ML20085B022

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

ML20085B022
Person / Time
Site:	Three Mile Island
Issue date:	12/03/1976
From:	BABCOCK & WILCOX CO.
To:
Shared Package
ML20085B020	List: ML20085B014 ML20085B022
References
TASK-*, TASK-02, TASK-2, TASK-GB 69-1001168-01, 69-1001168-1, BWNP-20004-(6-7, GPU-0548, GPU-548, NUDOCS 8307070472
Download: ML20085B022 (7)

Text

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wucteme powee annemanon oivision TECHNICAL DOCU14ENT 8m EMIRGENCY OPERATING SPECIFICATION t

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DOC. IO-SERIAL No.-REYlSION N0. .

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DRADOCK05000g9 T25750 PAGE 1

BENP-20005 (6-76)

• SASCOCE a wlLCOX N TM 8 E a MuCLt As Powta GENetAtlON CIVISISH RECORD OF REYlSION 69-loo 1168-x IEY. NO. CHANGE SECT / PARA. DESCRIPTION / CHANGE AUTHORIZATION 00 Original Issue - J. Veenstra Plant Perfor=anc.e Sves.

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NUC13 AR PCwg3 GE N t B AT1DN 80VISt%N M4Am *.8 8 TABLE OF CONTENTS / EFFECTIVE PAGE LIST 69-2001168-00 SECTION TITLE PAGE 00C. NO.

1.0 PURPOSE 4 69 ,1001168-00 2.0 SYMPTOMS 4 69-1001168-00

, , S 69-1001168-00' 3.0 - AIJr0MATIC ACTION 5 .

69-1001168-00 4.0 IMEDIATE OPERATOR ACTION 5 69-1001168-00 6 69-1001168-00 S.O SUBSEQUENT OPERATOR ACTION 6 69-1001168-00 7 69-1001168-00

6.0 REFERENCES

7 69-1001168-00 t

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l T25752 DATE: 12-3-76 PAGE 3

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• EUCitAs PQwtB Cgyggan H gevtSISM Muaarts 69-1001168-00 TECHNICAL DOCUMENT 1.0 PURPOSE This specification describes the recommer.ded : :tions in the event of 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 H1'gh 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 SYMFTOMS 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 incre.asing with stable T,y,.

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

2.1.4 Possible RB sump level increase.

2.1.5 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* ** knd '

makeup flow increasing to maximum.

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

2.2.3 Possible radiation alarm in RB or other location that could indi -

cate a RCS leak.

~ C0g n 1 den L 2.2.4 Increasing level in RB sump with possible high level }

2.2.5 Possible increase in RB pressure and te=perature. . ,

2.2.6 Possible makeup flow high alarm. '

T25753 I

l DATE: 12-3-76 PAGE 4

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NUCL1AR Powet etMitATICM CIVISitM 69-100116s-00 TECHiilCAL DOCUMENT 2.3 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 alarm in RB or other locat on that could indicate an RCS Jeak. + .

2.3.4 High reactor building pressure and temperature.

2s3.5 High RB sump level possibly with a high level alarm.

3.0 AUTOMATIC ACTION 3,1 Small Leak Flow increases th cugh pressurizer level control valve.

3.2 Intermediate Leak t

Flow increases through pressurizer level control valve. .

3.3 Large Leak - -

3.3.1 Ensetor trip (Low RCS pressure or low pressurizer level) -

3.3.2 Turbine trip ,

3.3.3 ESFAS Actuation (Low RCS pressure) ,

4.0 IMMEDIATE OPERATOR ACTION 4.1 Small Leak -

4.1.1 Isolate letdown , ,

4.1.2

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Attempt to locate and isolate the leak 4.2 Intermediate Leak ,,

4.2.1 Trip reactor and assure turbine trips C0pMN..,A;- i 4.2.2 Isolate letdo=

COGST_ ONt_Y 4.2.3 Initiate HPI -

T25754 DATE: 12-3-76 PA2 5

. SASCCCI & wtLCCE BWNP-20007 (6-76)

• MucttAt Powes otMERAfsgM CtWIUSH g agggg TECHNICAL DOCUMENT 69-1001168-00 4.3 Large Leak _ , ,

4.3.1 Verify automatic action has taken place 4.3.2 Isolate letdown 4.J.3 Trip all RC pumps 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 require'. d 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 RS purge if in progress.

5.3 Intermediate Leak 5.3.1 Operate third makeup pump to aid HPI as needed to maintain pressurizer level. i 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 R3 purge if in progress.

5.3.4 Cooldown the plant to cold shutdown.

l 5.3.5 Attempt to find and isolate the leak.

5.3.6 Prior to running out of water for HPI, if pressure l .

allowed for the Decay Heat Removal System (DHRS), tg q3:p eu t y supply wate_r from R3 sump to HPI per Reference 6.8Q g n 0 -- Vi I l .

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T25y55 DATE: 12-3-76 , ,, , PAGE b

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' ' TECHNICAL DOCUMENT 69-1001168-00 5.3.7 When RCS pressure allows, use DHR systems in the RB recirculation mode per Reference 6.8.

5.4 Large h um l'54-/4-S.4.1 Verify proper operation of ESFAS, including initiation of low pressure injection when the setpoint is reached. ,;4,:.sc.,.c q h4 S.4.2 Cooldown the plant in as near normal a manner as possible. N N. - -s L. Lb 5.4.3 -

While still using water from the borated water storage tank (BWST),

assure adequate fluid supply to the high or low pressure injection

' systems will be available from the RB sump prior to the BWST low level alarm. .u,#ccs _- _u

(.. , 4 n )s Y 5.4.4 Establish normal or RB sump recirculation decay heat removal as appropriate when the BWST low level alarm setpoint is reached.

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

5.4.6 Secure ESFAS components as necessary. ,b ie,u e,;,: c.__ g,4 5.4.7 Initia.te long term cooling with .the decay heat removal system. ,4.9.M.-f i-

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6.0 REFERENCES

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6.1 Plant Technical Specifications 6.2 RCS Leak Detection Procedure OS 5021 4 gw 6.3 Makiup and Purification System Operation OS 3521 -F ~

6.4 ESFAS Operation OS 2621 I '

6.5 Reactor trip EOS 0172

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6.6 Plant Shutdown OS 0135 .

6.7

• Plant Limits and Precautions OS 1101 L p wtsk.

6.8 5 Decay Heat Re= oval System Operation OS 3621 t

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T25756 DArc: 2;-3-76 PAGE 7

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