ML20085B066

Rev 1 to Emergency Operating Spec 69-1001168, Loss of Reactor Coolant/Rcs Pressure

ML20085B066
Person / Time
Site:	Three Mile Island
Issue date:	02/24/1978
From:	BABCOCK & WILCOX CO.
To:
Shared Package
ML20085B059	List: ML20085B057 ML20085B066
References
TASK-*, TASK-02, TASK-2, TASK-GB 69-1001168, BWNP-20004-(6-7, EOS-0162, EOS-162, GPU-0552, GPU-552, NUDOCS 8307070486
Download: ML20085B066 (8)

Text

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3WNP-20004 (6-76)

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ENERGENCY OPERATING SPECIFICATION et 1001168 69 DDC. ID-SERIAL N0.-REYlSI'0'N NO.

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BWP-20005 (6-76) 4 A 8 COCK & WILCOK MUCitAt POWtt C E M e t A llCM Devl38C M Muan e t s RECORD OF REYlSION 69-100116s-00 REY. No.

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TABl.E OF CONTENTS /EFFECTlYE PAGE LIST 69-1001163-ec.

SECTION TITLE PAGE 00C. NO.

1.0 PURPOSE 4

69,100116S-0F 2.0 SYMPTOMS 4

69-1001168-00"'

5 69-100116E-00' 3.0

- Aur0MATIC ACTION 5

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4.0 IEEDIATE OPERATOR ACTION 5_, p 69-1001168-06 I

4 69-1001168-Off 5.0 SUBSEQUENT OPERATOR ACTION 6

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6.0 REFERENCES

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B' K?-20007 i SASCCCK & witcC3 MucttAt Powga otMaaAncM EsvlilSM M' lane e t TECHNICAL DOCUMENT 69-1@ 1168 M

' F 1.0 PURPOSE This specification describes the recommended actions in the event of an abnor=al decrease in Reactor Coolant System (RCS) pressure or pressurizer level.

The symptoms and actions are considered according to the severity of the accident.

1.1 Small leak - within the capability of one makeup pump to maintain RCS pressure.

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1.2 Intermediate leak - within the capability of the Righ Pressure Injection (HPI) System to maintain RCS pressure.

1.3 Large leak - exceeds the capability of the HPI system to maintain RCS pressure.

2.0 SYMPTOMS 2.1 Small Leak 2.1.1 Makeup tank inventory decreasing during steady state operation greater than the normal rate but less than the capacity of one makeup pump.

2.1.2 Makeup flow increasing with stable T,y,.,

2.1.3 Possible radiaticn alarm in reactor building (RB) or other location that could indicate a RCS leak.

2.1.4 Possible RB sump level increase.

2.1.5 Greater than normal leakage during the routine perfo:=ance of Reference 6.2.

y 2.2 Intermediate Leak 2.2.1 Pressuri:er level and ECS pressure decreasing with stable T"#* and makeup flow increasing to maximum.

2.2.2 Makeup tank inventory decreasink gret :er than capacity of one makeup pump but less than capacity of h7I system.

2.2.3

" nille radiation alarm in RB or other location that could indi-cate a RCS leak.

Increasing level in RB sump with possible high level ah.,,)

2.2.4 j

2.2.5 Possible increase in RB pressure and te=perature*

COMS E.' Oi 2.2.6 Possible =akeup fitw high alarm.

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DATE:

12-3-76 FAGE 4

3WP-20007 (6-7 B A; COCK & witCoK NUCitAt PQwit GtNit Af TON DevlSION NUm e t t 69-2001168-oce \\

TECHNICAL DOCUMENT 2.5 Large Leak 2.3.1 Rapid decrease in pressurizer level and RCS pressure.

2.3.2 Reactor and turbine trips accompanied by Engineered Safety Features Actuation System (ESFAS) actuation.

2.3.3 High ' radiation ala:n in RB or other location that could indicate a RCS leak.

2.3.4 High reactor building pressure and temperature.

2.3.5 High RS su=p level @ with a high level alar =.

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3.0 AUTOMATIC ACTION 3.1 Small Leak Flow increases through pressuri:e level centrol valve.

