) (ft)
0 0 j O 8alt in D.T. -
a
1 3500 0.l | --- 830.2 .
2 4200 10.6 | --- 831.2
3 5100 0.8 |Bottom of Volute | 832.4
L 6150 0.93]Top of Volute 833.1
5 6550 11.0 [Top of Graphite 833.5
6 | 8350 . --- |Vessel Full 834.5
!
; g ’
é ‘
i | |
*If additional points are needed, record the data at proper places in the »

table. Decision to take additional will be at the discretion of the

shift supervisor or day shift personnel.
45??2%Zé}?/
Approved by Z47 Cfiy&uww\ 5I-37

10/ /65

5I1-z FUEL SALT FILL DATA

 

 

ACTUAL FILL DATA

 

 

 

 

 

 

o

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Weight Salt Level
Step DT Wt. | Transferred| From Curve| AP (DT - FP) [Initial| Date and
#lbs)* (1bs) (£t) (psi)** Time
0 |
|
!
i
4
3 ]
1
2|
3|
N
2
_6
i
| |
;
* From WR FD-1 or WR FD-2
**¥This is differential pressure required to hold the salt a%t this eleva-
tion. (PR-572B - PR-522A or PR-5TUB - PR-5224).

 
5I-3 COUNTING RATE DATA

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

| X
BF - CHAMBER* 1 FC No. 1 FC No. 2
: Elapsed| Count] Elapsed |Count Elapsed [Count Date
Step |Counts| Time |Rate | CR/CR, |Counts| Time Rate CR/CR, |Counte | Time [Rate { CR/CR_{Initial [And
3 (min) | (cps) (min) !(cps) (min) (cps) Time
0 ;
. ]
; z
| i
1
2
3 5 ;
k
5
6 s
i %
|
E 7
i
{

 

 

 

 

 

 

 

 

 

 

¥BF5 Scaler should be timed 10 minutes or 10000 counts.

Fission chamber scaler should be timed for 10 minutes or 1000 counts.

il

: = dd
Htfl%fit;?zggéééy’fiq paroxddy

 

6o/4/0T
gE-14
Approved by &7 ;E“f?€7fl4fiflq / E?él
9/14/65

 

5J CRITICALITY AND POWER OPERATION

The fuel and coolant salt will be circulated subcritically in the
loops until power operation is desired, at which time the control rods
will be withdrawn to obtain criticality.

During normal power operation, programming of the heat removal appa-
ratus and positioning of the control rods will be done by a preset instru-
mented system. However, if desired for special tests, complete manual
control is possible.

1 PREPARATION FOR POWER OPERATION

Prior to taking the reactor critical the system should be checked

 

to assure that all pertinent equipment and instrumentation are func-
tioning properly. The amount of testing depends upon the length of
the shutdown prior to startup and what was done during the shutdown.
If the reactor has been subcritical for as long as a day, 1.1 through
1.4 should be completed. If the shutdown has been extensive, all
items listed below should be completed.

Init. Date/Time

 

1.1 Check rod drop time for each rod toc be less
than 1 second. (Check List LH-12.6).

1.2 Check fiducial zero of each rod (Check List
LH-12.5).

1.3 Check flux, period, temperature, and voltage
scram on each channel (Check List 8D-k4).

1.4 Check that thermocouples on the radiator

 

 

 

outlet tubes are plugged into Scanner D and
E and that the gain on both scanners is set
at 100 so that an alarm will occur at QSOOF
or 1250°F.

 

1.5 Complete the entire safety circuits (Check
List 8D).

1.6 Complete the neutron instruments (Check List
8A).

 

 
hpproved by ZH N Kfessf ste 53-2
- </ 9/1L/65

Init. Date/Time

 

1.7 Complete the process monitor's (Check List
8B).

1.8 Complete the personnel monitor's (Check List
ac).

1.9 All annunciators should be clear or approved

 

 

by the shift supervisor. ghift Supervisor's
Approval
2 STARTING POWER OPERATION USING AUTOMATIC LOAD CONTROL
AND ROD SERVO

The rods will be withdrawn manually to attain criticality.

 

When the flux demand setpoint is reached, the servo controller will
manipulate the regulating rod to control the power at the setpoint.

To increase the nuclear power, the flux demand will be increased.
This may cause the regulating rod to withdraw until the regulating-
rod limit is reached. The limit can be changed by operating the
regulating-rod drive switch or the shim rods can be manually with-
drawn which will cause the regulating rod to insert.

As the flux demand is increased, the nuclear power will cause
the system temperatures to rise necessitating removal of heat at
the radiator. Number one blower will be started and the resultant
AP across the radiator will cause the bypass damper to open. Switch-
ing the load-demand switch to the "increase" position will cause
the radiator doors to open. The reactor-outlet temperature will be
maintained constant by manually balancing the load and flux demand.
Interlocks prevent automatically raising the power above 1 mw unless
the reactor is in "run."

Before pushing the run button, the powers should be between
0.5 and 1 Mw; both range selectors should be in the 1.5 Mw range,
and the temperature-demand setpoint should be slightly lower than
the outlet temperature. The regulating rod should be in the center
portion of its useful range and not at either the insert or with-
draw limit. When the reactor is switched to the "run" mode, the

range selector will be sealed in the 15 Mv range, and the rod-control
o
Approved Dby T \@’//4’1flr\ 5J -3

9/14/65

circuitry will be changed from flux serve to temperature servo.
Under these conditions, the regulating rod will be automatically
inserted or withdrawn to maintain the reactor-outlet temperature
constant. The temperature can be changed by adjusting the tempera-
ture-demand setpoint. The load-demand switch will be held in the
increase position to increase the heat-removal rate at the radiator
to the desired power. The sequence of operations, which automati-
cally occur as the heat-removal rate is increased is as follows:

The doors will open completely. This will set up the circuitry
to start raising the AP setpoint resulting in the bypass damper
closing. When the damper is completely closed, No. 3 blower will
start automatically. This will increase the AP above the AP set-
point, and the bypass damper will reopen. Further increase in load
demand will increase the AP setpoint, and the bypass damper will
clese. Operation at 10 mw will be reached with both doors open,
both blowers in operation and the bypass damper partially closed.
If the regulating rod reaches the withdraw limit, No. 2 and No. 3
rod will have to be manually withdrawn or the limit will have to |
be raised. Rod 2 and 3 should always be withdrawn the same amount
(within 1 inch of each other).

Details of the procedure are given below:

Init. Date/Time

 

2.1 Set bypass-damper controller (PAM AD2A) on
MB-4 on automatic.

2.2 Manually lower AP setpoint (PAIAD2A1) on

 

congole to zero using S5-27.

 

2.3 Switch load control to automatic using S5-23
on console. Note that light on console

indicates load control automatic.

 

2.4 DNote that the bypass dampers are fully open.
Check indicator and position light on MB-4

and position indicator on console.

 
Approved byfzéfégizkéggééz;mnafi

2.5 Put rod control on servo using servo-mode
selector switch (S-16). DNote that lights
on console indicate that the flux servo
control is on.

2.6 Set servo flux channel selector switech (S-17)
to No. 1 or No. 2 channel.

2.7 Set flux demand on selected channel as desired
using range-selector switch (RXNARCA 5), and
flux-demand knob (RXNARC-A6). Do not exceed
100 kw.

2.8 Set other channel range-selector switch at
lowest possible range.

2.9 Check that regulating rod is at the upper
regulating-rod limit.

2.10 Set fission-chamber selector switch (S-15)
as desired. No. 1 No. 2
Both

2.1l Set fission-chamber No. 1 mode selector switch
(5-13) to automatic (pushed in).

.12 Set fission-chamber No. 2 mode selector switch
(8-1k) to automatic (pushed in).

2.13 Withdraw the shim rods (No. 2 and No. 3) to

in.

2.1k Switch regulating-rod actuator switch (S-19)

 

to withdraw. This will raise the regulating-
rod limit switch allowing the flux servo to
withdraw the regulating rod. Continue regu-
lating-rod withdrawal until criticality is
attained and desired flux is reached. When
critical the regulating rod should be within
the range of 8 to 39 inches and should be at
least 4" below the shim rods.

NOTE: As flux increases change the range on the alter-

nate picoammeter as required and observe the linear

57 -1
9/14/65

Init. Date/Time

 

 

 

 

 

 
Approved by M ‘%”g;f(gmm
Y

flux indicator.

575
9/14/65

Init. Date/Time

 

Also observe the period meters on

the console.

2.15

2.16

2.17

2.18

2.19

When the flux reaches the flux demand

setpoint, the servo will stop withdrawing
the regulating rod. The regulating rod
actuator switch 5-19 should be released

-

when the regulating rod i1s near the cenver

of the regulating rod limit switches.
While maintairing the reactor at this power,

take a reactivity balance. Check that the
balance indicates

than £ .

a8 net reactivity of less
Shift Supervisor's per-

mission to increase power .

Increase the power to ~ 1 Mw and start heat

removal at the radiator toc maintain the re-

actor outlet temperature at lEZEOF as follows:

2.17.1 Increase nuclear flux to spproximately
1 Mw by increasing the setting on the se-
lected picoammeter range switch anfi/or
changing the flux demand knob. The alter-
nate pilcoammeter range switch should also
be adjusted as power is increased.

2.17.2 Start MB-1.

2.17.3 Switch the load-demand switch to the
"{increase” position. This will open the
inlet and outlet radiator doors.

2.17.% Manually adjust the flux demand and
the load demand to maintain the reactor-
outlet temperature at lZZBOF.

Ad just the temperature-demand setpoint to

1225°F (or slightly less) using XSNARCA.

Check that both range selectors on the pico-

ammeters are in the 1.5 Mw range.
Approved by«zfifi?zzbaéfiéf'z¢¢m 5J-6
~

9/14/65

Init. Date/Time

 

2.20 Adjust the regulating-rod limit switches so
that the regulating rod is approximately in
the center of its range.

2.21 Push the run button (S-11). This seals the
reactor in run and swiltchto temperature servo.
Check that lights on the console indicate
this.

2.22 Increase the radiator power withdrawal to
_____ Mw by holding the load-demand switch
in the "increase” position. The rod servo
controller should manipulate the rods to
keep the reactor-outlet temperature at
1225°F. Note that the following occurs:
2.22.1 Both radiator doors open to the

upper limit.

2.22.2 The AP setpoint increase and the
dampers close completely.

2.22.3 MB-3 starts.

2.22.4 The AP increases causing the bypass
dampers to partially open.

2.22.5 The AP getpoint increases causing
the bypass damper to close until de-
sired power is attained.

MANUAL AND SPECIAL POWER OPERATION
The reactor heat load and flux can be adjusted manually in a

number of -different ways. These may be desirable for special tests.

Details procedures will be written when needed.

The control rods can be manipulated manually to attain criti-
cality and adjust power using the individual actuator switches.
The regulating-rod limits have no function when in manual control.
Group insertion is possible at all times and group withdrawal can
be done when in the start mode. Rods 2 and 3 will normally be

withdrawn and inserted the same amount within 1 in. of each other.

kY
Approved by/%/ S “Y pagA
vV

5J-T
9/14/65

Rod 1 will be kept at least 4" below rod 2 and rod 3 and within
the range of 8 to 39 withdrawn.

At very low powers it may be necessary to adjust power removal
by adjusting the electrical heaters or it may be advantageous to
raise one or both radiator doors with the blower off. At higher
power with one or both of the blowers on, fine adjustment may be
made by setting the doors at a fixed position and changing the
bypass-damper position. The damper control may be set on avtomatic
which will hold a constant radiator AP or on manual which will

maintain a fixed damper position.
5K-1
9/17/65

Approved 5y,42712§k25éagfiufiw1

5K NORMAL OPERATING CONDITIONS

Normal operation of the reactor is considered to be whan fuel galt

The nuclear power will depend on the experimental program. Norral values
Tor other monitored variables are given in the building logs or ca he
compuver log sheete, details of experimewnts in progress are outlined
the run instructions, and operating limits are listed in Part VI. A
general description of the operations is given below.

The reacter outlet temperature will normally be held at 12250F and
other clreulating salt temperatures be allowed to vary with power. The
nuclear power and the heat removal rate will be adjusted to athain
steady state. Normally the heat load will be adjusted through the auto
load-control system. (At times manual contfol will be exercised over
the doors, damper, and blowers.) Nuclear power will normally be con-
trolled by the servo system: below about -l Mw the system will be in
the "start” mode and the servo will hold the power at a selected set-
point; at higher powers, the system will normally be in "run" and the
servo will adjust the nuclear power as required to maintain the selected
reactor outlet temperature. In this mode the nuclear power will be
brought to the prescribed level by adjusting the heat load.

Capsules of enriching salt will be added at intervals of approxi-
mately one week or longer tc compensate for #2°U burnup and the slow
growth of long-iived fission-product poisons. The regulating rod
(under servo control) and the shim rods will be adjusted to compensate
for shorter-term effects associated with changes in power level. The
shim rods will be adjusted as necessary 10 keep the regulating rod with-
in its most effective range, 8 to 39-inch withdrawal, and at least L
inches below the two shim rods. The two shim rods will be kept even
with each other. As the regulating rod is automatically insertsd or
withdrawn, the servo limit switches will be adjusted as necessary to
prevent the rod from encountering cither 1limit.

The logger-computer will ordinarily be in service, if not, normal
cperation can continue but with an increase in manual surveillance and

logging. 1In particular, if the computer is out of service, special
 

Approved byféz?2224622?4“4“4 : 5K-2
N

9/17/65

attention must be given to the reactivity behavior to watch for abnormal .
behavior. (When the computer is in service, a reactivity balance will be

computed every 5 minutes, monitoring for any deviation of the reactivity

from the normal behavior.)

The heaters on lines and equipment in the fuel and coolant systems
will be kept at approximately the same settings as required to hold the
temperatures in the system at lZZBOF when subcritical except for the
fuel-pump heaters which will be reduced in order to increase their usable
life.

FV-103, 204, and 206 will be frozen, but the temperatures will be
maintained so that they will thaw upon loss of electrical power in less
than 15 min. FV-105 and FV-106 will be thawed, and elther drain tank
shall have sufficient free space to drain the entire reactor system.
FV-104 and 107 through 112 will be deep frozen and will not thaw upon
loss of electrical power. However, all salt subjected to high radiation
(if in reactor or drain tank cells) will be kept above LOO°F to prevent
Tluorine evolution.

Temperatures in FD-1, FD-2, FFT, and the CDT will be kept above
1000°F. The FST may be cooled to ambient temperature if required. No
salt processing will be done while fuel or flush salt is in reactor. .
All drain lines in the fuel and coolant system will be kept above the
freezing point of the salt.

The proper water level will be maintained in the feedwater tank for
Nos. 1 and 2 steam drums, and cooling-tower water will be run continuously
through the condensers so that the afterheat removal system is in standby
condition.

Cover gas and bubbler flows will be maintained to the fuel and cool-
ant pumps. The offgas from the fuel pump will be sent to the maln char-
coal beds, and the coolant-pump offgas will go directly to the contain-
ment-ventilation filters. The equalizer valves HCV-5L4k, 545, and 546
between the fuel drain and the flush tanks and the fuel pump as well as
HCV~527 between the coolant-drain tank and the coolant pump will be open.

The helium-supply and vent valves on FD-1, FD-2, FFT, and CDT will be

clogsed. The FST will normally be maintained at a slight positive pressure.
Approved bydffigéj;%fg?/fllflWI 5K-3

9/17/65

The fuel system, coclant system, ¥D-1, FD-2, FFT, and CDT will be main-
tained at about 5 psig pressure by throttling PCV-522 and PCV-528 in the
offgas flow from the pumps. Two sections of the main charcoal beds will
be on stream at all times with the others valved off and in standby.

Lubrication and coolant oil will be circulated through the fuel
pump using FOP 1 or Z and through the coolant pump using COP 1 or 2. The
pumps will be alternated weekly. The over-pressure on the oil supply
tanks will be maintained at 7 psig. The oil level in the supply tank
will be maintained above 40%. Upon a gross leak in a pump seal, it is
desirable for the oil supply to the bearings to be shut off immediately;
however, a small leak can be tolerated indefinitely. It will, therefore,
be necessary to periodically change the level setpoint, on LI-0T-1-A3
and LI-OI-2-A3. This should never exceed 2% below indicated level.

The level in the oil catch tanks gives an indication of the leakage
through the seals. The large diameter upper portion of the tank is pro-
vided for shutdown margin in case of gross seal leakage. Therefore, the
0il level in the catch tanks will be kept below the upper portions. (<50%
on LI-524 or LI-526).

The cover-gas supply will be from a helium trailer with a bank of 6
standard helium cylinders in standby. One of the main helium dryers and
oxygen-removal units will be in service, and the others will be valved
off and at reduced temperature in standby. The auxiliary dryer downstream
of the main units will be in service.

A1l leak-detector headers will be pressurized to approximately 100
psig with all valves to in-cell flanges open. All header "A" valves will
be open and "B" valves closed.

Component coolant pump No. 1 or No. 2 will be in service for keeping
in-cell freeze plugs frozen and for cooling the fuel-pump bowl, control
rods, and reactor-access plug. Component coolant pump No. 2 will be
operated for the first full (7 day) week of each month to insure proper
operation and will be kept in standby to replace CCP No. 1 the rest of
the time. The No. 3 component coolant pump will be in operation to
keep the freeze valves in the coolant system and transfer lines frozen.

(Deep-frozen freeze valves may not require coolant air.) The service
swproved by P mem -

Y 9/17/65

alr compressor provides emergency cooling air and will be operated when
needed,

The reactor and drain-tank cell pressure will be held constant at
about 12.7 psia, using the component coolant pump No. 1 or No. 2. Valves
in the evacuation line (569) will be throttled to hold the pressure with-
in limits. UNitrogen will be continuously added to the cells to keep the
oxygen content below 5%. The cell leak rate as indicated by the cell
pressures or oxygen balance shall not exceed 1% of the cell volume per
day at conditions of the maximum credible accildent.

Contaimment ventilation stack fan No. 1 will be in operation with
No. 2 fan in standby. Dampers will be adjusted to maintain air flow from
less hazardous to more hazardous locatlons. All three stack filters will
be in service at all times.

The vapor-condensing system water tank will be 2/3 full, and the
pressure will be approximately atmospheric.

One cooling-tower pump will be in operation and the other in stand-
by. Each Monday the operating pump will be stopped and the standby pump
started and kept in operation for the next week. The cooling-tower fans
will be operated as needed to hold the water temperature within limits.
During freezing weather, the fans will be alternated to minimize icing
of the tower. When the ambient temperature is above freezing and only
one fan 1s required to control the water temperature, the fans will be
alternated weekly. One treated-water pump will be in operation,and the
other will be in standby. These will be alternated weekly.

The two space coolers in the reactor cell, the one in the fuel drain
tank cell, and the two in the coolant cell will be in continuous opera-
tion to maintain the temperatures in the cells below 15OOF.

Any water accumulating in the sumps of the reactor cell, drain-tank
cell, or other cells will be jetted to the waste tank. Accumulated
liquid waste will be pumped periodically to the Melton Valley waste
disposal plant.

Both radiator-duct blowers (MB 2 and MB L4) will be in operation at

all times.
Approved by fl/)dw/mm SK-5
v

9/17/65

One instrument air compressor and one air dryer will be in operation
and the other units in standby. Each Monday the standby air compressor
and dryer will be put into operation for the following week and the
operating compressor and dryer put in standby. One bank of 6 nitrogen
cylinders for emergency instrument air will be floating on the line with
another bank of 6 on standby.

The 125 kw ac-dc motor generator (MG&L)will be in operation. This
operates the 25 kw dc-ac motor generator (MGlO and keeps the 250v battery
bank charged. The battery bank provides emergency power for M L in
case MG 1 fails. MG L4 provides emergency power for the sampler enricher,
FOP No. 2, COP No. 2 and the 110v instrumentation.

One 48v ac-dc motor generator, MG2 or MG3, will be on line and
the other in standby. These provide UBv dc instrument power and keep
the L48v battery bank charged. The battery bank supplies emergency instru-
ment power in case both MG 2 and MG 3 fail. The MG sets will be alter-
nated weekly.

The batteries in the 250v and L8v system will be checked periodically
to assure that they are in good condition.

The diesel generators will not normally be in operation, but will be
tested periodically to assure that they are ready for operation.

A periodic operational check will be made of all safety interlocks.

The five scanners will be used to continuously monitor the system
temperatures. Scanners D and E will be set on a gain of 100and have the
reference set at 1100°F.

All process and personnel radiation monitors will be in service at
all times. Periodic checks will be made to determine that they are
operating properly.

The coolant stack will be monitored for beryllium at all times.
Beryllium sampling stations will be in service and the filtered samples
will be removed daily and checked by the industrial hygienist. One
beryllium blower will be in operation with the other in standby. These
will be alternated weekly.

The jumper board will have no jumpers not authorized by chief or
assistant chief of operations. There will be no red indicator lights on

jumper board above 1Mw operation (Run mode).
P
ot
S

Approved by3flfi”'fi4?KVé%5/#¢”&m 6-1
B 10/26/6

 

6 SAMPLING AND ADDITIONS

Various systems are sampled and analyzed periodically to determine
corrosion rate, build-up of contaminates, loss of corrosion-inhititing
chemicals, etc. Details of sampling and/or additions are given in the
following sections.

Table 6-1 lists the various samples routinely taken, giving the
normal frequency of analysis, numbering system used, and other pertinent
information. Any sample taken which does not logically fit into the
categories listed wlll be considered a miscellaneous sample and will be
numbered consecutively and preceded by an "M". (i.e. M-1, M-2, etc.)

When a sample is taken to the analytical laboratory, a "Request for
Control Analysis" form X-324 (Figure 6-1) should be filled out as com=-
pletely as possible and submitted with the sample. Cross out statement
regarding fissionable material 1f it does not apply. If rush analysis
is required on a particular analysis, this should be so indicated giving
priority if more than one rush analysis is needed. Results from rush
ahalyses will be phoned to the shift supervisor when completed. Perti-
nent information should be entered in the sample log when sample is
taken and when results are received. If results are questionable, advise

the analytical laboratory so that they can check their results.
TARLE 6-1 SAMPLING SCHEIULE

o
3
3
=
O
2
®
O
o'
e

 

Sampling Deliver Sample Analysis

 

 

 

Material Sample Sample Sample Normal Procedure To Normally
Sampled Number Point Size Frequency Used Bldg. Chemist  Requested Normal Limits

Fuel Salt FP-%- Fuel Pump 10 g Daily 6A 2026 Tamb “Li ~ 10.3 wt %
Be ~ 6.7 wt %
Zr ~ 11.11 wt %
238y ~ 3.0 wt %
235y ~ 1.6 wt %
LU ~ L6 wt %
F ~ 68.9 wt %
Fe <200 ppnm
Cr <100 ppm. Cr should increase and Fe and Ni

decrease during a run.

i <100 ppm
Mo
o 1100 £ 97C ppm

Flush Salt FP-%- Fuel Pump 9g Weekly 6A 2026 Lamb TLi ~ 13.1 wt %
e ~ 9.7 wt %
Zr
238y
235y
zZu
F ~ T7.1 wt %
Fe <200 ppm
Cr <100 ppm
Ni <100 ppm
Mo
0

 

* -
Tnsert the run number at ¥ and number consecubively for fuel and flush salt during each run (i.e. FP-4-1, FP-L-2, FP-L-3, etc. could be first
flush salt sample from Run L and the first and second fuel-salt sample).

69/92/0T
2-9
Teble 6-1 (continued)

 

 

 

 

 

 

 

 

 

&
3
H
Sempling Deliver Sample Analysis 2
Material Sample Sample Sample Normal Procedure To Normally D
Sampled Nunmber Point Size Freguency Used Rldg. Chemist  Requested Normal Limits 2
T4 g
Fusl Salt FST-%-  Tuel 10g As Li ~ 10.3 wt % <
Storage Requested  TM-GS07T 2026 Lamk Be ~ 6.7 wt 4
Tank Part VII 7y ~ 11.11 wt %
of Design o
& Operations U ~ 30wt %
Report 235y ~ 1.6 wt %
LU ~ L6 wt g
T ~ 68.9 wt %
Fe <200 ppm
Cr <100 ppm. Cr should increase and Fe and Ni
decrease during & run.
Ni <100 ppm
Mo
0 1100 * 970 ppm
Flush Salt FST-%- TFuel g As TM-907 2026 TLamb L ~ 13.1 wt %
Storage Requested Part VII Be ~ 9.7 wt %
Tank of Design & Zr
Operations 238y
Report
225y
U
F ~ 7.1 wt %
Fe <200 ppm
Cr <100 ppm
Ni <100 ppm
Mo
0

 

*
Insert the run number at * and number consecutively for fuel and flush salt during each run (i.e. Fp-4-1, FP-L-2, FP-L4-3, etc. could be first
flush salt sample from Run 4 and the first and second fuel-salt sample),

Gg/92/0T
£-9
Table 6-1 (continued)

 

 

 

 

 

&
K
Sampling Deliver Sample Analysis g
Material Sample Sample Sample Normal Procedure To Normally <
Sampled Number Point Size Frequency Used Bldg. Chemist Requested Normal Limits E&
Coolant Salt CP-%- Coolant Pump 9g Weekly 6B 4500 Iaing TLi ~ 13.1 wt % o'
Be ~ 9.7 wt % <
F ~ T7.1 wt %
Fe <200 ppm
Cr <100 ppm
Ni <100 ppm
Mo
0
Treated TW-%% v-8263 250 m# Note 1 6C 4500 Ilaing Total Inhibitor 1600-2100 ppm
Water from pH 8.8 - 9.2
Loop Hardness CaCO No increase
NOz 650 to 866 ppm (1200-1600 ppm potassium nitrite) ';§
B k6 to 57 ppm (400-500 ppm potassium tetra borate)
Al <2ppm
Fe <Z2ppm
Treated WPW-#*# v-8L8p 250 mf Note 1 6C 4500 Iaing Total Inhibitor 1600-2100 ppm
Water from pH 8.8 - 9.2
Nuclear Hardness CaCCx No increase
Penetration NOo 650 to 866 ppm {1200-1600 ppm potassium nitrite)
B L6 to 57 ppm (LOO-500 ppm potassium tetra borate)
Al <2ppm
Fe <ZPpm

 

¥
Tnsert the run number at * and number consecutively for fuel and flush salt during each run (i.e. FP-L-1, FP-L4-2, FP-4-3, ete. could be first
flush salt sample from Run 4 and the first and second fuel-salt sample).

Number consecutively (do not include run number).

Note 1: Samples are analyzed twice weekly by operation personnel for pH and total inhibitor and hardness and are not normally submitted to analytical
chemistry. Complete analysis listed, except total Inhibitor, is run weekly by analytical chemistry.

$9/92/0T
-9
Table 6-1 (continued)

 

 

 

 

 

 

Sampling Deliver Sample Analysis
Material Sample Sample Sample Normal Procedure To Normally
Sampied Nunmber Point Size Frequency Used EBldg. ~ChemIst Requested Normal Limits
Cooling Tower CTW-¥¥ V-829D 250mé Note 2 6C 4500 Iaing pH 7.0 - 8,0
Water from Chromate 3¢ - 50 ppm
Circulating Hardness CalO= <2x process water
System Fe <2 ppm
Process Tiy-%% V-890D 250mg Note 3 e 1500 Laing pH 6.5 - 8.0
Weter Hardness CaCOx <125 ppm (arbitrary)
Fe <1 ppn

Condensate W-*% Condensate  250m¢ When filled 6C 4500 Iaing Hardness CaCOs <5 ppu

Storage

Tank No. 1

V-C8T~1A
Condensate Wk Condensate 250mf When filled 6C L4500 Iaing  Hardness CaCOs <5 ppm

Storage

Tank No. 2

V-CST-2A
Reactor and  CA-%¥ V-5658 250mé Weekly 6D 2026 Lamb Be
Drain Tank 02
Cell Air D/M/me

Gemma. Spec

 

¥
Number consecutively (do not include run mumber).

Note 2: OSamples are analyzed daily by operations personnel for pH, chromate, and hardness.

Note 3: Damples are analyzed twice weekly by operations perscnnel for pH and hardness.

Complete analysis is run weekly by Analytical Chemistry.
Complete analysis 1s run weekly by Analytical Chemistry.

>
g
g

=

Q

<

o

2
o
=

 

¢9/9z/0T
5-9
 

 

 

 

 

Table £-1 (continued)
Sampling Deliver Sample Analysis
Material Sample Sample Sample Norma.l Procedure To Normally
Sampied Number Point Size Frequency Used Bldg. Chemist Requested Normal Limits
Tube oil IO-¥*% 703D and 250 m4 FEach new 6F 2026 Tanmb Carbon
Fuel & 753D drum and Sulphur
Coolant (or Drum) when Moisture
required Total Solids
PBromine number 66 895U at 100°F, 36 SSV at 210°F
Acid number
Flashpoint viscosity 322°F
at 100°F & 210°F
Interfacial tension
at 77°F
Infrared spectro-
photometric and
spectrographic
analyses
Weekly during 6 2026 Tamb Acid No., (ASTM-gT74) 0.06
power opera- Interfacial tension at 18 aynes/cm
tion only TT°F
Fuel and IOG-¥*  Line 535 250 m¢ When 6E 2026 Lamb D/M/me
Coolant {or 534) required Gamma Spec
Pump ILube
Qil Cover
Gas
Cover Gas CG-*% He Trailer Note L
Untreated CG-¥* Line 548 When 5F 9735 Sites 02 <1 ppm
Cover Gas required H=0 <6 ppm
From
Traller

 

Number consecutively (do not include run number).

Note h:

The trailer will be anslyzed at Y-12 each time after it is filled.

ped
e
g

H

Q

2

o®

o
=2
e

 

¢9/92/0T
9-9
 

 

 

 

 

 

 

&
I
H
<
R
®
oY
Table 6-1 (continued) &
]
Sampling Deliver Sample Analysis
Material Sample Sample Sample Normal Procedure To Normally
Sampled Number Point Size Freguency Used Bldg. Chemist Requested Normal Limits
Cover Gas CG-%%  TLine 549 When 5F 9735 Sites Oz <1 ppm
from Dryers required o0 <6 ppm
& Oz
Removal Units
Offgas from 0G-#* V-518F When 5G
the FP required
Liquid from  CS-%¥ V-33h When jetted 37 2026 Lamb D/M/mg
reactor (or (or 3LbL) Cemma Spec.
drain tank)
Cell Sump
Liguid from Co-%¥  Misc, Cell 250 mé When Dip 2026 Lamb D/M/mi
Sumps and Sumps required bample Gamma Spec
the Pump
Room Tank
Liquid in WT-¥% V-305B 250 mé Before 37 2026 Lamb pH >T7
Waste Tank Emptying NaOH required to
Tank neutralize,
Millicuries/me <1.3 millicuries/cc

 

Number consecutively (do not include run number).

G9/92/0T
L-9
 

 

 

 

 

 

 

 

 

 

 

 

 

 

6-8
10/26/65

Approved by

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Xs 324
CONTROL NO. — —
REQUEST FOR CONTROL ANALYSIS
T his form is to be used or sgmples containin less
than 55 milligrams concen%%%)t’ign ofgf%ssionable matgrial.
N AME DATE SUBMITTED . ——

 

 

 

SERIES NUMBER

 

 

ESTIMA- | PREVIOUS NATURE AND CONCENTRATION
SAMPLE DESIRED TION OF | HISTORY ESTIMATION OF ALL
CODE ANALYSIS CONCEN- OF OF CONSTITUENTS

TRATION SAMPLE ACTIVITY IN SAMPLE

 

 

 

 

 

-

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Requestor

 

 

FIGURE 6-1
V7
Approved by *fififijg2;4;//flwhq 6A-1
v o/5/e

6A TFUEL SYSTEM SAMPLING AND ENRICHING

The main parts of the sampler-enricher are: a transfer tube con-
nected to the pump bowl through which the sample capsule is lowered to
cbtain a sample, a shielded transfer box on the 852 level, a manipulator
used to handle the sample, helium supply end vacuum pumps used for purg-
ing, and the transport conatiners and transport casks. Interlocks are
provided to maintain containment and minimize harmful or dangerous
operations. A brief description of the manipulation necessary to remove
a sample or add an enrichment capsule is given in Section 6A-1 and 6A-2.
Precautions are taken to keep moisture and oxygen out of the sample and
out of the fuel system and to keep radiocactivity in. The purging neces-
sary to do this is not given in the general description but is covered
along with other details in the sampling check lists 6A-3 and 6A-lk.

The checkout and startup of the sampler-enricher after a long shutdown
is covered by 6A-5. Securing the sampler-enricher for a long shutdown
is covered by 6A-6. Unusual operating conditions are given in 6A-7.

Since sampling is potentially hazardous, two operators are required
for most of the manipulations. In general, one person reads out loud
each step in the procedure, observes the other operator as he does the
operations and then checks off the check list. Where one operator is
sufficient, this is indicated on the check lists.

1 GENERAL DESCRIPTION OF SAMPLING THE FUEL SYSTEM

Except for long shutdowns or sampler-enricher maintenance, the
sampler-enricher will be in standby condition when not in use. The
permigsive switch in the control room will be off, and the vacuum
pumps will not be running. An empty sample capsule will be hanging
on the latch in Area 1C, the operational or maintenance valve will
be closed, the accegs port will be closed, the manipulator cover
will be on, and the removal valve will be closed so that a sample
can be isolated quickly.

The first step in taking a sample is to turn the permissive
switech on. This turns on the instrument control power and permits

operation of the vacuum pump used in purging. A check is made to
 

N .
Approved by)/'23?§j2%{ S i 6A-2
v

9/8/65

assure that all pressures are within limits and all valves are in -
the proper position. The operational and/or maintenance valve 1is
then opened, and the capsule is inserted into the pump bowl and

the sample withdrawn using the capsule-drive motor. When the sample
is in Area 1C, the operational or the maintenance valve is closed.

Working in the glove box near the sampler-enricher, a clean
capsule is weighed and placed in a decontaminated transport con-
tainer. The transport container ils then lowered through a trans-
port cask on top of the sampler-enricher into the removal seal area.
The removal valve is then opened and the transport container low-
ered into Area 3A. The top of the transport container is unscrewed
and then is partially withdrawn, and the removal valve is closed.
The capsule is removed from the lower part of the transport con- )
tainer and placed on the floor in Area 3A.

The access port is then opened, and the sample is removed from
the latch using the manipulator, and is placed in the bottom por-
tion of the transport contaliner in Area 3A. The empty capsule is
hung on the latch, and the access port is closed. The removal
valve is opened, the top is lowered back into Area 3A and threaded
onto the bottom of the transport container, and it is withdrawn
into the carrier cask. The removal valve 1s then closed, and the
permissive switch turned off. The transport cask is loaded onto
a truck and taken to the analytical laboratory for analysis.

A decontaminated transport container and a transport cask are
brought back to the MSRE on the return trip. The transport con-
tainer is placed in the glove box, and the cask is placed on top -
of the sampler-enricher.

2 GENERAL DESCRIPTION OF. ADDING ENRICHING CAPSULES TO THE FUEL SYSTEM

The enriching salt as received at the MSRE is in arrays of 7
samples which are in sealed cans. These are stored in an approved
safe. The safe should be locked at all times except when removing
capsules. The safe can be opened by the head of the operations
department, the MSRE engineer responsible for S5 accountability

or the ORNL shift supervisors. The engineer responsible for o0 .
Approved byv,fi?22fl§zaxw%¢n_ 6A-3
| V 9/8/65

accountability will take care of the preliminary preparations of
the capsules. This will consist of opening the can, weighing the
array, cutting the capsules apart, weighing each individual capsule,
and attaching a latch key to each. These will then be put back
into the safe.

When it is necessary to add a capsule to the system, written
instructions will be issued giving the capsule number to be added.
This capsule is then removed from the safe and transferred to the
glove box. After weighing, holes are drilled through the capsule
to allow the salt to drain when inserted into the fuel pump. The
capsule is then reweighed and placed in a transport container. The
sampler-enricher permissive switch is turned on, and the transport
container is lowered through a transport cask on top of the sampler
into the removal seal area. The removal valve is then opened, and
the transport container lowered into Area 3A. The top of the trans-
port container is unscrewed and then is partially withdrawn, and -
the removal valve is closed. The access port is then opened, and
the empty sampling capsule is removed from the latch and placed
in Area 3A. The enriching capsule is hung on the latch, and the
access door is closed. The operational and/or the maintenance
valve 1s opened, and the capsule is inserted into the pump bowl.
After allowing sufficient time for the salt to melt, the capsule
is withdrawn into Area 1C, and the operational or maintenance valve
is closed. The access port is then opened. The empty enricher
capsule is placed in the bottom part of the transport container,
and the empty sample capsule ig hung on the latch in Area 1C. The
access port is closed, and the removal valve is opened. The top
is threaded onto the bottom of the transport container, and it is
withdrawn into the carrier cask. The removal valve is then closed,
and the permissive switch turned off. The transport cask is loaded
onto g truck and taken to the analytical laboratory for weighing
of the empty enriching capsule. A decontaminated transport con-
tainer and a transport cask are brought to the MSRE on the return
trip. The transport container is placed in the glove box, and the

cask is placed on top of the sampler-enricher.
Approved by 3;25fi3&€f%?5%2&1 6A3-1
i v 8-23-65

6A FUEL SYSTEM SAMPLING AND ENRICHING
Advise Analytical Isb.

 

Sample No. Date Time

 

 

 

3 FUEL SYSTEM SAMPLING CHECK LIST

 

Initial
3.1 Prepare to use sampler-enricher. (One operator can do
3.1.) (Control Room)
3.1.1 Notify shift supervisor (or comtrol room super-
visor) that sampling is ready to start.
3.1.1.1 Turn permissive switch on.
3.l.1.2 Check prior check list for number of the
capsule that is on the latch. Capsule Number
is _ Wt. of capsule
(Sampler Enricher)
NOTE: 3.1.2.1 and 3.1.2.2 are to be omitted except for the first
sample taken each week.
3.1.2 Check initial conditions.
3.1.2.1 Read pressures at sampler.

Removal valve buffer (Green pen 670B)

Access port buffer (Red pen 669B)

Area 3A (Green pen AR 3A)

Area 1C (Red pen 1CE)

Operational valve buffer (Red pen 668C)

Meintenance valve buffer (Green pen

6550)
PI-590 He supply (hold at 40 & 1 psig)

PI-664B (#1 Leak Detector)
PI-666B (hold at 20 £ 1 psig)
PI-6L4YB (#2 leak detector)
Approved byxfiflff

 

64 3-2
8-23-65

Initial

PI-522B Pump bowl - must be less than

10 psig before continuing.
3.1.2.2 Check valves

V-66k
V-6386
V-673
V-687
V-641
V-662
V-676
V-661
V-668
V-672
V-666
V-6L44
V-654
V-642
V-6L43
V-665
V-640
V-685
V-683
V-6U45
V-6U46
V-669
V-670
V-668
V-655
V-65T7
V-671
HS-668B
HSvV-678A
Hov-678RB2

Open

 

LT P

a
|

Closed

 

2I-668B on__

|
 

Approved by 'fifi?bafligéficy,fw1 6A3-3

 

8-23-65
Time Initial
Open Closed
 HSV-677A
HSV-66TA
HSV-6T78E
HSV-659B

3.1.2.3 Prepare equipment
Turn illuminator from 50v.to 120v
Turn vacuum pump #1 on
Turn vacuum pump #2 on
Adjust manipulator cover pressure PI-680 to

6" Hg vacuum. If high, open V-680 to adjust.

Open
V-650 PI-650@ 80 psig
HS-542A  ZI-542A on
HS-675A _ 7ZI-675A on

3.2 Isolate sample. (2 operators required)
3.2.1 Purge area 1C.
3.2.1.1 "Off-gas permissive' light on.
3.z2.1l.2 Evacuate area 1C for 2 minutes by opening
HCV-678E
HSV-678B2
HSV-6T8A
Check that PR-1C pressure starts decreasing
Time started Stopped
3.2.1.3 Close HSV-678A
HSV-678B2
HSV-6T78E
3.2.1.4 Pressurize using V-657 until PR-1C reads

 

15 psia.
3.2.2 Insert capsule into pump bowl.

3.2.2.1 Pump bowl pressure PIL-52ZA reads

Psig.
Approved by ;%’m/»ULL 6A3-4
</ ' 8-23-65

Time Initial

 

3.2.2.2 Adjust pressure in area 1C to pump bowl
pressure * 1 psi using V-657. Read on PR-1C
in psia {14 + psig).

3.2.2.3 Manipulator cover on. PI-680 reads 6 in.
Hg. vacuum.

3.2.2.4 "Removal valve closed" light on.

3.2.2.5 "Access port closed" light on.

3.2.2.6 Open operational valve by turning switch
to open and hold until closed position light
goes off.

3.2.2.7 Closed position light for maintenance
valve must be off. If it is not off, open
valve by turning switch to open and holding
until closed position light goes off.

3.2.2.8 Turn capsule drive motor switch to insert
and hold until capsule position indicator
reads 17 £t 5 in. or until upper limit goes
off, whichever is first. Time

3.2.3 Partially withdraw and freeze sample.

3.2.3.1 Leave capsule in pump bowl one minute.

3.2.3.2 Withdraw capsule 18 % 1 inches by turning
capsule drive motor switch to withdraw until
capsule position indicator reads 15 ft 11 in.
1f position indicator should stop at any time,
immediately release switch and notify shift
supervisor. Time

3.2.3.3 Wait 10 minutes for salt to solidify.

 

 

Time start Time stop
3.2.4 PFinish withdrawal and isolate capsule.
3.2.4.1 Finish withdrawing capsule into Area 1C
by turning capsule drive motor switch to with-
draw and holding. If position indicator should

stop at any time, immediately release switch

‘e
Approved byifififaeazfiég;jufflm_ 6A3-5

8-23-65

Time Initiagl

 

Loocandinotifyoshif € supervisor. Releage switch
when position indicator reads O or lower limit
light goes off, whichever is first.

3.2.4.2 Close operational valve by turning switch
to close and holding until cpen position light
goes off.

3.2.4.3 Notify control room that sample is in
Area 1C.

3.2.5 DPrepare to move capsule into Area 3A.

(Glove Box)

gHigh Bay)

3.2.5.1 Obtain a clean capsule and carefully
weigh it. Capsule number Welght

3.2.5.2 O0Obtaln decontaminated transport contalner.

3.2.5.3 Remove bottom part of transport container.

3.2.5.4 Check that O-rings are in good condition.

3.2.5.5 Place capsule into bottom plece with
cable extending above the sides.

3.2.5.6 Insert bottom part containing the capsule

into the top and engage about one thread.

3.2.5.7 Attach removal tool to tTransport con-
tainer using gasket to seal the joint.

3.2.5.8 Check that the pieces are aligned and
tightly joined together.

(Sample Enricher)

NOTE: Any time personnel enter restricted area omn top of 5. K.,

H. P. procedures must be followed.

3.2.5.9 Check that transport cask is in place on
top of sampler-enricher.

3.2.5.10 Check the aligrment.

3.2.5.11 Open bottom drawer of transport cask.

3.2.5.12 Insert transport contairer and removal

tool into the transport cask.
Approved by flé{%m 6A3-6

8-23-65

Time Initial

 

3.2.5.13 Lower transport container through removal
seal and lock in position.
3.2.5.14 Open HCV-666D, removal seal buffer.
3.2.5.15 Evacuate removal area for 1 min. using
HCV-679A. PI-6T1B should respond immediately.
3.2.5.16 Pressurize removal area to 7 % 2 psig
using V-6T71.
3.2.5.17 Repeat steps 15.
Repeat steps 16.
3.2.6 Purge Area 1C.
3.2.6.1 "Off-gas permissive" light on.
3.2.6.2 Read RI-6T8C RI-678D
3.2.6.3 Purge Area 1C with helium for 5 minutes
by opening HSV-66T7A
HSV-6T78B2
HSV-6T78A
V-657
(a) Time started
(b} After ~ 30 sec. read RI-678C

—_— 7
RI-678D
(¢) After ~ 5 min. read RI-678C ,
RI-678D . If not less than

30 MR/hr notify the shift supervisor.
(d) Time purge stopped
3.2.6.4 Close V-657
HSV-66TA
3.2.6.5 Evacuate Area 1C for 2 minutes by open-
ing HCV-6T8E
HSV-678B2
HSV-678A
Check that PR-1C responds immediately.
3.2.6.6 Close HSV-678A
HSV-678B2

*
Approved by,p-fi ”"% \ ';»QM-] 6a3-T7
8-23-65

Time ITrnitial

3.2.6.7 Pressurize through V-657 until PR-1C

 

reads L5 psia.
3.3.1 Purge Area 3A.
3.3.21.1 "Off-gas permissive” light on.
3.3.1.2 Evacuatbe buffer betwzen boots until PI-682
stops decreasing by opening HV-682
Close V-682
3.3.1.3 Evacuate manipulator cover to 8 in. Hg.
vacuum by opening V-680
3.3.1.4 BEvacuate Area 3A until PR-3A <2 psia by
opening V-680 , HCV-678E , and
HSV-67T7A
IMPORTANT: Watch boot to see that the pressure differential
between cover and 3A does not burst the boots. 1If koot starts
enlarging close HSV-67TA until it starts to collapse.
3.3.1.5 Close HCV-6T8E

HSV-6TTA
V-680
3.3.1.6 Pressurize by opening V-672 and.
throttling through V-663 until PI-680

reads O psig and PR-3A reads 1k psia.
IMPORTANT: Watch boot to prevent it from enlarging too much.
If it starts swelling throttle through V-663. When pressurized,
boot must not be collapsed against manipulator.
3.3.1.7 Close V-663 when PI-680 reads O psig.
Close V-672 when PR-3A reads 1l psia.
3.3.2 Move capsule into Ares 3A.
3.3.2.1 Evacuate buffer between manipulator boots
until PI-682 stops decreasing using V-682.
3.3.2.2 Adjust Area 3A pressure to 0 _ g psig.
3.3.2.3 Adjust manipulator cover pressure Lo O
psig using V-663 and V-672.

3.3.2.4 Remove manipulator cover.
Approved by -ZoF B ens iy 6A3-8
= v

8-23-65

Time Initial

 

3.3.2.5 Remove manipulator arm retainer.

3.3.2.6 Check that manipulator arm moves freely
through slide. Do not force. If it does not,
check that boot is not collapsed against arm.
If it is, reduce pressure slightly by opening
HCV-678E and HSV-67TA briefly.

3.3.2.7 "Access port closed" light on.

3.3.2.8 "Maintenance cor Operating valve' closed
1ight on.

3.3.2.9 "Removal seal closed” light on.

343.2.10 Open removal valve by holding switch to
open until close position light goes off.

3.3.2.11 Lower transport container into Area 3A.
It must fit over cross on floor. Use the
manipulator if necessary to guide into position.
The transport container should move freely
through the seal.

3+3.2.12 Open transport container by turning
removal tool counterclockwise until the
threads are disengaged.

3¢3.2.13 Carefully withdraw the top of the trans-
port container through the removal valve and
lock in position. Check that the bottom part
remains on the cross. Use manipulator if
necessary. Check that the capsule remains in
the bottom.

3.3.2.14 Close the removal valve by holding switch
to close until open position light goes off.

3«3.3 DMove full capsule into Area 3A.

3.3.3.1 Check that PR-3A is 14 psia.

3¢3.3.2 Remove empty capsule from transport
container.

3.3.3.3 Adjust Area 1C pressure to O psig.

iy
 

Approved by qfifiézeaztja%pflh¢fl1j 6A3-9
v 8-23-65

Time Initial

 

() If PR-1C is less than 1k psia, adjust
using IV-657 until PR-1C reads 1lh4 psia.
(b) If PR-1C is greater than 14 psia, adjust
using HCV-678E
HSV-678B2
HSV-6784
until PR-1C reads 14 psia.
3.3.3.4 "Lo diff. pressure - Area 1C" alarm must
‘be of f.
333.3.5 '"Main. or Oper. valve closed” light on.
3.3.3.6 "Removal valve closed” light on.
3.3.3.7 Open access port by turning HS-651A
to open.
3.3.3.8 Check that access port is open.
If access port does not open, see unusual
operating procedures. (6A-7)
3.3.3.9 1ift full capsule oubt of Area 1Clinto
Ares 3A.
3.3.3.10 Release full capsule key from latch.
3.3.3.11 Does this capsule contain salt?
If capsule does not contain salt, notify
ghift supervisor.
3.3.3.12 Place the full capsule into the bottom
of transport container. Insert empty capsule
key into drive unit latch while the capsule
remains outside access port and in Area 3A.
After checking that key is in vertical posi-
tion, place capsule in Area 1C being certain
that key remains in place before capsule is
released from manipulator.
3.3.3.13 Check that key is in latch and that cap-

sule is hanging straight down.
8-23-65

Approved bY~fi¢’35?2>fi§9297/#4/14 6A3-10
I

Time Initial
3.3.3.14 Withdraw manipulator hand from Area 1C

 

s0 that it will not interfere with shutting
door.

3.3.3.15 Close access port by furning EHS-651 to
closge and hold for 15 seconds to allow both
sets of clamps to close.

3.3.3.16 Check that all six clamps are closed.

3.3.4 Move capsule out of Area 3A.

3.3.4.1 "Operational or Maintenance valve" closed
light on.

3.3.4.2 "Removal seal closed" light on.

3.3.4.3 '"Access port closed” light on.

3.3.4.4 Open removal valve by turning switch to
cpen and holding until closed position light
goes off.

3.3.4.5 Slowly insert removal tool into Area 3A
observing that the top of the transport con-
tainer fits over the bottom and the capsule
wire remains inside in place.

3.3.4.6 Seal the two pleces together by rotating
the removal tool handle clockwise until the
top touches the stop on the bottom.

3.3.4.7  Withdraw removal tool assembly through
removal valve and lock in position. (HP
surveillance required for steps 3.3.4.7
through 3.3.4.12.)

3.3.4.8 Close the removal valve by turning switch
to close and holding until open position light
goes off.

3.3.4.9 PFinish withdrawing transport container
into cask. Do not pull btransport container

above the cask. Lock in top position.
Approved by fi /9/ ""/r;z 241,44 6A3-11

3.3

8-23-65

 

Time Initial
3.3.4.10 Close drawer in cask.
3.3.4.11 Remove removal to00l.
3.3.4,12 Lock transport container in cask.
3.3.4.13 Close HCV-666D, removal seal buffer.
3.3.4.14 Replace retainer on manipulator arm.
3.3.4.15 Replace cover on manipulator.
3.3.4.16 Adjust manipulator cover to 6" Hg
vacuum using V-680.
3.3.5 Purge Area 1C.
3.3.5.1 "Off-gas permissive” light on.
3+3.5.2 Evacuate Area 1C for 2 minutes by opening
HCV-678E
HSV-6T78B2 _
HSV-678A
PR-1C should respond immediately.
3.3.5.3 Close HSV-6784
HSV-6T78B2
HCV-6T8E |
3.3.5.4 Pressurize using HV-657 until PR-1C
reads 15 psia.
Prepare for stand-by conditions. (One operator can
do 3.3, 3.4, and 3.5.)
3.3.1 Prepare Egquipment
Turn illuminator to 50v.
Turn off vacuum pump #1.
Turn off vacuum pump #2.
Turn off HS-542A, HS-6T5A, V-650A.
3¢3.2 Nofity shift supervisor (or control room
supervisor) that sampling is finished.
3.3.2.1 Give time sample isolated. (This is the
time recorded in step 3.2.3.2).
3.3.2.2 Give sample number.

3.3.2.3 Turn off permissive switch.
 

Approved E¥¢é?f€;%;222/!ygflh O6A3-12

8-23-65

Time , Initial

3.4 Removing sample from MSRE Area.
3.4.1 Remove transport cask from top of sampler With
crane. Lower the transport cask through the Bilko
doors at the south end of High Bay into the speciar

can on truck.

3.4.2 Bolt transport cask ingide can.

—p—
————

3.4.3 Bolt 1lid in place on top of can.

3.4.4 Have H.P. ckay removing container from MSRE
Area.

3.4.5 Take sample to Building 2026. Have HP or
another operator follow the sample truck to the
analytical lab. If this is not possible, notify
control room supervisor upon leaving 7503, and
call him immediately on arrival at 2026. If the
lapsed time 1s longer than 10 minutes, the control
room supervisor is responsible for immediately
determining 1f difficulty was encountered en route.

3.5 Return to 7503.

3.5.1 Bring a decontaminated transport container and
a transport cask back to 7203.

3.5.2 Place transport container in glove box; take
it apart and turn on helium purge.

3.5.3 Place transport cask on sampler-enricher.

ty
 

HAL-1
9/2/65

 

Advise Analytical Iab. _ Tnitial
L FURL SYSTEM ENRICHING CHECK LIST
(Glove Box)

h,1

L.2

Prepare enriching capsule (one operator can do

L.l and 4.2)

4.1.1 Obtain the proper capsule from the safe (re-
lock safe) and place it in the glove box.

L.1.2 Weigh the capsule.
Capsule number ___ ; Weight

h.1.3 Drill 5 holes in the enriching capsule,
7/32 in. dis in the center of the bettow and 2
rows of 2 holes each 7/32 in. dia in the sides.
The rows shall be about 1-1/2 and 4 in. from the
bottom. Creat care must be taken in drililing tc
remove as little salt as possible.

L.1.4 Catch all shavings and store as salvage.

4.1.5 TInspect each hole for metal chips. Remove if
fTound,

L.1.6 Determine and reccrd the weight of the capsule
assembly after drilling the holes. ___  g.

4,1.7 Obtain decontaminated transport container.

4.1.8 Remove bottom part of transport container.

4.1.9 Check that O-rings are in good condition.

4.1,10 Place capsule into bottom piece with cable
extending abcocve the sides.

4.1.11 Insert bottom part containing capsule into
top and engage about one thread.

Prepare to use sampler-enricher.

(Control Room)

4.2.1 Notify shift supervisor (or control room super-
visor) that enriching is ready to start.

h,2.1.1 Turn permissive switech on.
Approved by, / Ay 6Ak-2
z é 9/2/65

(High Bay Area)

Time

 

Initial

4.2.2 Prepare eguipment.

Turn illuminator from 50v to 120v
Turn vacuum pump #1 on

Turn vacuum pump #2 on

Open:
V-650 _ PI-650 @ 80 psig
HS-5h2A  zI-5L2 on
HS-6754 _ ZI-675 on

4.3 Move capsule into enriching position (2 operators

required).

4.3.1 Prepare to move capsule into area 3A.

(High Bay Area)

L.3.

L.3.

1.1 Attach removal tool to transport con-
tainer using gasket to seal the joint.
1.2 Check that the pieces are aligned and

Joined together.

.1.3 Check that the transport cask is in

place on top of sampler-enricher in proper

alignment.

.1.4 Check the alignment.
3.1.5 Open bottom drawer of transport cask.

3.1.6 TInsert transport container and removal

tool into transport cask.

1.7 Lower transport container through removal

seal and lock in position,

3.1.8 Open HCV-666D, removal seal buffer.

3.1.9 Evacuate removal ares using HCV-6T9A for

about 1 minute. PI-671B should respond

immediately.

.1.10 Pressurize removal area to 7 £ 2 peig

through HV-671.

.1.11 Repeat steps 10 , 11

o
 

/%4 EAL-3
9/2/65

Time

 

. Initial
4.3.2 Move capsule into area 3A.
4.3.2.1 Evacuate buffer between manipulator boots
until PI-682 stops decreasing using V-682.
4,3.2.2 Area 3A pressure Q0 = 1 psig.
(a) TIf PR-34 is less than 14 psia, adjust

by opening V-663 __ and V-672 until PR-3A
) is 14 psia.
(b) If PR-3A is greater than 14 psia adjust
’ by opening HCV-678E _ , HSV-677A ___, and
. V-680 _ until PR-3A is 1k psia and PI-680
is O psig.
. Close V-680 .

Close HCV-678E __
Close HSV-6T7TA
4.3.2.3 Adjust manipulator cover pressure to O
psig by opening V-663 and V-672.
4.3.2.4% Remove manipulator cover.
4,3.2.5 Remove manipulator arm retainer.
4,3.2.6 Check that manipulator arm moves freely
through slide. Do not foree. If it does not,
check that boot is not collapsed against
arm. If it is, reduce pressure in area 3A
slightly by opening HCV-6T8E and HSV-67TA
momentarily.
- 4.3.2.7 "Access port closed" light on.
4.3.2.8 "Main or oper. valve closed" light on,
4.3.2.9 "Removal seal closed'" light on.
| 4.3.2.10 Open removal valve by holding switch
to open until closed position light goes off.
| L.3.2.11 ILower transport container into area 3A.
It must fit over cross on floor. Use the

manipulator if necessary to guide into posi-

tion. The transport container should move

freely through the seal.
Approved by~¢?7;€%55?§;71“”’% 6AL-1

9/2/65

Time

 

Initial

L.3.2.12 Open transport container by turning re-
moval tool counterclockwise until the threads
are disengaged.

L.3.2.13 Carefully withdraw the top of the trans-
port container through the removal valve but
not the seal. Check that the bottom part
remaing on the cross. Use the manipulator
if necessary. Check that the capsule remains
in the bottom.

k.3.2.14 TLock the removal tool in position.

4.3.2.15 Close the removal valve by holding
switch to close until open position light
goes off.

%.3.3 Move capsule into Area 1C.

k.3.3.1 Check that PR-34 is 1k psia.

L.3.3.2 Adjust Area 1C pressure to 1k psia.

