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{{#Wiki_filter:REGULATOINFORMATIONDISTRIBUTIONYSTEM(RIDS)ACCEEETONNER:9812230013DOC.DATE:98/12/17NOTARTEED:NODOCKET¹FACIL:50-315Donald,C.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAME.AUTHORAFFILIATIONBRASSART,"G.IndianaMichiganPowerCo.(formerlyIndiana5MichiganEleSAMPSON,J.R.IndianaMichiganPowerCo.(formerlyIndiana&,MichiganEleRECIP.NAMERECIPIENTAFFILIATION
{{#Wiki_filter:REGULATOINFORMATION DISTRIBUTION YSTEM(RIDS)ACCEEETON NER:9812230013 DOC.DATE:
98/12/17NOTARTEED:
NODOCKET¹FACIL:50-315 Donald,C.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAME.AUTHORAFFILIATION BRASSART,"G.
IndianaMichiganPowerCo.(formerly Indiana5MichiganEleSAMPSON,J.R.
IndianaMichiganPowerCo.(formerly Indiana&,MichiganEleRECIP.NAME RECIPIENT AFFILIATION


==SUBJECT:==
==SUBJECT:==
LER98-047-00:on981117,potential,forincreaseleakagefromreactorcoolantpumpsealswasidentified.UtilisworkingwithWtoresolveissue.CurrentexpectationsaretosubmitupdatetoLERby990215.With981217ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED'.LTRENCLSIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENTIDCODE/NAMEPD3-3PDINTERNAL:AEOD/SPDRAB~FILECENTE~R/DE7EELBNRR/DRCH/HICBNRR/DRCH/HQMBNRR/DSSA/SPLBRGN3FILE01EXTERNAL:LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1122111111111111111111RECIPIENTIDCODE/NAMESTANG,JAEOD/SPD/RRABNRR/DE/ECGBNRR/DE/EMEBNRR/DRCH/HOHBNRR/DRPM/PECBRES/DET/EIBLITCOBRYCE,JHNOACQUEENER,DSNUDOCSFULLTXTCOPIESLTTRENCL11111111111111111111DGNOTETOALLNRZDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROEDESK(DCD)ONEXTENSION415-2083FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR22ENCL22 OneCookRareBiidgnsn.@491066164655901ZINOIAMANICHIGINPOMfKRDecember17,1998UnitedStatesNuclearRegulatoryCommissi'onDocumentControlDeskWashington,DC20555OperatingLicenseDPR-58DocketNo.50-315DocumentControlManager:Inaccordancewiththecriteriaestablishedby10CFR50.73entitledLicenseeEventfIILER315/98-047-00,"Interim-PotentialforIncreaseLeakagefromReactorCoolantPumpSealsIdentified"NocommitmentswereidentifiedinthispreliminarysubmittalJ.R.SampsonSiteVicePresident/mbdAttachmentc:J.L.Caldwell(Acting),RegionIIIR.P.PowersP.A.BarrettJ.B.KingseedR.WhaleD..HahnRecordsCenter,INPONRCResidentInspector98i22300i398i2i7PDRADQCK050003i5SPDR tNRCForm366U.S.NUCLEARREGULATORYCOMMISSION(6-1998)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/charactersforeachblock)APPROVEDBYOMBNO.3150-0104EXPIRES06/30/2001ESTSJATEDBVRDENPERRESPONSETOCOMPLYWITHTISSMANDATORYINFORMATIONCOLLECTIONRKOVKST;$0.0HRS.REPORTEDLESSONSLEARNEDAREINCORPORATEDINTOTHELICENSNGPROCESSANOFEDBACKTOPIDVSTRY.FORWARDCOMMENTSREGARDINGBVRDENESTBJATETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCHrr4F33),V.S.NUCLEARREGVLATORYCOMMISSION,WASHINGTON.DC205550001.ANDTOTHKPAPERWORKREDVCTIONPROJECTo1504101).OFFICEOFMANAGEMENTANDBVDGEf,WASHINGTON,DC20503FACIUTYNAMEI1)TITLE(4)CookNuclearPlantUnit1OOCKETNUMBERI2)05000-315PAGEI3)1of1Interim-PotentialforIncreaseLeakagefromReactorCoolantPumpSealsIdentifiedMONTHDAYYEAREVENTDATE(5)LERNUMBER(6)SEQUENTIALNUMBERREVISIONNUMBERREPORTDATE(7)MONTHDAYYEARAILITYHAMDCCook-Unit2NUMB05000-316OTHERFACILITIESINVOLVED(8)1719981998-047-0012171998AILINKTNUMOPERATINGMODE(9)POWERLEVEL(10)0020.2201(b)20.2203(a)(1)20.2203(a)(2)(i)20.2203(a)(2)(v)20.2203(a)(3)(i)20.2203(a)(3)(ii)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)50.73(a)(2)(viii)50.73(a)(2)(x)73.71THISREPORTISSUBMITTEDPURSUANTTOTHEREQUIREMENTSOF10CFRIi:(Checkoneormore)(11)20.2203(a)(2)(ii)20.2203(a)(2)(iii)20.2203(a)(2)(iv)20.2203