ML17264A378: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:CATEGORY1REGULATORY INFORMATION DISTRIBUTION sYSTEM(RIDS)1ACCESSION'BR:9603010220 DOC.DATE:
{{#Wiki_filter:CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION sYSTEM (RIDS)1 ACCESSION'BR:9603010220 DOC.DATE: 96/02/22 NOTARIZED':
96/02/22NOTARIZED':
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NP41E AUTHOR AFFILIATION WI DAY,~.0).Rochester Gas a Elt,ctric Corp.RECIP.N+4E RECIPIENT AFFILIATION j 3//<c'OHNSON,A.R.
NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NP41E AUTHORAFFILIATION WIDAY,~.0).Rochester GasaElt,ctric Corp.RECIP.N+4E RECIPIENT AFFILIATION j3//<c'OHNSON,A.R.
DOCKET I 05000244 05000244 E SUBJEC':.Rev-ll to AP-CCW.1,"Leakage into Component Cooling Loop." , 8'/960222 ltr.A i DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR I ENCL$SIZE: TITLE: OR/Lj.censing Submittal:
DOCKETI0500024405000244ESUBJEC':.Rev
Suppl 1 to NUREG-0737(Generic Ltr 82-33)S!NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
-lltoAP-CCW.1, "LeakageintoComponent CoolingLoop.",8'/960222 ltr.AiDISTRIBUTION CODE:A003DCOPIESRECEIVED:LTR IENCL$SIZE:TITLE:OR/Lj.censing Submittal:
RECIPIENT ID PODE/NAME LA PM INTERNAL:m LE ENTER 0 PECB EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD NRR/DRCH/HHFB RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 Q D E N NOTE TO ALL"RIDS" RECIPIENTS:
Suppl1toNUREG-0737(Generic Ltr82-33)S!NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED/TOTAL NUMBER OF COPIES FEQiIIRED:
RECIPIENT IDPODE/NAME LAPMINTERNAL:m LEENTER0PECBEXTERNAL:
':"'R 9 ENCL 9 0 I~I 1 ZZi ZZZZI ANO IJIjit///I IjjjIjIjI/izui88 umw ROCHESTER GAS AND ELECTRIC CORPORATION re 89EASTAVENUE, ROCHESTER, N.Y.14649<001 JOSEPH A.WIDAY Rant Manager Ginna Nuclear Rant TELEPHONE AREA CODE 716 546-2700 February 22, 1996 U.S.Nuclear Regulatory Commission Document Control Desk ,Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555  
NOACCOPIESLTTRENCL111111111RECIPIENT IDCODE/NAME PDNRR/DRCH/HHFB RES/DSIR/EIB NRCPDRCOPIESLTTRENCL11111111QDENNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKSROOMOWFNSD-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED/TOTALNUMBEROFCOPIESFEQiIIRED:
':"'R9ENCL9 0I~I1 ZZiZZZZIANOIJIjit///I IjjjIjIjI
/izui88umwROCHESTER GASANDELECTRICCORPORATION re89EASTAVENUE, ROCHESTER, N.Y.14649<001 JOSEPHA.WIDAYRantManagerGinnaNuclearRantTELEPHONE AREACODE716546-2700February22,1996U.S.NuclearRegulatory Commission DocumentControlDesk,Attn:AllenR.JohnsonProjectDirectorate I-1Washington, D.C.20555


==Subject:==
==Subject:==
Emergency Operating Procedures R.E.GinnaNuclearPowerPlantDocketNo.50-244
Emergency Operating Procedures R.E.Ginna Nuclear Power Plant Docket No.50-244  


