ML17331B199

Notifies of LOCA Model Changes or Errors That Meet Definition of Significant as Defined in 10CFR50.46. Determination of Effect of LOCA Model Changes on Plant SBLOCA Analyses Encl

ML17331B199
Person / Time
Site:	Cook
Issue date:	01/12/1994
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1118G, NUDOCS 9401270213
Download: ML17331B199 (13)

Text

ACCELERATEDDI<TRJBUTIONDEMONSTRATIONSYSTEMW~'WREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9401270213DOC.DATE:94/01/12NOTARIZED:NODOCKETFACXL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPXENTAFFILIATIONRMURLEY,T.E.DocumentControlBranch(DocumentControlDesk)I

SUBJECT:

NotifiesofLOCAmodelchangesorerrorsthatmeetdefinitionofsignificantasdefinedin10CFR50.46.DeterminationofeffectofLOCAmodelchangesonpintSBLOCAanalysesencl.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRIENCLgSIZE:L0TXTLE:ORSubmittal:GeneralDistributionNOTES:DRECIPIENTXDCODE/NAMEPD3-1LAHXCKMAN,JINTERNAL:NRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2EXTERNAL:NRCPDRCOPIESLTTRENCL1122111111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DORS/OTSBNRR/DRPWNRR/DSSA/SRXBOCLFDCBG01NSICCOPIESLTTRENCL111111111011DDDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISISFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPXESREQUIRED:LTTR16ENCL14DD IndianaMichiganpowerCompanyp.O.Box16631Columbus,OH43216ELMMANECNEGQMPQWMAEP:NRC:1118GDonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNo.DPR-58andDPR-74REPORTOFSIGNIFICANTLOCAEVALUATIONMODELCHANGESPURSUANTTO10CFR50.46(a)(3)(ii)U.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyJanuary12,1994

DearDr.Murley:

Pursuanttotherequirementsof10CFR50.46(a)(3)(ii),thisletterprovidesnotificationofLOCAmodelchangesorerrorsthatmeetthedefinitionofsignificantasdefinedin10CFR50.46'pecifically,thisletterreportsontheeffectsofaninputerrorinauxiliaryfeedwaterflowrateusedtoanalyzeasmallbreakLOCAanalysisforUnit1.ThisletteralsoservestoprovideadditionalinformationregardinganerrorintheemergencycorecoolingsystemevaluationmethodologyusedbyWestinghouseforUnits1and2thatwasreportedpreviouslyinourletterAEP:NRC:1118F,datedOctober19,1993.TheoriginalsmallbreakLOCA(SBLOCA)analysisforUnits1and2ofDonaldC.CookNuclearPlantwasperformedbyWestinghouseElectricCorporation(Westinghouse)usingtheirNOTRUMPcomputercode.Subsequently,CookNuclearPlantUnits1and2werereanalyzedtodeterminetheimpactofanincreaseinthemainsteamsafetyvalve(MSSV)setpointtolerancefrom+1%to+3S.ThisreanalysiswassubmittedtotheNRCinsupportofourrequesttomodifytheMSSVTechnicalSpecificationsviaourletterAEP:NRC:1169,datedNovember11,1992.WehavediscoveredthattheUnit1SBLOCAreanalysissubmittedvialetterAEP:NRC:1169usednominalauxiliaryfeedwaterflowrates(1258gpmtotaldelivery)insteadofminimumauxiliaryfeedwaterflowrates(750gpmtotaldelivery).SinceminimumauxiliarygggfbP}('940i2702ig9g0ii2PDR,ADQCK05000315'-P,.';'PDR,-'Ql III0"'v~I4l

