ORNL-TM-3253.txt

  

ED BY DIIE APR 1 fy7f

RECE)V

 

  

 

OAK RIDGE NATIONAL LABORATORY %@&STER

- operated by
UNION CARBIDE CORPORATION

for the

U.S. ATOMIC ENERGY COMMISSION
ORNL- TM- 3253

DATE - February 10, 1971

MSRE PROCEDURES FOR THE PERIOD BETWEEN EXAMINATION
" AND ULTIMATE DISPOSAL
(Phase III of Decommissioning Program)

 

R. H. Guymon

ABSTRACT

This document describes the condition of the MSRE and specifies
procedures to be followed after the post-operation examinations and
before the ultimate disposal of the fissile and radioactive material in
the reactor. .The fuel salt will be kept frozen in the sealed drain tanks,
within secondary containment whose only opening is through filters to
a stack. OSurveillance will consist of remote monitoring and daily visits
by X-10 plant personnel. Personnel access will be controlled by the
security fence around the reactor building. The MSRE Procedures specify
remedial actions for abnormal conditions. Also specified are procedures
and responsibilities for maintensnce, modifications, and removal of

surplus equipment.

- Keywords: molten-salt reactors, MSRE; procedures, storage,
surveillance, administration, containment, flowsheets, maintenance,

operations, ORNL, plans, testing.

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

PHISTRIBUTION OF THIS DOCUMENT IS UNLIMITEP
»

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£

iii

Table of Contents

ABSTRACT

A. INTRODUCTION .

B. DESCRIPTION AND NORMAL OPERATING CONDITIONS

C. SURVEILLANCE . . . v ¢ ¢ & ¢ ¢ o o o o o

Do DATA v v v v v v v e e e e e e e e e e e e
1. Control-Room Log . . . ¢« ¢ & v ¢ v v ¢ v o o« o @
2. Periocdic Logs . ¢ ¢ ¢ ¢« v 4 ¢ o ¢ o e 0 o

E. ABNORMAL CONDITIONS . . . . . .

F. POWER OUTAGES. . & & & & v v v o o o o o o o &«

Gl ANNUAL TASKS - . » - - a - - . - - - - - - - - * - -
1. Recombine Fluorine by Heating the Drain Tank . .
2. Pressure Test of the Reactor and Drain Tank Cells
3. FD-2 and FP Pressure . . « v v v v o o « o o « o
b, Ventilation System . . . « v v v +v v v v o o o o .
5. RC Air Activity. . « ¢ ¢ ¢ v v ¢ v v v v v . W
6. Sump PUMPS « - + + + + ¢ v 4 4 e e e e e e e .
T. MiscellaneoUs . . . + v . v v o & o o o o o + o«

H. MAINTENANCE AND REPAIRS . + + & v v v o « o .« . .

I. REMOVAL OF EQUIPMENT _OR INSTRUMENTATION . . . . . .

J. ACCESS CONTROL « 4 & o o s s o o« = o o o o o o « o o 4

K. ORGANIZATION AND CHANGES . + v v v v v o v o o o o . ,

REFERENCES « & « v v v v v o e oe o n e e e e e e e e i

 

 

 

 

 

 

 

 

: is report Was prepared as an sccount of work
o 'srphoifié;or:zd by the %nited States Government, Neither

1} the United States nor the United States Atomic Energy
. " { Commission, nor any of their employees, nor any of
© 1 | their contractors, subcontractors, or their employees,
| makes any warsanty, express or implied, or assumes any

-Jegal Mability or responsibility for the accuracy, com-

|7 product or process disclosed, or represents that lts use
+1-would not infringe privately owned rights.

 

"  pleteness or usefulness of any information, apparatus, |

 

 

 

Fa o F

PASTRIBUTION OF THIS DOCUMENT [S UNLI}

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A. INTRODUCTION .

The retirement or decommissioning of the MSRE involves several phases.
Phase I is the period between the end of power operation and the post-
operation exeminations, which is Phase II. Phase III is the interim period
between the completion of the examinations and the final disposal which
is Phase IV. | |

During Phese III, some_of‘the information given in the MSRE Design
and Opérations Reports (Refs. 1 through 9) and the facility drawings will
still be applicable. Much of the eqfiipment will not be in service, however,
and most of the procedures which were followed during operastion will no
longer be‘applicable. This report describes the systems which will be
used and specifies the normal conditions and surveillance required dufing
Phase III. It also lists the more probablé_abnormal situations which
could dévelop and prescribes remedial actions. The system of access controi, 
apprbvals required for maintenance and changes, and respdnsibilities are
delineated. This document supersedes all previous operating procedures
for the MSRE. '

B. DESCRIPTION AND NORMAL OPERATING CONDITIONS

Most of the equipment and instrumentation involved during Phase III
is shown in Figure B-1. Pertinent information on the instruments in
service is given in Table B-1. Plan views of the building showing evacu-
ation routes are shown in Figure B-2. The most often used abbreviations
are given in Table B-2. Master, marked-up,  copies of the flowsheets
(D-AA-A-40880 to 40890), the instrument application drawings (D-AA-B-40500
to 40515) and the electrical power distribution drawing (E-2079L4-ED-153-D)
will be kept up to date and avaeilable in the MSRE control room in |
Building 7503. Another up~to-date set of drawings will be kept in the
outermost room of the office building (Room 17, Building 7509).

About one-half of the fuel selt (5,460 1bs) is stored in FD-1 and
the other half (L4784 1bs) in FD-2. All of the flush salt (9,460 1bs) is

 

 
 

 

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———

TZAY

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I oXD HCV-575
_—o#-D HCV-545

 

 

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ORNL DWG. 71-2095

 

 
 
   

 

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@_. DRAIN TANK CELL % I FIGURE B-|
T MSRE FLOWSHEET
T T T Twaug yameesn _gav"l = L 1 t FOR PHASE IO
‘ L : :
' TO WASTE TfiN_lf a;‘? E
_ e I
’ LeP 2-8-N
Fig. B-1l. sheet for Phase ITI

 

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MSRE Flow

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B

Table Bl

*} A

INSTRUMENTATION

 

 

 

 

RS-81-C

All annnnciators repeat at ORNL Central Waste Monitoring Facility (Building 3105).
See calibration curve for conversion to flow.
High activity indication (>20 mR/hr) on either RSS—SGS-B or -C will close HCV~-565.

HERN

Range switching is provided.
Monitoring Facility (Building 3105).