==DearMr.Johnson:==
==Dear Mr.Johnson:==
Asrequested, enclosedareGinnaStationEmergency Operating Procedures.
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Verytrulyyours,shA.WidJAW/jdwxc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406-1415 GinnaUSNRCSeniorResidentInspector Enclosure(s):
Very truly yours, s hA.Wid JAW/jdw xc: U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
AP-CCW.1, Rev.11AP-ELEC.3, Rev.2AP-CCW.2, Rev.12AP-PRZR.1, Rev.8AP-CVCS.1, Rev.10AP-RCC.1, Rev.6AP-ELEC.1, Rev.12AP-RCC.2, Rev.6II9b030%0220 9b0222PDR'ADQCK05000244PDRAP-RCC.3, Rev.1AP-RCP.1, Rev.9AP-RCS.1, Rev.10AP-SW,1,Rev.10AP-TURB.2, Rev.14  
AP-CCW.1, Rev.11 AP-ELEC.3, Rev.2 AP-CCW.2, Rev.12 AP-PRZR.1, Rev.8 AP-CVCS.1, Rev.10 AP-RCC.1, Rev.6 AP-ELEC.1, Rev.12 AP-RCC.2, Rev.6 I I 9b030%0220 9b0222 PDR'ADQCK 05000244 PDR AP-RCC.3, Rev.1 AP-RCP.1, Rev.9 AP-RCS.1, Rev.10 AP-SW,1, Rev.10 AP-TURB.2, Rev.14  
~~I~T~a APCCW.1TITl.f:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE1of14ROCHESTER GASANDELECTRICCORPOTIONGINNASTATIONCONTROLLED COPYNUMBERTECHNICAL REVIPORCREEWDATEPLANTSERINTENDENT EFFECTIVE TECATEGORY1.0REVIEWEDBY:
~~I~T~a AP CCW.1 T I Tl.f: LEAKAGE INTO THE COMPONENT COOLING LOOPREV 9 PAGE 1 of 14 ROCHESTER GAS AND ELECTRIC CORPO TION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVI PORC RE EW DATE PLANT S ERINTENDENT EFFECTIVE TE CATEGORY 1.0 REVIEWED BY:
aD0~t~(~",)'>'<5.h1II EOP:AP-CCW.1LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV'PAGE2of14A.PURPOSE-Thisprocedure providestheactionsrequiredtoidentifyandisolateleakageintotheCCWsystemandtocontroltheplantduringthecourseoftheevent.B.ENTRYCONDITIONS/SYMPTOMS 1.ENTRYCONDITIONS
aD 0~t~(~",)'>'<5.h1 II EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 2 of 14 A.PURPOSE-This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
-Thisprocedure isenteredfrom;a.AP-CVCS.1, CVCSLEAK,or,b.AP-RCS.1, RCSLEAK,or,c.AP-RCP.lRCPSEALMALFUNCTION, whenCCWsurgetanklevelincreasing.
-This procedure is entered from;a.AP-CVCS.1, CVCS LEAK, or, b.AP-RCS.1, RCS LEAK, or, c.AP-RCP.l RCP SEAL MALFUNCTION, when CCW surge tank level increasing.
2.SYMPTOMS-ThesymptomsofLEAKAGEINTOTHECOMPONENT COOLINGLOOPare;a.Annunciator A-5,CCWSURGETANKHILEVEL58.8%,litorb.CCWradiation monitor(R-17)alarm,orc.Annunciator A-7(15),RCPA(B)CCWRETURNHITEMPORLOFLOW165GPM125'F,litord.ErraticRCPlabyrinth sealD/P.  
2.SYMPTOMS-The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;a.Annunciator A-5, CCW SURGE TANK HI LEVEL 58.8%, lit or b.CCW radiation monitor (R-17)alarm, or c.Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, lit or d.Erratic RCP labyrinth seal D/P.  
-~j1MlCtg EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV:9PAGE3of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED*************
-~j1M l C tg EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 3 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*************
x4**xxxx*x*x0***************
x 4**x x x x*x*x 0***************
CAUTIONoIF,ATANYTIMEDURINGTHISPROCEDURE, AREACTORTRIPORSIOCCURS,THENE-O,REACTORTRIPORSAFETYINJECTION, SHALLBEPERFORMED.
CAUTION o IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, THEN E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
oIFCCWSYSTEMRADIATION MONITORALARMS,THENVERIFYCCWSURGETANKVENT,RCV-017,CLOSES.*********
o IF CCW SYSTEM RADIATION MONITOR ALARMS, THEN VERIFY CCW SURGE TANK VENT, RCV-017, CLOSES.************x***x************************
***x***x************************
1 Check CCW Indications a.Check CCW surge tank level INCREASING a.IF level decreasing, THEN go to AP-CCW.2, LOSS OF CCW DURING POWER OPERATION or AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN as necessary.
1CheckCCWIndications a.CheckCCWsurgetanklevelINCREASING a.IFleveldecreasing, THENgotoAP-CCW.2, LOSSOFCCWDURINGPOWEROPERATION orAP-CCW.3, LOSSOFCCW-PLANTSHUTDOWNasnecessary.
IF level stable, THEN return to procedure or step in effect.b.Direct RP tech to perform PC-12.3, DETERMINATION OF CCW SYSTEM LEAKAGE c.CCW radiation monitor, R-17;INCREASING c.Check RCS leakrate.IF RCS leakrate increasing, THEN go to Step 2 (Refer to RCS Leakage Surveillance Sheet)IF RCS leakage and R-17 indication normal, THEN go to Step 13.
IFlevelstable,THENreturntoprocedure orstepineffect.b.DirectRPtechtoperformPC-12.3,DETERMINATION OFCCWSYSTEMLEAKAGEc.CCWradiation monitor,R-17;INCREASING c.CheckRCSleakrate.
I I IIr 4 I I A
IFRCSleakrateincreasing, THENgotoStep2(RefertoRCSLeakageSurveillance Sheet)IFRCSleakageandR-17indication normal,THENgotoStep13.
>~EOP: AP-CCW.1 LITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED********x***0***x*x x x**x x x***************
IIIIr4IIA
CAUTION IF EITHER RCP&#xb9;1 SEAL OUTLET TEMPERATURE EXCEEDS 215'F, THEN THE AFFECTED RCP(S)SHOULD BE STOPPED.********x*****x x x**x x x*x x x***x***********
>~EOP:AP-CCW.1LITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE4of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED********x***0***x*xxx**xxx***************
NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flow is maintained.
CAUTIONIFEITHERRCP&#xb9;1SEALOUTLETTEMPERATURE EXCEEDS215'F,THENTHEAFFECTEDRCP(S)SHOULDBESTOPPED.********x
2 Check RCP Thermal Barrier Indications:
*****xxx**xxx*xxx***x***********
o Labyrinth sea'1 D/Ps-GREATER THAN 15 INCHES OF WATER AND APPROXIMATELY EQUAL o RCP&#xb9;1 seal leak off flows BETWEEN 0.25 GPM AND 5.5 GPM o Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F-EXTINGUISHED IF either pump has indication of a thermal barrier leak, THEN perform the following:
NOTE:RCPsmaybesafelyoperatedwithoutCCWtothethermalbarrierifsealinjection flowismaintained.
