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

ACCELERATED DI<TRJBUTION DEMONSTRATION SYSTEMW~'WREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9401270213 DOC.DATE:

94/01/12NOTARIZED:

NODOCKETFACXL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.

IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPXENT AFFILIATION RMURLEY,T.E.

DocumentControlBranch(Document ControlDesk)I

SUBJECT:

NotifiesofLOCAmodelchangesorerrorsthatmeetdefinition ofsignificant asdefinedin10CFR50.46.

Determination ofeffectofLOCAmodelchangesonpintSBLOCAanalysesencl.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:L TRIENCLgSIZE:L0TXTLE:ORSubmittal:

GeneralDistribution NOTES:DRECIPIENT XDCODE/NAME PD3-1LAHXCKMAN,J INTERNAL:

NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNAL:

NRCPDRCOPIESLTTRENCL1122111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPWNRR/DSSA/SRXB OCLFDCBG01NSICCOPIESLTTRENCL111111111011DDDNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISISFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPXESREQUIRED:

LTTR16ENCL14DD IndianaMichiganpowerCompanyp.O.Box16631Columbus, OH43216ELMMANECNEGQMPQWMAEP:NRC:1118G DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNo.DPR-58andDPR-74REPORTOFSIGNIFICANT LOCAEVALUATION MODELCHANGESPURSUANTTO10CFR50.46(a)(3)(ii)

U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyJanuary12,1994

DearDr.Murley:

Pursuanttotherequirements of10CFR50.46(a)(3)(ii),

thisletterprovidesnotification ofLOCAmodelchangesorerrorsthatmeetthedefinition ofsignificant asdefinedin10CFR50.46

'pecifically, thisletterreportsontheeffectsofaninputerrorinauxiliary feedwater flowrateusedtoanalyzeasmallbreakLOCAanalysisforUnit1.Thisletteralsoservestoprovideadditional information regarding anerrorintheemergency corecoolingsystemevaluation methodology usedbyWestinghouse forUnits1and2thatwasreportedpreviously inourletterAEP:NRC:1118F, datedOctober19,1993.TheoriginalsmallbreakLOCA(SBLOCA)analysisforUnits1and2ofDonaldC.CookNuclearPlantwasperformed byWestinghouse ElectricCorporation (Westinghouse) usingtheirNOTRUMPcomputercode.Subsequently, CookNuclearPlantUnits1and2werereanalyzed todetermine theimpactofanincreaseinthemainsteamsafetyvalve(MSSV)setpointtolerance from+1%to+3S.Thisreanalysis wassubmitted totheNRCinsupportofourrequesttomodifytheMSSVTechnical Specifications viaourletterAEP:NRC:1169, datedNovember11,1992.Wehavediscovered thattheUnit1SBLOCAreanalysis submitted vialetterAEP:NRC:1169 usednominalauxiliary feedwater flowrates(1258gpmtotaldelivery) insteadofminimumauxiliary feedwater flowrates(750gpmtotaldelivery).

Sinceminimumauxiliary gggfbP}('940i2702ig 9g0ii2PDR,ADQCK05000315'-P,.';'PDR,-'Ql III0"'v~I4l

Dr.T.E.Murley-2-AEP:NRC:1118G feedwater flowratesaremorelimiting, thesmallbreakLOCAforCookNuclearPlantUnit1for+3SMSSVsetpointtolerance hasbeenreanalyzed usingminimumauxiliary feedwater flowrates(750gpmtotaldelivery).

Thereanalysis isbeingreportedundertheprovisions of10CFR50.46 becausetheMSSVsetpointtolerance relaxation SBLOCAanalyseshavebeenincludedinour10CFR50.46 reportssinceAEP:NRC:1118D, datedMarch12,1993,wassubmitted.

Therefore, webelieveitisappropriate toreporterrorsfoundintheseanalysesunder10CFR50.46 eventhoughtheyhavenotyetbeenapprovedandarenotyetpartofourlicensing basis.Theseanalysesincludeintheirmodelingnon-discretionary changestotheSBLOCAmodelasdefinedinWCAP-13251.

TheMSSVSBLOCAanalysesboundcurrently approvedoperational limitsandaretherefore conservative.

Therevisedanalysisshowsthatthetotalpeakcladtemperature (PCT)withminimumauxiliary feedwater flowratewithhighheadsafetyinjection crosstiesclosedis2068F,whilethePCTreportedinAEP:NRC:1169 withnominalauxiliary feedwater was1878.7~F.

Sincetheabsolutevalueofthechangeincalculated PCTexceeds50'F,thechangemeetsthedefinition ofsignificant providedin10CFR50.46.

