ML20062L704
ML20062L704 | |
Person / Time | |
---|---|
Site: | Salem |
Issue date: | 09/19/1980 |
From: | Bailey J, Connor G Public Service Enterprise Group |
To: | |
Shared Package | |
ML18085A819 | List: |
References | |
I-4.7-01, I-4.7-1, NUDOCS 8102170402 | |
Download: ML20062L704 (12) | |
Text
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,t . 1-4.7 EMERGENCY INSTRUCTION l-4.7 STE!t GENERATOR TUBE FAILURE V .
1.0 PU:00SE ,
1.1 IHl3 INSTRUCTION COVERS THE SYMPTOMS, AUTOMATIC ACTIONS AND MANUAL ACTIONS FOR A STEAM 6ENERATOR TURE LEAK AND A STEAM GENERATOR TURE RUPTURE. EITHER OF THESE CONDITIONS RESULT IN LEAKAGE OF REACT 0F COOLANT INTO THE SECONDARY SYSTEM.
1.2 OPERATOR ACTION 15 REQUIRED, IN ACCORDANCE WITH THE ACCIDENT ANALYS!$ IN THE FSAR, IN ORDER TO IDENTIFY AND ISOLATE THE FAULTED STEAM GENERATOR ON A TURE AUPTURE. REACTOR COOLANT SYSTEM PRES $URE MUST BE REDUCED TO LESS THAN 1000 PSI WITHIN 30 MINUTES IN ORDER TO PREVENT LIFTING OF THE STEAM GENERATER SAFETIES AND POWER OPERATED RELIEF VALVE ON TnE AFFECTED STEAM 6ENER' TOR. IHIS WILL MINIMIDE THE RADICACTIV' RELEASE TO TME i ATMOSPHERE AND ENSURE COMPL' ANCE WITH THE LIMITS SPECIFIED IN 10CFR '
1.3 Ih!S INSTRUCTION 13 DIVIDED INTO' TWO PARTS:
? ART I - STEAM 6ENERATOR IU E LEAK, WHICH DEALS WITH LEAKS SMALL ENOUGH WHERE SAFETY INJECTION IS NOT ACTUATED.
EART ll - STEAM GENERATCR I:.3E RUPTURE, WHICH DEALS WITH LEAKS OF A MAGNITUDE NMERE SAFETY INJECT!0*.* '.$ INITIATED.
v PART I 1 T i' f N N '09 TUEE 'EAK 2.0 '"*~!:t CCNDITIONS 2.1 ANY CF THE FOLLOWING HIGH RADIATION ALARMS.
l}(21) STEAM GENERATOR BLOWc:WN 1(2)R19A 12(22) STEAM GENERATOR 3 LOWDOWN 1(2)R193 13(23) STEAM SENERATOR 3LOWDJWN 1(2)R19C 14(24) STEAM GENERATOR BLOWD:WN 1(2)R19D CO*4 DENSER $!R EJECTOR 1(2)R13 SG 3 LOWDOWN FILTER DISCuARGE 1C)R35 CONDENSATE FOLISHING FILTER 1(2)R40 2.2 CHARGING PUMP SPEED AND CHAR 3!NG FLOW INCREASE TO MAINTA!N PRESSURIZER LEVEL NORMAL.
3.0 !"* 01 ATE ACTIONS 3.1 .ci:n s 3.1,.1 (MARGING FLOW I NC R E A! ' *4G 3.1.2 AUTOMATIC MAKEUP TO V".I l
SALEM 5:7 1/. UNIT 2 1 0F 12 REV. 6 8J0 2170%04 ;
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I-4.7 3.1.3 WARNING ALARM ON P?S CHANNEL R19 !$0LATES 12f 22) S/G BD TANx VALVES 11, 12, 13 AND 14 (21, 22, 23 Arc 24)G310 AND 1(2)G350.
3.1.4 HIGH ALARM CN THE STE/.M GENERATOR 3 LOWDOWN RADI ATION MONITORS (R19 THE FOLLOWING:
- A) UNIT 1 - ALARM ON ANY CHANNEL,1R19A-D, WILL TRIP CLOSED 11, 12, 13 AND 14GB4 STEAM GENERATOR 3 LOWDOWN ISCLATION VALVES.