(a)(4)50.36(c)(1)50.36(c)(2)LICENSEECONTACTFORTHISLER(12)50.73(a)(2)(iv)50.73(a)(2)(v)50.73(a)(2)(vii)OTHERSpeoEynAberracrbeIowornNRCForm366AMr.GaryBrassart,NuclearSafetyAnalysisSupervisorTELEPHONENUMBER(BICSJdeAreaCode)616/697-5106COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT(13)CAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETOEPlXCAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETOEPIXSUPPLEMENTALREPORTEXPECTED(14)XYES(IfYes,completeEXPECTEDSUBMISSIONDATENOEXPECTEDSUBMISSIONDATE(15MONTH02DAY1598Abstract(Limitto1400spaces,i.e.,approximately15single-spacedtypewrittenlines)(16)OnNovember17,1998,withUnits1and2inMode5,ColdShutdown,itwasidentifiedthatinsomecasestheReactorCoolantPump(RCP)thermalbarrierheatexchangermightnotbeabletomaintainsealleak-offtemperaturesbelowthe235degreeFahrenheit(F)limitduringalossofsealinjection.TheCookUFSARstatesthattheRCPscanbeoperated"indefinitelysincethethermalbarriercoolerhassufficientcapacitytocoolthereactorcoolantflowwhichwouldpassthroughthethermalbarriercoolerandsealleakofffromthepumpvolute".ThisimpliesthattheComponentCoolingWater(CCW)flowtothethermalbarrierheatexchangerprovidesredundantcoolingfortheRCPseals.AsaresultofquestionsaskedbyplantpersonnelregardingtherangeofallowableCCWflowratestothethermalbarrierheatexchangerfortherangeofsealleakoffflowspermittedbyCookoperatingprocedure,WestinghousedeterminedthatiftheRCPsealleakoffflowwerelessthan2gallonsperminute,andtheCCWtemperaturewereabove95degreesF,thesealleakofftemperaturecouldpotentiallyflashtosteamandcausedamagetotheRCPnumber1seal.ThepostulatedRCPnumber1sealdamageduetoflashingmaydegradetheabilitytoperformitsfunctionofRCSpressureboundaryAtthistimeitisnotknownifthepotentialsealdamagewouldbeextensiveenoughtoallowincreasedleakagealongtheRCPshaft.Westinghousehasbeeninformedofthisissue,theWestinghouseSafetyReviewcommitteehasbeguntheirinvestigation,andWestinghousehasputthisissueintotheirPart21reviewprocess.AsCookhasoperatedinthepastwithsealleak-offflowlessthan2gpm,thispotentialconditionwasdeterminedtobereportableinaccordancewith10CFR50.73(a)(2)(ii)(B),asaconditionwhichresultedinthenuclearpowerplantbeinginaconditionthatwasoutsidethedesignbasisoftheplant,astheplantwasdesignedtohaveacertainamountofleakagealongtheshaft.CookisworkingwithWestinghousetoresolvethisissue.CurrentexpectationsaretosubmitanupdatetothisLERbyFebruary15,1999.NRCFORM366(6-1998)}}
LER98-047-00:on 981117,potential, forincreaseleakagefromreactorcoolantpumpsealswasidentified.
UtilisworkingwithWtoresolveissue.Currentexpectations aretosubmitupdatetoLERby990215.With 981217ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED'.LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD3-3PDINTERNAL:
AEOD/SPDRAB~FILECENTE~R/DE7EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3FILE01EXTERNAL:
LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1122111111111111111111RECIPIENT IDCODE/NAME STANG,JAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11111111111111111111DGNOTETOALLNRZDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROEDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR22ENCL22 OneCookRareBiidgnsn.
@491066164655901ZINOIAMANICHIGINPOMfKRDecember17,1998UnitedStatesNuclearRegulatory Commissi'on DocumentControlDeskWashington, DC20555Operating LicenseDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledLicenseeEventfIILER315/98-047-00, "Interim-Potential forIncreaseLeakagefromReactorCoolantPumpSealsIdentified" Nocommitments wereidentified inthispreliminary submittal J.R.SampsonSiteVicePresident