() If PR-1C is less than 14 psia, adjust
using V-657 until PR-1C reads 1k psia.,
(b) If PR-1C is greater than 14 psia, adjust
using

HCV-6T78E

HSV-678B2

HSV-6T78A
until PR-1C reads 14 psia.

4.3.3.3 "Io 4iff. pressure-area 1C" alarm must be

off. If on, reduce area 1C pressure per step

L.3.3.2(b).

.3.3.4% "Main. or oper. valve closed" light on.
.3.3.5 "Removal valve closed" light on.
.3.3.6 Open access port by turning HS-6T71A to open.

o=

.3.3.7 Check that access port is open. If access
port does not open, see unusual operating

procedures (6GA6).
Approved by¢§2§£§%§§%%%%hnt CAL-5
9/2/65

4.3,

Time

 

Initial
4.3.3.8 Remove sample capsule from latch and place
in Area 3A.

%,3.3.9 Remove enriching capsule from transport con-
tainer. 1Insert enriching capsule key into drive
unit lateh while the capsule remains outgide
access port and in Area 3A. Check that key is
in vertical position. Then place capsule in
Area 1C being certain that key remains in place
before capsule is released from manipulator.

4.3.3.10 Check that key is in the latch and that
capsule 1s hanging straight down.

4.3.3.11 Withdraw manipulator hand from area 1C o
it does not interfere with access port closing.

4.3.3.12 Close access port by turning HS-651A to
close and hold for 15 seconds to allow both
sets of clamps to close.

L.3.3.13 Check that all six clamps are closed.

4h.3.3.14 Replace manipulator arm retainer.

1]

4.3.3.15 Replace manipulator cover.
4.3.3.16 Adjust manipulator cover to 6" Hg vacuum
by opening V-680.
L Purge Area 1C.
L.3.4,1 "Offgas permissive"™ light on.
L.3.4.2 Evacuate Area 1C for 2 minutes by opening
HCV-6T78E
H3V-678B2
HSV-6T78A
Area 1C pressure should respond immediately.
4.3.4.3 Close HSV-6T78A
HSV-6T78R2
HCV-678E
L.3.4.k Pressurize using V-657 until PR-1C reads
1h psia.
GAL-6
9/2/65

Approved by

 

Time

 

Initial.

L.k Add enriching salt.
L.h,1 Insert capsule into pump bowl.

h.4.1.1 Obtain permission of control room super-
visor to insert the capsule at this time.

L.4.1.2 Pump bowl pressure PI-5224 reads  psig.

L.4,1.3 Adjust pressure in Area 1C to pump bowl
pressure * 1 psi using V-657. Read on PR-1C
in psia (14 + psig).

L.h.1.4 Manipulator cover on. PI-680 reads 6"
Hg vacuum.

4,4,1.5 "Removal valve closed" light on.

L.4b.1.6 "Access port closed" light on.

L.4.1.7T Open operational valve by turning switech to
open and hold until closed position light goes
off.

L.1.8 Closed position light for maintenance valve

=

must be off. If not, open valve by turning
switeh to open and holding until closed position
light goes off.

L.4.1.9 Turn capsule drive motor switch to insert
and hold until capsule position indicator reads
17 £t 4 in. or upper limit light goes off
whichever is first. Time capsule reaches lower
limit

hiol,2 Melt enriching salt from capsule.

L.4.2.1 1Ieave capsule in pump bowl for five
minutes. Start = Stop
Time capsule removed from pump bowl

L., 2,2 Withdraw capsule about 12 inches.

h.L.2.3 Reinsert the capsule into the pump bowl.

h.h.2. bk leave capsule in pump bowl for one minute.

‘e
6AL-T
9/2/65

 

Time

 

Initial
4.k.3 Withdrawal and isolate capsule.
h.h,3.1 Withdraw capsule into Area 1C by turning
capsule-drive-motor switch to withdraw and
and holding. If position indiecator should
stop at any time, immediately release
switch and notify shift supervisor. Release
switeh when position indicator reads O or
lower limit light goes off whichever is first.
4L.L.3.2 (Close operational valve by turning switch
to close and holding until open position
light goes off.
L.4.3.3 Notify control room supervisor that
addition is compilete.
h.h.L Purge Area 1C.
L.h.h,1 Offgas permissive light on.
4. h.h.2 Read RI-678C ___ RI-678D
b.4.4,3 Purge Area 1C with helium for 5 minutes
by opening '
HSV-66TA
HSV-678B2
HSV-6T78A
V=657
(2} Time started
(b) After ~ 30 sec read RI-678C

 

RI-678D .
(c) After ~ 5 min. read RI-676C
RI-6T8D ___ . &

If not less than 30 MR/hr notify
shift supervisor.

(a) Time purge stopped
Loh k.l Close V-675 , HBV-66TA
 

FAL-8

 

9/2/65
Time
Initial
L.4.h.5 Evacuate area 1C for 2 minutes by opening:
HCV-6T8E
HSV-678R2
HSV-6T76A

PR-1C should respond immediately.

4.h.h.6 Close HSV-6T8A ___, HSV-678B2 .

L.4b.L.7T Pressurize using V-657 until PR-1C
reads 14 psia.

L.4.5 Purge Area 3A,

L.4.5.1 "Offgas permissive" light on.

L.4.5,2 Evacuate buffer between boots until PI-682
stops decreasing using V-682 .

4.4.5.3 Evacuate manipulator cover to 8 in. Hg
vacuum by opening V-680 .

L.h.5.4 Evacuate area 3A until PR-34 <2 psig
using V-680, _ , HCV-678E _ and HSV-677A

 

IMPORTANT: Watch boot to see that the pressure differential
between cover and 3A does not burst the boots. If
boot starts enlarging, close HSV-67T7A until it starts
to collapse.,

b.4.5.5 Close HCV-678E __ , HSV-6TTA

V-680 .
L.4.5.6 Pressurize Area 3A by opening V-672
and throttling through V-663 until

PI-680 reads O psig and PR-3A reads 1k psia.
IMPORTANT: Watch boot to prevent it from enlarging too much.
If it starts swelling, throttle through V-663. When
pressurized, boot must not be collapsed against
manipulator.
L.L.5.7 Close V-663 when PI-680 reads O psig.
Close V-672 when PR-3A reads 1L psia.

‘e
 

6AL~9
9/2/65

Time

 

Initial

4.5 Remove capsule from sampler.

h.5.1

L,

= o o

Move capsule into area 3A.
5.1.1 Area 3A pressure 0 = 1 psig
(PR-34 = 1k psia) ( see section b.3.2.2

if adjustment necessary).

.5.1.2 Evacuate buffer between manipulator boots

until PT~-682 stops decreasing using V-682.

.5.1.5 Remove marnipulator cover.
.5.1.4 Remove manipulator arm retainer.

.5.1.5 Area 1 pressure Q0 * 1 psig (see

Section 4.3.3.2 if adjustment necessary).

.5.1.6 '"Io differential pressure-area 1C"

alarm off.

.5.1.7 "Removal valve closed" light on.

.5.1.8 "Operatiocnal or maintenance valve closed”

light on.

.5.1.9 Open access port by turning switch to

open.

.5.1.10 Check that asccess port is open.

.5.1.11 Life capsule out of Area 1C into Area 3A.
.5.1.12 Release capsule key from latch.

.5.1.13 Does the capsule contain salt?

If "Yes" notify shift supervisor.

.5,1.14 Place the capsule into bottom of trans-

port container upside down.

.5.1.15 Attach empty sample capsule to latch

being certain capsule key is properly locked

in place arnd the capsule is hanging properly.

.5.1.16 (lose access port by turning switch to

close and holding for 15 sec to allow both

sets of clamps to close.

.5.1.17 Check that all six clamps did close.
Approved by fl}%flm 6!}1726&)
9/2/65

Time

 

Initial
4.5.2 Move capsule into transport cask.

4L.5.2.1 '"Operational or maintenance valve closed"
light on.

L.5.2.2 '"Removal seal closed” light on.

L.5.2.3 "Access port closed" light on.

L.5.2.4k Open removal valve by turning switch to
open and holding until closed position
light goes out.

h.5.2.5 Slowly insert removal tool into Area 3A
observing that the top of the transport
container fits over the bottom.

4.5.2.6 Seal the two pileces together by rotating
the removal tool handle clockwise until the
top touches the stop at the bottom.

L.5.2.7 Withdraw removal tool assembly through
removal valve, but not removal seal, lock
in position. (HP surveillance required for
steps 4.5.2.7 through 4.5.2.12)

L.5.2.8 Close the removal valve by turning switch
to close and holding until open position
light goes out.

L.5.2.9 TFinish withdrawing transport container
into cask. Do not pull the transport con-
tainer above the cask! Lock in top position.

L.5.2.10 Close drawer in cask.

4.5.2.11 Remove removal tool.

4.,5.2.12 Lock transport container in cask.

L.5.2.13 Close HCV-666D, removal seal buffer.

4.5.2.14 Replace retainer on manipulator arm.

4.5.2.15 Replace cover on manipulator.
4.5.3 Purge Area 1C.
4.5.3.1 "Offgas permissive" light on.

e
Approved byfi %»—ié:gfi Mg 6AL-11
9/2/65

»

Time
Initial
4.5.3.2 Evacuate Area 1 C for 2 minutes by opening
HCV-678E _ , HSV-67832 _ , HSV-6T78A _ .
PR~1C should respond immediately.
4.5.3.3 Close HSV-6T8A  , HSV-678B2 _
HSV-678E .
4.5.3.4 Pressurize using V-657 until PR-1C

reads 15 psia.

L.6 Prepare for standby conditions. (One operator can
do 4.6, L.7 and L4.8.)
4.6.1 Prepare equipment.

k.7

L.6.

Turn illuminator to 50v ___
Turn off vacuum pump #1
Turn off vacuum pump #2 .
Turn off HS-542A, HS-6754, V-650A .
2 Notify shift supervisor (or control room
supervisor) that enriching is finished.
4.6.2.1 Give time salt added . (This is
time recorded in L.4.2.1.)
4.6,2.2 Give Capsule No.

4.6.2.3 Turn off permissive switech.

Removing sample from MSRE Area.

L.7.

L.7.
L.7.
L.7.
L.7.

1 Remove transport cask from top of sampler with
crane. Lower the transport cask through the
Bilko Doors at the south end of high bay into the
special can on truck.

2 Bolt transport cask inside can.

3 Bolt 1lid in place on top of can.

4 Have HP okay removing container from MSRE Area.
5 Take empty capsule to Building 2026 for
weighing. Have HP or another operator follow the
sample truck to the analytical lab. If this is not
possible, notify control room supervisor upon

leaving 7503, and call him immediately on arrival
Approved bY,azzfgéZ%;figzfla

L.8

Time

L.7.5 (continued)
at 2026. If the lapsed time is longer than
10 minutes, the control room supervisor is re-
ponsible for immediately determining if diffi-
culty was encountered en route.

Return to T7503.

L,8.1 Bring a decontaminated transport container
and a transport cask back to T7503.

4.8.2 Place transport container in glove box; take
it apart and turn on helium purge.

%.8,3 Place transport cask on sampler-enricher.

6AL-12
9/2/65

Initial
- :"r}’
Approved by;/ffl%flyhfgflfi?flx 6AL5-1
9/29/65

Date Time

 

 

6A FUEL SYSTEM SAMPLING AND ENRICHING

5 FUEL SYSTEM SAMPLER STARTUP

I the sampler enricher has been chut down for long

 

periods or extensive maintenance has been performed on the
sampler, a thorough check should be made to assure that
it i8 in condition tc take samples.
5.4 - Startup Check Lisgt
(Control Room)

 

5.1.1 Notify chifv superviscr of the start of start-

up procedures.
(High Bay Area)

5.1.2 Check that re work is in progress in the sampler-
enricher panel pcards or Junction boxes. All junction
box covers shouid be closed.

(Control Room)

5.1.3 Energize the following circuits and remove the

"do not operate" tags:
IPP A3 Cir 2 (Foxboro ECI power)
IPP 5 Cir 21 (vacuum pumps)
IPP 5 Cir 25, 27, 29 (208v 36 power)
TPP 1 Cir 10 (4Bv DC power)
IPP 2 Cir 16, 18 (Control power)
(High Bay Area)
5.1.4 Open the following valves:

v-66Lk  v-6ih  v-683
v-673 _ V-65h  V-669
v-6h1  v-6h2  V-670
v-662 _ V-643  V-668
V-676 V=665 V=655
7-661 V-6L0

V-638
i
Approved by _éfifiézi?fivffl/wfl,

5.1.5 Reset the following:

RM-678C

RM-678D

RM-675A 1ight 14 377 on

RM-675A 1light 1B 377 on
5.1.6 Turn on HS-668B 1light ZI 668B on
5.1.7 Purge area 1C per check list 6A3 sec. 3.2.1.
5.1.8 Purge area 3A per check list 6A3 sec. 3.3.1.
5.1.9 Check that the vacuum pump is turned off .

5.1.10 Check out all instrumentation per section LH.

"
Approved by ,fjgfizi%/&fiéfinfl@nl 6A6-1
’ V 9/29/65

Date Time

 

 

Init.
6A FUEL SYSTEM SAMPLING AND ENRICHING

6 FUEL SYSTEM SAMPLER SHUTDOWN

If the sample enricher is to be shut down for long periads

 

or extensive maintenance is to be done on the sampler, pre-
cautions should be taken to assure that the sampler is adequately
secured.
6.1 Shutdown Check List
(Control Room)
6.1.1 Notify shift supervisor of the start of shutdown

 

procedures.
(High Bay Area)
6.1.2 Close the maintenance valve by holding HS-MV at

close until the open position light goes off.

6.1..3 Check that the operational and removal valves

are closed and the access port isshut.

|

6.1.4 Adjust the pressure in area 1C to O psig.

6.1.5 Adjust the pressure in area 3A and the manipu-
lator cover to O psig.

6.1.6 Close all hand valves that are located in the

|

sampler-enricher panel boards.
(Control Room)
6.1.7 Turn off the following electrical circuits and

i

tag each "do not operate’.
IPP A3 Cir 2 (Foxboro ECI power)
IPP 5 Cir 21 (vacuum pumps )
IPP 5 Cir 25, 27, 29 (208v 3¢ power)
IPP 1 Cir 10 (48v DC power)
IPP 2 Cir 16, 18 (Control power)

T
da
e

 

AT .
Approved byrfigff!-f**“y&f~n{ OAT-1
V 10/20/65
GAT
UNUSUAL OPERATING CONDITIONS
for the

SAMPLER-ENRICHER

During operation of the sampler-enricher, one or more of the com-
ponents may fail to operate properly. The following procedure attempts
to list the failures most likely to occur and gives operator action
to be used to overcome the difficulty. Whenever corrective action is
required, an entry should be made in the console log describing action
taken.

T.1 The access port fails to open when HS-651A is turned to "open".

7.1.1 If all six Knu-Vise operators have opened and the access port
remains closed, increase the pressure in Area 1C to about 2 psi
above the pressure in Area 3A using V-657. Should the port
still remein closed, check again for some obstruction in Area 3A
that would prevent opening.

7.1.2 If one or more of the Knu-Vise operators fail to open when
H3-651A is turned to "open', turn the switch to "closed" and
hold it for 15 sec to allow all operators to close. Walt about
2 minutes for the pressure in line 650 to build up through
FE-650D. Then, turn HS-651A to "open" again. If the operators
still fail to open, gently push the knob on the center pin of
the operator linkage which remained closed with the manipulator
while holding HS-651A at "open". The operator should open
easily.

7.1.3 If all six operators fail to open, check that all interlock
circuits are satisfied: '"removal valve closed" light on,
"operational or maintenance valve closed" light on, "1C pressure
greater than 3A" alarm off, and fuel-pump bowl pressure 1s less
than 10 psig. Next, check that PI-650B indicates at least
75 psig. Check that HSV-651A, 6524, and 653A function properly.
Failure of any of these to seat or to open properly will cause
a malfunction of the operators. Also check that HSV-675A1 is

open.
Approved by

7.2

T3

7.4

TS

6AT-2
10/20/65

 

The access port fails to close when HS-651A is turned toc "close".

7.2.] If the Knu-Vise operators fall to close properly, check that
PI-650B indicates at least 75 psig, HSV-651A, 6524, and 653A
are seating and opening properly, HSV-675A1 is open, and there
are no obstructions in the way.

The access port buffer pressure fails to increase properly when the

access port is closed.

7.3.1 If the buffer pressure fails to ilncrease properly, turn
H3-651A to "close" and hold for 15 sec to seal any operators
that had failed to lock shut.

T7.3.2 If step 7.3.1 fails to correct the difficulty, open the access .
port and check for dirt or damage on the sealing surface on the
gaskets.

Removal valve fails to open or close.

T.4.1 If the removal valve fails to open when HS-RV-A is turned to
open, check that all interlocks are satisfied: 'removal seal
buffer pressure’ light on, "access port closed" light on, and
"operational or maintenance valve closed" light on. If the
interlocks are satisfied, check the HCV-RV-Al and HCV-RV-A2
are cperating properly. A flow of air from the vent port :
indicates a valve failure. Another possible cause of trouble
would be slipping of the air operator on the valve body.
Failure of the limit switches would indicate improper valve
operation when it is actually working satisfactorily. >

T.4.2 TIf the valve fails to close properly, check for an obstruction
in the valve,

The buffer gas pressure to the maintenance or the operational valve

decreases slowly during standby.

7.5.1 The pressure should bleed down only if the supply is blocked.

Block valves in the helium lines to the operational and mainte-
nance valves close upon receiving high radiation in the sampler
offgas and/or high fuel-pump bowl pressure (>10 psig). If

radiation caused the trip, reset the monitors by pushing reset
Approved byfijézja%gfizy“fl/”\~ BAT-3

7.6

T.T

V 10/20/65

7.5.1 (continued)

buttons $-113 and/or S-114. If the radiation level is low this

will reopen the valves. If the FP bowl pressure is high, the

pressure receding below 1C psig will automatically reopen the
valves,

Failure of the manipulator-boct buffer to hold a vacuum indicates
a leak in the buffer system. If all tubing fittings are leak tight,
one or both boots have a hole and must be replaced.

High radiation in the contaimment areas which will be detected
by RE-6T75A and RE-675RB indicates a release of gaseous activity to the
building ventilation system. Block valves on all sources of gaseous
activity close when either element trips. The following valves
close: HSV-6T78A; HSV-6T78B2; HSV-67TA; ESV-5L2A; HSV-675A; HSV-659B;
HSV-65TD; HSV-668B; and HSV-655B. To determine the source of activity,
close the hand switches controlling each of these valves. When the
radiation level area LA decreases sufficiently, reset the circuits
using S-113 and S-114. ILights 1A-377 and 1B-377 must be on. Then
open each possible source of activity ocne at a time walting to see
if that was the one. A suggested order to use is HS-668B which opens
H3V-668B, HSV-655B, HSV-657D, and HSV-657D, then HS-6T75A, HS-659B,
H3-5L42A, and HS-675A. HS-6T78B and HS-6T77 should be opened oae &t
a time with HS-678A closed. Corrective action will be determined

by the source of activity.
%
"-

9/29/65

 

6B COOLANT SYSTEM SAMPLING

The coolant sampler is designed to allow sampling without contami-
nating the salt with moisture or oxygen or endangering personnel due
to beryllium release. The primary components of the coolant sampler
are: a glove box located above the coolant cell, a transfer tube
connected to the coolant pump bowl, helium supply and vacuum pumps to
be used for purging, and a sample carrier which attaches to the top of
the glove box for inserting empty capsules and extracting full capsules.

Interlocks are provided to minimize dangerous operations. The
interlocking system is a "key interlock"” system in which one key must
be inserted and turned before the key necessary for the next operation
can be removed. The keys and locks are color coded to aid the operator.

A brief description of the manipulations necessary to remove a
sample is given in Section H6A 1. Purging operations which are utilized
are not covered in this description but are given in detail in the
sampling check list 6A 2. Startup of the coolant sampler is covered in
startup check list 6B 3, and shutdown of the coolant sampler for a sus-
tained duration is covered in 6B k.

Since cooclant sampling is considerably less hazardous than fuel
sampling, one operator is considered sufficient for normal coolant
sampling operations.

1 GENERAL DESCRIPTION OF SAMPLING THE COOLANT SYSTEM
Except for long reactor shutdowns or sampler maintenance,

the coolant sampler will be in standby condition when not in use.

The key which must be used to start the sampling operations will

be in a lock switch on the main countrol board. An empty capsule

will be hanging on the latch in the glove box. The glove port
access will be locked closed, and the vacuum pump and light will
be turned off.

At the start of the sampling operation, the key is removed
from the main bocard. At the coolant sampler, a check is made to
insure that pressures and valves are set properly to start the

sampling. Lights and vacuum pump are turned on.
Approved byfggfi;ji%gzgéfig/dgggw\k 6B-2
W/ 9/29/65

A clean, empty capsule is weighed in the dry box (near the
sampler-enricher). The capsule is placed in the sample carrier
and taken to the coolant sampler. It is then attached to the top
of the glove box.

The key which was removed from the control room is inserted
in the proper lock (the only one it will fit). Unlocking this
lock allows the removal of a key which is necessary in the next
cperation.

Using the key interlock system, valves are opened which con-
nect the pump bowl to the glove box. The empty capsule is lowered
into the pump bowl, a sample is obtained, and the salt-filled
capsule is withdrawn into the glove box. The valves opening into
the pump bowl are closed.

When the sample is isolated in the glove box, the glove port
access 1is opened. The empty capsule in the sample carrier atop
the glove box is inserted into the glove box. Using the glove
the operator switches places with the empty and full capsules.
The full capsule is then pulled into the sample carrier and the
valves are closed to isolate it. The glove part is relocked and
the coolant pump sampler is prepared for standby conditions.

The sample carrier with the full sample is taken to analytic
chemistry and the sample removed from the carrier. The carrier is

returned to the MSRE ares so it may be utilized again when needed.

t.
 

 

 

 

 

Approved bzfifljfgfiiijéifé?;ép*fia¢9y\\h_ éfizfil
4 9/29/65
6B COOLANT SYSTEM SAMPLING
Sample No. Date Time
Advise Analytical Iab. Init.
2 COOLANT SYSTEM SAMPLING CHECK LIST
c.l Preparstion For Sampling
(Control Room)
2.1.1 Notify shift supervisor (or control room super-
visor) of start of sampling. L
2.1.2 Obtain K1 from lock on MB-6. .
2.1.3 Read pump bowl pressure PI-528  psig. Pump
bowl pressure must be between 4 and 6 psig before
proceeding. .
2.1.4 Check prior check list for number of the capsule

(Hi Bay Area)
2.1.

2.1

201.
2.1.

2'1!

Zels
2‘19

that is on the latch. Capsule No.
Weight of capsule

5 At the coolant pump sampler record the following
pressures:
PI-CS-A
PI-C651
.6 Close red valves C-654%
C-657
C-661
7 Turn on light and start the vacuum pump.
8 Obtain capsule from glove box.
Capsule No. Capsule Weight
9 Open ball valve on carrier, push 1/4" rod down

until hook is through valve, hang capsule on hook,
withdraw rod and capsule into carrier, and close
ball valve.

1.0 Flace snple carrier in place above V-3.

11 Connect flexible line (C-664) to valve C-669

and open valve C-669 and ball valve on carrier.
Lt
e f’)') -~ e"’
4T s

Approved by % 1 Aten ER2L2
i ' R

 

2.1.12 Evacuate carrier for about 1 minute by opening
valves C-664 and C-662.

2.1.13 Close valve C-66L and watch PIC-66L. An increase
in pressure indicates a leak elther at the sliding
seal or the connection between the ball valves.

Stop leaks.

2.1.14 Pressurize carrier to about 5 psig using valve
C-670.

2.1.15 Close valves C-669, C-670, C-662, and carrier ball

valve.
2.2 Samgling

2.2.1 To purge glove box abtmosphere ending with box at

pump bowl pressure:

2.2.1.1 Insert Kl in V1, unlock open V1, lock open
with K2, and remove K2z.

2.2.1.2 Insert K2 in VZ, unlock, and open VZ.

2.2.1.3 Open blue valve C-662.

2.2.1.4 Evacuate for L minutes. Start
Stop

2.2.1.5 Close blue valve C-662.

2.2.1.6 Close V2, lock closed with K2, remove K2.

z.2.1.7 Insert K2 in V1, unlock, close, lock closed
with K1, and remove Kl.

2.2.1.8 Pressurize glove box to pump bowl pressure

9/29/65

Init.

ety

]

a

+ 0.2 psig using red and blue valve C-650. Read

on PI-C5-A
2.2.2 In order to insert capsule into pump bowl:

c.2.2.1 Insert Kl into No. 2 lock switch, unlock,
and remove Klh.

2.2.2.2 1Insert K4 in V4, unlock, open Vi, lock
open with K5 and remove K5.

2.2.2.3 Insert K5 in V5, unlock, open V5 slowly,
lock open with K6, and remove Kb.

te
-

.

e e

e ’ ’y ’ f,'/
Approved by;zzgf””-5f<;£g;i¢flfifl 6B2-3
Ve 9/29/65

Init.
2.2.2.4 Insert K6 in No. 3 lock switch and unlock.
2.2.2.5 Insert capsule into pump bowl by turning

capsule drive switeh clockwise to insert.
Watch cable during insertion. If cable does
not remain straight, stop inserting, withdraw
partly and reinsert. ZILower limit switch will
stop motor when capsule is fully inserted.

Release switch when cable stops moving.

a

Z2.2.3 Leave capsule in pump bowl one minute.
2.2.4t Withdraw capsule until amber light comes on

(~ 25 seconds required). Time withdrawal

started _—
2.2.5 Allow gt least 10 minutes for salt to solidify.
Start Stop

2.2.6 'To withdraw capsule into glove box:

2.2.6.1 Turn drive unit motor switch counterclock-
wise to withdraw. Watch cable. If it stops
moving before being fully withdrawn, immediately
release switch and notify shift supervisor.

2.2.6.2 Lock No. 3 lock switch with K6 and remove
K6.

2.2.6.3 1Insert K6 in V5, unlock, close, lock closed

—— e

with K5, and remove K5.
2.2.6.4 Insert K5 in V4, unlock, close, lock closed
with K4, and remove K.

2.2.6.5 Insert K4 in No. 2 lock switch, lock switch,

Attt

and remove Ki.
2.2.7 In order to purge glove box atmosphere ending
with box at 0 psig:
2.2.7.1 Insert K1 in V1, unlock, open V1, lock open
with K2, and remove KZ.
2.2.7.2 Insert K2 in V2, unlock, and open Va.
2.2.7.3 Open blue valve C-662.
Approved by .- -

i
o

g

-

A

- :_');":!“, \ K - ."I/’,r{/’/( i 1
3 ,r‘!

- §

2.2.7.4 Evacuate for 4 minutes. Start
Stop

2.2.7.5 Close blue valve C-662.

2.2.7.6 Close V2, lock closed with K2, remove Kz,
and ingert in No. 1 lock switeh on glove port.

2.2.7.7 Pressurize glove box to 3 + 1/2 inches
vacuum using red and blue valve C-650. Read
on PI-CS-A

2.2.7.8 Vent glove port by opening blue valve
C-665 until PI-CS-A indicates 0 + 1/2 psig.

2.2.7.9 Close blue valve C-665.

2.2.8 To remove capsule and seal in sample carrier:

2.2.8.1 Unlock No. 1 lock gwitch, remove K3, and
insert in V3.

2.2.8.2 Open glove port. Lower all three parts
carefully into their open position.

2.2.8.3 Unlock and open V3.

2.8.4 Open ball valve on capsule carrier.

2.2.8.5 Push 1/4" rod through packing gland until
about 14" of rod remain exposed.

2.2.8.6 Using the glove open the Plexiglas door,
remove capsule from latch, hang it on the rod.

2.2.8.7 Look at capsule. Does it contain salt?

Notify 8.8. if no salt is in capsule.

2.2.8.8 Remove empty capsule from the rod, hang it
on the latch and close the Plexiglas door.

2.2.8.9 Check capsule on latch to be certain key
is secure in latch and the capsule is hanging
straight down.

2.2.8.10 Withdraw 1/4" rod into carrier.

2.2.8.11 (lose ball valve on bottom of carrier.

2.2.8.12 Close V3 and lock closed with K3.

2.8.13 Close glove port cover being certain glove

6BR2-4
9/29/65

Init.
2 -~

Approved by =7 7’?///7“ 20 6B-g-5
™

23

9/29/65

Init.
2.2.8.13 (continued)
is inside and cover fits over dowel pin.
Pull clamps together until lock blocks are
about 1/16" apart.
2.2.8.14 Remove K3 from V3, insert in No. 1 lock
switch, lock shut, and remove K2.
2.2.9 To purge glove box atmosphere ending with box at
pump bowl pressure:
2.2.9.1 Insert K2 in V2, unlock, and open V2.
2.2.9.2 Open blue valve C-662.
2.2.9.3 Evacuate for 4 minutes. Start
Stop
2.2.9.4 Close blue valve C-662.
2.2.9.5 Close V2, lock closed with K2, and remove
K2.
2.2.9.6 Insert K2 in V1, unlock, close, lock closed
with K1, and remove KIl.
2.2.9.7 Pressurize glove box to pump bowl pressure
* 0.2 psig using red and blue valve C-650.
Read on PI-C5-A
Preparing The Sampler For Standby Condition
2.3.1 Turn off vacuum pump.
light.
2.3.2 Open red valve C-654
C-65T7
C-661
2.3.3 Adjust buffer header pressure to 40 psig by

 

opening red valve C-651.
2.3.4 Close red valve C-651. PIC-651 reads
2.3.5 Return KL to lock on MB-6 and notify shift super-
visor (or control room supervisor) of completion

of sampling.
Approved by. 2/ - \x’:/'//x/f’?\, 6BE6

9/29/65

IMPORTANT: Do not leave carrier on top of sampler with rod
withdrawn. The rod interferes with the operation of the over-
head crane.
2.3.6 Remove sample carrier from sampier and cOver
opening above V3 with pipe cap.
Date Time
2.4 Handling Of Sample And Carrier
2.h.1 Deliver the assembly to analytical chemistry
(Bldg. 4500). Date and time delivered

 

2.4.2 Using analytic chemistry's procedures, Tremove
the sample from the carrier and return the carrier

to Bldg. 7503.
 

"‘\” A gt A 1 6B3 91

 

 

 

Approved by _ 7,
‘, - 9/29/65
Date .
Init.

 

6B COOLANT SYSTEM SAMPLING

3 COOLANT SYSTEM SAMPLER STARTUP
1f the coolant sampler has been shutdown for long periods
or extensive maintenance has been done on the sampler, a
thorough. check should be made to assure that it is in con-
dition to take samples.
3.1 Startup Check List
(Control Room)

 

3.1.1 Notify shift supervisor of startup.
3.1.2 Check that no work is in progress connected with
the sampler.
3.1.3 Turn on circuit breaker No. 14 in IPP-2 and re-
move tag.
(At Sampler)
3.1.4 Record PI-651
PI-CS-A .
3.1.5 Connect line C-664 to valve C-669.
3.1.6 Close valve C-669.
3.1.7 Start vacuum pump.
3.1.8 Open valves C-662
Cc-664
C-670
Cc-651
C-661
C-653
C-652
C-654
C-656
C-655
C-657
C-658
;gpv,fiflw
Approved by»{ffi€?w¢4;“§ffihfl\\ 6B3-2

 

9/29/65
3.1.9 Evacuate buffer header for 10 minutes.
Start Stop -
3.1.10 Close valves C-670
C-664
C-662

3.1.11 Stop vacuum pump.
3.1.12 Open main helium supply valve V-515. (Near
Sampler-Enricher).
3.1.13 When PI-651 reads LO psig, close valve C-651.
Date Time

 
 

 

 

Approved bx,xf%?’v”“ e 6BLL]
Vv | 9/29/65

Date Time
Init.

6B COOLANT SYSTEM SAMPLING

L COOLANT SYSTEM SAMPLER SHUTDOWN

If the coolant sampler is to be shut down for long

 

vreriods or extension maintenance is to be done on the
sampler, precautions should be taken to assure that
the sampler 1s adequately secured.
4.1 Shutdown Check List
(Control Room)
4.1.1 Notify operations chief and control room super-
visor of shutdown of sampler.
4.1.2 Close main helium supply valve V-515. (Near
sampler~enricher)
(At Coolant Sampler)
4.1.3 Close valves C-661
C-653
Cc-652
C-654
C-656
C-655
C-657
C-658
C-651
L.1.4 Read PI-651
PI-CS-A
4.1.5 Turn off circuit breaker in Panel No. 2.

Circuit No. 1k in control room and tag off.
 

Approved.bygffi:gpz%i24%2§3/%flqflt_ 6C-1

10/21/65

6C WATER SYSTEM

The water system is sampled and analyzed as listed in Table 6-1 to
assure that the proper concentration of chemicals are present for corrosion
protection. The sample lines should be flushed before each sample 1s
taken. Use one-pint or 2 sample-line volumes (whichever is largest).

Due to possible induced activity, the treated water and nuclear penetra-
tion water should be handled as contaminated waste. The sample points

are located as follows:

Treated Water System V-8268 Diesel House
Nuclear Instrument Penetration V-8L48F High Bay
Tower Water V-829D Diegsel House
Process Water V-890D Cocling Tower
CST-1 V-CST-1A Water Room
CoST-2 V-CST-2A Water Room

The analytical procedures to be used by the MSRE operators are

described in the following sections:

Total Inhibitor - Section 6C-k
Chromate - Section 6C-5
Total Hardness - Section 6C-6
PH - Section 6C-7

Tnit. Date/Time

 

1 TREATMENT OF TREATED WATER OR NUCLEAR PENETRATION
WATER
1.1 If analysis indicates that the total inhibitor

 

is low (Section 6C-L), chemical adjustments
are calculated as follows:
NOTE: Always add the calculated amount of both chemicals
to the system.
Treated Water System (4000 gallons capacity)
Pounds of KW to add = 0.0225[1900 - Total

 

inhibitor (ppm)] =
Pounds of K2B,07 * 5Hz0 to add = 0.375 x
pounds of KOz added =
 

Approved by,/f??§;24;<;‘i;;&Xth

Wuclear Penetration Water (1700 gallons capacity)

 

Pounds of KNOs to add = 0.0096 [1900 - total
inhibitor (ppm)] =

 

Pounds of KsB.07; + 5H20 to add = 0.375 x
pounds KNOo added =

 

1.5 Tf either boron (B ) or nitrite (NOz)
from the Iab analyses are low based on curves
of Figure 6C-1, adjustments can be calcu-
lated as follows:

Treated Water System (4000 gallons capacity)

Pounds of KsB,O7 + S5H0 to add = 0.0075
[total inhibitor (ppm) -

B~ (ppm) x 20004
57

 

Pounds of KNOs to add = 0.0225 [total

inhibitor (ppm) - NO?(pgfg £ 2900, -
Nuclear Penetration (1700 gallons capacity)

Pounds of KsB,0-+ S5H20 to add = 0.0032
[total inhibitor (ppm) -

B (ppm) x QOOO] ~
57 -

1

Pounds of KNOs to add = 0.0096 [total

inhibitor (ppm) -

0o {(ppm) x 2000

812 }=
1.3 If pH, Fe, or Al analysis are above limits or
if turbidity appears in samples, notify the

responsible chemist (Paul Neumaan or R. Thoma ) .

6C-2
10/21/65

Tnit. Date/Time

 

 

 
sC-3
10-27-&45
/724.!/-3 eCt Deoron + [foz vs Tolal Inkibi7er

PP

3

 

oo 1000 25c0 2000 2 SO0 Bo0 O
Toto) [mkhid; 75~ oL

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

1 1
-
42 /,/ =
AT 7
| =
/
y //”’ »
& PDEP%=
Loy — //_)/
} - |
N _ 1 L7
S T
=
Foe— T
// /, ;
P e §
- - | |
o _/ a6 ffla@i S50 - OO0 2500 Xobs

 

Teotal Lrh/8;ler - Pom
Approved by _ ;o "a‘;fZKVfirfi

6C-4
10/21/65

Tnit. Date/Time

 

2 TREATMENT OF COOLING TOWER WATER
2.1 Add two balls of Nalco 360 to basin addition

2.2

243

2.4

tube each day after sampling. If chromate
analysis is low, add an extra chromate ball
(falco 360) to addition tube. If >100 ppm
chromate, add only one chromate ball instead

of two.

T

 

If total hardness is greater than 2 x total
hardness of raw water, increase blowdown from
tower basin to maintain a ratio near 2:1.

If pH, or Fe are out of limits when hardness
is within limits, notify the responsible
chemist (Paul Neumann or Roy Thoma). The
process water analysis is used as a gulide for

CTW limits.

 

 

Check cooling tower for algae. If algae are
present as indicated by green growth on cooling

tower, add one ball of Nalco No. 215 to basin.

 

3 CONDENSATE

 

3.1

Condensate samples should be analyzed before
use., If the total hardness exceeds the 1limit,
the tank should be drained. The gource of
the hardness, probably a leaking condenser
tube, should be located and repaired as soon

as possible.

 

b PROCETURE FOR TOTATL TNHTBITOR ANATYSIS USING
CS _ANAIYSIS KIT

 

4,1 Add water sample to the mark on bottle

L.2

(10ms).

 

Add 1 dipperful of CS Reagent No. 1A, cap
bottle, and mix until reagent is dissolved

(2 grams).

 
6C~5
10/21/65

‘Iait., Date/Time

Approved by,

 

 

L.3 Tmmediately add CS Reagent No. 2 rapidly a
drop at a time with dropper vertical, swirl-
ing bottle after each drop. Continue addition
until the pink color remains for one-half

minute.

 

L.4 The number of drops required times 200 equals
ppm Corrosion Inhibitor CS present in the

water.

 

2 PROCEDURE FOR CHROMATE ANATYSTS USING NAICO
CHROMATE TEST XKIT
5.1 Determine the proper size of sample from the
table below:

 

 

Expected Chromate ... .
Content bample Size

 

20 ppm 200 mf
- 50 ppm 100 m4
100 ppm 50 mg
200 ppm 25 mh
400 ppm 12.5 mg

 

5.2 Using the 50 mé graduate, measure out the
sample into the Erlenmeyer flask.

 

5.3 Add 5 mf C-1 (Sol 290) to the sample, using the
*
2.5 mf pipette dropper, and mix well.

 

5.4 Add 5 mg C-2 (Sol 291) to the sample, using
*
the 2.5 m{ pipette dropper, and mix.

 

*
5.5 Add 1 mf C-3 (Sol 292) with pipette dropper.

 

5.6 While agitating the sample in the flask, add
C-4 (80l 293) one drop at a time  with the
pipette held in a vertical position. Count
the drops used until the sample just loses its
blue or blue-black color. The color of the

sample will then be near its original color.

 

*NOTE: Care should be taken to prevent pipette dropper
from touching the flask containing the sample.
Approved.byfigfi}”m}fiflvfifiygmf@%. 6C-6
o 10/21/65

Init. Date/Time

 

 

5.7 Chromate content of the sample in ppm as
Cr0, may be calculated as follows:
200 m# sample - multiply drops C-U4 used by 2.5
100 mf sample - multiply drops C-4 used by 5
50 m{ sample - multiply drops C-4 used by 10
25 mf sample - multiply drops C-4 used by 20
12.5 mf sample - multiply drops C-4 used by L0

 

6 PROCETIURE FCR HARDNESS ANALYSIS USING COLORIMETRIC
HARDNESS KIT
6.1 Take 50 mf sample of clear water at room
temperature. Filter if necessary and add

to clean cassercle or to the 250 mf flask.

 

6.2 Add 1 mf of H-2 (Sol. 275) solution, mix and
add H-3 (Sol. 277), indicator power. The
correct quantity of indicator will be obtained
by inverting the special container over cas-

serole with a single "salt shaker" motion.

 

6.3 Titrate with H-1 (Sol. 274). The color change
is from red to blue with an Intermediate
purple color. The end point is obtained when
the last purple coloration is Just discharged.
Thorough mixing or stirring is necessary after
the addition of ecach reagent and during the

titration.

 

6.4 The number of milliliters of H~1 solution
used multiplied by 20 equals parts per million

total soluble hardness as calcium carbonate.

 
>
-

Approved by{fi§§?>%fisfiégznyak 60-7

T

10/21/65
Tnit. Date/Time

 

pH MEASUREMENT

Measure the pH of water samples using the
instructions on the pH meter and the following:
7.1 Rinse electrcdes with condensate and wipe dry

with tissue bhefore use.

 

T.2 ©Standardize the pH meter with a standard
buffer solution. For TW and NIP water use
buffer with pH of 10. TFor CTW and condensate
use buffer with pH of 7.

 

7.3 Be sure to rinse beaker with condensate and
then rinse twice with small portions of the

sample before measuring pH.

 

7.4 After measuring pH, rinse and leave electrodes.

standing in a beaker of condensate.

 

7.5 Leave pH meter in neutral after use.

 
Approved by Z_ E i ‘é/#'"m ) 2521
T/26/65

6D CELL AIR

During nuclear operations the in-cell atmosphere will be controlled
to give it a low Oz content, 5% by volume or less. A continuous oxygen
analyzer is installed to determine the Oz content. To check the analyzer
and to determine the type of activity in case of accidents, the cell air
will be sampled periodically. The sample station is located in the vent
house and is a part of lines 569 and 565. A portable sample bomb with
a valve at each end will be used to take the semple. The details of
sampling are given below.

Init. Dete/Time

 

1. Connect the sample bomb between valves V-565B
and V-569C.

 

2. Open the valves at the ends of the bomb.

 

3. Open V's 565B and 569C. Close V-5694 and check
closed V-565C.

 

 

 

L. After 5 minutes, close the valves at the ends of
the bomb.

5. Open V-569A and close V-565B and V-569C.

6. Remove the sample from the sample station and

submit for analysis.

 

NOTE: Be sure that the cell is being evacuated during

sampling as indicated by FgI-569.
e
Approved by .7/ i’\fi:Q?M¢n\\ N
. 10/6/6

 

6E LUBE OIl, SYSTEM

1 SAMPLING OF NEW OIL AS RECEIVED
The lubricating oil (Gulfspin 35) for both the fuel and coolant
systems will be sampled (~ 500 ml per sample) on arrival at MSRE.

 

Before use each drum of oil will be analyzed chemically for carbon,
sulfur, bromine number, acid number, flash point, and moisture;
viscosity determinations will be made at 100°F and 210°F. Inter-
facial tension of the oil will be determined at TTOF. Also spec-
trographic and infrared spectrophotometric analyses will be made
before approval for use is given by the operations chief. Each
drum will be tagged with a waterproof covered tag showing identi-
fication, sample number, analysis, certification and current inven-
tory. The o0il will be stored in the Flammable Materials Storage
Building, west of the offgas vent stack.

The acid number (a measure of the oxidation inhibition in the
0il) and the interfacial tension at 77°F will be determined on a
weekly basis during power operations whereas the remainder of the
zanalyses listed above will be made annually or when required.

2 SAMPLING AT OLL PACKAGES
The lube oil in the fuel and coolant system will be sampled

 

weekly during power operation into 250 ml bottles from V-703D
and V-753D. (depleting each oil system ~ 3 gal~yr). In the event
of radiocactive contamination of the lube o0il, the entire lube oil
package will be shielded with lead bricks. The oll will be sampled
with HP surveillance into an evacuated metal container equipped
with an autoclave fitting and a compound gage. The valves, auto-
clave fittings, and sample container may require extended handles
or additional shielding for the sampling operation. Details of
procedure are given below.

Init. Date/Time

 

(Service Tunnel)
2.1 Attach evacuated sample bomb to autoclave

fitting at V-703.D (V-753D ).

 
Approved by lfijfi’yfifxzflazym,fl«\ ER-2
; v

 

 

 

 

 

 

 

 

 

 

 

 

 

10/6/65
Init. Date/Time ;
2.2 Open valve on evacuated sample bomb and check
that pressure in bomb does not increase. 1T
pressure increases, disconnect, re-evacuate
and repeat Steps 1 and 2.
2.3 Open V-703D (V-753D).
2.4 Slowly throttle V-703C (V-753C) until bomb
pressure increases to 2 in. Hg. "
2.5 Close V-703C (V-753C) when pressure reaches
2 in. Hg. )
2.6 After 10 minutes drainage time close V-703D )
(753D).
2.7 Close valve on sample bomb and disconnect at .
autoclave fitting.
2.8 Record sample number on bomb, in sample log,
and in console log.
2.9 Readjust alarm and control setpoints on
II 0oT-1 (LI OT-2) according to building
log.
3 ADDITION OF LUBE OIL TO THE OIL PACKAGES .
Since the oil system is considered secondary
containment, addition of olil to the lube oil system
during operation will be made with HP survelllance ’
and without opening the system to the atmosphere. .
Detalils of procedure are given below.
3.1 Mount a hand-operated barrel pump onto the oil .
supply drum. .
3.2 Connect metering pump discharge to quick dis-
connect 711 (761). .
3.3 Open V-711 (V-761). L
3.4 Add oil until LI OT-1 or (-2) reads 60% while
pump is running (95% when pump is off). .
3.5 Close V-711 (761).
2.6 Remove oil drum from oil package at guick .
10/6/65

I '
Approved bxkgéff?%3$?yfl1rm_ 6E-3

3.6

3.7

Init. Date/Time

 

(continued)

disconnect. Drain oil from horizontal line

between quick disconnect and CV-T11 (CV-761)

 

into a catch pan.
Record on oil drum inventory card and in con-

sole log the amount of oil (gal.) transferred.
P
Approved by*gfifi%%%f’ 6F-1

9-1-65
6F SAMPLE COVER GAS

The Cover Gas System will be saupled for spectrograpalc analiysis
each time a new trailer of helium is obtained. Two samples should be
collected, one from L-548& and one from L-549.

1  SAMPLE FROM LINE 548 ITnisial Date/Time

 

 

1.1 Evacuate a 30 ml sample bomb to <500 u and

close the velve at each end of the bomb.

 

1.2 C(Close analyzer valves (V-548-A) red and blue.

 

1.3 Close analyzer valves (V-5M8-B) red and blue.

 

1.4 Install evacuated bomb between valves (548-A)

and (548-B).

 

1.5 Open valve (548-A) - red and upstream bomb

valve.

 

1.6 After bomb is pressurized open down stream

bomp valve and check fittings for leaks.

 

1.7 Open analyzer valves (548-B) red and blue and
adjust moisture analyzer and Op analyzer

flows to 100 cc/min.

 

1.8 Purge through bome untii moisture analyzer

reaches equilibrium (~ 8 - 24 hrs).

 

1.9 Isolate the samplie by closing:
Analyzer valves(548-A) red and blue
Analyzer valves (548-B) red and blue

Bormb inlet valve outlet valve

 

1.10 Disconnect vomb and submit for spectrographic

analysis, HoD, 0o, Ns, COp content.

 

2 SAMPLE FROM LINE 549

 

2.1 Evacuasite a 30 ml sample pomb to <500 p and

close the valve at =zgch end of the bomd.

 

 

 

2.2 (lose analyzer valves (548-A) red and blue.
2.3 Close analyzer valves (548-B) red and blue.
2.4 Tnstall evacuabed bomb between valves (548-4)

and (548-B).

 
” L,
Approved b T 6F-2

2.5

2.6

2.7

2.8

2.9

2.10

 

VvV 9-1-65

 

Initial Date/rime

Open valve (548-A) blue and upstream bomb

vglve.

 

After bomb is pressurized open down stream

bomb valve and check fittings for leaks.

 

Open analyzer valves (548-B) red and blue
and adjust moisture analyzer and Op analyzer

flows to 100 cc/min.

 

Purge through bomb until moisture analyzer

reaches equilibrium (~ 8 - 24 hrs).

 

Isolate the sample by cliosing:
Analyzer valves (548-A) red and blue
Analyzer valves(548-B) red and blue

Bomb inlet valve outlet valve

 

Disconnect bomb and submit for spectrographic

analysis, 050, O, Nz, COo content.

 
Approved byKZQZEzgégéépytaq 6G-1
| 8/30/65

6G SAMPLING OFFGAS SYSTEM

Normal samples of the offgas system shall be taken at the "line 518"
sampling station in the vent house. The offgas samples will be radio-

active so special precautions must be taken when removing the samples.

Tnit. Date/Time

1 TO ISOIATE A SAMPLE
1.1 At least 1 week before a sample is to be

isclated, check the following valves:

 

Tag open
V-518-4A
V-518-E V-518-D
V-518-B% __ _ V-518-C%

*¥Tag open the B and C valves to the volume holdup which

is to be used.

Close
vV-522-B ____, V-518-F ___ , Vv-518-G
V-518-H  and the remaining 518 B and
C valves V-518-B __ _ , v-518 ¢
V-518-B___ ___, V-518Cc

 

1.2 In order to isolate a sample, merely close
the valves on both sides of the holdup volume.
Tag closed:
V-518-B
V-518-C

————

Open
V-522-B

 

2 TO REMOVE A SAMPLE FROM THE SYSTEM
NOTE: The following procedure must be done one
item at a time in the order listed.
2.1 Evacuate the carrier sample bomb To less than

500 microns and close V-518-K . Attach
£
Approved by &gfi ZVézg;gw/w

2,1

no
W

2.k

no
1

2.6

(continued)
the bomb to line 518 at the special fitting.
Have helium cylinder attached downstream of
V-518-H
Before proceeding further, health physics
coverage 1s necessary.

H. P. man present
Open or check open V-522-B

Close or check ciosed:

V-518-4 V-518-G

V-518-E V-518-F

V-518-D V-518-H

V-518-B1 V-518-C1

V-518-B2 V-518-c2

V-518-B3 V-518-C3
Open V-518-F __ , V-518-G ___ , and
v-518-1

Using helium bottle, pressurize this section

of line to 25 psig.

Close V-518-F and V-518-G
Open V-518-E _ , and V-518-D
Close V-518-E , and V-518-D .

Repeat step 2.5 five (5) times.

1,2 o3,k , 5

In order to reduce the pressure between valves

518-G and 518-K clogse V-518-H

Open V-518-G and V-518-F . Leave open

a few seconds then close V-518-F and V-518-G
Open V-518-D and V-518-E . [Ieave

 

 

open a few seconds, then close V-518-D and
V-518-E . Repeat step 2.6 three times.
- s 3 .

1 2

J

 

6G-2
8/30/65
Init. Date/Time

 

 

 

 

 

 

 
Approved by/@)flm 8/ 6(%3
30/65

2.7

2.8

2.9

2.10

2.11

Tnit. Date/Time

 

Check the following valves closed.

 

V-518-B1 V-518-c1
V-518-B2 V-518-c2
V-518-B3 V-518-C3
V-518-D V-518-E
V-518-H | V-518-K

Open:

V-518-F

V-518-G

V-518-C (1, 2, or 3 depending on which sample

bomb the sample is to taken from.) Note

 

 

which
Open V-518-K and leave open ~ 10 seconds.
Close V-518-K , V-518-G __ , V-518-F

Close the "C'" valve which was opened in
step 2.8 . The sample is now in the

sample carrier bomb.

 

Repeat steps 2.5 and 2.6 in order

to purge the radiocactive gasses from line 518.

 

While wearing masks and with close health
physics surveillance, disconnect the carrier
sample bomb at the special connection and
transport the sample to the lab. Cap both

ends of line disconnected.

 
Approved by

 

jf"?f-zfi‘z»l
7. HEAT BATANCE

Heat balances will be taken periodically to determine the thermal
power that is generated by the reactor. The heat balance results will
be used to keep a close check on the calibration of more direct methods
of power indication, i.e. flow times AT of the coolant salt, and the

various neutron level instruments.
  

7 l TA-1

Approved by .~ 3

TA  GENERAL DESCRIPTION

The heat balance will be made by considering the walls of the Re-
actor and Drain Tank Cells as an envelope into which heat is added or
from which heat is taken. The net heat removal, whether positive or
negative, represents the thermal power of the reactor. Terms 1in the
heat balance, either heat scurces or heat sinks, may vary from a few
watts, as is the case with control rod drive motors, to ~ 10 megawatts
which may be removed by the coolant salt at full power. The terms are
many and varied in value so only the most significant ones are calcu-
lated, i.e. those greater than about 5 to 10 kilowatts. There are other
terms, especially heat sink terms, which cannot be measured directly,
i.e. heat losses through the cell walls to the earth, concrete, etc.
The terms that are not evaluated individually will be evaluated
collective-ly as a single correction term which will be called
"heat losses."
There will be a total of nine terms to be evaluated for the heat
balance. These terms will be listed here and described later. Heat
sink terms will be:
1. Heat removal from the reactor cell by the coolant salt,
0.1 - 10 Mw. (Computer notation QCSRC)

D, Heat removal by cooling water (treated), 0.1 — 0.5 Mw.
(Computer notation QCWT)

3. Heat removal by comporent cooling air, 0.02 — 0.06 Mw.
( Computer notation QCCA)

L. Heat removal by fuel pump oll system, both lube and shield

cooling, 0.005 — 0.01 Mw. (Computer notation QFPY)

5. Heat losseg, this will be a collection of unevaluated terms

which will be used as a correction term for the overall heat

balance, -0.1 — 0.5 Mw. (Computer notation QL¥S)
Approved by :;2%§%%;7}4&flm? | TA-2

8/L/65

Heat Source terms will be:

1.

1. Power added by the fuel pump, 0.027 — 0.035 Mw.
(Computer notation PFE) |

2. Total power added by electric heaters, 0.0 - 0.2 Mw.
Computer notaticn QRCH)

3. Heat energy added by ccolant pump impeller, 0.02 — 0.03 Mw.
(Computer notation QCP)

L.  Power added by the space cooler motors, __ Mw.

(Computer notaticn PSC)

Heat Balance Terms

1.1 Heat Removed by the Coolant Salt. At any significant power
this will be the largest and therefore the most important term
in the heat balance calculation. Since this is true, consider-
able effort has been made to provide reliable and precise
instrumentation for the measurement of this term. Thermo-
couples located in wells at the inlet and outlet of the radiator
will be used to calculate average radiator inlet (ARAIT) and
average radiator outlet (ARAQT) temperatures. A venturi flow
meter is located just upstream of the radiator; information
from this device will be used in the calculation of the coolant
flow rate. Knowing the heat capacity of the salt, the flow
rate, and the temperature difference across the radiator, the
total heat removed at the radiator may be calculated.

1.2 Heat Removed by Ccoling Water. Five significant heat sinks
are included in this term. They comprise heat removed by
cooling water from:

Drain-Tank-Cell Air Cooler (DICAC),

Reactor-Cell Air Cooler #1 (RCAC1),

Reactor-Cell Air Cooler #2 (RCAC2),

Fuel-Pump Motor Cooler (FPMC) and

5.  Thermal Shield (TS¢).

In each of these five cases the temperature rise of the cooling

= w N

water is measured, the cooling weter flow rate is set and assumed
+ -

 

mapry TA-3
8/L/65

to remain constant. Knowing these quantities the heat removal may

be calculated.

1.3

1.4

Heat Removed by Component Cocling Air. Energy is removed from

 

the component cooling air both by the reduction of the gas
stream temperature and by the work done compressing the gas.
Since this is true, not ouly must the temperature change and
the flow rate of gas be determined, but also the change in
pressure which takes place across the compressor. By using
the cooling water AT and flow rate and the gas stream AT the
gas flow rate is established. Now using the gas flow rate Fg,
the absoclute gas outlet temperature T, the temperature dif-
ference between the cell alr and the gas outlet A é, the

cell pressure P,, the pressure rise across the compressor AP,

and the constants, heat capacity of the gas C the universal

pg’
gas constant R, and the molecular weight of the cell gas M,
the total heat removed may be calculated by the following
equation:

R

t * C
Q=TFg (Cpg AT + 3y T In—p— )

Heat Removed by the Fuel Q0il System. The flow rate and temperea-

 

ture rise for the Iube 01l stream and the Shield Cooling oil
stream are measured. The heat removal by the oil stream 1s
calculated, assuming that the heat capacity for oll is a
constant. The heat removed by the two cll streams ie calcu-

lated separately and the results are then combined.

Heat Losses. At a time when the system is hot and circulating

but no power is being produced an evaluation of the heat-loss
term can be made. This may be accomplished by measuring the
energy added to the envelope by heaters, fuel circulating
pump, space cooler motors, etc., and the energy removed by
cooling water, coolant salt, cooling oil, codling air, etec.;

the differerce between these two energy tabulations will be the
Approved bx@% o TA-1
. 8/ /65

term in question. This term will be evaluated several times
both before and after power operation has begun. By the time
this measurement hags been made several times the value should
be known with geood statistical confidence.

1.6 Heat Added by ‘the Fuel Pump Motor. The power that is required

 

by the fuel pump will contribute to the total heat in the
reactor cell. This quantity may be read_directly from the
fuel pump watt meter, E M-FPD.

1.7 Heat Added by the Electric Heaters. The total heat inpat to
the Reactor and Drain Tank Cells and to the coolant salt loop
outside the Reactor Cell will be taken into accourt in & heat
balance. A value for this heat source will be obtained by
tabulating the current drawn by the heaters that are in service.
Any changes in heater settings or in heaters in or out of
service will affect the heat balance results. In general,
this will be considered as a constant with a correction for
variation in line voltage.

1.8 Heat Added by the Coolant Pump. Only that heat which is intro-

 

duced to the coolant salt as work will be considered. The
power that is used by the coolant pump will be read from
EfiM—CPD. come fraction of this value will be used. The value
of the fraction will be established.