 

Read-Out Instrument Primary Element Annunciator*
Switch
No. Location Range No. Varidblg-Mbnitored No. No. Setpoint

FI-S1 Stack Pnl. O-1 in. HpO = FE-S1 Stack Flow

LI-RC-C ' TR 0-20 in. Hzo LE-RC-C RC Sump Level

LI-DTC-A1 TR " LE-DTC-AL  DIC Sump Level

LI-FSC-A TR 0-52 in. Hp0 LE-DC-C  DC Sump Level

LI-FSC-A TR | " LE-FSC-A  FSC-Sump Level

?_Jni FSC-A TR " LE-TC-A  TC Sump Level
LI-FSC-A TR " LE-SC-A  SC Sump Level
| LI-FSC-A TR " LE-WIC-A  WIC Sump Level |

e e -—~  LS-PRS Pump Room Sump Level XA-SD-8  LS-PRS ¢+

PI-ST2B ~ ACR 0-50 psig  PT-572B  FD-2 Pressure XA-SD-1 PS-572 42 psig
PI-589A  ACR 0-50 psig  PT-592B FP Pressure  XA-SD-2 PS-589  40.5 psig
PI-92TA  Stack Pnl. -8-0 in. Hy0 PI-92TA Stack Filter Inlet Suction XA-SD-3 PS-927 4-1 in. Hy0
PI-RC-A MCR -15-50 psig PT-RC-A RC Pressure XA-SD-4 PS-RC-1 41 psig
RI-565-B ACR 0-100 mR/hr RM-565-B  RC Air Activity XA-5D-5 RS-565-B 420 mR/hr
RI-565-C  ACR 0-100 mR/hr RM-565-C  RC Air Activity XA-SD-5 RS-565-C  +20 mR/hr
RI-S1-A - ACR ###%  RM-S1-A = Stack B,y activity XA-SD-6 RS-S1-A <6000 c¢/m
RI-S1-B  ACR. . #sx®  RM-S1-B Stack o activity ¥A-SD-6 RS-51-B <6000 c/m
RI-S1-C ~ ACR #AN®  RM_S1-C Stack Iodine Activity XA-SD-6 | <6000 ¢/m

These also indicate as well as annunciate at the ORNL Central Waste

 
Table B~1 Instrumentation

(continued)

 

 

 

. Read-Out Instrumeht Primary Element Annuncia.tor*
Switeh .
No. Location Range No. Variable Monitored No. No. Setpoint
RI-TO01 Hi Bay 0-5000 cpm RM=TOO1 Hi Bay Constant Air Monitor XA-SD-7 RS=-TOO1 4000 cpm
RI-T012 Hi Bay 0-25 mR/hr RM-T012 Hi Bay Monitron XA-SD-T RS-T7012 25 mR/hr
TR-SD-1-1 ACR 0-1000°F TE-FD1-10A FD-1 temp. ~- Probe
TR-SD-1-2 ACR 0-1000°F TE-FD1~5 FD-1 temp. -- Bottom
TR-SD-1-3 ACR 0-1000°F TE-FD1-15 FD-1 temp. —- Lower side
TR-SD~1-4 ACR 0-1000°F 'TE-FD2-19A FD-2 temp. ~- Probe
TR-5D-1-5 ACR 0-1000°F TE-FD2-5 FD=-2 temp. -- Bottom
TR-SD—l-G ACR 0-1000°F TE-FD2-15 FD-2 temp. -- Lower side
TR-SD-1-T ACR 0-1000°F TE-FFT-4 FFT temp. -- Bottom
TR-SD-1-8 ACR 0-1000°F TE-FFT-11 FFT temp. == Lower Side
TR-SD-1-9 ACR 0-1000°F TE-FFT-7 FFT temp. -- Mid Side
TR-SD-1-10 ACR 0-1000°F TE-DTC-6 DTC temp, =- SE
TR-SD-1-11 ACR 0~1000°F TE-RC-1 RC temp, = SW

 

. .
All annunciators repeat at ORNL Central Waste Monitoring Facility (Building 3105).

» ‘
Range switching is provided. These also indicate as well as annunciate at the ORNL Central Waste
Monitoring Facility (Building 3105). '

. RRR

 
ORNL-DWG 71-998

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

     

 

 

    
 

MAIN
CONTROL ROOM HOT CHANGE ROOM

 

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LIQUID
WASTE
CELL

Lt Ta

 

PLOT PLAN— MSRE AREA

| ' . ¢ ./ \ - - ’I’
T e ; \ REACTOR SAMPLER ™~ pumMP ROOM -
y CELL ENRICHER  gE|ow "z
"‘ N \ - ~ PANELS BUILDING 7509
i 1 | . ~ 1 i —— OFFICE AREA
{ 4 ’ | ’ | I \
\ . ~ DRAIN TANK CELL
> \ PARKING ! N
g e s e e e | g 4O \ H fl f Hgggg
3 \ WIND i REMOTE
= DIRECTION - b x {
> - ‘ MAINTENANCE
z \x ' ARROW ——@ | j CONTROL ROOM
S B e e x N ; _ ELEVATION 862ft Oin. D
= 75094 Xorefax——rx :
g : \ _ i BLDG. 7503 — 852-ft LEVEL
. \ } '
s Q X _ ;
\ o 8 /|z| e Al ) \ O S\\ ,;___.”1 "a* uP
- — é A" ' % STACK h p T oI
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NORTHI N - ' BATTER* D NI BN
GATE | N / Es=s=ds Lo N&;. M,
> W b x ‘-:.‘-_:.‘__.\ I.\ -
/ ) L outh P ' SERVICE e U
N uGll ISOUTH RWM \§\ ~ \\\')>
| " D o \ f oatE \t"—-:==-'____ =/ \\; 7
f DIESEL\ ~ r{," " BLOWER 1 / s mmsmr\z;— v
House_X } f Hou / l -— -—— == | NESA AND
an I | I:I / yd DOWN OIo I W ‘ " SESA BELOW
HEATER - '.:'.'. I | ]
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| ‘ i ///”’ _—- | _ SPECIAL
. ' ‘ jRA Y EQUIPMENT
: ROOM
T : REMOTE |
~—— '] MAINTENANCE F REACTOR
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T —~ ‘ E-:: Sp e A T e S A
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DECONTAMINATION Sroe |l COOLING
CELL -——/ PROCESSING CELL WATER 4 |
EQUIPMENT ——
SWITCH ROOM Qi
——|‘ HOUSE ; ]

 

BLDG. 7503 —840-ft LEVEL

Fig. B-2. Emergency Evacuation Routes

 

 

 

 
 

ACB
ACR
BH
CB
cC
CDC
CDT
CT
DC
DH
DTC

FSC
ST
HB

HCP

T & ' : '
- "' . e

Table B-2

EQUIPMENT AND LOCATION ABBREVIATIONS

Auxiliary Board MB Main Board
Auxiliary Charcosal Bed MCR Main Control Room
Auxiliary Control Room NESA North Electric Service Area
Blower House PR Pump Room
Charcoal Bed (main) PRS Pump Room Sump
Coolant Cell RC Reactor Cell |
Coolant Drain Cell RMC Remote Maintenance Practice Cell
Coolant Drain Tank SC  Equipment Storage Cell
Cooling Tower S1 Stack
Decontamination Cell SESA South Electric Service Aresa
Diesel House SER  Special Equipment Room
Drain Tank Cell SF Stack Fan
Fuel Drain Tank SFA  Stack Filter (fan) Area
Fuel Flush Tank SH Switch House )
Fuel Storage Cell - 87T Service Tunnel .
Fuel Storage Tank TC Spare Cell
High Bay TR Transmitter Room
Heater Control Panel VH Vent House

WR Water Room

WT Liquid Waste Tank

WIC Waste Tank Cell
"

x)

x

stored in FFT. The salt is at ambient temperature and pressure with all
heaters turned off. The salt f£ill lines (104, 105, and 106) have been
severed and are blanked in the drain tank cell. Salt is frozen in the
transfer freeze valves (107, 108, and 109). The equalizer line (521)
between the tanks and the fuel circulating system has been blanked ih the
drain cell. The helium supply lines (572, 5T4, 576) are capped. The
vent valves (HCV-573, =575, -5TT, and -533) are open (since they are fail-
open valves) but HV's-5L2, -522A, -522B, -538B, -571B, and -561 in the
vent house are closed. Thus there normally is no purge or vent from the
tanks. The drain tanks and the flush tank gas spaces are interconnected
through the vent valves and the equalizer valves (HCV-5hk, -545, -5L46).
The pressure in the tank syspem is indicated and annunciated by PIA-5T2

-in the auxiliary control room. The drain tank and other temperatures

can be read on TR-SD-1. o

The fuel circulating system contains only residual amounts of flush
salt. The system was opened at the reactor, fuel pump, heat exchanger,
and line 103. These openings'were sealed in various ways and were shown
not to leak exceseively at 5.psig. Since some of the heat exchanger tubes
were cut out, the_main coolant salt lines (200 and 201) communicate with
the fuel system andwere.tfierefore welded shut Just outside the reactor
cell. The system is at embient temperature and pressure. The helium
supply lines (516, 592, 593, 596, 589, 599, and 600) are capped. The
main vent line (522) is closed by HV-522A and the upper offgas line (524)
is capped 1n ‘the Special Equlpment Roomn. 'The pressure is indicated and
annunC1ated by PIA—589 in the Auxlllary Control Room.