/mbdAttachment c:J.L.Caldwell(Acting),
RegionIIIR.P.PowersP.A.BarrettJ.B.KingseedR.WhaleD..HahnRecordsCenter,INPONRCResidentInspector 98i22300i3 98i2i7PDRADQCK050003i5SPDR tNRCForm366U.S.NUCLEARREGULATORY COMMISSION (6-1998)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNO.3150-0104 EXPIRES06/30/2001 ESTSJATED BVRDENPERRESPONSETOCOMPLYWITHTISSMANDATORY INFORMATION COLLECTION RKOVKST;$0.0HRS.REPORTEDLESSONSLEARNEDAREINCORPORATED INTOTHELICENSNGPROCESSANOFEDBACKTOPIDVSTRY.
FORWARDCOMMENTSREGARDING BVRDENESTBJATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCHrr4F33),V.S.NUCLEARREGVLATORY COMMISSION, WASHINGTON.
DC205550001.
ANDTOTHKPAPERWORK REDVCTION PROJECTo1504101).
OFFICEOFMANAGEMENT ANDBVDGEf,WASHINGTON, DC20503FACIUTYNAMEI1)TITLE(4)CookNuclearPlantUnit1OOCKETNUMBERI2) 05000-315 PAGEI3)1of1Interim-Potential forIncreaseLeakagefromReactorCoolantPumpSealsIdentified MONTHDAYYEAREVENTDATE(5)LERNUMBER(6)SEQUENTIAL NUMBERREVISIONNUMBERREPORTDATE(7)MONTHDAYYEARAILITYHAMDCCook-Unit2NUMB05000-316 OTHERFACILITIES INVOLVED(8)1719981998-047-0012171998AILINKTNUMOPERATING MODE(9)POWERLEVEL(10)0020.2201(b)20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFRIi:(Checkoneormore)(11)20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)
LICENSEECONTACTFORTHISLER(12)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)
OTHERSpeoEynAberracrbeIowornNRCForm366AMr.GaryBrassart, NuclearSafetyAnalysisSupervisor TELEPHONE NUMBER(BICSJdeAreaCode)616/697-5106 COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPlXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(14)XYES(IfYes,completeEXPECTEDSUBMISSION DATENOEXPECTEDSUBMISSION DATE(15MONTH02DAY1598Abstract(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnNovember17,1998,withUnits1and2inMode5,ColdShutdown, itwasidentified thatinsomecasestheReactorCoolantPump(RCP)thermalbarrierheatexchanger mightnotbeabletomaintainsealleak-offtemperatures belowthe235degreeFahrenheit (F)limitduringalossofsealinjection.
TheCookUFSARstatesthattheRCPscanbeoperated"indefinitely sincethethermalbarriercoolerhassufficient capacitytocoolthereactorcoolantflowwhichwouldpassthroughthethermalbarriercoolerandsealleakofffromthepumpvolute".ThisimpliesthattheComponent CoolingWater(CCW)flowtothethermalbarrierheatexchanger providesredundant coolingfortheRCPseals.Asaresultofquestions askedbyplantpersonnel regarding therangeofallowable CCWflowratestothethermalbarrierheatexchanger fortherangeofsealleakoffflowspermitted byCookoperating procedure, Westinghouse determined thatiftheRCPsealleakoffflowwerelessthan2gallonsperminute,andtheCCWtemperature wereabove95degreesF,thesealleakofftemperature couldpotentially flashtosteamandcausedamagetotheRCPnumber1seal.Thepostulated RCPnumber1sealdamageduetoflashingmaydegradetheabilitytoperformitsfunctionofRCSpressureboundaryAt thistimeitisnotknownifthepotential sealdamagewouldbeextensive enoughtoallowincreased leakagealongtheRCPshaft.Westinghouse hasbeeninformedofthisissue,theWestinghouse SafetyReviewcommittee hasbeguntheirinvestigation, andWestinghouse hasputthisissueintotheirPart21reviewprocess.AsCookhasoperatedinthepastwithsealleak-offflowlessthan2gpm,thispotential condition wasdetermined tobereportable inaccordance with10CFR50.73(a)(2)(ii)(B),
asacondition whichresultedinthenuclearpowerplantbeinginacondition thatwasoutsidethedesignbasisoftheplant,astheplantwasdesignedtohaveacertainamountofleakagealongtheshaft.CookisworkingwithWestinghouse toresolvethisissue.Currentexpectations aretosubmitanupdatetothisLERbyFebruary15,1999.NRCFORM366(6-1998)}}