1.9 Heat Added by the Space Coclers. The heat that is added to the

 

system by the space cooler motors (3) will be determined by
measuring the power reguired under normal conditions, for the
operation of each motor. This will be done by using a "clamp-
on" ammeter to measure the current. This will be done several
times to establish the power, then the value will be rechecked

periodicaily.
 

TB-1
8/L /65

B Computer Heat Belance

1. Routine Calculation.

 

A heat balance will be calculated routinely by the on-line

computer every U4 hours. The results will consist of one line on

the preprinted form in typer number 2 and will include, in the

order stated, the following (The nomenclature used for each term

on the preprinted form is given in parentheses.):

1)
2)
3)
i)
5)
6)
7)
8)
9)
10)
11)

Time

Net power (Power)

Average radiator inlet temperature (ARAIT)
Average radiator outlet temperature (ARAQT)
Radiator AT (RADT)

Coolant salt flow rate (CSFLY)

Heat removed by the radiator (QCSRA)

Heat removed by cooling water (treated) (QCWT)
Heat removed by component cooling air (QCCA)
Heat removed by fuel pump oil system (QFPY)
Fuel salt flow rate (FSFLQ)

The next ceven entries will be ratios of Net Power (item 2

above) to the power indicated by the each of the following nuclear

instrument channels,

12)  Linear power #1 (NPFLL)
13) Linear power #2 (NPFL2)
14)  ILog power #1 (NPFFL)

15) Log power #2 (NPFF2)

16) Safety channel #1 (NPFS1)
17) Safety channel #2 (NPFS2)
18) Safety channel #3 (NFFS3)

2. Requested Calculation.

 

A heat balance may be requested at any time and as often as

one might wish to do so. The requested heat balance will not

interfere with the calculation of the routine heat balance. The
Approved b vy It 7 f TB-2
8/4/65

results of the requested heat balance will consist of two lines ¢
of data, without identifiers, on typer number 3. The first line
will have the same order and content as listed above under "Routine
Calculation"”, the second line will include, in the order stated,
the following:

19) Radiator inlet AT (difference between two thermocouples in

the same well)
20) Radiastor outlet AT {(difference between two thermocouples
in the same well)

21)  Heat removed by drain-tank-cell air cooler

22)  Heat removed by reactor-cell air cooler #1

23)  Heat removed by reactor-cell air cooler #2

2Lk)  Heat removed by fuel pump motor cooler .

25)  Heat removed by thermal shield cooler

26)  Component-cooling-air flow rate

27)  Heat removed by fuel-pump lube oil

28) Heat removed by fuel-pump shield cooling oil

29) Radiator air flow rate

30) Heat added by electric heaters

31) Heat added by fuel circulating pump

32)  Heat added by cell air cooler motors

33) Heat added by coolant circulating pump

34)  Heat lost from the Reactor and drain tank cells.

3. Operator Regulrements.

The computer will read many variables for each heat balance
and use these wvariables together with constants that have been
established to complete the calculation. Many of the constants
that are used for the computer calculation are controllable by the
reactor operators, for example: the various treated cooling water
flow rates are assumed by the computer to be set at gome constant
value, in reality this value may drift or be changed by an ocperator

thus yielding an erroneous result. .
Approved by% 257 TB-3
8/1/65

The following 1s a list of flow rates that are assumed by the

computer (these will be modified if the operating conditions

change. ) :
FIA-836 60 gpm
FIA-8L0 60 gpm
FIA-838 60 gpm
FIA-830 > gpm
FT -8L4L 60 gpm
FI -873 20 gpm

The computer also assumes that some constant amount of power
is being added by heaters. If a heater fails or if heater current
settings are changed then the power added by the heaters changes
and an erroneous heat balance results. The total power added to the
system by heaters will be about 200 kw.

The computer also assumes that all three cell air coolers are
in operation. Thege should be checked "on".

Routine heat balances are calculated six times daily beginning
at 0230 and every 4 hours thereafter. The operator must check and
if necessary adjust water flows approximately 15 minutes before the
heat balance is made. He must also note if any heater settings

have been changed and if any of the cell air coolers are off.
Approved by, 3 i TC-1
’ 8/4/65

7C MANUAL HEAT BALANCE

Manual calculation of heat balances will be done to check out the
operation of the computer. It may also be necessary to make several
manual heat balances during the zero power experiments since the computer
may not be in full operation by that time. The calculations necessary
are identical to those done by the computer, those calculations are
described in the "Computer Systems Report.” The part of the manual
heat balance that has the greatest importance to the operator is the
taking of data necegsary for its calculation. The following list is to

be used for collecting this data.

Run No. Date Time Initials

BELECTRIC POWER

Switeh House
TVA bus voltage #1 #0 #3

Main Control Room
POWER TO SPACE COOLER MOTORS

Check Space Coolers "On"

DICAC
RCACHL
RCAC#2
POWER TO PUMPS
fuel Pump Power EWR-FPD kw
Coolant Pump Power EWR-CFD kw

Heater Panel
POWER TO HEATERS

Heater Current

CR—l, Amps

CR-2, Amps

TX-3790 (6-65)
/
! :
Approved byZé ’3 “‘f’%mw

CR-3, Amps

CR-4, Amps

CR-5, Amps

CR-6, Amps

CR-T7, Amps

H-200-13, Amps
1.
2.
3.
H-201-12, Amps
1.
2.

3.

TC-2
8/k4 /65
Approved byqééifii%géf%?*“v”

. H-202-2, Amps
1.
2.
3.

Heaters Powerstat Setting and Current

 

H-200-1k
Setting
' Amps
H-200-15
Setting
Amps
H-201-10
. setting
Amps
H-201-11
Setting
Amps
H-201-13
Setting
Amps
H-202-1
cetting
Amps
H-20k4-2
Setting
Amps
H-205-1
Setting
Amps
FV-204-3
Setting
’ Amps

7C-3
8/L/65
Approved by‘fizzfilzwé%%;: AH P

FT-201A-1
cetting
Amps
FT-201A-3
Setting
Amps
FT-201A-2
Setting
Amps
FT-201A-4
Setting
Amps
FT-201B-1
Setting
Amps
FT-201B-3
Setting
Amps
FT-201B-2
Setting
Amps
FT-201B-4
Setting
Amps
LE CP 1
Setting
Amps
LE CP 2
Setting
Amps
FV-20L-1
cetting
Amps

o
8/k/65
Approved by PN BN 7C-5
8/4/65

FV-204-2 FV-204-A2
Setting Setting
Amps Amps
FV-206-1 FV-206-A2
Setting Setting
Amps Amps
FV-206-2 (SP-16)
Setting
Amps
H-20k4-1
Amps
H-206-1
Amps
CP-1
Setting
Amps
CP-2
Setting
Amps
H-200-1
Setting
Amps
H-200-11 -
Setting
Amps
H-200-12
Setting
Amps
H-201-1
Setting
Amps
H-201-2 -
setting
Amps
 

H-201-9
Setting

Amps
H-100-1

Setting

Amps
RCH-1 (Amps)

 

\

 

RCH-2 (Amps)

 

l

 

RCH-3 (Amps)

 

\

 

RCH-U4 (Amps)
1.
2.
3.
H-100-2

 

l

 

Setting
Amp
H-101-2

n

Setting
Amp
H-101-3

wm

Setting
Amps

7C-6
8/k /65
Approved b - afl s
y *4é§E:—~;E?V‘””*\ TC-7
8/k/65

b RCH-5, Amps

 

 

 

. H-102-2,
1.
2,

R-1, Amps
1.

|

R-2, Amps
l.
2.

R'B: Amps
l‘

!

 

HX-1, Amps
1.
2.

3¢
Approved by gfiz“fz/Jl%é;{/M%»7

 

 

 

X-2, Amps
3.
HX-3, Amps
1.
FP-1, Amps
3.
FP-2, Amps
RAN-1
Setting
Amps
RAN-2
Setting
Amps
H-102-3
Setting
Amps
H-102-1
Setting
Amps
H-102-L
Setting
Amps
H-102-5
Setting

Amps

 

TC-8
8/L/6
 

-
NSy 7C-9

Approved by
| 8/L /65

» H-103
Setting
Amps
FV-103
Setting
Anmps
H-10L4-1
Setting
Amps
FFP-1, Amps
1.
2.
v 3.
FFT-2, .Amps
1.
2.
3.
FD-1-1, Amps

 

l

 

 

l

 

 

l

3.
FD-1-2, Amps

 

 

l

 

i FD-2-1, Amps

 

I

 

FD-2-2, Amps

 

l

 
_ .
Approved by fl Iz ‘5"'.‘/" ¥yl

FV-10k-1
Setting
Amps
FV-104-3
Setting
Amps
H-104-5
Setting
Amps
H-10L-6
Setting
Amps
FV-105-1
Setting
Amps
FV-105-3
Setting
Amps
H-105-1
Setting
Amps
H-105-k
Setting
Amps
FV-106-1
Setting
Amps
FV-106-3
Setting
Amps
H~106-1
Setting
Amps

7C-10
8/1/65
Py
Approved b17435.2/;¢t$/;¢ow\

H-106-4

Setting

, Amps
H-10h4-2
Amps
H-10L-3
Amps
H-10L-4
Amps
H-105-2
Amps
H-105-3
Amps
H-10L-7
Amps
H-106-2
Amps
H-106-3
Amps
H-110-2
Amps
H-110-3
Amps
H-107-1

Setting

Amps
H-107-2

Setting

Amps
HF-107-3

Setting

Amps

FV-10L-1A

Setting
Amps -

FvV-105-1A

Setting
Amps

FV-106-1A

Setting
Amps

TC-11
8/4/65
 

Fv-107-1
cetting
Amps
FV-107-3
setting
rAmps
H-108-1
setting
Amps
H-108-2
Setting
Amps
H-108-3
Setting
Amps
FV~108-1
Setting
Amps
FV-108-3
Setting
Amps
H-109-1
Setting
Amps
H-109-2
Setting
Amps
H-109-3
setting
Amps
FV-109-1
Setting
Amps

- »':’//
LYl J1 7 gy

TC~12
8/L /65

o,
Approved bxfizZZE%gégéfiwgnq

» FV-109-3
Setting
Amps
H-110-1
Setting
Amps
i THERMOCOUPLES
’ Thermocouple
’ COOLANT SALT TEMPERATURES
i Radiator Inlet TE~201-A-1A
g Radiator Inlet TE-201-A-1B
{
Radiator Outlet TE-201-A-24
Radiator‘Outlet TE-201-A-2B

COMPONENT COOLING ATR TEMPERATURES

Component cooling air at outlet
of cooler

Component cooling air at inlet
to cooler

Component cooling air at inlet
to system

OTT, SYSTEM TEMPERATURES
Iube and Shield cooling oil inlet

i Iube 0il outlet

i Shield cooling oil outlet

| TREATED COOLING WATER TEMPERATURES
Cooling water in
Outlet from Drain Tank cell cooler
Outlet from Reactor cell cooler #1
Outlet from Reactor cell cooler #2
Outlet from Fuel Pump cooler
Outlet from Thermal Shield

. Outlet from Component air cooler

TE-917
TE-916

TE-022

TE-T702-1B
TE-705-1A
TE-TOT-1A

TE-826-1
TE-837-1
TE-846~1
TE-841-1
TE-831-1
TE-8L45-1
TE-87h-1

Jack
Panel
No.

805
806
807
808

898
897

899

872
873
875

887
890
893,
891
886
892
895

7C-13
8/4/65

Temperature
°F
Approved by f"f?”; (%u -

 

FIOWS

Transmitter

Auxiliary Control Room
COOILANT SALT FIOWS

Coolant Salt Flow FT-201-A
Coolant Salt Flow FT-201-38

 

Main Control Room
OIL FIOWS

Lube 0il Flows FT-TO3-A

Shield cooling oil flows FT-704-A
COOLING WATER FIOWS

Water Room

Drain tank cell cooler

Reactor cell cooler #1

Reactor Cell cooler #2

Fuel Pump Motor Cooler

Thermal Shield Cooler

Component Cooling Air Cooler

PRESSURES

Main Control Room

 

Reactor Cell Pressure
Blower AP
NUCLEAR POWER
Linear Power #1 Range
Reading
Linear Power #2 Range

Reading

Linear Chamber selected (S 17) #1 or #2

Linear Power on chamber selected Range
Reading

ILcg Power #1 (Red Pen)

Log Power #2 (Green Pen)

Safety Channel #1

Safety Channel #2

Safety Channel #3

Date Time Tnitialis

7C- 1k
8/4 /65
Read-out
FI-201-A gpm
FI-201-B gpm
FI-7C3-A~-1 gpm
FI-TOL-A-1 gpm
Reading gpm

FI-836 X T =
FI"'8)'|-O - X T = _
FI-838 X T =
FI-8LL X T =
FI-830 X T =
FI-873

PI-RC-A psia

PAIC-960-A psig
IXNIC1A watts
RINIC1Al %
HXNIC2A watts
RINICPAL %
RR- 3600 watts
RR- 3600 %
RR- 3700 watts
RR- 3700 watts
RMNSC1AL %
RMNSC2A1 %
RMNSC 3A1 %
8-1
10/22/65

Approved byfiffifi,jzfiéé%yyzfiwx
8 PERIODIC INSTRUMENT CALIBRATION
AND
CIRCUIT CHECKS

During each startup of the MSRE the instrumentation will be tested
to assure that it is functioning properly as described in Section LH.
These startup tests will include a thorough checkout of all instrumen-
tation and circuitry. Due to the importance of some instruments or
circuits, they will also be tested periodically during operation.
Details of these tests are given in the following section. The frequency
of testing is given in Table 8-1.

If the tests indicate that the instrumentation has failed in an
unsafe manner, consideration should be given to manually actuating the
safety action. In the case of 2 out of 3 circuitry,this will not in-
terfere with normal operation. It will require extra steps during the
testing of the other two channels. 1In the case of one out of two
channels, it may be possible to increase the frequency of testing of
the other channel and using other administrative controls. In most

cases the operations chief should be consulted.
Approved bXMfM{f)

 

° &

 

 

 

N 8-2
A4 10/22/65
TABLE 8-1
PERIODIC ON-LINE CHECKING OF INSTRUMENTATTION
PROCEDURE INSTRUMENTATION REMARKS FREQUENCY

SA-1 Nuclear Wide Range Instrument Calibration Monthl
Counrving Channel

8A-1.3, 1.4, 1.7 Log Count Rate, Instrument Calibration Weekly

and 1.8 Log Power and
Period

8A-2 Nuclesar Sefety Instrument Calibration Monthly
Channelis

84A-3 Linear Power Instrument Calibration Monthly
Channels

8B Process Radiation  Surveillance Check 8 Hours
GM Tubes

8B Process Radiation  Instrument Calibration 8 Hours
GM Tubes

8B Process Radiation  Surveillance Check 8 Hours
10N Chambexr

8B Process Radiation Zero Check 8 Hours
ION Chanber

8B-2 Process Radiation  Source Check Weekly
GM Tubes RM 557

8B-3 Process Radiation  Source Check Weekly
GM Tubes RM 528

SB-4 Procegs Radiation  Source Check Weekly
GM Tubes RM 565

88-5 Procegs Radiation Source Check Weekly
GM Tubes RM 500

&B-6 Process Radiation  Source Check Weekly
GM Tubes EM 596

8B-7 Process Radiation  Source Check Weekly
10N Cramber RM
827

8B-8 Process Radiation  Source Check Weekly
GM Tube RM 0T 1
and 2z

8C-1 Persomnel Monitors Source Check Weekly

8C-2 Personnel Moniters Alarm Matrix Check Monthly

8C-3 Personnel Monitors Evacuation Alarm Check Biannually
 

 

 

Approved'byfljfiégéibégéwfiflm 8-3
v 10/22/65
TABLE 8-1
(continued)
PROCEDURE INSTRUMENTATION REMARKS FREQUENCY
8c-L Containment Stack  Source Check Weekly
Monitors
8D-1 FP and OFT Pressure Electronic Simulation  Weekly
Check and Surveil-
lance Check
8D-2 Helium Supply Relay Check Weekly
Pressure
8D-3 FP and OFT Bub- Flow and Level Checks  Weekly
blers
8D-L4 Rod Scram Fast Trip Comparator Daily
Checks
8D-5 Emergency Drain Simulated Temperature  Weekly
and Levels Checks
8D-6 Reactor Cell Similated Pressure Weekly
Pressure Checks
8D-7 Coolant Pump Speed Relay Check Weekly
and Coolant Flow
8D-8 Sampler Interlocks Check Monthly
8D-9 Exercise Control Surveillance Check Weekly

Rods

 
 

Approved byflgfifir## 7

ety Bt o 8A-1
7 L 10/28/65

8A NEUTRON LEVEL

Due to the complexity of the nuclear instrumentation and the
possibility of it drifting, all components are given periodic on line
tests. These tests as described in this section are done mainly by
instrument technicians; however, operational personnel should follow
the work closely. No jumpers should be installed without the prior
approval of the operations chief.

Obtain Shift Supervisor's permission before starting this procedure

 

Init. Date/Time

 

1 WIDE RANGE COUNTING CHANNELS

Since only one counting channel is required,

 

the following tests can be performed on a single
channel while the reactor is in service. The
other channel should be in service before starting
this check if reactor power is less than 1 Mw.

1.1 Reference Voltages Channel 1

 

Measure all DC voltages with a digital
voltmeter at the tests points indicated. If
adjustments are required, follow the procedure
given in the individual module manual. The
regulated supply voltages should be adjusted
only when measured in drawer W-2 (RX-NCC 1-AL).
l.1.1 Msake sure channel to be tested is not

the one selected for operation.

1.1.2 Drawer W-2 (RX NCC1-AL) (Reference
drawing RC13-13-574)

 

 

 

 

 

 

Test Blk Voltage Ground Rdng. Adj. Rdng.
A-1 +10v = 10mv % Ov Reg.
A-3 ~-10v * 10mv + Ov Reg.
A-5 -15v £ 10mv  * Ov Reg.
A-T7 -25v = 10mv %= Ov Reg.
A-Q +15v £ 10mv  + Ov Reg.

 
%
APPTOV@},.W%/A% A1 L 8A_2

Test Blk

A-11
A-17
A-19

10/28/65

Init. Date/Time

 

1.1.2 (continued)
Voltage Ground Rdng. Adj. Rdng.
+25v £ 10mv Ov Reg.
+32v £ 100mv £ Ov Batt.
-32v £ 100mv * Ov Batt.

 

I+

 

 

 

 

1.1.3 Drawer W-3 (RX-NCC1-2A6) (Reference
drawing RC13-13-584)

Test Blk Voltage iround Rdng.
TPh-9 -10v * 10mv % Ov Reg.
TP4-16  +10v * 10mv % Ov Reg. __
TPL-12 -15v £ 10mv % Ov Reg.
TPL-18 +15v = 10mv % Ov Reg.
TP4-14 ~25v * 10mv  * Ov Reg.
TP4-20 +25v * 10mv % Ov Reg.
TPk -k ~-32v = 100mv % Ov BRatt.

 

 

Measure the preamp and fission chamber
supply voltages at the test points located
in the transformer shield enclosure mounted
on the rear panel. Adjust per procedure
given in Q-2617-5 mamual (RX-NCC1-A7).

Test Point  Voltage Reading  Adj. Reading

 

 

 

 

1 Ovi¥

2 22V
3 Ov¥x
L +110v
5 +300v

 

*Return for -22v
**¥Return for 110 and 300v
Measure chopper supply voltage
(6.3 v ac £ 0.5) between TP6-3 and TP6-6

with Triplett meter or equal.

 

Operational Amplifier Balance Channel 1

 

Balance esch operational amplifier by
 

102

1.3

8A-3
10/28/65

Init. Date/Time

 

(continued)

depressing "Bal" push button on top of the
module and adjusting the adjacent trim
potentiometer until the meter in the left
rear corner of the drawer indicates zero.
All operational amplifiers are located in
drawver W-3 {RX-NCC1l-A6). These are

RM NCC1l-A5, Ab, A7, A3, A9, and AlO.

 

Log Count Rate and Log Power Calibration

 

Channel 1
1.3.1 Place chamnel 2 switch (S-14) in
automatic mode and turn chamber selector

switeh (S-15) to position 2.

 

1.3.2 Place channel 1 in manual mcde.

 

1.3.3 Position "operate-calibrate’ switch
located on pulse amplifier to "10 cps”
position; note output of "reactor power”
gmplifier  , measured between TP5-19
and HQ ground. The "log count rate"
panel meter should indicate 10 cps _
and the output of the "log count rate"
amplifier should measure -2 volts
between TP3-6 (W-3) and H. G. ground

 

 

1.3.4 Position "operate-calibrate" switeh to
"10% cps ___ , and the "log count rate”
amplifier output should be -8 volts
The "reactor power" amplifier output
should increase by +3 volts _ , while
the "reactor power” panel meter indication

goes up 3 decades

 

1.3.5 Measure the counting rate using the
scaler with the 10 and 10% cps test

signal applied:
10/28/65

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Init. Date/Time

 

1.3.5 (continued)
Test Signal Scaler Rdg. Time Scaler cps

 

 

10 cps

 

 

 

 

 

10% cps .
1.4 PFast-Trip Comparator SetPoints
The fast-trip comparator (Q-2609) set

 

points may be visually checked by verifying
the reference potentiometer settings as

tabulated below. (Dial reads directly in

 

volts.)

Fast Trip Poténtiometer

Comparator Dial Setting Check
RXS-NCC1L-A2 1 {<50 X cps) 9.L _
RXS-NCC1l-A1 2 (>2 cps) 0.6 L
RXS-NCC1-46 3 (<200 kw) 7.3 L
RXS-NCC1-A7T L (>500 kw) 7.7 o
RXS-NCC1-48 5 (>1.5 Mw) 8.18 L
RXS-NCC1-A3 6 (<10 sec) 5.71 L
RIS-NCC1-Ak 7 (<20 sec) 3.57 L
RXS-NCC1-45 8 (330 sec) 2.86

 

1.4.1 Log Count Rate FIC's

The counting rate may be adjusted over
the instruments entire range by adjustment
of the pulse amplifier gain and/or the
discriminator level.

With the digital vcltmeter connected
between TP3-13 in drawer W-4 {RX-NCC1-A8)
and H. G. ground, increase the counting
rate, by increasing the pulse amplifier
gain and decreasing the PHS setting, until
the 50 kcps fast-trip comparator changes
state (RXS-NCC1l-A2). Voltmeter should

indicate -9.4v * 0.05v . Decrease
«

   

Approved by E$23§§25¢zft,<fiu4fl\ 8A-5
s

/4 10/28/65

1.4.1 (continued) Init. Date/Time
the counting rate by decreasing the pulse

 

amplifier gain and increasing the PHS

setting until the 2 cps fast-trip compa-

rator operates (RXS-NCCL-Al) voltmeter

should indicate -0.6v + 0.05v . Return

PHS dial to proper setting record:
1l.k.2 ILog Power FIC's

 

The setpalnt of the power fast-trip
comparator is determined by applying a
calibrated voltage to their inputs. This
signal is adjusted with a potentiometer
located inside drawer W-1 (RX-NCC1-A5).
The output of the potentiometer 1s applied
to the log power amplifier.
Connect digital voltmeter between
TP3-15 and H. Q. ground in drawer W-4
(RX-NCC1-A8). Bet "operate-calibrate"
switch to “period." Depress 'power test”
push button inside drawer W-1 (RX-NCC1-AS).
Adjust adjacent potentiometer to check trip
points as tabulated below:
Trip Voltmeter Indication Pot. Setting
200 Kw RXS-NCCl-A6 7.3 £ 0.05v
500 Kw RX8-NCCl-A7 7.7 %= 0.05v
1.5 Kw RXS-NCCL-A8 8.18 * 0.05v

 

 

 

 

1.4.3 Period FTC's
The period trips are tested by applying
calibrated voltage ramps to the function
generator amplifier. These ramps are selected
t0 generate period signals slightly larger
than the set points.
Connect digital voltmeter between

TP3-17 in drawer W-4% (RX-NCCL-A8) and H. G.
Approved by -7 ~

1.5

 

8A-6
10/28/65

 

Tnit. Date/Time

 

1.k.3 (continued)
ground. Set "cperate-calibrate” switch
to "period."” Set "test" selector switch
inside drawer W-1 (RX-NCC1-A5) to the
desired period (10, 20, or 30 sec.).

ITrip Voltmeter Indication

10 sec. RXS-NCC1-A3 ~ + 6.0

20 sec. RXS-NCCL-AY ~ + 3.7

30 sec. RXS-NCCl-A5 ~ -+ 3.0

Reference Voltages Channel 2

 

 

 

 

Test Blk

A-1
A-3
A-5
A-T7
A-9
A-11
A-17
A-19

Meagure all DC voltages with a digital
voltmeter at the tests points indicatea. If
adjustments are required, follow the procedure
given in the individual module manual. The
regulated supply voltages should be adjusted
only when measured in drawer W-2 (RX-NCCZ2-AkL).
1.5.1 Make sure chanunel +“o be tested is not

the one selected for operation.

1.5.2 Drawer W-2 (RX-NCC2-24%) (Reference
drawing RC13-13-57A)

 

 

 

 

 

 

 

 

 

Voltage Ground Rdng. Adj. Rdng.
+10v £ 10mv %+ Ov Reg.
-10v £ 10mv  * Ov Reg.
-15v £ 10mv  * Ov Reg.
-¢bv £ 10mv £ Ov Reg.
+15v £ 10mv = Ov Reg.
+25v £ 10mv = Ov Reg.
+32v £ 100mv £ Ov Batt.
-32v £ 100mv + Ov Batt.

 

 

1.1.3 Drawer W-3 (RX-NCC2-46) (Reference

drawing RC13-13-584)
Approvedybyggifffir

 

sy fen, BA-7
zfi7 10/28/65

Init. Date/Time

 

1.1.3 (continued)

Test Blk Voltage Ground Rdng.
TPL-9 -10v # 10mv % Ov Reg.
TP4-16  +10v * 10mv % Ov Reg.
TP4-12  -15v = 10mv  * Ov Reg.
TP4-18  +15v = 10mv £ Ov Reg.
TPL-1h  -25v + 10mv % Ov Reg.
TP4-20  +25v £ 10mv  + Ov Reg.
TP -1 -32v £ 100mv * Ov Batt.

1.6

 

 

Measure the preasmp and fission
chamber supply voltages at the test
points located in the transformer shield
enclosure mounted on the rear panel.
Adjust per procedure given in Q-2617-5
manual (RX-NCC2-AT).

Test Point Voltage Reading Adj. Reading

 

 

 

 

1 Ov* _
2 -22V

3 Q¥

L +110v

5 +300v

 

 

¥Return for -22v
*¥*¥Return for 110 and 300v
Measure chopper supply voltage
(6.3 v ac * 0.5) between TP6-3 and TP6-6
with Triplett meter or equal.
Operational Amplifier Balance Channel 2
Balance each operational amplifier by
depressing "Bal" push button on top of the
module and adjusting the adjacent trim
potentiometer until the meter in the left
rear corner of the drawer indicates zero.

All operational amplifiers are located in
7
Approved.byjl4f§§;€E;Z%;g;2&¢4h\ 84-8
o V

10/28 /65

Init. Date/Time

 

1.6 {(continued)

drawer W-3 (RX-NCC2-46). These are

RM NCC 2-25, AG, A7, A8, A9, and AlO.
Log Count Rate and Log Power Calibration
Channel 2

1.7

1.7.

1.7.

1.7

1.7.

1.7.

1 Place channel 2 switch (S-14) in
automatic mode and turn chamber selector

switeh (8-15) to position 2.

 

o Place channel 1 in manual mode.

 

.3 Position "operate-calibrate" switch

located on pulse amplifier to "10 cps"
position; note output of "reactor power"
amplifier  , measured between TP5-19
and HQ ground. The "log count rate” panel
meter should indicate 10 cps __ , and the
ocutput cf the "log count rate" amplifier
should measure -2 volts between TP3-6
(W-3) and H. G. ground

L Position "operate-calibrate" switeh to

 

"10% cps _ , =nd the'log count rate”
amplifier output should be -8 volts

The "reactor power" amplifier
output should increase by 43 volts s
while the "reactor power” panel meter

indication goes up 3 decades

 

5 Mesasure the counting rate using the
scaler with the 10 and 10% cps test

signal applied:

Test Signal Scaler Rdg. Time Scaler cps

 

10 cps

10% cps

 

 

1.8 Fast-Trip Comparator Set Points Channel 2

 

The fast-trip comparator {(Q-2609) set
Approved by

 

1.8 (continued)
points may be visually checked by verifying

the reference potentiometer settings as tabu-
lated below.

(Dial reads directly in volts.)

 

Fast Trip Potentiometer

Comparator Dial Setting  Check
RXS-NCC2-A2 1 (<50 K cps) 9.4 L
RXS-NCC2-A1 2 (>2 cps) 0.6 o
RXS-NCC2-46 3 (<200 kw) 7.3 L
RXS-NCC2-A7 4 (>500 kw) 7.7 L
RXS-NCC2-A8 5 (>1.5 Mw) 8.18 o
RXS-NCC2-43 6 (<10 sec) 5.71 L
RXS-NcC2-Ah 7 (<20 sec) 3.57 -
RXS-NCC2-45 8 (>30 sec) 2.86 -

8A-9
10/28/65

Init. Date/Time

 

 

1.8.1 Log Count Rate FIC's

The counting rate may be adjusted
over the instruments entire range by
adjustment of the pulse amplifier gain
and/or the discriminator level.

With the digital voltmeter connected
between TP3-13 in drawer W-4 (RX-NCC2-AS)
and H. G. ground, increase the counting
rate, by increasing the pulse amplifier
gain and decreasing the PHS setting, until
the 50 keps fast-trip comparator changes
state (RXS-NCC2-A2). Voltmeter should
indicate -Q.4v £ 0.05v __ . Decrease
the counting rate by decreasing the pulse
amplifier gain and increasing the PHS
setting until the 2 cps fast-trip compa-
rator operates (RXS-NCC2-Al) voltmeter
should indicate -0.6v % 0.05v
Return PHS dial to proper setting record:

 
8A-10

Approved by
10/28/65

 

 

Init. Date/Time
1.8.2 Log Power FIC's
The set point of the power fast-
trip comparator is determined by applying
a calibrated voltage to their inputs.
This signal is adjusted with a potentiometer
located inside drawer W-1 (RX-NCC2-A5).
The output of the potentiometer is applied
to the log power asmplifier.
Connect digital voltmeter between
TP3-15 and H. Q. ground in drawer W-k4
(RX-NCC2-A8). Set "operate-calibrate"
switch to "period". Depress "power test"
push button inside drawer W-1 (RX-NCC2-A5).
Adjust adjacent potentiometer to check
trip points as tabulated below:
Trip Voltmeter Indication Pot. Setting
200 Kw RXS-NCC2-46 7.3 * 0.05v
510 Kw RXS-NCC2-A7 7.7 £ 0.05v
1.5 Kw RXS-NCC2-A8 8.18 + 0.05v

 

 

 

 

1.8.3 Period FIC'a

The period trips are tested by
applying calibrated wvoltage ramps to
the function generator amplifier. These
ramps are selected to generate period
signals slightly larger than the set
points.

Connect digital voltmeter between
TP3-17 in drawer W-4 (RX-NCC2-A8) and
H. G. ground. Set "operate-calibrate"
switch to "period.” Set "test"” selector
switch inside drawer W-1 {RX-NCC2-A5) to
the desired periocd (10, 20, or 30 sec.)
 

Approved by{fgjé?;széZE;//awflu\‘ 8A-11

 

 

10/28/65
b Init. Date/Time
1.8.3 (continued)
Trip Voltmeter Indication
10 sec. RXS-NCC2-A3 ~ + 6.0
20 sec. RXS-NCC2-AkL ~ + 3.7
30 sec. RXS-NCC2-A5 ~ + 3.0

 

2 NUCLEAR SAFETY CHANNELS
2.l Since the MSRE safety system has three separate

 

channels connected in a 2/3 arrangement, the
following tests may be performed on a single
. channel while the reactor is in service;
however, it 1s imperative that all three safety
. channels are in the untripped condition before
testing is started since the channel under test
must be tripped.
2.2 Reference Voitages: Channel 1
2.2.1 Drawer S-1 (RX-NSCl-Al) (Reference
drawing RC13-9-56A)
Measure the supply voltage at the

 

. indicated test points with a digital
voltmeter. Adjust the regulators es
required, following the adjustment

procedure described in the individual

 

 

 

 

 

 

 

 

. module manual.
Test Block A Voltage Return Rdg. Adj. Rdg.

| Pin 18 +32v £ 100mv + Ov Batt

Pin 19 -32v £ 100mv % Ov Batt

Pin 1 +10v * 10mv  + Ov Reg.

Pin 3 -10v £ 10mv  #* Ov Reg.

Pin 5 ~15v £ 10mv £ Ov Reg.

Pin 7 -25v * 10mv £ Ov Reg.
* Pin 10 +15v £ 10mv % Ov Reg.

Pin 11 +25v £ 10mv % Ov Reg.

 

 

 
Approved by ZZ zpé"'%i{ finfi?

2.2.2 Drawer $S-2 (RX-NSV1-A6) (Reference
drawing RC13-9-57A)
Measure the supply voltages at the
indicated test points with a digital

voltmeter.
Test Block Voltage Return Rdng .

TP1-A +32v £ 100mv * 9v Batt (TP1-K)

TP1-U -32v £ 100mv I Ov Batt

TPL-F +10v £ 10mv  * Ov Reg (TP1l-H)

TP1-N -10v £ 10mw £ Ov Reg (TP1l-H)

TPL-R ~15v + 10mv  + Ov Reg. (TP1-E)

TP2-6 ~25v £ 10mv % Ov Reg. (TP1-H)

TP1-D +15v + 10mv  + Ov Reg (TP1-H)

TP1-B +25v * 10mv £ Ov Reg (TP1l-H)

z.2.3 Chamber High Voltage Supply
Measure the chamber high voltage sup-
Ply with a Triplett meter at the test
points located in the module. The white
point (TP3) is ground; the red point is
the high-voltage output test point (TP2).
The voltage should read +250v * 25v.

2.3 Instrument Balance Channel 1

 

The instruments requiring balancing are
the Flux Amplifier (RM-NSCl-Al) and the
Period Safety Module (BRM-NSCLl-A43).

2.3.1 TFlux Amplifier Balance
A zero-center balance meter on the

top of the module is visible with the
drawer pulled out. The meter is used
with the zero push button and zero
adjustment located at the edge of the
printed circuit board to correct for
drift. Depress the zero push button

and observe balance meter.

8A-12
10/28/65

Init. Date/Time

 

 

 
Approved byffiéfy

 

~gfiéé73¢¢¢n1 8A-13
V 10/28/65

2.3.1 (continued) Init. Date/Time
If the meter reads anywhere on scale
with the pushbutton depressed, the
balance is satisfactory. If adjust-
ment is necessary, turn zero-adjustment.

2.3.2 Period Safety Balance

With the drawer withdrawn, there

 

are visible on top of the module, five

test points, and three "Bal" potentio-

meters.

2.3.2.1 Place a Jjumper between TPl
and TP2 (Brown) and measure the
voltage between TP3 and TP4 (Black)
with a Triplett meter. Operations
Chief's approval
Adjust "Bal l'until the voltage is
zero.

2.3.2.2 Place jumper between TP3 and TPh
(Black) and TP6 (Yellow). Operations
Chief's approval . Adjust

 

"Bal 2" until the voltage between

TP5 (Red) and TP6 (Yellow) is zero.
2.3.2.3 The period amplifier may be zeroed

by adjusting "Bal 3" until the front-

panel meter indicates " w.”

2.3.2.4 Remove jumpers. Shift Supervisor's

 

approval B
"Reverse' Fast-Trip Comparator (RSS-NSC1-A2)
Channel 1 and "Level Scram'" Fast-Trip Comparator
(RSS-NSC1-A3) Calibration.

The purpose of this section is to check

S r————r——r——

the trip point of the above comparators. It
is assumed that the safety system is in the

low sensitivity mode (15 Mw scram).
  

2
./:/f»;r/ HLL /8187%&
10/28/65

Approved'gxf’”'
Init. Date/Time
2.4 (continued)
This test injects a test current into the
Flux amplifier which is adjusted to cause the
comparators to just operate. The potentiometer
and push button referred to hereafter are located
on the Monitor and Test Unit (RM-NSClL-A2).
Connect the digital voltmeter to the Flux
Amplifier output, (TPL-W and H. Q. ground).
With the "ecurrent adjust"” potentiometer set
to zero, depress the "high current” push
button, adjust the potentiometer and observe
at what voltage the comparators change state.
Flux Ampl.

Fast Trip  Potentiometer Output at.
Comparator  Dial Setting Trip Point Rdg. Ad. Rdg.

1 {scram) 7.50 ~-715v * 0.05v

2 (reverse
and load set-
back) 6.00 ~-6.0v = 0.05v

 

Return potentiometer to zero setting.

 

2.5 Period Calibration Test Channel 1

Depressing the "period calibration" test
button on the test module causes a voltage
ramp o be applied to the log current amplifier.
Differentiation of this ramp by the period
amplifier produces a constant voltage output
for the duration of the ramp. Two ramp rates
are available: one produces a period of
approximately 2 sec and one a period slightly
shorter than 1 sec.
2.5.1 Connect a digital voltmeter between

TP2-3 (period output) and H. Q. ground.
Approved by e 8A-15
‘ 10/28/65

2.6

Init. Date/Time

 

2.5.2 Depress the "2 sec period" push button.
The "period" front panel meter should show
an approximate 2 sec indication. Record
period . Record voltage (should
be 500 mv + 50)

2.5.3 Depress the "1l sec period" push button

 

and record period indicated

Record voltage (should be 1.lv + 100mv).

"Period' Fast-Trip Comparator Channel 1

 

2.7

2.8

2.6.1 Depress the "l sec period" push
button and observe that the “period
scram' fast-trip comparator does change
state (trip).

2.6.2 Observe that when the "2 sec period”

 

push button is depressed that the trip
comparator does not remain tripped
after the initial transient. (Momentary

trip).

Caution Before proceeding to the next channel

or section, make sure that all channels are

reset (untripped). In addition, observe that

all meters are indicating correctly and ail

latch lights are reset.

Reference Voltages: Channel 2

2.8.1 Drawer S-1 (RX-NSC2-Al) (Reference
drawing RC13-9-56A)

Measure the supply voltage at the
indicated test points with a digitai
voltmeter. Adjust the regulators as
required, following the adjustment pro-

cedure described in the individual module
manual.
 

2.8.1 (continued)

R

eturn

8A-16
10/28/65

Init. Date/Time

 

Rdg. Adj. Rag.

 

+ O+

i+

Ov Batt
Ov Batt
Ov Reg.
Ov Reg.
Ov Reg.
Ov Reg.
Ov Reg.
Ov Reg.

(RX-N3V2-46) (Reference

drawing RC13-9-57A)
Measure the supply voltages at the

 

———

indicated test points with a digital

 

ov
Ov
Ov
Ov
Ov

Ov
Ov

Test Block A Voltage
Pin 18 +32v £ 100mv
Pin 19 -32v & 100mv
Pin 1 +10v = 10mv
Pin 3 -10v £ 10mv
Pin 5 -15v £ 10mv
Pin 7 -25v £ 10mv
Pin 10 +15v £ 10mv
Pin 11 +25v = 10mv

2.8.2 Drawer 8-2
voltmeter.

Test Block  Voltage

TP1-A +32v £ 100mv £
TP1-U -32v £ 100mv *
TP1-F +10v £ 10mv =
TP1-N -10v £ 10mw =
TP1-R -15v = 10mv £
TP2 -6 -25v = 10mv =
TP1-D +15v * 10mv =+
TP1-B +25v £ 10mv =%

Ov

Return

Rdng.

Batt (TP1-K)

Batt

———

Reg (TP1-H) .

Reg (TPl-H)
Reg (TFP1-H)
Reg (TPl-H)
Reg (TP1l-H)
Reg (TP1-H)

—r—————
——————
——r———
————————

 

 

2.8.3 Chamber High Voltage Supply

Measure the chamber high voltage

supply with a Triplett meter at the

test points located in the module.
The white point (TP3) is ground; the
red point is the high-voltage output

test point (TP2).

read 250v %

25v.

The voltage should

 
 

 

Approved by ,jj

f€£7%§/¢a¢wn\\hh 8A-17

10/28/65

Init. Date/Time

2.9 Instrument Balance Channel 2

the

The instruments requiring balancing are
Flux Amplifier (RM-NSC2-Al) and the

Period Safety Module (RM-NSC2-A3).

2.9.

2.9.

1 TFlux Amplifier Balance

A zero-center balance meter on the
top of the module is visible with the
drawer pulled out. The meter is used
with the zero push button and zero
adjusfment located at the edge of the
printed circuit board to correct for
drift. Depress the zero push button
and observe balance meter. If the
meter reads anywhere on scale with the
pushbutton depressed, the balance is
satisfactory. If adjustment is necessary,
turn zero-adjustment.
2 Period Safety Balance

With the drawer withdrawn, there

 

are visible on top of the module, five

test points, and three "Bal" potentio-

meters.

z.9.2.1 Place a jumper between TPl and
TP2 (Brown) and measure the voltage
between TP3 and TP4 (Black) with a
Triplett meter. Operations Chief's
approval . Adjust "Bal 1"
until the voltage is zero.

2.9.2.2 Place jumper between TP3 and TPL
(Black) and TP6 (Yellow). Operations
Chief's approval . Adjust
"Ball 2" until the voltage between
TP5 (Red) and TP6 (Yellow) is zero.

 
10/28/65

Approvedby'ézqgi:agygiééfimfiqzy\ 8A-18

Init. Date/Time
2.9.2.3 The pericd amplifier may be
zero by adjusting "Bal 3" until

t_tt
Lo,

the frontpanel meter indicates
2.9.2.4 Remove jumpers. Shift Supervisor's

check .

 

 

 

2,10 "Reverse” Fast-Trip Comparator (RSS-NSC2-A2)

Channel 2 and "Level Scram" Fast-Trip Comparator
(RSS-NSC2-A3) Calibration.

The purpose of this section is to check
the trip point of the above comparators. It
is assumed that the safety system is in the
low sensitivity mode (15 Mw scram).

This test injects a test current into the
Flux amplifier which is adjusted to cause the
comparators to just operate. The potentio-
meter and push button referred to hereafter
are located on the Monitor and Test Unit
(RM-NSC2~A2).

Connect the digltal voltmeter to the Flux
Amplifier output. (TP1-W and H. Q. ground).
With the "current adjust" potentiometer set
to zero, depress the "high current” push
button, adjust the potentiometer and observe

at what voltage the comparators change state.

Fast Trip  Potentiometer Flux Ampl.
_Comparator — Disl Setting Output at  Rdg. Ad. Rdg.

1 (scram)

Trip Point
7050 -Tl5V i OUOEV

2 (reverse
and load set-

back)

65.00 -6.0v £ 0.05v

Return potentiometer to zero setting.

 
 

Approved by/42§:€2/a%§%fluufha\ 8A-19

10/28/65

iInit. Datelgime

 

2.11 Period Calibration Test Channel 2

 

2.12

Depressing the "period calibration” test
button on the test module causes a voltage
ramp to be applied to the log current amplifier.
Differentiation of this ramp by the period
amplifier produces a constant voltage output
for the duration of the ramp. Two ramp rates
are avallable: one produces a period of approxi-
mately 2 sec and one a period slightly shorter
than 1 sec.
2.11.1 Connect a digital voltmeter between
TP2-3 (period output) and H. Q. ground.
2.11.2 Dépress the "2 sec period" push button.
The "period" from panel meter should show
an approximate 2 sec indication. Record
period . Record voltage (should be
500 mv ¥ 50) .

2.11.3 Depress the "1 sec period” push button

e ————————

and record period indicated

Record voltage (should be 1.lv * 100 mv).

 

"Period" Fast-Trip Comparator Channel 12

 

2.13

2.12.1 Depress the "L sec periocd"” push button
and observe that the "period scram" fast
trip comparator does change state (trip) .

2.12.2 Observe that when the "2 sec period”
push button is depressed that the trip
comparator does not remain tripped after

the initial transient. (Momentary trip.)

 

Caution Before proceeding to the next channel
or section make sure that all channels are
reset (untripped). In addition, observe that
all meters are indicating correctly and gll

latch lights are reset.
PV
Approved by ,1??5223/Lqi%§{¢¢¢m@\

2.14 Reference Voltages:

Channel 3

 

2.14.1 Drawer S-1 (RX-NSC3-Al) (Reference

drawing RC13-9-564)

indicated

Measure the supply voltage at the

voltmeter.

required,

procedure

Adjust the regulators as

module manual.

test points with a digital

following the adjustment

described in the individual

 

 

 

Test Block A Voltage Return Rdg. Adj. Rdg.
Pin 18 +32v * 100mv £ Ov Batt
Pin 19 -32v + 100mv £ Ov Batt
Pin 1 +10v & 10mv % Ov Reg
Pin 3 -10v £ 10mv % Ov Reg
Pin 5 -15v £ 10mv * Ov Reg
Pin 7 -25v £ 10mv * Ov Reg
Pin 10 +15v £ 10mv % Ov Reg
Pin 11 +25v £ 10mv £ Ov Reg
2.14.2 Drawer $-2 (RX-NSV3-A6) (Refereunce
drawing RC13-9-574)

Measure the supply voltages at the
indicated test points with a digital volt-
meter.

Test Block Voltage Return Rdng.
TP1-A  +32v £ 100mv * 9v Batt (TP1-K)
TP1-U -32v £ 100mv * Ov Batt
TP1-F  +10v £ 1O0mv £ Ov Reg (TP1-H)
TP1-N  -10v * 10mw % Ov Reg (TPl-H)
TP1-R -15v £ 10mv % Ov Reg (TP1-H) _

TP2 -6 -25v £ 10mv £ Ov Reg {TPL-H)
TP1-D  +15v * 10mv % Ov Reg (TP1-E)
TP1-B +25v £ 10mv + Ov Reg (TPL-H)

8A-20
10/28/65

Init. Date/Time ,

 

 

 
Approved by(flégijézfi}fé??@&d“1\ 84-21

10/28/65

. Init. Date/Time

 

2.14.3 Chamber High Voltage Supply
Measure the chamber high voltage

supply with a Triplett meter at the
test points located in the module. The
white point (TP3) is ground; the red
point is the high-voltage output test

: point (TP2). The voltage should read
250 v = 25v.

2.15 Instrument Balance Channel 3

 

 

The instruments requiring balancing are
the Flux Amplifier (BM-NSC3-Al) and the
Period Safety Module (RM-NSC3-A3).

2.15.1 Flux Amplifier Balance
A zero-center balance meter on the
top of the module is visible with the
drawer pulled out. The meter is used
with the zero push button and 2810
adjustment located at the edge of the
printed circuit board to correct for
drift. Depress the zero push button
and cbserve balance meter. If the
meter reads anywhere on scale with

the pushbutton depressed, the balance

is satisfactory. I1If adjustment is
* necessary, turn zero-adjustment.
2.15.2 Period Safety Balance

With the drawer withdrawn, there are

 

vigible on top of the module, five test

points, and three "Bal" potentiometers.

2.15.2.1. Place a Jjumper between TPl and
. TP2 (Brown) and measure the voltage
between TP3 and TPh (Black) with a
Triplett meter. Operations Chief's
 
  

s _;7?
Approved by = AN g e £ BA-22
v T

10/28/65

Init. Date/Time

 

2.15.2.1 (continued)
approval . Adjust "Bal
1" until the voltage is zero.
2.15.2.2 Place jumper between TP3 and
TPh (Black) and TF6 (Yellow). Oper- .
ations Chief's approval .
Adjust "Bal 2" until the voltage be-
tween TP5 (Red) and TP6 (Yellow) is

 

ZETO.

 

2.15.2.3 The period amplifier may be
zero by adjusting "Bal 3" until the
frontpanel meter indicates "00".

2.15.2.4 Remove jumpers. Shift Super-

 

visor's check .

2.16 "Reverse" Fast-Trip Comparator (RSS-NSCL-A2)
Channel 3 and "Level Scram" Fast-Trip Comparator
(RSS-NSC3-A3) Calibration.

The purpose of this section is to check the

 

 

trip point of the above comparators. It is
assumed that the safety system is in the low
sensitivity mode (15 Mw scram).

This test injects a test current into the
Flux amplifier which is adjusted to cause the
comparators to just operate. The potentiometer
and push button referred to hereafter are located
on the Monitor and Test Unit (RM-NSCl-A2).

Connect the digital voltmeter to the Flux
Amplifier output. (TP1-W and H. Q. ground).
With the "eurrent adjust' potentiometer set
to zero, depress the "high current" push
button, adjust the potentiometer and observe

at what voltage the comparators change state.
Approved byzégcgéagfiéépéawwflq 8A-23

10/28/65

Init. Date/Time

2.16 (continued)

Fast Trip Potentiometer Fiux Ampl.
Comparator Dial Setting Output at  Rdg. Ad. Rdg.

1 (scram)

Trip Point
7.50 -715v = 0.05v

2 (reverse
and load set-

back)

2.17

6.00 -6.0v £ 0.05v

 

Return potentiometer to zero setting.

 

Period Calibration Test Channel 3

 

2.18

Depressing the "period calibration" test

button on the test module causes a voltage

ramp to be applied to the log current amplifier.

Differentiation of this ramp by the period

amplifier produces a constant voltage output

for the duration of the ramp. Two ramp rates

are available: one produces a period of approxi-

mately 2 sec and one a period slightly shorter

than 1 sec.

2.17.1 Connect a digital voltmeter between
TP2-3 (period oubput) and H. Q. ground.

2.17.2 Depress the "2 sec period” push
button. The "period" front panel meter
should show an approximate 2 sec indi-
cation. Record period . Record
voltage (should be 500 mv * 50) .

2.17.3 Depress the "1 sec period"” push

 

button and record period indicated
Record voltage (should be l.lv *
100 mv). .

"Period" Fast-Trip Comparator Channel 3

 

 

 

2.18.1 Depress the "1 sec period" push
button and cbserve that the "period
scram' fast-trip comparator does change

state (trip).

 
Approved by Tzte 84-24
T 10/28/65

2.19

2.

z0

Init. Date/Time

 

2.18.2 CObserve that when the "2 sec period"
push button is depressed that the trip
comparator does not remain tripped after

the initial transient. (Momentary Trip)

 

Caution Before proceeding to the next

channel or section, make sure that all

channels are reset (untripped). In

addlition, observe that all meters are

indicating correctly and all latch lights

are reset.

General: Channels 1, Z, and 3
The purpose of this section is to deter-

mine that when a single channel is tripped,

the proper two branches of the relay matrices

are opened. This test 1s also designed %o

detect partial shorts areocund the matrix relay

contacts. The front panel meters on the coinci-
dence matrix monitors (drawer 5-3) (RX-NSC1-AT)
indicate the total clutch current as well as

the current through each branch of the matrix.

At all times the total clutch current must

equal the sum of the three currents through

the individual matrix, as indicated by the
panel meters. The following table gives the
proper meter indication for all conditions.

Any deviation from the values may indicate

improper operning or closing of relay con-

tacts. Record currents.

2.20.1 Trip the channel by depressing the
"test" push button on the Relay Safety
Element.

CAUTION: Make sure all channels are reset

before pushing the test button.
Approved by ,4gf§232462§%/%qé§1 8A-25

10/28/65

Init. Date/Time

 

2.20.1 (continued)

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

: Total Clutch Current
%Tripped ‘ | ma,
;Channel Rod 1 Rod 2 Rod 3
1 None 150 150 150
1 133 133 133
2 133 133 133
3 133 133 133
Rod 1 Clutch Current
ma,
Tripped Branch Currents
.Channel Total AB BC CA
' None 150 50 50 50
C1 133 __ o {133 ___ o
{2 133 0 o 133
% 3 133 |w3__ | o___ o
Rod 2 Clutch Current
§ ma,
jITripped Branch Currents
EChannel Total AB BC CA
. None 150 50 50 50

|
{
, 1 133 0 133 0
b2 133 0 0 133
! 3 133 133 0 o

 

 

 

 

 

 
MR e L e oeem daar e S

Approved by442§f§Z§§%;§¢&zéa¢_. /8§726
10/28/65

2.20.1 {continued)

Init. Date/Time

 

 

Rod 3 Clutech Current

 

 

 

Tripped Brgich Currents é
gChannel Total AB BC CA é
" Ione 150 fso_ 1 so__ fso__ |
1 133 ol o ____,
Z 133 - L {133 |
3 133 {133 . o__ |

 

 

 

 

 

3 LINFAR POWER CHANNELS

 

3.1 Reference Voltages

 

3.1.1 Drawer R-1 (RX-NARC-A2)
Reference drawing RC13-12-564
Measure the supply voltages at

the indicated test points with a digital

 

voltmeter.
Test Block A Voltage

Pin 18 +32v + 100mv
Pin 19 -32v £ 100mv
Pin 1 +10v £ 10mv
Pin 3 ~10v = 10mv
Pin 5 -15v = 10mv
Pin 7 -25v © 10mv
Pin 10 +15v £ 10mv
Pin 11 +25v &£ 10mv

Adjust as required.
Return  Rdng. Adj. Rdng.

= H + + + B+ I+

I+

 

Ov
Ov
Ov
Ov
Qv
Ov
Oov
Ov

 

Batt
Batt

 

 

Reg

 

Reg

 

Reg

 

Reg

 

Reg

 

Reg

 

Adjust the regulators as required, follow

procedure given in individual module manual.
3.1.2 Drawer R-2 (RX-NARC-Al)
Reference drawing RCL3-12-5T7A.

 

Measure the supply voltages at the

indicated test points with a digital voltmeter.
Approved bxzié;figgzfig;éxdflflx 8A-27

 

 

 

T v 10/28/65
. 3.1.2 (continued) Init. Date/Time

Test Point Voltage Return Rdg.

TP2-15 -32v * 100mv * Ov Batt (TP2-10) ..

TP3-3 +25v £ 10mv  * Ov Reg L

TP2~1 +15v £ 10mv £ Ov Reg L

TP3-5 -25v £ 10mv  * Ov Reg L

TPz-3 -15v * 10mv .. Ov Reg o

L TP2-19 +10v £ 10mv £ Ov Reg L
f TP3-1 -10v £ 10mv % Ov Reg

LA

3.1.

 

Measure the chopper supply voltage
with a Triplett meter or equivalent, between
test point TP1l-1 and TPL-3. Voltage should
be approximately 6.3 VAC. £ 0.5v.
3 Chamber High Voltage Supply

Observe the chamber high voltage as
indicated on front panel meters of the

supply. (Supplies are located in Nuclear

 

Board . 4). CH1  CH 2
+HV-==-- 600 volts
“HV--=~- 300 volts

 

.2 Operational Amplifier Balance

 

List amplifier by number. Balance each

operational amplifier by depressing the "Bal”

push buttons on top of the module and adjusting

the

adjacent trim potentiometer until the meter

in the left rear corner of the drawer indicates

ZeTro.

RM-NARC-A1
RM-NARC-A2
RM-NARC-A3
RM-NARC -Al

 
8B-1
10/22/65

 

8B CALIBRATION CHECK
OF
PROCESS RADIATION MONITORS

INTRODUCTION

It will be necessary to check periodically the calibration of the
process radiation monitors and associated equipment to insure their
reliability for the protection of personnel and as a warning system of
radioactive escape. Two methods are used for checking this system.

One method 1s a frequent check of the readout instruments, and the other
is a check of the entire system using a known gource.

A finite reading on the readout instruments, from both the G-M
tubes and ion chambers, is usually an indication that the system is
operating properly. The readings of these instruments are checked
periodically as well as the calibration of the G-M tubes and the zero
on the electrometers. |

The system check-out using a source will consist of removing a plug
from the shield around the detectors, inserting a source, and checking
that the appropriate readings and alarms are received. Details are
given below. Frequency of testing is given in Table 8-1.

Init. Date/Time

 

1 PREPARATION

1.1 Obtain permission from shift supervisor to

 

test calibration of process radiation equip-

ment. Shift Supervisor's initials

 

1:2 Check and adjust if necessary the calibrate and
alarm setpoints on all radiation monitors

(Q-1916-1R3).

 

1.3 Obtain source in lead carrier from instrument
shop. Read the specifications carefully.
The source is Uobalt-60 which has & half-life
of ~ 5 1/3 years.

 

1.4 Estabiish communications between Auxillary

Control Room and sensor location.

 
S e i ermmt e, et 4. 38

Approved by477’flfl/" 

8B-2
10/22/65

  

Init. Date/Time

 

2 RADIATION MONITOR 557 (OFF GAS FROM CHARCOAL BEDS)
VENT HOUSE

2.1

2.2

2.3
2.4

2.5

Push alarm buttons on RM-557-A and RM-557-B
and check that alarm settings are 20 mr/hr.

Adjust if necessary.

 

When the source is inserted to give the alarm

on RE-557, control action will close HCV-557-Cl,
PCV-510-A2 and PCV-513-A2. Before proceeding
further, make certain that this will not adversly

affect operations.

 

Remove the source plug from the shield.

 

‘Place position plug in place of the source

plug.

 

Insert source fully and record readings indi-
cated on RI-557 A and B. Readings should be
25-35 mr/hr above background. Check that
this causes alarms on XA-4043-3 in ACR and
XA 4010-2 in MCR.