The coolant salt (3, 575 1bs) is in the coolant draln tank, at ambient
temperature and pressure. . Freeze valves 204 and 206 are frozen to separate
it from the coolant c1rculatingrsystem. The helium supply valve (HV-
511B) is closed and the vent line is blanked off to isolate the tank.

‘The coolant circulating eysfem]cbntains only residual_amounts of

- coolant salt. It has beefi_opened in several places and is lightly sealed

(masking tape). There are ne,heliUm inputs to the system or vents from
it. T "
The main charcoal beds are isolated by valves 522B and 55TB. The
auxiliery charcoal bed is isolated by valves 561 and 562A.
 

 

 

The reactor and drain tank cell membranes are sealed and the blocks
are secured. The ventilation valves (930B and 955B) are closed and locked.
The cells are vented to the stack through line 565. (HCV-565 is kept open
by pressure from a cylinder of nitrogen.) Activify in the line is moni-
_tored by RIA-565 B and C. High activity indication on either detector
'will close HCV-565 and annunciate in the auxiliary control room. All other
lines and penetrations into the cells are mechanically sealed. _

Steck fan SF-1 is in service and SF-2 is in standby (damper 925 open
and 926 closed). All three stack filters are in service. IMOst of the
‘building ventilation flow is from the high bay with smaller amounts from
other areas including the chemical processing cell. (The relative distri-
bution is not critical.) The stack flow is indicated by FI-S1 at the stack.
The pressure at the inlet to the filters is indicated and annunciated by
PIA-92TA. The a, B-Y, and iodine activities in the stack are indicated
and annunciated in the auxiliary control room and at the ORNL Central Waste
‘Monitoring Facility (CWMF).

All water lines to the reactor and drain tank cells have been discon-
nected. The water levels in all cell sumps can be checked using the bub-
bler level indicators, dbut nd ennunciation is provided. The waste tank is
essentially empty and can also be checked using & bubbler level indicator.
The pump-room sump, which collects water from the filter pit, french drains,
etc., is automatically pumped to the drainage ditch by the sump pumps .

High level in this sump is annunciated. | |

The fire alarm and sprinkler system is in service and maintained by

the ORNL fire department.

C. SURVEILLANCE

| Surveillance of the MSRE shall be sdequate to prevent the development
of any condition that would threaten personnel safety or the continuity of
. other ORNL activities. |

Radiéactive and fissile materials are so contained and situated that

criticality is prevénted and the probability of any significant release to
9

n

the environment is extremely small. The potentials for increasing tempera-
ture and pressure in the'containment or the development of other potenti-
ally damaging conditions are limited'so that such conditions can arise only
slowly, if at all. Thus the continuous presence of personnel at the reac-
tor site is not required. Surveillance therefore consists of scheduled
visits for data-logging ahd'checking plus the.COntinuous'monitoring at the
ORNL Central Waste Monitoring Facility of key signals from the MSRE instru-
mentation. | |

Each day a member of the ORNL Central Waste Monitoring Group shall
enter the reactor building to mske observations as required on a Daily Log
Form. During the last week'bf each monthia qualified member of the Reactor
Division shall make an inspecfiidnof the reactor building, record data, and
make checks as required on a quthly Log Fofm. Equipment and instrumenta-
tion shall be maintained on a regular”schedule ahd as requifed by personnel
of the ORNL Plafit'and Equipment‘Division and Instruments and Controls
Division.

When any of a selected list of variables goes out of limits (prescribed
in Table B-1) alarms occurrboth‘in the reactor building and at the ORNL
Central Waste Monitoring Facility in Building 3105. When an alarm occurs,
one person from the group on duty at the CWMF shall go to the MSRE site,
enter the main control room.and take appropriate action to restore normal:
conditions. - o |

Corrective actions for foreseeable abnormal situations are prescribed

in Section E of these Procedures. In addition, experienced former members

of the MSRE opératiohs'staff shéll:be designated and availfible on call for

(See Fig. K-1.)

assistance in meéting”néedsithatlmay arise. |
~ The ORNL Plant Protection Division provides prdteétion against entry

by unauthorized personnel ($ée Section J) and against fire damage.
 

 

10
D. DATA

1. Control-Room Log | | |
Every significant event or action affecting the reactor shall be re-
corded in a Journal-type logbook that is kept in the control room. Some
items which shall be included in this 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 com—
pleted.

Changes in setpoints df switches.
Annunciations, and action teken.
Abnormal conditionsror malfunctioning equipment found.

Maintenance and other non-operational jobs done.

The person who makes an observation, or takes action, or is in charge
Iof any Job shall be responsible for seeing that én entry is made. Log
entries shall be sufficiently descriptive for others to understand and
each shall include time, date, and the name of the person making the

| entry. | _
| Carbon copies of the logbook sheets will be removed when the monthly

log is taken end will be stored in a file cebinet in Room 17, Building 7509.

2. Periodiec Logs _ _ , -

The Daily Log includes recording various readings as indicated on
Form D-1. This form prescribes "Log Limits" and identifies therappropriate
corrective action if a variable is outside these limits. (Corrective
actions, identified on Form D-1 by a letter, are detailed in Section E of
these Procedures.) .

The Monthly Log, which shall be filled out during the monthly in-
spection, is Form D-2. This form requires reading the salt tank temperatures,
the waste tank level and T sump levels. It also has spaces for indicating:

that other routine mofithl&'taSks have been done.
)

Tocation ACR

{ Readout

Alarm Limits

|Log Limits

_|What to do if,
10ut of Limits

{Init.|Date/Time

 

11

Form D-1
DAILY LOG — PHASE III

, - ACR ACR ACR
Description FD-1 | FD-2 "FFT DTC -T
Element! TE-FD-1-19A | TE-FD-2-19A| TE-FFT-4 |TE-D
TR-SD-1-1 § TR-SD-1-4 |TR-S5D-1-T7}TR-SD-1-10
no alarm no alarm | no alarm|{ no alarm
<200°F <200°F <200°F . <150°F

A . B. - C i D

Re
| F

« .
See Section E.

TX-4413

ACR | ACR
RC T RC Press.
TE-RC- | PT-RC-A
TR-SD-1-11{ PI-RC-A
no alarm |+ 1 i
<1 -2 to +0.