- 3) UNIT 2 - 2R19A w!LL TRIP CLOSED 21G34, STEAM GENERATOR 3 LOWDOWN ISCLATION VALVE.
2R19B WILL TRIP CLOSED 22G34, STEAM GENERATOR 31.0WDOWN ISCLATION ,
VALVE.
2R19C w!LL TRIP CLOSED 23GB4, STEAM 6ENERATOR 3 LOWDOWN ISCLATICN VALVE.
2R19D w!L-. TRIP CLOSED 24634, STEAM GENERATOR 3 LOWDOWN ISCLATION VALVE.
3.1.5 HIGH ALARM ON THE 3LCh:0WN FILTER RADI ATION MCu! TOR,1(2)R35, SHIFTS 3- AY VALVES 1(2)GB74 AND IC)G3112 TO D;scHARGE TO THE WASTE MON! TOR HOLDUP IANKS.
3.2 5.1.ns.:., -
3.2.1 VERIFY Aut:MA:.: ACTIC.5, INITIATE ANY THAT DID NOT OCCUR.
v 3.2.2 ON A HIGH RADI ATION ALAEM CN THE CONDENSATE P0t.!$HING FILTER,1(2)R40, 3YPASS THE CONDENSATE 30LISHlf;3 SYSTEM. i .^ s OPEN 11-13(21-:3)CN108, CCNDENSATE POLISHINGS 3YPASS YALVES CLOSE 1(2)CNICi, CONDENSATE POLISHING INLET VAIVE' 3.2.3 ON A HIGH RADIATION ALARM ON 1R19A-D: ~
OPEN IWD900, 3;0dDOWN SAMPLE DISCHARGE To WASTC HEADER CLOSE IWD901, ;_0WDOWN SAMPLE hlSCHARGE TO NON-NADICACTIVE WASTE.
3.2.4 NOTIFY PERFORMANCE DEPARTMENT s 0F POSSIBLE STEAM GE$ERATOR TUBE LEAK.
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4.0 St9Sio":NT ACTIONS COMMENTS y
4.1 VERIFY ALL IMMEDIATE ACTIONS ARE COMPLETED.
ACCOMPLISH ANY WHICH ARE NOT. ,
4.2. DETERM!NE PRIMARY TO SECONDARY LEAK RATE. 4.2 JECH SPEC .3.4.6.2. s 4.3 DETERMINE wHICH STEAM GENERAToi !S LEAK!NG .4.3 STEAM GENERATOF. 0 AMPLE LINES SY SAMPLi ANALYS!S AND CBSERVI:;3 READINGS w AND RADI ATION t*0N! TORS ARE NOT ON$f!AAl5NERATORSAMPLERAOIAT!0NMONITORS. ISCLATED 3Y THE HIGH RADIATICN DETERMINE SECCMDARY ACTIVITY. $!GNAL.
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SALEM UNIT 1/ UNIT 2 2 ca 12 8? v. 6
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l-4.7 4.4 MONITOR CHARGING PUMP FLOW FC4 A%Y INCREASE AND THE STEAM GENERATOR " AMPLE RADIAT,10N MONITORS h FOR INCREASED READINGS WHICH INDICATE HIGHER LEAKAGE.
4.5 SHUTDOWN THE PLANT WHEN TECHNICAL SPECIFICATION 4.5 THE FAULTY STEAM GENERATOR LEAKAGE L!MITS CR SECONDARY ACT!VITY LIMITS AF.. SHOULD NOT BE STEAMED DURIlJG REACHED LAW 01 1-3.4, "P0wER CPERAT!oN", 1-3.5, SUBSEQUENT C00LDOWN. C00LDOWN
" MINIMUM l.0AD To HOT STANDBY", AND l-3.6, "Hof SHCULD BE ACCOMPLISHED BY USING STANDBY TO COLD SHUTDOWN". THE ATMCSPHERIC STEAM RELIEF
,. VALVES (MS-10) FoR'THE UNAFFECTED STEAM GENERATCRS.
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s PART 11' l-4.7 II. STEAM GFNrRATCR TUEF 00PTURE g,j 2.0 INITI A! CONDITIONS '
2.1 SAFETY INJECT!0N HAS BEEN INITIATED AND IT HAS BEEN DETERM!NED BY USE OF SECTION 5.0, -
"lDENTIFICAT:0N CP ICLLCWUP ACTIONS" OF El I-4.0, " SAFETY INJECTION INITIATICN", THAT A STEAM GENERATOR IUBE RUPTLRE HAS QCCURRED.