 

 

SENSOR

CHECK THAT

ALARMS {HCV 557 CliPCV’5lO A2 1PCV 513 A2

READING | OCCUR CLOSES | CLOSES CLOSES

 

RM-55T7-A

 

RM-557-B

 

 

 

 

 

 

2.6

2.7
2.8

Remove source and position plug from lead
shield.

 

Replace source plug.

 

Reset RM-557~A and RM-557-B and check that
alarms clear and HCV-557-Cl, PCV-510-A2 and
PCV-513~-AZ open.

 
0--5*'*‘"}‘_';;-.'.""“ ' f‘*
Approved by i eaill / Lt I 8B-3
10/22/65

  

. Init. Date/Time
3 RADIATION MONITOR 528 (COOLANT SYSTEM OFF GAS)
VENT HCUSE
3.1 Check that alarm settings on RM-528-B and
RM-528-C are 20 mr/hr by pressing alarm
buttons. Adjust if necessary.
3.2 When the source is inserted to test RE-528-B
and RE-528-C, control action will instigate

 

an emergency drain and will stop the fuel
pump. Before proceeding further, make
. certain that this will not adversly affect
operations. Insert jumpers around RE-528
. in ECC 1h7.
3.3 Remove the shield plug from the lead shield.

 

 

3.4 Place position plug in place of the source
plug.

3.5 1Insert source fully and record readings
indicated on RI-528-B and RI-528-C. Readings
should be between 25-35 mr/hr above background.
Check that this causes alarms on XA-4043-U4 in
ACR and XA-4010-2 in MCR.

 

 

 

 

 

 

. CHECK THAT
ALARMS EMERGENCY -
SENSOR READING OCCUR DRAIN INITIATED*
RM-528-B
RM-528-C

 

 

 

 

¥As indicated by lights going out in Ckt. 18 and 19.

3.6 Remove source and position plug from lead

shield.

 

3.7 Replace source plug.
* 3.8 Reset RM-528-B and RM-528-C and check that
alarms clear. Ckt. 18 and 19 is made up.

 

 
APPI'OVG@. by,/a/\;%;f/ AT PN
e \/ TN

3.9 Remove jumpers from ECC 147.
L RADIATION MONITOR 565 (CELL OFF GAS)
VENT HCOUSE
4.1 Check that alarm settings on RM-565-B and
RM-565-C are 20 mr/hr by pressing alarm

 

buttons. Adjust if necessary.
4.2 When the source is inserted to test RE-565-B
and RE-565-C, control actlon will instigate
an emergency drain, close HCV 565, close
HCV-015-A1 which shuts off cooling air to
the control rods, and close RC oxygen
analyzer block valves HCV-566-A1 and
HCV-566-A3. Before proceeding further,
make certain that this will not adversly
affect operatiocns.
CAUTION: This section of the procedure should be per-
formed as quickly as possible to insure that the control
rods do not overheat.
k.3 Remove the shield plug from the lead shield.
L.4h Insert source fully and record readings indi-
cated on RI-565-B and RI-565~C. Readings
should be 30-40 mr/hr above background. Check
that this causes alarms on XA-4043-5 in ACR
and on XA-4010-2 in MCR.

8B-k
10/22/65

Init. Date/Time

 

 

 

 

 

 

 

| CHECK THAT

3 | | ; "HCV 566
ALARMS‘EMERGENCY DRATN|HCV 565{A1 AID A3
SENSOR |READING|OCOUR | IS INITIATED* |CLOSHS | CLOSE

 

RM-565-R

 

 

 

 

 

RM-565-C; :

 

Y -

*As indicated by lights going out in Ckt. 18 and 19.

 
 

k.5
L.6
L.7

8B-5
10/22/65

 

Init. Date/Time

 

Remove source from lead shield.

 

Replace source plug.

 

Reset RM-565-B and RM-565-C and check that
alarms clear. Ckt. 18 and 19 is made up and
HCV 565 opens.

 

5 RADTATION MONITOR 500 (MAIN HELIUM SUPPLY)

 

 

 

 

 

 

 

 

 

 

 

 

WATER ROOM

5.1 Check that alarm sstting on RM-500D is set on
20 mr/hr by pressing alarm button. Adjust if
necessary.

5.2 Remove the shield plug from the lead shield.

5+3 Place position plug in place of the source
plug.

5.4 Insert source fully and record reading indi-
cated on RIL-500-D. Reading should be 25-35
mr/hr above background. This should cause
alarm on XA-4OL3-2 in ACR and on XA-4010-2
in MCR.

F CHECK . THAT
SENSOR READING. ALARMS OCCUR

REM-500-D

5.5 Remove gource and position plug from lead
shield.

5.6 Replace source plug.

5.7 Check that alarms clear.

 

6 PROCESS MONITOR 596 (OUTSIDE TRANSMITTER ROOM)

6.1

Push alarm buttons on RM-596-A, RM-596-B, and
RM-596-C. Check that the alarm setpoints are
at 20 mr/hr.

 
Approved bymflfl' AN

Init.

8B-6
10/22/65

Date/Time

 

6.2 These three elements are checked individually
and should not give control action. If two
elements are set off, the helium supply %o
the fuel pump and overflow tank bubblers will
be blocked.

 

6.3 Check that shield is completely assembled.

 

6.4 Insert source in a hole and record the reading
indicated on that channel. Reading should be
28 + 5 mr/hr above background. Check that
this channel causes an alarm on XA-4O43-1 in
ACR and on XA-L4010-2 in MCR.

 

6.5 Remove the source.

 

6.6 Reset the monitor and check that alarms clear.

 

6.7 After alarms clear and readings have returned
to their previous valve, repeat 6.4 through

6.6 on the other two channels.

 

 

 

 

 

| CHECK THAT |
| Sensor Reading Aarms Ocecur
RM-596-A

RM-596~B

RM-596-C |

 

 

 

7 PROCESS MONITOR 827 (TREATED WATER)
WATER ROOM
7.1 Check that the alarm setpoints (red pointers)

 

on RM-827-A, B and C are indicating a current

that is equivalent to 20 mr/hr.

 

T.2 Control action is initiated by two of the
three monitors going into alarm condition.
This should not happen, but if it does it
will close block valves in all return water

lines which are from in-cell components.

 
‘o
Approved bzzfiffigggz?fi'%qCZnify\ 8B-7

YV 10/22/65

Init. Date/Time

 

7.3 Check that shield is completely assembled

before proceeding.

 

7.4 Insert the source in one hole and record the
reading indicated on that channel. Reading
should be . Check that this
channel causes an alarm on XA-4042-1 in
ACR and XA-4010-2 in MCR.

T.5 Remove the source.

 

 

7.6 Reset the electrometer and check that alarms

clear,

 

T.7 After alarms clear and readings return to
their original valve, repeat 7.4 through 7.6

on the othey two channels.

 

 

 

 

 

CHECK THAT |

Sensor Reading Alarms Occur §
RM-827-4
RM-827-B

|

RM-827-C !

 

 

 

 

8  OIL SYSTEM PROCESS MONITORS (SERVICE TUNNEL)
8.1 Check that alarm settings on RM-OT-1B and

RM-0T-2B (located in service room) are set

 

gt 20 mr/hr. Adjust if necessary.

 

8.2 Place source in special source support beside
the detector at O0T-1B. RM-0T-1B should read
25 to 30 mr/hr with the source 1 3/4" from
the detector. Record reading. Alarms should
be received on XA-4O42-1 in the ACR and
XA-LOLZ-2 in the MCR.

8.3 Repeat 8.2 at 0T-2. RM-0T-2B should read
25-30 mr/hr with the source 1 3/4" from the
detector. Record reading and check that the

 

same alarms are received as before.

 
8B-8

Approved by / /6
10/22/05

 

Init. Date/Time ‘

8.4 Check that alarms clear when source is removed.

 

(
CHECK THAT
Sensor x Reading Alarms Occur

 

RM-0T-1B
RM-0T~23B

 

 

 

 

 
_..wf
Approved by@gfl,, 8C-1
9/10/65

8C CALIBRATION OF PERSONNEL MONITORS AND STACK MONITORS

It will be necessary to pericdically check the calibration and
operability of all fixed radiation monitors, personnel radiation alarm
units, and the evacuation alarm system. This will be done in conjunction
with the health physics department. The calibration and operability of
the stack monitor will be checked in conjunction with the Laboratory
Facilities Department. Details of the tests and data to be taken are
described below.

1 ROUTINE SOURCE CHECK Init. Date/Time

 

1.1 Have Health Physicist test each fixed radiation
monitor with a source to assure that each
responds properly and gives local and/or
control room alarms. Record data in Table
8C1-1.

 

1.2 Reset glarm after each test.

 

2 ATARM MATRIX CHECK
The following test requires that the evacu-
ation alarm system be disabled. Therefore, 1if
two radiation monitors alarm, (other than those
activated by the test), the evacuation alarm
should be manuelly actuated.

2.1 Bhift supervisor's permission to proceed.

 

 

2.2 Notify the emergency control center, then
turn the key operated switch to disable.

Operations Chief's permission to disable.

 

 

2.3 Have Health Physicist activate the monitron

in the control room (RE-7011) with a source.

 

2.4 Have the Health Physicist activate each of
the other monitrons (see Table 8C2-1) with a
source and note that the matrix would have

caused an evacuation as indicated by the
8c-2

 

 

 

 

 

 

 

 

 

 

 

 

9/10/65
Init. Date/Time
2.4 (continued) “
evacuate light in the auxiliary control room.
Reset the module before the next instrument
is tested. Do not reset RE-T01ll. Record
results in Table 6C2-1.
2.5 When finished reset RE-TOil.
2.6 Have Health Physicist activate the office
cAM (RE-7002) with a source. ’
2.7 Have the Health Physicist activate each of the .
other CAM's (see table 8C2-2) with a source |
and note that the matrix would have caused .
an evacuation as indicated by the evacuate
light in the suxiliary control room. Do .
not reset RE-T002. Record results in
Table 8C2-2.
2.8 When finished, reset RE-T002.
2.9 Bwitch key switch from disable to normal and
put key in drawer of console.
3 EVACUATION ALARM TEST
3.1 Operations Chief and .
Shift Supervisor
approval to proceed. i
3.2 Have a spare nitrogen cylinder located at
each evacuation horn. v

 

3.3 Notify the emergency control center.

 

3.4 Manually sound evacuation alarm.

3.5 Note that a1l 4 horns alarmed and that

 

everyone evacuated.

 

3.6 Reset and valve in standby nitrogen cylinder.

 

3.7 Announce all clear.

 

3.8 Replace used nitrogen bottles.

 
8C-3
9/10/65
Init. Date/Time

 

 

Ly CONTAINMENT STACK MONITOR TESTS

 

4,1 Have Iaboratory Facilities Department
personnel check each monitor with a source
and note that the recorder responds properly
and that an alarm occurs in the control room.

Record data in Table 8CL-1.

 

k,2 Reset alarm after each test.

 

W
 

 

8C-4

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

| 9/10/65
TABLE 8C1-1
SOURCE CHECK OF FIXED RADIATTION MONITOR ¢
5 ’Proper i__ |
Aux. Control ; ?
’ Local :Control Room = | |
; : Check i Room Alarm %Reset{
Type | Number Lecation ‘Batisfactory} Alarm |(XA-4010-1) Alarm
Monitron | RE-TOL1l | Control Room | % | o
" RE-7012 | High Bay - South : |
" | RE-7013 | High Bay - West i ; E .
" RE-701L | 840! level -North 5 | |
" RE-T7015 Transmitter Room % g ‘
" RE-7016 | Basement - Center, §
" RE-7017 ! Service Tunnel % % :
CAM RE-7000 | High Bay - West | §
" RE-7001 | High Bey - South |
" RE-7002 | Offices é
! RE-7003 | Basement - North | - |
" RE-700k : Transmitter Room ? | |
" RE-7005 . Service Tunnel | | .
" RE-T7006 ; Mcbile Unit 3 XXXX XXXX XXXX
Q-2091 7 instruments | XXXX XXXX XXXK
Q-1939 7503 Hall 5 XXXX XXXX XXX ;

 

 

 

 

. T
 

Approved bxfig;g§§22§%§%;fi¢gn\ , 83é5
9/10

TARLE 8C2-1.
MONITRON ATARM MATRIX CHECK

 

Monitron
Number Matrix Functioned Preoperly Alarm Was Reset

 

RE-T7012
RE-7013
RE-T701L
RE-7015 ]
RE-T016
RE-T017

 

 

 

 

 

 

 

 

TABLE 8C2-2
CAM AIARM MATRIX CHECK

 

CAM
Number Matrix Functioned Properly Alarm Was Reset!

 

RE-T003
RE-T00k

 

 

 

 

 

RE-T7005_ : a

 

 
8C-6

 

 

 

 

9/10/65
TABLE 8Ck-1 :
STACK RADIATION MONITOR CHECKS
, Proper Aux.
i Control Room
Type Number Counts per Minute Alarm MCR Alarm { Alarm
XA-4003-1

 

 

Beta Gammsa RM S1-A
Alpha RM S1-B -
| Todine RM S1-C

 

 

 

 

 

 

 

 

 

 
ff_;;;::fi'w?”/:{,(}"‘ 4
Approved by - AN g #H) 8D-1
10/26/65

 

 

. 8D SAFETY CIRCUIT CHECKS

Additional periocdical on-line checks will be made of the safety
instrumentation. Details of these tests are described in this section.
Init. Date/Time

 

1 FUEL PUMP AND OVERFLOW TANK PRESSURE
1.1 Record system pressures.
PRC-522-A (MB~8)

 

 

PI-522-A __ (S-E Panel 3)
PI-589-A1 _ (AB-8)

. PI-589-A2 ___ (TB-5)
PI-592-B ____ (AB-8)

. 1.2 Depress test button on PM-589 and PM-592

(in ACR) one at a time, and note that actions

listed below occur.

 

; TEST BUTTON DEPRESSED
| PM-589 PM-592
I XA-4006-5 annunciates

 

 

 

 

 

. Second light out in ECC 18 XXXX
Second light out in ECC 19 | XXXX
* FV-103 starts to thaw* | _

 

FV-105 or 106 starts to tha

HCV-573, 575, and 57T open
(MB Lights)

|HCV-533 open (MB Lights)
*Check TR 3600

*%Both may be in thawed condition; if so, it is not
necessary to check this.

 

 

 

 

 

 

 

1.3 Reduce system pressure from 5 psig to 4.5 psig,
as indicated by PRC-522-A. Record:
PRC-522-A
. PI-522-A
IV
Approved by;gfi?fiajébgé4:;fififfit\

1.3 (continued)
PI-580-A1
PI-589-A2
PI-592-~-B
1.4 ©Note that each changed at least 0.5 psig from
Step 1.1.
1.5 DReset PRC-52z-A to 5 psig.
HELTUM SUPPLY PRESSURE

 

2.1 While observing relay K-U6, have HV-500-N1 A
and B opened and cbserve that relay K-46& opens.

2.2 Close HV-500-N1 A and B and note that relay
closes.

2.3 While observing relay K-47, have HV-500-N2 A
and B opened and observe that relay K-47 opens.

2.t Close HV-500-I2 A and B and note that relay
closes,

2.5 While observing relay K-48, have HV~-500-N3 A
and B opened and observe that relay K-L8

opens .

8D-2
10/26/65
Init. Date/Time

 

 

 

 

 

 

 

 

2.6 Close HV~500-N3 A and B and note that relay
K-48 closes.
FP AND OFT BUBRLERS

 

3.1 Switch OFT test switch 8-38 to No. 1 equalizer
and note that OFT level indicators LI-599-B
and LI-599-B2 to approximately zerc and return
to original value when test switch is released.

3.2 Switch OFT test switeh $-38 to No. 2 equalizer
and note that OFT level indicators LI-600-B
and LI-600-B2 to approximately zero and return
to original value when test switch is released.

3.3 Actuate HS-599 and note that LI-599 increases
and emergency drain is initiated as indicated
by lights in ECC 19 at ~ 20% level. Record

 

 
 

3.5

3.8

3.9

3.10

3.11

3.12

3.13

3.14

3.15

8D-3
10/26/65

Init. Date/Time

 

(continued)

level .
Actuate HS-600 and note that LI-600 increases
and emergency drain is initiated as indicated

by lights in ECC 18 at ~ 20% level. Record

 

level

 

Switch fuel pump selector switch S-36 to record
LT_596 -
Switch fuel pump test switch S5-37 to No. 2

block and note that valve closes as indicated

 

by FI-593-A increasing to line pressure.

 

Release test switch and note that pressure on
FI1-593-A returns to normal.
Switch FP test switch S-37 to reference block

 

and note that valve closes as indicated by

FI-592-A increasing to line pressure.

 

Release test switch and note that pressure

on FI-592-A return to normal.

Switch fuel pump selector switch S-36 to
record LT-593.

Switceh FP selector switch 5-37 to No. 1
block and note that valve closes as indicated

by FI-596-A increasing to line pressure.

 

Releage test switch and note that pressure

on FI-596-A returns to normal.

Switch overflow tank test switch S-38 to No.

1 block and note that valve closes as indi-
cated by FI-599-A increasing to line pressure.
Release test switch and note that pressure on
F1-599-A returns to normal.

Switch OFT test switch to Reference block and
note that valve closes as indicated by

FI-589-A increasing to line pressure.
Approved by -7 /,{ Aty £

3.16

3.17

3.18

Release test switch and note that pressure on
FI-589-A returns to normal.
Switch OFT test switch to No. 2 block and note
that valve closes as indicated by FI-600-A in-
creasing to line pressure.
Release test switch and note that pressure on

FI-600-A returns to normal.

L ROD SCRAM CIRCUITS

 

)_""?l

4.2

4.3
bk

L.5
k.6

L.7
L.8

L.9

L.10

L.11

h,12

Check that all three safety channels are un-
tripped.

Push H5-100-A1 and note that safety channel
No. 1 trips at approximately l3OOOF. Record
temperature

Reset safety channel No. 1.

Push HS-100-AZ2 and note that safety channel
No. 2 trips at approximately l3OOOF. Record
temperature

Reset safety channel No. 2.

Push HS-100-A3 and note that safety channel
No. 3 trips at approximately l3OOOF. Record
temperature

Reset safety channel No. 3.

Push voltage monitor test switch on RM-NSCl-AZ
(Monitor and Test Unit) and note that safety
channel trips.

Push reset on RM-NSCl-A2, RSS-NSCl-4 and on
RSS-NSC1-46.

Push test switch on RM-NSCZ-AZ and note that
safety channel trips.

Push reset on RM-NSC2-A2, RSS-NSC2-A4 and on
RSS-NSC2-46.

Push test switch on RM-NSC3-AZ and note that

safety channel trips.

8D-4
10/26/65

Init. Date/Time

 

 

 

 

 

 

 

 

 

 

 

 
Approved by

 

Init.

10/26/65

Date/Time

 

4.13 Push reset on RM-NSC3-A2, RSS-NSC3-Al and
on RSS-NSC3-46.

 

.14 Push "test" on RSS-NSCL-AL and note that

all "A" control rod amps. go to zero.

 

L4.15 Reset RSS-NSC1-Ak.

 

4,16 Push "test" on RSS-NSC2-Al and note that all

"B" control rod amps. go to zero.

 

4.17 Reset RSS-NSC2-Ak.

 

L.18 Push "test" on RSS-NSC3-AL and note that all

11~ 1t
o

control rod amps. go to zero.

 

.19 Reset RSS-NSC3-Alk.

 

L.20 Push "1 sec. period" on RSS-NSCl-A2 and check
that ~ 1 sec period will trip RSS-NSCL-A6.

 

4.21 Reset RSS-NSC1-AlL and 46.

 

4.22 Push "1 sec. period" on RSS-NSC2-A2 and check
that ~ 1 sec. period will trip RSS-NSC2-46.

 

.23 Reset RSS-NSC2-AL and 46.

 

L.2l Push "1 sec. periocd"” button on RSS-NSC3-A2 and
check that ~ 1 sec. period will trip RSS-NSC3-A6.
4.25 Reset RSS-NSC3-A2 and 46.

 

4,26 Push "high current" button on RSS-NSCL-A2.
Adjust "adjust knob" on RS8S-NSCl-A2, and
note that RSS-N3C1-A3 trips at ~ 150% on
RM-NSC1 -Al.

L.27 Record vernier setting on RSS-NSC1-A2.

 

L.28 Reset all channel No. 1 trips.

4.29 Push "high current” button on RSS-NSC2-A2.
Adjust "adjust knob" on RSS-NSC2-A2, and
note that RSS-NSC2-A3 trips at ~ 150% on
RM-NoC2-Al..

L.30 Record vernier setting on RSS-NSC2-A2.

4.31 Reset all channel No. 2 trips.

4.32 Push "high current' button on RS8-NSC3-A2.
Approved by.fifiégégi&ifigfii‘fl*ffix / 2?@6
Y 10/26/65

Init. Date/Time

 

4.32 (continued)
Adjust "adjust knob" on RSS-NSC3-AzZ, and
note that RSS-NSC3-A3 trips at ~ 150% on
REM-NSC3-Al.
%.33 Record vernier setting on RSS-NSC3-AZ.
4.34 Reset all channel No. 3 trips.
5 EMERGENCY FUEL DRAIN

 

 

 

 

Initiate an emergency fuel drain by the following
procedures, and check that the actions listed occur.
Keep the time of drain test to a minimum to avoid
thawing FV-103 and verting drain tanks. Monitor
the freeze valves temperatures on TR 3600 to
assure that this does not occur.

5.1 Switch the emergency drain switch on the
console to drein, and note the following:
5,1.1 Lights go out in ecircuits 18 and 19.
5.1.2 The drain tank vent valves, HCV-573-Al,

HCV-575-A1 and HCV-577-ALl, open (Check
lights on MB 8, 9, and 10.). -

5.1.3 The drain tank bypass valves, HCV-~5u4L-AT,

HCV-545-A1 and HCV-546-Al are closed, check
that they open.

 

——————

5.1.4 If the drain tank helium supply valves,
HCV-572-A1, HCV-574-A1l, HCV-576-A1 and
PCV-517-Al are open, check that they close._

5.1.5 The air block valves to FV-103, HCV-919-Al,
HCV-919-Bl, close as indicated by FV 103
temperature.

5.2 Check high temperature scram as follows.

5.2.1 Push BS 100-Al and hold in. Note that
temperature indicates above 13OOOF.

5.2.2 Push HS 100-A2 and note that lights in
ECC 18 and 19 go out when temperature
   

Approved by. 8D-7

10/26/65

Init. Date/Time

 

5.2.2 (continued)
indication reaches 13OOOF. Record tem-
perature

5.2.3 Releage HS 100-Al and depress.HS 100-A3.
Note that lights in ECC 18 and 19 go out

 

when temperature indication reaches 13OOOF.
Record temperature

5.2.4 Release HS 100-A2 and depress HS 100-Al.
Note that the lights in ECC 18 and 19 go

out when temperature reaches 13OOOF.

 

Record temperature

5.2.5 Release HS 100-Al and A3 and note that
lights in ECC 16 and 12 are on.

5.2.6 Observe FV 103 temperatures until con-
ditions are normal.

5.3 Push OFT level test switches H5-599-B and
HS-600-B, one at a time, and note that lights
in ECC 18 and 19 go off when level exceeds
20%. Record LI~599-BL and LI-600-Bl.

 

6  HIGH/LOW REACTOR CELL PRESSURE
6.1 Reactor cell pressure <10.5 psia on 2/3 of
P33-RC-H, PSS-RC-J and PBS5-RC-K causes the

 

following control actions to occur:

6.1.1 CCP No. 1 and CCP No. 2 to stop.

6.1.2 Cell evacuation valve HCV-565-A1 to
close.

6.2 Reactor cell pressure >16.7 psia on 2/3 of
PSS-RC-B, PSS-RC-F and PSS-RC-G causes the
following control actions to occur:

6.2.1 Emergency contaimment block which
cleses instrument air line block valves

and liquid waste block valves.
Approved by

6£.2.

 

8D-8
10/26/65

Init. Date/Time
2 Cell evacuation valve HCV-565-A1 to open

 

(or stay open).

6.3 Reactor cell pressure <10.5 psia:

0.3.

6.3.

6.3.

6.3.

6.3

6.3.

1 At the valve panel in the North Electric
Service Area, slowly cpen HV-RC-K and ralse
the pressure on PSS-RC-K until XA-L002-5
alarms. (Do not exceed 5 psig on PI-RC-K.)
2 Slowly open HV-RC-H and raise the
pressure on PSS-RC-H. (Do not exceed 5
psig on PI-RC-H.) Note that CCP 1 or

CCP 2 stops __ and reactor cell
evacuation valve(HCV-565-A1) closes
when the difference between DP back

pressure + cell pressure is U4 psi.

 

(PI-RCE minus PI-RC-B = ).
3 Close HV-RC-H . Start CCP No. 1
or No. 2

L Slowly open HV-RC-J and raise pressure
on PSS-RC~J. (Do not exceed 5 psig on
PI-RC-J.) Note that CCP 1 or CCP 2

stops __ and reactor cell evacuation
valve (HCV-565-A1) closes __ when

the difference between DP back pressure
and cell pressure is 4 psi. (PI-RC-J
minus PI-RC-B = ____.)

 

.5 Close HV-RC-K. ©Start CCP No. 1 or

No. 2
6 Slowly open HV-RC-K and raise pressure

 

on PSS-RC-K. (Do not exceed 5 psig on
PI-RC-K.) Note that CCP 1 or CCP 2 stops
____and reactor cell evacuation valve
(HCV-565-41) closes __ when the difference
between DP back pressure and cell pressure

is b psi. (PI-RC-K minus PI-RC-B = .)

 
Approved brm@(mm 80-9
10/26/65

6.3.

6.3.

Init. Dabte/Time

 

7 Close HV-RC-J and HV-RC~H and note
that XA-L0O02-5 clears.
8 Start CCP No. 1 or No. 2

 

r————

 

6.4 Reactor cell pressure 16.7 psia:

6.4.1 Slowly open HV-RC-G and increase

6.k,

pressure on PI-RC-G until XA-4002-5 alarms
(Do not exceed 5 psig on PI-RC-G.)
Record PI-RC-G . Note that PI-9013-1AL
drops to zero _ and all other gages
in the 9013 geries do not change
Slowly open HV-RC~B and increase pressure
on PI-RC-B (Do not exceed 5 psig on
PI-RC-B.) until HCV-9013-1A1 and 9013-1A2
operate . Record PI-RC-B
Note that the following actions occur:
6.4.1.1 Instrument air line block valves
close . . (PI-9013-1A6 goes to
Zero )
6.4.1.2 Liguid waste block valves close:
FCV-333-£1  FCV-3h3-pm1
FCV-333-A2 _#___FCV-3A3—A2 L
6.4.,1.3 Reactor cell evacuation valve

HCV-565-A1 opens (or remains opened)

 

 

2 Close HV-RC-B _ . ©Slowly open
HV-RC-F and increase pressure on PI-RC-F
(Do not exceed 5 psig on PI-RC-F.) until
HCV-9013-1B1 and 9013-1B2 operate. Record

PI-RC-F . DNote that the actions listed
in 6.4.1.1 through 6.1.4.3 occur:

6.4b.0.2

6.4.1.2

6.4.1.3

 
Approved bM 7S %?_/_ My - /523363;%(5)

Init. Date/Time

 

6.4.3 Close HV-RC-G __ . Slowly open
HV-RC-B and increase pressure on PI-RC-B
(Do not exceed 5 psig on PI-RC-B.) until
HCV-90L3-1AL and 9013-1AZ operate
Record PL-RC-B . lNote that the
actions listed in 6.4.1.1 through 6.4.1.3
occur: .

6.4h.2.1
6412 .
6.4.1.3

6.4.4 Close HV-RC-F and HV-RC-B ___ and

note that XA-4002-5 clears and that all

 

pressure gages in the 9013 series read
about 50 psig .
7 COOLANT PUMP SPEED AND COOLANT SALT FLOW
7.1 Actuate the following test switches one at a

time and observe that the corresponding relays

 

 

drop out:
SWITCH RELAY
HS-202-A Kb |
H5-20z2-B K5
H3-202-C KAG and KB6 ’
H5-201-A Ky .
HS-201-B K8 .

(.2 Push the calibrate buttons on the following .

instruments one at a time and observe that
the corresponding relays drop out:
INSTRUMENT RELAY

Sl-CP-G1 K9

SI-CP-G2 K10

8 SAMPLER-ENRICHER
8.1 Check that the permissive lights in the main

 

control room and at the sampler enricher panel ’
Approved bx/zéfigzzééz?)wth 8D-11

8.1

8.3
8t)'l'

8.5

8.7

8.8

8.9

10/26/65

Init. Date/Time

 

(continued)
are actuated by the permissive switch on MB-8.

Leave on.

 

Close capsule access port (HS-651-A)
removal valve {HS-RV-A4)  , operational
valve (HS-OV-A) _ , and HSV-678-A .
Maintenance valve should be open _ , cable
drive fully withdrewn __ , fuel pump bowl
pressure less than 10 psig _ , cover on
manipulator  , and area 1C at the same
pressure as area 3A . RE-675-A and
RE-675-B must not be in alarm condition
Buffer pressure should be applied to RV, 0OV,
MV, and AP

Note that removal valve will not open.

 

 

Insert transport container through removal
seal and open HCV-666-D. After "removal
seal closed" light comes on (ZI-666-E),

note that removal valve can be opened.

Close removal valve. Before buffer pressure
reaches 50 pesia (PR-670-B), note that access
port and operational valve will not open.
After "removal valve closed" light (zI-670-B)
comes on, note that access port will open.
Close access port. Note that there is a 15-
second time delay on HSV-053-A.

 

Before buffer pressure reaches 50 psia
(PR-669-B), note that removal valve and
operational valve will not opens.

Increage pressure in area 1C to pump bowl
pressure using HV-557 or until PdS-1C-E
alarms XA-4036-5 and XA-L008-2 whichever

is higher. Note difference in pressure
Approved by4(’#;f;/;

8.9

8.10

8.11

8.12

8.13

8.14

IMPORTANT:

8D-12
10/26/65

 

Init. Dat@/Time

 

(continued)
between area 3A and area 1C at which alarm

sounds. Record AP

 

Note that access port will not open when PdS-1C-E
is in alarm condition. o
Note that capsule drive motor will not insert.

After “access port closed" light (ZI-669-B)

comes on, open operational valve until closed

light (ZI-OV-A2) goes off.

 

Note that capsule drive motor will operate

when closed light on operational valve (ZI-OV-A2)
and on maintenance valve (2I-MV-A2) are off.
Insert cable more than & inches. Note that
operational and maintenance valves will not
close

Should either or both valves start to close,

release the switch immediately or there will be permanent

damage to

8.15

8.16

8.17

drive unit cable and to valve.

Withdraw cable and note that drive motor stops
automatically and lower limit light (ZI-CD-A3)
goes off.

 

Close maintenance valve leaving operational
valve open. Before buffer pressure reaches
35 psia (PR-655-C), note that HSV-678-A
will not open.

Before PR-655-C reaches 50 psia, note that

 

access port and removal valve will not open

and cable drive will not insert. o
After "operational or maintenance valve closed"
light comes on (ZI-OV-MV-C), open and close

removal valve. Before buffer pressure reaches

50 psia (PR-670-B), note that maintenance valve

and access port will not operate.
Approved by széfiggzéiyhfiflfifxlj 8D-13

’ 16/26/65

Init. Date/Time

 

8.19 Réduce pressure in area 1C to that of area
3A through HSV-678-A. Note that alarm
XA-4036-5 clears.

8.20 After "removal valve closed" light (ZI-670-B)

 

comes on, open and close access port. Before
buffer pressure reaches 50 psia (PR-669-B)
note that maintenance valve and removal valve
will not open.

8.21 Open HSV-678-A. DNote that it will close when

 

either the operational or maintenance valve

is opened.

 

.22 Pressurize area 1C until PS-1C-E activates
XA-4037-1 and XA-4008-2 per switch tabulation.

Record pressure reading of PR-1C-E

 

8.23 Pressurize area 3A, and manipulator cover
until PS-AR-3A activates XA-4037-2 and
XA-4008-2 per switch tabulation. Record
pressure reading of PE-AR-3A .

8.24 Activate RS-678-C and RS-678-D, one at a time,
with a source. DNote that XA-4037-6 and XA-4008-2

 

annunciate each time.
8.25 Activate R§675-A and RS-675-B, one at a time,

with a source. Note that XA-L037-5 and XA-L008-2

annunciate  and HSV-678-A _ , HSV-078-B2

___, HSV-677-A __, EsV-5h2-A __, HSV-665-B

__, HSV-655-B ____, HS8V-657-D ___, HSV-680-B

___, H8V-675-A2 __ , and HSV-659-B

close each time.

————————

—

 

8.26 Check with Operations Chief before proceeding:
Increase fuel pump bowl pressure until PS-522-A3
glarms XA-4037-4 and XA-U40OC8-2 per switch tabu-
lation. Note that HSV-668-B _ , HSV-655-B
___, BBV-657-D ___, and HEV-680-B ____ close
7
Approved by,é§2;3234553@ga\ 8D-1k

10/26/65

Init. Date/Time

 

8.26 (continued)

and that access port , Operatiocnal valve

, and maintenance valve will not

open.

8.27 In area 3B carefully close HV-542
NOTE: This is a soft-~seated valve.

Open HSV-6T8-A  , HSV-678-BL __ , HCV-66T7-A
____, and BESV-542-A . Pressurize area 1C
and note that PSS-542-B and PSS-542-C both
operate to close ESV-542-A per switch tabulation.
Record pressure . Open HV-542.

9 EXFERCISE CONTROL RODS

 

9.1

9.2

9.3

9.4 Readjust rods to desired positions.

Record control rod position.
Rod No. 1 Rod No. 2 Rod No. 3

While observing control rod motor current in

 

NESA, raise rod No. 2 and No. 3 approximately

2 inches. Adjust rod No. 1 (manually or by
servo) to maintain reactivity constant. Record
control rod motor currents while rods are
moving.

Rod No. 1 Rod No. 2 Rod No. 3

 

Record control rod positions

Rod No. 1 Rod No. 2 Rod No. 3

 
v
Approved Ly ity 9-1
7 - 10/4/65

9 UNUSUAL OPERATING CONDITIONS

During operation difficulties of various kinds and severity may be
encountered. To plan in advance for all possible troubles would be im-
practical. In this section an attempt is made to anticipate some of the
more probable or more serious ones; and suggest remedial actions,
Conditions at the time may alter the a&otion to be taken. In some cases
it may be possible to instigate strict administrative control as a substi-
tute for control or even safety interlocks. 1In this case it will usually
be desirable to consult the Operations Chief.

The sections are written as check lists to a&id in recording the
action taken. However they need not be filled out until the situation
is under controil.

A1l personnel should be thoroughly familiar with the suggested

corrective action.
\ i{{’
Approved byfl%mfl 9A-1

9A LOSS OF ELECTRICAL POWER

Various degrees of loss of electrical power are possible atv the
MSRE. The operator actions required and control actions which will
occur are given in the sections below.

1 1,055 OF PREFERRED TVA FEEDER

 

If power is lost on the preferred feeder (line 23k4) the motor-
operated pole-line switch No. 129 will open. Following a 6-second
delay the alternate feeder (line 294) motor-operated pole-line
switeh No. 229 will close and power will be resumed. It wiil be
necessary to restart some of the equipment as described in section
3A 3.1. After this, operation can continue until voltage return
on the preferred feeder. To avoid overloading the alternate feeder,
the radiator blowers should not be operated at this time.

2 COMPLETE LOSS OF TVA POWER - ALL DIESELS OPERABLE

 

If power is lost on both TVA feeders, the two motor-operated
pole-line switches (No. 129 and 229) will open. The operator should
proceed ag follows:

Tnit. Date/Time

 

2.1 Start all three diesel generators and restart
the egquipment asg given in section 3A 3.2. The
radiator blowers cannot be operated on the
generators. The scanners, chart drives and
control room clock will be automatically
transferred to motor generator L.

2.2 Continue operation at heat loss power or lower
until the voltage from the 250v battery bank
drops below acceptable limits. At which time,
the fuel and coolant systems should be drained,
and if necessary, the afterheat removal system
rut into service. o

2.2 Since the life expectancy of the 250v batteries

is approximately 2 hours, reduce all unnecessary

load-

bt ik
) A
Approved by 7 ' 7Y . SA-2
& Efi%; 10/1/65

Init. Date/Time

 

(Main Control Room)

Z2.3.1 Stop FOP-2 and COP-2 and start FOP-1
and COP-1. This will transfer 4-8kw to
the diesel generator.

(Outside Battery Room)

2.3.2 Open the 250 VDC light breaker in the
250v distribution panel. This will remove
the emergency DC lights from the batteries.
This amounts to approximately 4 kw. (4
portable battery operated light should be
in the control room at this time.) L

3 FAITURE OF DIESEL GENERATOR NO. 3 DURING A TVA POWER
CUTAGE

If diesel generator No. 3 cannot be started

 

or fails during operation, the operator should pro-
ceed as follows:
(Outside Battery Room)
3.1 The fuel and coolant pumps will not be operable.
Refer to sectlion 9C for details of operation.
3.2 Close the 250v Dc light breaker in the 250v
digtribution panel to supply emergency Dc
lighting if lights are not already on.
(Main Control Room)
3.3 Check that FOP-2 is in operation. (FOP-1 can-
not be operated unless diesel generator No. 3
hag power. )
3.4 Stop COP-2 and start COP-1. This will conserve
250v battery life.
3.5 Where alternate equipmenf 1s powered by both

diesel generator No. 3 and No. L, start the
equipment on diesel generator No. 4 (Sec. 34,
Table VI).

(Switch House)
Approved bywfim /9%3
10/1/65

3.6

3«7

Init. Date/Time

 

Check that the drain-tank space-cooler DCC
transfer switch (located near entrance to

M G room) is set to MCC-GL. Restart DCC

if necessary.

Since component coolant pump No. 3 will not
be operable, emergency alr from the auxiliary
air compressor will be needed to keep FV-204
and 206 frozen asg well as fuel processing

freeze valves if they are not deep frozen.

 

(Diesel House)

3.7.1 Start the service alr compressor.

 

(Water Room)

3.8

3.7.2 Open V-967A.

3.7.3 Set PCV-967 to & psig.

Since one of the reactor cell space coolers
(RCC 1) will not be in operation, the cell

 

 

temperature will increase with resulting
increase in pressure. Operator should

proceed as follows:

(Water Room)

3.8.1 Close V-838A to shut off the water
flow to RCC 1.

3.8.2 Open V-840A, V-836A and V-8T73A to
give maximum water flow to RCC 2 and
DCC and the component coolant heat

exchanger.

(Vent House)

3.8.3 If the cell pressure increases due 10
the temperature rise, increase the rate
of evacuation by opening V-560A and
V-569B or V-565C to control pressure at
12.7 psia.

Arre—— e

NOTE: When TVA power is resumed or when diesel generator
  

Approved 9A-L

10/1./65

Init. Date/Time

 

No. 3 is in operation, RCC-1 can be put back in service.
The water flow (V-8384) should be increased gradually

in order to avoid pulling too high a vacuum on the cell.
Flow to RCC 2, DCC and component coolant heat exchanger
should be decreased to normal flow rate (V-840A, 836A and
873-4).

3.9 When the voltage from the 250v battery drops
to 212v or the cell air temperature rises to
200 degrees F, the fuel and cooclant systems
should be drained.

3.10 One of the tower fang, TF 1, will not be in
operation. During periods of high heat locad
during the summer this could increase the
cooling tower water temperature and subse-
quently heat the treated water. All equip-
ment should be watched for overheating.

(S8ee section 9B.) L
L FAITLURE OF DIESEL GENERATOR NO. 4 DURING A TVA POWER

OUTAGE
If diesel generator No. 4 cannot be started

or fails during operation, the operator should

proceed ag follows:

(Main Control Room)

L.l The fuel pump will not be operable. Refer to
section 9C for details of operation.

4.2 Check that COP-2 is in operation (COP-1 can-
not be operated unless diesel generator buss
No. 4 has power.). .

L.3 Stop FOP~2 and start FOP-1. This will conserve
250v battery life.

L. Where alternate equipment is powered by gener-
ator No. 3 and No. 4, start the equipment on

generator No. 3 . (See section 34, Table V.)
  

:-;;?C}/, a OA-5

10/2/65

Approved by .-~

Init. Date/Time

 

(Switch House)

4.5 Check that DCC transfer switch (located near
entrance to MG room) is set to MOC-G3. Restart
DCC if recessary. .

4.6 Since one of reactor cell coolers (RC-2) will
not be in operation, the cell temperature will
increase with a resulting increase in pressure.
The operator should proceed as follows:

(Water Room)
L.6.1 Close V-84CA to shut off water to RCO-2.
4.6.2 Cpen V-838A, V-83€4, and V-8734 to give
a maximum flow to RCC-1, DCC and component
coolant heat exchanger.
h.6.3 If the cell bressure lncreases due to
the temperature rise, increase the rate
of cell evacuvation by opening V-5694 ard
V-569B or V-565C to conbrol pressure at
1Z2.7 psia. .
NOTE: When TVA power is resumed or when diesel generator
No. 4 is in operation, RCZ-2 can be put back in service.
The water flow (V-840A) should be throttled and increased
gradually to avoid pulling too high a vacuum on the cell.
Flow to RCC-1, DCC and component cooling heat exchanger
should be decreased to the normal flow rate (V-8384, V-8364
and V-8734).

4.7 When the 250v battery drops to 212v or the cell
alr temperature rises to 200 degrees F, the
fuel and coolant systems should be drained.

4.8 One of the tower fans, TF-2, will not be in
operation. During periods of high heat load
during the summer,this could increase the

A

cooling tower water tempersture and subse-

quently hesat the treated water. ALl equipment
9A-6
10/1/65

 

 

Init. Date/Time

 

4.8 {continued)

should be watched for overheating. (See
section 9B.)
5 FAILURE OF DIESEL GENERATOR NO. 5 DURING A TVA
POWER OUTAGE

 

This diesel furnishes all emergency electrical
heat to the process system. Continued operation
on emergency power without diesel generator No. 5
would endanger the ability to drain the system by
cooling the thawed FV in the reactor system drain
line and FV's in the coolant system.
The operator should proceed as follows:
5.1 If diesel generator No. 5 cannot be started
within two minutes after a power outage,
switch FV-103, FV-204, and FV-206 to thaw.

5.2 Continue to try and start diesel generator

 

No. 5. If diesel generator No. 5 starts or

TVA power is regained before the drain begins,

freeze FV-204, 206 and 103 and resume operation.

5.3 Bince the life expectancy of the 250v
batteries is approximately 2 hours, reduce
all unnecessary load.
(Main Control Room)

5.3.1 Stop FOP-2 and COP-2 and start FOP-1
and COP-1. This will transfer 4-8 kw to
the diesel generator.

(Outside Battery Room)

5.3.2 Open the 250v Dc light breaker in the
250v distribution panel. This will remove
the emergency Dc lights from the batteries.
This amounts to approximately U kw.

6 FATLURE OF DIESEL GENERATOR NO. 3 AND DIESEL

 

GENERATOR NO. 4 DURING A TVA POWER OUTAGE

 
- '(l‘j : Tt
Approved'@gfifi?f??“aiérha/vk

Init.
6.1 This automatically drains both systems as no
cooling air is provided to keep the FV's
frozen.
6.2 Continue attempts to start these diesels to
get equipment back into operation (See section

OA3 and 9AL.).

Date/Time

 

7 FATILURE OF DIESEL GENERATOR 3 AND DIESEL GENERATOR
5 OR DIESEL GENERATOR L AND DIESEL GENERATOR 5
DURING A TVA POWER OUTAGE
7.1 Start a drain of both fuel and coolant system

 

 

 

if DG No. 5 fails to start within two minutes.
7.2 Operator should switch FV-20k, 206, and 103
to thaw (section 9A5).

 

7.3 Operate equipment on DG No. 3 or No. 4 depend-
ing on which is operating. (See Section 9A3

or 9ak.)

 

NOTE: If operating on Diesel Fmergency power if possible
do not transfer to TVA alternste line, Feeder 294. Wait
until preferred line is restored, then return to TVA as
outlined in section 3A 3.3.1.
8 L0OSS OF 250v Dc SYSTEMS
8.1 Loss Of 13.8 KV Control Power
Tf the 13.8 KV control power is lost, no

 

 

operation of the preferred or alternate feeder

switches can be made from the ACR panel 11.

If the 13.8 KV control power is lost and
there is an outrage on the preferred feeder,
the operator should proceed as follows:

8.1.1 Start all three diesel generators and
restart the equipment as given in Section
3A 3.2 "Complete Loss Of TVA Power.”

8.1.2 Continue operation on diesel emergency

power if possible. If it ds necessary %o
OA-8

APPI'OVed -by“ ’f"fl;*i '
) 10/1/65

 

Init. Date/Time

 

8.1.2 (continued)
transfer to the alternate feeder, call
the electrical utility group to make the
transfer to the alternate feeder manually
at pole E after permission to make the
transfer has been given by the switch

house group.

 

8.1.3 Transfer load from Generator 3 and 4
without loss of power to bus No. 3 and
No. 4. After transfer shut down generator
3 and 4. Transfer load from Generator
5 to bus 5. Continue operation on alter-
nate feeder until voltage is restored on

the preferred feeder.

 

8.2 Loss Of 250v It Trip Power For Process Power

 

Breakers

1f the 250v IX trip power is lost, the
following breskers will have to be tripped
manually at the switch house until the 250v
DC voltage is restored. Since the control
circuits will not function, consideration
should be given to stopping MBL, MB3, FP

and CP.

Breaker Equipment

Q MB No. 3

P MB No. 1

R TVA Bus Main Breaker
Z Bus No. 5 Tie Breaker
AA Gen. No. 5-2 MCC

CC Gen. No. 5-1 MCC
Approved bX/,fifzggjfgzk%;%;;flngfi%\ 9A-9
- v/

10/1/65

Init. Date/Time

 

Breaker Eouipment

D Fuel Pump

E C. C. P. No. 2

H C. C. P. No. 1

K Coolant Pump

A-1 Bus No. 3 Tie Breaker
A-2 Bus No. 4 Tie Breaker
A-3 Gen. No. 4 Main Breaker
A~k Gen. No. 5 Main Breaker
A-5 Gen. No. 3 Main Breaker

8.3 Loss Of 250v DC To Motor Generator No. 4

 

The loss of 250v IC to motor generator No.
4 will stop the generator, thus causing the
loss of the emergency 120/240v AC power. TFOP
No. 2z and COP No.z will stop and the instru-
ment power panel No. 2 and No. 3 will be auto-
matically transferred to TVA. FOP No. 1 and
COP No. 1 will sutomatically start due to low
0il pressure. Check and restart required
equipment listed in Tables IV, V, and VI, !
Section 3A that was operating before the
momentary loss of control power. TUse con-
trol room and walking logs to determine
eguipment to be restarted.
9 IO0SS OF TINSTRUMENT POWER

The many possible combinations of loss of instrument power make
it difficult to recommend corrective action. The following is a
list of various instrument breakers and the instruments which they
serve. This can be used as a guide in restoring instrument power.
Instrument power is supplied from 9 panels. Instrument power

panel No. 1 and No. Al are supplied from 48v IC system. Instrument
power panel No. 2, No. 3, and No. A3 are supplied from MG No. 4 with
  

9A-10
10/1/65

Approved by/””
9 (continued)
automatic transfer to MCC~GL. To transfer back to MG No. 4, push
reset button mounted above transfer switch. Instrument power panel
No. 4, No. Al, No. 5, and No. 6 are supplied from MCC-G3. System
supplied from individual breakers are as follcws:
9.1 Instrument Power Panel No. 1 (L48v DC)
Breaker No. System
1 vafety Circuits
safety Circuits
safety Circuits
Safety Circuits
IFP Al
Safety Circuits

-~ O V1 F W o

Safety Circuits
Channel No. 3

Control Circuits

Control Circuits

 

10 Bampler-Enricher
11 Spare
12 opare
13 Spare
1h Spare
9.2 Instrument Power Panel Al (48v DC to 120v AG)
Breaker System
1 Process Radilation

Monitors Channel No. 3

2 Radiator Outlet Temp. Modules
Reactor Outlet Temp. Modules
Coolant Salt Flow Meters

3 Recorder Drives
Control Room Clock
Control Room Scanner
Standby Power

L Spare
Approved bfififgfif/éfi;{%;/%%4fi? OA-11

 

10/1/65
9.3 TInstrument Power Panel No. 2 (115v AC - Reliable)
Breaker No. System
1 Control Circuit

FV 103, 10k, 105, 106

2 Control Circuit

Fv 107, 108, 109, 110, 111, and 112
3 Control Circuit

FV 204k, 206
L Control Circuilt

AC No. 1, FOP No. 1, COP No. 1

5 Control Circuit
AC No., 2, FOP No. 2, COP No. 2
6 Spare
T ' Safety Circuits
Channel No. 1
8 Radiator
Load Control
9 Rod Drives
Interlock Relays
10 Rochester Alarms
Substation Power Supplies
1l Annunciators Main Board and
TS FOP 1 and 2, TS COP 1 and 2
12 Indicator Lamps -
13 Annunciators
(Aux., Muclear, and TSP Boards)
14 Coolant Salt Sampler
15 Annunciators
Fuel System,
16 Sampler-Enricher
17 Control Circuits
Fuel System
18 Annunciators

Sampler-Enricher

19 Spare
20 Bell Telephone Intercom System
QA-12
10/1/65

 

9.4  Instrument Power Panel No. 3 (115v AC - Reliable)

Breaker No. System
1 Beryllium Monitor

Oxygen Analyzer

™ 202 A5-B5-C5
™ 100 All-A21-AR1

no

3 Temperature Scanner
Standby Power

Iy Spare
Spare

FV Temp. Switches,

High Level Gamma Monitors
fuel Pump Speed,

Coolant Pump ILevel

 

 

T RX NC1-A, RX NC2-A
8 IPP A3
9 Nuclear Instrument
10 ECT Power Supplies
Safety Channel No. 1
11 Nuclear Instrument
12 Spare
13 Nuclear Instrument
14 Spare
15 Chemical Processing
16 Spare
17 Spare
18 Spare
19 Spare
20 Spare
9.5 TInstrument Power Panel No. A3 (Regulated 115v AC)
Breaker No. System
1 Process Radiator Monitors

Safety Channel No. 1
sampler-Enricher
Safety Channel No. 1
ECT Control

Spare

O 1 ow N

opare
  

Approved by f””akiflvy OA-13
10/1/65

9.6  Instrument Power Panel No. 4 (115v AC - TVA Bus)

 

 

Breaker No. oystenm

1 Safety Circuit
Channel No. 2

2 IPP AL

3 Power Supplies
Safety Channel No. 2

L Cabinet Lights

*.

5 Recorder Drives

Control Rocom Clock
Control Room Scanner
Normal Power

6** Temperature Scanner
Normal Power

7 safety Circuits
O- Analyzer Block Valves

8 Coolant Drain Cell
Sump Pump

9 HCV-93hA

10 Reactor "On'" Lights

11 77

12 Spare

13 Spare

1k Spare

15 Spare

16 7?2

17 Spare

18 Spare

19 Spare

20 opare

 

*IPP No. 4 - Breaker No. 5 normal supply, with automatic transfer to

IPP No. Al - Breaker No. 3 on loss of voltage on load side of IPP No. Lk -
Breaker No. 5. Will automatically transfer back when voltage is restored
to IPP No. 4 - Breaker No. 5.

**IPP No. 4 -Breaker No. 6 normal supply, with automatic transfer to IPP
No. 3 - Breaker No. 3 on loss of voltage on load side of IPP No. L4 --
Breaker No. 6. Will automatically transfer back when voltage is restored

to IPP No. &t - Breaker No. 6.
OA-14

 

 

 

 

 

10/1/65
9.7 Instrument Power Panel No. AL (Regulated 115v AC)
Breaker No. System ¥
L Process Radiation Monitors
Safety Channel No. 2
2 ECTI Connectors
vafety Channel No. 2
3 RQ NCC1lA
RQ NCC 2A
L Spare .
9.8 TInstrument Power Panel No. 5 (120/208v AC 3¢ - TVA)
Breaker No. System
1 RM-TOL5-A2
2 RM-T016-A2 :
3 RM-T01T7-A2
4 RM-T7011-A2 :
> RM-T7012-A2
6 RM-T013-A2
T RM-T014-A2
8 RM-T000-A2
9 RM-TO01-A2
10 RM-T002-4A2
11 RM-T7003-42 '
12 RM-T7004-A2
13 RM-T7005-A2 ’
1k RA-7025 Alarm Buzzer
15 Stack Light
Stack Receptacle
Stack Tape Deck Receptacle *
16 Stack Sample Pump Receptacle
17 Stack Sample Pump Receptacle
18 Stack Sample Pump Receptacle
19 RM-STA-2A
RM-STR-2A
RM-STIC-2A
20 Coolant Sampler *

Vacuum Pump
-t
Approved bxéé%f??%%é;afi&!l 9A-15
10/1/65

9.8 (continued)

 

Breaker No. oystem

21 Sampler-Enricher Controls

22 Spare

23 Spare

oL Spare

25, 27, 29* Maintenance and Operational Valve

) Motors

26 Spare
. 28 Spare

30 Spare

*
Breaker handles linked together for 3 ¢ circuit.
9.9 Instrument Power Panel No. 6 (120/208v AC - 34 - TVA)

 

 

Breaker No. oystem
1, 3, 5** Tape Drive
o, L, &%F Tape Drive
T Spare
8 Spare
9 Input - Output No. 1
10 opare
' 11 X-Y Plotter
12 logger No. 2 and No. 3
’ 13 Spare
. 14 Blank
15 Blank
. 16 Spare
17 Tape Punch and Conscle
18 Ioggers No. 1 and No. k&
19, 20, 21, 22 Spare
23 Core Memory
25 Core Memory
oly, 26, 28%%F Ma.in
. 27 Blank

*¥%
Fach a 3-pole breaker.
Approved Db

  

fl%fi%\ OB-1
7/28/65

9B LOSS OF COOLING WATER

1 TREATED WATER SYSTEM

The loss of all treated water flow could lead to serious damage to

equipment if operation were continued too loog. On loss of flow the

operator should proceed as follows:

1.1
1.2

1.3

1.k

otart standby pump.

Determine reason for failure of first pump. Put repair request

on punch list or proceed to get punp back in service,

If both treated water pumps are out of service, take necessary

steps to repair the less damaged one as soon as possible.

Determine time needed for repairs and proceed tc protect the

equipment listed below within the time 1imit specified.

1.k,

1.k

1 Fuel Pump and Coolant Pump Motors can be run without
cooling for ~ 10-15 minutes. After this time the flow switch
will stop the pumps. Keep a check on system temperatures

and drain systems 1f freezing appears to be possible.

.2 Reactor Cell and Drain Tank Cell Space Coolers can be

without water for ~ 20 minutes before the cell temperature
reaches 200 degrees F. During this period the cell can be
kept below atmospheric pressure by evacuating through L-569
or L-565. When cell reaches 200 degrees F drain the system
and turn off all heaters in RC and DIC. Close V-836A,
V-838A, V-8LOA. Do not allow salt to freeze in the drain

or flush tanks. Periodically turn on heaters or transfer
salt to the fuel storage tank if necessary. When water flow
is restarted, throttle flow to the space coolers and put

one cooler in service at a time fto prevent over-evacuating
the cells. Increase nitrogen purge and if necessary to avoid
evacuating cell below 10 psia add air to the cells through
sump Jjet supply. Keep discharge from Jjets closed. Stop

cell evacuation until cell temperature returns to normal.
Approved 1 -’hhfbl 9B-2
T/28/65

1.4.3 Thermal Shield water can be off ~ 110 minutes at full
power or 270 minutes at zero power before boiling starts.
If at power take the reactor subcritical. If water flow
cannot be restored within time limit, drain the system and
shut off heaters in reactor cell.

1.5 Radiation Block

 

Radiation in the cooling water would block all flow to the RC
and DIC equipment. The operator should proceed as follows:
1.5.1 Take reactor to heat loss power.

1.5.2 Determine which water line contains the source of
radiation. Isolate this system by closing hand valves in
the supply and discharge lines.

1.5.3 Reset RIA 827 and FSV-84LAL to allow block valves to open
and restore circulation to other equipment.

1.5.4 Observe time limits in step 1.4 to various equipment for
continued operation.

2 COOLING TOWER WATER

Although the cooling tower water is less critical than the treated

water, certain equipment cannot be kept in coperation after loss of

cooling tower water flow. Therefore both pumps should be kept in
good operating condition. On loss of flow the operator should pro-
ceed as follows:

2.1 On loss of one pump, the stand-by pump should be started
immediately. As soon as possible repairs should be made to the
damaged pump.

2.2 On loss of both pumps determine the time needed for repairs.
Based on the repair time, proceed as follows:

2.2.1 Check and adjust water flow to Drain Tank Condensers,
V-810 and V-812 in water room. (Transfer to process water
is automatic.)

2.2.2 Manually transfer instrument air compressor to process

water. Close V-880 and open V-872 in Diesel House.

e
Approved by

o

2.2

2.2.

A7 | 98-3
7/28/65

.3 'The Fuel and Coolant Tube 0il Packages can be without

cooling for 10-20 minutes. If water will be off longer than
this, shut down reactor and drain fuel and ccolant system.

Do not shut off lube oil pumps.