E ' F

 
 

12

Form D-1
DAILY LOG — PHASE ITI

{Tocation TACR ACR - ACR
Description FD-2 Press FP Press RC Activi Stack Activi

|Primary Element | PT-5T2B PT- RM-565B RM-565C B-y o I,
5Readout. PI- PT- RI- TI- C S51I-1A 1 SI-1B | SI-1C
§Alarm Limits 42 i +0. i 420 mR 420 mR < 0%]| <6000%} <

lLog Limits <1. si <0, i <10 mR <10 mR <1 <1l <1500

at to do ifyx e J J

10ut of Limits I 1 J

|Init.| Date/Time

       
 

 

 

Setpoint-is adjustsble and will normally be set lower than 6000 cpm.
See Section E. . o |

TX-4413
cation

   

ceription
Element
adout
arm Limits -1.
Limits= -1.
at to do if,
of Limits
t.|Date/Time

 

See Section E.

TX-4k13

In. H,O

13

Form D-1
DAILY LOG — PHASE III

Stack Panel {Stack Panel VH
Vecuum |  Flow

No, Cyl.
FE-S1 PE-Cyl.

A
P1 A - FI-81 PI-Cyl.
TH

0 No Alarm s
in. H=20}>0.4 in. J| >200 psi
K . K Replace
- o Readi
- In. H50 psig

VH

PE-Hdr
PI-Hdr

- —

Adjust

psig

N, Header

i

Monitron

RE-T012
RI-T7012
25 mR/hr
<25 mR/hr

L
 

 

1k

Form D-2

MONTHLY LOG

(To be taken during the last week of each month)

NOTE: NOTIFY WASTE MONITORING GROUP BEFORE STARTING

 

What

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

to do : o -
if out |[Jan Feb | Mar |April| May June
Item of or or or or or or
Limits { Limits |July | Aug | Sept Oct Nov | Dec
ate Log was Taken- - -
Initiai - —_
eview Dailly Logs —— -
[Review Console Log - -
Record TR-SD-1 Temps — - - -] =- - mm |
1l - TE-FD1-19A <200°F A
2 - TE-FD1-5 " A
3 - TE-FD1-15 " A
i - TE-FD2-19A " B
5 = TE-FD2-5 " B
6 - TE-FD2-15 " B -
7 - TE-FFT-4 " C .
8 - TE-FFT-11 " C
9 - TE-FFT-T " C
10 - TE-DTC-6 <150°F .D
11 - TE-RC-1 " E

 

 

 

 

 

 

 

 

 

 

 

 

 

 

TX-hL12

 
»

-\

- 15

Form'D—Q
MONTHLY LOG

What
to do
: if out | Jan
Item : of or
' Limits)| Limits |J

te Log was Taken
tial

eck that HCV-565 is
n -

ord Levels

t N, Supply at
20 i

Level

C S Level

-A1 Sump Level

Level

C-A S Level

A Sump Level

A Level

—A‘ Level
 off N linder

le Data _

view Stack Release
_Reports

té 6-month : rt
Annual Tests

Tx-L10

Feb | Mar

or
A

or
Sept

Apri
or
Oct

May | June

or
Nov

or
Dec

 

 
 

16

Form D-2
- MONTHLY LOG

Tour the building. Inspect each of the following areas for hézards
or malfunctioning items or abnormal radiation.
which are needed. Take cutie pie or chirper on tour.¥

Punch-list any repairs

*

 

Location

Jan
or

July.

Feb
or
Aug

Mar
or
Sept

April]
or
Oct

May |
or
Nov

June’
or
-Dec

 

Control Room

 

7503 Offices

 

7509 Offices

 

Tnstrument Shop

 

Change Room

 

High Bay

 

High Bay North

 

N.E. of 7503 (underground water leaks)

 

Steam Supply Line

 

Air Intake Filters and Heaters

 

Shop

 

Diesel House

 

Switch House

 

Remote Maintenance Control Room

 

Water Roonm

 

Blower House

 

CDT Cell

 

Special Equipment Room

 

{Cooling Tower

 

|South Electric Service Area

 

Vent House -

 

{Stack Area

 

High Bay South

 

Sump Room

 

840 Level

 

Transmitter Room

 

North Electric Service Area

 

Service Tuhnel

 

 

 

 

 

 

 

 

*
Notify key holders of sabnormel radiation or

(See Section J.)
TX-L412

contamination areas.-

 
w“

17

E. ABNORMAL CONDITIONS

Whenever the log 1imits are exceeded or an annunciation occurs,
corrective action is necessary. To plan in advance fér all possible
trouble,is-ifipractiéal.-hAn éttéfipt fias been made to anticipate some of
the more probable difficulties‘and suggest remedial actions. "What to do _
if ofit_of limits" columns have been inclfided in the logs (Forms D-1 and
D-2) and in the list of ahnunciatbrs (T&ble'E-l). Letters in these columns
refer to the suggested actibn given'in Table E-2. Power outages are cov-

‘ered in Section F.

 

€
 

 

18

Table E-1

ANNUNCIATION

 

 

Annunciator  Switch | , " What to Do
No. No. Cause of Annunciation If Out of Limits

XA-SD-1 PS-572 High FD-2 Pressure G

- XA-SD-2 PS-589 High FP Pressure H
XA-SD-3 PS-927 Low Ventilation Suction K

XA-SD-4 PS-RC-1 High RC Pressure F
XA-SD-5 RS-S1-A  Hi Stack Activity (B-y) J
‘ RS-S1-B Hi Stack Activity (a) J
RS-S1-C  Hi Stack Activity (Iodine) J
XA-SD-6 RS-565B  Hi RC Air Activity I
RS-565C Hi RC Air Activity I

XA-SD-T RS-T7001  Hi Air Activity L
RS-T012 Hi Radistion L
XA-SD-8 LS-FRS Hi Pump Room Sump Level R

 

NOTE:

*
See Table E-2.

Loss of electrical power will also annunciate at the ORNL

Central Waste Monitoring Facility (Building 3105).
19

Table E-2

ABNORMAL CONDITIONS

 

- Code

Variable
Out of Limits

Corrective Action

 

A

/ FD-1 Temp

FD-2 Temp

FFT Temp

- DTC Temp

heaters are off,

If TE-FD1-19A (TR-SD-1-1) indicates greater

than 200°F, other FD-1 temperatures should
be checked (TR-SD-1-2 & 3). If these are
less than 200°F, notify the MSRE Supervisor
on the next regular work day. If all three
temperatures are greater than 200°F, notify
him as soon as possible and check that all:
If TR-SD-1 fails, read the.
temperstures with a portable instrument and
have TR-SD-1 repaired on the next regular
work day.

If TE—FD2-19A (TR-SD-1-4) indicates greater

than 200°F, other FD-2 temperatures

‘should be checked (TR-SD-1-5 & 6). If these
are less than 200°F, notify the MSRE Super-
- visor on the next regular work day. If all

three temperatures are greater than 200°F,
notify him as soon as possible and check that
all heaters are off. If TR-SD-1 fails, read

-the temperatures with a portable instrument

and have TR-SD-1 repaired on the next regular
work day.

If TE-FFT-L4 (TR-SD-1-7) indicates greater than
~ 200°F, other flush tank temperatures should
be checked (TR-SD-1-8 & 9).

- If these are

less than 200°F, notify the MSRE Supervisor
on the next regular work day. If all three
temperatures are greater than 200°F, notify

~him as soon as possible and check that all

hesters are off. If TR-SD-1 fails, read the

temperatures with a portsble instrument and

" have TR-SD-1 repalred on the next regular

work dey.

