ML20024C731
| ML20024C731 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 01/05/1977 |
| From: | Veenstra J BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-*, TASK-02, TASK-07, TASK-08, TASK-2, TASK-7, TASK-8, TASK-GB 69-1001168, 69-1001168-00, BWNP-20004, EOS-0162, EOS-162, GPU-0474, GPU-474, NUDOCS 8307130163 | |
| Download: ML20024C731 (8) | |
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7% s EMERE.NCY OPERATING SPECIFICATION I, . g
, o . 69 - 1001168 - 00 ed t DGC. ID-51 RIAL No.-REVISION NO.
FOR . l I 1 j LOSS OF REACTOR CCOLANT/REACTUR , CCOLLNT SYSTEM PRESSURE
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TECHNICAL DOC 3 MENT 69-ico116a-co - G 4.3 Large Leak 4.3.1 Verify automatic action has taken place 4.3.2 Isolate letdown 4.3.3 Trip all RC pumps if adequate suction pressure cannot be maintained, then, isolate seal flow. , 5.0 SUBSEQUENT OPERATOR ACTION 5.1 If a steam generator (SG) tube leak is sitspected as the casualty (radiation in secondary steam system or other indication), isolate
, the affected SG an'd use r=4"4"g SG for cooldown as required.
Additional measures to reduce secondary system contamination and to reduce or prevent the release of radioactive elements to the at=osphere should be taken. 5.2 Small Leak
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. 5.2.1 If leakage cannot be reduced to under the limits of Reference 6.1 follow the actions required by Reference 6.1.
,g 5.2.2 Maintain makeup tank lever per. Reference 6.3. .
I 5. 2. 3 Terminate R3 purgo if in progress. I l 5.3 Intermediate Leak , - ~ l i . -
! 5.3.1 Operate third makeup pump to aid HPI as needed to maintain j pressuri:er level. -
l NOTE: It will be necessary to take water from the nakeup tank
!. periodically to prevent overfilling due to the return j flow from RC puhp 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 pl. tat to cold shutdown.
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! 5.3.3 Attempt to find and isolate the leak.
5.3.6 Pr-lor- to :. .ing out of water for HPI, if pressure is above naximum allowed for the Decay Hez: Re= oval System (CHRS), use CHR pu=p to supply water from R3 sump to HPI per Reference 6.3. h XC4C717 i DAT3: 12 3 76 .s . P.E 6
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m-20cos (6-76) l Cu.. ,owis ===eeinoa :a==a == TA8LE OF CONTEllT3/EF7ECTlYE PAGE UST 69-2001168-00 Q srcTion Tlitt nst asc. no. 1.0 PURPOSE 4 69-1001168-00 2.0 SN 4 69-1001168-00 5 69-1001168-00
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- AIJICMATIC ETICN S** 69-1001168-00 4.0 IMG!DIATE 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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TIC 3NICAL DOCURIHT 68-2001188 4 O 1.0 PURPOSE This specification describes the recommended actions in the event of,an abnormal decrease in Reactor Coolant System (RC3) pressure or pressuriser 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 Intermedh. ate leak - within the capability of the High Pressure Injection (HPI) System to nhtain RCS pressure. 1.3 Large leak - exceeds the capability of the HPI system to maintain RCS prassure. - - 2.0 SYMFTCME
. 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.
Q 2.1.2 Makeup ficw increasing with stable T,y,. 2.1.3 Possible radiation alarm in reactor building (R3) or other location that could indicats a RCS leak. ~ i - 2.1.4 Possible RB sump 1,evel increase. l 2.1.5 Greater than no: mal leakage during the routine performance of
.I Reference 6.2.
. 2.2 Intermediate Leak "
2.2.1 P:sssuriter level and RCS pressure decreasing with stable T,y, and
; makeup flow increasing to nW mm.
t 2.2.2 Makeup tank inventory decreasing greater than , capacity of one makeup pump bu. less than capacity of HPI system. , 2.2.3 Possible radiation alarm in RS or othe~ location that c:uld indi-cate a RCS leak. 2.2.4 Increasing level in R3 su=p with possible high level alarm. 2.2.5 P ssible increase i$ R3 pressure and te=perature. O 2.2.s Possibte make=g fic hizh ala==. l l
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TECHICAL DOCUMUT 69-1001168-oo 2.3 Larte 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 (ESPAS) actuation. l 2.3.3 High radiation alars in R3 or other location that could indicate a
; RCS leak.
2.3.4 High reactor building pressure and temperature. 2.3.5 High RB sump level possibly with a high level alars. 3.0 AUTCMATIC ACTICN
- 3.1 Small Leak Flow increases through pressuriser level control valve.
i 3.2 Intenediate Leak
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, L7 Flow increases through pressuri:er level control valve. .
3.3
- Large Leak 3.3.1 ,
Reactor trip (Low RCS pressure or icw pressurizer level) , 3.3.2 Turbine trip -
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3.3.3 ESFAS Actuation (Low RCS pressure) , 4.o D94EDIATE OPERATOR AC"'ICN
- 4.1 Small Leak -
4.1.1 Isolate letdown
- t 4.1.2 Attempt to locate and isolate the leak 4.2 Intenediate Leak i
l ! 4.2.1 Trip reactor and assure t=bine trips l, 4.2.2 Isolate letdcwn
!* 4.2.3 Initiate h7I I
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MUCLSAs powge geMesATION 04Wissete MUE448 RECORD OF REYlSION 69-1001168-0a ! EY. No. CNANGE SECT / PARA. DESC21PTION/CNANCE AUTHOtt2ATION 00 Original Issue - J. Veenstra i Plant Perfor: nance Sves. t 9:epared By // [4 w '
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,T,, , e as n.a eaa.= 1 -ea TECHNICAL 80C311131T 69-1 02168-00 5.3.7 When RCS pressure allows, use DHR systems in the RB recirculation mode per Reference 6.8.
5.4 Larze Runture 5.4.1 Verify proper operation of ESFAS, including initiation of low pressure injection when the setpoint is reached. ' l 5.4.2 ' Cooldown the plant in as near normal a manner as possible.
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5.4.3 While still using water from the borated water storage tank (3WST), assure adequate fluid supply to the high or low pressure injection systems will be available from the RB sump prior to the SWST low level alarm. 5.4;4 Establish normal or RB sump recirculation decay heat removal as appropriate when the SWST low level ala=n serpoint is reached.
! 5.4.5 Sample RB hydrogen and initiate hydrogen remeval procedures if ; required. ~
l l '5.4.6 Secure ESFAS components as necessary. . I' Initiate'long ter:n cooling with the decay heat removal system.
' .D,,.5.4.7 ,
6.0 REFERENCES
9 l 6.1 PlantTechnicalSpecificaEions ' 6.2 RCS Leak Detection Procedure OS 5021 - 6.3 Makeup and Purification System Operation CS 3521, 6.4 ESFAS Operation CS 2621 l 6.5 Reactor trip EOS 0172 l l 6.6 Plant Shu-Sown 05 0135 i 5.7 Plant Limits and Precautions CS 1101 l ! 6.3 Decay. Heat Re=cval Systen Operatica 05 3621 l t i
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