 

L With tower water off the treated water would heat at
~ 2 degrees F/minute and the charcoal heds ~ 1/4 degrees
F/minute. This could cause some heating of equipment in
treated water system, see Sect. 98B 1. If charcoal bed is
fully loaded the increasing temperature could cause some
increase in stack activity. If stack activity exceeds
allowable 1limits, open standby charcoal bed and isolate

operating bed.
Approved by@fl\ /9@‘?1
7/26/65

o

1

9C LOSS OF FUEL OR COOLANT PUMP

1055 OF FUEL PUMP

 

1.1.1 Loss of fuel pump level. This could be caused by low
salt temperature, lossg of pump bubble helium flow, bubbler
switch in the off position or a leak in the system.

1.1.2 Loss of coolant pump - see Section 9C-2.

1.1.3 Loss of treated cooling water flow - see Section 9B-1.
Low ccoling water flow could be caused by mis-operation of
throttling valves, or a plugged line. A time delay relay
will allow the pump to operate for 15 minutes without water.

1.1.4 Electrical trouble. This could include accidental pushing
of the stop button or opening breaker D on switchgear
Bus #L. Other electrical trouble should be investigated

1.1.5 Coolant off-gas activity. This would indicate a leak in
the fuel heat exchanger (or malfunction of the radiation

monitor) and automatically would initiate an emergency

1.1.6 Thawing of FV-103. This could be caused by loss of FV
cooling air supply, failure of HCV-919A or HCV-919B in air

lines, or malfunction in the FV control circuits, ECC 6L0O-660.

 

1.2.2 Toss of fuel pump will cause & rod scram if above 15 kw,

take reactor out of run mode and automatic load control.

1.1 Causes of loss of fuel pump
and traced to its source.
drain.
1.2 Alarm and control action
1.2.1 Any of these items will give an alarm.
1.3 Operator Action

 

While determining and correcting the cause of the pump fallure

the operator should proceed as follows:

1.3.1 Turn on Scanner A and scan all points for low temperature.
Keep loop temperature balanced in preparation for restarting
pump. This can be done with loop heaters. Drain fuel sys-

tem if temperatures indicate salt may freeze.
Approved by %fl-\ / 63%-2
T7/26/65

1.3.2 Following coolant system off-gas activity which initiates
an emergency fuel drain, the coolant system should be

drained after fuel is below HX.

2 [0SS OF COOLANT PUMP

 

2.1 Causes of losgss of coolant pump

 

2.2

2.1.1 Low coolant pump level. This could be caused by loss
of bubbler helium flow, bubbler selector switch being off,
by low salt temperature or coolant salt leak, Thawing of
FV-204 and 206 would cause low level and drain system.
This could be initiated by failure of CCP #3 or valves
HCV-906 or HCV-907, or malfunction of control circuits.

2.1.2 Low cooling water flow. This could be caused by nmis-
operation of throttling valve or loss of treated cooling
water, Section 9B-1.

2.1.3 Electrical trouble. This includes accldental pushing
stop button or opening breaker K on Switchgear Bus #3. Any
real electrical trouble should be investigated and repairs
made .

Alarm and Control Action

 

2.3

2.2.1 Any of these items will give an alarm.

2.2.2 Loss of coolant pump will stop the fuel pump, Section
9C-1 and cause a load scram and put load control on manual.

Operator Action
While determining and correcting the difficulty, the operator

should proceed as follows:

2.3.1 BStart and operate Scanners A and B, D, E, F. Adjust
heaters on fuel and coolant system to keep loop temperatures
balanced.

2.3.2 If temperature indicates salt may freeze in any portion
of the system the fuel and or coolant system should be

drained.
L
Approved by izjéiijzézéfiqufl!”k 9D-1

9/29/65

9D LOSS OF INSTRUMENT AIR

The instrument air system consists of an operating Joy Compressor

and a stand-by unit which starts automatically on low supply pressure.

On loss of both instrument alr compressors, the service alr compressor

can be manually put on stream. If it should alsc fail, two banks of

nitrogen cylinders with a capacity of 20 to 30 minutes will supply gas

to critical pneumatic instruments.

1 AIR COMPRESSOR ELECTRICAL DLEFFICULITIES

 

The electrical power for AC No. 1 is from MCC-G3 (TVA or DG3)

and for AC No. 2 is from Bus MCC-Gh (TVA or D64). The control

power is normally Tfrom IPP2 {MGh) but is transferred to MCC-GU

(TVA or DG4) on loss of Mi4. Loss of either primary power or

control power wilil stop the compressors.

1.1

1.2
1.3

1.b

Operator action in case of wvarious power loses is given below:

Init. Date/Time

 

After momentary loss of power, restart the

degired air compressor.

 

If only DGk is operating, start AC No. 2.
If only DG3 is operating, start AC No. 1.

 

MGL must be operating to supply control

power.

 

If MGY ie lost the air compressor will stop
before the control power is transferred to

MCC-G4. Restart either air compressor.

 

2 OTHER AIR COMPRESSOR DIFFICULTIES

 

2.1

2.3

If the operating instrument alr compressor

stops, start the other one.

 

If neither of the instrument air compressors
will operate, start the service air compressor

and valve it in.

 

If the pressure at the compressors decreases
below the setpoint, the compressors cannot

be restarted from the control room. Push
Approved by fif”ffif “€5a:;MWA71 9D-2

- 4 - 9/29/65

Init. Date/Time

   

 

*e

2.3 (continued)
the reset button on the south wall of the

diesel house and then restart.

 

2.4 If all three compressors are out of service
emergency nitzogen will supply critical instru-
ments.

2.4.1 Check that valves are set properly
to supply nitrogen to the emergency air

header.

 

2.4.2 Change cylinders as reguired until
reactor has been drained. .
3 EFFECTS OF LOSS OF INSTRUMENT AIR

Logss of instrument air will initiate a drain

 

 

by closing the air valves which keep FV's 104,
105 and 106 frozen (FV 104 iz deep frozen during
normal operation.). In addition to this,air-
operated valves will go to their fail position,
all air line block valves will close, and the
pneumatic instruments will not function. This
will include weigh cells, cell sump level indi-
cators' pressure controller and some cooling
water flow indicators. The operator should

take the following steps to assure a drain
before salt freezes. .

3.1 Scram the rods.

 

3.2 PHwitch to emergency drain.

3.3 Increase the heat on FV 103, 204 and

 

206 if necessary.
3.4 If FV 103, 204, or 206 do not thaw, turn
off CCP No. 1, No. 2, and No. 3.

 

 
!

2 *
Approved by;<f32?zj o 9E-1
T ~

9/21/65

OE RADIATTION INCREASES

Due to the hazardous nature of radiation, any radiation increases

should be given prompt and careful consideration, and if necessary, action

taken to insure that no harm is incurred by personnel. The following

procedure will attempt to guide the operating personnel in case of high

and/or increasing radiation as indicated on the personnel monitors, pro-

cess radiation monitors, and stack monitors.

PERSONNEL MONITORS

1

 

The handling of radiation ilncreases is described in the Safety

Procedures and Emergency Plans (Part IX of Design and Operations

Report). The general philosophy to be followed is given below.

Init. Date/Time

 

1.1 The person discovering a high and/or increasing

1.3

radiation field should:
1.1.1 Bvacuate personnel from the immediate

area.

 

1.1.2 Take any local action which would

alleviate the hazard.

 

1.1.3 Notify the control room as rapidly as

possible.

 

The control room operator upon receiving noti-
fication of high and/or increasing radiation
should:

1.2.1 Notify the shift supervisor and other

members of the local emergency sguad.

 

1.2.2 Maintain control of the reactor, making
changes in operation as required by the

situation.

 

1.2.3 Take any other action necessary to
insure personnel safety (such as actuating

the evacuation alarm).

 

The shift supervisor should:

1.3.1 Direct the efforts of all operating
 

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9/21/65

Init. Date/Time

 

1.3.1 (continued)
personnel to determine the source of
activity, prevent the spread of con-
tamination and/or reduce the intensity

or ares of the radiation zone.

 

1.3.2 BSet up contamination and radiation
zones immediately. 1f entry is necessary,
a change area should be established with
clear instructions posted describing in
detall what percautions are necessary,
where the contamination zone ends and the

clean area begins.

 

1.3.3 Direct the cleanup operations.

 

2 PROCESS RADIATION DETECTORS
2.1 RM-827 (Treated Water) (2 out of 3 monitors

 

 

causes control action. )

 

A rapid large increase in treated water
activity would probably be caused by a major
component failure in-cell. In case of treated
water activibty increase, the operator should
proceed as follows:

2.1l.1 Evacuate non-coperating personnel from

the water room. Use the P. A. System.

 

2.1.2 Try resetting the instruments. This
would correct the problem if it were
caused by an instrument power surge. 1f
poseible have instrument mechanic check

the instrument.

 

NOTE: Electrometers will not indicate above the alarm
set point. Therefore, to determine the actual radiation
level, change to a less sensitive scale and push the

reset button.

te
Approved by , 9E-3

9/21/65

 

. Init. Date/Time

 

2.1.3 Check other process radiation monitors.
In case of a major in-cell release, RM-565
(cell offgas) should respond. Personnel
monitors (cams and monitrons) may also
show increases. Check the FP level. A

system leak might be seen here.

 

2.1.4 If other radiation monitors show sig-
nificant increases, see the section of
this procedvre which deals with the

. monitor of interest.

 

- 2.1.5 After these preliminary actions are
. taken, refer to Procedure 9B, Step 1.5,
which gives operator action for a radia-

tion block of water to in-cell components.

 

2.2 RM-565 (Cell Air) (1 out of 2 monitors causes

 

control action.)

 

Any large changes in radiation in the cell
could be reflected by small changes in the cell
. offgas activity. (Note that changes in power
should only produce glight changes in cell air
" activity.)
Any fast or large increases of activity
20 mr/hr) in the offgas may be a sign of
serious component failure. The operator should
proceed as follows:
2.2.1 Initiate an emergency drain if the con-

trol circuits have failed to do this.

 

2.2.2 Actuate the evacuation horn to remove

non-cperating personnel from the area.

 

2.2.3 1If possible have an instrument mechanic

. check the instrument.

 

2.2.4 If the instrument is at fault and can

be corrected quickly, try to reset the
Approved byifi(”f ff{iz;}fdfirflxv OE-1

2.3

9/21/65

Init. Date/Time

 

2.2.4 (continued)
alarms and stop the drain. If it is
truly radiation, allow the system to

drain.

 

2.2.5 Make any steps possible to reduce
the leakage such as reducing the pres-
sure on various components or stopping

the fuel pump.

 

2.2.6 Take data which might be used in
determining the location of the leak
such as levels, welghts, effects of
pressure changes, etc.

2.2.( When the system indicates that it

 

has drained, switch the freeze valves
1o freeze. Any action beyond this
point will have to be determined at
the time and will depend upon the
situation,

RM-528 (Coolant System Offgas) (1 out of 2

causes control action.)

 

 

Significant increases in coolant offgas
activity (>20 mr/hr) would probably be
caused by a leak in the primary heat exchanger.
Activity in the coolant offgas should automat-
ically give an emergency drain and stop the
fuel pump.

Upon notification of coolant offgas activ-
ity, the operator should proceed as follows:
2.3.1 Check that an "emergency fuel drain”

has been initiated and the fuel pump

stopped. If not, the operator should

instigate these actions.

 

2.3.2 Drain the coolant system after the

fuel system has drained.

 

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Approved by ALl P
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2.4

2.3.

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N/ 9/21/65

Init. Date/Time

 

3  PFurther action will be determined at
the time of the incident. The next
actions would probably be concerned with
checking the heat exchanger for a leak.
A method which might be used for this
would be to pressurize the coolant sys-
tems and watch for pressure buildup in

the fuel system.

RM-500 (Main Felium Supply) (Alarms Only)

Activity in the line at RM-500 would indi-

cate a fallure in the containment system. This

may

necessitate shutting down the helium sys-

tem which in turn destroys the reliability of

level indication in both the pump bowls and

the

overflow tank. Since the overflow tank

level is considered safety, loss of it requires

a reactor shutdown.

ity
2.4

2.4,

2.4,

In case of high and/or increasing activ-

at RM-500, the operator should:

.1 Make a hasty check to determine if

the indication 1s real. Take a portable
radiation detector and measure the activ-
ity at the line, and have an instrument

mechanic check the instruments.

 

2 Any actual activity in the line would
probably be caused by high pressure in
the system involved or low supply pres-
sure. If possible adjust pressures,
purge out the lines and valve off the

system or component involved.

 

3 If source of activity cannct be
located and isolated, consider taking
the reactor subcritical and stopping

the fuel and coolant pumps.

 
Approved byffféfingézfé“

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<~/ 9/21/65

  

Init. Date/Time

 

2.4k If it is necessary to stop the helium
flow to the FP bubblers, a reliable level
indication in the pump bowls and overflow
tank will be lost. This necessitates
draining both the fuel and coolant systems.

2.4.5 Continue efforts to determine which line
allowed the backflow of activity.

RM-596 (Helium Suovply To FP Bubblers) (1 out

of 2 monitors causes control action.)

Activity in the line at RM-596 indicates

 

a breakdown in containment. High radiation

level at RM-596 automatically closes the

block valves in the bubbler lines. This
destroys the reliability of the fuel salt
level indicators in both the pump bowl and
the overflow tank. The overflow tank level
is considered part of the safety system,

and loss of this necessitates a shutdown.
Upon receiving high radiation indication

on RM-596, the operator should proceed as
follows:

2.5.1 Quickly attempt to determine if the
activity ds real. Using a portable
radiation instrument measure the
activity of the lines next to the
process monitor, and have an instrument
mechanic check the instruments.

z.5.2 1f the activity is real, take the

 

reactor subcritical and stop the fuel
pump. Adjust pressures to prevent
further backup of activity.

2.5.3 Switch the fuel pump bubbler switch

 

to "off" position.

 

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init. Date/Time

 

2.5.4 Close all of the fuel system bubbler

A and B valves..

 

2.5.5 Bince it would be necessary to violate
containment to replace or repair the
check valves in the bubbler lines with
salt in the pump bowl, proceed with a

normal drain of the fuel system.

 

2.5.6 Upon completion of the drain, freeze
the freeze valves.

RM-0T-1 and RM-07-2 (Lube 0il Tanks) (Alarms

 

 

only)

Activity in OT-1 may increase as the
approach to full power is made. This would
probably be due to fissiocn product diffusion
across the pump sealg into the oil stream.
This increase in radiation should be small
unless the pump seals start lesking exces-
sively. In case of high and/or increasing
radiation at either or both of the lube aQil
packages, the operstor should proceed as
follows:

2.6.1 Check with a portable radiation
instrument to verify the indications
received on the monitors.

2.6.2 Check the level of the oil catch
tank which is attached to the system

 

of interest. A seal leaking badly
enough to allow rapid radiation in-
creases in the oill tank may cause an
increase of oil level in the oil
cateh tank.

2.6.3 If the o0il catch-tank level is

 

increasing, refer to PBrocedure GH.

 
 

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2.7

9/21/65

Init. Date/Time

 

2.6.4 Check that the main helium flow to the
pump in question (line 512 or 516) is set
at the value given in the building log.

The bulk of the gas flowing through these
lines flows down the vump shafts and should
help prevent fission product gasses from
reaching the oll seals.

2.6.5 If it is verified that the radiation

 

indicated 1s real and reading above limits
at the tank, take the reactor subcritical
and stop the salt pump.

2.6.6 If RM-557 increases close valves in

 

the offgas lines from the oil system to

prevent automatic closing of RCV-557.

 

2.6.7 If there is an abnormal increase in
the OCT level, proceed as described in
OH. Consideration should be given to
reducing the shield oil flow rate to
minimize suction from the shield oil
ocutlet jet.

2.6.8 If there is no abnormal oil leakage
as indicated by OCT level, continue oil
flow to the pump bearings.

2.6.9 To prevent over heating of the fuel
pump, keep an oil flow to the shield
plug until the reactor is drained or
until the amount of activity in the
cil system endangers personnel.

RM-557 (Main Offgas To Stack Filters)

The three most likely methods by which
activity might reach RM-557 are; a break-
through in the charcoal beds, a fuel pump

seal failure, or a heat exchanger fallure

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Approved by -

 

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. Init. Date/Time

 

allowing fuel salt to get into the coolant
salt system.

If high and/or increasing radiation is
noted on RIA-557A or RIA-557B, the operator
should proceed ags follows:

2.7.1 Check with a portable radiation instru-
ment to determine if the activity indica-
tion is real. Have an instrument mechanic

check the instruments.

 

. a.7.2 If the activity increases above limits,
check that the control circuits close
. HCV-557, PCV-513-Az, and PCV-510-A2. If
the control circuits fail, close these
manually.
2.7.3 Check RM-528A and B. If these are
reading high, consult Section 9E 2.3

 

of this procedure.
2.7.4 Check RM-Q0T-1 and RM-0T-2. If these
. are reading high, consult Section 9E

2.6 of this procedure.

 

c.7.5 Try to determine the source of the
activity. Use a portable radiation
‘ indicator and check the following
lines individually.
562 - from auxillary charcoal bed
557 - from main charcoal beds
560 - from oil system and coolant

system.

 

2.7.6 Close the hand valve in the line which
shows activity. Then try to reset RM-55T7A
. and B. If these will reset, operations
using the other lines may continue. How-

ever, 1if the activity is from the coolant
 

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9/21/65

Init. Date/Time

 

2.7.6 (continued)
system or the main charcoal beds, opera-
tion will continue only long enough to
shut down.

2.7.7 If the activity is from the main char-
coal beds and/or if HCV-557 will not re-
open, take the reactor suberitical and -
consider stopping the fuel pump. IT
necessary stop the helium flow to the
pump. The bubblers may remain in opera-
tion until pressure starts building up
in the charcoal beds.

2.7.8 If repairs are needed or an excessive
amount of time is involved before the
situation can be corrected, it may be
desirable to drain the system.

3 HIGH STACK ACTIVITY

It is conceivable that highly radioactive contaminants could

 

be expelled to the stack, then on to the atmosphere. This is a
particularly hazardous situation because the entire surrounding
area could be involved.
Instrumentation is provided on the offgas stack for detecting
beta, gamma, and alpha activity. A charcoal trap is also provided .
to aid in the detection of iodine. These detectors are all of the
type which collect contaminants on filter paper or in the charcoal; .
therefore, they may continually show a slight increase in activity.
1t is fast and/or large increases in the detector readings which
should warn the operator of trouble.
The stack monitors are set to alarm upon receiving an increase
of 20% on the beta-gamma detector, 30% on the alpha detector, and
80% on the iodine detector. These are percentages of full scale
with full scale normally being 250 count/min. The scale may be

changed to meet the operating conditions; however, when the scale
il e

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needs to be changed, notify the stack monitoring group btefore making
the switch except in emergency cases. Under unusual conditions the
Laboratory Facilities Department may request MSRE personnel to
change ranges. If the shift supervisor agrees, these requests
should be complied with.

The percentages of increase listed previously must be within
a 15 minute period before the Laboratory Facilities Department will
notify the operator of abnormal release. 1If this increase persists
for another 30 minutes, the laboratory shift supervisor will be
notified, and he may reduest a reactor shutdown. His requests
must be followed to insure the safety cf the entire ORNL Area.

The tapes of these detectors are advanced every 8 hours.

The percentage of increase listed previously (20% for Beta-gamma,
30% for alpha, 80% for iodine) within this time period will cause
the respective module to go into alaxm condition. Even though a
slow increase over an 8-hour period would not be considered hazard-
ous, each stack activity alarm must be investigated promptly.

It seems logical to expect that stack increases will be either
very rapid or very slow. The following steps are to aid the oper-
ator for these cases. Any intermediate increases should be
handled in such a way as to insure personnel saflety. The shift
supervisor should assess the situation and made decisions concern-
ing operations with tThis in mind.

Init. Date/Time

 

3.1 High Stack Activity Check List

Upon receiving a stack activity alarm
or notification of high stack activity, the
operator should check the chart of the instru-
ment giving the high activity indication.
Verify the reading by contacting the stack
monitoring group. Phone No. 3-623L4. If the
activity is increasing rapidly (greater than
alarm set point in 15 minutes) with no signs
of leveling off, assume that hazardous quan-

tities of activity are being released, and
Approved p¥4§2é; /fiéévfiiygzqflm\ OE-1Z2

9/21/65

Init. Date/Time

 

proceed as follows:

3.1.1 Take the reactor subecritical.

 

3.1.2 Report the incident to the Emergency
Control Center (Phone No. 3-6358).
3.1.3 Ask the Hmergency Control Center to

send Health Physics Surveyors if sur-

 

veyors are not already on hand.

 

3.1.4 Announce the emergency over the P. A.
and request all personnel (except those
involved in combating the emergency) to
assemble at the northwest corner of the
7503 bullding basement (84O-ft level),
if this action appears necessary.

3.1.5 Dispatch two Emergency Squad Members
equipped with assault masks and portable
radiation meters to check outside the
building and assess the nature and extent
of the hazard. Further action depends
upon the assessment of the hazard.

3.1.6 1In case the activity is increasing
slowly (greater than the set point in
Ik hours), the operator should proceed
as folliows:
3.1.6.1 Ask the stack monitoring group

to advance the tape. This should
reduce the chart to background.
3.1.6.2 Keep a careful watch on the

instrument for further increases.

 

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Approved by bty mon oF-1
8/11/65

9F CONTROL ROD DRIVE DIFFICULTY

Due to the dependence placed on control rod reliability, any anoma-

lous control rod behavior must be considered very serious in nature. If

any irregularity in ccntrol rod behavior is noted, the reactor should be

taken subcritical by inserting all rods and the cause of the malfunction

should be corrected if possible. If repairs can not be made a reactor

drain may be necessary.

ouggested corrective actions to be taken under varlous circumstances

are gilven below:

Tnit. Date/Time

 

1 INABILITY TO WITHDRAW ROD(s)

1.1

1.2

1.3

1.k

If a control rod will not withdraw, check
the jumper board. If control action is
inhibiting the withdrawal, change the opera-

ting conditions to satisfy the interlocks.

 

If control action is not preventing the rods
from withdrawing, insert all rods to their

lower limit. If necessary, scram the rods.

 

If any rod fails to insert to lower limit,

consider draining the fuel system.

 

If all rods drop to lower limit, determine
the cause of the difficulty and take neces-

sary action to correct it.

 

2 INABILITY TO INSERT ROD(s)

2.1

2.2

If a control rod does not insert upon re-
quest, when not already on lower limit,
scram the rods. Failure of a control rod to

insert is a potentially dangerous situation.

 

After scramming the rods check that all rods
dropped to the lower limit. If all did not,

consider draining the fuel system.

 
Approved byfii/_‘%g W —"

2.3

If all rods drop to lower limit, determine
the cause of the difficulty and take necessary

action to correct it.

Tnit.

OF-2
8/11/65

Date/Time

 

3 SERVO DIFFICULTY

 

3.1

3.2

CAUTION:

If the servo were to start oscillating
excessively, fail to withdraw or insert, or
in any other manner become erratic or un-
reliable in behavior, the operator should

switeh to manual control.

 

Determine the cause of the difficulty and

correct it.

 

Erratic servo behavior could possibly be

caused by some anomalous nuclear behavior so the

operator should be especlally watchful for

excursions, etc.
L UNCONTROLLED ROD ACTION

b1

2

4.3

Control rod withdrawal or insertion due to
an unknown reason may indicate trouble in the

circuitry. Insert the rods immediately.

 

Correct the trouble if possible and test
the rods one at a time to regain confidence

in them.

 

Consider draining the reactor if unable

to correct the difficulty.

 
Approved by ;¢¢5§Z€;L4§?ié§;/yu¢;mq G-1

9/20/65
9G LOSS OF COMPUTER

One normally-operating component which is operated in conjunction
with the reactor is the "on-line" computer, a Bunker-Ramo 340. When in
operation, the computer will log system data, scan selected variables
to see that they remain within limite, and perform routine calculations
such as heat balances. It is estimated that the computer will be "on
line"” about 99% of the time. During the time when the computer is not
in operation, part of its duties must be performed manually. There are
two hours of maintenance scheduled for the computer every two weeks.
This is not considered abnormal, and with the exception of belng espe-
cially alert for abnormalities, the operator will not normally have any

added duties at this time.

Init. Date/Time

 

1 CHECK LIST WHEN COMPUTER IS ABNORMALLY SHUT DOWN

 

It is especially important to make log entries
as thorough and exact as possible since some infor-
mation normally on the logger will not be avallable.
1.1 Start taking the abnormal control-room log

(12A-2B).

 

1.2 Start using the addendum %o the check lists
12B 1.1 (shift supervisor's check list) as
well as the regular check lists. This
addendum includes such things as calculating

heat balances and reactivity balances.

 

1.3 If the anticipated shutdown of the computer
is to be longer than 2 days, transfer the
following thermocouples to the special
recorders so they may be watched closely.
Finish filling out the following table.
For short periods when the computer is
shut down, these will be recorded periodically
on the building log. These will be read out
by momentarily plugging each into T 1.3200

or a portable veadout instrument.

 
 
 
 
 
  
  
   
  
  
 

TE JACK PANEL - NORMAL READOUT SPECIAL READOUT DATE
NUMBER NUMBER INSTRUMENT P. P. NUMBER RECORDER POINT INITIAL AND TIME

£q poroxddy

 

8461 8
8511 8
07-1A 8
57-14

R-2

R-26A

R-27A

R-28A
'R-29A
R-304
.
R-4
R-50
=51

826-1 88 6 ,
831-1 a R
833-1 88 A
'837-1 8 TSQ
8h1-1 891 <V
§81+ -1 892 T

 

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9/20/65
OH LUBE OIL SYSTEM DIFFICULTIES

Due to the importance of the lube oil supply to the pumps, consider-
able redundancy has been bullt into the system. BSuggested corrective
action for some of the difficulties which could be encountered are given
below:

1 COOLANT SALT PUMP LUBE SYSTEM FATLURE

The operator should connect the fuel pump, lube oil system to

 

the coolant salt pump as follows:
Init. Date/Time

 

(Service Tunnel)

 

 

1.1 Record LI-CTl-Az_  LI-OTz-AZ . o
1.2 Lower set points on LI-OT1-A3 ~ 20%. L
1.3 Close V-753A (downstream of filter). ___”_
1.4 Open breather intercommection V-601. L
1.5 Close breather valve V-501. L
1.6 Cloge oil return V-756.
1.7 Open return interconnection V-T71lzA. -
1.8 Open supply interconnection V-762A. L
1.9 Adjust flows per walking log.

FlL 703

F1 70k

F1 753 __

F1 75k o
1.10 Record LI-OT1-Az  LI-0Tz-Az2

1.11 Adjust level setpoints per walking log.
LI-0TL-A3 red (alarm)
purple (operates valve)
LI-0T2-A3 red (alarm)
purple (operates valve)

 

1.12 Check oil levels frequently for leakage from
one system to the other. Check oil and
cooling water temperatures to maintain oil

supply temperature'<lSOoF.
~e

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Approved by 5 %’7""9’),-umfi e
, 9/20/65

2 FURL SALT PUMP LUBE SYSTEM FAILURE

The operator should connect the coolant lube oil system to the

e

fuel salt pump as follows:
Init. Date/Time

 

(Service Tunnel)

 

 

 

 

 

 

 

 

2.1 Record LI-OIl-A2 _ LI-OT2-A2
2.2 Lower setpoints on LI-0T2-A3 ~ 20%.
2.3 Close V-703A (downstream of filter). .
2.4 Open breather inter-connection V-601.
c.5 Close breather valve V-590. :
2.6 Close oil return valve V-706. .
.7 Open return inter-connection V-T12A.
2.8 Open supply inter-connection V-762A.
2.9 Adjust flows per walking log. ’
F1-703
FI-TO4
FI-753 ____
o FI-TSh -
2.10 Record LI-OT1-AZ  LI-0T2-A2

2.1l Adjust level setpoints per walking log..
LI-OT1-A3 red (alarm)
purple (operates valve)
LI-0T2-A3 red (alarm)
purple (operates valve) .
2.1z Check oil levels frequently for leakage from
one system to the other. Check oil and cooling .
water temperatures to maintain oil supply tem-
perature <1500F.
3 TOTAL OIL SYSTEM FAILURE

In event of loss of all lube and coolant oil

 

 

flow at both oil packages, initiate emergency drain
of fuel and coolant salts. Turn off heaters CP-1,
CpP-z, FP-1, IP-2 immediately after salt drains from
Pump bowls.
.

 

Approved gygééfia?( ' #25

9H-3
9/20/65
Init. Date/Time

 

. L EXCESS OIL SEAL LEAKAGE
k.l DNormal oil seal leakage is O to 4O cc/day;

 

however, a larger seal leakage can be toler=
ated. If the oil leakage across the seal
exceeds 100 cc/day, notify the operations
chief and prepare for a normal reactor shut-
down per Procedure 10A.

4.2 Should a gross leak develop (31000 cc/hr),
drain reactor per Procedure 10B (special
shutdown).

’ NOTE: Assuming that the syphon pot is full and the lower
section of the OCT is 1/2 full, a leak rate of 1000 ce/hr
allows ~ 2 shifts for fuel drain refill with flush salt
and drain before OCT's is full.

 

In addition, the operator should do the following:
4.2.1 Reduce pressure differential between
oil supply tank and salt system to zero
psi.
4.2.2 Reduce bearing oil flow (FI-703, 753)
. toc ~ 1 gpm.
4.2.3 Turn off fuel or coolant pump heaters
. when pump bowl is empty.
h.2.4 Turn off oil flow to pump bearings
when thermocouples at bottom and side
of pump bowl drop below 400°F or when
OCT indicates full, whichever occurs

first.
gy

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Approved by M%fifiy oL-1
| 9-2-65

9T SALT IN OVERFLOW TANK

Fuel salt can enter the OFT by overfilling the pump bowl, by splash-
ing during pump operation and by a volume expansion due L0 a temperature
excursion. Whenever the 10% level alarm point of the OFT or the FP low
level alarm point is reached, the salt must be emptied from the OFT.

If the reactor is at power, it must first be reduced to zero by the
procedure in Section 10A of the Operating Procedures. The OFT off-gas
line will then be closed and the bubbler gas will build up pressure and
force the salt to the pump bowl. If the FP stops when the gas pressure
in the OFT is releaged . through the overflow line into the pump bowl,
the pump should be restarted.

Init. Date/Time

 

1 DETAILED PROCEDURE FOR EMPTYING THE OFT
1.1 Reduce the reactor power level to zero by .
Procedure 10A. Do not stop the FP. Fully

ingsert all three control rods. After-heat

 

generation will continue to heat the fuel
salt; therefore, the reactor outlet temper-
ature must be observed and the coolant system
operated in such a manner as to prevent
overheating. Raising the outlet radiator
door should be sufficient to remove this
heat. If not, raise the inlet door as
required after the outlet door is full open.
Observe the reactor and radiator outlet
temperatures repeatedly and make the neces-
sary changes in operating conditions to
prevent overheating or overcooling either

system.

 

1.2 Transmitter Room Record
LI-593 LI-599
LI-596 LI-600

 
Approved byzéfi?éékjgz;wemn
7

1.3

1.kb

1.5

1.6

1.8

T

Control Room Record
LR-593 Switch 36 Position 2
LR-593 Switch 36 Position 3
Ingtall the jumper tube in air line to
HCV-523 and close HCV-523.
When the pressure builds up sufficiently
to force gas into the FP bowl, the FP will
probably stop. Restart it.
Repeat Step 1.5
Transmitter Room
1.7.1 Open HCV-523, remove the jumper
tube and cap the open ends of the air
line.
1.7.2 Record LI-599 _ LI-600
LI-593 ___  LI-59% ____
Control Room Record
LR-593 Switch 36 Position 2
LR-593 Switch 36 Position 3

91-2

9-2-65

Init.

Date/Time .

 

 

 
¥

CE e -

N
Approved bmfifzzz?ffé;éfiétl ) Eiél
9/14/65

9J LOSS OF He PURGE TO THE CIRCULATING PUMPS

Loss of He purge to the circulating pumps could result from low

supply pressure which closes the supply valves, radiocactivity in the FP

bubbler lines which closes the block valves, or failure of the valves or

valve operators.

1

L0SS OF FIOW THROUGH LINE 516

 

The most critical situation occurs when fleow through line 516,
the FP purge line, stops during power operation. Radioactive gas
could migrate up the annulus around the shaft to the bearing lube
oil and salt mist could migrate up the annuius and freeze. This
could clog the annulus and seize the pump rotary element. The pump
should not be operated longer than 1/2 hour or after the radioac-
tivity level in the lube oil exceeds 20 mr/hr., the low level alarm
point. If the reactor is at power, 1t should be taken to the zero
power level by the normal shutdown procedure section 10A, before
stopping the pump. The system temperatures must be observed
carefully after stopping the pump and the system drained if it appears
they will exceed 130C°F. Drain the fuel system only and do not
flush at this time.

[0SS OF FIOW TO THE OVERFIOW TANK BUBBLERS

A loss of flow to the overflow tank bubblers will be annunciated
in the control room. Unless flow can be reestablished the fuel
system should be drained.
1OSS OF FIOW TO THE FP BUBBLERS

If flow is lost to one of the FP bubblers, the cother bubbler can
be selected and normal operation can continue. However, if both
bubblers are inoperative the system must be shut down and drained.
Drain fuel system only and do not flush,

LO5S OF FIOW THROUGH LINE 512

If flow stops in line 512 and can not be reestablished, the

coolant pump should be stopped within 1/2 hour. The power should be
Approved b@«l ) %; %2
9/14/05

reduced to zero. If the system temperatures exceed 1300°F, drain the
fuel system but do not flush.
5 I0SS OF FIOW TO THE COOIANT PUMP BUBBLERS
If flow is lost to both bubblers, operation can continue by
selecting the float level element. If no level indicator is
operable on the ccoolant pump, the power should be reduced until a

level element is in operation.

*y
Approved bxzé?ffi%fig?;ééamfl\m 8/ 95"1
10/65

9K 1085 OF COMPONENT COOLING BLOWERS

1 10SS OF EITHER CCP-1 or CCP-2
The loss of the operating CCP will be indicated by low AP on PAT 960

 

and/or low CCP oil pressure. These are annunciated on MB-2.

On loss of one CCP, the alternate blower should be started. The
stop button of the malfunctioning blower may have to be pushed before
starting the stand-by unit.

A delay in starting the stand-by unit will contribute to the Tollow-
ing actions:

1. Thermocycle of fuel pump bowl.

2. Damage to control rod drive motors.

3. Thawing FV-103 and draining the fuel system.

T Loss of cooling to reactor neck and control rods.

After starting the stand-by blower, the Chief of Operations should be
notified. Continued operation without an alternate blower will be an
administrative decision.

2 1IO0SS OF CCP-1 and CCP-2

Loss of both blowers will initiate a drain when FV-103 thaws,

Since loss of cooling air can damage the control rod motors and
pump bowl an effort should be made to get at least one of the blowers
back in service as soon as possible.

3 10SS OF CCP #3
Loss of this blower will cause thawing of FV-204 and FV-206 which

 

will drain the cooclant system and terminate operatlons. Service air from
AC-3 ( or Instrument Air Compressors) should be valved into line 906 at
V-06TA. PCV-967 should be set at 8 pesig to maintain normal air flow to

the freeze valves.
o
Approved bxkiéfgigzgé%;zazezL_ /9?él
9/9/65

OL REMOVAL OF WATER FROM THE STEAM DOMES

If water from the FWI's ig inadvertently dumped into the steam
domes it could cause the fuel salt to freeze. The presence of the water
will be indicated by the steam dome level indicators on the main instru-
ment panels, by the FWT level indicators in the water room and a decrease
in temperature in the drain tanks. The operator should remove the water
from the steam domes and refill the feed water tanks in the following
manner; a radiation survey meter should be used to monitor the operation.
1 DETATLED PROCEDURE FOR REMOVING WATER FROM STEAM DOMES

Init. Date/Time

 

 

1.l Determine which steam dome the water ig in.

Steam Drum No.

 

(NESA)
1.2 Check V-806-3 closed and open V-806-2 if the
water is in Steam Dome No. 1 (FD-1) or V-807-2
if it i1s in Steam Dome No. 2 (FD-2).

1.3 Start the steam dome water removal pump,

 

and pump the water to the drum.

 

1.4 Monitor the drum into which the water is
being pumped with the radiation survey

meter.

 

1.5 When the steam dome is empty stop the pump.
1.6 Close or check closed V-806-2 and 807-2.
1.7 1If the water shows no activity, open V-806-3

 

 

and drain the tank, and then close this

valve.

 

1.8 If there is radiocactivity in the water,
take a sample and dispose of it as directed

by the Operations Chief.

 

1.9 Determine and correct the trouble.
1.10 Refill the FWT's by Section LC-5.

 

 
Approved by'ggzi%zé$4@¢44flq_ -1
T/26/65

oM REGENERATION OF HELIUM DRYER

When the water concentration in the helium cover gas from the puri-~
fication system exceeds 1 ppm the molecular sieve (helium dryer) must be
regenerated. The regeneration consists of putting the stand-by purifi-
cation system in service, then heating and back-purging the dryer which
needs regeneration,

Detalls of the regeneration procedure are as follows:

NOTE: The procedure is written for regeneration of #1 dryer. To regene-
rate #2 dryer, use the number in parenthesis.

Init. Date/Time

 

1. Prepare the No. 1 (No. 2) Dryer, Pre-Heater and Oa.
Remover for operation by the procedure given in
Section 5B.

 

2. Open V-503A and V-503C (V-500B and V-500D).

 

3. Close V-500B and V-500D (V-503A and V-503C).

 

L.  Connect a helium supply cylinder to line 500 (503)
at V-500C ( V-503B) with a pressure regulator
and gauge having a range of O to 100 psi. Purge
the line thoroughly as the connection is being

made. Check for leaks with leak detector solution.

 

5.  Open V-505 (V-504) and bleed pressure off system by
setting needle valve on FI-505 wide open then
close V-505 (V-50L4).

 

5. Open V-500C (V-503B) and set the regulator on the
helium ecylinder at 5-10 psig.

 

7. Set the temperature controller on Dryer, TIC DR-1
(TIC DR-2).

 

8. Open V-505 {V-50L4) adjust purge of approximately
1.0 £/min as indicated by FI-505 (full scale)
using FI-505 needle valve.

 

9. Check the dryer and preheater temperatures at 30-
minute intervals and continue the purge for at
least 2 hours after the dryer reaches 500 degrees F.

Record time temperature reached 500 degrees F.

 
Approved bYfi%w« / gb/aéz
7/26/65

Init. Date/Time
10. When 2 hour purge is finished, close V-505 (V-50k4).

 

 

11. Turn off heater to dryer.

 

12. Close V-500C (V-503B) and slowly open V-500B
(V-5034) to bring pressure up to 250 psig.

 

CAUTION: Do not place regenerated bed on stream until TICA DR-1 (DR-2)

returns to room temperature.
  

 

Approved by i /)/ %f/fi?/mfi4 ON-1

9/8/65
ON HIGH CELL LEAK RATE INDICATION

A high RC leak rate indication could result from a high leak rate,

an increase in cell ambient temperature or water leaking into the cell

and vaporizing. A rise in the RC pressure will be indicated by an

alarm and pressure indication in the main control room.

tive
tive
1

The cell evacuation rate should be increased to maintain a nega-
pressure and the cause of the difficulty investigated and correc-
action taken as given below:

SALT LEAKING INTO THE CELL

 

This would be indicated by high cell air activity or a loss
of fuel salt level (FV-103 still frozen) or a loss of coolant salt
level (FV-20L4 and 206 still frozen). The operator should drain
the fuel and/or coolant systems immediately. ©See Section 10B
of the MSRE Operating Procedures.

WATER LEAKING INTO THE CELL

 

This would be indicated by the reactor or drain tank sump
bubbler and/or sump level probes. There would also be a decrease
in level in the condensate tank in use or in the treated water
surge tank. The operator should valve off the leasking line and
proceed accordingly.

2.1 If a cell space cooler water line is leaking, proceed as de-
scribed in 9N-3.

2.2 1If the water line to the fuel pump motor is leaking, the
motor may overheat. Monitor the thermoccouple on the motor
TE-FPM-1 and drain the fuel system to prevent the tempersture
from exceeding l5OOF. If 1t is necessary to shut off the
motor, it can probably be restarted after draining the pump
to aid in afterheat removal. The power required to circulate
helium is a small fraction of that required to circulate salt;
therefore, the motor should not require as much cooling.

2.3 If the leak is in the water lines to the thermal shield, the

reactor should be drained and the fuel system cooled .
Approved by mm IN-2
v

9/8/65

3 LOSS OF REACTOR OR DRAIN TANK SPACE COOQLERS
This would be indicated by a loss of cooling water flow, lights

at the motor starter for the space coolers or high cell temperatures.
The operator should monitor the cell temperatures while trying to
correct the trouble. If the average cell temperature reaches ZOOOF,
the reactor should be drained and as many heaters shut off as pos-
sible. If it 1s necessary to keep the RC pressure below atmospheric
while correcting the trouble, evacuate through line 565 by opening
V-565-C in the VH. When the cell cooler is restarted, observe the
cell pressure carefully. To avoid depressurizing the cell below
-3 psig,connect a N5 cylinder to line 332 in the water room and
add Ny to the cell through it, or if necessary, add compressed air
through line 332.

L ACTUAL HIGH CELL LEAK RATE

This would be indicated by the cell pressure increasing and

 

the inability to find any reason for this such ag given above.
The operator should take the reactor subcritical by the procedure
of Section 10A and start evacuating through line 565 to maintain
a -2 psig in the RC. He should attempt to locate the source of
Tthe leak and repair it if possible without draining the system.
Otherwise, he should continue with the shutdown as given in

Section 10A.
Approved by - I 7/26/65

SECTION 10
REACTOR SHUTDOWN

Periodical normal shutdowns are planned for the reactor to sample
the graphite, make equipment modifications and change fuel salt composition.
The shutdowns may be necessary due to equipment failures or abnormal
conditions. Shutdown, as described in this section, consists of storing
the molten fuel salt in the drain tanks and freezing the freeze valves

to isolate it from the fuel system.

TX 3573
(7-6L)
1y
Approved by gf?%g%eyww\ 10A-1

8-12-65
10A NORMAL SHUTDOWN

Normal shutdown as described in this section consists of lowering

the reactor power from 10 Mw, draining the salt to the drain tanks,

flushing the fuel system with flush salt, and cooling the fuel and cool-

ant systems to ambient temperature. Salt in the drain tanks will nor-

mally be kept molten. Freeze valves will be frozen to isolate each tank

from the rest of the system. If it is necessary to quickly drain the

reactor without removing the afterheat, follow procedure given in 10B.

1

POWER REDUCTION AND GOING SUBCRITICAL

 

The power removal rate will be lowered by lowering the air flow
through the radiator. The nuclear power will be reduced to main-
tain a constant reactor outlet temperature. The manipulations nec-
essary depend on the mode of operation. Two possible modes are de-
scribed below.

1.1 ILoad Control Automatic and Control Rods on Servo Control

 

Under these conditions the power removal rate is reduced by
switching the load control switch to decrease. The servo con-
troller will manipulate the rods to maintain a constant outlet
temperature. The radiator doors will not go below the inter-
mediate limit (corresponding to approximately 1 Mw). Manual
load control and rod manipulaticn will be necessary below this

level. BSteps involved are listed below:

Initg. Date/Time

 

1.1.1 Switch load demand (S24) to decrease
load and hold. Note that the AP set point
will lower causing the bypass dampers to
open until fully opened. The AP set point
will stop changing and the automatic blower
will stop. This will cause the AP to de-
crease below the set point. The dampers
will start closing and the AP set point
start decreasing. When AP and AP set
point are equal, the AP set point will
 

Approved by ’Z/‘g%ym 5 igfigg

Init. Date/Time

 

1.1.1 (continued)
continue to decrease which will cause
the dampers to reopen. When they are
fully open again, the inlet and outlet
doors will start lowering. When they
reach the intermediate position, they
will stop. During this time, check
that the servo control manipulates
the rods to maintain a constant reactor
outlet temperature. Manually adjust

the shim rods as necessary.

Sy

 

1.1.2 Switch the load control mode selector
switch (823) to manual.

 

1.1.3 Push the "run off" button (8-12) which
will put the reactor in the "start" mode.
This will switch the rod servo to flux
servo and will control the flux at 1 Mw
or at the flux demand if both pico
ammeter range switches are in the 1.5

Mw range.

 

1.1.4 Check that both pico ammeter range
switches are in 1.5 Mw range and adjust
flux demand to hold the outlet tempera-

ture constant.

 

1.1.5 Manually turn off the operating radi-

ator blower.

 

1.1.6 Fully insert all three control rods
and manually adjust the outlet and/or
inlet doors to maintain the fuel and
coolant systems at approximately 12259F.
1f temperature decreases 1t may be nec-
essary to increase the input to the elec-

trical heaters.

 
Approved by ‘,/’gfi“

1.2

  

10A-3
8-12-65

Init. Date/Time

 

L.l.7 Continue salt circulation for 5
hours to take care of the afterheat
and avoid overheating the graphite.

1.1.8 Take a fuel sample.

 

 

Load Control Manual and Control Rod Servo Off.

 

Under these conditions the power removal rate

can be decreased by various sequences of

operation of the dampers, doors, or blowers.

Steps for the preferred sequence are given

below.

l.2.1 Manually open the bypass damper and
manipulate control rods to maintain the
reactor outlet temperature approximately

constant.

 

NOTE: Keep the two shim rods approximately equal and

the regulating rod at least 6" lower.

1.2.2 Stop one of the main radiator blowers
and manipulate the control rods to main-
tain the reactor outlet temperature

approximately :constant.

 

1.2.3 Manually lower both radiator doors
to the intermediate position and manip-
ulate control rods to maintain the
reactor outlet temperature approximately
constant.

1.2.4 Push the "run off" button (S-12)

which will put the reactor in the "start"

 

mode.

 

1.2.5 Manually turn off the other main radi-

ator blower.

 

1.2.6 Fully insert all three control rods
and manually adjust the outlet and/or

inlet doors to maintain the fuel and
 

Approved by fi%/ nig v

1.2.6 (continued)
coolant systems at approximately 12250F.
1f temperature decreases 1t may be nec-
essary to increase the input to the elec-
trical heaters.

1.2.7 Continue salt circulation for 5 hours
to take care of the afterheat and avoid
overheating the graphite.

1.2.8 Take g fuel sample.

2 DRAINING AND FIUSHING FUEL SYSTEM
The fuel will be drained to the selected drain
tank, and the fuel system will be flushed with
flush salt. No flush is provided for the coolant

 

system. Details of the procedure are given below:

2.1 Take a complete inventory (check list

Init.

10A-k
8-12-65

Date/Time

 

 

 

 

 

 

12B-5).

2.2 Check that FV-105 or 106 to selected drain
tank is thawed. FV-105 _ or FV-106 .

2.3 Deep freeze FV-106 or 105 to other drain tank.
FV-106 or FV-105

2.4 Check that all other FV's are deep frozen.
FV-10L _  FV-107 , FV-108

FV-109 , FV-110 , FV-111 y

FV-112
2.5 Check that HCV-544 , HCV-5L45 ,
and HCV-546 are open.

2.6 Thaw FV-103 by switching drain switch to
"drain" and allow the salt to flow to the
selected drain tank.

2.7 Check that the fuel pump stops on low
level. (The coolant pump should continue

to operate. )

 

 

 

 

 

 

*e
Approved by =7

2.8

2,10

2,11

2.12
2.13
2.1k

2.15

2.16

2.17

2.18

2.19
2.20

2.21

=

 
 

10A-5
8-12-65

Init. Date/Time

 

When the FP stops, close HCV-903 (set
HIC-903 to maximum) to shut off the air
to the FP shroud.

 

Continuously scan the fuel system for cold
spots or hot spots from fisslon products.

When the bulk of the salt has drained

 

(approximately 40 minutes), switch FV-103
to thaw and the drain switch to "off."

Jumper the prefill mode in ECC-1L7 and

 

run the Fuel Pump for a few minutes to
shake off the salt. Permission To insert

Jumper

 

 

Shut Fuel Pump off and remove jumper.

 

Raise the control rods to the fill position.
Close HCV-ShL or 545. (Equalizer on Tank

 

containing fuel). Specify
Open HCV-573 or 575. (Vent on Tank com- -
taining fuel). Specify

 

 

Continue purging through FCV-516 and the
bubblers until all of the salt has blown
down to the drain tank.

Clogse FCV-516 and the bubblers and allow

 

pressures to come to equilibrium.

Close HCV-573 or 575 and pressurize FD-1

 

or FD-2 (tank containing fuel) approximately
1/2 psi higher than at equilibrium.
Deep freeze FV-105 and FV-106.

 

 

When valves indicate frozen,-reactor will
drop out of operate mode and CP will stop.
Push prefill mode button and start coolant

punp .
Set up flows through FCV-516 and bubblers

 

to increase FP pressure to 2 psig and open
 

8-12-65

Approved,h%fgfiji%/ w1 104-6

NOTE:

NOTE:

Init. Date/Time

 

2.21 (continued)
HCV-573 or 575 to reduce drain tank pressure

to test Preeze Valves.

 

2.22 Close HCV-573 or 575 and open HCV-SLh or 545.

 

2.23 Take a complete inventory (check list 12B-5).

 

LT drain tank afterheat removal system is in
service, the water in the steam domes will be .
included in the drain tank weight.

2.24 Adjust the drain tank heaters to maintain
the temperature at 1200 £ 1009F. If tem-
peratures continue to rise, it will be
necessaxry to put the drain tank cooling
system into operation. This will occur
auvtomatically when the drain tank tem-
perature (FD-1-19B or 20B or FD-2-19B or
20B) exceeds 1300°F. Check that sufficient
water 1s available and cooling water to
heat exchanger is at value given in building

log.

 

z2.25 1f the inventory is satisfactory, fill the
fuel system with flush salt as outlined in
Section H5I-~-2.

 

2.26 Sample the flush salt after 1 to 2 hrs of

circulation.

 

2.27 Check that the equalizing valves (HCV-5hk,
545, and 546) are open, FFT pressure and
pump bowl pressure are approximately equal
and FV-104 is thawed. (FV-105 through FV-112

should be deep frozen.)

 

2.28 Thaw FV-103 by switching "drain" switch to
drain and allow the salt to flow to the FFT.

 

The coolant system can also be drained at this

time. (See section 3 below.)
Approved by M 10A-T7

N DN N NN

.29

.30

.31

.32

.33

.3k

.35
.36

.37

.38

-39

4o

L4l
L2

43

vV 8-12-65

Init. Date/Time

 

Check that the fuel pump stops on low level.

(The coolant pump should comtinue to operate. )

 

When the IFP stops set HIC-903 to maximum 1o
shut off the air to the FP shroud.
Continuously scan the fuel system for cold

spots or hot spots from fission products.

 

When the bulk of the salt has drained
(approximately 40 min.), switch FV-103 to

thaw and the drain switech to "off."

 

Jumper the prefill mode in ECC-147 and,
run the fuel pump for a few minutes to
shake off the salt. Permission to insert

Jumper

 

 

shut fuel pump off and remove jumper.

 

Raise the rods to the fill position.
Close HCV-5h46.
Open HCV-577.

 

 

 

Continue purging through FCV-516 and the
bubblers until all of the salt has been

blown down to the drain tank.

Close FCV-516 and the bubblers and allow

 

pressure to come to equilibrium.

 

Close HCV-5T77 and pressurize FFT approx-
imately 1/2 psi higher than at equilibrium.
Deep freeze FV-104.

When valves indicate frozen, reactor will

 

 

drop out of operate mode and coolant pump
will stop. Push prefill mode button and
start coolant pump if coolant drain is not
in progress.

Set up flows through FCV-516 and bubblers

 

to increase FP pressure and open HCV-577 to

reduce fuel flush tank pressure to test
Approved bxyéfigfiag/%?%%fihifa_ 10A-8

2.43

2.4h
2.45

2.46

8-12-65

Init. Date/Time

 

(continued)

freeze valves.

 

Close HCV-577 and open HCV-54L6.

 

Teke a complete inventory (Check List
12B-5)

 

Start fuel pump and maintain normal helium
flows and pressures in fuel system and fuel

drain tank system.

 

3 DRAINING COOLANT SYSTEM

 

3.1

3.2

3.3

3.4
3¢5

3.6

3.7

3.8
3.9

Check that HCV-527 is open and CDT pressure

and CP pressures are approximately equal.

 

Switch cooclant drain switch to drain.

This will thaw FV-204 and FV-206 and drain
the coolant salt to the coolant drain tank.
Since the system will be in the prefill
mode, the coolant pump will not stop on

low level and must be manually siopped.

 

When the bulk of the coolant salt has
drained (approximately 30 minutes), run
the coolant pump for a few minutes to shake

off the salt. Then stop the pump.

 

Close HCV-527 and open HCV-54T.

 

Continue purging through FCV-512 and the
bubblers until all of the salt has been
blown down to the drain tank.

 

Close FCV-512 and the bubblers and allow

pressures to come to equilibrium.

 

Close HCV-547 and pressurize CDT approximately
1/2 psi higher than that at equilibrium.

 

Deep freeze FV-204 and 206.

 

When freeze valves indicate frozen set up
flows through FCV-512 and the bubblers to

increase CP pressure to 2 psig and open

A
 

Approved by,455?;;4¢zéy»¢yn 10A-9

v 8-12-65

Init. Date/Time

 

3.9 (continued)
HCV-547 to reduce CDT pressure to testh
freeze valves.

3.10 Close HCV-547 and open HCV-527.

3.11 Take a complete inventory (Check Lish
12B-5)

3.12 Start CP and maintain normal flows and

 

 

 

pressures.
COOLDOWN OF FUEL AND COOLANT SYSTEMS

 

 

Lower the heater settings or turn off the heaters
to cool down the fuel and coolant systems. The
circulating pumps will be used to circulate helium
during cooldown to help egualize temperature and
cool down the graphite. Cooldown rate should be
limited to approximately 300°F per hour to allow
time for the graphite to cool. Helium purge

rate will be kept maintained to avoilid a vacuum

on the systems. The drain tanks will not normally
be cooled. If malntenance is necessary on them,
precautions will be necessary in safely storing
the salt. Specilal instructions will be issued
when needed.

L.l If inventories are satisfactory, check that

the CP and FP are in operation.

 

L.2 Maintain FIC-516 and 512 at normal rate.
See Building Log. Increase flows if nec-
essary to avold pulling a vacuum.

L.3 Turn off reactor heaters listed in Table

 

5F-1, 2, 3, and 4; and allow the system to
cool. Put individual heaters back in service
if necessary to maintain all temperatures
within + 300°F, o hold the cocling rate to a

maximum of 300°F per hour and to avoid pulling
Approved by .fi%&m_

4.3 (continued)

a vacuum on the fuel or coclant systems.

Init.

10A-10
8-12-65

Date/Time

 

Minimize temperature gradients at the

penetrations.

 

L.} When the radiator annulus and coolant system

temperatures are less than 5000F, turn off the

radiator annulus blowers No. 2 and No. i&.

 

4.5 When a2ll temperatures have been less than

2000F for at least four hours, turn off the

CP and FP and all heaters which have been

put back into service.
5 SHUT DOWN OF REMAINING EQUIPMENT

 

 

The lube oll systems can be shut down at this

time, and the helium purge can be turned off

from the fuel and coolant systems and the drain

tanks 1if desired. Details are given below:
5.1 Shut off the lube oil pumps (FOP—l, FOP-2,

COP-1, and COP-2).

 

5.2 Leave the pressure on the oil tanks (OT-1

and OP-2) at normal (PIC-513A and 510A).

 

5.3 Adjust the fuel system and fuel drain tank

system pressure at 1 to 5 psig to prevent

inleakage of moisture. Unless maintenance

is

be

Control Room

HCV-572
HCV-5T7h
HCV-576
FCV-516

to be done on either system, they should

inter-connected. 8Set valveg as follows:

closed__ HCV-573 closed  HCV-5L4i4 open
closed _ HCV-575 closed _ HCV-545 open
closed _ HCV-577 closed _ HCV-546 open
closed__  HCV-533 closed
Approved by£47¢99“i§?yn¢AV1 10A-11

NESA

8-12-65

Init. Date/Time

 

HCV-519 closed

Transmitter Room

 

V-592A closed V-589A closed
V-593A closed V-599A closed
V-596A closed V-600A closed

Vent House

V-522B closed

5.4

(Maintain pressures by periodically opening
FCV-516 or HGV-573, 5Tk, or 575)

Adjust the coolant system and coolant drain

 

tank system pressure at 2 to 5 psig to prevent
inleakage of moisture. Unless maintenance
is to be done on elther system, they should

be inter-connected. 8Set valves as follows:

Control Room
FCV-512 closed HCV-547 closed
HCV-536 closed HCV-511A closed
HCV-527 open

Transmitter Room

 

V-5944A closed

V-595A closed

V-598A closed
Vent House

V-560B closed

5.5

Maintain pressures by periodically opening
HCOV-511A or HCV-547 and V-560B.

 

When afterheat removal is no longer needed . v o v
in the drain tank steam domes, drain all
water from the steam domes by the procedure

given in Section 9L.