Revision as of 07:07, 29 June 2018

LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A411
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 12/17/1998
From: BRASSART G, SAMPSON J R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-047, LER-98-47, NUDOCS 9812230013
Download: ML17335A411 (3)


Text

REGULATOINFORMATION DISTRIBUTION YSTEM(RIDS)ACCEEETON NER:9812230013 DOC.DATE:

98/12/17NOTARTEED:

NODOCKET¹FACIL:50-315 Donald,C.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAME.AUTHORAFFILIATION BRASSART,"G.

IndianaMichiganPowerCo.(formerly Indiana5MichiganEleSAMPSON,J.R.

IndianaMichiganPowerCo.(formerly Indiana&,MichiganEleRECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER98-047-00:on 981117,potential, forincreaseleakagefromreactorcoolantpumpsealswasidentified.

UtilisworkingwithWtoresolveissue.Currentexpectations aretosubmitupdatetoLERby990215.With 981217ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED'.LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD3-3PDINTERNAL:

AEOD/SPDRAB~FILECENTE~R/DE7EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3FILE01EXTERNAL:

LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1122111111111111111111RECIPIENT IDCODE/NAME STANG,JAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11111111111111111111DGNOTETOALLNRZDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROEDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:

LTTR22ENCL22 OneCookRareBiidgnsn.

@491066164655901ZINOIAMANICHIGINPOMfKRDecember17,1998UnitedStatesNuclearRegulatory Commissi'on DocumentControlDeskWashington, DC20555Operating LicenseDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledLicenseeEventfIILER315/98-047-00, "Interim-Potential forIncreaseLeakagefromReactorCoolantPumpSealsIdentified" Nocommitments wereidentified inthispreliminary submittal J.R.SampsonSiteVicePresident

/mbdAttachment c:J.L.Caldwell(Acting),

RegionIIIR.P.PowersP.A.BarrettJ.B.KingseedR.WhaleD..HahnRecordsCenter,INPONRCResidentInspector 98i22300i3 98i2i7PDRADQCK050003i5SPDR tNRCForm366U.S.NUCLEARREGULATORY COMMISSION (6-1998)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNO.3150-0104 EXPIRES06/30/2001 ESTSJATED BVRDENPERRESPONSETOCOMPLYWITHTISSMANDATORY INFORMATION COLLECTION RKOVKST;$0.0HRS.REPORTEDLESSONSLEARNEDAREINCORPORATED INTOTHELICENSNGPROCESSANOFEDBACKTOPIDVSTRY.