a.Verify seal injection flow to affected RCP.b.Close CCW return from affected RCP thermal barrier (labyrinth seal D/P should increase).
2CheckRCPThermalBarrierIndications:
~RCP A, AOV-754A~RCP B, AOV-754B c.Evaluate CCW surge tank level trend.IF leakage into the CCW system has stopped, THEN go to Step 17.3 Check RCS temperature GREATER THAN 350'F Go to Step 7.
oLabyrinth sea'1D/Ps-GREATERTHAN15INCHESOFWATERANDAPPROXIMATELY EQUALoRCP&#xb9;1sealleakoffflowsBETWEEN0.25GPMAND5.5GPMoAnnunciator A-7(15),RCPA(B)CCWRETURNHITEMPORLOFLOW165GPM125'F-EXTINGUISHED IFeitherpumphasindication ofathermalbarrierleak,THENperformthefollowing:
0 I~W s'>0 EOP: AP-CCW F 1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 5 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****x*********x x x%x 4*x x***4****x*x'*******CAUTION CLOSELY MONITOR PRZR LEVEL WHILE LETDOWN IS ISOLATED.********************w********************4 Check NRHX For Le'akage: a.Normal letdown-IN SERVICE a.IF excess letdown in service, THEN perform the following:
a.Verifysealinjection flowtoaffectedRCP.b.CloseCCWreturnfromaffectedRCPthermalbarrier(labyrinth sealD/Pshouldincrease).
1)Close excess letdown flow control valve, HCV-123.2)Close EXCESS LTDN LOOP A COLD TO Hx, AOV-310.3)Go to Step 5.b.Check Letdown Indications:
~RCPA,AOV-754A~RCPB,AOV-754Bc.EvaluateCCWsurgetankleveltrend.IFleakageintotheCCWsystemhasstopped,THENgotoStep17.3CheckRCStemperature GREATERTHAN350'FGotoStep7.
b.Isolate Normal Letdown: o Letdown line flow APPROXIMATELY 40 GPM 1)Close loop B cold leg to REGEN Hx, AOV-427.o Low press LTDN pressure APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand APPROXIMATELY 35%OPEN 2)Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202).3)Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).4)Control charging pump speed as necessary to maintain RCP labyrinth seal D/P less than 80 inches.5)Close charging flow control valve, HCV-142.c.Go to Step 6 6)Go to Step 5.  
0I~Ws'>0 EOP:AP-CCWF1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV:9PAGE5of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED****x*********
~~'f I t+Jf'4'J EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 6 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW surge tank level still increasing, THEN perform the following:
xxx%x4*xx***4****x*x'*******
l)Restore letdown flowpath previously isolated (Refer to Attachment LETDOWN).2)Adjust charging as necessary to restore PRZR level.b.Restore an intact letdown flowpath if available (Refer to Attachment LETDOWN)3)Go to Step 13.c.Check any letdown flowpath RESTORED c.IF no letdown flowpath available, THEN consult Plant Staff.d.Adjust charging as necessary to restore PRZR level
CAUTIONCLOSELYMONITORPRZRLEVELWHILELETDOWNISISOLATED.
~~-l'PC 5>~')y'4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV.-9 PAGE 7 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Stable Plant Conditions:
********************w********************4CheckNRHXForLe'akage:
a.Check Tavg-TRENDING TO TREF b.Check PRZR pressure-TRENDING TO 2235 PSIG a.Insert/withdraw control rods or, if necessary, adjust turbine load to match Tavg to Tref.b.Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.c.Check PRZR level-'RENDING TO PROGRAM c.Verify proper operation of charging pump speed controllers or take manual control of speed controllers to control PRZR level.d.Go to'Step 17 0
a.Normalletdown-INSERVICEa.IFexcessletdowninservice,THENperformthefollowing:
EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 8 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****xx**xx**%x**xxxw4**x%***********x****
1)Closeexcessletdownflowcontrolvalve,HCV-123.2)CloseEXCESSLTDNLOOPACOLDTOHx,AOV-310.3)GotoStep5.b.CheckLetdownIndications:
CAUTION o CLOSELY MONITOR PRZR LEVEL AND RCS PRESSURE WHILE LETDOWN IS ISOLATED.o UNFILTERED WATER MAY DAMAGE RCP SEAL SURFACES.****************
b.IsolateNormalLetdown:oLetdownlineflowAPPROXIMATELY 40GPM1)CloseloopBcoldlegtoREGENHx,AOV-427.oLowpressLTDNpressureAPPROXIMATELY 250PSIGoLetdownpressurecontrolvalve,PCV-135,demandAPPROXIMATELY 35%OPEN2)Closeletdownorificevalves(AOV-200A, AOV-200B, andAOV-202).
x**x**x x x****************
3)Placeletdownpressurecontroller, PCV-135,inMANUALandclosevalve(demandat100%).4)Controlchargingpumpspeedasnecessary tomaintainRCPlabyrinth sealD/Plessthan80inches.5)Closechargingflowcontrolvalve,HCV-142.c.GotoStep66)GotoStep5.  
7 Check NRHX For Leakage: a.Narrow range PRZR level-ON SCALE a.IF the RCS is solid, THEN perform the following:
~~'fIt+Jf'4'J EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV:9PAGE6of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED5CheckIfCCWInleakage HasStopped:a.CCWsurgetanklevel-STABLEa.IFCCWsurgetanklevelstillincreasing, THENperformthefollowing:
b.Isolate letdown flow to NRHX: 1)Stop any running RCP.2)WHEN RCPs stopped, THEN stop any running charging pump.o Ensure the following valves CLOSED~Loop B cold leg to REGEN Hx, AOV-427~Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)~RHR letdown flow control valve, HCV-133 o Close letdown isolation valve, AOV-371 o Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).  
l)Restoreletdownflowpathpreviously isolated(RefertoAttachment LETDOWN).
'I>g',)I l EOP: AP-CCW.1 TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 9 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED************x*x%
2)Adjustchargingasnecessary torestorePRZRlevel.b.Restoreanintactletdownflowpathifavailable (RefertoAttachment LETDOWN)3)GotoStep13.c.CheckanyletdownflowpathRESTOREDc.IFnoletdownflowpathavailable, THENconsultPlantStaff.d.Adjustchargingasnecessary torestorePRZRlevel