Dr.T.E.Murley-2-AEP:NRC:1118Gfeedwaterflowratesaremorelimiting,thesmallbreakLOCAforCookNuclearPlantUnit1for+3SMSSVsetpointtolerancehasbeenreanalyzedusingminimumauxiliaryfeedwaterflowrates(750gpmtotaldelivery).Thereanalysisisbeingreportedundertheprovisionsof10CFR50.46becausetheMSSVsetpointtolerancerelaxationSBLOCAanalyseshavebeenincludedinour10CFR50.46reportssinceAEP:NRC:1118D,datedMarch12,1993,wassubmitted.Therefore,webelieveitisappropriatetoreporterrorsfoundintheseanalysesunder10CFR50.46eventhoughtheyhavenotyetbeenapprovedandarenotyetpartofourlicensingbasis.Theseanalysesincludeintheirmodelingnon-discretionarychangestotheSBLOCAmodelasdefinedinWCAP-13251.TheMSSVSBLOCAanalysesboundcurrentlyapprovedoperationallimitsandarethereforeconservative.Therevisedanalysisshowsthatthetotalpeakcladtemperature(PCT)withminimumauxiliaryfeedwaterflowratewithhighheadsafetyinjectioncrosstiesclosedis2068F,whilethePCTreportedinAEP:NRC:1169withnominalauxiliaryfeedwaterwas1878.7~F.SincetheabsolutevalueofthechangeincalculatedPCTexceeds50'F,thechangemeetsthedefinitionofsignificantprovidedin10CFR50.46.Attachment1containsthepeakcladtemperaturescalculatedspecificallyforthesmallbreakLOCAanalysesforCookNuclearPlantUnit1.ThepeakcladtemperaturesforthelargebreakLOCA(LBLOCA)remainthesameasreportedtotheNRCviaourletterAEP:NRC:1118D,datedMarch12,1993'helicensingbasisPCTpluspermanentassessmentforSBLOCAforCookNuclearPlantincludesallpreviouspermanent10CFR50.46modelassessments.TheassessmentofthisreportconsistsofaPCTchangeof189.3FtotheUnit1SBLOCAcrosstiesclosedanalysisbecauseoftheNOTRUMPcodeinputerrorinauxiliaryfeedwaterflowrate.TheSBLOCAanalysiswithhighheadsafetyinjectioncross-tievalveopenhasnotyetbeenperformedbyWestinghouse.Forthiscase,thechangeinPCTformodelassessmentshasbeenestimatedtobe97oFRegardingthesecondissueoferrorinEmergencyCoreCoolingSystem(ECCS)methodology,ourletterAEP:NRC:1118F,datedOctober19,1993,reportederrorswhichWestinghousediscoveredintheirNOTRUMPcomputercodeusedforSBLOCAanalysis,andanerrorinECCSevaluationmethodologyusedbyWestinghousefor ytgD Dr.T.E.Murley-3-AEP:NRC:1118GbothUnits1and2ofCookNuclearPlant.ThefollowingadditionalinformationontheWestinghouseECCSevaluationmethodologyhasbeenprovidedtousbytheWestinghouseOwnersGroup(WOG).WestinghouseplanstomeetwiththeNRCinJanuary1994topresenttheresultsoftheinvestigationsperformedforsafetyinjection(SI)inthebrokenloop,anddiscussthecondensationonsafetyinjectiontestdataandresultingcorrelation.ThismeetingwillserveasthefocalpointfordeterminingthelevelofdetailandschedulerequiredbytheNRCinordertocompletetheirreviewoftheSIinthebrokenloopissue.ShouldfinalresolutionoftheSIinthebrokenloopissuenotchangetheconclusionofWestinghouseletterET-NRC-93-3971,datedSeptember21,1993,andourletterAEP:NRC:1118F,wewillnotfileanadditionalreport.However,shouldfinalresolutionofthisissuechangetheconclusionofourcurrent30dayreport,IndianaMichiganPowerCompanywillprovidefurtherinformationtotheNRCunderlOCFR50.46requirements.Attachment2providesreplacementpagesforpages1,2,and5ofAttachment3tooursubmittalAEP:NRC:1118F,whichcontainedinadvertenterrors.Regardingplansforfutureanalysis,theMSSVanalysiswillprovidethenewanalysisofrecordforSBLOCAforUnit1.Thecross-tievalveopencaseisscheduledtobecompletedinJune1994.SrelE.E.FitzatrickVicePresidentcadAttachmentscc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC:1118GDETERMINATIONOFEFFECTOFLOCAMODELCHANGESONCOOKNUCLEARPLANTSMALLBREAKLOCAANALYSES Attachment1toAEP:NRC:1118GPage1SMALLBREAK.LOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT-2122oF(Comments:EvaluationModel:NOTRUMP,FQT-232,FdH-155,SGTP-15X,OtherHHSICrossTieValveClosed3250MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONSC.PRIORPERMANENTLOCAMODELASSESSMENTS8PCT--268'Fi6PCT-10FD,199310CFR50.46MODELASSESSMENTS(PermanentAssessmentofPCTMargin)1.AuxiliaryFeedwaterFlowRateInputErrorinNOTRUMPComputerCode8PCT-1893FE.LICENSINGBASISPCT+PERMANENTASSESSMENTSPCT-20333'PNote:Asdiscussedinthebodyofthissubmission,priorLOCAmodelassessmentshavebeenabsorbedinnewanalysesperformedtosupportarequestforrelaxationofthemainsteamsafetyvalve(MSSV)setpointtolerance.TheanalysesweresubmittedforNRCreviewwithourletterAEP:NRC:1169,datedNovemberll,1992.Sincetheseanalysesboundcurrentlylicensedoperatingconditions,theresultingchangesarebeingreportedinlieuofdevelopingarackupofevaluationsforeachissuethathasbeenabsorbedintheanalyses.