3.0 IMYEDIAT
ACTIONS 3.1 AuYorAYtc 3.1.1 WARN!NG ALARM ON EMS lHANNEL R19 ISOLATES 12(22) S/G 3D IANK VALVES 11, 12, 13 AND 14(21, 22, 23 ANr 24)G310 AND 1(2)G350.
3.1.2 HIGH ALARM ON THE STE AM 6ENERATOR 3LOWLCWN RADIATION MCNITORS (R19 THE FOLLOWING:
A) UNIT 1 - ALARM CN C4Y CHANNEL, IR19A-D, WILL TRIP CLOSED 11,12,13 AND 14G34, STEAM GENEa2 tor 3tCWDCWN ISOLATION VALVES.
B) UNIT 2 - 2R19A w!.L TRIP CLOSED 21G34, STEAM GENERATOR 3LOWDCWN ISOLAT!sN VALVE 2R193 WI L TRIP CLOSED 22G34, STEAM GENERATCR BLowochN ISCLATION VALVE 2R19C w!'.L TRIP CLOSED 23634, STEAM 6ENERATCR 3 LOWDOWN ISCLATICN VALVE 2R193 WILL TRIP CLOSED 23G34, STEtM GENERATOR 3LOWDCWN ISCLATICN VALVE 3.1.3 HIGH ALARM ON THE 3LOLOCWN FILTER RADIATION MONITCR 1(2)R35, SHIFTS 3-WAY VALVES 1(2)BG74 AND 1(2)3F111 TO DISCHARGE TO THE WASTE MONITOR HOLDUP IANKS.
3.2 h !
3.2.1 VERIFY THAT ALL IMMEDI ATE LND SUBSEQUENT ACTIONS DESCRIBED IN El 1-4.0, " SAFETY INJECTION }NITIATION", HAVE BEEN PERFCRMED. CCMPLETE ANY ACTIONS WHICH HAVE NOT BEEN PREV!0USLY CCMPLETED.
3.2.2 IF A WARN!NG LLARM HAS BEEN REACHED ON ANY OF THE R-19 CHANNELS, VERIFY THE FOLLOWING ARE CLOSED:
11-14(21-24)G310, 30. 12(22) BLOWDOWN IANK INLET VALVES 1(2)GB50, No.12(22) 3.0WDOWN IANK,lNLET CONTRCL YALVE 3.2.3 IF A HIGH ALARM HAS BEEN REACHED ON AN R-19 CHANNEL, VERIFY THE FOLLOWING ARE I
CLOSED :
UNIT 1 14G34, STEAM GENERATOR 3LCWDOWN ISCLATICN VALVES UNIT 2 - 2R19A - TRIPS 21G34, STEAM GENER$ TOR 3LOWDCWN ISCLATICN VALVES 2R193 - IRIPS 22G34, STEAM GENERAYOR 3LCWDCWN ISCLATICN .'ALVES
(. 2R19C - IRIPS 23G34, STEAM GENERATOR 3LOWDCWN ISCLATION VALVES 2R19D - IRIPS 24GB4, STEAM 6ENERATCR 3LCWDOWN ISOLATION VALVES 1
SALEM UNIT 1/ UNIT 2 gay, 5 '. !
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I-4.7 3.2.4 ON A HIGH RADI ATION ALARM.0N THE CONDENSATE POLISHING FILTER,1(2)R40, BYPASS THE CONDENSATE POLISHi4G SYSTEM.
\,,s OPEN OPCN 11-13(21-23)CNiO8, CONDENSATE POLISHING 3YPASS VALVES CLOSE 1(2)CNIC3, CONDENSATE POLISHING INLET VALVE 3.2.5 ON A HIGH RAb!ATION ALARM ON 1R19A-D:
OPEN IWD900, 3.0WDOWN SAMPLE DISCHARGE TO WASTE HEADER CLOSE IWD901, 3towDOWN SAMPLE DISCHARGE TO NCN-RADICACT!vE WASTE.