~~-l'PC5>~')y'4 EOP:AP-CCW.1LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV.-9PAGE7of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED6Establish StablePlantConditions:
a.CheckTavg-TRENDINGTOTREFb.CheckPRZRpressure-TRENDINGTO2235PSIGa.Insert/withdraw controlrodsor,ifnecessary, adjustturbineloadtomatchTavgtoTref.b.Verifyproperoperation ofPRZRheatersandsprayortakemanualcontrolofPRZRpressurecontroller 431K.c.CheckPRZRlevel-'RENDING TOPROGRAMc.Verifyproperoperation ofchargingpumpspeedcontrollers ortakemanualcontrolofspeedcontrollers tocontrolPRZRlevel.d.Goto'Step17 0
EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE8of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED****xx**xx**%x**xxxw4**x%***********x****
CAUTIONoCLOSELYMONITORPRZRLEVELANDRCSPRESSUREWHILELETDOWNISISOLATED.
oUNFILTERED WATERMAYDAMAGERCPSEALSURFACES.
****************
x**x**xxx****************
7CheckNRHXForLeakage:a.NarrowrangePRZRlevel-ONSCALEa.IFtheRCSissolid,THENperformthefollowing:
b.IsolateletdownflowtoNRHX:1)StopanyrunningRCP.2)WHENRCPsstopped,THENstopanyrunningchargingpump.oEnsurethefollowing valvesCLOSED~LoopBcoldlegtoREGENHx,AOV-427~Letdownorificevalves(AOV-200A, AOV-200B, andAOV-202)~RHRletdownflowcontrolvalve,HCV-133oCloseletdownisolation valve,AOV-371oPlaceletdownpressurecontroller, PCV-135,inMANUALandclosevalve(demandat100%).  
'I>g',)Il EOP:AP-CCW.1TITLELEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE9of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED************x*x%
x*x**%%*>****************
x*x**%%*>****************
CAUTIONIFTHERCSISWATERSOLID,THENANYINCREASEINRCSTEMPERATURE MAYRESULTINASIGNIFICANT RCSPRESSUREINCREASE.
CAUTION IF THE RCS IS WATER SOLID, THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE.RCS HEATUP SHOULD BE PREVENTED.
RCSHEATUPSHOULDBEPREVENTED.
**************
**************
xx%*x*xx*4*x*0*************
x x%*x*x x*4*x*0*************
8CheckIfCCWInleakage HasStopped:a.CCWsurgetanklevel-STABLEa.IFCCWinleakage continues, THENgotoStep9.b.NarrowrangePRZRlevel-ONSCALEb.IFRCSissolid,THENperformthefollowing:
8 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW inleakage continues, THEN go to Step 9.b.Narrow range PRZR level-ON SCALE b.IF RCS is solid, THEN perform the following:
1)EnsurebothRCPsoff.c.Establish excessletdown(RefertoAttachment LETDOWN)2)Cyclechargingpumpsasnecessary tocontrolRCSpressure.
1)Ensure both RCPs off.c.Establish excess letdown (Refer to Attachment LETDOWN)2)Cycle charging pumps as necessary to control RCS pressure.d.Start one charging pump e.Adjust charging flow as necessary to restore PRZR level f.Check RCS temperature
d.Startonechargingpumpe.Adjustchargingflowasnecessary torestorePRZRlevelf.CheckRCStemperature
-STABLE g.Go to Step 17 f.Adjust RHR cooling as necessary.  
-STABLEg.GotoStep17f.AdjustRHRcoolingasnecessary.  
~~o EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 10 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Restore Letdown: a.Check RHR-IN SERVICE a.Perform the following:
~~o EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV'PAGE10of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED9RestoreLetdown:a.CheckRHR-INSERVICEa.Performthefollowing:
1)Establish normal letdown'(Refer to Attachment LETDOWN).b.Open letdown isolation valve, AOV-371 2)Go to Step 10.c.Place letdown controllers in MANUAL at 40%open~TCV-130~PCV-135 d.Manually open RHR LETDOWN TO CVCS, HCV-133 e.Place TCV-130 in AUTO at 105'F f.Place PCV-135 in AUTO at desired pressure g.Start one charging pump h.Adjust charging flow as necessary to restore PRZR, pressure/level  
1)Establish normalletdown'(RefertoAttachment LETDOWN).
b.Openletdownisolation valve,AOV-3712)GotoStep10.c.Placeletdowncontrollers inMANUALat40%open~TCV-130~PCV-135d.ManuallyopenRHRLETDOWNTOCVCS,HCV-133e.PlaceTCV-130inAUTOat105'Ff.PlacePCV-135inAUTOatdesiredpressureg.Startonechargingpumph.Adjustchargingflowasnecessary torestorePRZR,pressure/level  
~~
~~
EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV:9PAGE11of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED**********%
EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**********%
x*xxx*x%%xx*%%%**%'x**xx**x**x*
x*xxx*x%%xx*%%%**%'x**xx**x**x*
CAUTIONoONETRAINOFRHRSHALLBEOPERABLEATALLTIMES.oIFANRHRPUMPORHXISREMOVEDFROMSERVICE,THENOPERABILITY REQUIREMENTS SHOULDBEEVALUATED (REFERTOTECHSPECSECTIONS3.1.1.1AND3.3.1).**************%**************************10CheckRHRSystemForLeakage:a.BothRHRloops-ALIGNEDANDOPERABLEa.IFanyloopisolatedforthisleakinvestigation, THENperformthefollowing:
CAUTION o ONE TRAIN OF RHR SHALL BE OPERABLE AT ALL TIMES.o IF AN RHR PUMP OR HX IS REMOVED FROM SERVICE, THEN OPERABILITY REQUIREMENTS SHOULD BE EVALUATED (REFER TO TECH SPEC SECTIONS 3.1.1.1 AND 3.3.1).**************%**************************10 Check RHR System For Leakage: a.Both RHR loops-ALIGNED AND OPERABLE a.IF any loop isolated for this leak investigation, THEN perform the following:
1)Restoreisolatedlooptoservice(RefertoAttachment RHRISOLandS-13A,RHRLINEUPFORSAFETYINJECTION).
1)Restore isolated loop to service (Refer to Attachment RHR ISOL and S-13A, RHR LINEUP FOR SAFETY INJECTION).
2)WHENlooprestored, THENisolateotherRHRloop(RefertoAttachment RHRISOL).b.IsolateselectedRHRloop(RefertoAttachment RHRISOL)3)GotoStep11.11VerifyRCStemperature-STABLEORDECEASING Increasecoolingfromavailable RHRloop.Attempttoestablish S/Gcoolingifnecessary.