Attachment 1containsthepeakcladtemperatures calculated specifically forthesmallbreakLOCAanalysesforCookNuclearPlantUnit1.Thepeakcladtemperatures forthelargebreakLOCA(LBLOCA)remainthesameasreportedtotheNRCviaourletterAEP:NRC:1118D, datedMarch12,1993'helicensing basisPCTpluspermanent assessment forSBLOCAforCookNuclearPlantincludesallpreviouspermanent 10CFR50.46 modelassessments.

Theassessment ofthisreportconsistsofaPCTchangeof189.3FtotheUnit1SBLOCAcrosstiesclosedanalysisbecauseoftheNOTRUMPcodeinputerrorinauxiliary feedwater flowrate.TheSBLOCAanalysiswithhighheadsafetyinjection cross-tie valveopenhasnotyetbeenperformed byWestinghouse.

Forthiscase,thechangeinPCTformodelassessments hasbeenestimated tobe97oFRegarding thesecondissueoferrorinEmergency CoreCoolingSystem(ECCS)methodology, ourletterAEP:NRC:1118F, datedOctober19,1993,reportederrorswhichWestinghouse discovered intheirNOTRUMPcomputercodeusedforSBLOCAanalysis, andanerrorinECCSevaluation methodology usedbyWestinghouse for ytgD Dr.T.E.Murley-3-AEP:NRC:1118G bothUnits1and2ofCookNuclearPlant.Thefollowing additional information ontheWestinghouse ECCSevaluation methodology hasbeenprovidedtousbytheWestinghouse OwnersGroup(WOG).Westinghouse planstomeetwiththeNRCinJanuary1994topresenttheresultsoftheinvestigations performed forsafetyinjection (SI)inthebrokenloop,anddiscussthecondensation onsafetyinjection testdataandresulting correlation.

Thismeetingwillserveasthefocalpointfordetermining thelevelofdetailandschedulerequiredbytheNRCinordertocompletetheirreviewoftheSIinthebrokenloopissue.Shouldfinalresolution oftheSIinthebrokenloopissuenotchangetheconclusion ofWestinghouse letterET-NRC-93-3971, datedSeptember 21,1993,andourletterAEP:NRC:1118F, wewillnotfileanadditional report.However,shouldfinalresolution ofthisissuechangetheconclusion ofourcurrent30dayreport,IndianaMichiganPowerCompanywillprovidefurtherinformation totheNRCunderlOCFR50.46 requirements.

Attachment 2providesreplacement pagesforpages1,2,and5ofAttachment 3tooursubmittal AEP:NRC:1118F, whichcontained inadvertent errors.Regarding plansforfutureanalysis, theMSSVanalysiswillprovidethenewanalysisofrecordforSBLOCAforUnit1.Thecross-tie valveopencaseisscheduled tobecompleted inJune1994.SrelE.E.FitzatrickVicePresident cadAttachments cc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector

-BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC:1118G DETERMINATION OFEFFECTOFLOCAMODELCHANGESONCOOKNUCLEARPLANTSMALLBREAKLOCAANALYSES Attachment 1toAEP:NRC:1118G Page1SMALLBREAK.LOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT-2122oF(Comments:

Evaluation Model:NOTRUMP,FQT-232,FdH-155,SGTP-15X, OtherHHSICrossTieValveClosed3250MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONS C.PRIORPERMANENT LOCAMODELASSESSMENTS 8PCT--268'Fi6PCT-10FD,199310CFR50.46MODELASSESSMENTS (Permanent Assessment ofPCTMargin)1.Auxiliary Feedwater FlowRateInputErrorinNOTRUMPComputerCode8PCT-1893FE.LICENSING BASISPCT+PERMANENT ASSESSMENTS PCT-20333'PNote:Asdiscussed inthebodyofthissubmission, priorLOCAmodelassessments havebeenabsorbedinnewanalysesperformed tosupportarequestforrelaxation ofthemainsteamsafetyvalve(MSSV)setpointtolerance.

Theanalysesweresubmitted forNRCreviewwithourletterAEP:NRC:1169, datedNovemberll,1992.Sincetheseanalysesboundcurrently licensedoperating conditions, theresulting changesarebeingreportedinlieuofdeveloping arackupofevaluations foreachissuethathasbeenabsorbedintheanalyses.

Attachment 1toAEP:NRC:1118G Page2SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT2122P(Comments:

Evaluation Model:NCTRUMP,FQT-232,FdM-155,SGTP15X,.Other'HSI CrossTieValve0en3588MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONS C.PRIORPERMANENT LOCAMODELASSESSMENTS 4PCT-552Ps4PCT-13FD.199310CFR50e46MODELASSESSMENTS (Permanent Assessment ofPCTMargin)1.Auxiliary Feedwater FlowRateInputErrorinNOTRUMPComputerCode4PCT~9FE.LICENSING BASISPCT+PERMANENT ASSESSMENTS PCT1654oFNote:Asdiscussed inthebodyofthissubmission, priorLOCAmodelassessments havebeenabsorbedinnewanalysesperformed tosupportarequestforrelaxation ofthemainsteamsafetyvalve(MSSV)setpointtolerance, Theanalysesweresubmitted forNRCreviewwithourletterAEP:NRC:1169, datedNovember11,1992.Sincetheseanalysesboundcurrently licensedoperating conditions, theresulting changesarebeingreportedinlieu'fdeveloping arackupofevaluations foreachissuethathasbeenabsorbedintheanalyses.