If TE—DTC— . (TR-SD-l-lo), 1ndlcates greater

than 150°F, other drain tank cell temperatures

"['should be checked (Patch panel 208 to 212).
If these are less than 150°F, notify the

MSRE Supervisor on the next regular work
day. If they are greater than 150°F, notify
 

 

 

20

Table E-2

ABNORMAL CONDITIONS
(continued)

 

Variable | |
Code Out of Limits Corrective Action -

 

D (con't) S ~ - him as soon as possible and check. that all
in-cell heaters are turned off. If TR-SD-1
fails, read the temperatures with a portable
instrument and have TR-SD-1 repaired on the
next regular work day. :

E RC Temp . If TE-RC-1 (TR-SD-1-11) indicates gresater
' then 150°F, other reactor cell temperatures

.should be checked. (Patch panel 82 to 90.)
If these are less than 150°F, notify the
MSRE supervisor on the next regular work
day. If they are greater than 150°F, notify
'him as soon as possible and check that all
in-cell heaters are turned off. If TR-5D-1
fails, read the temperatures with a portable
instrument and have TR-SD-1 repaired on the
next regular work day.

F RC Press. - If PI-RC-A indicates greater than 0.5 psig or
less than -2 psig or if XA-SD-4 annunciates,
check in the vent house that HCV-565 and
V-565A, C, and D are open. If not, push reset
buttons on RE-565 B & C in the control room
and open the hand valves. If the pressure is

- 8till out of limits and cell air activity is
normal, vent the cell by opening V-955 A and B
in the service tunnel. After sbout 30 minutes,
close V-955 A and B. Notify the MSRE Super-
visor on the next regular work day. If PI-RC-A
or XA-SD-h fails, have it repaired on the next
regular work day. If both fail, notify the
MSRE Supervisor as soon as possible.

G : FD-2 Press.. If PI-5T2B reaches 2 psig or XA-SD-1 annunciates, .
vent the drain tanks to the stack by opening
V-561 and V-562A in the vent house. When the
pressure is 0 to 1 psig, close V-561 and V-562A.
Notify the MSRE Supervisor on the next regular
work dey. If the pressure reaches 5 psig,
notify the MSRE Supervisor as soon as possible.
If PI-5T2B or XA-SD-1 fails, have it repaired
on the next regular work day. If both fail,
notify the MSRE Supervisor as soon as possible.
21

Table E=2

ABNORMAT, CONDITIONS

(continued)

 

Code

Out of Limits

Corrective Action

 

.

"

FP Press.

RC Activity

Stack Activity

| Ventilation

- If PI-589A reaches 0.5 psig or if XA-SD-2

annunciates, vent the fuel system to the
stack by opening V-522A, V-561, and V-5624

'in the vent house. When the pressure is O
to 0.1 psig, close V-522A, V=561, and V-562A.

Notify the MSRE Supervisor on the next
regular work day. If the pressure reaches

5 psig, notify the MSRE Supervisor as soon

as possible,
If PI-589A or XA-SD-2 fail, have them repaired
on the next regular work day.

If RI-565B or C reach 20 mR/hr or if XA-SD-5

annunciates, (or if the instruments fail)
close V=565C in the vent house and notify

- the MSRE Supervisor on the next regular
work day.

If RI-S1-A, B, or C in the auxiliary control

~ ‘room indicate asbnormal stack activity, i.e.
- >1500 ¢/m, notify the MSRE Supervisor on the
" next regular work day. If any exceed 6000
‘e/m, notify him as soon as possible. If any

instrument should' fail, repairs should be

"'madé as soon as possible.

If FI-S1 is less than 0.4 in. Hy0 (~ 15,000 cfm)
or if PI-92TA is less than 1.0 in. H0 vacuum,
~or if PI-92TA annunciates on XA~-SD-3, check

that one stack fan is operating properly and

" there is a good flow of air into duct 935 in
‘the southeast corner of the high bay. If

ventilation is adequate, notify the MSRE
Supervisor. on the next regular work day.
If neither stack fan is in operation, or if

- ventilation flow is low, start the alternate
_stack fan as follows: Stop both stack fans
from the control room. Open the discharge

damper on the stack fan to be operated
(Damper 925. for SF #1 - west and damper 926 for
SF #2 - east). Close the discharge damper
 

 

 

22

Table E-2

ABNORMAL CONDITIONS
(continued)

 

Variable :
Code Out of Limits Corrective Action

 

K (continued) (926 or 925) on the other stack fan. Start
the desired stack fan. (It may be necessary
to energize the proper breaker in the switch
house. This is G3-2L4 for SF #1 and Gh-3k
for SF #2. Notify the MSRE Supervisor on
the next regular work day. If the above does
not correct the difficulty, notify the MSRE
Supervisor as soon as possible. If any of the
instruments fail to function, have them re-
paired on the next regular work day.

L Personnel
Monitors If RI-T001 indicates high air activity (>4000

cpn) or if RI-T012 indicates high radiation
(>25 mR/hr.), have Health Physics survey
the area. If abnormal conditions are found,
notify the MSRE Supervisor as soon as
possible. If instrument failure occurs, re-

~ pairs should be made as soon as possible.
Notify the MSRE Supervisor on the next regu-
lar work day. .

M WT Level If WT level is greater than 100 inches, trans-
fer the contents to the Melton Valley Waste
Station as follows: Call ORNL Waste Station
(Telephone 3-6234) and report volume to be
pumped. When permission to transfer is ob-
tained, remove blocks and set valves as
follows in the Remote Maintenance Practice
Cell: Open V~300. Close V=301, V-302,
V-303B, V-305A, V-305B, and V-307. ©Start
the waste pumps. (It may be necessary to
energize bresker GlU-4 in the switch house.)
Throttle V-305A to give flow acceptable at
Melton Valley Waste Station. PI-305 should
not exceed 35 psig. When desired amount
has been transferred, stop pump. Close
V-300 and 305A and replace blocks on remote
maintenance practice cell. Record waste
tank levels in the console log (before and
after transfer).
o

23

Table E-2

ABNORMAIL CONDITIONS
(continued)

 

Variasble
Code Out of Limits = Corrective Action

 

"

N RC Sump | If LI-RC-C indicates a level greater than
- 15 inches in the reactor cell sump, Jjet the
. water to the waste tank as follows:
. Record LI-RC-C and waste tank level in
the console log. Connect steam to line 332
~on the west side of the building. Connect
instrument air or nitrogen to the wvalve
operators of FCV-333A1 and A2 and open
them. Open the steam supply to line 332
~and Jet the sump. When complete, remove
steam supply and cap line 332. Remove air
or N, supply to FCV-333A1 and A2. Record
LI-RC-C and waste tank level in the console
log.

0 DTC Sump - .If LI-DTC-Al indicates a level greater than
: - 15 in. in the drain tank cell sump, Jet the
water to the waste tank as follows: Record
LI-DTC~-Al and waste tank level in the console
‘log. Connect steam to line 342 on the west
side of the building. Connect instrument air
or nitrogen to the valve operator of FCV-343A1
and A2 and open them. Open the steam supply
to line 342 and jet the sump. When complete,
remove steam supply and cap line 342. Remove
air or N, supply to FCV-3L43A1 and A2. Record
, LI-DTC—Al and waste tank level 1n the console
_ ;log

P DC Sump If the level in the decontamination cell ex-
' ' : - . ceeds 15 in., pump it to the waste tank as
. follows: Record the sump level and the
~ waste tank level in the console log. Remove
"~ the blocks from the remote maintenance
~  practice cell. Close V-300, V-302, V-30T,
.. and 303A. Open V-303B and V-301. GStart
- waste pump from RMPC and pump DC to WT.
'V,Stop pump and close V-303B and V-301.
Record DC sump level, LI-DC and waste tank
- level in the console log.
 