2)WHEN loop restored, THEN isolate other RHR loop (Refer to Attachment RHR ISOL).b.Isolate selected RHR loop (Refer to Attachment RHR ISOL)3)Go to Step 11.11 Verify RCS temperature-STABLE OR DECEASING Increase cooling from available RHR loop.Attempt to establish S/G cooling if necessary.
0'litV,fIv".''J~Es'eJI'k%t EOP:AP-CCW.1LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV'PAGE12of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED12CheckIfCCWInleakage HasStopped:a.CCWsurgetanklevel-STABLEb.GotoStep17a.IFanyRHRloophasNOTbeencheckedforleakage,THENreturntoStep10.IFbothRHRloopshavebeenchecked,THENrestoreRHRloopstooperableandgotoStep13.13CheckRMW.toCCWSurgeTank:oVerifyCCWsurgetankfillvalve,MOV-823-CLOSEDoVerifyRMWpump(s)-OFFIFRMWtoCCWsurgetank,MOV-823,openORRMWpumprunning,THENperformthefollowing:
0'litV,f I v".''J~Es'e J I'k%t EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 12 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE b.Go to Step 17 a.IF any RHR loop has NOT been checked for leakage, THEN return to Step 10.IF both RHR loops have been checked, THEN restore RHR loops to operable and go to Step 13.13 Check RMW.to CCW Surge Tank: o Verify CCW surge tank fill valve, MOV-823-CLOSED o Verify RMW pump(s)-OFF IF RMW to CCW surge tank, MOV-823, open OR RMW pump running, THEN perform the following:
a.CloseCCWsurgetankfillvalve,MOV-823.b.ShutoffrunningRMWpumps.c.IFCCWinleakage stops,THENgotoStep17.  
a.Close CCW surge tank fill valve, MOV-823.b.Shut off running RMW pumps.c.IF CCW inleakage stops, THEN go to Step 17.  
~~Np EOP:AP-CCW.1TITLE:LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE13of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED14CheckForSampleHxLeaks:a.DirectAOtolocallychecknuclearsampleroomHxsoSampleHx(TI-602)commonCCWreturntemperature fromsampleHxs-NORMAL(RefertoAuxBldglogsheet,3of3)oSampleHx(FI-603)commonCCWreturnflowfromsampleHxsNORMAL(RefertoAuxBldglogsheet,3of3)a.Determine whichsampleHxCCWoutlettemperature ishigh,THENperformthefollowing:
~~Np EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 13 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check For Sample Hx Leaks: a.Direct AO to locally check nuclear sample room Hxs o Sample Hx (TI-602)common CCW return temperature from sample Hxs-NORMAL (Refer to Aux Bldg log sheet, 3 of 3)o Sample Hx (FI-603)common CCW return flow from sample Hxs NORMAL (Refer to Aux Bldg log sheet, 3 of 3)a.Determine which sample Hx CCW outlet temperature is high, THEN perform the following:
1)IsolatetheaffectedHx.2)IFCCWinleakage hasstopped,THENgotoStep17.b.DirectRPTechtocheckPASS,-SAMPLINGINPROGRESSb.GotoStep15.c.DirectRPTechtoterminate PASS'sampling d.VerifyCCWinleakage
1)Isolate the affected Hx.2)IF CCW inleakage has stopped, THEN go to Step 17.b.Direct RP Tech to check PASS,-SAMPLING IN PROGRESS b.Go to Step 15.c.Direct RP Tech to terminate PASS'sampling d.Verify CCW inleakage-STOPPED 15 Check SW Header Pressure-LESS THAN 60 PSIG Dispatch AO to check CCW pump discharge pressure.IF SW pressure greater than CCW pressure, THEN investigate possible SW leak into CCW system.**x x x**x*%**x*x x~x x x****%****************
-STOPPED15CheckSWHeaderPressure-LESSTHAN60PSIGDispatchAOtocheckCCWpumpdischarge pressure.
CAUTION IF A SAFEGUARDS PUMP IS TO BE REMOVED FROM SERVICE DURING AN EMERGENCY CONDITION, THEN CONSULT WITH PLANT STAFF PRIOR TO STOPPING PUMP.**************0
IFSWpressuregreaterthanCCWpressure, THENinvestigate possibleSWleakintoCCWsystem.**xxx**x*%**x*xx~xxx****%****************
CAUTIONIFASAFEGUARDS PUMPISTOBEREMOVEDFROMSERVICEDURINGANEMERGENCY CONDITION, THENCONSULTWITHPLANTSTAFFPRIORTOSTOPPINGPUMP.**************0
*0%***%x******************
*0%***%x******************
16CheckSafeguards,Pump StatusALLSAFEGUARDS PUMPSOFF~SIpumps~RHRpumps~CSpumpsIFanyeventinprogressrequiring safeguards pumpoperation, THENconsultPlantStaffforguidanceoncheckingsafeguards pumpsforCCWleakage.
16 Check Safeguards,Pump Status ALL SAFEGUARDS PUMPS OFF~SI pumps~RHR pumps~CS pumps IF any event in progress requiring safeguards pump operation, THEN consult Plant Staff for guidance on checking safeguards pumps for CCW leakage.
04 EOP:AP-CCW.1LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV9PAGE14of14STEPACTION/EXPECTED RESPONSERESPONSENOTOBTAINED17EvaluatePlantConditions:
0 4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Evaluate Plant Conditions:
a.CCWinleakage
a.CCW inleakage-IDENTIFIED AND ISOLATED a.Return to Step 2.b.Determine if operation can continue (Consult Plant staff if necessary)
-IDENTIFIED ANDISOLATEDa.ReturntoStep2.b.Determine ifoperation cancontinue(ConsultPlantstaffifnecessary)
-OPERATION CAN CONTINUE b.IF plant shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.18 Check CCW Surge Tank Level-APPROXIMATELY 50>o Consult RP tech to determine method to drain and dispose of excess CCW.NOTE: Refer to 0-9.3','RC IMMEDIATE NOTIFICATION, for reporting requirements.
-OPERATION CANCONTINUEb.IFplantshutdownisrequired, THENreferto0-2.1,NORMALSHUTDOWNTOHOTSHUTDOWN.
19 Notify Higher Supervision 20 Return To Procedure Or Guidance In Effect-END-A ytgye'(r AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 1 of 1 AP-CCW.1 APPENDIX LIST TITLE 1)ATTACHMENT RHR ISOL 2)ATTACHMENT LETDOWN PAGES
18CheckCCWSurgeTankLevel-APPROXIMATELY 50>oConsultRPtechtodetermine methodtodrainanddisposeofexcessCCW.NOTE:Referto0-9.3','RC IMMEDIATE NOTIFICATION, forreporting requirements.
.0 ll 0~4 ji~y 1 4}}
19NotifyHigherSupervision 20ReturnToProcedure OrGuidanceInEffect-END-Aytgye'(r AP-CCW.1LEAKAGEINTOTHECOMPONENT COOLINGLOOPREV:9PAGE1of1AP-CCW.1APPENDIXLISTTITLE1)ATTACHMENT RHRISOL2)ATTACHMENT LETDOWNPAGES
.0ll0~4ji~y14}}