 
‘e
o
Approved byZ- " mE 10B-1

v 9/7/65

10B SPECIAL SHUTDOWNS

There are a number of known conditions which wlll cause some degree
of automatic shutdown (see Part IT on process instrumentation) or which
will make it desirable to take some action toward shutting down the re-
actor (see Section 9 of this part). If it is necessary to quickly drain
the reactor without removing the afterheat, the procedure is somewhat
different than a normal shutdown. Details of the procedure are given

below:

1 POWER REDUCTION AND GOING SUBCRITICAL
If an automatic or manual emergency drain has been initiated,
FV-103, 105, and 106 will start to thaw and the vent valves on the
drain and flush tanks will open. When fuel salt starts to drain,
the fuel pump will stop which will seram the control rods if the
power 1s greater than 15 kw. The coolant radiator ocutlet tempera-
tures will decrease causing a load scram and coolant drain. After
a drain request has been initiated there will be 10 or 15 minutes
before FV-103 thaws. The operator should do the following:

Tnit. Date/Tinme

 

1.1 Determine the cause of the drain request and
remedy the situation if possible. If not
possible, record all informatlion which might

aid in future evaluation of the difficulty.

 

1.2 Isolate a fuel sample.

 

Record FD-1 and FD-2 weigh cell readings.

 

1.4 Scram the control rods and note that they are

fully inserted.

 

1.5 Lower power removal by stopping both blowers

(MB-1 and 3) and closing both radiator doors.

 

1.6 Adjust radiator doors if necessary to remove

afterheat.

 
Approved by %/%7 Ao

NOTE :

Init.

10B-2
9/7/65
Date/Time

 

DRATNING AND FIUSHING The : FUEL SYSTEM
If time permits, Section 10A-2 should be

 

followed including flushing with flush salt. In

addition the following should e done.

2.1 Check temperatures of FV-103 to determine
that the valve is thawing. If it appears that
component cooling air is still on to the
valve, shut off both component coolant pumps
untlil the valve thaws. Then restart a
component coolant pump to restore cooling to

the other freeze valves and control rods.

 

Stopping the component coolant pumps should be
avolded if possible because it thermal cycles the
pump bowl. Close HCV-903 (set HIC-903 at maximum)
before starting component coolant pumps.

2.2 The drain tank cooling system will automati-
cally go into operation if the drain tank
temperature exceeds 1300°F. However, the
Tollowing should be done to assure proper
operation. Check that adequate condensate is
available in the feed water tanks and cooling

water to the drain tank condensers.

 

2.3 Check that the drain tank temperatures are
controlled between 1350°F and 900°F.

 

2.4 Take a complete inventory (check list
12B-5) if possible. At least record FD-1

and FD-2 manometers when drain 1s complete,

 

2.5 If it 1s not possible to flush the system
with flush salt, switch to prefill and start
the fuel pump to circulate helium, which will
aid in the removal of afterheat. The fuel
system temperatures should be continuously

scanned for hot spots from fission products.

 
Approved by, - ffiMgnc 10B-3
/ 9/7/65

3 SHUTDOWN OF REMAINING EQUIPMENT

As soon as possible drain the coolant system and shut down the

remaining equipment as described in Section 10B-2.
L
Approved b&ffié%%i%%i%?é?hfifll 11-1
9/7/65

11. GSHUTDOWN OPERATIONS

During periods when the reactor is shut down, a variety of operations
may be necessary. Due to the fact that these are not done routinely and
that the manner of accomplishing them may change from shutdown teo shutdown,
it is extremely important that the operating crew be alert to all possible
hazardous or otherwise undesirable conditions. As during operation, the
shift supervisor is in charge of and is responsible for all work done in
the area. As the daily cost of shutdown is quite high, all unnecessary
delays should be avoided. However, it should be emphasized that a wrong
decision made hastily may be costly in time or money.

During shutdown an abbreviated log will be taken. This should be used
as a guide only, and the person taking the log should be alert to undesir-
able conditions which might exist.

Detailed procedures are given below for some of the foreseeable shutdown
operaticns. Remote maintenance procedures are given in Part IX of the

MSRE Design of Cperations Report,
11A-1
8/5/65

Approved by

 

11A TUEL OR FIUSH SALT TRANSFERS

No salt transfers will be made while the reactor is in operation or
when there is salt in the fuel system. Most transfers will be made with
the reactor and drain tank cells at 12.7 psia; howsver, transfers can be
made with the seal pans removed but with all lower cell blocks in place.
Controlled ventilation would then serve as the secondary containment. No
fuel should be transferred to F3T until 4 days after a drain to allow for
Xenon decay.

The transfer operations consist of:

(a) Heating the transfer lines and tanks,

(b) Taking inventory,

(¢c) Thawing or freezing the necessary freeze valves,

(d) Pressurizing the supply tank and venting the receiver tank un-

til the transfer is complete,

(e) Blowing the salt out of the transfer lines,

(f) Freezing the freeze valves,

(g) Taking another inventory.

Details of the transfer operations are given below. Descriptions are
given for transferrirg to and from FD-1, FD-2, FFT, and FST. Instructions
for fuel or flush salt removal to the waste storage tank or removél of
coolant salt will be issued at the time this is to be done.

The following procedures are based on the assumption that the trans-
fer lines contain no salt other than that at or near the freeze valves. If
salt is known to be in the lines, special instructions will be issued.

Init. Date/Time

 

1 PREPARATION FOR TRANSFERS
1.1 Cheeck that the reactor has been drailned.
FV-10L4, 105, and 106 are deep frozen and re-

actor is in the prefill mode.

 

1.2 Heat up the two tanks involved in the transfer
to 1200°F. Details of the heatup as well as
a listing of the heaters and thermocouples are
given in paragraph 5C for tanks in the drain
tank cell and paragraph 11A-14 for the fuel

storage tank.

 
Approved by MM@

1.3 Heat up the transfer lines as described below.

This section covers the heatup of L-107, 108,

109, 110, 111 in the area isolated by the

freeze valves in these lines.

1.3.1 Check to see that records indicate
that no salt is in the lines other than
at the freeze valves.

1.3.2 Chec% that the following FV's are set

in the freeze position and frozen.

FV-107 FV 110
FV-108 FV-111
FV-109

1.3.3 Plug in the thermocouples listed in
Table 11A-1 into a readout device and
record readout in Col. 3 & k.

1.3.4 Set 8-L4 to receiver tank selected for
the transfer and S5-5 to the supply tank.

1.3.5 Check Syphon Break Temperatures on
FV-107, 108, 109, 110, and 111 to be
>900°F (These are heated with tanks in-
volved, see step 1.2).

1.3.6 Turn on shoulder heaters to the re-

ceiver tank freeze valve and heat to. °F,

11A-2
8/5/65

Tnit. Date/Time .

 

 

 

 

 

 

 

 

1.3.7 When shoulder temperatures of receiver
tank freeze valve exceeds 900°F, thaw
Receiver Tank Freeze Valve to vent gas
from heatup of lines.

1.3.8 Turn on heaters listed in Table 11A-1
to 10% of normal value.

1.3.9 Increase controllers to heat transfer
lines to 1200°F. Set controllers at 30%,
5%, 90%, and 105% of 1200°F setting. Do
not exceed 200°F/hr. The Al and Bh

 

 
Approved

 

114-3
8/5/65
Tnit. Date/Time

1.3.9 (continued)

thermocouples on the freeze valves

should be heated above 950°F.

 

1.3.10 When transfer lines reach 1200°F

freeze Receiver Tank Freewze Valve.

 

1.4 Check that shield blocks are in place on
reactor cell, drain tank cell, and fuel pro-
cessing cell and no maintenance work is in
progress in these cells. Set FV-103 to freeze
and monitor FV-103 temperatures to assure
that no salt is transferred to the reactor.

ohift Supervisor's approval to prcceed.

 

 

2 TRANSFER FROM FD-1 TO FST
2.1 After completing 11A-1, take a complete inven-
tory. (Check list 12B-5).

 

 

2.2 Check that the switches for FV-106, 107, 108,
109, 111, and 112 are in the frozen position
and the temperatures indicate that they are

frozen (all associated alarms cleared).

 

2.3 Check that HOV-692 is open and the FST
pressure (PR-608) is less than 2 psig. Check
that FST has been purged of air.

 

2.4 Close HV-60T7B , HV-608B __ , HCV-530
and HCV-690 .

 

2.5 If FD-1 pressure (PR-572) is greater than
2 psig, vent through line 573 and then close
HCV-5T73.

 

Close HCV-SLL ) HCV-545  , and HCV-5L46
Set 8-L4 to FST (Receiver).

Set S-5 to FD-1 (Supply Tank).

Thaw FV-109 and FV-110.

 

2.8 Check all rods at the fill position.

 
  

A/t
Approved byZ fifi’«w .

2.9 Check pump bowl pressure <L psi (PRC-522A)
2.10 Adjust PIC-51T7, open HCV-572 and pressurize

FD-1 to transfer the salt. (A AP of 20 psi is

needed to start the transfer and 29 psi when
FD-1 is empty and FST contains ~ 7O £t° of
fuel salt.)

2.11 When transfer is complete, reduce FD-1
pressure ~ 1/2 psi through HCV-573 and
freeze FV-110.

0.12 Take system inventory. (Check 1list 12B-5)

2.13 FV-109 should be frozen at this time if the
transfer lines are not to be deep frozen.

2.14 Vent FD-1 pressure to 5 psig through HCV-573.

TRANSFER FROM FD-2 TO TST

3.1 After completing 11A-1 take a complete inven-
tory. Check list 12B-5.

3.2 Check that the switches for FV-105, 107, 108,
109, 111, and 112 are in the frozen position
and the temperatures indicate that they are
frozen (all associated alarms cleared).

3.3 Check that HCV-692 is open and FST pressure
PR-608 ig less than 2 psig.

3.4 Close HV-607B, HV-608B, HCV-530, and HCV-690.
If FD-2 pressure (PR-574) is greater than
2 peig, vent through line 575 and then close
HCV-5T75.

Init.

11A-)
8/5/65
Date /Time

 

 

 

 

 

 

 

 

Close HCV-S5kL | HCV-545  and HCV-546 _ .

Set 5-4 to FST (Receiver).

Set S-5 to FD-2 (Supply Tank).

Thaw FV-108 and 110.

Check all rods at the fill position.
Check PRC-522 <1 psig.
Approved byflfflfiffikfié%%fi)flwfl¢ 11A-5
8/5/65

Tnit. Date/Time

 

3.10 Pressurize FD-2 and transfer the salt (4 AP

3.11

3.12
3.13

3.1k

of 20 psi is needed to start the salt transfer
and 29 psi when FD-2 is empty and FST contains

approximately TO £t° of fuel salt.)

 

When the transfer is complste, reduce FD-2
pressure ~ 1/2 psi through HCV-575 and freeze
Fv-110.

 

Take system inventory, Check list 12B-5.

 

FV-108 should be frozen at this time if the

ftransfer lines are not to be deep frozen.

 

Vent FD-2 pressure to 5 psig through HCV-573.

 

L TRANSFER FROM FFT TO FST

 

h.1

L.2

4.3

L.h
h.5

k.6
b7

1.8
k.9
k.10

After completing 11A-1, take a complete inven-
tory, Check list 12B-5.

Check that the switches for FV-104, 107, 108,
109, 111 are in the frozen position and the
temperatures indicate that they are frozen
(all associated alarms cleared).

Check that HCV-629 is open and FST pressure
(PR-608) is less than 2 psig.

Close HV-607TB, HV-608B, HCV-530, and HCV-690.
If FFT pressure (PR-576) is greater than 2
psig, vent through line 577 and then close
HCV-5T7T.

Close HCV-54L |, HCV-545 & HCV-546 .
Set S-4 to FST (Receiver)

Set 8-5 to FFT (Supply Tank)

Thaw FV-107 and 110.

Check all control rods at the fill position.
Check PRC-522 <1 psig.

Pressurize FFT and transfer the salt. (A AP

 

 

of 17 psi is needed tco start the transfer and
25 psi when FFT is empty and FST contains
approximately 7O £t° of flush salt.)
Approved by

 

Init.

L,11 When transfer is complete, reduce FFT pressure

4,12 Take system inventory, check list 12B-5.

~ 1/2 psi through HCV-577 and freeze FV-110.

4.13 FV-10T7 should be frozen at this time if the

transfer lines are not to be deep frozen.

L.1k Vent FFT pressure to 5 psig through HCV-5T7T.
5 TRANSFER FROM FST TO FD-1

5.1

5.2

5.3

5.k

5.5

5.6

5.7

5.8

After completing 11A-1, take a complete inven-
tory, check list 12B-5.

Check that the switches for FV-106, 107, 108,
110, 111, and 112 are in the frozen position
and temperatures indicate that they are frozen
(a1l associated alarms cleared).

Check that HCV-54% and HCV-533 are open and
FD-1 pressure (PR~572) and FP pressure (PR-522)

A ————

are less than 1 psig.
If FST pressure (PR-608) is greater than

———

2 psig, vent through line 692 and then close
HCV-692.

Close HV-60TA, HV~608A, and HCV-530 and
HCV-690,

11A-6
8/5/65

Date/Time

 

Set S~4 to FD-1 (receiver).

Set 8-5 to FST (supply).

Thaw FV-110 and 109.

Pressurize FST by adjusting PCV-530 to opening
HCV-530, and transfer the salt. ( A AP of

v s—————

16 psi is needed to start the transfer and then
it should continue unless the syphon is lost
or the back pressure equals the salt head of

20 psi.

 

When the transfer is complete, reduce 5T
pressure ~ 1/2 psi through HCV-692 and freeze
FV-109,

 
Approved'byfiéffizzf§2%7/h4anf S}lfiéT
5/65

5.9

Tnit. Date/Time
Take a system inventory, Check 1ist 128-5.

 

5.10 FV-110 should be frozen at this time if the

transfer lines are not to be deep frozen.

 

5.11 Vent pressure in FST to 5 psig through

HCV-692.

6 TRANSFER FROM FST TO FD-2

 

6.1

6.2

6.3

6.4

6.5
6.6

6.7

6.8

6.9
6.10

After completing 11A-1 take a complete inven-
tory, Check List 12B-5.

 

Check that the switches for Fv-105, 107, 109,
110, 111, and 112 are in the frozen position
and temperatures indicate that they are
frozen (all associated alarms cleared).
Check that HCV-545 and HCV-533 are open and
FD-2 pressure (PR-5T4) and FP pressure
(PR-522) are less than 1 psig.

If FST pressure (PR-608) is greater than 2

 

psig, vent through line 692, and then close
HCV-692,

Close HV-60TA, HV-608A, HCV-530, and HCV-690.
Set 8-4 to FD-2 (Recéiver)

Set $-5 to FST (Supply Tank)

Thaw FV-110 and 108.

Pressurize FST by adjusting PCV-530 and opening
HCV-530 and transfer the salt. (A AP of

 

 

 

16 psi is needed to start the transfer and
then it should continue unless the syphon is
lost or the back pressure equals the salt

head (20 psi).

 

When the transfer is complete, reduce FST
pressure ~ 1/2 psig through HCV-692 and
freeze FV-108.

Take a system inventory, Cheek List 12B-5.

 

 

FV-110 should be frozen at this time if the

transfer lines are not to be deep frozen.

 
Approved by ni

6,11

Init.
Vent pressure in FST to 5 psig through
HCV-692.

7 TRANSFER FROM FST TO FET

7.1

7.2

7.3

7.k

Te5
7.6

T

7.8

7.9
7.10

T.11

After completing 11A-1, take a complete in-
ventory, Check List 12B-5.

Check that the switches for FV-104, 108, 109,
110, 111, and 112 are in the frozen position
and temperatures indicate that they are
frozen {(all associated alarms cleared).

Check that HCV-5L6 and HCV-533 are open

and FFT pressure (PR-576) and FP pressure
(PR-522) are less than 1 psig.

If FST pressure (PR-608) is greater than 17
psia, vent through line 692 and then close
HCV-692.

Close HV-60TA, HV-608A, HCV-530, and HCV-690.
Set 8-4 to FFT (Receiver)

Set S-5 to FST (Supply Tank)

Thaw FV-110 and 107.

Pressurize FST by adjusting PCV-530 and
opening HCV-530 and transfer the salt. (A AP
of 14 psi is needed to start the transfer and
then it should continue unless the syphon is
lost or the back pressure is greater than the
salt head (17 psi).

When the transfer is complete, reduce F5T
pressure ~ 1/2 psi through HCV-592 and freeze
FV-10T7.

Take a system inventory, Check List 12B-5.
FV-110 should be frozen at this time if the
transfer lines are not to be deep frozen,
Vent pressure in FST to 5 psig through
HCV-592.

114-8
8/5/65

Date/Time
Approved by .~

  

n4y] 11A-9
8/5/65
Init, Date /Time

 

8 TRANSFER FROM FD-1 TO FD-2

8.1

8.12

After completing 11A-1, take a complete inven-
tory, Check List 12B-5.
Check that the switches for FV-105, 106, 107,

 

109, and 110 are in the frozen position and
the temperatures indicate that they are frozen

(all associated alarms cleared).

 

Check that HCV-575 is open and FD-2 pressure
(PR-574) is less than 2 psig.
If FD-1 pressure (PR-573) is greater than

 

2 psig, vent through line 573 and then close
OCV-573.

 

 

Close HCV-5L4 | HCV-54L5 _ , & HCV-5L6
Set S-4 to FD-2 (Receiver)

Set S-5 to FD-1 (Supply)

Thaw FV-108 and 109.

Check all control rods at the fill position.

 

 

Pressurize FD-1 and transfer the salt (A AP
of 7 pel is needed to start the transfer and

11 psi to complete transfer.)

 

When the transfer 1s complete, reduce FD-1
pressure ~ 1/2 psi through HCV-573 and freeze
Fv-108.

 

Take a system inventory, Check List 12B-5.

 

FV-109 should be frozen at this time if the

transfer lines are not to be deep frozen.

 

Vent pressure in FD-1 to 5 psig through
HCV-5T73.

 

9 TRANSFER FROM FD-2 TO FD-1

9.1

9.2

After completing 11A.1, take a complete in-
ventory, Check List 12B-5.
Check that the switches for FV-105, 106, 107,

108, and 110 are in the frozen position and

 

the temperatures indicate that they are frozen

(all associated alarms cleared).

 
Approved by

10

 

Init.

11A-10

8/5/65
Dete /Time

 

9.3 Check that HCV-5T73 is open and FD-1 pressure
(PR-572) is less than 2 psig.

 

9.4 If FD-2 pressure (PR-5T4) is greater than
2 psig, vent through line 575 and then close
HCV-575.

 

9.5 Close HCOV-5LL  , HCOV-545 _ , HCV-5k6

 

 

9.6 Set S-b to FD-1 (Receiver)
Set S-5 to FD-2 (Supply)
Thaw FV-108 and 109.

 

9.7 Check all control rods at the fill position.

 

9.8 Pressurize FD-2 and transfer the salt. (A AP
of 2 psi is needed to start the transfer and

11 psi to complete transfer.)

 

9.9 When the transfer is complete, reduce FD-2
pressure ~ 1/2 psi through HCV-5T75 and
freeze FV-109.

 

9.10 Take a system inventory, Check List 12B-5.

 

9.11 FV-108 should be frozen at this time if the

transfer lines are not toc be deep frozen.

 

Q.12 Vent pressure in FD-2 to 5 psig through
HOV-576.

 

HEATUP OF FST

 

This section covers the heatup of FST, line
110 to the surge pot of FV-110, line 111 to
FV-111, includes both surge pots of FV-110 and
H-110-7 on both sides of FV-110.
10.1 Check that oxygen has been purged from the

system.

 

10.2 Check to see that records indicate that no
salt is in the lines other than at the

freeze valves.

 

10.3 Check that the following FV's are set in the
freeze position and frozen.

FY-110 _ , Fv-111 _ , FV-112 :

 

1C.4 Open HCOV-692.

 
Approved by ey 11A-11

11

8/5/65
Init. Date/Time
10.5 Set V-608B to maintain a flow of 0.5 £/m on

FIA-608. This will purge the tank and will

prevent activity from backing up the line.

 

10.6 Check that the thermocouples listed in Table
11A-2 are plugged into a readout instrument
and that these are in operation. Record

Inst. No. and T.E. Readout Points.

 

10.7 Set controllers listed in Table at 10% of their
maximum setting and start heating the system.

(Push start button on induction regulators.)

 

10.8 Using the heater calibration curves as guides,
heat the system at approximately 100°F per
hour. Maintain temperatures within * 100°F

of each other if possible.

 

10.9 Adjust controllers to level out the tempera-
tures at approximately 1200°F.

 

10.10 Close V-608 and HCV-692. Maintain PR-608
at 1 to 5 psig.

 

HEATUP OF FILL LINE 111

 

This section covers the heatup of the fill line
from the disconnect flange to FV-111. Details of
the procedure are given helow.

11.1 Check to see that the line does not contain
any salt,

 

11.2 Connect the thermocouples listed for the fill
line in Table 11A-3 to a readout inst.
Record instrument and point number in Table

11A-3,

 

11.3 Increase the setting on the controllers given
in Table 11A-3 to give approximately
200°F/hr heatup.

 

11.4 Adjust the controllers to level out the
temperature at approximately 1200°F.

 

HEATUP OF WASTE LINE 112

This section covers the heatup of L-112 from

“the tee in L-110 to the capped penetration.
Approved by;géfé@%éfié»fid?} 11A-12
| 8/5/65

Init. Date/Time
12.1 Check L~110 empty of salt or salt molten.

 

12,2 Connect the TE's listed in Table 11A-L to a
read out instrument. Record instrument and

point number in Table 11A-L.

 

12.3 Adjust heater control H-112-1 to heat line.
Since line will contain salt do not heat -
up faster than 50°F/hr.

12.4 Adjust controller to level temperature out
at 1200°F.

13  HEATUP OF FILL LINE 203

This section covers the heatup of the fill 1line

from the disconnect flange to the CDT.

13.1 Check to see that the line does not contain
any salt.

13.2 Connect line 203 to the CDT. Open HCV-511B
to purge I-203. CAUTION: Line may contain
salt which could present a beryllium hazard.
Teke proper precautions.. Then blank the top
end of the line to exclude oxygen or have it
connected to a shipping container. Close
HCV-511B.

13.3 Connect the thermocouples listed for the fill
line in Table 11A-5 to a readout instrument.
Record instrument and point number in Table
11A-5,

13.4 Increase the setting on the controllers given
in Teble 11A-5 to give approximately 200°F/hr
heatup.

13.5 Adjust the controller to level out the
temperatures at approximately 1200°F.

14 HEATUP OF TRANSFER AND SALT ADDITION FREEZE VALVE ASSEMBLIES

 

When a freeze valve is frozen to obstruct flow,
only a small volume of salt near the center of the

valve is frozen. Occasionally it will be desirable
e

i’ 1k

'V
No

107
108
109
110
111
112

Approved by/éfig fi/# A 11A-13
8/5/65

Init. Date/Time

(continued)
or necessary to cool the surge pots and piping
associated with the freeze valve. BSince it is not
possible to remove all of the salt (except for
FV-103), special precautions must be taken to
prevent rupturing the pipe due to expansion of the
salt as it is heated. The outside areas are heated
first to melt the salt so that there is room for
expansion. In all cases it is assumed that the
adjacent pipe does not contain salt or that the
salt is molten. Interlocks on TE's prevent thaw-
ing of the FV's if the pot temperatures are less
than 950°F. Other interlocks prevent thawing
FV's under certain conditions.
1h,1 Heatup of Freeze Valve Assemblies FV-107,

108, 109, 110, 111, and 112.

 

 

To prevent possible rupture of the assemblies,
the freeze valve Syphon break on adjacent
lines should be heated to above 900°F before
thawing the valve. The valve heater control-
lers will then have to be adjusted for normal
operation (See Section LI).

The thermocouples and heaters involved are

listed below:

 

Controller
TE No. Heater No. No. HCP
FV-107-AL & B4Y  FV-10T7-24,B,C,D FV-107-3 10
FV-108-AL & B4+  FV-108-24,B,C,D FV-108-3 11
FV-109-Al & B4  FV-109-24,B,C,D FV-109-3 11
FV-110-Ak & B4  FV-110-24,B,C,D FV-110-3 12
FV-111-A4 & B4 FV-111-24,B,C,D Fv-111-3 12

my-112-ALk & B4  FV-112-2A,3,C,D FV-112-3 12

 
, o
Approved by:éf?fé?fii%%fifi?fifv é?fl;éu
5/65

Init. Date/Time
14.2 Heatup of Freeze Valve Assemblies FV-204 and 206.

The vertical sectlons of the lines near the
freeze valves must be heated before the freeze
valve shoulders. These lines will normally
be heated as the coolant system is heated
(see Section 5F) and the FV pot is heated with
the CDT (See Section 5C). Details of the
procedure is given below.
14,2.1 Check to see that temperatures at

TE-204-6, TE-206-6, and TE-FV-204-5B

are above 1100°F.

 

14.2.2 Heat up shoulders of FV-20L4 and 206
by raising the setting on controllers

FV-20L-2 and 206-2.

 

14.2.3 When the temperatures at TE FV-20L-Al,
Bt and TE FV-206-Ak, Bh are above 1000°F
on TR-3300, the freeze valves can be
operated without rupturing the lines.

It will be necessary to adjust the freeze
valve heaters for normsl operation (See

Section 3I).

 
 

 

 

Approved by e/ it o 11 A45
E ;7 8/5/65
Table 11 A-1
TRANSFER LINE THERMOCOUPLES AND HEATER CONTROL
TE PATCH PNI, TE READOUT HEATER [CONTROLLER HCP
NOs: N0+ Inst Point NO. N0+ NO.
FV 107-Ak 206 TRA 3300 7 FV 107-1A, 3B PV 107-1 10
FV 107-3A, B FV 107-3
FV 107-B4 297 " 3 FV 107-1¢,D FV 107-1
FV 107-3C, D By O107-3
FV 108-AkL 308 " 9 FV 108-14, B FV 108-1 il
FV 108-3A0 R PV 108-3
FV 108-Bk 309 " 10 FV 108-1C,D FV 108-T1
, FV 108-3C,D FV 108-3
FV 109-Ak 320 ' 11 FV 109-1IA,R FV 109-1 11
. FV 109-3A, B FV 109-3
FV 109-B4 321 12 FV 109-1C,D FV 109-1
' FV 109-3C,D FV 100-3
FV 110-Ak 332 ! 13 FV 110-24, 3 FV 110-2 12
, FV 110-3A, R FV 110-3
FV 110-Bk4 333 ! 14 FV 11C-2C, D FV 110-5 12
. FV 110-3C,D FV 110-3
FV 111-Ah 344 15 FV 111-24A, B FV 111-2 12
| TV 111~340R FV 111-3
FV 111-BL 345 16 FV 111-2C,D FV 111-5 12
E 111-1-1 H 111-1
108-7 433 H-110-1-1A H 110-1 11
109-7 hiq H-110-1-24 H 110-1 11
110-1 L3 H 110~2-14 H 110-2 10
110-2 Ll H 110-2-24 " 10
110-A3 L5 H 110-2~-3A " 10
110-B3 hr1 H110~-3-1A 110-3 10
110-C3 Lo H 110-3-24 " 10
110-LkA hhg H 110-% H-100-4 12
110-54A LLE H 110-5 H 110-5 12
110-6 450 H 110-6-1 H-110-6 12
110=-7 451 H 110-6-2 " "
110-8 L5o H 110-6-3 " "
110-9 453 H 110-6-4 4 "
110-A10 L5k H 110-7-1 H 110-7 "
110-E10 L6k H 110-7-1 " "
lll'T )4-63 E llO'T'l " "

 

 

 

 

 

 

 

 

 
Approved by . 11 A-16

 

 

 

 

 

 

 

 

8/5/65
Table 11 A-2
FUEL STORAGE TANK THERMOCOUPLES AND HEATER CONTROLLERS
TE PATCH PNL TE READOUT HEATER ] CONTROLLER | HCP
NO. NO. Inst Point No. NO. No.
FST - 1A 21k FST-4 FST-4 13
FST - 1B 215 TR 3002 11 1A, B, 28;B
FST -2A 216 "
FST - 2B 217 TR 3002 12 "
FST - 3A 218
FST - LA 220 |
FST - LB 221 TR 3002 14 N
FST - 5 202 FST-3 FST-3 13
14, B
FST - B 225 oA, B
3A, B
FST - 6 223 TR 3002 15 "
FST - 9 226 " FST-2 13
FST-2
FST - T 2oL 1 1A,B
2A, B
FST - 10 227 - Aa B
LA, B
FST - 11 228 ¥
FST - 12 229 FST-1 FST-1
1-8 "
FST - 13 230 TR 3002 16 " "
110-A10 L5k 110-7-1 H-110-7
110-B10 | g 110-7-1 12
111-7 463 110-7-1
;110-11 455 110-7-2 12
%110-12 L56
|

 

 

 

 

 

 

 

 

 

 

 
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

| Approved by;fléfiqa%é%%%jgzuaflw 11 A-17
| 8/5/65
' Table 11A-3
LINE 111 THERMOCOUPLES AND HEATER CONTROL
TE PATCH PNIL TE READOUT HEATER CONTROLLER | HCP
NO, NO. Inst Point NO. NO. NO.
111-1 hsT 111-2-2 H-111-2 #12
111-2 458 111-2-1 "
111-3 k59
111-k LEO 111-1-3 H-111-1 12
111-5 el 111-1-2 "
111-6 Leo 111-1-1 "
Table 11A-L
LINE 112 THERMOCOUPLES AND HEATER CONTROIS
TR PATCH PNL TE READOUT HEATER iCONTROLLER | HCP
NO. NO. Inst Point NO. ¢ NO. NO.
112-41 Lol H1l2-1-1 H 112-1 #12
112-B1 H 112-1-2 "
112-R82 L6 "~ JH 112-1-3 "
112-B3 LéeT H 112-1-4 "
FV 112-5B FV 112-34,B FV 112-3

 

 

 

 
 

7~
Approved bz%fi@fl

LINE 203 THERMOCCUPLES AND HEATER CONTROLLERS

Table 11A-5

11 A-18
8/5/65

 

 

T i PATCH PNL TE_READOUT HEATER CONTROLLER | HCP

NO. NO. Inst Point NO. NO. NO.
203-1 821 H 203-1A H 203-1 L
203-2 822 H 203-1B " "
203-3 823 H 203-1C " "
203-k 824 H 203-1D " "
203-5 825 H 203-1E " "
203-6 826 H 203-1F " "
203-T 827 H 203-2 H 203-2 3

 

 

 

 

 

 

 

 
Approved by Mm 11B-1

v 9/20/65

 

11B OPENING REACTOR CELL, DRAIN TANK
CELL AND COQLANT CEHLL

After a power operation considerable radioactivity may be present
in the reactor cell, drain tank cell and coolant cell. Therefore, great
care must be exercised when opening the shields. Tae fuel should be
drained into one of the drain tanks. Since a rupture in the drain tank
afterheat-removal thimbles could cause a release of considerable steam
and radloactivity, it is desirable to allow sufficient time after shut-
down so thav ccoling 1s no longer required. The cooling thimbles should
be boiled dry and the water stored in the FWD's. The coolant salt should
also be drained. All heatere except those required to keep the salts
molten in the tanks should be off if the shutdown is to be a lengthy one.

Since secondary containment i1s provided by inflow of air when the
shields are opened, the stack must run continuously. In order to main-
tain the regquired 100 ft/min flow into the cells, the maximum open area
ls restricted to approximately 130 sq ft.

Bach shutdown will involve different operations, and it is difficult
to write specific instructions in advance. Therefore, it is especially
important for the cperator to be alert for hazards or other items which
have been overlooked. It is desirable to shut off all electrical power
not required in order to reduce shock hazard during maintenance opera-
tions. Other equipment and systems such as water and oil systems should
be shut down if not needed. "Do not operate” tags should be attached to
all valves and breakers involved. These tags should state that the
reason for tagging is a reactor shutdown. Shift supervisor's permission
should be given as the condition required to remove them. In case a
specific piece of equipment is to be worked on, an additional tag should
be attached giving the work request number.

The white slips should be attached to a copy of this section of the
Operating Procedures and should be removed at the end of the shutdown
when the shield is closed.

Care should be taken to valve out the leak detector to any flange
before it is opened. When 1t is closed, a leak check should be started

immediately.
Approved by

 

A

 

/’figfigz;/fifihwx
~

11B-2

9/20/65

The following is a check list covering most of the operations which

may be reguired before opening the shield.

depending on the malintenance which is to be done.

1 RC HEATER SHUTDOWN CHECK LIST

 

Open and tag distribution breakers which apply.
1.
1.

i.__l

1 Heater
2 Heater

Heater
Heater

Heater

.10 Heater
.11 Heater
.12 Heater
.13 Heater
.14 Heater
.15 Heater
.16 Heater
.17 Heater

FV-103
H-103
RAN-1
RAN-2
RCH-3
FP-1
FP-2
RCH-4
HX1
HX2
HX3
RCH-1
RCH-2
RCH-5
RCH-6
RCH-T
H-102-2

.18 Heater H-200-15
.19 Heater H-200-16
.20 Heater H-201-10
.21 Heater H-201-14

2 R R R P R R R PR R R R

.22 Heater
.23 Heater
.24 Heater
.25 Heater
.26 Heater
.2'{ Heater
.28 Heater

H-101-2
H-100-1
H-100-2
H-101-3
R1
R2
R3

G5-1-Ab-2
G5-1-AbL-4
G5-1-A5-1
G5-1-A5-2
T-1-A-6
T-1-A-10
T-1-A-8
T-1-B-6
T-1-B-9
T-1-B-10
T-1-B-8
T-1-C-7
T-1-C-9
T-1-C-10
T-1-C-8
T-1-C-5
T-1-C-6
T-2-V1-22
T-2-V1-17
T-2-V1-18
T-2-V1-19
T-2-V1-9
T-2-V1-1
T-2-V1-5
T-2-V1-13
T-2-Y-3
T-2-Y-5
T-2-Y-6

ERRRRRENE

]

 

Init.

Do only parts which apply

Date/Time

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
Approved by_,4255?5:2;%4§?§;w«4n\ 118-3
vV

9/20/65

Init. Date/Time

 

1.29 Heater H-200-1k  T2-wi-z2

1.30 Heater H-201-11 T2-W1-5

1.31 Heater H-200-1 T2-W2-2

1.32 Heater H-200-11 T2-W2-6

1.33 Heater H-200-12 T2-W2-10

1.34 Heater H-201-1 T2-W2-1k

1.35 Heater H-201-2 T2-W2-18

1.36 Heater H-201-9 T2-W2-17

1.37 Heater H-102-5 T2-W2-13

1.38 Heater H-102-1 T2-W2-5

1.39 Heater H-102-k4 T2-W2-9
2 DIC HEATER SHUTDOWN CHECK LIST

Open and tag distribution breakers which apply.
2 Heater FV-103 GS5-1-Ak-2
2 Heater H-10L-1 G5-1-A1-1
2 Heater FV-10Lk-1  G5-1-A1-9
2 Heater FV-10L-1A G5-1-Ak-1
2.5 Heater FV-104-3  G5-1-A1-11
2 Heater H-104-5 G5-1-A1-3
2 Heater H-104-6 GS5-1-A1-5
2 Heater FV-105-1  G5-1-A1-6
2 Heater FV-105-1A G5-1-A1-10 _
2 Heater FV-105-3 (5-1-A1-8
2.11 Heater H-105-1 GH-1-Al-2
2
2
2
2
2
2
2
2
2

 

 

 

 

 

 

 

 

 

 

 

 

s

 

 

 

 

 

 

 

 

O @ 9 0N G

 

°
O

 

 

——

.12 Heater H-105-4 G5-1-A1-L
.13 Heater FV-106-1 (G5-1-A2-5
.14 Heater FV-106-1A G5-1-Ak-3
-15 Heater FV-106-3  (G5-1-A2-7
.16 Heater FV-106-1  G5-1-A2-1
.17 Heater H-106-L G5-1-A2-3
.18 Heater H-107-1 G5-1-A2-2
.19 Heater H-107-2 G5-1-A2-4
.20 Heater H-107-3  G5-1-42-6

 

 

 

 

 

 

 

—

 

 
Approved byfigg:§§£?%3fi§§7,W,yl 118~k
N : 9/20/65
Date/Time

2.21 Heater FV-107-1  G5-1-A2-8
2.22 Heater FV-107-3  G5-1-A2-12 _
2.23 Heater H~103-1 G5-1-A3-1
2.24 Heater H-108-2 G5-1-A3-3
2.25 Heater E-108-3 G5-1-A3-5
2.26 Heater FV-108-1  G5-1-A3-11
2.27 Heater FV-108-3  G5-1-A3-7
2.28 Heater H-109-1 G5-1-A3-2
2.29 Heater H-109-2 G5-1-A3-4
2.30 Heater H-109-3 G5-1-A3-6
2.31 Heater FV-109-1 G5-1-A3-lz _
2.32 Heater FV-109-3  G5-1-A3-8
2.33 Heater H-110-1 G5-1-A3-9
2.34 Heater H-104-2 35-1-C1l-1
2.35 Heater H-10L-3 G5-1-C1-3
2.36 Heater H-10k-k G5-1-Cl-5
2.37 Heater H-105-2 G5-1-Cl-4
2.38 Heater H-105-3 G5-1-C1l-6
2.39 Heater H-10L-7 G5-1-C1-7
2.40 Heater H~110-2 G5-1-C1-2
2.41 Heater H-110-3 G5-1-C1-8
2.42 Heater H-106-2 G5-1-C2-2
2.43 Heater H-106-~3 G5-1-C2-7
2.4l Heater FPT-1 G5-BB-6
2.45 Heater FDL-1 G5-BB-10
2.46 Heater FD2-1 G5-BB-8
2.47 Heater FFT-2 T-1-B-7
2.48 Heater FD1-Z T-1-B-3
2.49 Heater FD2-2 T-1-B-5

 

3 CC HEATER SHUTDOWN CHECK LIST

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Open and tag distribution breakers which apply.
3.1 Heater H-203-1 35-1-C2-8 L
3.2 Heater H-20L-1 G5-~1-C2-6 _

 

 
 

11B-5

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

9/20/65
Init. Date/Time

3.3 Heater H-206-1  G5-1-C2-5
3.4 Heater CDT-1 G5-1-C2-4
3.5 Heater H-204-2 G5-1-C3-5
3.6 Heater FV-204-1  G5-1-C3-5
3.7 Heater FV-204-1A

3.8 Heater FV-204-2  G5-1-C3-4
3.9 Heater FV-204-3  G5-1-C3-6
3.10 Heater FV-206-1  G5-1-03-1
3,11 Heater FV-206-1A

3.12 Heater FV-206-2 (G5-1-C3-3
3.13 Heater CRL G5-BB-3
3.14% Heater CR2 G5-BB-5
3.15 Heater CR3 G>-BB-7
3.16 Heater CRL G5-BB-9
3.17 Heater CR5 G5-a-Y-3
3.18 Heater CR6 G5-2-Y-h
3.19 Heater CRT G5-2-Y-5
3.20 Heater CRS8 G5-2-Y-6
3.21 Heater H-200-13 T-1-A-5
3.22 Heater H-201-12 T-1-A-7 _
3.23 Heater H-202-2 T-1-A-9
3.24 Heater H-201-13 T2-Wl-9
3.25 Heater H-202-1 T2-WL-20
3.26 Heater H-205-1  T2-Wi-18

 

3.27 Heater FT-201A-1 T2-Wl-2
3.28 Heater FT-2014-2 T2-Wi-4

3.29 Heater PFT-201A-3 T2-Wl-6

3.30 Heater FT-201A-4 T2-W1-8

3.31 Heater FI-201B-1 T2-W1l-10
3.32 Heater FT-201B-2 T2-W1l-12
3.33 Heater FT-201B-3 T2-Wl-1h
3.34 Heater FT-201B-4 T2-W1-16
3.35 Heater H~203-2 T2-WL-17

 

 

 

 

 

 

 

 

 
Approved by

3.36
337
3.38

 
 

Heater CDT-Z
Heater CDT-3
Heater CP1

3.39 Heater CP2

T-2-V1-2 ___
T-2-V1-6
T-2-V1-10
T-2-Vi-1k

 

 

b COOLING WATER SHUTDOWN CHECK LIST
Close and tag those that apply.
(WR, BH, CC, SER)
4.1 Fuel Pump V-830-A
4.2 Fuel Pump V-831
4.3 Thermal Shield v-8hb-A
4.4 Thermal Shield — V-8LLC-A
4.5 Thermal Shield V-845
.6 RC Cooler No. 1  V-8Lo-A
4.7 RC Cooler No. 1  V-846-A
L.8 RC Cooler No. 2 V-838-A
L.9 RC Cooler No. 2 V-84L1-A
k.10 Drain Cell Cooler V-836-A
4.11 Drain Cell Cooler V-837-4
4.12 Cooclant Pump V-832-A
4.13 Coolant Pump V-833-A
4.14 Gas Cooler V-873-A
4.15 Gas Coocler V-8Th-4
L.16 CCP No. 1
(Lube 0il) vV-875-D
L.17 CCP No. 1
(Lube 0il) V-876
4,18 CCP No. 2
(Lube 0il) V-886
4,19 CCP No. 2
(Lube 0il) v-887
5 FREEZE VALVES SHUTDOWN CHECK LIST

 

Deep freeze valves that apply per Section 3T.4.

5.1

FV-10L4

Init.

11BR-6
9/20/65

Date/Time

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
Approved byW %\;/MM

W @ ~1 O ot =W

10

5.
5.
5.
5.
5.
5.
5.
5,
5.
5.11

6 COMPONENT COOLING AIR TO COMPONENTS SHUTDOWN CHECK

FV-105
FV-106
FV-107
FV-108
FV-109
FV-110
FV-111
FV-112
FV-204
FV-206

Init.

11B-7
9/20/65

Date/Time

 

 

 

 

 

 

 

 

 

 

 

LIST

 

Shut off and tag cooling air supply valves that apply.

(TR)
6.1
6.2
6.3
6.4
6.5
6.6
6.7
6.8
6.9
6.10
6.11
6.12
6.13
6.14

Fuel Pump HCV-903
Reactor Neck HCV-962
Reactor Neck | HCV-963

Graphite Sampler HCV-961
Control Rod Drives HCV-91
FV-103 HIC-919-A1
FV-104 HIC-208-A1
Fy-105 HIC-909-A1
FV-106 HIC~910-A1
FV-107 HIC-911-Al
FV-108 HIC-912-A1
FV-109 Close HIC-913-Al
FV-204% Close HIC-906-Al
FV-206 Close HIC-907-Al

Close
Close
Close
Close
Close
Close

>

—_—

e’

HIC-919-A2
HIC-908-A2
HIC-909-A2
HIC-910-A2
HIC-911-A2
HIC-912-A2
HIC-913-A2
HIC-906-A2
HIC-907-A2

7 COMPONENT COQLING PUMPS SHUTDOWN CHECK LIST
(Breaker House and SER)

7.1 CCP-1 Open and Tag Breaker
2__.__....._
Close and Tag V-916

7.2
7.3

Close and Tag V-92

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 
e

Approved by’fi?fifffi

 

Py
?§;§355;24?/Wfl 11B-8

9/20/65

Init. Date/Time

 

7.4 CCP-2 Open and Tag Breaker
7.5 Close and Tag V-923
7.6 Close and Tag V-921

8 ELECTRICAL BREAKERS SHUTDOWN CHECK LIST
Open or rack out the breakers and tag those which apply.

 

 

 

 

(Breaker House)
8.1 Fuel Pump Bus 4 Breaker D

 

 

 

 

 

 

 

 

 

 

 

 

 

 

8.2 Reactor Cell Cooler No. 1 (3-10
8.3 Reactor Cell Cooler No. 2 Gh-24
8. FOP-1 (Local)
8.5 FoP-2 (Local)
8.6 Drain Tank Cell Cooler G3-5 and GL4-5
8.7 Component Cooling Pump No. 1 Bus 3-H
8.8 Component Cooling Pump No. 2 Bug 4-E
8.9 Coolant Pump
8.10 Coolant Cell Cooler No. 1 G3-17
8.11 Coolant Cell Cooler No. 2 Gh-17
8.12 Radiator Door Drive T2-X
8.13 COP-1 (Local)
8.14 CcoP-2 (Local)
8.15 Control Rod Drive No. 1 (Process Power Panel
No. 2) o
8.16 Control Rod Drive No. 2 (Process Power Panel
No. 2) | L
8.17 Control Rod Drive No. 3 (Process Power Panel
No. 2)

9 OPENING RC AND DIC
If the RC or DIC is to be opened proceed as follows:
9.1 Close V-565C, V-965C and 966C. Open V's 9554
and B and raise the cell pressure to atmospheric
as indicated by PIA-RC-A,then close V's 955-A
and B. L

9.2 Cheeck that the steam drums have been boiled dry.

 
s
4
Approved by‘gfég%iia;éééffiwfifif
L= v

10

9.3 Open HCV's 930-A and B.

9.4 Remove the necessary blocks of the top layer.

9.5 C(Close HCV-935 ~ half.

9.6 Have HP survey made to assure it is safe to
work on membrane.

9.7 Remove that portion of the membrane seal as
necessary for the removal of the lower plugs
or shield blocks.

9.8 Close HCV-935A and with HP approval, remove
the plugs or blocks needed for maintenance.

2.9 When remote maintenance shield has been in-
stalled, adjust HCV-935A as required.

OPENING THE COOLANT CELL

If the coolant cell is to be entered, proceed as

follows:

10.1 Open dampers in ducts 933 and 93.L.

10.2 Remove the caulking from the shield blocks
as required.

10.3 With HP approval remove shield blocks and
Open doors as required. Have IH take air
samples to check for Be. Wear masks and
protective clothing as required by HP and
IH when entering the cell. Keep the number
and size of the openings in the cell to a

mi nimum.

11B-9
9/20/65

Init. Date/Time

 

 

 

 

 
Approved byxh;ffi

) ‘,:i ; : 'f_‘T; o
s 11c-1
- 9/20/65

 

11C GRAPHITE SAMPLING

At times to be specified, a graphite sample will be removed from

the reactor core through the 2 1/2 inch opening provided for this purpose.

This section gives the procedure forpreparing the system for this operation.
1 DETAILS OF THE PREPARATION FOR GRAPHITE SAMPLING ARE AS FOLLOWS.

Init. Date/Time

 

 

 

 

 

 

 

 

 

1.1 Bhut down the reactor as described in Section
10A.

1.2 Prepare for opening the shield by Section 11B
through Step 1.9.6.

1.3 Remove the standpipe cover plate and plug
under it. While this is in progress, proceed.
with Step 1.4, 1.5, and 1.6 of this section.

(SER)

1.4 Check that V-918A is closed.

1.5 With HP and IH coverage, remove the blank
flanges from line 918 and install the spool
piece. Gas masks are required for this
operation.

(SER and ST)
1.6 Open V-918A and 918B.
(HB and ST)

1.7 After the special work plug has been put in
place and the purge gas line connected, start
the purge gas flow and the standpipe evacu-
ating blower at about the same time.

1.8 Maintain the purge on the standpipe through-
out the sampling operation.

1.9 When the sampling is complete, allow the

purge to continue 1/2 hour after all opera-
tions inside the special work shield have

been complete.

 

(HB and ST)
 

Approved ?yfiffi; /%Z;é;bffiMfihg

(SER)

1.10 Stop the purge and standpipe evacuating
blower, and close V-918B.

1.11 Close V-918A and with HP and IH coverage
remove the spoclpiece in L-918 and blank
off the openings. Gas masks are required
for this operaticn.

1.12 Remove the special work shield, replace the
plug and the standpipe cover plate, and leak
test by the procedure of Section LE.

1ic-2
9/20/65

Init. Date/Time

 

 

 

 
Approved by -~

X-3582
(7-64)

   

~@wx'fifiw7 11D=1
11D ROUMINE INSPECTION AND TESTING OF EQUIPMENT 8}55%5

Periodically all pressure containing equipment will be inspected and tested

to insure the safety of personnel, prevent spread of contamination, prevent

damage to equipment, and reduce the number of unnecessary shut downs.

1.

PROCESS SYSTEMS

The process systems will be tested by gas pressurizing to €5 psig

at temperature orf 1200°F as outlined in Operating Procedure, Section
Sit,

AUXILIARY SYSTEMS

All systems and components will be hydrostatically tested where
safety or equipment integrity requires such a test. The requirements
of Section VIII of the ASBME Unfired Pressure Vessel Code will be
adhered to. ©See Table 1. Commercial gas equipment will be tested

or returned to the supplier for testing by procedures governed by

plant policy and 1.C.C. No. 73.34 J.

PRESSURE RELIEF VALVES

Table 2 lists all pressure relief valves that are protective devices,
the normal setting, test limits and frequency of testing. Valves
affecting personnel safety will be tested annually and valves

protecting only equipment will be tested biannually.

RUPTURE DISCO

The rupture discs in the MSRE are tabulated in Table 3. Unless

frequent pressure fluctuations are observed which might affect the
accuracy of the discs, all rupture discs will be changed after every
two years of operation.

R, C. and D, T. C. CONTAINMENT VESSELS

The Reactor Cell and brain Tank Cell were hydrostatically tested

upon completion to 48 psig and pneumatically tested to 20 psig.
Approved by'ffifi%j%x!ffii,'%méfli. | 11D~-2
v 8/5/65

With equipment now installed, it is impossible to hudrostatically

test the cells again. However, the cell leak rate (at a -2 psig

pressure differential) is monitored continuously during operation,
and the cells will be tested at 20 psig after each time they are
opened. The vapor condensing system will be pneumatically tested
along with the reactor and drain tank cells.
6. SECONDARY CONTAINMENT VESSELS
All small secondary containment vessels which are isolated from the
main cells will be tested about every two years with sa pneumatié test to 1.25

times the design pressure, see containment vessels, Table b,
 

  

Approved by,

Table 1

ROUTINE PRESSURE TEST OF EQUIPMENT

11-D-3

8/5/65

 

 

 

 

EQUIPMENT é SYSTEM DESIGN TEST AND INSPECTION
! Press. Temp. Type Press. Freq.

Air Compressor 1,2,3 %Inst. Air 100 100 iHydro 150! Biannual
Air Receiver 1,2,3 iInst. Air 100 100 {Hydro} 150 Biannual
Air Dryer, 1,2 iInst. Air 100 100 {Hydro 1501 Biannual
Diesel #5 Air Comp. & Tenk |Flectrical 250 100 |Hydro| 375} Biannual
Helium Trailer gCover Gas 2400 80 {Hydroy 3600| 5 years
Helium Cylinders, emergency §Cover Gas 2400 80 Hydrot! 3600| 5 years
Helium Dryer.: iCover Gas 400 70 |Pneu. 500 | Biannual
Helium O, Remover Cover Gas %00 | 1000 {Pneu.| 700| Annual
He Storage Cover Gas 500 80 |Pneu.! 310| Biannual
0il Tank 1,2 Tube 0il 75 200 |Pneu. 65{ Biannual
Surge Tank Water 50 120 |Hydro 85| Biannual
Treated Water Cooler Water 50 120 |Hydro 85| Biannual
Feed Water Tank 1,2 Heat Removal | 50 | 208 |Pneu.| 31| Biannual
Drain Tank Condenser 1,2 Heat Removal 50 % 298 |Pneu. 31| Biannual
Steam Domes 1,2 Heat Removal 25 % 2698 |Pneu. 31t Biannual
N, Cylinders Inst. Air 2400 ¢ 80 Hydro| 3600| 5 years

 

 

 

 

 

 

 
iy
oF

 

 

 

 

 

Approved by 'y ST Sl 11-D-4
1ABLE ¥ PRESSURE RELIEF VALVES TABULATION 8/5/65 s
P. R. V.
Valve No. Setting Limits 'Frequency
INST, AIR SYSTEM
9110 Q0 + 3 ps_i Annual
9120 90 + 3 psi Annual '
Rec #1 90 + 3 Annual " .
Rec #2 90 +3 Annual
9006 A 90 +3 Biannual *
9006 B 90 + 3 Bianmial
9005-1 30 + 2 Biannual .
9002-1 40 +2 Biannual
9002-2 25 + 2 Biannual
9001-1 30 +2 Biannual
9007-1 30 + 2 Biannual
90072 4o +2 Biannual
9008-1 25 + 2 Biannual
9009~1 Lo + 2 Biannual .
9010-1 40 +2 Biannual
9010=-2 | 25 + 2 Biannmual .
9011-1 25 + 2 Biannual
g0l1ll1l-2 25 + 2 Biannual
9011-3 Lo + 2 Biannual
9011-4 25 + 2 Biannual *
DIESEL #5 AIR SYSTEM
Rec v 275 + 8 Biannual
COMPONENT AIR SYSTEM
CCh-1 12 + 2 Annual
CCP-2 12 ' + Annual
CCP=-3 10 + 2 Annual *

nX.
»*

/ Table 2 -Page 2

Approved by’ffi{);w/fl/g Y | 11-D-5
; 8/5/65

 

P. R. V. _ Test
Valve No. setting Limits Frequency

 

COVER GAS SYSTEM

 

‘ 508 Lo + 2 Biannual
COOLING WATER SYSTEM

| 837 100 +3 Biannual

. 841 100 +3 Biannual

8L6 100 + 3 Biannual

8L7 100 3 Biannual

b |
!
»

aav
L e B

- el
Approved by A 11-D -6

 

 

 

8/5/65
TABLE 3  MSRE RUPTURE DISC TABULATION
Inspection
Location Rating | Op. Press Change Freq.

 

VENTILLATLON SYSTEM
L 980-3" 20 psig 7 -2 psig D years
L, 980-10" 20 psig -2 psig 2 years

COVER GAp SYSTEM

L 508 50 40 2 years
L 507 350 250 2 years
L 506 | 350 250 2 years

COOLING WATER .
L 845 18 10.5 1 year

L 8uk 18 12 1 year

 

 

 

 

 

 
¥

 

 

 

Approved by 11-D-7
8/5/65
. TABIE 4 CONTATINMENT TANKS
DESTGN TEST
TANK TOCATION PRESS TEMP TYPE PRESS FREQ.
Cont. Enclos. 1 Sp. Eq. Room | Lo 80 Pneu. 50 |Biannual
" " 2 Sp. Eg. Room Lo 150 Pneu. 50 Biannual
" " 3 No. E. S. A. Lo 80 Pneu. 50 Biannual
. " " L No. E. S. A, Lo 80 Pneu. 50 Biannual
" " 5 No. E. S. A. Lo 80 Pneu. 50 Biannual’
" " 6 No. E. S. A. 4o 80 Pneu. 50 Biannual
. Vv T-1 So. of Bldg Lo Pneu. £0 Annually
Vv T-2 So. of Bldg Lo Pneu. 20 Annually
Sampler Enricher High Bay Lo 80 Pneu. 50 Annually
’ Sampler Enricher
V. Box High Bay 40 80 Pneu. 50 Annually

 

 

 

 

 

 

 

 

 
.
 

 

Approved by TV I pirm, 12-1
. 10 / 13 /6 5

SECTION 12
ROUTINE OBSERVATIONS

 

The most important functions of the operating crew are Lo carry
out the prescribed program in a logical manner and record adeguate
data.

The acquisition of data can be accomplished in a number of differ-
ent ways; however, with an operation such as the MSRE, which is manned
on all three shifts, it is necessary to standardize this as much as

possible. The following describes the method to be usged at the MSRE.
- v
o*

3/

 

Approved by ) T asuesy, 12A-1

10/13/65
12A LOGS

CONTROL ROOM LOG BOOK

 

The control room log book is a journal in which the time and
nature of all operations are recorded. This log provides a record
of operations for evaluation of the performance of the reactor, for
keeping operating personnel mutually informed, and particularly for
providing each oncoming shift (and day supervision) with a record of
what the previous shifts have done.

The log 1s ncrmally kept by a control room technician; however,
each member of the operating crew must be sure that a record of all
significant operations which he performs or observes is adequately
entered in the log. Each entry should begin with the time the
operation tcok place, and should be initialed.

The log must be a complete record of all significant operations,
but be as free as possible of unnecessary details. It is better to
put too much in the log than to leave out details which may later
prove to be significant. Operations personnel are responsible for
adequately recording all activities that occur on each shift. This
includes activities of non-operating personnel.

At the start of each shift, enter in the log the personnel
assigrments for the shift, and the reactor conditions at shift
change. Enter the date and shift at the top of each page. This
makes it convenient to find who worked a given shift and what work
was in progress. Conclude the shift entries with a "status,” which
should include a summary of the reactor operating conditions for
the previous 8 hours, a list of all important changes in operations,
and sufficient information about operations in progress to enable .
the next shift to take over smoothly.

New log books are kept in the operations file cabinet. DHince
the page numbering continues from log to log, care should be taken
that the proper new log book is selected. Completed logs are also
filed in the operations office. A carbon copy is made for use by

non-operating personnel and is filed in the operations office.
 

*E%f o 124-2
10/13/65

Approved byzéfifififq

 

Xerox copies are provided for the coordinstor and the department .
head.
The shift supervisor is responsible for reviewing the log at
the end of his shift to be certain that all significant occurrences
are adequately recorded.

1.1 Items which should be included in the log are:

 

Equipment started or stopped.

Valves opened or closed.

Switches or breakers opened or closed.

Procedures or parts of procedures started, worked on, or
completed. ‘
Changes in settings of controls or valves.

Major changes in settings of heater controllers.
Annunciations, and action taken.

Abnormal conditions or malfunctioning equipment found.
Purpose of a given series of operations, unless obvious Or
routine.

Observations, interpretations, and conclusions drawn from
operating results.

Samples taken.

Significant maintenance and other non-operational jobs done.