Attachment1toAEP:NRC:1118GPage2SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT2122P(Comments:EvaluationModel:NCTRUMP,FQT-232,FdM-155,SGTP15X,.Other'HSICrossTieValve0en3588MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONSC.PRIORPERMANENTLOCAMODELASSESSMENTS4PCT-552Ps4PCT-13FD.199310CFR50e46MODELASSESSMENTS(PermanentAssessmentofPCTMargin)1.AuxiliaryFeedwaterFlowRateInputErrorinNOTRUMPComputerCode4PCT~9FE.LICENSINGBASISPCT+PERMANENTASSESSMENTSPCT1654oFNote:Asdiscussedinthebodyofthissubmission,priorLOCAmodelassessmentshavebeenabsorbedinnewanalysesperformedtosupportarequestforrelaxationofthemainsteamsafetyvalve(MSSV)setpointtolerance,TheanalysesweresubmittedforNRCreviewwithourletterAEP:NRC:1169,datedNovember11,1992.Sincetheseanalysesboundcurrentlylicensedoperatingconditions,theresultingchangesarebeingreportedinlieu'fdevelopingarackupofevaluationsforeachissuethathasbeenabsorbedintheanalyses.

ATTACHMENT2TOAEP'NRC'1118GREPLACEMENTPAGESFORATTACHMENT3TOAEP'NRC'1118FLETTER Attachment3toAEP:NRC:1118FPage1SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.PCT'122FgOTRUHP,FQT232,FCR155,3250MwtReactorPowerANALYSISOFRECORD(Comments:EvaluationModel:SGTP15','IOther'HSICrossTieValveClosedB.10CFR50.92SAFETYEVALUATIONSC.PRIORPERMANENTLOCAMODELASSESSMENTShPCT-268~F~RPCT3FD.199310CFR50.46MODELASSESSMENTS(PermanentAssessmentofPCTMargin)1.EffectofSIinBrokenLoop2.EffectofImprovedCondensationModel3.DriftFluxFlowRegimeErrorsRPCT-150'F5PCT150oFRPCT-13FE.LICENSINGBASISPCT+PERMANENTASSESSMENTShPCT1844oFNote:Asdiscussedinthebodyofthissubmission,priorLOCAmodelassessmentshavebeenabsorbedinnewanalysesperformedtosupportarequestforrelaxationofthemainsteamsafetyvalve(MSSV)setpointtolerance.TheanalysesweresubmittedforNRCreviewwithourletterAEP:NRC:1169,datedNovember11,1992.Sincetheseanalysesboundcurrentlylicensedoperatingconditions,theresultingchangesarebeingreportedinlieuofdevelopingarackupofevaluationsforeachissuethathasbeenabsorbedintheanalyses.

Attachment3toAEP:NRC:1118FPage2SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT2122P(Comments:EvaluationModel:NCTRCMP,PQT-232,FdH-155,SGTP15X,Other'HSICrossTieVal~e0en3588MwtReactoPowerB.10CFR50.92SAFETYEVALUATIONSC.PRIORPERMANENTLOCAMODELASSESSMENTSEPCT-552FsRPCT0FD.199310CFR50e46MODELASSESSMENTS(PermanentAssessmentofPCTMargin)l.EffectofSIinBrokenLoop2.EffectofImprovedCondensationModel3.DriftFluxFlowRegimeErrorsEPCT150FRPCT--150'F5PCT-13FE.LICENSINGBASISPCT+PERMANENTASSESSMENTSEPCT1557FNote:Asdiscussedinthebodyofthissubmission,priorLOCAmodelassessmentshavebeenabsorbedinnewanalysesperformedtosupportarequestforrelaxationofthemainsteamsafetyvalve(MSSV)setpointtolerance.TheanalysesweresubmittedforNRCreviewwithourletterAEP:NRC.'1169,datedNovemberll,1992.Sincetheseanalysesboundcurrentlylicensedoperationconditions,theresultingchangesarebeingreportedinlieuofdevelopingarackupofevaluationsforeachissuethathasbeenabsorbedintheanalyses.

Attachment3toAEP:NRC:1118FPage5SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT2A.ANALYSISOFRECORDPCT-~135'F(Comments:EvaluationModel:NOTRUMP,FQT-232,FdH162,SGTP15X,Other'HSICrossTieValve0en3588MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONSdPCT~+14F~C.199310CFR50.46MODELASSESSMENTS(PermanentAssessmentofPCTMargin)1.EffectofSIinBrokenLoop2.EffectofImprovedCondensationModel3.DriftFluxFlowRegimeErrorshPCT150OFhPCT-1500FAPCT-13~FD.LICENSINGBASISPCT+PERMANENTASSESSMENTSPCT15180FNote:Asdiscussedinthebodyofthissubmission,priorLOCAmodelassessmentshavebeenabsorbedinnewanalysesperformedtosupportarequestforrelaxationofthemainsteamsafetyvalve(MSSV)setpointtolerance.TheanalysesweresubmittedforNRCreviewwithourletterAEP:NRC:1169,datedNovemberll,1992.Sincetheseanalysesboundcurrentlylicensedoperatingconditions,theresultingchanges-arebeingreportedinlieuofdevelopingarackupofevaluationsforeachissuethathasbeenabsorbedintheanalyses.