Revision as of 13:52, 7 July 2018

Rev 11 to AP-CCW.1, Leakage Into Component Cooling Loop, Emergency Operating procedure.W/960222 Ltr
ML17264A378
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/22/1996
From: WIDAY J A
ROCHESTER GAS & ELECTRIC CORP.
To: JOHNSON A R
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AP-CCW.1, NUDOCS 9603010220
Download: ML17264A378 (34)


Text

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION sYSTEM (RIDS)1 ACCESSION'BR:9603010220 DOC.DATE: 96/02/22 NOTARIZED':

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NP41E AUTHOR AFFILIATION WI DAY,~.0).Rochester Gas a Elt,ctric Corp.RECIP.N+4E RECIPIENT AFFILIATION j 3//<c'OHNSON,A.R.

DOCKET I 05000244 05000244 E SUBJEC':.Rev-ll to AP-CCW.1,"Leakage into Component Cooling Loop." , 8'/960222 ltr.A i DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR I ENCL$SIZE: TITLE: OR/Lj.censing Submittal:

Suppl 1 to NUREG-0737(Generic Ltr 82-33)S!NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

RECIPIENT ID PODE/NAME LA PM INTERNAL:m LE ENTER 0 PECB EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD NRR/DRCH/HHFB RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 Q D E N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED/TOTAL NUMBER OF COPIES FEQiIIRED:

':"'R 9 ENCL 9 0 I~I 1 ZZi ZZZZI ANO IJIjit///I IjjjIjIjI/izui88 umw ROCHESTER GAS AND ELECTRIC CORPORATION re 89EASTAVENUE, ROCHESTER, N.Y.14649<001 JOSEPH A.WIDAY Rant Manager Ginna Nuclear Rant TELEPHONE AREA CODE 716 546-2700 February 22, 1996 U.S.Nuclear Regulatory Commission Document Control Desk ,Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555

Subject:

Emergency Operating Procedures R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Johnson:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, s hA.Wid JAW/jdw xc: U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

AP-CCW.1, Rev.11 AP-ELEC.3, Rev.2 AP-CCW.2, Rev.12 AP-PRZR.1, Rev.8 AP-CVCS.1, Rev.10 AP-RCC.1, Rev.6 AP-ELEC.1, Rev.12 AP-RCC.2, Rev.6 I I 9b030%0220 9b0222 PDR'ADQCK 05000244 PDR AP-RCC.3, Rev.1 AP-RCP.1, Rev.9 AP-RCS.1, Rev.10 AP-SW,1, Rev.10 AP-TURB.2, Rev.14

~~I~T~a AP CCW.1 T I Tl.f: LEAKAGE INTO THE COMPONENT COOLING LOOPREV 9 PAGE 1 of 14 ROCHESTER GAS AND ELECTRIC CORPO TION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVI PORC RE EW DATE PLANT S ERINTENDENT EFFECTIVE TE CATEGORY 1.0 REVIEWED BY:

aD 0~t~(~",)'>'<5.h1 II EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 2 of 14 A.PURPOSE-This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS

-This procedure is entered from;a.AP-CVCS.1, CVCS LEAK, or, b.AP-RCS.1, RCS LEAK, or, c.AP-RCP.l RCP SEAL MALFUNCTION, when CCW surge tank level increasing.