1.2 Items which need not be recorded in this log are: .

 

Those which are recorded elsewhere except for especially
important items which may be repeated for emphasis.

Details of operations covered by a written procedure or
check list. Any exception to the procedure should be noted
as well as time referencesand results if of significance.

2 CONTROL ROOM AND BUILDING LOGS

A1l pertinent temperatures, flows, pressures, etc., not recorded

 

elsewhere are recorded on the control room and building logs. When
the computer is not in operation;. it is necessary to manually record
some items. normally recorded by the computer. These extra items

are on the control room log. Therefore, 2 control room log forms

are provided. Since the building log does not change, only one
Approved by Efigf;fiAaéigy%m¢k1 ~ 124-3
Y 10/13/65

. building log form is required.

12A-2A Control Room Log (Computer in Operation), 12A-2B

Control Room Log (Computer not in Operation), 12A-3 Building

Log.

Where possible the normal reading for each item is given at
the head of each data column. The person initiating a new log
should correct iV to agree with the master log, located in "Master
Forms" file drawer.

. Each person taking a log must report any abnormal conditions
to the shift supervisor promptly. In addition, he must be alert
for signs of trouble or malfunctioning equipment as he makes the
rounds of the area.

Completed log sheets are placed in data holder in the control
room and are subsequently filed in the operations office by day
personnel.

3 LEAK-DETECTOR 1LOG

Since the operation of the leak-detector system is somewhat

 

independent of the rest of the reactor, operations done on this
system are recorded in a seperate log.
It 1s particularly important to note the status of any leak-
hunting cperations and all valves that are closed at the end of
. each shift.
L THERMOCOUPLE TABULATION LOG (12A-k4)

There are some 900 thermocouples and 700 temperature readout

 

locations at the MSRE. Since the readout of any thermocouple (except
for 120 on the coolant radiator) can be easily changed at the patch
panel, a thermocouple tabulation log will be maintained. In the
"Thermocouple to Instrument” log, the thermocouples are lisbed
numerically along with a brief description of their locations in

the system. Columns are provided to enter the "readout"” location

of each thermocouple. When the "readout” of any thermocouple is
changed, this fact should be entered along with the date, time, and

. initial of the person making the entry.
Approved by25;?5§$/572%77van< 12A-4

10/13/65

The "Instrument to Thermocouple" log lists the "readout” instru- .
ments and "readout” points in numerical order along with the location
of the instrument in the building. Columns are provided for indi-
cating which thermocouple is attached to each point. When a change
is made on the input to any instrument, this fact should be entered
along with the date, time, and initial of the person making the

entry. Thus it is possible to determine where any thermocouple was

 

recorded at any time or what thermocouple was recorded on any instru-~ .
ment.

5 HEATER CONTROLLER SETTINGS LOG (12A-5) |

The heater controller settings will be recorded periodically .

on the building log; however, a chronological history of the settings
will be helpful to operations. A log is available at the heater
control area with columns for entering date, time and controller
setting. As these are strictly an operational guide, they may be
discarded after use.
6 FLANGE LOG
A history of all reactor system flanges monitored by the leak

 

detector system will be kept jointly by operations and maintenance.
Pertinent information on closing of these flanges such as torque
and leak rates will be kept in this log.
In the back of this log will be kept a list of any fittings
which have been opened which require helium leak testing. This
list will be in the form of a punch list requesting the leak checks .
of a particular fitting. These punch lists are accumulated and all
leak tested by maintenance during shutdown. .
Ji SAMPLE LOGS
A record of all samples taken from all systems will be kept

 

in the sample logs in the operations office. Entries will be made
in these logs both when the sample is taken and when the analysis
result is obtained. A sample number will be assigned according to
the last previous record in the sample log. The sample log will
also contain information on the allowable limits for analysis of

desired (or undesirable) contents.
   

Approved byf4277‘”” ~ 12A-5

10/13/65

8 DIESEL LOG

This log is maintained in the switch room, and entries will be

 

made for any operations involving the diesel generators.
 

 

 

Approved bdeZEZ%é%;éggm 12A~2A
| 8/6/65
. 12A-24
CONTROL, ROOM LOG
‘Computer in Operaticn)
CONSCLE
Record every 4 hours etfarting at 0830 unless obtherwise indicated.
By-Pass
RADIATOR DOOR RADIATOR Duect
* POSITION Damper
CGUTLET INLEY AP AP Demand |Position
. Init. Time Z21-0D-A Zi-1ID-A PETADRAD PATAD2AL ZL~-AD-2

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Time

. Date Started

REACTCR CUTLE®R
Temperature
Demand
XTINARC A2

Temperature

T 1G0-

1200°F £ 50°

 

. TX-3839
(10-65)

1200°F + 50°F

COMP .
Ammeter. Range
#1 il

ION C

Rng Seal
Light
1

 

 
Approved by fi@/«m 124-24
| 8/6/65

Record every U4 hours starting at 0830 unless otherwise indicated.

Regulating | Servo Servo CONTIRCGL ROD
Flux POSTTTON*
Flux fod Mode Channel Total

Time Demand Position Light| OSelector 1
25 - 75% #1 or #2

 

¥
Read coarse position indicator to nearest printed number below pointer.
Add fine reading to this and record the sum.

Ioad | Safety | FISSTON CHAMBER | FISSIGN CHAMEER

Scram Channel 1
e
Lights| Lights |, ... Count osition Count Chamber
Tnit.| Time On On Rate Rate Selecte

None None 104 Fd* 1040pe®

 

 

*
If at low power counts may be <10* cps.

Date Started

 
Approved by - 12A-24
’ 8/6/65
MATN CONTROL BOARD

Record every 8 hours starting at 0830 unless otherwise indicated.

Containment |Stack| Standby | Comp. Cell oT-2
otack Flow Fan |Stack Fan|Coolant CCP AP Pressurel Pregssure
Init.1Time T 8T On t On | PDIiC PI-RCA | PIC~510A

>60% 41 On #1 or #2 8 psi |-2 psig | T psig

 

 

 

Coolant‘ Prime Bypass
0T-2 0il Stand-by Damper Annulus {Radiator
Level Pump I 0il Pump Position Rlowers Blowers
Tnit.| Time |LI-0T2 Cn COP | Time % On On*
>50 |#1 or #2 <10 #0 & #h
sec

 

 

 

 

-
!
o

 

 

 

 

 

 

 

 

 

 

 

*
Depending upon operation one or both radiator blowers may be on or off.

g RADITATOR TEMPERATURE HELTUM W
tack

Flow Outlet Tnlet From CP To CP
Init. {Time | FT-AD-3A | TI-AD3-8A | TI-AD1-1A FI-526C FIC-512A

Ambient >, 048 /m to .654/m

 

 

Date Started | -3-
Approved by Z;affi%fié%%Zwa« éiéjéfi
/65

Record every 8 hours except as otherwise indicated.

     
   
     

      
   
  

Radiator

 
    
  

  
  
   

0CT-2

   
   

    

      

    

0 T0 CP Temperatire
Shield Bearings LIGEY Difference
Init. | Time FT 754 FI 753 (on or OFF) TdT-201-A

   

 

       
  
     
     

6 to 9 gpm Ooff

3to5 gpm

 

Radlator
Qutlet
Temperature
TI-202 A2

      

 
    

   

Init. | Time Speed

1750 rpm

 

     

S1000°F

 

 

 

 

 

 

cp CcP Coolant 20T
Ievel Level Radlator Flow Pressure
IR 595C Selector Power FR-201 { PR 511D
Tnit.| Time (Red) S~39 XpR-201 % Scale| (Green)
56 to 2% { 2, 3, or L 80 5 psig

 

 

 

 

 

 

 

 

 

 

 

 

 

Date Started -l
s

st

Approved by»g25§§§f§%§z29&¢______

 

 

 

12A-2A
8/6/65
Record every 8 hours except as ctherwise indicated.
REACTOR TEMPERATURE
CDT Reactor
Weight Power Red Pen Green Pen
: WR-CDT-C1 | RR-8100 Outlet Inlet
Init. | Time (Red)* (Watts) TR-100-A5 TR-102-5C
<8% 1200°F + 50° | 1200°F # 50°

 

 

 

 

 

 

 

 

 

 

 

*
Tf ccolant drain tank is full, WR~CDT should read ~ 55%.

 

Init. Time

Date Started

   

Salt
36

o Salt Salt

2 kw hg

 

FUREL PUMP

No Salt SFEED

19 amp 120C + 50 rpm

 
 

Approved by Adfiéfiygfi:?%kdn
ko,

Record every 8 hours except when otherwise indicated.

TP
Pregsure
PRC-522A

Green

<
Ja

FP
Ievel
LR~593C

Re

-6

FP

Tevel S

Selector

g-

cxr

p-2
team Dome
Ievel
LTC-807A

12A-2A
8/6,/65

 

 

 

 

 

 

 

 

 

FD-2 FD-2 OIL TO FP
Pressure Weight
| PR-574B | wR-FD-p¢ | DEARINGS) SHIELD
Init. } Time | (Green) (Red)* 1 FT-7038 | FI-70kA
, 5 psig <B% =5/gpm | 6-9/gpm
A j
—t Y

 

 

 

 

 

 

% ,
If FDT #2 is full, WR-FD-2 should read ~ 824,

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

e . FRT FFT
OCT #1 HELIUM FIOW Pressure Welght
Iight To FP From FP FR-5765 WR-FFT-C
Init, | Time 1{On or Off) | FI-5168 | FI-5248 | (green) (Reg)#
) 24:2 - 216
Crf ) 4/m T.O4 £/m 5 psig 70%
|
i
* — . o
If flush salt is being used, WR-FFT should read <8%.
Date Started -6~

 
-

Appreved byééféi?fifi?%;zzwfnk | 12A-2h

8/6/65

Record every 8 hours except when otherwisze indicated,

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

’.
R TVE
SIRND T HETLIUM
FUEL OZL | OT-1 ’\T—l UL PUME SEATERS
PUMFE EVET FRESSF b b Time FREZCURE
Irnit. Time Qo Tl i=1 \I'ijfé 7 regd., Pi-500-A
- 4o e . . 150 to
#1 or #2 >50) / peig <0 sz | o227 Y
' 250 prig
v I
! ;
i

 

. ri~l Fom RS FaT e
STEAM LOME] FRESSURE | WEIGD PRESSURE WETUST [ ICC POWER
LEVEL ' 93-535,5 WR~F0L -0 PR 6385 WR-#3T | RR~8200
Init. Time|LI:-806-A {oreen) (Red ) (Watts)

 

 

 

5 paig <8% iote 5 paig | <5%

 

 

~ g

 

 

 

 

 

 

 

 

 

 

 

;_.1
i
3
e
I_.I
s
o
!—h
-
l_,...
(n-d
=
=y
i
g
e
i1
i
b
s
l—\J
;—1
i.
o
h
o
&
£
i
N
1
NI
O
==
2

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

. . R . -
TWE S S 5-53
init. |Time % G e 00 BC 00 GCR-3 AL Pusition
) 1 or 2L or = L& 201 &2 #1 ] 0a 1 or 2 {Oper. Comp
-

- Date Started -

-]

 

 

 
 

AmmmmdeéEEZQéééfi&vk‘

Observe Temperature Recorders every 4 hours starting at 0830 and

record any abncrmal temperatures,

12A-24
8/6/65

 

 

 

\ TR TR

Init. Time 3100 3500 Record Unusual Temperatures
>950 >950
<1300 | <1300

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

AUXTLIARY CONTROL ROOM

Record every 8 hours starting at 0830 unless otherwise indicated.

 

 

OCT-1 MCB AP 0CT-2 Filter Waste Tank

Level Level AP Level
Init. | Time | LI-524-C PAI-556-4 LI-526-A | PAI-927-B2 LI-WI-A

<50% <50% <L" vater <135"

 

<2 psi

 

 

 

 

 

 

 

 

 

 

 

 

Date Started

 

 

 

 
»

Approved bl%qv 12A-2A
8/6/65

Record every 8 hours unless otherwise indicated:

 

 

 

 

 

 

| - Hi-Bay VOLIMETERS
- Pregsure
Tnit. | Time PT-HB-A TVA Bus 3 Bus b Bus 5
| 0.1 Htg 0.3 4oo-ko | hoo-bko | koo-kbo | Loo-Lbo
=

 

— e—

 

 

 

 

 

 

 

 

 

 

 

 

SAFETY
Reactor Outlet
Te rature
Time TI-100-A1 TT-100-A2 TI-100-A3

 

1200°F = 50° 1200°F * 50° 1200°F + 50°

 

 

 

 

 

 

SAFETY 5
Radiator Outlet Coclant Salt
Temperature Flow
Init. {Time TT-202-A TT-202-B TI-202-C  |FI-201-A |FI-201-3
1200°F # 50° ]1200°F * 50°| 1200°F £ 50° | ~ 80% ~ 80%

 

 

 

 

 

 

 

 

 

 

 

 

Date Started _ -9~
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Approved by / 12A=2A
8/6/65
Record every 8 hours unless otherwise indicated:
SAFPETY
Tuel Pregsure QFT Level
Tnit. | Time | PI-592 | PI-589 | LI-599-B | LI-600-B
5 psig | 5 psig <10% <10%
WIDE RANGE COUNTING CHANNEL #1
Chamber Oper-Calib
Power Log CR Position Sw. PHS Sw.
Init. }Time RXI-NCC-1A3 |RI-NCC-1A1 { RI-NCC-1A4 | Setting Setting
10% cps* 0.3 174
* 4
If at low power, counts may be <lO™ cps.
WIDE RANGE COUNTING CHANNEL #2
Chamber Oper-Calib
Power Log CR Position oW PHS Swe.
Init. { Time RXI-NCC-2A3 |RI-NCC-2A1 | RI-NCC-2AL | Setting Setting
4* ‘
10 0.3 17hL
,*— .
If at low power, counts may be <10* cps.
Date Started -10-

 

¢,
? ¥

Approved by Ly pe A 12A~2A
| 8/6/65

Record every 8 hours starting at 0830 unless otherwise indicated,

POWER SUPPLY
a1 .
Vo S 0

31-33} ~ 4 | 31-33 | ~ 7.5]

 

  
     
       

CLITCH CURRENT
ROD #1

  

SAFETY CHANNETS
ux’ ux
RM-NSC-2A71| RM-NSC-

% %

  

ux

  
   
  

 
   
  

u
Cur.

         

   

BC CA
50~60 [50-60{50-60

   
 
 

   
 
 

   

   

~ 165

   
  
      
   
  
  

 

  
 
  
 
    
   
 

Nal
o

 

COAMMETERS
Channel #1 [Charnel

     
 
  
 
    

od

   
   

 

Cltech
Cur.

Clteh
AB [Cur.

     

CA |AB
50~
60"

BC
50=
60

RINIZ 1A1 [RINIC 241

   
   

   
   

Init.{ Time| BC

 
 

   

50-60}50-60 ~1T5

  

 

Date Started -11-

 

 
Approved byé??22/;7§£3/»Qfl\,~ 12A-2A
Y | 8/6/65

On the first log of each shift, 1list any nuclear modules which

have the ncrmal and the latch 1ight on. Then push reset

button and note that latch light clears.

-1600 1600-2400 2400-0800
Normal + Cleared Normal + Cleared Normal + Cleared

tateh Tt. onl P50 1aten Tt. On| "PSR ligteh Lt. On| NPSD

t.] Time Reget Reget Reget

 

Record every 8 hours starting at 083C unless otherwise indicated. Push
the neutralize button and zero the instrument before readiang. Be sure
tc read scale for range selected.

 

 

 

 

‘ RM 827 Alarm
RM-82T7A RM-8278 RM-827C Set Point
init.|Time | Range |Reading| Range |Reading| Range [Reading A B | C
A1 (=12 ra-12 1 12 20 20 20
JXlOL 3x10 3x10 mr /hr|me/br|nr/hr

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

i §
i |

 

 

Record every 8 hours starting at 0830 unless otherwise indicated,

RM_6000%
RM 6010 | Pos. 1 Pog. 2 Posg. Pos. Pos . Pcs,
Tnit. {Time |Range |Rdg |Range |Rdg |Range |Rdg |Range |Rdg |Range |Rdg |Range {Rdg | Range [Rdg

¥

 

L i

¥
NCTE: Read each on lowest possible range. ©OSwitch to zero and change to next
position. Do not ge beiow 3 x 10712,

Date Started ' ~le-
.l

Init.

Approved byzz;Ef§5f%2%%z:&um«

12A-2A
8/6/65

Record every 8 hours starting at 0830 unless otherwise indicated.

Check and reset calibration of all @-1916 instruments at
(0.25 to 0.35) mr/hr before reading.

 
  

   

Time

 

  

<.5

 

<.5

 

 

RM-596A | RM-596B |RM-596C

           

<.5

  

RM-500D |RM-55TA |RM-55T7B

<.5

 

 

 

 

 

Tnit. | Time RM-528¢C |RM-528B |RM-565B | RM-565C | Check Q-1916 B%i%A Efig
_ | Set Points (sec).—
<.5 <.5 10 - 20 mr/hr

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

RMSLC
. axri . axm
(cPM) [Point| (CPM) | (CPM) [Point

RMS1A RMS1B

(cPM)| Point| (CPM)

e
Init|Time| (CPM)

<1000 <B0o0 *

<1000 <800 * <1000 <B00 *

 

¥Alarm should be set at Readihg X2 but skould be >150 and <LOOC.

Date Started -13-
Approved by Mm o 1zA-24
4 1 8/6/65

List Jumper inserted in Jumper Board at start of each shift and have
Shift Supervisor approve list.

 

1600~ Shift 2400-0800 Shift

- t
umper} Circuit No. |Jumper | Circuit No.| Jumper | Circuit No.

         

 

List Red Lights which are on on Jumper Board

 

Light] Circuit No. [Light ]| Circuit No.} Light ]| Circuit No.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Initi&l.
Time

S. S.
Approval

 

 

 

 

 

 

-Time

 

Date Started

 

 
S _t".‘

Se .

-
»”

my b B gt

e?

Approved byygé??i&颧%yfixcfll 124-2A

8/6/65

List Annunciater lights that are on ia Main Control Roum and Auxiliary
Control Room at start of each shift and have Shift Supsrviscr approves

1ist. (Check Rochesters, ldights above all panels, Radiation Monitors,
ete.) Also list anaunciator relays which have been removed.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

0800-1600 Shift 1600-2400 Shift |2400-08C0 Shift
_Annunciator Anquneistcry Anaunciator
Initial
Time
3. 8,
Approval
| Time ]
- Date Started ' -15-

 

 
Approved byl46f§€;/%§%%zyuau

Check the following at approximate time indicated.

124-24
8/6/65

 

Normal

0930

1230

1730

2030} 0130] OL30

 

 

All Charts Inking

 

Time All Charts

 

MCR Ann. ILamp Check

 

 

ACR Ann. Tamp Check

 

%Sampler Permissive Switch
.__Record On or Off

Off

 

EAll Computer Typewriters

 

 

)__Printing Properly

 

 

‘Record Computer Time

i

 

Record Clock Time

Initial

 

e ———

 

 

Date Started

 

 

 

 

 

e

u.___. 44,4‘34 s
ot

Approved byfiéf?%42%?aamfl _ 12A-2A

8/6/65
. TI-3200
Record once per shift.

Point T ormal Foint

2
6

b
48

 

Recorded by

- Mme

 

' Date Started -17-
4

I
,l

Approved by W #BN\__ 12A-2B
| 4 |

10/7/65

12A-2B
~ CONTROL ROOM LOG

(Computer Not in Operation)

CONSOLE
Record every 2 hours starting at 0830 unless otherwise indicated.

RADIATOR DOCR RADTATOR
P ON
OUTLET ¢ INLET OP AP Demand
t. Time Z1-0D-A Z1-ID-A PAIADzZAZ PAIADZAL

 

Date Started ' . - -1-

 

TX-3837
(10-65)
12A=28
1C6/7/65

Approved by W

Record every 2 hours starting at 0830 unless otherwise indicated.

REACTOR QUILET COMP. ION CHAMBER
Temperature Rng Se
Temperature Demand Ammeter e gkt
Time oI 100~ XTINARC A2 1 2 1

12007 F £ 50 1200 F £ 50°F

 

Dete Started k -2-

 
Approved by Wé%/flfi/\ 124-23

10/7/€5

Record every 2 hours starting at 0830 unless otherwise indicated.

Servo CONTROL, ROD
Reguiating} Servo Flux POSITION*
Flux Rod. Mode | Channel Tota.L
t. 1 Time | Demand| Poeltion t| Selector

2h = B #1 or #2

{

 

*¥Read coarse position indicator to nearest printed number below pointer.
Add fine reading to this and record the sum.

Date Started | -3

 
Approved by ML 12A-2B

10/7/65

Record every 2 hours starting at 0830 unless otherwise indicated.

CONTROL ROD Load | Safety FISSION CHAMBER
CLUTCH CURRENT Scram | Channel
) Iights| Lights | Position } Count
Init. | Time |#1 #2 #3 On On Rate

g S5a {~l75a| ~L175a) None None 10% cps¥

 

*If at low power, counts may be <iC¥ cps.

Date Started -l

 
>

; { ;
Approved by /Wy }fip-v\ 124A-28
V </ ~

10/7/65

Record every 2 hours starting at 0830 unless otherwise indicated.

FISSION CHAMBER
2
Pogition Count Chanber

 

Init. Rate Selected

10% cpe¥*

 

*If at low power, counts may be <10% cps.

Date Started -5
Approved UpgZ

MAIN CONTROL BOARD
Record. every U4 hours starting at 0830 unless otherwise indicated.

i

!
i

    

Init. ™Mme :

  

Stack Flow
¥1 81

AN

o

Contaimment [Stack! Standby
Fan |Stack Fan|Coolant

Punmp On

     
 

       
     

On

Lighv

On

 
     

Comp »

  

2t 8

 

or

     
 

CCrk AP

 

      
     

    

  

gl

Cell
Pressure |Pregsure,
PDIC 960A] PI-RCA |PIC-5104;

-2

12A-28
10/7/65

      

 

S

     

    
    

 

or-2z

el ;

 

Coolant Prime Goolant
f On-2 Oiy Standby Bypass | Amnulus |Radiator| Otack !
: Level Pump ;Oil.Pump ! Deaper Rlowers |Blowers Flow
fInit.; TMre (LI-012 On ‘ CcoP iPosition On On - FIAD3A
i b >50% B or 42 | | #2  #h o *
! e ¥ | :
, 4
l |
- XX, | XX
|
v i EX i XX
i o dxe i | xx |

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

*¥Depending on

Date Started

operation, one

or both radiastor blowers

 

may be on or off.

-

 
¥

Approved by:;gi?fijég/é%%%%?"“1n”\§_

Record every U hours except as otherwise indicated.

RADIATOR TEMPERATURE EELTIM FLOW
OUTLET INLFF | From CP To CP
TL ADR-CA | TIL ADL-1A | FI 526C . FIC 5124

>.0g/m  |.55 to .654/m

Radiator

 OIL FLOW TO GP | OCT-2 Temperature
Shield LIGES Difference
FL 754 FL 753 | (On or Off)| TAI-201-A

6 o 3 %0 0ff

124-25
10/7/65

 

 

Date Started

 
Approved by m oy 12A-~2B

Record every U hours except as cotherwise indicated. .

| Radiator

Outlet COOLANT PUMP
Temperature 5 Watts
| Time | TI-202 A2 Speed +] No Salt |Salt [No

i
'

>1000 F L 211 2 kw

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

- g ?
ar - GP ‘_ ooz
- Level Level Rediator|{ Coolant| Pressure
IR 595C Selector Power Flow PR 511D
Init. | Time (Red) S~39 XpR-20L | FR-20L | (Green)
e ety = =t ok -
' 56 to T72% §2, 3, or 4 800 gpm| 5 psig
XX
XX |
- .
- !
{ | XX !
T " =

 

 

 

 

 

Date Started ~8.-
P

Approved bM/ Lo 12A-2B
\/

10/7/65

Record every U4 hours except as otherwise indicated.

 

 

 

 

 

 

 

 

 

 

 

| CDF | Linear REACTOR TEMPERATURE
Welght Power ~Red. Pen Green Pen

| WR-CDT-CL | RR-8100 Outlet Inlet

Init. | Time (Red )* {Watts) TR~-100-A5 TR-102-5C
6% | 1200°F £ 50°F | 1200 F % 50°F
fi

! XX

|

! XX

.i

| xx

 

 

 

 

 

 

 

(=
*¥If coolant drain bank is full, WR-CDI-Cl should read ~ 55%.

 

 

FUEL PUMP
AMPS
Time Salt No Salt No Salt

6 2 kw L i

 

 

Date Started -9~
Approved by fi){@w\ lB/A/;?’fl%
L 10/7/65

%

e
v
S

e
=

Recdf&~%?ery 4 hours except when otherwise indicated.

 

FP FP FP FD-2
Pressure level Level Steam Dome
PRC 522A | LR-5930 Selector Level
Init. | Time | {Green) (Red) 5-36 LIC-807A

 

—

i 5 psig 56 ~ 65% cor 3

 

+

 

 

 

 

S22

 

 

 

e
g

 

 

 

 

 

 

 

 

 

 

FD-2 FD-2
Pressure Welght OLL TO FP
PR-5T4B WR-FD-2C
(3reen) (Red )* FI-TO34 FL-TOUA

s <B - 6-

XX XX
¥If FD? No. 2 is full, WR-FD-2C should read ~ 82%.

 

Daue Sharted | =10-
ok

Approved by M LZA-2F
S 1047/65

Record every 4 hours exceph when otherwise indicated.

€4 Ex ca

00T Moo L ___HFLIUM FLOW _| PRESSURE

LIGET Do PR-874.5
Time | {On cr Off) FI1-516-B FI-52%-B| {trecn)

£

ofsf 202 = 2664/m | >Chg/n s

FI2 : Zelivm Prime
Welght | Jusl OLL; OZ-1 Q-1 Headers [Standby
WR FFL-C Pump Level § Pressure} Prezsure (011 Pump
Time { {Red)* On LI-07-1] PI-513-A| PI-500-A |FOP No.

70 #1 ox #2| >50% 7 peig | 150 %o
250 pg

XX XX

 

*¥If flush salt is in the reactor; WR-FFU.( should he <B8%.

Date Started

 
Approved by MM | - 12A-2B

10/7/65

Record every 4 hours except when otherwise indicated.

FD-1 FD-1 ¥FD-1
Steam Dome| Pressure| Weight FST FST Log Powe
OooF . Level PR~572-B| WR-FDL~C| Pressure Weight{ RR-8200
te | Time| LIC-806-A | {Green) {(Red ) PR-608 WR-FST{ (Watts)

1 to

 

Date Started ~12-
Approved by ffi%m 1PA~2
4

10/7/65

Record which are on every 8 hours starting at 0830:

TWP | CTP |TF 5.53
n | On |Ony cCC | RO IDOUC|CCP-3| AC | Position

1 or 2|1 or 2 Te 21L& 2172 | on 1L or 2 r. C

N

 

Observe Temperaturs Recordsrs every 2 hours sbarting st 0830 and record
ary abrormal tempergtires.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

7R TR 7R
Inite | Time | 3100 3500 2600 Record uauvsual temperatures
>950 >050
<L300] <1200
* | |
XX XX XX
XX XX XX
XX XX XK i
XX XX XX
XX, XX XX
_:lfxx b oxx i xx

 

 

 

Date Started -13-

 
>

Approved by~[z;;5;52%23;;<uq¢>\‘ 1%5%72%

 

AUXTIIARY CONTROL ROOM |
Record every 4 hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

 

 

 

 

 

| | oom-1 0GT-2 | Filter | Waste Tank |

g Level MCB AP Level AP Level
Initei Time Ll-524-9 PAT-556-A ILI-526-A PAI-927-B2 L;:Hfi-A

; 509 | <2 pSi 0% <k water | <35 Bz

;fi XX XX XX XX XX

I = X

: i | XX XX
m;mi_xx XX - : XX XX XX

 

 

 

 

 

 

Record every 4 hours unless otherwise indicated.

Hi -Bay VOLTMETERS
Pressure
Init. Time PI-HB-A TVA Bus 3 Bus 4 Bus 5

- &

 

Date Started =1l -
é"«
v el whe

| Z
Approved bY¢€25£f;Z;;:%%%fin»~

-

7 "

1ZA-2B

10/7/65

Record the following every 4 hours unless otherwise indicahed.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Record every 4 hours unless otherwise indicated:

SAFELY
Reactor OQutlet
Temperature
Init.] Time TI~100-A1 TI-100-A2 TT-100-A3
- 0. o o 1. O, B
1200 £ 50°F | 1200 £ 5C°F {1200 + 50°F
XX XK XX
XX | XX XX
XX XX XX E

 

 

 

 

    

  
  

  
 

   
    
 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

el

 

SAFETY
Radiator Outlet Coolant Salt
Temperature | _ Flow
Init.| Time| TI-202-A TL-202-B TL-202-C | FI1-201-A} FI1-201-B
s e e T . e
1200 % 50°F| 1200  50°F] 1200 + 50°F1  ~80% | ~80%
e T - e 2 = #r = «__1
XX 1oxx XX XX XX
§ XX XX XX XX XX
|
_L i XX XX KX XX XX

Date Started

 

-15-

 

 
Approved by M W'\
4

Record every 4 hours unless otherwise indicated.

12A-2R
10/7/65

 

 

 

 

 

 

 

 

 

 

 

 

 

 

E SAFETY
‘fh.‘” Fuel Pressure - O Level
Tiitt. PIL-502 PI-589 11-599-B 1.I-600-~B
% ==
ke psig | 5 psig | <10% <10%
1oxx XX XX
XX XX XX

 

 

 

 

 

 

 

 

Date Started

 

~16-
L)

Approved by % 12A-2B
- . 10/7/65

Record every 8 hours starting at 0830 uniess otherwise indicated.

WIDE RANGE COUNTING CHANNEL. #1

Chamber Oper-Calib
Power Log CR Position Sw. PHS Sw.
Init.| Time| RXI-NCC-LA3 {RI-NCC-1A1] RI-NCC-iAk] Setbting Setting

10% cpg* oR 174

 

*¥If at low power, counts may be <1C% cps.

Record every 8 hours starting abt 0830 unless otherwise indicated.

WIDE RANGE COJNTTNZ CBANNEL #2
Chamter Oper-Calih
Power Log CR Position SWa PHS Sw.
Init. |Time |RXT-NCC-2A3 IRI-NCGI-2A%1 {RI-NCO-2484 | Setting Setting

10% cps* 0. 17h

 

¥If at low power, counbs may be <i0? cps.

Record every 8 hours starting at 0830 ualess otkherwise indicated.

POWER SUPPLY

 

er | Lower
Time Voits Amps - Volts Amps

1-3 ekl 1-

 

Date Started

 
 

Approved by M/m 12A~2F
T V .

10/7/65
Record every 8 hours sbarting at 0830 unless otherwise indicated.

SAFETY CHANNELS R

Flux Flux 3 Flux ’ Clutel:
te [Time |RM-NSC-1A1 | RM-NSC-2A1 |RM-NSC-3AL| 3C CA AR Cuer.

% % % N7-53{47-53 {47-53|135-165

ma, ma, mna ma.

 

 

LITCH CURRENT

 

 

T Rod ¥2 Rod #3
Clutech Clutch
Init. §Time BC CA AR Cure =C CA AB Cuar.

 

|47-53{ 47-53) 47-53] 135-165 f47-53 k7-52 IWT-53) 135-1€5

 

 

 

 

 

 

 

 

ma, me, ma, nia ma, ma e, ms,

 

 

 

 

 

 

 

Record every 4 hours unless otherwlse indicated.

PICOAMMELERS

Cranre 1 Charrnel 7 2
RINLC-1AL RINLZG-24%

 

Date Shtarted ' =18~

y——

) . v
e

v

 

Approved byf;;;a;;;aggfia;%/'?*1/54 12A-2B
v

10/7/65

Every 4 hours list amy nuelear modules which have the normal and the

latch light on.

Then push reset button and note that latch light clears.

0800-1600 1600-2400 2400-0800

Normal -+ ared| Normal + Cleared] Normal -+ Cleared
Latch Lt. When Latch Lt. When Latch Lt. When

t. ] Time

Date Started

On Reset On Reset On Reset

 

-19-

 
12A-23
10/7/65
Record every 4 hours starting at 0830 unless otherwise indicated. Push
the neutralize button and zero the instruments before reading.

i) i
Approved byggf;;;#éflxiqyf;wzfiflfl

RM-82TA RM-827B RM-827¢C RM-827 Alarm
Set Point
TnitJ Time ! Range |Rdg| Range |Rdg| Range |Rdg| A B

C

3 x 10 2 3 x 10 *° x 10 12 20 mr|20 mrl20 mr

 

Record every 8 hours starting at 0830 unless otherwise indicated.

RM 6010 RM 6000%
Pos.,1 Pos.,2

Pos.
Init. Time | Range | Rdg | Range | Rdg

Range | Rdg |Range Rdg

 

¥#Read each on lowest possible range.

Switch to zero and change to next
position. Do not go below 3 x 10 12,

RM 6000%

Pos. L Pos.

Pos. 6
Time Rangé Rdg

Range Rdg Range Rdg

 

*Read cach on lowest possible range.
position. Do not go below 3 x 10712,

Date Started

Switch te zero and change to next

 

_20_
 

Approved by/g§;;?532%/‘aéfi%j?/;mqu\__ 12A-ZB

10/7/65

Record every U4 hours starting at 0830 unless otherwise indicated.
Check and reset calibration of all Q-1916 instruments at (0.25 to $.35)
mr/hr before reading. ‘

Init.{ Time| RM-506A| RM-5963| RM-596C| RM-500D IRM-557A [RM-557H

<s <o <a <e

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Creck all Q 1916| RMSIA,B,C
Init.| Time| RM-528C |RM-52838 |RM-565B |RM-565C Set Points Tnt. Time
TRy = %(gggi——-——“""“**
<2 <eD 10 - 20 mr/hr 21 - |
xx =
_— e
% XX —
| .
E ; : ] —
mfij % ::4:: . e} XX oo}

Record every 8 hours.

RMS1A e 13 . RMSiC
: e . e . arm e oW
(cpM) [ (CPM)} Point] (CPM) | {CPM){Point| (CPM)

<1000 * 1<000 Q0 * <1000 00

(CPM)

\

!

 

*Alarm should be get at Reading X2 but should be >15C and <1L000.

Date Started D
Approved by ~F '1j\’f?[f”fiW\ 1ea-28
- 10/7/65

Iist Jumpers found inserted in Jumper Board at start of each shift and have
Shift Supervisor approve list.

 

i 0800-~1600 Shift 1600-2400 Shift 2400-0800 Shift §

 

Circuit No.j Jumperj Circuit No.} Jumper} Circuit No.| Jumper

 

 

 

 

 

 

 

 

 

 

 

 

e e

-

 

 

 

 

 

List the Red Lights which are on the Jumper Board.

     

     

  

   

      
 
 

Cireuit No. | Light | Circuit No.| Iight | Circuit No.

      

  

  

Initial

  
 
 

Time

S. S,
Approval
Time

 
  
 
 

Date Started -20-

 
-

    
  
 
 

i
Approvfigwbyéw

»”

o
v‘{;fig;fiaufm\ _ 12A-28
7 - 10/7/65

List Annunciator Lights that are on in Msin Control Room ard Auxiiiary
Control Room at start of each shift and have Shift Supervisor approve

list. (Check Rochesters, Lights Above all Panels, Radiaticon Monitors,
etc.) Also list annunciator relays which have been removed.

0800-1600 Shift {1600-2400 Shitt § 2400-0800 Skifi

Annunciator Annunciator Annuneiator

tial

S. 8.
roval

Time

Date Started | » | | | -23-

 
o
Approved by M V@#m 12A-2B
r Vv

10/7/65

Check the following at approximate time indicated.

 

 

 

Normal| 0930] 1230 [1730 2030' 0130 |0430 o

 

 

All Charts Inking

 

 

Time A1l Charte 1

 

 

MCR Ann. Lamp Checké

 

 

ACR Ann. Lamp Check.

Sampler Permigsive |
Switch Record On ,

or Off CP/FP | orgfore! | L
e R e e T et ettt '

 

 

e e - el A T
msa————

 

 

 

 

 

 

 

™

Date Started ok
Approved by;:§?<;:2;z<t?a;4/flmfim¢ 12A-28

10/7/65

MISCELLANEQUS
TEMPERATURES ON TI-3200

Record once per shift.

 

INT| TE | 8-k|k-12112-8 TE | 8-k {4-12] 12-8
1 | ADL- oy R-TA
2 | CC-1 | R-10
3 CP-B2A | R-34
4 . CP-5A R-36A
5 | CPLE-A5 o R-374
6 CPLE-A6 | - {R-384
7 lCR-123 ! S R-394
8 | FDL-17A ! | R-L0OA
9 . FDL-19A | R-414
10 | FD1-204 o
11 | FD2-174 o 100-14
12  |{FD2-19A r 100-2A
13 ;FD2-20A : 102-5A
14 {FFP-100-2 ° ' 103-6
15  |FF-101-2 : 1103-Bil
116  'FF-102-2 5121
FF-200-2 ~ 516-1
18 ' FF-201-2 ‘
19 FFT-5A
20  FP-2B
21  FP-3B
22  |CP-OA
23  FP-12A
2k H-103
8-4 Initial __ Time
4-12 Initial __~ Time
12-8 Initial = Time

Date Started -25-
Approved by ,,;zzfsngéai;efifl¢rv\ 124-2B
e ¥ V

10/7/65

CELL TEMPERATURES

Record once per shift.
Read out on spare point on TI-3200 or on a O - 200 °F recorder.

TEMP ERATURE* TEMPERATURE*
No. | P. P. No. 12, 12 ' . P. 123 12

-1 81

-2 82
|Re- 8 | | =1 ' 208
RC-l 8l u P

- 8 . 210
RC-6 86 | . 211
RC- 8 ) 212
RC-8 : 88 ; b DIC-6 ' 21
*¥These should all be below 150 F. Any variations (>5 should be reported‘.

to the shift supervisor.

   

8-4 Initial - Time
h-12 Initisl Time
12-8 Initial : Time

i

Date Started - N | | | o 26-

 
 

oy N ]
C vV

WATER AND OIL TEMPERATURES

Record the following every 8 hours.

TE PP Special

No. No. Recorder

826-1 887
831-1 888
833-1 889
837-1 890
841-1 891
8h5-1 892
8h6-1 89

851-1 89l
TO0T-1A 871

T57-1A 881

Readout

Point

12A-2B
10/7/65

TEMPERATURES*

-12

 

*Any Temperature variation greater than 5OF should be reported to the

shift supervisor.

8-4 Tnitial Time
4-12 Tnitial Time
12-8 Initial Time

Date Started

 

- 2"{’_
swveoves vy _ Ao e
7

AT - FUEL INLET TO LOWER HEAD AND SUPPORT FLANGE ANNULUS
These temperatures will be read either from a special recorder
or may be plugged into an indicator depending on estimated time
of computer shutdown.
FUEL INLET TEMPERATURE

n oo 10800 - 1600 1600 - 2400 0000 - 0800
TE PP | TND. | ACTGAL )IND. | ACTUAL| IND. ' ACTUAL

RDT | NO. | NO- l BIAS | 7EMP | TEMP*  |TEMP | TEMPX | TEMP . TEMP¥

102- |

| 50 | 385 :
‘ i

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

AT AND LOWER HEAD AND SUPPCRT FLANGE ANNULUS TEMPERATURES

0800 - 1600 1600 - 2400 0000 - 0800
IND. | ACTUAL .| ACTUAL IND. AL
TEMP | TEMP¥* |%%| TEMP| TEMP* [*%x |TEMP| TEMP* [#*

 

*To get actual temperature, subtract the bias from the indicated tempera-
ture.

¥*To get AT, subtract actual fuel inlet temperature from actual tempera-
tures in this table. If AT is more than °F, notify the shift
supervisor.

8-4 Initial Time
L-12 Initial Time
12-8 Initial | Time
Date Started -28-

 
Approved for Usef’jzéi%i>§£:§22?q%£7\\h‘~ 12A-3

10/5/65
12A-3 BJTIDING I0G
SERVICE TUNNEL

Record every 4 hours starting at 0830 unless otherwise indieated.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

: _ -2
5 Personnel Monitors OI-= Water
—— Temperature
Monitren CAM Fi- (FI- out In Flow
Init.} Time| RE 7017 RE 7005 753 {754k |TT 822-1 |TT 823-1 FI-823-A
i - * —— =
a ‘ 3-5 16-9 ° °
| <3 mr/hr [<1000 cpm ~ 85°F ~ 80°F .
| 3 mr/ B0 oo |gom 5 7.5 gom
E
!
f XX XX XX
; XX XX xx
i T
| I
x '
j E XX XX XX
Coolant 0il Pump |[Filter AP OT-1 Water
Pressure® PI-T752-C Temperature
#1 #o Minus Oout In Flow
Init.{Time |PT 751A | PL T52A [PZ-753-C |TI 820~-1 | 7T 82i-1 | FI 821-A
K AP ~ o ~ o
’ <5 psi 85°w 80°F T.5 gpm

 

 

 

 

 

 

 

 

 

 

 

 

 

 

XX XX XX XX XX XX
XX

XX XX XX XX XX XX
XX

| XX XX XX XX XX XX

 

 

*
Call control room and aid in priming standby oil pumps.

*‘* ‘ .
Discharge pressure f{rom the. pumps which are on should be >60 psig.

Date Started ‘ -1~

 

TX~3838
(10-65)
 

 

 

— AT e, WO

 

Approved by,/fiézg;%;4%§;a“flfl 12A-3
y =

10/5/65

Record every L hours starting at 0830 unless otherwise indicated.

 

Fuel 0il Pump Filter AP
Pressure® PI-T702-C
#1 #2 Minus FI-
Init. Time PT 701-A | PT T02-A | PI-T03-C 0 Ol

3=> -9

*% #¥ <5 psi

- XX XX

 

*
Call control room and aild in priming standby oil pumps.

*%
Discharge pressure from the pumps which are on should be >60 paig.

SERVICE AREA

Record every 4 hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

 

 

 

 

F. 0il Supply Taxk |C. 0il Supply Tank Process Monitor*
Reading Reading

Init.| Time JLTOTIA3 |Set Point [LIOT2A3 (Set Point | RM OT-1 RM CT-2
>50% Reading >50% Reading <.5 mr/hr| <,5 mr/hr

-2% -2%

XX XX XX XX
XX XX XX XX
XX XX XX XX

 

 

 

 

 

 

 

 

 

 

 

*
Set calibration at 0.25 to 0.35 mr/hr before reading.

Date Started -2-

 
 

  

e 2

Approved by * 2~
10/5/65
Record every 4 hours starting at 0830 unless otherwise indicated.

Tube 0il Current
Init. Time FOP-1 FOP-2  COP-1 COP-2

PUMP RUNNING 7-9 amps

 

Record every 8 hours starting at 0830 unless otherwise indicated.

&

Instrument Air Cont. Air
Instrument Air Station - Station #h - pooPal
Init, | Time |PT 9010-3|PI 9010-2{PT 9010-1 |PI 9004-2 PT 9004-1 ST=-D

 

20 0 0-80 20 0-80 >0

 

Date Started -3~
Approved by /M}?m 12A-3

10/5/65

HORN HALL

Record every U hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

ATR o !
FIDING EVACUATION :
PERSONNZL, MONITOR CONDITTONER | PorLOTC VACUATION
COMPRESSOR Torn  |Cylinder and |
. Q-2091 3 Gages Pressure |Supply Valves:
VMoni ot ——I&LQH————-—~~
Monitron RE 7029 Within RA 7023-A2|Tagged!
Tnit, |Time [RE 7016 | Scale Reading Limits High | Low | Open {Closed
. Lowest L . _
<3 mr/hr| ool e <3/4 scale| As Marked*|>1500|~ 100N or S:N or S{
! i
E XX XX XX XX
|
g XX XX XX XX
f i
%XX XX XX XX

 

 

 

 

 

 

 

 

 

 

*
If running and out of limits, turn of f and punch list.

TRANSMITTER ROOM

PERSONNEL MONITOR LEAK, DETRCTOR PRESSURE

; Monitron CAM Other FI
Init. Time RE 701 RE 7004 PL Lo If Isolated

<3 mr/hr }<1000 cpm |90-110 psig | 90-110 psig

 

 

Date Started iy
Approved by fl,4zf§§§§§§:4zaw }2§é3
10/5/65

Record every L hours starting at 0830 unless otherwise indicated.

NOTE: Record all readings to the nearest 0.01 in. Hg. Tare setting
need only to be within 0.1 in. of Hg.

 

FD-1 FD-2 FET
Pos 1 Pog 2 Pos Pos Pos Pos
Time |Tare |Live |Tare|Live [Tare |Iive |Tare |Live |Tare| Iive Tare|Live

80.3 80.4 83.5 80.7 43,9 W, 0

XX XX XX XX XX XX XX XX XX XX XX

- FST CDT
Pos 1 Pos 2 Pos Pos
Time |Tare {Idive [Tare [Live |Tare Live [Tare |Live

.8 9, 1 6.2

 

Date Started -5=

 
12A-3
10/5/65

Approved by ,ffié??§%<i11fi14fi1\

Record every U4 hours starting at 0830 unless otherwise indicated.

CFT ILEVEL
LI-599B [LI-600B

OFT BUBBLER FIQOWS
FI-599 {FI-589| FI-
20-30 20-30 20-30

si si si

Time PI-589-A2 | PI-501A

35 psig

<10%

<10%

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

FP RUBBLER FIOWS FP LEVEL
Tnit. {Time FI-596 FI-592 FI-593-A LI-593C LI-596B
03-27 psig |23-27 psig |23-27 psig |5.6-6.5 in. |5.6-6.5 in.
XX XX
XX XX
i XX XX

 

Date Started

 

 

 
Approved by

 

124-3
10/5/65

Record every 4 hours starting at 0830 unless cotherwlse indicated.

 

Init.

Time

cP
FI-598
20-30

WS

FI-5
22-30

FI-595
20~30

CP LEVEL
LI' 5

Lo-595C
5.0 to
.2 in,

XX

5.

.2 1n.

to 5.

Tloat

to
.2 in,

 

Record HIC Settings every 8 hours starting at 0830 unless otherwise

 

 

 

 

 

‘indicated.
REACTOR NECK
 ATR FIpW#* FI-903 Control
Sampler | Cutslide [Inside P SCALE x Rod
Init. | Time 961 A 962 A 963 A | HIC 903A | 10 = CFM 915 A
-1 | — % > |
0 0 O

 

 

 

 

 

 

 

 

 

 

 

 

 

*
Set HiC's at minimum to glve maximum air flow.

Koo
Set HIC at Maximum to get maximum air flow

KoK
20 sefm if salt is in FP.

Date Started

 

7Zero CFM 1if galt is not in FP.

 
12A-3

Approved by -
10/5/65

 

Record HIC Settings every 8 hours starting at 0830 unless otherwise
indicated.

 
 
  
  
 

   
   

FREEZE VALVES
10

   

10

      

     
   
    

19-A2 10-A2 AP
Set

Time! 919 Al|Temp.|Point

     
 

     
   

oet Set
91C Al |Temp.| Pocint| 909-A1l |Temp. |Point

  

 

FREEZE VALVES
20
10L I 206 AP
cet
Time |08 Al . Al | Temp. {Point

 

 

VALVES
1 10 108
Init. |Time |924% Al {924 A2 [913 Al 913 A2 |919 Al [919 A2

 

 

Date Started | -8-
Approved by.—Z WA MO 12A-3
10/5/65

Record HIC Settings every 8 hours starting at 0830 unless otherwise
indicated.

VALVES
1C 2 111
Time |911 Al {91l A2 Set loo7 21 oo a1 [929 Ao
Point

REACTOR CELL DRATIN TANK CELIL
Power Suppliy for SUMP
Drain Tank > Flow Ievel Nz Flow Tevel
Time Tevel Probe FCRC-C LT RC-C | FC DIC-A LI DIC-A

Lo~-L5v 0.75 scth 0 0.75 sefh 0

 

  
 

   
   
 

 
   
 
  
 
  

   
    

 
      
 

     

  

   

FUEL PROCESSING SPARE CELL STORAGE
CELL SUMP SUMP CELL SUMP
Time | FC-FSC-A | LI-FSC#* FC~TCA LI-P5C%* FC-SCA LI-FOC*

 

       
  
 

             

 

0.4 scfth

  

0.4 sefh 0 0.4 sefh 0

 

*
Read mencmeter when sump of interest only is valved into manometer.

Date Started ~9-
Approved by‘f’ZEg?zkfiég;O*a”f 10A-3

10/5/65

Record every 8 hours unless otherwise specified.

 

co ATR
WASTE WASTE TANK SESA to
TANK StMP TR AP
FC-WI-A 0= WIC-A ~FE

0.4 gefh 0.4 sc 0 >0

 

3
Read manometer when surp of iaterest only is valved into manometer.
Record every 4 hours unless otherwise specified.

Reactor Cell AP
PAT-RC-E
Digl Readingg* AP
R T Teft TIeft + R

 

 

*
Record dlal readings at point where needles touch liquid surface. Right
slde is connected to c¢ell, left glde is comnected to reference volume. -

Date Started -10- .

 
+*

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Approved byW M 12A-3
Y 10/5/65
Record every 8 hours unless otherwise specified.
ECT Power Supplies XEM 1001~
Init., | Time Al -El -C1l ~DL -El -F1
60-65 | 60-65 | 60-65 | 60-65 | 60-65 | 60-65
NESA
Record every 4 hours unless otherwlse specified.
CONTROL ROD DRIVE
Fan Motor Lights*
Init, | Time 71 #2 #3
out Out Qut
*
If any light is on, contact the Shift Supervisor immediately. A light
on indicates that the fuse is blown in the fan-motor circuit.
Date Started -11-

 

 

 
Approved by <,4%?¢;j%&<7?@flflflh\\‘ 124-3
-~ \ 10/5/65

NESA

TR HFADER TEST#*

Record every 8 hours unless otherwise indicated.

Tnit. |Time {IB1-1|031-2]B1-3{0B 10-1{JB 10-2{J3 10-3|JB2-1|JB2-2|JB2-3|JB2-k

 

*
A1l pressures on headers shculd be >5 psig. If any header is below 5 psig
repressurize to 50 psilg. Header valves should normally be closed.

Blow down Line 519 once per day on 8:00 to 4:00 shift.

 

 

 

 

 

 

 

 

 

PI-519 CONTAINMENT
Init. | Time Before After PI-RC-B | PI-RC~F | PT-RC-G
~ 2 psig ~ 2 psig ~ 4" Hg Vac.
XX XX
XX XX

 

 

 

 

 

 

 

 

Record every 8 hours unless otherwise indicated.

TRUMENT ATR STATION
FT 900z~ FI 9002-5 | PI 9002-2 { PI 9002-1

25 20 30 70-80

 

Date Started -l2-

 
¢ "

Approved byMflM 1254-~73
| 10/5/65

Record every 8 hours unless otherwise indicated.

TS T, ATR STA. #3 TNE™, ATR STA, #13
BT 9008-2 | PT 9008-1 FL 9013-1

2C 70-80 75-80

 

 

 

 

 

 

 

 

 

BERYLI.LUM DETECTION SYSTEM
#1 Blower | #2 Blower
{Init. ]| Time | On-Cff Pressure 10ff-0n Presgure
| Onk 1.8" ¥g Vac | Cff*  [1.8" Eg Vac
XX XX XX XX
XX XX XX XX

 

 

 

 

 

 

 

 

 

%,
#0 Blower 1s standby for #1. If #1 is off #2 should be ozn.

Date Started -13-

 
Approved by/;Z?fifg&g%%;éflafiaL 124-3
Y

10/5/65
FEATER CONTROL PANEL

Record all values on ore rog of each chift, preferably the first

 

 

 

10,
8:00 - L:00 Teitial Time Started
10O - 12:00 Initial Time Startesd
12:00 - 8:00 Initial Time Started

 

 

EEATER CURRENT
CR- H-200-1 E-201-12 H-202-2
A =

2 132 1 12 112

GROJND DETECTOR VOLTACE
CR-1 (B~ CR-
o3

2 - 1 2 3 L

 

 

Iate Started -1k~

 
Approved by W g MY 12A-3

10/5/65

 

HEATERS POWERSTAT SETTING AND CURRENT
H-200-14 q-200-15 H-201-10 H-201-11.
Setting { Amps Setting | Laps Setting | Amps Setting | Amps

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

TEATERS POWERSTAN SETTING AND CURRENT
H-202- H-204-2 H-205-1
Sett S Sett S Sett

 

 

HEATERS POWER STAT SETTING AND CURRENT
FV-204~3 FT-2018-1 'T-201A-3 FT-201A-2
Setting | Amps Setting | Amps Settin Amps | Setting | Amps

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

HEATERS POWERSTAT SETTING AND CURRENT
F-201R-1 FT-201B~- FT-2018~-2
Sett 3 Sett S Sett

   

Date Started

 

 
 

Approved bVM/m 124-3
~

10/5/65

 

HEATERS POWERSTAT SETTING AND CURRENT
H-203-2 -204-1A IE-CP-1
Sett S Sett g Sett

 

 

HEATERS POWERSTAT SE AND CURRENT
FV-204~1 FV-204~5 FV-206-1
Sett Setti Sett

 

 

 

HEATERS POWERSTAT SETTING AND CURRENT
-o0L4-1) H-206-1] CDI-1 -003- C
8 Sett

HEATERS PO TAT SETTING CURRENT
CP-1 CP-2 H-200-1 H-200-11
g |Sett s | Sett s | Sett Sett

 

-16-

Date Started

 

 
10/5/65

HEATERS POWERSTAT SETTING AND CURRENT
H-200-12 H-201-1 H-201~-2 H-201-
Settin Sett sl Sett s{ Sett

 

 

FEATERS POUWERSTAT SETTING AND CURRENT
RCH-2 RCH- RCTH~
2

id12 i |2

GROUND TETECTCR VOLTAGE
R-1 R-2 R-
2 112 112

 

 

Date Started -17-
Approved by %%:flm 103/?%;)

 

HEATERS POWERSTAT SETTING AND CURRENT
H-102-2 R-1 R-2 R-
1412 112 112 112

HEATERS POWERSTAT SETTING AND CURRENT
HX-3 FP-1 FP-2 RAN-1
1l 12 112 1 12 Sett Amps

 

 

HEATERS POWERSTAT SETTING AND CURRENT
H-200-1 H-201-1 H-102~1
Sett Sett Sett

HEATERS POWERSTAT SETTING AND CURRENT
H-102~ H-10 V-
Sett Sett Sett

 

Date Started -18-

 

 

 
Approved by /N 12A-3

 

YEATERS POWERSTAT SETTTNG AND CURRENT
H-10L-1 FV-104-1A FV-105-1A FET-1 FET
Setting | Amps | Setting | Amps | Setting | Amps 1 ]2 31 1} 2 3

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

HEATERS POWERSTAT S AND CURRENT )
1-2 FD e- FD 2-2 Fy-104-1
o 112 1102 Sett

 

 

HEATERS POWERSTAT SETTING AND CURRENT
H-10 H-104~ BPV-105~1
Sett Sett Amps Sett

 

 

 

HEATERS POWERSTAT SETTING AND CURRENT
H-105-1 H-105~ FV-106-1
Sett 8 Sett Sett

 

Date Started -19-
10/5/65

iy S
Approved by/f‘ffif?;55553?4w1401 12A-3

 

HEATERS POWERSTAT SETTING AND CURRENT
H-106-1 H-1006- -106-~1A
Sett Amps Sett Amps Sett Amps

   

 

HEATERS POWEERSTTAT SE e AND CURRENT
H-104-21 T-104~- H-104- H-105-2}1 H-105~-
S 5 5 Amps 8

 

PO TAT SETTTNG AND CURRENT
H-11C-2 1H-110- H-107-1
g S Sett

 

 

 

HEATERS POWERSTAT SETTING AND CURRENT
b-107- Fy-107-1 .

i ¢ e e e el st b
. ‘ 4

Sett : e Sett

 

 

Date Started - -20-

 

 
Approved by@%fi@ 3/;4%3
10/5/65

HEA

 

PG TAT SE AND CURRENT
-108-1 -1086=2 H-1038-
Sett s Sett

          

  

 

 

 

Date Started : -1~

 
o
Approved bytéifgiiézéééégéflHAW\

12A-3
10/5/65

HEATER CONTROL PANEL

8:00 - L:00 Initial
4:00 - 12:00 TInitial

12:00 - 8:00 Initial

Time Finished

 

Time Finished

 

Time Finished

 

 

Record every 4 hours starting at 0830 unless otherwise indicated.

NITROGEN FILOW
To Scanners scfh Purge SCANNER Scanner
Time B |C Dl E {Pressure |A |B | C D E |Selected¥*

.15 to .25

5-10 psig {50 |50| 50 J100 }100 A

XX XX XX XX XXX

 

XX XX XX XX XXX XX XX XX XX IXX XX

*In order to get best results from scanner in control room, leave "A"
as the scanner selected at scanner panel.

Record every 8 hours starting at 0830 unless otherwise indicated.

RECORD MAXIMUM AND MINIMUM
SCANNER TEMPERATURES
| A B C D
Init.}] Time |HiL Low Low (H Low |Hi Low

 

Date Started -DD-
Approved byzé%fffié%f%é%%fié?&WL_ 12A-3
| 10/5/65

SCANNER SPAN -- Obtain from Instrument Mechanic (Deily)

Time | Scanner | Gain | °F/in.