3.2 Intermediate Leak

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_ Flow increases through pressurizer level control valve.

. cec, 3.3 Large Leak 3.3.1 Reactor trip '(Low RCS pressure or low pressurizer level) 3.3.2 Turbine trip 3.3.3 ESFAS Actuation (Low RCS pressure) 4.0 IEEDIATE OPERATOR ACTION 4.1 Small Leak 4.1.1 Isolate letdown 4.1.2 Attempt to locate and isolate the leak 4.2 Inter =ediate Ler.k 4.2.1 Trip reactor and assure turbine trips u 0 \\".-~)

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4.2.2 Isolate letdown pgl l g

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4.2.3 Inittate HPI

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TECHNICAL D0011 MENT 69-loo 116s-nop i 1

l 4.3 Large Leak 4.3.1 Verify automatic action has taken place i4.3.2, Isolate letdown cLfJLa)::= c.R.

4.3.3 Trip ali RC pumps if adequate suction pressure cannot be maintained,

-thef :.insL4se-seab-flow.

i 5.0 SUBSEOUENT OPERATOR ACTION W'N r-K If a steam generator (SG) tube leak is suspected as the casual _ty (radiation in secondary steam system or other indication)fTsolate j the affected SG and use re=aining SG for cooldown as required.

Additional measures to reduce second.y system contamination and p v_';-

to reduce or prevent the release of adio etive e'lements to the

..<i atmosphere should be taken.

5.1 Small Leak

/gss IHM 5.j.1 If leakage cannot be reduced to usuhar the limits of Reference 6.1 follow the actions required by Reference 6.1~.

5.f.2 Maintain makeup tank level per Reference 6.3.

5.f.3 Terminate RB purge if in progress.

5.i Intermediate Leak

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. Operate third makeup pump to aid HPI as needed to maintun pressurizer level.

NOTE:

It will be necessary to take water frcm the makeup tank periodically to prevent overfilling due to the return flow from RC pump seals.

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.cI 5.'$. 2 Reduce number of operating RC pumps to one in each loep.

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5.13 Te=inate RS purge if in progress. '

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5.% 4 Cooldown the plant to cold shutdown.

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5.A 5 Attempt to find and isolate the leak.., /J C '~ a~0

-fi,c 5.% 6 Prior to running out of water for HPI, -fif pressure i e maximum allowed for the tepay Heat Removal System (DHRS), use HR pu=p to supply water from'R3 su=p to HPI per Reference 3b$. %, 3 p oG,7 CO UDT A_

COLNSI_ Oh _Yr2 m DATE: 12-3-76 l

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4ticitAs powna c:Mt At:2w civtS83H Mumus 69-100116S-d TECHNICAL. 00Ct! DENT 5.$ 7 EnenRCSpressureallows,useDHRsystekintheRS[eirculation

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5.p Large Rteture--- f jf/}fy

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5.l.1 Verify Proper operation of ESFAS, including initiation of Icw pressure injection when the setpoint is reache i: q s.

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532 Cooldown the plant in as near normal a manne possib.. %., e.. c..,. G L".

5.f.3 - While stil1 using water from the borated water, storage tank (BNST),

assure adequate fluid supply to the high or low pressure injection syste=s will be available from the RS sump pri.or to the SWST low level a

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5.'d. 4 Establi nor=al or RB su=p recirculation decay heat removal a p ',

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appropriate when the BWST low level alarm setpoint is reached. /' 'l S.k.S Sa=ple RB hydrogen and initiate hydrogen re= oval procedures 1.

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5I.6 Secure ESFAS components as necessar.

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5.f.7 Initiate long term cooling with.the decay heat removal syste=.

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6.0 REFERENCES

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6.1 Plant Technical Specifications.

6.2 RCS Leak Detection P " : OS 5021F

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6.3 Makeup and Purification System Operation OS 3521 /

6.4 ESFAS Operation OS 2621 6.5 Reactor trip EOS 0172 6.6 Plant Shutdown OS 0135 e g _ s yt:)::C '

6.7 Plant Limits and Precautions 05 1101

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