4.0 SGSEQUENT ACi10Ns 4.1 VERIFY ALL IMMEDI ATE ACTIONS ARE COMPLETED.
ACCOMPLISH ANY WH1CH ARE NOT, 4.2 IF NOT ALREA*t IDENTIrlED, IDINTIFY THE
- FAULTED STEAM GENERATOR BY:
4.2.1 EXAMINE THE STEAM FLOW' FEED FLOW 4.2.1 A DECREASE IN FEED FLCw ON ONE RECORDERS CN THE CONSC.E FOR STEAM 6Ei.ERATOR PRICR TO THE UNEXPLAINED OR SUDDEN "!SMATCHES 3AFETY INJECTION WILL IDENTIFY ON ONE STEAM GENERATCR. THE FAULTED STEAM GENERATOR.
4.2.2 ISOLATE AUX 1LIARY FEED'ATER FLCW TO 4.2.2 CLOSE THE AF11 t. 21'S. THE ALL STEAM 6F*:9RATCRS A'D OBSERVE THE Aux. FEED PUMPS WILL AUTC-LEVELS AS IND!CATED ON THE NARRCW RANGE MATICALLY RESTART IF LEVEL LEVEL INDICATORS. IHE STEAM GENERATOR IS (18I.
THAT HAS AN INCREASING LEVEL IS THE FAULTY UNIT.
4.2.3 COMPARE RADIATION READ:NGS ON THE 4.2.3 SAMPLE LINES AND RADIATION STEAM GENERATCR 3LOWDCh*J SAMPLE MCNITCRS HAVE BEEN ISOLATED RADIATION MONITORS. ire ONE WITH BY PHASE "A" ISOLATION AND THE H!GHER READING !$ 'ME FAULTY MAY NOT SHOh ANY INCREASE UNIT. IN RADIATION LEVELS.
4.3 RE-ESTABLISM AUXILIARY FEEDWATER FLOW TO 4.3 DO NOT FEED THE FAULTED STEAM THE UNAFFECTED STEAM GENERATOF$ LND CON- 6ENERATOR.
' TROL THE LEVEL AT %33% IN THE 'iARROW RANGE.
4.4 CLcSETHESTEAMGENERATORSTCFVALVE,P.5157, 4.4 THE MAIN STEAM ISCLATION PUSH-
~ 3YPASS VALVE, P.S-18, AND DRAIN VALVE, f.S7, BUTTCN(S) ON THE SAFEGUARDS ON THE AFFECTED STEAM GENERATCR. 3EZEL(S) MAY BE USED.
IF ANY OF THESE VALVES ON THE AULTED ISOLATION OF NCN-FAutTED STEAM STEAM GENERATCR WILL NOT CLOSE, CLCSE THE GENERATCRS WILL RESUt* IN VALVES ON ALL UNAFFECTED STEAP 3ENERATCRS. ISOLAT!CN OF THE FAULTED STEAM GENERATCR.
SALEM U'(!T 1/UN!T 2 3 gp 1] ?EV. 6
l-4.7 4.5 IF THE RCP'S E IN SERVICE, COMPLETE STEPS 4.6 AND 4.7. IF THE RCP'S E 01 IN SERVICE, V COMPLETE STEPS 4.8 AND 4.9.
4.6 REDUCE RCS TEMPERATURE TO <503*F AS Qu!CKLY .
AS POSSIBLE.
4.6.1 IF THE CONMNMR 15 AVt.!LABLt:
- 1. SHIFT THE STEAM DU '? TO PRESS 1. APPROXIMATELY SATURATION CONT AND REDUCE THE SETPolNT TO ?RESSURE FOR 500*F.
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3660 PSIG.
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- 2. WHEN TAVG DECREASES To BELOW THE 2. STEAM DUMP SHOULD i41NTAIN Low-low IAVG INTER CCK RE-ESTABLISH RCS TEMP. s500*F.
STEAM DUMP BY DEPRIS$1NG THE BYPASS IF THE CONTROLLER HAS SATURATED TAVG PuSHBuTTONS 0:; THE STEAM OUMP AND THE DEMAND REMAINS HIGH, GO INTERLOCK IRAIN "$" OR "3" 3EZELS. TO MANUAL AND REDUCE THE DE-MAND AfC., THEN GO 3ACx TO AUTO.