24

 

 

 

 

 

Table E-2
ABNORMAY, CONDITIONS
(continued)
7 Variable |
Code Out of Limits Corrective Action
Q Aux. Sumps  If the level in any of the auxiliary cell
' sumps exceeds 15 in., jet the water to the
waste tank as follows: Record the sump
~level and the waste tank level (LI-WT) in
the console log. Open proper jet supply
valves {these are located in the NE corner
of the transmitter room).
Cell Level Element Jet Supply Valves
Fuel Storage ~ LE-FSC V-321, V-311B
Equipment Storage LE-SC V-317, V-311B
Waste Tank | LE-WTC ~ V-315A, V-315B
Spare LE-TC V-319, V-311B
Remote Maintenance -
Practice None V-315A, V-323
When jetting is complete, close the valves
and record the sump level and the waste tank
level in the console log. '
R PRS Level If the pump'room sump level annunciates, check

the pump room to see if it is flooded. (Entrance
is in the SE corner of the high bay.) Do not

" enter without the exhaust fan in operation and
another person on hand for emergency. If
possible, check the float switches of both
sump pumps. If the sump cannot be emptied with
the pumps, try jetting the coolant drain cell
sump (which connects with the pump room) using
steam through lines 309 and 310.
"

»

25 -

F. POWER OUTAGES

A power outage at the MSRE should not cause much difficulty and
should not be hazardous. - An\alarm'will occur at the ORNL Control Waste
Monitoring Facility unless. they also lose powerj in that case no alarm
will océur'until their power trouble is corrected. .

When power is available, a stack fan should be started. HCV-565
should be opened by pushing the reset buttons on RE-565 B and C, and the
high-bey CAM and monitron should be checked. A log should be taken to
assure that everything is within limits and that nothing appears abnormal
in the area. Check that there is no water in the pump room (cbserve
from 852 level). Freeze protection should be considered in the winter,

The MSRE supervisor should be notified on the next regular work day.
 

 

26

G. ANNUAL TASKS

The fuel and flush salt in the drain tanks will be heated once a year

" t0 recombine fluorine.

An annusl check will be made to determine that all

valving and electrical switches are in the proper position, that standby

equipment will operate if needed and that the annunciator and control

switches have the proper setpoints. The following check lists are used

to accomplish this.

1. Recombine Fluorine by Heating the Drain Tank

l.l

1.2

1.3

1.h

1.5

1.6

1.7

Close switchés 1 - T in Panel FD-1-1,
switches 1 - 6 and 11 in Psnel FD-2-1, and
switches 1 - 6 and 11 in Panel FFT-1 (North

~ end of 849 level) and energize Breaker G5-BB.

Push FD-1-1, FD-2-1, and FFT-1 "ON" buttons and
raise or lower settings to get approximately
9 amps on the heaters (HCP-8).

Open and leave V-561 and 562A open to vent the
drain tanks.

Record temperatures daily in Table G-1 until
the salt has been above 300°F for at least one
week (do not exceed 500°F).

Turn heaters off and open switches 1 - T in
Panel FD-1-1, switches 1 - 6 and 11 in Panel

FD-2-1, and switches 1 - 6 and 11 in Panel FFT-1

and rack out Breaker G-5-BB.
Close V-561 and V-562A.

Record temperatures daily in Table G-1 until
temperatures are less than 250°F.

NOTE: Add helium as necessary through V-518A to keep
FD-1 pressure between O and 2 psig. (See G-3 for
valving.)

‘Init. Date/Time

 

 

 

 

 

 

 
v

-SD-1 Pt. No.

te/Time

[})

1 2

27

Table G-1

Temperature Readings

3 | v | s 6 | 71

— apn — — — — — — e a— — — w— — — — S e — —— —

1-15 2-19A |FD-2-5| FD-2-15 |FFT-4

FD=-1-19A {FD-1-5

 
 

 

28

Init.

Pressure Test of the Reactor and Drain Tank Cells

2.1 Connect the reference side of the hook gage in
' the transmitter room to the in-cell reference
volume. (Penetration A-27 in the NESA.) Open
the hook gage equalizer valve.

Date/Time

 

2.2 Connect the other side of the hook gage to the
drain tank cell (Penetration A-5 in the NESA)

 

2.3 Close HCV-565 using handswitch in the control
room.

 

2.4  Connect a portable diesel air compressor to
line 342 at the west side of the bu1ld1ng
(8L0 level).

 

2.5 Pressurlze the cell through 11ne 342 to
approximately 6 psig® per PI-RC-A in the control
room. As the cell is pressurized, note the pressure
at which PS-RC-1 annunciates on XA-SD-k.

psig. If the alarm does not occur be-
tween 0.5 and 1.5, the switch should be reset.
Record final setting psig.

 

2.6 Disconnect the compressor from line 3h2 cap
the line and soap check.

 

2.T Close the hook gage equalizer valve. Record and
plot the hook gage reading and PI-RC-A once per
shift until the leak rate is established (minimum -
of 48 hrs). Acceptsble leak rate is LOO sefd at
5 psig. Use the following formula for calcu-
lating the leak rate.

AP
L = 1000 T

where L = lesgk rate in standard cu ft
per day

AP = change in pressure during test in
inches of water (from the hook gage)
t = duration of the test in hours.

 

2.8 When the test is complete, open the hook gage

 

equallzer valve.

 

¥
Do not exceed 10 psig.
®

2.9

2.10

29

Init. Date/Time

Open HCV-565 and vent the cells to atmospheric
pressure.

 

Disconnect the hook gage'andflcap the lines at

 

penetrations A-5 and A-27 in the NESA.

¥FD-2 and FP Pressure

(To be done after drain tank temperaturés have cooled

below 250°F following the fluorine recombination.)

3.1

3-2,

3.4

3.5

3.T

3.8

. whlch stack fan is 1n serV1ce .

Connect a nitrogen cylinder with regulator to
V-518G in the vent house and check that fitting
does not leeak.

 

Check that the auxiliary charcoal bed inlet

 

valve 561 is closed and V-522B is closed.

Open V-522A, and V-5184, Bl, Cl, F, and G and
pressurize systems until PS-5890 annunciates on
XA-SD-2 psig. (Do noit exceed ~ 0.6 psig on
PI-592B.) Ad ust setpoint if necessary to 0.k

 

to 0.6 psig. Record final settlng psig.

Close V-522A and pressurize drain tanks until
PS-5T72 annunciates on XA-SD~1 psig. (Do not
exceed 2.5 psig on PI~572B.) Reset PS-572 to 1.5
to 2.5 psig if necessary. Record final setting

psig.

 

Close V-5184, Bl, Cl, F, and G and remove

nitrogen cylinder and cap'line at 518G.

 

Open V=561 and V-562A and vent DI's to atmos~
pheric pressure..:'

 

Then open V;522A and vent FP to atmospherlc
pressure.

 

Close V-5224, V=561, and'V-562A;

 

: Ventllatlon System

'h_-:L

_Record FI-SI ~in. H,0 (should'be greater
than .5 in. H205 PI-92TA ___in. Hy0 (suction

should be more than 1.5 in. of'water) Record

 
 

 

NOTE:

30
'Init.

4,2 Stop both stack fans and note pressure at which
- PS-92TA annunciates on XA-SD-3 in. H0. If
necessary, reset PS-92TA to -0.9 to =1.1 in. of
water as indicated on PI-927TA. Record final
setting in. Hy0.