 

Record every 8 hours unless otherwise indicated.

 

TEMPERATURE. RECORDERS

 

 

 

Init. | Time |TR-3300 | TR-3400 Record Unusual Temperatures
x >950°F
<1300°F

 

 

 

 

 

 

 

 

 

 

 

*
On TR-3300, points 1, 2, and T through 17 should read LOO°F to 600°F.
The remainder of the points should read between 1C00°F and 1200°F.

Date Started : =23~
Approved by%flifl_

Record every 4

 

PERSONNEL MONITORS

 

Monitor CAM
Init. Time | RE-701k4 RE-T7003
<3 mr/hr | <1000 cpm

 

 

 

 

 

 

 

 

 

 

 

 

 

Check blowers to induction regulators every 4 hours unless otherwise noted.

12A-3

10/5/65

hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

G5 | G5 | G5 | T2

Init. |Time |TTC-1 |TIC-2 | TTA-1 |TTA-2 |TIB-1|TTIB-2 BB-1|BB-2]oy-1]¥Y-1
ON ON ON ON ON OoN ON | ON | ON |ON

XX xx |xx XX XX XX Xx |{xx |xx XX

XX XX XX XX XX XX XX XX xx XX

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Date Started

 

-0l

%

4
-

 

Approved by w‘ ?2?2
10/5/65

48v DG CONTROL PATHL,

Record every 8 hours starting at 0830 unless otherwise indicated.

TORS #2 and Battery
GVe LES o T JOLTAGH M.G. Room
Init. {Tine 3 {Batt. 3{laad Gen #2 tt. (Gen Or1 TFan

Diml Diim | >0 5oy 5oy %2 or #3] On

XX

XX

N. WALL 840! IEVEL

Record every 8 hours starting at 0830 unless otherwise indicated.

 

 

 

Scanner
Ko Erader Haader Header
Preggure® In Pregsure
Init., | Time West Fagt Service | PT-9012

 

>050 pedg { 250 peig t W or B 50 psig

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Energeney N Emergency Nz Emergency
Header Pregpure® Header Controller Air
West Fast in Bet Peint Flow
Init. | Time] PI 0006-1 {PL 9006-2] Service [PIC 9006-1 A & BJ FI-9006
>500 >500 Wor E 65 psig

 

 

 

 

 

 

 

 

 

 

 

 

 

P ===
Standby headers should be at 1500 psig or greater.

Date Started - -25=-

 
Approved by4gf;;zzéaéazgyf%8fl_

</

124-73
10/5/65

Record every U hours starting at 0830 unless otherwise indicated.

Voltmeter

Gen.

260v

Bat.

Gnd Det
Lights
On~-Dim-0ff

Dim

MG- 4

Transfer
owitch
Red-TVA

recn-

Green

MG-4
Blower
On

- Light

On

 

 

 

 

 

Gd. Det Lts
MG-4 TVA Bus Sect. 5
Amps Voltage Dim-Brt-0ut
Init. | Time | Volts AC | I-1 | I-2 | Cycles { 1 2 1 2 | 3
120 + 2 60 450 to 480 {Dim| Dim | Dim

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Date Started

 

-26=

 
,

Approved by ‘455252%%252;4mgn1

12A-3

10/5/65

Record every 4 hours starting at 0830 unless otherwise indicated.

BUILDING EVACUATION

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Cylinder and

Horn Pressure Supply Vaives
| RA T023A3 Tagged

High Low Open Closed
>1500 |~ 100{ N or 8 { Nor S
XX XX XX XX
XX xx | xx XX

)

XX XX XX XX

Record every 8 hours unless otherwlse specified.

 

 

Blow Down
AC #3 DG #5 Pressure | Inst. Air Inst. Alr
(Valve East of | Alr Tank #3 Moisture Flow
Init.{ Time | South Door) Pregsure | Receiver |Content (%)* | FI-9000
>200 pelg 15-30%

 

 

 

 

 

 

 

 

 

 

 

 

*
Turn switeh to "Adj. 100" and adjust indieator to read 100%. Then
switch to "Operate'" and record reading.

Date Started

 

_27_

 
Approved by Mw\

Record every 8

hours unless otherwise specified.

12A~3
10/5/65

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

AC #3 HEADER g #h
Cooler Head Load Speed
Init. | Time | 881-3B j 881-3A | PI-9000-1 | Idmit | Droop
<110°F | <115°F 80 peig 5 0
| xx o
!
i XX fi
FRESSURES DG #3
#1 Receiver | #2 Receiver | Load Speed
Init. ]| Time PI-R1 PI-R2 Limit | Droop
~ 80 psig ~ 80 psig 5 0
XX XX
XX XX
ATR CCMPRESSORS
OUTLET WATER TEMPERATURE
AC-2 AC-1
Coolexr Head | Cooler Head
inlt. | Time { 881-2B | 881-2A1 881-18 | 881-1A
<110°F | <115°F| <110°F | <115°F

 

 

 

 

 

 

 

 

 

 

 

 

Date Started

 

-08-

 

 

 
e
Approved by ¢,§§:2%i?%;g%;kflnfiflfl

Record every 4 hours starting at 0830 unless otherwise indicated.

12A-3
10/5/65

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

He TREATING STATION TEMPERATURES
Station #1 Station #2 _
Preheater Preheater
Init. [Time] TIC-PH-1|TIC-Cz-R1}TS-05-R1-2| TIC-PH-21TIC-05-R-2|TS-05-R2-2
| SR =
* *
800°F 1200°F | <1000°F 800°T 1200°F <1000°F
§
i
i
==
Standby unit should be held at 800°F.
He SUPPLY HEADERS
Emergency He Treating Low He
Pressure Trailer Station Pressure Flow
Tnit.| Time| PI-5024 PI-502B | PI-500-F | PI-500-H |PI-500-M |FIC-500-J
>500 psig| >500 psig| >500 psig 250 35 <10 £/m
i

 

 

 

 

 

 

Date Started

 

-29

 
Approved by é%//w
Y N

Record every U4 hours starting at 0830 unless otherwise indicated.

12A-3
10/5/65

 

MOISTURE ANAIYZER

OXYGEN ANATYZER

Line

 

 

He STATION
Ambient
Temp. at

 

oist. Span 0o Contd Moni+ Moisture
Inttd Time | Flow [Range ppm) | Flow JAd3.|Rdg. tored | Analyzer
100 <10 100 | 548
cc/min ppm  jec/min or o
5149 F

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Record every 8 hours starting at 0830 unlese otherwise indilcated.

 

TREATED WATER COOLER °F

TW _FILTER PRESSURE

 

 

 

™ In IW Out |} CIW Out In
Init. | Time | TT 829 { 7T 826 § 7T 854 |PT 829 Qut
| AP <20 peig

 

 

 

 

 

 

 

 

 

 

 

Date Started

 

 

- 30_

 

 
-~

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Approved by 124-3
% 10/5/65
Record every U4 hours unless otherwise specified.
PERSONMNEL MONITOR RC RC
Q-2091 9 DTC Cooler Cooler
RE-T030 Cooler Cocler 1 #0
Init.] Time] OScale Reading FI-851-C{ F1-836-A | Fi-838-4| FI-8L0-A
Lowest y . ~ _ ,
possihle <3/L ?Léle 260 gpm{ >50 gpm | > 50 gpm| >50 gpm
i
| |
Thermal
Shield
Init, | Time | FT-844-A | TI-FWT-1A | LI-FWT-2A | PI-Q06-B2
50 gpm 9 psig
. Date Started -31-~

 
Approved by 4fg7;;?%gi§%79flih 12A-3

10/5/65
Record every 4 hours unless otherwise specified.
C.T. TEMFERATURE

0 8
Time | Set Point| Readir LI-CST-2

T9°F 85°F - 50~150 gal

 

 

Fual Coolant c.C.P. CP PI-829-4
Pump Pump 0il Cooler or
Tnit.} Time | LI-CST-1 FI-830 | FI-832 FI-875 | FI-873 | PI-835-A

 

150-190 gal | 4.5 gpm 5 gpm 10 gpm | 20 gpm | >60 psig

 

 

XX

-

 

XX

 

XX

 

XX

 

 

 

 

XX

 

 

 

 

 

 

ete Started -32-

 
L d

 

Approved by Mfim }3%3
| 10/5/65

Record every U4 hours Startingrat G830 unless ctherwise indicated.

 

Thermal Bhiseld

 

 

- Blides -
Init, | Time -850 Cell Anrulus | PI-84h-p
17% {3.6 o) Ta, <13 peig

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Record every 8 hours starting at 0830 urless ctherwise indicated.

 

INSURCMENT AIR
Station #5
Init. | Time | PT-9005-1 § PI-9005-2 | PI-9005-3

70-80 60 20

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

   
 
   
    

T TRUMENT AR
Stati 10
1i- PT 9011-

 
   

  
    

   

 

11-2 | PT

      

 

60

   

20 3C.

Dete Started _ 33~
 

A db ifii&y/ 124-3
pprove x/ang;%L/ =7 Azdw\\ rofares

COOLING TOWER
Record every 4 hours starting at 0830 unless otherwise indicated.

POWER TO FREEZE
Time PI-851-A PROTECTION LIGHIS*
35 peig : ) White reen Red
- On On

Gff

 

-
X
Record these every 4 hours November through March.

VENT HQOUSE

Record every U4 hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

r
Tnit. Time | PI-950-A | PT-VH-A
>0 >0
XX XX
XX LX
XX XX

 

 

 

 

 

 

 

 

Date Started - 34~
/A,
Approved by fiéfi”fi”\

VENT HOUSE

Record every 4 hours unless otherwise specified.

Tower
PERSONNEIL MONITOR Water to
Q~ 2091 Tharcoal
RE-TC31 Bed

Time¥ Seale Rea rT-893 .

Lowest
Possible

<3/4 Scale

Process

Water to

Charceoal
Bed
-8

*
Time to be recorded is the time that FQI-569-A is read.

124-3
10/5/65

Wet Test
Meter
T - A%

- -

 

 

FQT-569 Water
Init, | Tme |- Ievel FI#569

 

At Pointer

 

 

 

 

J v R

 

 

[ J—

 

 

 

 

 

 

Date Started

 

~35=

 
Record every 8 hours sterting at 083C unless otherwise indicated.

12A-73
10/5/65

 

 

 

 

 

 

 

 

 

 

 

 

 

 

CXYCEN ANALTZEE
Calibrate O2 Lnalyzer
Tnit Time Anglyoep® Flow Presgure] Scale 0o Content
50-250 ce/min 0-10% <5%

|

;

}
_______ e ‘ m o

 

 

¥ . - -
nalyzer should be calibrated per Procedure 3H, Step 6.2,

CHARCOAL EED TEMPERATURES: All should be between

Record daily on 12-8 ghift.

°F and

°F.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

THERMOCOUPLE | TEMPERATURE | THERMOGUUPLE | TEMPERATURE
|
TE-CR-14-1 | _TE~C2-2B-1
TE-CB-1A-2 [ _TE-CB-23-2
TE-CB-1A-3 | TE-CB-2B-3
E-CP-15-2 _ TE-AC-P1-1
TE-(5-15-2 | TEepe-mp-l
TE-C3-1B-3 L CE-CE-3
TE-CB-2A-1 | _CE-CRN-1
TE-CB-2A-2 Y Nm-C3W-2 —
TE-CB-2A-3 %

 

 

 

 

Tate Started

 
Approved by fifig?céfigéyu@fvx 12A-3
- v 10 5 65

BERYLLIUM MONITOR

 

Record every L4 hours unless otherwise indicated.

 
  
  
   

  
    
         
 
   

RECORDER
Beryllium Elect.

Level Zero
Spark*¥ | (Sparking) |{No Spark)

   
    

Voltage
Scale High
Selector Voltage

    

   

Init. |[Time |Amperage

 

*

*When sparking.

*¥If monitor is operating on "continuous" the spark should be continuous.
If operation is "intermittent" listen through one complete cycle for
unusval noises.

STACK PANEL

Record every 8 hours unless otherwise indicated.

%Init. Time PI-927A | PI-927C | PAIl Fi4, | PAI-F;A,

Date Started -37-

 
Approved by

12A-3

 

0 m mlgy e

 

 

 

 

 

 

 

 

 

 

 

 

 

_ 10/5/65
Record every 8 hours unless otherwlse indicated.
omall
Beryllium
Init.{ Time [PAI-Fol, |PAI-Fols |PAT-F=A, 1PAT-TzAp |PI-927-BL Blower
: On
L | ! ‘
XX X% XX o
X KX flmmu&_ f

 

 

 

 

 

ABOVE SPECTAIL, EQUIPMENT ROOM

Record every 4 hours starting at 0830 unless otherwise indicated.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Fast CONTAINMENT AIR PRESSURE |
cce | Speclal PERSONNEI, MONTTOR
Water Coolant Equipment Q-2091
Flow Cell Room RE-T7027
Tnit.] Time | FI-86L4-A | PAT-933 PI SER B Scale Reading
. Lowest .
20 gpm ! >0 >0  Possibie <3/l Scale
+ | ;
: XX ;XX P XX
i 1 | |
; Xx xx xx |
| Z | |
XX XX XX |

 

 

 

Date Started

 
 

 

 

 

 

 

 

 

Approved by ZE W Py 124-3
<~ 10/5/65
ABOVE VAPOR SUPPRESSTON SYSTEM
Init. | Time | PI-VI-1 | Annunciators
0 psig None
i =~ . ]

 

 

 

 

 

- SOUTH SIDE OF OFFICE BUILDING

 

i HUTIDING EVACUATION
CYLTNDER AND

' HORN PRESSURE

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

i _RA=T7023-Al SUPPLY VALVES
Init, | Time ¢ High Low | Tagged | Closed |
!
>1500 | ~ 100 | Eor W | E or W
]
i . T
| XX XX XX XX
_— ]
| | xx XX lxx XX
| : XX . xx ' Lxx

 

Date Started

 

- 39_

 

 
 

Approved byfjfzggzgziéQMag¥ 12A-3
Vv

10/5/65
HOT CHANGE ROOM AND HIGH BRAY

 

CHANGE ROOM
Q~2091
RE-T7028
Init. Time Scale Rea
Lowest
Possible

 

<3/l Scale

 

BERYLLTUM MONTTOR

 

Check following every 4 hours.

Reload” Tndicator
Tait. | Time Light Re-Zero~ ea S

Off

 

lRe-zero instrument every L4 hours (about) by following the procedure:
A} Turn black knob to CAL. position and zero with potentiometer
marked CAL. |
B) Depress zero check and adjust meter to zero with potentiometer
marked zero.
C) Reset black knob to integrate position.

=Tr opark light is 1it, wait and re-zero.

°If reload light is on or mechine is not operating properly, turn off and
punch list for day shift to repair.

Dete Started - LO-

 

 
Approved.by<§§f§§%%%é&2f&3

Record every 4 hours starting at OB30 unless otherwise indicated.

32A-3
10/5/65

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

Nuc Pen ‘ | -
) 2 -J.\ fr I\’[@'\afim% Ik
Recyole PERSONNEL MONITORS ‘ PERSONNET, MONTTORS
Pump HB-S HB-S West CCC HB~-W FBW H.R.
Press CAM Monitron {Water Flow|Monitron CAW CAM
JInit . 4Time IPT-848 { RE-7001 | RE-7012} FI-862-A| RE-7013] RT-700C | RE-7006 |
>5 peig (<1000 cpm (<3 mr/hr% 20 gpm |<3 mr/hr <1000 cpm|<1000 cpm
. B i
7 — T s
; 3 XX
4 § z
) ; :
+ XX
g ‘
HIGH BAY
Record every 4 hours starting at 0830 unless otherwise indicated.
CONTATNMENT ATR PRESSURE
Fuel Fuel Maint.
Processing| Spare {Processing{Storsge { Decon. |Practice| Waste
Cell Cell Cell Cell Cell Cell Cell
Init. |Time| FI-oLO |PaI-941A} PAT-940A |PAT-0OL2A |PAT-9L3A|PaT-9ksa {PAT-94EA
>0 >0 >0 >0 >0 >0
XX XX xX XX XX XX XX
_ XX XX XX XX XX éxx ;gx
, XX ixx XX XX :xx i XX ' XX
!
_hl_

 

Date Started

 

 

 
Approved ’W%flm | 10}?%2

Becord every I hours starting at 0830 unless otherwise indicated.

U TNG EVACUATIO
Cylinder and
Horn Pressure ou alves
RA-TOZ Tagged
High Low en Closed

>1500 | ~ 100 | BEorw { E or W

 

 

 

 

 

 

 

 

 

 

 

 

 

852 LEVEL
Record every L hours starting at 0830 unless otherwise indicated.
PERCONNET, MONTTORS
(Office Hall) (Control Room)
CAM Monitron
nitf Time RE-TC02 RE- 7011
<100C cpm <3 nr/hr
: . § ;
— i i
KN

 

 

 

 

 

 

 

Date Started -

 
- Approved by aéffi%fié%;zgmgan | 12A-3
10/5/65

CONTROL ROOM

Record every 8 hours starting at 0830 unless cotherwise indicated.

Instrument Air
Station 1 trument Air Station

-9001-1_|Pi- ' -9007-4 |PI-9007-

T0-80 i 20 30

 

 

 

 

 

 

852 IEVEL ‘ | |
. Record every U hours starting at 0830‘unle$s otherwise indicated.
;;nit. Time | Scale VRéag;ng el |
Lowest 3/l Goald |

 

| mmiemerer ol e .(:4,.....“..;,..‘«.,.‘..,..--_. T s

 

 

 

 

 

 

 

 

 

 

 

 

 

Date Started __ -43-
b
Approved by ,fifflf“ifimfififgévfg?K\ 12B-1
(7 10/13/65

12B CHECK LISTS

Check lists are provided for detailed operations which are repeated
often. When properly completed, these serve as data sheets and are
placed with other logs and completed data in the holder in the control
room. These are subsequently filed by day personnel in the operations

office. Available check lists are listed below:

LA to 4I Auxiliary Systems Startup Check Lists
5A to 5K Reactor Startup

6A to 6H Sampling Check Lists

8A Neutron Level Detector Check List

8B Process Monitor's Check List

8C Personnel Monitor's Check List

8D Safety Circuits Check List

SA to 9N Unusual Operating Conditions

10 Reactor Shutdown

11 Shutdown Operations

12A-2A Control Room Log

12A-2B Control Room Log

12A-3 Building Log

12B-1.1 Shift Supervisor's Check List
12B-1.2 Assistant Shift Supervisor's Check List
12B-2.1 12-8 Weekly Check List

12B-2.2 8-4 Weekly Check List

12B-2.3 4-12 Weekly Check List

12B-3 Operations Supplies Check List

12B-4 Salt Inventory

The check lists are filed in procedures file in the operations file.
Before using these, they should be corrected to agree with the magter

copy, which is also kept in the operations office.
TX-38&7 (11-65)

 

Approved by iy,/flkfifgéé/flffi%\ 12B-2
’ v N~ 10/13/65

TABLE 12B 1.1
SHIFT SUPERVISOR'S CHECK LIST

The following should be done each shift unless otherwise indicated:
0000 - 0800 0800 - 1600 1600 - 2400

 

1. Read console log.

 

Review building log, control
room log and computer typed
logs.

 

3. Review scanner photos.

 

Ik, Review auxiliary control room
for bypassed alarms, etc.

 

5. Review TI 3200 temperatures. XX XX

 

6. Review console log summary.

 

Initial when all items are complete.

 

If the computer is out of operation, see Table 12B 1.l Addendum 1.

Date Started

 
CAN e 12B-3

Approved by ¥
o 14 10/13/65

TABLE 12B 1.1 ADDENIUM 1
SHIFT SUPERVISOR'S CHECK LIST

The following items are to be done whenever the reactor is in
operation but the computer is not. These are "must"” items and should

be performed each shift unless otherwise indicated.

0000 - 0800 0800 - 1600 1600 - 0000

 

1. Calculate a reactivity balance
(This need not be done if the
reactor is subcritical.).

2 Calculate a heat balance if
the reactor power is greater
than 1 MW. XX XX

 

3. If any changes in power are
made, check that a reactivity
balance and heat balance (if
>l MW) are calculated before
and after the power change.

 

4. Review the temperatures of the
reactor cell, drain tank cell,
TW return lines and oil return
lines. These are recorded on
the last few pages of the con-
trol room log.

 

Initial when all items are complete.

 

Date Started

 
)

T 2o
Approved by =7 ;é’ [7e 2l 2y

‘lOa

V

TABLE 12B 1.2

ASSISTANT SHIFT SUPERVISOR'S CHECK LIST

The following should be done each shift.

12B-4L
10/13/65

0000 - 0800 0800 - 1600 1600 - 2400

 

Check out work requests for
day shift maintenance.

Review all punch list items.

Read console iog.

 

Isclate salt sample Trom FP
(Check list 6A-3). This will
be done weekly if flush salt
is circulating.

Isolate a cooling tower water

‘sample according to check list

6C, make entry in sample log,
analyze for items listed in
Tzble 6-1 and make additions
if out of limits. If not
possible to sample on desig-
nated shift punch list for
following shift. Cooling
tower water (CTW).

Tour entire building.

 

Check out completed work re-

- quests.

Check that all required sam-

ples are taken.

Read console log.

 

 

Review weekly check list.

 

Initial when complete.

 

 

Date Started

 
TX-3850 (11-65)

Approved by ,’7/*4&( Sy 12B-5

 

7 10/13/65

12B 2.1
12-8 SHIFT WEEKLY CHECK LIST

 

Perform the foliowing each week (If possible these should be done

on Sunday or Monday unless otherwise indicated.) on 12-8 shift.

l.

Init. Date/Time

 

Blow down instrument air filters:
Service area, Stations No. 9 and 4;
Transmitter room, Stations No. z and T;
Blower House, Stations No. 5 and 10;
High Bay, South wall of change room, Station
No. 8;
Behind ACP in Mein Control room, Stations No.

1 and 6.

 

Check that traps are working on entraimment separa-
tors.

Sight Glass Level

 

AC No. 1
AC No. 2
AC No. 3

 

 

 

 

Should H-O level appear in any sight glass, the
level should be recorded, reported to the shift
supervisor,and the entrainment separator should
be blowh down by opening the drain valve upstream
of the condensate trap. The entraimment separator
should then be checked each two hours and blow:
down as necessary.
Check that air compressor receiver tank traps are
working by opening the drain valve upstream of
each trap and recording the volume of Hz0 drained
rom each tank. Should the volume be in excess
of akout 300 mf, notify the shift supervisor,
determine the rate at which the Hz0 is collecting

in the recelver tank and blow down as necessary.
Approved by*/?“}’%fi e

3

L.

6.

 

(continued)

s

v

Vol.

Receiver Tank No. 1

Receiver Tank No. 2

Receiver Tank No. 3

Check that

 

all emergency lights operate lst week .

of each month.

No.

13

H R oW W

1

Location
840 ft., level and ESA
High bay ares
Control room
852 £t level, offices and hall
Service tunnel
Vent house
Switch house

Diesel house

These emergency lights can be operated by

opening hol

panel H on

ding coil at right of lighting
the North end of the 8L0O-ft level.

12B-6

1Q/13/65

Init.

Date/Time

 

 

T

 

 

 

 

Becord the following timers.

| | Reading

(Max. = 4000 hr) CCP-1 (Switch House)

(Max. = LOOO hr) CCP-2 (Switch House)
CCP-3 o
FP (Switch House) L
CP (Switch House) L
FOP-1 (Switch House)
COP-1 (Switch House)

FOP-2 (Service tunnel) (zero = 3314 hr)

COP-2 (Service tunnel) f{zero = 5218 hr)

AC 1 (Diesel House) (zero = 4790 hr)

AC 2 (Diesel House) (zero = 5308 hr)

 

Record all TC's not monitored. Plug portable

ingtrument

into each patch panel point not
Approved by.- .

6

lOu

11.

1z,

i | 12B-7
: 10/13/65

. .
1
N

(continued)
Init. Date/Time

 

filled except scanners D and E patch panel
No. 505 to 624k. Data sheets and master in
"Master Forms" drawer in operations office.
Check that thermocouples TE-200AS-BIB and
TE-201AS-BIB are between 500°F and 700°F.
Adjust heaters (if necessary) H-200-16 and
H-201-14 respectively.

JP No. 936 TE-200AS-BIB ____ °F

JP No, 940 TE-201AS-BIB ____ °F

Check that battery room fan is operating

 

 

properliy.
Check that there is essentially no water leaking
from the back flow preventers vents.

BFP 809-1

BEP 819

Check the ventilation air inlet house for steam

 

leaks and sticking louvers. Check the weighted

damper action by operating the attached rope.

 

Isclate and analyze the following water samples
semi-weekly. Use sample check list 6C, making
entry in sample log, analyze for items listed
in Table 6-1. If out of limits, make additions
as necessary on Saturdsy and Wednesday of eaéh
week. Sample:

Treated Water System (TW)

Process Water System (PW)

Nuclear Penetration (NPW)

 

 

 

A number of samples need to be taken on a weekly
basis, and submitted to the proper lab for
analysis. Take these samples per the check list

in parenthecis and make entry in sample log.
’

A A

| V4 - 10/13/65
12  (continued)
Init. Date/Time
Fuel pump (6A-3)*
Coolant pump (6B-2)
Treated water, loop (6C)

 

 

 

Treated water, nuclear penetration (6C)

 

Cooling tower water, loop (6C)
Cell air (6D)
Coolant lube oil (6E)
Fuel lube oil (6E)
*When flush salt is in the pump bowl.

 

 

 

 
TX 3849 (1165)

Approved by fg#"J/?fV?jflflfi”1 12B-9
10/13/65

 

12B 2.2
8-4 SHIFT WEEKLY CHECK LIST

Init. Date/Time

 

Perform the following (If possible these should
be done on Sunday or Monday unless otherwise indicated.).
1. Change caustic in Oz analyzer.
2. Check level of Diesel o0il storage tank.
3.  Check that "Day Tank" levels are normal for all

 

 

three diesels.

 

4. Check or clean cocling tower basin.

Parallel DG No. 3 with TVA and load.

 

 

This is to be done during the weekly check
of diesels on the first week of the month.
6. Parallel DG No. 4 with TVA and load.

 

This is to be done during the weekly check
of diesel on the second week of the month.
7. Load DG No. 5.
This is to be done during the weekly check
of diesel on the third week of the month.
8. Check that voltmeter for DT level probes (on
TB-8) is between 40 and 60 volts.

 

 
TX-3848 (1165)

Approved by BN e ' 12B-10
I | 10/13/65

 

12B 2.3
.12 SHIFT WEEKLY CHECK LIST

 

Init. Date/Time

 

1. Each Friday have the Shift Instrument man check
all recorders. Ink all those nct printing and

make any other necessary adjustments.

 

2. Perform a housekeeping and safety inspection tour
of the building. During the tour make note of
any of:the following conditions:

(a) Trash and unnecessary clutter in areas, also

overflowing trash cans.

 

 

 

(o) Safety hazards such as unroped openings,
high voltage cables on floor, gas cylinders

improperly secured, etc.

 

 

 

 

(¢) Unmarked hazard areas such as radiation,

electrical circults energized, etc.

 

 

 

 

(d) Fire hazards: Check for existgnce of
extinguishers where indicated, oil in lube
system pans, olly rags, fire doors blocked

open, etc.

 

 

 

 
LS
Approved byfijgf//fb<4¥94wWfl1

(e) Most of the areas are equipped with a clock.
Set each clock to agree with the control room
time.
3. Areas inspected for housekeeping and safety.
(a) Control room and data room
(b) Offices and HP room
(¢) Change Rooms
(d) High Bay 852
(e) Transmitter room and area
(f) Service tunnel and area:
(g) Heater control area
(h) Nitrogen bottle rack ares
(i) Switch room
(j) Diesel House
(k) Blower House
(1) Water Room
(m) Vent house and ares
(n) Exterior
L.  Check that cutie pies and victoreens are
located in the following areas:
Control room
HP office
(Cutie Pie only) Guard Shack
5. Check that there is a flashlight for emergency
use in MCR.
6. Items noted requiring attention have either
been corrected or punch listed.
7.  Bach Monday, switch the units which are operating
to standby and put the standby unit in operation.

12B-11

10/13/65

Init.

Date/Time

 

 

ANRRRRRRRRRER

T

|
Approved by _+ i .l 12B-12
[ | 10/13/65

 

Init. Date/Time

 

7.  (continued)

STOPPED

AC (LNST.
ATIR DRYER
MG SET (48v
Be BLOWERS
FOP

CcOoP

 

*CCP No. 2 should be operated fOT seven days each
month. (First Monday to second Monday)

*¥¥Switeh TF's only when heat lcad permits operating only

 

one Tan.
8. Calculate the cell leak rate. See procedure 3E
for model, .. . ...

Leak Rate £43 [1r

 
Approved by . o

g L 12B-13
\ 10/13/65
12B-3
OPERATIONS SUPPLIES CHECK LIST
(To be taken weekly by day shift technicians)

 

Work order number to be used for supplies is A-50865-95.
Init. DateZTime

 

Check for adequate supply of Polaroid film and
reorder when down to 50 packs. (ASA 3000 type
L7 from Chem. Stores.)

 

Check supply of gases.

Helium

2.1 Bottle - keep minimum of 10 (Order from
Mr. Simpson - phone 3-6476.).

2.2 Trailer - reorder when pressure reaches
500 psig. (Mr. Easter - phone 3-66Tk.)

2.3 Nitrogen -~ keep minimum of 20 bottles.
(Mr. Simpson - phone 3-6476.)

 

 

 

Check operations supply cabinets (electrical area
840") for the following items and reorder if nec-
essary.

3.1 Rubber gloves.

3.2 Sample bottles.

3.3 Rubber coat and apron.

3.4 Plastic bags, large and small.

3.5 Operations tags.

 
P
S

Approved byggfifik'; Vet

 

Check the hot change bouse for the following

items and order if necessary.

L.
k.2
L.3
hob

4.5
L.6
L.
4.8
e

Plastic bags - large..

Plastic bags - small.

Cleaning gauze.

Clean filter masks (minimum of 10)
(Bldg. 3550).

Caps and coveralls.

Tape.

Shoe covers.

Soap and tovels.

Rubber gloves.

k.10 Cotton gloves.

4.11 Cleaning rags.

Check for supplies in the HP emergency cabinet

(MCR) for items listed on the inventory card.

Chack in operations office for following items

and order as necessary.

6.1

6.2

6.3

Adequate supply of check lists and operating
procedures ~ especially ones used often.
Control room and building logs 1lzA-2A,
12A-2B.

Console log books. {Order from S. B.

Newman Printing Co., P. 0. Box 2029,
Knoxville. )

12B-14L
10/13/65

Init. Date/Time

 

 

 
  
 

v

Approved byfif§7ll, 5’”f/ffv‘u _ 12B-15

1 10/13/65
Tnit. Date/Time
6.4 Thermocouple log sheets (forms UNC 6676
UNC 6677).
6.5 MSRE data sheets and punch lists (forms
UNC 5928, UNC 5929, UNC 5879).
6.6 Sample analysis request forms (UNC 1910).
6.7 Radiation work permit (UNC 2779).

 

 

 

 

7. Check for adequate supply (one month) of water

treatment chemicals stored in the diesel house.

 

7.1 NAICO 360 (balls).

7.2 NAICO 215 (balls).

7.3 Potassium nitrite (KNOs).

7.4 Potassium tetrabvorate (KzB.O07).

e e b
————
——————

 

8. Check for adequate supply of 25% XOH (stored
behind Oz analyzer in diesel house). Order
from Iaing's Iab., Building 4500-SM, Rm. S-156,

 

phone - 3-1511.
,‘;;-"“7 h' /"
Approved byffj?}/%/iéflffibdng 12B-16
TAEIE 1254 YSALT INVENTORY AND TRANSFER DATA SHEET 1043/65

Before transfer or drain, check that level probe voltage
is 40 to 60 volts (On TB-8).

  
  

   
    
 
 
   
  

Procedure
&

  
   
 

Pos.
Tare

  

F
D
T Step No.

Start

  
   

  

Tinish

Transferred

Procedure
&
WR-FD2 Sstep No. Init.

tart
Finish

Trangfe d {

 

 

)i} . F . Procedure Date
& &
WR~FFT Step No.| Time Init.

Start

Finish

 

Transferred

 

. _ Procedure
S ‘ &
. 4q, ~-FPST Ste O.
tart
Finish

Transferred

C Pos. Pos. Procedure
Tare [Live &
W1 -- . Wt. WR-CDT St No.

1Start

Finish

 

Transferred :

s form is to be used for all transfers, £ills, and drains. The tares
should be set per master copy of building log before each reading. Assuming
that the tares have been set, the weight 1s calculated as follows: Wt. =
(x+y- 12.26) X F wvhere x & y are live manometer readings. F = T78.0 for FD-1,

qg;ggBEgfi%lfiggfu F = 58.3 for CDT. (Tare factors are 38.3 & 19.6 respectively.)

4
Approved by 55?;;53{2§4:;/fiH¢V\i 12C-1
v

10/13/65
12C RECORDERS AND INDICATORS

Numerous recording and indicating instruments are used throughout
the plant. In general, indicators are used where needed as guides TO
operation and where only periodic records are necessary. Recorders
are used where & continuous record of the variable is required or when
a trend would be helpful to operating personnel. In order that the
recorder charts are cf maximum value, proper functioning of the instru-
ment must be assured. This necessitates periodic inspection to assure
that the instrument is running, chart paper is installed properly and
is tracking, and that the pen is marking (or points printing). It is,
of course, highly important that the instrument never runs out of chart
paper without immediate replacement.

Since no timing devices are installed, the time should be carefully
marked on all operating charts at least twice per shift. This should
be at the start and near the middlie of the shift. When operating
conditions are changed or disturbances occur, the time and probable
reason for the disturbance or change should be noted.

The 12-8 shift will routinely remove charts from all operating
recorders each day at approximately OTOO_(exception ~ cams). If a
special experiment is in progress, it may be desirable to remove them
at different intervals. All charts removed on a given date are filed
together in a pigeonhole file in Building 7503. Charts are held in
this file for three weeks after removal from the recorders. Then they
are placed in boxes and sent to Laboratory Records for storage in
Building 4500. Each chart file box is given an identification number
and can be checked out through Laboratory Records at any time for study
of the contents. A file index is kept so that the location of the chart
from any instrument covering any period of time can be determined. When
special experiments are being run, the person in charge of the experi-
ment may have sections of chart removed at any time if this will facil-
itate analysis of the experiment. However, these sections of chart

should be filed in the same manner as other charts.
</
Approved by ,ffé;éiagiiééfzmflhx 12C-2
> \/

10/13/65

One person will be placed in charge of the chart filing systen.
It is his duty to do the following:

1. Fach day check all newly removed charts to see that they are
properly marked with recorder number, time and date of instal-
lation and removal.

2. Twenty-one days after removal from recorder, place charts in
a chart file box.

3. When a file box is full, transmit to Laboratory Records for
storage. Record the dates covered by the charts. Laboratory
Records will record the identification number of the file box
in the Chart File Index.

Referring to Charts.

 

Recent charts can be found in the pigeonhole file under the
date of removal. When a chart is removed, a slip telling who
borrowed what must be placed in the pigeon hole. Charts should
be replaced as socn as possible.

Charts not filed in the pigeonholes should be obtained from
the Analysis Group.

Details of Recorder and Indicator Operations are as follows:
1. Avoid parallax when reading.
2. Record pen reading rather than pointer on recorders.

(Exception - beryllium monitor in vent house.)

3. Mark charts where pen is inking.
4. Push reset buttons once per shift.

When a chart is removed, mark it with the recorder number,

time, and date of removal. If the chart covers some particular

experiment or test, record this information also.

6. When installing a new chart, mark it with the recorder number,
time, and date of installation.

Mo If a chart is cut in two, mark both edges with the time, date,

and recorder number.
e
ipproved by __ 7" ANy g 12D-1.

10/13/65

 

12D COMPUTER

The normal, permanent output of the computer is in the form of

Typewritten sheets from each of the four typewriters and full, or

partly full, reels of magnetic tape. During special experiments, graphs

mey be produced on the X-Y plotter as part of the output. In general,

all of this material will be permanently stored at the reactor site

with special arrangements as required.

1 TYPER OUTPUT

The preprinted log sheets used in Typer 2 must be replaced

once each shift using the detailed procedure in the Reactor
Operators’ Computer Manual. The completed sheets from the other
Typers may be removed at the convenience of the operators, depending
on the volume of paper generated. It is the responsibility of the
operators to insure that each sheet contains a calendar date to
identify the data. All typer sheets will be placed in the box
for completed data forms. Day personnel will file and subsequently
bind the sheets in chronological order by typer number and run
number for permanent storage.

2 MAGNETTIC TAPES

Megnetic tapes will be removed from the drives, as required,

according to the procedure in the computer manual. The identifi-
cation and removal of magnetic tapes should be recorded in the
control room log bock as a backup for other records. The operators
are responsible for adequate identification of all magnetic tapes
which they remove. 1In general, all magnetic tapes will be stored
in the tape cabinet in the computer room; full tapes will be filed
chronologically in the top of the cabinet,and blank tapes will be
stored in the bottom. Groups of partially filled tapes will be
consolidated periodically on single tapes and the partial tapes
returned to blank-type storage. Special arrangements will be made

if the storage capacity of the tape cabinet is exceeded.
Approved bgfifiggizgézkfiW/w\ 12D-2
S vV 10/13/65
3 GRAPHS
Graphs of reactor parameters may be made at will by reactor
operators or other personnel. Any graphs that are pertinent to
the reactor operation or experimental program will be stored at
the reactor site with other run data. The original graphs may
be stored as such or they may become the property of individual
experiments. If original graphs are to be permanently removed,

properly identified copies must be made for the reactor files.
  

“*‘ “a/ 10/7/65

 

Approved by .

12E TAGS AND SIGNS

It is the policy of all personnel at the MSRE to honor all tags
and signs and assume that they are vallid until definitely proven other-
wise. When it is determined that tags or signs no longer apply, they
should be removed. Removing them often requires the permission of the
person who installed them.

1 TAGS
There are only 3 types of official tags in use at the MSRE.

Others should be used only in emergency and should be replaced by

an officlal tag as soon as possible. Tags should be installed by

operations personnel only.

1.1 Operational Tags

 

During operation there are certain valves, electrical
breakers, etc. which are normally open or closed. When these
are extremely important or could cause operational difficulties
or hazards if improperly operated, an operational tag is
attached. (See Figure 12E-1 and 12E-2.) In keeping with the
color scheme used at the MSRE, tags on closed valves or switches
vhich are off (Figure 12E-1) are green, and those on open
valves or switches which are on (Figure 12E-2) are red. As
indicated the shift supervisor's permission is required to
remove the tag or operate the valve or switch. An entry is
made in the console log when an operational tag is removed,
and the tag is discarded.

1.2 "Do Not Operate" Tags

During maintenance it is often necessary to tag out valves

 

or switches for the safety of the reactor or personnel. A
"do not operate" tag is used for this purpose. (See Figure
12E-3.) These tags are also used for special procedures etc.
where additional information needs to be included on the tag
or on the procedure. The tag is red cardboard. The bottom
half has a white paper on top with carbon paper between 1t

and the red cardboard. ter the blanks have been filied in,
R o

 

©

KEEP VALVE CLOSED
OR SWITCH OFF

 

 

 

 

This is the normal position for this valve or switch
during operation. It should not be operated
without permission of the shift supervisor.

Item No.: Date

 

 

Signed

UCN — 5924
3 7-64)

 

 

 

Figure 12E-1
Approved by 6 1N 1o}$§é§

 

©

| KEEP VALVE CLOSED ’
| OR SWITCH OFF |

 

 

This is the normal position for this valve or switch
during operation. It should not be operafed
without permission of the shift supervisor.

ltem No.:___.___Dai'e

 

Signed

UCN -- 5923
(3 7-64)

 

 

 

Figure 12E-2
Approved by é é@ Fég&im

 

©

 

D0 NOT OPERATE

 

UCN - 5925
(3 7-64}

 

o — e — ———

Description

Item No.___ __ Work Order Ne.

 

 

Location

 

Reason for Tagging

 

 

 

Conditions Required to Remove Tag

 

 

 

 

Signod

 

Date

 

 

 

 

 

Figure 12kE-3

12E-4
10/7/65
fl
> RED CARDBOARD
-/
j
WHITE PAPER WITH
RED CARDBOARD
BEHIND AND CARBON
PAPER BETWEEN
-
2
Approved by <7 Nl o 12E-5
Y

10/7/65

1.2 (continued)
the white sheets and carbon paper are removed. The white
sheets are filed with the work request or the procedure. When
the work or the procedure has been completed, all tags are
removed. These are cross checked with the white slips to
assure that none were missed and are then discarded. The
valves or switches are then free to be operated as needed.

2 SIGNS

All signs should be kept current at all times. Permanent

signs, 1f not applicable, should be removed or covered until they

again are applicable. When temporary signs are installed, the

reason for the sign should be clearly stated, signed, and dated.
Y 13-1
10/21/65

 

 

13 MATNTENANCE AND CHANGES

Responsibilities of the MSRE operations group with regard to main-
tenance include recognizing the need, requesting the necessary work,
and coordinating operations and maintenance. The maintenance group
of the MSRE staff will schedule and arrange for the necessary materials
and manpower to do the work.

Becavse the MSRE is an experiment, operation will inevitably show
the need for some changes. These will be approved, made, and documented
with care equal to that exercised in the original design.

This section contains procedures whose object is to insure that
maintenance and changes are made in an orderly, efficient, and safe

manner.
Approved by _fifizfi?“

 

s
Ny 13A-1
"/ 10/21/65

13A MAINTENANCE

DEFINITION

 

Maintenance means repair or replacement of defective compo-

nents, cervicing of equipment, and alterations or additions which

do not come under the definition of modifications given in 13B.

PROCEDURE

The following procedure applies to all maintenance except for

emergencies which require immediate "first-aid."

2.1 Initial Request

 

2.

The initial request Tor maintenance 1s made through the
Punch List. Anyone seeing a need for maintenance describes
it on a punch list form (Fig. 13.1), available in the reactor
control room. The following instructions apply to filling
out the punch list form:

(a) Enter date of request.

(b) Describe location, equipment and work as specifically
as possible, using sketches where they would clarify
the request.

(c) At end of description, state when the job needs to
be finished.

(d) List any precautions known to be needed.

(e) Sign on line above "SIGNED."

Normally the requestor leaves the completed form on the
punch list clipboard in the reactor control room. If a high
priority is needed, the requestor contacts the Operations
Chief (0C) or Assistant Operations Chief (AOC) to expedite
action.

Handling by Operations Group

 

The Shift Supervisor periodically reviews the punch 1list
and assigns suitable jobs to shift craftsmen. A job 1s suit-
able for this type of handling if the job is straightforward,
has nc wide-reaching effects and can be handled by the shift

craftsmen without interference with thelr primary functilon,
13A-2
10/21/65

 

 

PUNCH LIST

TO T PRIORITY JDATE

LOCATION

 

 

 

 

 

EQUIPMENT. LINE NO., ETC..

 

 

 

 

DESCRIPTION

 

 

 

 

 

 

 

 

 

 

PRECAUTIONS

 

 

 

 

 

 

 

 

SIGNED:
Approval for Shift Craftsman to proceed of Work Request to be written

SHIFT SUFPERVISOR OQPERATIONS CHIEF OR ASSISTANT
Shift Craftsman has completed job

SHIFT SUPERVISOR DATE

 

 

UCN-5879
3 1-8%)

 

 

FIGURE 13.1
Approved by Vi ;“A/‘{Q‘é;;fi.f, 4o / ~ ‘,-“f‘i; l3A-3

2.3

7 ~ 10/21/65

which is to take care of emergency or essential work.

At the beginning of each day shift, the OC or AOC reviews
the punch list and removes jobs which will not be done by
shift craftsmen. He puts aside requesgts which he cannot
approve and notifies the requestor of the reasons for denying
approval. He signs the punch list forms for approved requests,
checks priorities and passes the forms on to the MSRE Mainte=
nance Supervisor. Priority may be one of these three:

(a) Urgent

The work is or could become the critical path
and should be completed as soon as possible.

(b) Medium

The work should be completed as soon as it can
be done without delaying work having an URGENT prior-
ity.

(¢) Low

The scheduling of this work is at the convenience
of the craft groups.
Execution of Simple Jobs

"Simple" here means that the job is not hazardous to the
craftsmen, does not interfere with reactor operations, and
does not otherwise require extensive arrangements. No form
other than the punch list is used for these jobs. The pro-
cedure is as follows.

(a) The Maintenance Supervisor checks that the priority
is in line with other work in progress, and resolves
any conflict with the OC or AOC.

(b) If necessary, the Maintenance Supervisor checks that
the required material is available.

(¢) The Maintenance Supervisor addresses the punch list
form and turns it over to the executing group (nor-
mally P and E or I and C).

(d) Immediately after the work is finished, the craft

foreman initials the form and returns it to the
   

Approved by [ AN 13A-4

10/21/65

(d) (continued)
Maintenance Supervisor.

(e) The Maintenasnce Supervisor checks the job, marks the
punch 1list form "completed" and returns it to the
control room.

2.4t Execution of Complicated Jobs

 

A job is "complicated" if it could interfere with the
operation of the reactor or is hazardous. A form called
"MSRE Work Request” (Fig. 13.2) is used in connection with
this type Jjob. The procedure is as follows.

(a) The Maintenance Supervisor checks the priority as in
"simple" jobs.

(b) The reactor maintenance group assigns & work request
number and enters tThis on the Work Request form along
with a description based on the punch 1list description.
Where necessary, 'CAUTION - CHECK WITH OPERATIONS
BEFORE PROCEEDING" is stamped on the work request.

The original of the work request is held in the
Maintenance Supervisor's file; coples are made as
necessary. One copy of the work request goes to the
craft group involved, one to the AOC and one to the
oC.

(c) The Maintenance Supervisor, after consultation with
the executing craft group, estimates the time required
and passes this information on to the Operations Chief.

(d) The OC reviews the request, initials his copy and
passes it on to the MSRE Shift Supervisor.

(e} If the job has a high priority, the Maintenance
Supervisor coordinstes preparations of the craft
group and operations. Otherwise the craft super-
vision will schedule the wecrk on the basis of re-
quested date of completion, relative priorities of
other jobs, and available manpower. In such cases

the craft supervision notifies the Shift Supervisor
13A-5
10/21/65

 

 

MSRE WORK REQUEST

WORK ORDER NUMBER WORK REQUEST NUMBER PRIORITY DATE

 

 

 

ISSUED TQ EQUIPMENT, SYSTEM, ETC.

 

 

DESCRIPTION OF WORK

 

 

 

 

 

 

AFPROVED MAINTENANCE APPROVED OPERATIONS

 

PRECAUTIONS

 

 

 

SHIFT SUPERYISOR'S APPROVAL TO PROCEED
STARTING DATE OR TIME ENDING DATE OR TIME SIGNED

REACTOR DIVISION | REACTOR DIVISION
CRAFTSMAN MAINTENANCE OPERATIONS

WORK COMPLETED

WORK INSPECTED

WORK APPROVED

 

REMARKS

 

 

 

 

UCN-3824

DATE COMPLETED
(3 1-65)

 

 

FIGURE 13.2

 
   

13A-6
10/21/65

Approved by

(e) (continued)

a day in advance of scheduled work.

(f) Before work starts, the MSRE Shift Supervisor will
make necessary preparations such as shutting down
machinery, closing valves and opening switches. He
uses MSRE tags where advantageous, and attaches the
white copy of the tag to the Control Room copy of
the work request. (MSRE tags and their use are
described in Section 12E.)

(g) When all preparations have been made, the Shift
Supervisor signs control room copy and the crafts-
man's copy of the work request, permitting the crafts
to proceed.

Columns are provided for indicating when the
work can be started and when the work must be com-
pleted or stopped. The shift supervisor enters this
information and any additional precautions or restric-
tions on the craftman's copy as well as the control
room copy.

(h) As soon as the work is completed, inspected, and
approved by craft supervision and the MSRE Mainte-
nance Supervisor, the signed copy is turned over to
the Shift Supervisor.

(1) The Shift Supervisor removes tags, compares these
with the white slips attached to the WR, and makes
an operational check of the job.

e changes control room copies of affected
drawings and indicates this on the work request and
briefly states what was done to check out the job.
The work requests are then turned over to the
Assistant Operations Chief or Operations Chief.
Should the operatilional check show that more work
needs to be done, the Shift Supervisor contacts the

Maintenance Supervisor who arranges for the completion
Approved by Aflzg?r

(1)

(3)

 

é'// o, 13A-
-:4/4/ L 10/21/6%

(continued)
of the job.
The Maintenance Supervisor keeps a record of all

completed work requests. In addition, on any job
relevant to the performance or service of important
machinery or equipment, he files a copy of the com-

pleted work request in the folder for that piece of

equipment.
g
Approved by Afififizzzflékgzflflnfih 13B-1
T v

10/21/65
13B MODIFICATIONS

1 DEFINITTION

A modification is defined as = change in the physical plant

 

which produces a significantly different characteristic or function
in any component or systenl.
2 PROCEDURE
2.1 Redquest
A person should formally request any modification which
he believes to be worthwhile or to possess advantages at least
worth considering. The requestor describes the change on an
MSRE Change Request Form (Fig. 12.3) and submits it to the
MSRE Design Liaison Engineer.
2.2 Review
No modification will be made before adequate review and
approval. To insure that all aspects are considered, a per-
son responsible for each area affected by the change will be
asked to review and approve the change. The MSRE Operations
Department Head will review all requests and will determine
what other reviewers are necessarys.
When the Design Liaison Engineer (DLE) receives a request,
he assigns it a2 number. He then has the request typed on a
Change Request Form. A copy of the typed request goes to the
MSRE Project Director for his consideration. The typed re-
quest goes to the Department Head, who checks the appropriate
boxes under "Approval to Proceed"” and routes the request to
reviewers in the MSRE area (Buildings 7503 and 7509). When
the internal review is completed, the form comes back to the
DLE, who sends it out for external reviews which may be
required. After external reviews, the request is again
returned to the DLE. He sends a copy of the request, with
approvels and comments of the reviewers, TO the Reactor

Division Director for his information.
13B-2

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

10/21/65
MSRE CHANGE REQUEST
SUBJECT NUMBER
DATE REQUESTED
TYPE CHANG REQUESTOR
To DATE NEEDED T
[ ] PERMANENT (] TEMPORARY
DESCRIPTION AND PURPQSE
DOCUMENTS AFFECTED
APPRCVAL TO PRCCEED
INIT. DATE INIT. DATE

) MSRE OPERATIONS O
[ ] MSRE MAINTENANCE ! -

{
MSRE DEPT. HEAD \ O
(] RD DEVELOPMENT [ ] MSR PROJECT DIRECTOR %
11&C DESIGN J_ ] REACTOR DIV. DIRECTOR
COMMENTS OF REVIEWERS

ASSIGNMENTS

STATUS
| DATE DATE

 

[ "] DESIGN INITIATED

  

 

 

"] DESIGN COMPLETED

[ J PROCUREMENT INITIATED

REMARKS

[] WORK COMPLETED

 

    
 

 

 

[_] ORIGINAL DOCUMENTS CHANGED

[_] CONTROL ROOM DOCUMENTS CHANGED

 

 

 

UCN-6820
3 7-8%)

 

 

FIGURE 13,3
['\i'.‘)]_)'['(_,"\f@d_ by L =

2.3

 

Y = 10/%?;62

Any reviewer may either approve or not and may suggest
alternatives. If he disapproves he should indicate his reasons
under "Comments"” or on a separate gheet which becomes part of
the request. The reviewer may register his views on alterna-
tives in the same way.

The DLE will maintain a file of change requests whicia
will reveal the status of all requests at any time.

Action

If all reviewers approve a change, the DLE will arrange
for necessary desgign work; on jobs requiring no design, he
will arrange with the MSRE Maintenance Supervisor to get the
work done. Changes not unanimously approved or for which
alternatives are proposed must be arbitrated. The DLE will
attempt to obtain agreement, but if this is impossible the
MSRE Department Head or the Project Director will decide what
to do about the change.

On change requests where only the desired result is
specified, "Approval the Proceed" means merely that the re-
viewer approves study or design of means to the desired end.
Responsibilities for design will be listed under "Assigrments. "
After the design is completed, the MSRE Department Head or the
Project Director must approve the design before the change is
actually made.

When a modification is completed, the DLE is responsible
for seeing that affected documents are changed. Changes in
Control Room documents will be made by the MSRE Operations

Chief or his assilgstant.
Approved bgc /fl/%;/ e 13C0-1

10/21/65
13C CHANGES IN OPERATING PROCEDURES

These operating procedures are for the instruction of and routine
use by reactor operators; the copies being put vo this use must, there-
fore, be kept up-to-date, reflecting changes in the system or in ils
operation. Changes must be made only after adequate review and approval,
and it must be possible to tell if a copy contains alli autiiorized changes.
The procedure described in the following paragraphs is aimed at this goal.

The operating procedures used during prenuclear testing were written
by members of the MSRE Operations Department, most of whom had partici-
pated in the design arnd development of the MSRE. A review of existing,
tried procedures was made after Run PC-1 by the operating engineers, and
recommended changes were incorporated as approved by the Operations Chilef.
After Run 3, all sections of the Operating Procedures were completed and
approved, and copies were issued. Copies were elther bound or loose-
leaf, according to the needs of the recipients.

There is one loose-leaf copy of the Operating Procedures, the Master
Copy, in which changes are made only by the Operations Chief (or the
Assistant Operations Chief acting in his stead). The Master Copy is kept
in the Operations Office (Room 3, Building 7503). Eech of the four crews
has a Crew Copy, in which changes are made only by the Shift Supervisor.

Anyone seeing the need for a change in the Operating Procedures
submits a request to the Operations Chief on an MSRE Change Request Form.
A brief description of the purpose of and justification for the change
must go on the form.

The Operations Chief reviews each request and may ask others to
review it and give théir approval or advice. If he approves a change,
the Operations Chief enters the change in the Master Copy and notifies
the Shift Supervisors by means of a list on the Control Room Bulletin
Board. The list includes date of change, location (page mimbers ), brief
description of change, whether or not revised pages will be issued, and
a place for each Shift Supervisor to initial.

As soon as possible after notice of a change is posted, each shift

supervisor will study the change in the Master Copy. If the change 1s
Approved by125:5;222’%?2§gffigzfi1 130-2
‘ 7

10/21/65

brief, he will write in the change in the Crew Copy of the Operating
Procedures. (An up-to-date Crew Copy will be maintained by each crew
for its information and use.) If it is a lengthy change, the Shift
Supervisor will circle with red pencil the superseded portion in the
Crew Copy and mark it "Revised -- See Master,” with the date. The
Shift Bupervisor will then instruct his crew with regard to the change.
After each crew member has been instructed and has read the change, the
Shift Supervisor will initial the change list on the bulletin board.
When revised sheets are distributed, marked pages in the Crew Copy will
be replaced by the Shift Supervisor.

Whether or not revised sheets are issued depends mainly on the
length of the change. If a change can be easily and clearly transcribed
by the Shift Supervisors to the Crew Copies, retyping and issuing re-
vised pages is not compulsory or desirable. If pages are retyped, copies
will be sent to persons who need to have an up-to-date version of the
Procedures.

Every page of the Operating Procedures has the approval and date
at the top, as on this page. Revised pages bear the revision date; this
applies to retyped pages and also to marked pages in the Master Copy and
Crew Copies, where the date is changed when the change is written in.
Holders of loose-leaf copies of the Procedures can tell if their copy

ig up-to-date by comparing page dates with those in the Master Copy.
ot
Approved by gfifizzzzéké%%%q/n 13D-1

10/21/65
13D CHANGES IN COMPUTER PROGRAM

One of the advantages of the computer-logger over conventional
recorders is that its functions can be readily changed to meet the
changing needs of the Reactor Experiment or to improve the operation
of the computer. Changes in the computer program are made by a pro-
grammer after proper approval.

Anyone recognizing the need for a change, describes it on a Change
Request Form. Requests from the Operations Group ge first to the
Operations Chief; others send their requests to the head of the Nuclear
and Mechanical Analysis Group of the MSRE Operations Department. Re-
guests are handled as described in Section 3H of the Operating Pro-

cedures.
  

Approved by .

 

Wf/xzx/—q 13E-1
vV 10/21/65

13E REVISION OF APPROVED DOCUMENTS

The MSRE has been the subject of many documents of all kinds, many
of them preliminary and now out-of-date. "Approved documents' are those
which are intended to give an accurate, up-to-date description of the
MSRE and its operation. Because the operator needs to make use of these
documents in training and operation, they must be revised to keep up as
nearly as is practical with changes in the system.

A set of up-to-date approved documents will be kept on file at the
MSRE. They include:

(&) all published parts of the MSRE Design and Operations Report,

(b) drawings,

(c) instrument application tabulations,

(d) instrument specifications,

(e) switch tabulations,

(f) line schedule,

(g) thermocouple tabulations,

(h) design data sheets.

Revision of these documents to reflect modifications in the system
is routinely handled as part of the procedure for modifications (Section
13B, These Procedures). Other revisions will be in the nature of correc-
tions. Anyone discovering an error or recognizing a need to bring an
approved document up-to-date should notify the MSRE Department Head in
writing of the regquired change. He will arrange for errata sheets or

other corrections.
-

\O CO—1 O o o H

ORNL~-TM-908

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