4.6.2 IF THE Q CE311.3 15 NC AVAILABLL 4.6.2 Eo t{Q.I STEAM THE AFFECTED OR THE NCN-FAULTED STE a GENERATORS : TEAM 6ENERATOR.
ARE ISC'.ATED, REDUCE T-E SETPO!NT TO IF THE CONTROLLERS HAVE SAT-s56C PSIG CN THE ATMOS 2HERIC STEAM URATED AND THE DEMAND REMAINS RELIEF YALVES, MS-10 7:R THE UNAFFECTED HIGH AS PRESSURE APPROACHES STEAM GENERATORS. 650 PSIG GO TO MANUAL AND REDUCE THE DEMAND AND THEN Go BACK TO AUTO.
. 4.7 REDUCE RCS PRESSURE TO APPROX.MATELY THE 4.7 MAINTAIN AT LEAST 50*T SuB-PRESSURE OF THE FAULTED STEAM 2ENERATOR COOLING.
3Y FULLY OPENING ONE PRESSUR:'ER SPRAY IME RC? MUST BE RUNNING IN ORDER VALVE USl OR 3). TO GET SPRAY Flow.
IME CRITERIA FOR TRIPPING ALL RCP'S AT 1500 PSIG DOES NOT I APPLY.
4.7.1 IERMINATE THE PRESSURE REDUCTION SY CLOSING THE SPRAY VALVE WHEN RCS PRESSURE IS EQUAL TO T-E FAULTED ,
4.I IF THE RCP'S E E l IN SERVICE, PROCIED 4.8 THE REDUCTION IN RCS TEMP.
l AS FOLLot.S TO REDUCE RCS TEMPERATURE TO AND PRESS. MUST BE DONE QUICXLY 1500*F AS QUICKLY AS POSSIBLE. To MINIMlZE THE RELEASE TO THE ATMOSPHERE FRCM THE AFFECTED l S/G.
1 1 1 1 SALEM INIT 1/ UNIT 2 REV. 6 6 '0F 12
1-4.7 4.8.1 FULLY OPEN THE ATMCSPHERIC' STEAM RELIEF VALVES, .".S-10, CN TH( UN-i AFFECTED STEAN 6ENERATORS.
4.8.2 REDuCs RCS. TEMPERATURE TO 1500*F AS 4.8.2 IAVG l$ NOT VALID WITH NO INDICATED BY THE INCORE THERMOCOUPLES RCP'S IN SERVICE.
OR I HIN THE UNAFFECTED LOOPS. REFER
. TO THE PRESSURE-IEMPEGTURE CURVE TO S/G PRESS IS DETERMINED SY DETERMINE THE REQUIRED STEAM GENERATCR IC. t PRESSURE.
REculRED S/G PRESS IS DE-TERM!NED BY AMCUNT OF DECAY HEAT AS INCICATED BY AI.
EYM PLE.
450*F.
STEAM PRESS SHCULD 3E 410 PSIG.
4.9 REDUCE RCS PRESSURE TC APPRCX MATELY THE 4.9 MAINTAIN AT LEAST 50*F SuB-PRESSURE OF THE FAULTED STEA* SENERATOR C0 CLING.
3Y CPENING ONE PRESSURIZER PC ER OPERATED POWER OPERATED RELIEF VALVE RELIEF VALVE, (PR1 OR 2). StCCx VALVE (PR6 OR 7) MUST BE OPEN.
N 4.9.1 TERMINATE THE PRESSURE REDUCTION BY 4.9.1 PRI RUPTURE DISCS MAY RUPTURE THE PCWER OPERATED REL'EF WHEN RCS G!vlNG CCNTAINMENT INDICATIONS PRESSURE IS ECUAL TO T-E FAULTED SIMILAR TO A LOCA.
STrAM GENERATOR.
4.10 IF 1rit! CAULTED STEAM GENERATC:.15 IDENTIFIED 4.10 NO. 13(23) Aux. :EED PUMP AS E!THER 11 OR 13(21 CR 23) E NO. 11 1 12 TU'3!NE EXHAUSTS TO ATMCSPHERE.
(21 1 22) Aux! !ARY IEEDW TER PUMPS ARE SUPPLYING WATER TO THE NON-FAJLTED STEAM GENERATCRS, STCP NO. 13(23i A,x FEED PUMP.