ATTACHMENT 2TOAEP'NRC'1118G REPLACEMENT PAGESFORATTACHMENT 3TOAEP'NRC'1118F LETTER Attachment 3toAEP:NRC:1118F Page1SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.PCT'122FgOTRUHP,FQT232,FCR155,3250MwtReactorPowerANALYSISOFRECORD(Comments:

Evaluation Model:SGTP15','IOther'HSI CrossTieValveClosedB.10CFR50.92SAFETYEVALUATIONS C.PRIORPERMANENT LOCAMODELASSESSMENTS hPCT-268~F~RPCT3FD.199310CFR50.46MODELASSESSMENTS (Permanent Assessment ofPCTMargin)1.EffectofSIinBrokenLoop2.EffectofImprovedCondensation Model3.DriftFluxFlowRegimeErrorsRPCT-150'F5PCT150oFRPCT-13FE.LICENSING BASISPCT+PERMANENT ASSESSMENTS hPCT1844oFNote:Asdiscussed inthebodyofthissubmission, priorLOCAmodelassessments havebeenabsorbedinnewanalysesperformed tosupportarequestforrelaxation ofthemainsteamsafetyvalve(MSSV)setpointtolerance.

Theanalysesweresubmitted forNRCreviewwithourletterAEP:NRC:1169, datedNovember11,1992.Sincetheseanalysesboundcurrently licensedoperating conditions, theresulting changesarebeingreportedinlieuofdeveloping arackupofevaluations foreachissuethathasbeenabsorbedintheanalyses.

Attachment 3toAEP:NRC:1118F Page2SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT1A.ANALYSISOFRECORDPCT2122P(Comments:

Evaluation Model:NCTRCMP,PQT-232,FdH-155,SGTP15X,Other'HSI CrossTieVal~e0en3588MwtReactoPowerB.10CFR50.92SAFETYEVALUATIONS C.PRIORPERMANENT LOCAMODELASSESSMENTS EPCT-552FsRPCT0FD.199310CFR50e46MODELASSESSMENTS (Permanent Assessment ofPCTMargin)l.EffectofSIinBrokenLoop2.EffectofImprovedCondensation Model3.DriftFluxFlowRegimeErrorsEPCT150FRPCT--150'F5PCT-13FE.LICENSING BASISPCT+PERMANENT ASSESSMENTS EPCT1557FNote:Asdiscussed inthebodyofthissubmission, priorLOCAmodelassessments havebeenabsorbedinnewanalysesperformed tosupportarequestforrelaxation ofthemainsteamsafetyvalve(MSSV)setpointtolerance.

Theanalysesweresubmitted forNRCreviewwithourletterAEP:NRC.'1169, datedNovemberll,1992.Sincetheseanalysesboundcurrently licensedoperation conditions, theresulting changesarebeingreportedinlieuofdeveloping arackupofevaluations foreachissuethathasbeenabsorbedintheanalyses.

Attachment 3toAEP:NRC:1118F Page5SMALLBREAKLOCAPLANTNAME:DONALDC.COOKNUCLEARPLANTUNIT2A.ANALYSISOFRECORDPCT-~135'F(Comments:

Evaluation Model:NOTRUMP,FQT-232,FdH162,SGTP15X,Other'HSI CrossTieValve0en3588MwtReactorPowerB.10CFR50.92SAFETYEVALUATIONS dPCT~+14F~C.199310CFR50.46MODELASSESSMENTS (Permanent Assessment ofPCTMargin)1.EffectofSIinBrokenLoop2.EffectofImprovedCondensation Model3.DriftFluxFlowRegimeErrorshPCT150OFhPCT-1500FAPCT-13~FD.LICENSING BASISPCT+PERMANENT ASSESSMENTS PCT15180FNote:Asdiscussed inthebodyofthissubmission, priorLOCAmodelassessments havebeenabsorbedinnewanalysesperformed tosupportarequestforrelaxation ofthemainsteamsafetyvalve(MSSV)setpointtolerance.

Theanalysesweresubmitted forNRCreviewwithourletterAEP:NRC:1169, datedNovemberll,1992.Sincetheseanalysesboundcurrently licensedoperating conditions, theresulting changes-arebeingreportedinlieuofdeveloping arackupofevaluations foreachissuethathasbeenabsorbedintheanalyses.