ML20085B041

Rev 0 to Emergency Operating Spec 69-1001168, Loss of Reactor Coolant/Rcs Pressure, Technical Document

ML20085B041
Person / Time
Site:	Three Mile Island
Issue date:	12/02/1976
From:	BABCOCK & WILCOX CO.
To:
Shared Package
ML20085B036	List: ML20085B030 ML20085B041
References
TASK-*, TASK-02, TASK-2, TASK-GB 69-1001168-02, 69-1001168-2, BWNP-20004-(6-7, GPU-0549, GPU-549, NUDOCS 8307070478
Download: ML20085B041 (7)

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EM!RENCY OPERATING SPECIFICATION t

00 1001168 69 00C. ID-SERIAL NO.-REVISi0it NO.

FOR LO3S OF REACTOR COOLANT / REACTOR COOLANT SYSTEM PRESSURE EOS 0162

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BWP-20005 (6-76) 8ASCOCE & wtLCOI HUCitAt Powte GEMesAftOH oevess3 H Mumass RECORD OF REYlSION 69-1001168-00 REY. NO.

CHANGE SECT / PARA.

DESCRIPTION / CHANGE AUTHORIZATION 00 Original Issue - J. Veenstra Plant Perfor=ance Sves.

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'. TABLE OF CONTENTS / EFFECTIVE PAGE LIST 69-1001168-00 stCTION TITLE PAGE D0C. No.

1.0 PURPOSE 4

69.1001168-00 2.0 SYMPTOMS 4

69-1001168-00

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69-1001168-00 4

3.0 AIITOMATIC ACTION 5

69-1001168-00 4.0 IMEDIATE OPERATOR ACTICN 5

69-1001168-00 6

69-1001168-00 5.0 SUBSEQUENT OPERATOR ACTION 6

69-1001168-00 7

69-1001168-00

6.0 REFERENCES

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,ggg gg g TECifulCAL DOCUMENT 69-1001168-00 1.0 PURPOSE

'This specification describes the recoc: mended actions in the event cf an abnormal 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.

1.2 Intermediate leak - within the capability of the High 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 radiation alarm in reactor building (RS) or other location that could indicate a RCS leak.

2.1.4 Possible RB sump level increase.

2.1.S Greater than normal leakage during the routine performance of Reference 6.2.

2.2 Intermediate Leak 2.2.1 Pressurizer level and RCS pressure decreasing with stable T*** and makeup flow increasing to maximum.

2.2.2 Makeup tank inventory decreasing greater than capacity of one makeup pump but less than capacity of HPI systen.

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

2.2.4 Increasing level in RB su=p with possible high level alarm.

Possible iacrease in RB pressure and te=perature. CONFID 2.2.5 COUNSEL 00 2.2.6 Possible makeup flow high alarm.

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$ASCoCr & wttcoK powet GtHitAttoM OIVIS13N N'D484 3 TECHNICAL DOCUMENT 69-1001168-00 2.3 Large Leak 2.3.1 Rapid decrease in pressuri2.cr level and RCS pressure.

2.3.2

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

2.3.3 liigh ' radiation alarm in RB or other location that could indicate a RCS leak.

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2.3.4 High reactor building pressure and temperature.

2s3.S High RB sump level possibly with a high level alarm.

3.0 AUTOMATIC ACTION 3.1 Small Leak Flow increases through pressuri:er level control valve.

3.2 Intermediate Leak 1

Flow increases through pressurizer level control valve.

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 (Im RCS pressure) 4.0 IMMEDIATE OPERATOR ACTION 4.1 Small Leak 4.1.1 Isolate letdown 4.1.2 Attempt to locate and isolate the leak 4.2 Intermediate Leak 4.2.1 Trip reactor and assure turbine trips C O E 3 M A,-

4.2.2 Isolate letdon 4.2.3 Initiate HPI COLR,lSE ON.Y

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'. TECHNICAL. DOCUMENT 69-1001168-oo 4.3 Large Leak 4.3.1 Verify autcznatic action has taken place

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4.3.2 Isolate letdown 4.3.3 Trip all RC ms if. adequate suction pressure cannot be maintained, then isolate seal flow.

5.0 SUBSEOUENT OPERATOR ACTION 5.1 If a steam generator (SG) tube leak is suspected as the casualty (radiation in secondary steam system or other indication), isolate the affected SG and use remaining SG for, cooldown as required.

Additional measures to reduce secondary system contamination and to reduce or prevent the release of radioactive elements to the atmosphere should be taken.

5.2 Small Leak 5.2.1_

If leakage cannot be reduced to under the limits of Reference 6.1 follow the actions required by Reference 6.1.

5,.2.2 Maintain makeup tank level per Reference 6.3.

5.2.3 Terminate RB purge if in progress.

5.3 Intermediate Leak

• 5.3.1 Operate third makeup pump to aid HPI as needed to maintain pressurizer level.

NOTE:

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

5.3.2 Reduce number of operating RC pumps to one in each loop.

5.3.3 Terminate RB purge if in progress.

5.3.4 Cooldown the plant to cold sh ttdown.

5.3.5 Attempt to find and isolate the leak.

5.3.6 Prior to running out of water for HPI, if pressure is above maximum allowed for the Decay Heat Removal Systen (DHRS), use DHR pump to supply water from RB sump to HPI per Referece 6.8.

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.' TECHNICAL DOCUMENT 69-loo 2168-oo 5.3.7 When RCS pressun allows, use DHR systems in tne RB recirculation mode per Reference 6.8 5.4 Large Ruoture 5.4.1 Verify proper operation of ESFAS, including initiation of low pressure injection when the setpoint is reached.

5.4.2 Cooldown the plant in as near nomal a manner as possible.

While still using water from the borated water storage ta:0: (BWST),

5.4.3 assure adequate fluid supply to the high or low pressure injection systems will be available from the RS sump prior to the BWST low level alam.

5.4.4 Establish normal or RB sump recirculation decay heat removal as appropriate when the BWST low level alam setpoint is reached.

5.4.5 Sample RB hydrogen and initiate hydrogen removal procedures if required.

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5.4.6 Secure ESFAS components as necessary.

5.4.7 Initia.te long term cooling with.the decay heat removal system.

6.0 REFERENCES

6.1 Plant Technical Specifications 6.2 RCS Leak Detection Procedure OS 5021 4

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6.3 Makeisp and Purification System Operatien OS 3521 #

6.4 ESFAS Operation OS 2621 I 6.5 Reactor trip EOS 0172

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6.6 Plant Shut'down OS 0135 6.7 Plant Limits and Precautions OS 1101 7

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t 6.8 DecayHeatItemovalSystemOperatiEOS3621 CO M ElC A'_

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