4.11 STOP THE RESIDUAL HEAT REMOVA. PUMP AS 4.11 IHE RHR PUMPS SHCULD NOT BE
. FOLLowS: ALLOWED TO RUN CN RECIRC FOR MORE THAN s30 MINUTES SINCE THERE IS NO COMPONENT COOLING TO THE RHR HEAT ExCHANGERS.
4.11.1 RESET SAFETY INJECT!0N 3Y DEPRESSING 4.11.1 AUTCMATIC ACTUATICN CF BOTH IRAIN "A" & "3" S'. RESET PU$H- SAFETY INJECTICN WILL NO SUTTONS CN THE SAFEGUA"tDS ACTUATION LCNGER BE AVAILABLE.
SE;ELS ON THE CCNTRCL :CNSOLE. ANY SUBSECUENT ACTUATICN i
MUST SE ACCOMPL SHED MAN- )
UALLY BE INSERTING THE j SAFEGUARDS XEY IN~~. EITHER I
. . . . . , 's- !? Dev. 6 l l
l-4.7 IRAIN "A" OR "3" OPERATE ON THE SAFEGUARDS ACTUATICH V ,
BEZEL AND TURN THE KEY.
IF AT ANY TIME AFTER SAFETY
- INJECTION !$ RESET, A BLACKOUT SIGNAL 13 RECE;VED, THE VITAL B'J SSES WOULD BE STRIPPED Aun THE BLACKOUT LOADS WCULD BE SE-QUENCED ON BY THE SEC. IHE.
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SAFETY INJE TION PUMPS WILL NOT BE RESTARTED. IHEY MUST BE MANUALLY STA9TED AFTER THE LOADING SEQUENCE IS COMPLETE AS INDICATED BY THE LOADING COMPLETE LIGHTS ON THE 1A,13 AND 1C(2A, 23 AND 2C) DIESEL 6ENERATOR BEZELS.
THIS IS TO BE ACCOMPLISHED IN SUCH A MANNER AS TO PREVENT OVERLOADING THE DIESELS. INE LOADS SHOULD BE APPLIED AT s10 SEC. INTERVALS.
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@ MQI, RESTART THE Pur.ii BY MANUALLY INITIATING SAFETY INJECTION AS THIS WILL ALSO START THE RHR PUMPS.
4.11.2 RETET THE SAFEGUARDS L7aDING SEQUENCE BY DEPRESSING ErfRGENCY L'. ADING RESET PUSH-BUTIONS ON THE CCNTROL l0NSOLE FOR 1A, 13 AND 1C(2A, 23 AnD 20 DIESEL GENERATORS.
4.11.3 $TCP BOTH RHR PUMPS.
4.12,WHEN ONE SET OF THE FOLLOWING CONDITIONS EXIST:
4.12.1 PRESSUR!:ER LEVEL >50" ...D INCREASLNG eE >50*F SuBC00 LING.
N 4.12.2 REACTOR COOLANT PRES $L':E INCREASES BY INJECTICN FLOW IS GREATER )
200 PSIG AFTER THE CON ROLLED DEPRES- THAN LEAK FLOW.
g SURIZATION (STED 4.7 C: 4.9)
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- CC is N' 5
c 1-4.7 M
y PRESSURIZER LEVEL IS INCREASING CN 2/3 CHANNELS.
M REACTOR COOLANT SYSTEP' TEMPERATURE !$ MORE IF TEMPERATURE REMAINS BELow THAN 50'F SusC00 LED AS INDICATED BY EITHER THE ISAT -50*F curve ON THE THE WIDE RANGE Ig INDI:ATOR$ ON THE NCN- PRESSURE-IEMPERATURE CURVE, FAULTED LOOPS OR THE INC0FE THERMCCOUPLES. 50*F SUBC00 LING IS ASSURED.
IEli 4.12.1 STOP No. 11 1 12(21 & 22) SAFETY IN-JECTION PUMPS.
4.12.2 IF NO. 13(23) CHARG!NG ? UMP 15 RUNNING, STOP NO. 11 & 12(21 & 22) CHARGING PUMPS. IF NO. 13(23) '.HARGING PUMP IS
[191 RUNN!NG, STCP EIT-t. NO. 11 c., 12 (21 CR 22) CHARG!NG P;'8
- 2.13 ESTABLISH NORMAL CHARGING AN: LETDCWM }AW 0 11-3.3.1, "LSTABt!SHING (==l:GING, l.ET-
" ;0WN AND SEAL-INJECTICN PLCW" 4.13.1 CONTROL PRESSURIZE: LE'EL AT 221.