Date/Time

 

4.3 Manually switch dempers to operate alternate stack |
fan. Damper 925 should be open to operate SF-1
West. Damper 926 should be open to operate SF-2
East.

 

4.4 Start other stack fan and record FI-Sl in. Hy0
(should be greater than .5 in. Hy0) and PI-92T7A
in. Hy0 (suction should be greater than -1.5 in.
water). Record which stack fan is in service .
It may be necessary to energize the proper breaker
in the switch house. This is G3-24 for SF #1 and
G4-34 for SF #2. | 1

 

 

4.5 Set up for and put SF-1 in service. Open

 

breaker Gh-3k.
RC Air Activity
5.1 Check that alarm settings on RS-565B and C are

20 mR/hr by pressing the alarm buttons. Adjust
if necessary. Adjust calibrate to 0.3 mR/hr.

 

5.2 Have a Health Physicist insert a source in lead shield-
ing around RE-565B in the vent house and note that
XA-SD-5 ennuncistes and that HCV-565 closes.
(Observe valve located below the grating in the -
north side of the vent house.)

 

5.3 Remove source, reset RS-565B in ACR and note that
' HCV-565 opens and XA-SD-5 clears.

 

5.4 Have a Health Physicist insert a source near RE-565C
and note that XA-SD-5 annunciates and that
HCV-565 closes.

 

5.5 Remove source, reset RM-565C in ACR and note that

 

HCV-565 opens and XA-SD-5 clears.

Sump Pumps

Two people are reQuired for the following. Be

_sure to turn on the blower and-allow: to run:ifor sbout .-

5 minutes before entering the pump room.
Y

C

31

6.1 Add water to the pump room sump. When sump
pump "A" starts, physically hold the float
switch on sump pump "A" down.

6.2 Note that sump pump "B" starts and LS-PRS
annunciates on XA-SD-8 (before the floor is
flooded), stop adding water.

6.3 Release both pump float switches and note that
annunciation clears and both pumps stop when sump
level is normal.

Miécellaneous

The following miscellaneous checks should be com-
pleted annually.

T.1 Check that equipment valves, switches, etc., are
as indicated in Table G-2.

T.2 Check results of annual DOP test of stack filters.
T.3 'Review results of monthly stack monitor checks.

7.4 Review results of monthly personnel radiation
monitor checks.

T.5 Review list of programmed maintenance being done
~ and results of previous year's maintenance work.

 

Date/Time

 

 

 

 

 

 

 

 
 

32

Table G-2

Miscellaneous Equipment Check

 

 

 

 

Check

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

: ’ when
Location What to Check Required Condition Complete
SE V-542 Tagged Closed
HB 035 filter Clean
| sT HCY-930A Closed
ST HCV-930B Locked Closed
ST V-930C Closed
ST V-955A Closed
| ST V-955B " Locked Closed
ST V-955C Closed
TR V-514C Tagged Closed
TR All LKD Valves Closed
Near TR Dist. Panel 1A-5 Tagged closed
SH G3-3 Tagged Closed
SH G3-24 Tagged Closed
SH GL-34 Tagged Open

 

 

 

 

 

 
"y

%)

Table G-2

Misceilaneous Equipment Check
(continued)

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

SF-2 (East)

 

 

| Check
. _ o ' when

Location. What to Check Required Condition . . Complete
CDT_Cell V-511B __Tagged Closed
{VH | V;518 A, E,\&.G ___Tagged Closed

VH v-5186 | capped

VE V522 A& B Tagged Closed

VH V=531 Tagged Closed

VH V-538 A & B Tagged Closed

VH V-571B Tagged Closed

VH HCV-565 . Open

VH V-565 A, B, & C Tagged Open

VH V-557B Closed

VH- . y-5624 Closed

VH V-5620 Open

VH V-561 Tageed Closed

Stack .Damber 925 \Qpen |

Stack Damper:926 S Closed

Stack SF-1 (West) Running

Stack " ‘Not Running

 

 
34

H. MAINTENANCE AND REPAIRS

Operating equipment which fails should be repaired as soon as pos-
sible. The urgency depends upon the consequences. Table E-2 lists most
of the possible process repairs and delineates the importance of each.

Repairs will be done only with the approval of the ORNL Central Waste
Monitoring Group, the MSRE Maintenance Supervisor, or the MSRE Supervisor
(or his representative). The person initiating the request for repairs
will be responsible for the safety of personnel ahd the facility.

During regular working hours a Punch List form (FORM H-1) will be

filled out and given to the Maintenance Supervisor (Fig. K-1) who will

expedite the repairs. Any deviation from the punch list should be approved

by the requestor. When the work is complete, the punch list will be re-
turned to the Maintenance Supervisor who will be respoheible for entering
all details in the console log and filing the completed punch list in '
Room 1T, Building 7509. | | o |

On other shifts, the ORNL shift supervisor shall arrange to have the
repairs made and shall be responsible for getting the details recorded in
the console log. |

Most of the programmed maintenance will be done during the last week
of each month when the mpnthly leg is being teken. Permission must be |
obtained from the Maintenance Supervisor, the MSRE Supervisor, or his
representative before doing these.

No modification will be made to the facility without the approval of

the MSRE Supervisor or his supervisors.
I. REMOVAL OF EQUIPMENT OR INSTRUMENTATION

Equipment and instrumentation needed for the interim storage of the |

fuel or for the future transfer or processing of the fuel will be'retained

intact. Other‘things may be removed if needed after obtaining the approval -

of the MSRE Surplus Property Custodian, the MSRE Supervisor, or Assistant
MSRE Supervisor. All ORNL procedures will be strictly adhered to (see
ORNI~-SPP-37). In addition an MSRE Property Transfer Form I-1, and Punch
*r

ay

¢

“Approval to proceed:

35

Form H-1. MSRE PUNCH LIST

 

 

To . ' Priority Date
Location ‘ o _ - Requested by:

 

Equipment, Line No., etc.

 

 

Description of Work to be Done:

 

 

 

 

Precautions:

 

 

Estimated Cost:

 

 

Describe work done 1if different from above:

 

 

 

 

 

Job Completed and Accepted by: = o Date:

 

 

TX-4410

 
- Item:

36

MSRE SURPLUS EQUIPMENT TRANSFER

Tag No.

 

Quaentity eand Units:

 

 

Brief Description:

 

 

Location at MSRE:

 

 

Property No.: X-

Requested by:

Date:

 

For use in: DMSRP; [C] other ,(specify).

Cherge removal costs to:

When needed:

 

 

 

- Transfer epproved by:

Date:

 

 

Item received by:

Date:

 

 

TX-4L11

1¥2
-

g}

37

List, Form H-1, will be filled out for each item or group of items re-
moved. A file of these will be maintained in Room 17, Building 7509.