FORWARDCOMMENTSREGARDING BVRDENESTBJATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCHrr4F33),V.S.NUCLEARREGVLATORY COMMISSION, WASHINGTON.

DC205550001.

ANDTOTHKPAPERWORK REDVCTION PROJECTo1504101).

OFFICEOFMANAGEMENT ANDBVDGEf,WASHINGTON, DC20503FACIUTYNAMEI1)TITLE(4)CookNuclearPlantUnit1OOCKETNUMBERI2) 05000-315 PAGEI3)1of1Interim-Potential forIncreaseLeakagefromReactorCoolantPumpSealsIdentified MONTHDAYYEAREVENTDATE(5)LERNUMBER(6)SEQUENTIAL NUMBERREVISIONNUMBERREPORTDATE(7)MONTHDAYYEARAILITYHAMDCCook-Unit2NUMB05000-316 OTHERFACILITIES INVOLVED(8)1719981998-047-0012171998AILINKTNUMOPERATING MODE(9)POWERLEVEL(10)0020.2201(b)20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFRIi:(Checkoneormore)(11)20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEECONTACTFORTHISLER(12)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)

OTHERSpeoEynAberracrbeIowornNRCForm366AMr.GaryBrassart, NuclearSafetyAnalysisSupervisor TELEPHONE NUMBER(BICSJdeAreaCode)616/697-5106 COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPlXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(14)XYES(IfYes,completeEXPECTEDSUBMISSION DATENOEXPECTEDSUBMISSION DATE(15MONTH02DAY1598Abstract(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnNovember17,1998,withUnits1and2inMode5,ColdShutdown, itwasidentified thatinsomecasestheReactorCoolantPump(RCP)thermalbarrierheatexchanger mightnotbeabletomaintainsealleak-offtemperatures belowthe235degreeFahrenheit (F)limitduringalossofsealinjection.

TheCookUFSARstatesthattheRCPscanbeoperated"indefinitely sincethethermalbarriercoolerhassufficient capacitytocoolthereactorcoolantflowwhichwouldpassthroughthethermalbarriercoolerandsealleakofffromthepumpvolute".ThisimpliesthattheComponent CoolingWater(CCW)flowtothethermalbarrierheatexchanger providesredundant coolingfortheRCPseals.Asaresultofquestions askedbyplantpersonnel regarding therangeofallowable CCWflowratestothethermalbarrierheatexchanger fortherangeofsealleakoffflowspermitted byCookoperating procedure, Westinghouse determined thatiftheRCPsealleakoffflowwerelessthan2gallonsperminute,andtheCCWtemperature wereabove95degreesF,thesealleakofftemperature couldpotentially flashtosteamandcausedamagetotheRCPnumber1seal.Thepostulated RCPnumber1sealdamageduetoflashingmaydegradetheabilitytoperformitsfunctionofRCSpressureboundaryAt thistimeitisnotknownifthepotential sealdamagewouldbeextensive enoughtoallowincreased leakagealongtheRCPshaft.Westinghouse hasbeeninformedofthisissue,theWestinghouse SafetyReviewcommittee hasbeguntheirinvestigation, andWestinghouse hasputthisissueintotheirPart21reviewprocess.AsCookhasoperatedinthepastwithsealleak-offflowlessthan2gpm,thispotential condition wasdetermined tobereportable inaccordance with10CFR50.73(a)(2)(ii)(B),

asacondition whichresultedinthenuclearpowerplantbeinginacondition thatwasoutsidethedesignbasisoftheplant,astheplantwasdesignedtohaveacertainamountofleakagealongtheshaft.CookisworkingwithWestinghouse toresolvethisissue.Currentexpectations aretosubmitanupdatetothisLERbyFebruary15,1999.NRCFORM366(6-1998)