4.13.2 OPERATE THE PRESSURIZE 7 Hi TERS AS REQUIRED TO MAINTAIN E.IACTOR COCLANT PRES $URE DURING THE SU"SECUENT
- COOL-DOWN.
4.14 IF PRESSURIZER LEVEL CANNOT BF MAINTAINED 4.14 CONTINUE TO MON!TCR FCR THESE
>17%, 01, RCS SuBCO: LING CANNCT BE MAINTAINED CCNDITIONS THRCUGHCUT THE
>50*F, IEN, RESTART NO.114:,D/CR 12 SuBSECuENT COOLDOWN.
(21 AND/OR 22) SAFETY INJECT!!1 PUMP (S).
4.15 IF NO. 11 AND 12(21 AND 22) S;"ETY INJECT!CN 4.15 CONTINUE TO MONITOR THE THESE PUMFS ARE RUNNING AND EITHER fiES$UR!!ER IEVEL CCNDITIONS THROUGHCUT THE CR SUBC00 LING CANNCT BE MAINT!!NED, MANUALLY SUBSECUENT C00LDOWN.
REINITIATE SAFETY INJECTION Bf INSERTING THE SAFEGUARDS KEY INTO EITHER ira!N "A" CR "3" SAFETY INJECTION OPERATE BEZEL AND TURN THE
<!Y. RETURN 70 STEP 4.7 0F Tr!$ INSTRUCTION A?C PROCEED FRCM THERE.
4.16 Wr.EN CONDIT!CNS PERMIT, RETUR . THE 4KV V!TAL sus 3ES TO NCRMAL BY:
ca.E " - 1/UN!T 2 9 Cr 12 Piv. 6
l-4.7 4.16.1 STOP THE EMERGENCY D!ESEL 6ENERATORS LAW 01 IV-16.3.1, " EMERGENCY PCwER - DIESEL
= OPERATION"..
4.16.2 START uR ST'QP VITAL EJS LOAD AS NECESSARY.
4.17 REFER TO El 1-4.2, " RECOVERY FROM SAFETY 4.17 DUE TO ABNCRMAL PLAT;T COND!-
INJECTION" FOR GUIDANCE IN SETURNING TIONS, SCME STEPS MAY NOT BE SYSTEMS TO NORMAL OPERATION IN PREPARATION APPROPRIATE AND SOME EQUIPMENT FOR C00LDOWN. UNAVAILABLE.
4.18 IF NO REACTOR COOLANT ? UMPS ARE IN OPERATION, 4.18 RUNNING NO. 13(23)RCP GIVES START ONE PUMP IN AN UNAFFECTED LOOP. THE BEST PRESSURE CCNTROL.
NO.1](2])RCP WOULD BE THE SECOND CHolCE.
4.19 C0:1MENCr. A CCOLDOWN AND DEPFESSURIZATION OF THE REACTCR CCCLANT SYSTE". AS CESCRIBED BELow. OBSERVE THE FOLLOWI'3 PRECAUTIONS. .
4.19.1 DO NOT ATTEMPT TO CCC.DOWN WITHOUT AT LEAST Or:E RCP IN C:ERATICN.
w., IF AN RCP CANNOT BE STARTED, MAIN- 4.19.1 THE FAULTED STEAM GENERATOR TAIN PRESSURIZER LEVE. AND THE IS AN INTEGRAL PART OF THE FAULTED STEAM GENERATCR LEVI. BY RCS. THE LEVEL WILL BE CONTRCL.ING CHARGING LOW AND CCNTROLLED BY THE PRESSURE PRESSURIZER PRESSURE. IN THE RCS.
4.19.2 MA' i!N LEVEL IN TFE FAULTED STEAM 4.19.2 A SUPERHEATED STEAM BUBBLE GFs sTOR IN THE NARF;W RANGE. MAY EXIST IN THE FAULTED STEAM GENERATCR. IF THIS IS ALLOWED TO CCME IN CCN-TACT WITH THE SUBC00 LED TUBES A RAPID DEPRES$URIZATIC 0F THAT STEAM 6ENERATOR WILL RESULT IN A LARGE OUTFLOW OF WATER FRCM THE RCS AND A RESULTANT'DRCP IN PRESSURIZER LEVEL.