If special precautions are necessary, these shofild'be described fully

on'the Punch‘List. |

J. ACCESS CONTROL
" As indieated in Fig. B-2 , an B-foot lighted security fence completely

encloses & compact erea immedlately surroundlng the MSRE buildings. Two

gates 1n the fence (North and West Gates) open onto Melton Valley Drive

(a road posted as "Official Use Only") The other two gates and the office

bulldlng door are inside the controlled—access HFIR~TRU-TURF area. All
four gates and the office door will normally be kept locked. On the office
door and on each of the four gates is a sign of the formelndlcated below,
where the blanks contein the names and phone numbers of (l) the MSRE Super-
visor, (2) the Assistant MSRE Supervisor, (3) the MSRP Aesociate Director,
end (4) the MSRP Director. | |

IS

CONTROLLED ACCESS AREA
DO NOT ENTER WITHOUT PERMISSION

' Persons Authorized to Give Permission:

 

 

 

 

 

 

 

 

 

 

 

Normal entrance to the MSRE.. Area w1ll be~through the guard gate

- on the HFIR Access Road, then through either the office door, the East

Gate or the South Gate. Keys to the door and these two gates will be is-
sued to a limited number of people, 1nclud1ng the MSRP Associate Director,

‘the MSRE Superv1sor, the MSRE Surplus Property Custodlan, the Assistant

MSRE Supervisor, the MSRE Meintenance Superv1sor, the ORNL Waste Monitoring
Group, and the ORNL Shift Supervisors. |

 
 

 

38

The North and West gates will have security<type locks which are
controlled by the ORNL Guard Department. Only a limited number of people
will be authorized to have the Guard Department open these. These wili
include the‘MSRP Assoc1ate Dlrector, the MSRE Supervisor, the MSRE Asst,
Supervisor, and the ORNL Shift Superv1sors. These gates will not be left
open without a guard in attendance. | '

There will be radiation.and contamination outside of the containment
cells. Where required, Radiation and Contaminétioh Zénes will be identi-
fied and protection provided as presecribed by ORNL procedures. Monthly
radiation and safety surveys will be fiade td assure that no'inadequately
guarded hazards exist. Those persons hav1ng keys will be adv1sed of any
llmltatlons on use of the area, and 1t will be thelr responsiblllty to

so advise anyone that they admit to the area.

K. ~ ORGANIZATION AND CHANGES

The organization chart for the MSRE during Phase III is shown in |
Fig. K-1. The MSRE supervisor has the prime responsibility for the area.
He must approve of any changes in the procedures or modlflcatlon of the

fac111ty. A master up-to-date copy of the procedures w1ll be kept in

i Room 17, Building 7509. All changes will be initialed and dated. If sig-

nificant modifications are needed, others in the MSRP project will be

consulted.
8

¥

39

 

MSRP Director

M. W. Rosenthal

 

|

 

Associate MSRP Director

 

P, N. Hafibenreich

 

 

MSRE Supervisor

R. H. Guymon

 

 

~ Assistant MSRE Supervisor

A. T. Kf'a_koviak

 

 

 

 

 

' MSRE SurplusrProperty‘Custodian

’ L. Ps Pugh.

 

 

 

Surveillance

L. C. Lasher

W. T. Newton |
Shift Operators

 

 

 

 

Maintenance

*
H. G. Kern

 

" H. E. Felts
C. T. Carney

 

 

*
MSRE Maintenance Supervisor

 

 

 

Advisors
(former MSRE staff)

General
J. L. Crowley
R. H. Guymon
- P. H. Harley-
A. I. Krakoviak
Electrical

T. L. Hudson
Mechanical

M. Richardson
R. S. Jackson

'Instrfiments

J. L. Redford
R. W. Tucker

Parts and Supplies
L. P. Pugh
Remote Maintenance

J. R. Shugart

 

Fig. K~1. MSRE Organization Chart (January, 1971)

 
 

 

Lo

REFERENCES

| 1. R. C. Robertson, MSRE Design and Operations Report, Part I,
Description of Reactor Design, ORNL-TM-728 (Jan. 1965).

- 2. J. R. Tallackson, MSRE Design and Operations Report, Part II,
- Nuclear and Process Instrumentation, ORNL-TM-T29 (Feb. 1968).

3. J. R. Engel, B. E. Prince, and H. C. Claiborne, MSRE Design and
‘Operations Report, Part III, Nuclear Analysis, ORNL-TM-730 (Feb. 196k).

L. S. E. Beall, P. N. Haubenreich, R. B. Lindauer, and J. .R.
Tallackson, MSRE Design and Operations Report, Part V, Reactor Safety
Analysis Report, ORNL-TM-T32 (Aug. 1964).

5. P. N. Haubenreich, J. R. Engel, C. H. Gabbard, R. H. Guymon,
and B. E. Prince, MSRE De51§n and Operations Report, Part V-A, Safety
 Analysis of Operation with U 'ORNL-TM-2111 (Feb 1968).

6. R. B, Lindauér, MSRE Design and Operations Report, Part VII,
Fuel Hendling and Processing Plant, ORNI-TM-907 (May 1965).

T. R. H. Guymon, MSRE Design and Operations Report, Part VIII,
Operating Procedures, ORNL-TM-908 (Jan. 1966).

8. A. N. Smith, MSRE Design end Operations Report, Part IX, Safety
Procedures and Emergency Plans, ORNL-TM-909 (June 1965).

9. E. C. Hise and R. Blumberg, MSRE Design and Operations Report,
Part X, Maintenance Equipment and Procedures, ORNL-TM-910 (June 1968).
99. .

L1

Internal Distribution

 

49.
50,
51.
52,
53.
54-55.
56.
5T
58.
59.
60.
61.
62.

8.
85.
86.
87.

M
dJd
M
W
I
D
. R
D
R
B
G
J
M

E?fl???fibflbbhfl?flbiflwm

*

»

.

E**Ugt*t*mcqtdfiflflt’-:ltljfi

ORNL-TM-3253

MacPherson
MacPherson
McCoy
Magnuson

. McCurdy
MeIntosh, AEC-Washington

McNeese
Miller
Meyer
Moore
Nicholson

. Perry
. Pugh

Redford

'Rlchardson

M W. Rosenthal

H. M. Roth, AEC-ORO
A. W. Savolainen

R. W. Schaich
Dunlap Scott

J
G.
G

External Dlstrlbutlon

*
»
-
-
®
-
-
-

 

1. R. G. Affel
s 2. J. L. Anderson
3. T. A. Arehart
L. C. F. Baes
5. S. E. Beall
6. E. S. Bettis
T. E. G. Bohlmann
8. G. E. Boyd
9. R. B. Briggs
10. W. B. Cottrell
11. J. L. Crowley
12. J. R. Distefano
13. S. J. Ditto
14. W. P. Eatherly
15. J. R. Engel
16. D. E. Ferguson
17. L. M. Ferris
18. A. P. Fraas
19. W. R. Grimes
20. A. G. Grindell
21-30. R. H. Guymon
- 31. P. H. Harley
32. P. N. Haubenreich
33. P. W. Hembree, Jr.
3 34, H. W. Hoffmen
35. T. L. Hudson
36. R. S. Jackson
37. J. E. Kahn
38. S. I. Kaplan
39. P. R. Kasten
4bo. J. J. Keyes.
4bi. A. I. Krekoviak
42. Kermit Leughon, AEC-OSR
43-45. L. C. Lasher ' '
46. B. Lieberman
k7. M. I. Lundin
4L8. R. N. Lyon
88-89.
90.
91-93.
9L,
fifiij '95r96:
97.
98,

Central Research Library

Y-12 Document Reference Section
Laboratory Records Department
Laboratory Records Department (RC)

c:c:miwggra:s!w:y:b

. Shaw, AEC-Washington
. R. '
. d.
. L.
. Spiewak

. Sundberg

Shugart
Skinner ,
Smalley, AEC-ORO

Thoma

. Trauger

Tucker

. Walters

Watson
Weir
Whatley

. White

Whitmmn

ale Young

Division ofrTechnical Information Extension (DTIE)
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