2.SYMPTOMS-The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;a.Annunciator A-5, CCW SURGE TANK HI LEVEL 58.8%, lit or b.CCW radiation monitor (R-17)alarm, or c.Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, lit or d.Erratic RCP labyrinth seal D/P.

-~j1M l C tg EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 3 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*************

x 4**x x x x*x*x 0***************

CAUTION o IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, THEN E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.

o IF CCW SYSTEM RADIATION MONITOR ALARMS, THEN VERIFY CCW SURGE TANK VENT, RCV-017, CLOSES.************x***x************************

1 Check CCW Indications a.Check CCW surge tank level INCREASING a.IF level decreasing, THEN go to AP-CCW.2, LOSS OF CCW DURING POWER OPERATION or AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN as necessary.

IF level stable, THEN return to procedure or step in effect.b.Direct RP tech to perform PC-12.3, DETERMINATION OF CCW SYSTEM LEAKAGE c.CCW radiation monitor, R-17;INCREASING c.Check RCS leakrate.IF RCS leakrate increasing, THEN go to Step 2 (Refer to RCS Leakage Surveillance Sheet)IF RCS leakage and R-17 indication normal, THEN go to Step 13.

I I IIr 4 I I A

>~EOP: AP-CCW.1 LITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED********x***0***x*x x x**x x x***************

CAUTION IF EITHER RCP¹1 SEAL OUTLET TEMPERATURE EXCEEDS 215'F, THEN THE AFFECTED RCP(S)SHOULD BE STOPPED.********x*****x x x**x x x*x x x***x***********

NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flow is maintained.

2 Check RCP Thermal Barrier Indications:

o Labyrinth sea'1 D/Ps-GREATER THAN 15 INCHES OF WATER AND APPROXIMATELY EQUAL o RCP¹1 seal leak off flows BETWEEN 0.25 GPM AND 5.5 GPM o Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F-EXTINGUISHED IF either pump has indication of a thermal barrier leak, THEN perform the following:

a.Verify seal injection flow to affected RCP.b.Close CCW return from affected RCP thermal barrier (labyrinth seal D/P should increase).

~RCP A, AOV-754A~RCP B, AOV-754B c.Evaluate CCW surge tank level trend.IF leakage into the CCW system has stopped, THEN go to Step 17.3 Check RCS temperature GREATER THAN 350'F Go to Step 7.

0 I~W s'>0 EOP: AP-CCW F 1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 5 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****x*********x x x%x 4*x x***4****x*x'*******CAUTION CLOSELY MONITOR PRZR LEVEL WHILE LETDOWN IS ISOLATED.********************w********************4 Check NRHX For Le'akage: a.Normal letdown-IN SERVICE a.IF excess letdown in service, THEN perform the following:

1)Close excess letdown flow control valve, HCV-123.2)Close EXCESS LTDN LOOP A COLD TO Hx, AOV-310.3)Go to Step 5.b.Check Letdown Indications:

b.Isolate Normal Letdown: o Letdown line flow APPROXIMATELY 40 GPM 1)Close loop B cold leg to REGEN Hx, AOV-427.o Low press LTDN pressure APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand APPROXIMATELY 35%OPEN 2)Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202).3)Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).4)Control charging pump speed as necessary to maintain RCP labyrinth seal D/P less than 80 inches.5)Close charging flow control valve, HCV-142.c.Go to Step 6 6)Go to Step 5.

~~'f I t+Jf'4'J EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 6 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW surge tank level still increasing, THEN perform the following:

l)Restore letdown flowpath previously isolated (Refer to Attachment LETDOWN).2)Adjust charging as necessary to restore PRZR level.b.Restore an intact letdown flowpath if available (Refer to Attachment LETDOWN)3)Go to Step 13.c.Check any letdown flowpath RESTORED c.IF no letdown flowpath available, THEN consult Plant Staff.d.Adjust charging as necessary to restore PRZR level

~~-l'PC 5>~')y'4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV.-9 PAGE 7 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Stable Plant Conditions:

a.Check Tavg-TRENDING TO TREF b.Check PRZR pressure-TRENDING TO 2235 PSIG a.Insert/withdraw control rods or, if necessary, adjust turbine load to match Tavg to Tref.b.Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.c.Check PRZR level-'RENDING TO PROGRAM c.Verify proper operation of charging pump speed controllers or take manual control of speed controllers to control PRZR level.d.Go to'Step 17 0

EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 8 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****xx**xx**%x**xxxw4**x%***********x****

CAUTION o CLOSELY MONITOR PRZR LEVEL AND RCS PRESSURE WHILE LETDOWN IS ISOLATED.o UNFILTERED WATER MAY DAMAGE RCP SEAL SURFACES.****************

x**x**x x x****************

7 Check NRHX For Leakage: a.Narrow range PRZR level-ON SCALE a.IF the RCS is solid, THEN perform the following:

b.Isolate letdown flow to NRHX: 1)Stop any running RCP.2)WHEN RCPs stopped, THEN stop any running charging pump.o Ensure the following valves CLOSED~Loop B cold leg to REGEN Hx, AOV-427~Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)~RHR letdown flow control valve, HCV-133 o Close letdown isolation valve, AOV-371 o Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).