4.19.3 IT IS PREFERRED TO OE:RESSURIZE THE 4.19.3 ALL POTENTIAL RELEASES FAC STEAM GENERATCR BY ALLOWING FROM THE STEAM GENERATCR IT '._ dAIN BACK TO THE RCS. IF TO THE ATMOSPHERE MUST BE FCR SOME REASON THIS IS NOT PCSSIBLE, CALCULATED BEFORE THE g THE FAULTED STEAM GE!:ERATOR w!LL RELEASE. THE RELEASES HAVE TO BE DEPRESSUR::ED BY BLEEDING MUST BE LESS THAN THAT OF STEAM BY CNE OF TFE FOLLOWING: ALLOWED BY 10CFR20.
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1-4.7 I 3. OPEN THE MAIN STEAM STOP 3YPASS ALL RELEASES MUST BE VALVE, MS18, AND 3LEED STEAM TO PREVIOUSLY APPROVED BY THE k*M THE CONDENSER, O', SENIOR SHIFT SUPERVISOR.
- 2. 3RIEFLY'OPEN THE 3 TEAM 6ENERATOR POWER O'PERATED RE'_!EF VALVE, MS-10, APPROXIMATELY 101.
' 4.20 REFER TO 01 1-3.5, " HOT STAN:BY TO COLD SHUTDOWN" FOR DIRECTION AS T3 THE OPERATION OF SUPPORT SYSTEMS DURING THE
.C00LDOWN.
4.21 SAMPLE THE RCS FOR BORON.
4.21.1 30 RATE THE RCS AS NE ESSARY TO 4.21.1 REFER To REACTOR ENGINEER-INSURE SHUTDOWN MARC;N WILL BE ING MANUAL, FIGURE 20A.
MA!! TAINED WHEN COLD SHUTDOWN IS ACHIEVED.
4.21.2 PERIODICALLY SAMPLE THE RCS DURING 4.21.2 THE RCS BnRON CONCENTRATION C00LDOWN TO INSURE S 'JTDOWN MARGIN MAY DECREASE AS THE FAULTED IS MAINTAINED. STEAM 6ENERATC' DRAINS BACE TO THE RCS.
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4.22 DUMP STEAM FROM THE UNAFFECT 3 STEAM 4.22 USE EITHER STEAM DUMP TO 6ENERATORS AND ESTABLISH A C20L 0WN THE CONDENSER OR THE MS-10'S RATE OF '50*F/HR.
4.22.1 MAINTAIN THE LEVEL !:. THE UNAFFECTED S1?ar. GENERATORS
- 333.
4.22.2 MAINTAIN PRESSUR!!EF 3RESSURE LAW THE PRES $URE IEMPERATURE CURVE.
4.27.3 WHEN RCS PRESSURE DECREASES TO 4.22.3 RELEASE THE TAGS AND ENERG121
<1000 PSIG, ISCLATE THE SAFETY THE VALVES. ONCE VALVES INJECTION ACCUMULATOT.S BY CLOSING ARE CLOSED, OPEN THE BREAKER:
THE ACCUMULATOR ISCLATION VALVES, AND TAG FOR THE SHIFT SUPER-11-14(21-14)SJ54. . VISOR.
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1-4.7 4.22.4 WHEN RCS TEMPERATURE IN'THE UN-AFFECTED LOOPS IS DECREASED TO 6%./ <350*F AND RC3 PRES URE IS
<400 PSIG, PLACE THE RHR SYSTEM IN OPERATION IAW O! 11-6.3.2, -
"INITIATidG RESIDUAL HEAT RE-MOVAL".
4.22.5 CONTINUE THE COOLDCwN TO COLD SHUTDOWN CONDITIONS.
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PREPARED 5'Y J. BAllev --
MANAGER-SA(EMGENERATINGSTAilCN REvlEws$ zy G. cause.
50RC MEETING No. 74-80 DATE )/'J5#'J' ,
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SALEM Ust: 1/ UNIT 2 ), n. p, Rgy, g