'I>g',)I l EOP: AP-CCW.1 TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 9 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED************x*x%

x*x**%%*>****************

CAUTION IF THE RCS IS WATER SOLID, THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE.RCS HEATUP SHOULD BE PREVENTED.

x x%*x*x x*4*x*0*************

8 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW inleakage continues, THEN go to Step 9.b.Narrow range PRZR level-ON SCALE b.IF RCS is solid, THEN perform the following:

1)Ensure both RCPs off.c.Establish excess letdown (Refer to Attachment LETDOWN)2)Cycle charging pumps as necessary to control RCS pressure.d.Start one charging pump e.Adjust charging flow as necessary to restore PRZR level f.Check RCS temperature

-STABLE g.Go to Step 17 f.Adjust RHR cooling as necessary.

~~o EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 10 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Restore Letdown: a.Check RHR-IN SERVICE a.Perform the following:

1)Establish normal letdown'(Refer to Attachment LETDOWN).b.Open letdown isolation valve, AOV-371 2)Go to Step 10.c.Place letdown controllers in MANUAL at 40%open~TCV-130~PCV-135 d.Manually open RHR LETDOWN TO CVCS, HCV-133 e.Place TCV-130 in AUTO at 105'F f.Place PCV-135 in AUTO at desired pressure g.Start one charging pump h.Adjust charging flow as necessary to restore PRZR, pressure/level

~~

EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**********%

x*xxx*x%%xx*%%%**%'x**xx**x**x*

CAUTION o ONE TRAIN OF RHR SHALL BE OPERABLE AT ALL TIMES.o IF AN RHR PUMP OR HX IS REMOVED FROM SERVICE, THEN OPERABILITY REQUIREMENTS SHOULD BE EVALUATED (REFER TO TECH SPEC SECTIONS 3.1.1.1 AND 3.3.1).**************%**************************10 Check RHR System For Leakage: a.Both RHR loops-ALIGNED AND OPERABLE a.IF any loop isolated for this leak investigation, THEN perform the following:

1)Restore isolated loop to service (Refer to Attachment RHR ISOL and S-13A, RHR LINEUP FOR SAFETY INJECTION).

2)WHEN loop restored, THEN isolate other RHR loop (Refer to Attachment RHR ISOL).b.Isolate selected RHR loop (Refer to Attachment RHR ISOL)3)Go to Step 11.11 Verify RCS temperature-STABLE OR DECEASING Increase cooling from available RHR loop.Attempt to establish S/G cooling if necessary.

0'litV,f I v".J~Es'e J I'k%t EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 12 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE b.Go to Step 17 a.IF any RHR loop has NOT been checked for leakage, THEN return to Step 10.IF both RHR loops have been checked, THEN restore RHR loops to operable and go to Step 13.13 Check RMW.to CCW Surge Tank: o Verify CCW surge tank fill valve, MOV-823-CLOSED o Verify RMW pump(s)-OFF IF RMW to CCW surge tank, MOV-823, open OR RMW pump running, THEN perform the following:

a.Close CCW surge tank fill valve, MOV-823.b.Shut off running RMW pumps.c.IF CCW inleakage stops, THEN go to Step 17.

~~Np EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 13 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check For Sample Hx Leaks: a.Direct AO to locally check nuclear sample room Hxs o Sample Hx (TI-602)common CCW return temperature from sample Hxs-NORMAL (Refer to Aux Bldg log sheet, 3 of 3)o Sample Hx (FI-603)common CCW return flow from sample Hxs NORMAL (Refer to Aux Bldg log sheet, 3 of 3)a.Determine which sample Hx CCW outlet temperature is high, THEN perform the following:

1)Isolate the affected Hx.2)IF CCW inleakage has stopped, THEN go to Step 17.b.Direct RP Tech to check PASS,-SAMPLING IN PROGRESS b.Go to Step 15.c.Direct RP Tech to terminate PASS'sampling d.Verify CCW inleakage-STOPPED 15 Check SW Header Pressure-LESS THAN 60 PSIG Dispatch AO to check CCW pump discharge pressure.IF SW pressure greater than CCW pressure, THEN investigate possible SW leak into CCW system.**x x x**x*%**x*x x~x x x****%****************

CAUTION IF A SAFEGUARDS PUMP IS TO BE REMOVED FROM SERVICE DURING AN EMERGENCY CONDITION, THEN CONSULT WITH PLANT STAFF PRIOR TO STOPPING PUMP.**************0

  • 0%***%x******************

16 Check Safeguards,Pump Status ALL SAFEGUARDS PUMPS OFF~SI pumps~RHR pumps~CS pumps IF any event in progress requiring safeguards pump operation, THEN consult Plant Staff for guidance on checking safeguards pumps for CCW leakage.

0 4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Evaluate Plant Conditions:

a.CCW inleakage-IDENTIFIED AND ISOLATED a.Return to Step 2.b.Determine if operation can continue (Consult Plant staff if necessary)

-OPERATION CAN CONTINUE b.IF plant shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.18 Check CCW Surge Tank Level-APPROXIMATELY 50>o Consult RP tech to determine method to drain and dispose of excess CCW.NOTE: Refer to 0-9.3','RC IMMEDIATE NOTIFICATION, for reporting requirements.

19 Notify Higher Supervision 20 Return To Procedure Or Guidance In Effect-END-A ytgye'(r AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 1 of 1 AP-CCW.1 APPENDIX LIST TITLE 1)ATTACHMENT RHR ISOL 2)ATTACHMENT LETDOWN PAGES

.0 ll 0~4 ji~y 1 4