ML17333A287

Responds to 950925 RAI Re 941116 Ltr Requesting Change to Min Time Delay Required After Shutdown for Movement of Spent Fuel from Core to Storage in Spent Fuel Pool

ML17333A287
Person / Time
Site:	Cook
Issue date:	02/01/1996
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A288	List: ML17333A287 ML17333A289
References
AEP:NRC:1202A, NUDOCS 9602080078
Download: ML17333A287 (9)

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CATEGORY1REGULATOINFORMATIONDISTRIBUTIONSYSTEM(RIDS)i"ACCESSIONNBR:960208007'8",DOC.DATE:96/02/01NOTARIZED:YESDOCKETFACIi".50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM,.05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndianaSMichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

Respondsto950925RAIre941116ltrrequestingchangetomintimedelayrequiredaftershutdownformovementofspentfuelfromcoretostorageinspentfuelpool.DISTRIBUTIONCODE:00010COPIESRECEIVED:LTR!ENCLlSIZE:7+TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNL:FILECEN~ER~N01RRDRY/HICBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL111111111.1NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKiROOMOWFN5D-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11 0i' IndianaMichiganPowerCompanyPOBox16631Columbus,OH43216February1,1996lNOIANAMICHlGANPWKRAEP:NRC:1202ADocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2REFUELINGOPERATIONSDECAYTIMEUPDATEDANALYSISANDRESPONSETOREQUESTFORADDITIONALINFORMATIONThisletteranditsattachmentsconstitutearesponsetotheSeptember25,1995,requestforadditionalinformationconcerningourNovember16,1994,submittal(AEP:NRC:1202).Ouroriginal,submittalrequestedachangetotheminimumtimedelayrequiredaftershutdownformovementofspentfuelfromthecoretostorageinthespentfuelpool.Attachment1containsourresponsetotherequestforinformation.Attachment2containsarevisedthermal-hydraulicanalysiswhichreflectschangesinoperationalstrategiestoincludelongerfuelcyclesonbothunits,andapotentialincreaseinlicensedpowerforDonaldC.CookNuclearPlantUnit2.Thethermal-hydraulicanalysissummarizedinattachment2superce'desthethermal-hydraulicanalysissubmittedinAEP:NRC:1202.TheclarificationstothespentnuclearfuelpoolstoragerackboralpoisonsurveillanceprogrampresentedinAEP:NRC:1202do,however,remainvalid.Theresultspresentedinattachment2demonstratethatthemaximumbulkspentfuelpoolwatertemperatureisboundedbythe155FpresentedinAEP:NRC:1202fornormaldischargescenerios.Theconclusionsofthenosignificanthazardsconsiderationperformedpursuantto10CFR50.92containedintheoriginalsubmittal,therefore,remainvalid.Incompliancewiththerequirementsof10CFR50.91(b)(l),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.J.R.Padgett,oftheMichiganPublicServiceCommission,andtotheMichiganDepartmentofPublicHealth.0800349602080078'760201PDRADQCK05000315,PPDRpgiI U.S.NuclearRegulatoryCommissionPage2AEP'NRC:1202AThisletterissubmittedpursuantto10CFR50.30(b)and,assuch,anoathstatementisattached.Sincerely,E.E.FitzatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS@~DAYOF~~1996NoaryPublid-dpitAttachmentsCC:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC1202ARESPONSETOREQUESTFORADDITIONALINFORMATION ATTACHMENT1TOAEP:NRC:1202APage1SWERSTORAIBYThissectioncontainsresponsestoquestionsposedbytheUSNRCinresponsetothepreviouslysubmittedHoltecReportHI-941183.Anyreferencetotablesorfiguresinthissectionrefertothecorrespondingarticlesineithertheoriginallicensingreport(datedJuly26,1991)orHoltecReportHI-941183.Ql.ItisassumedthatthecombinedSFPHxheatloadandevaporativeheatlosses(asshowninTable2.2ofHoltecReportHI-941183)areequivalenttothetotaldecayheatgenerationineachcase,e.g.,CaselASFPHxload30.84E6BTU/Hr.+evaporativelosses3.14E6BTU/Hr.,foratotalof33.98E6BTU/Hr.Ifthisisincorrect,explainwhatthecorrectdecayheatloadisineachcaseandjustifyanydifferences.A1.Yourassumptioniscorrectasstated.ThetotaldecayheatgenerationisequaltothesumoftheSPFHxheatloadandtheevaporativecoolingloss.Q2.Apreliminarycomparisonwasmadeofthedecayheatgeneratedbythe80fuelelementsdepositedinthespentfuelpoolincases1A,1Band2forthedecaytimesshowninTable2.2withsimilarcasesinTable5.5.1ofyourprevioussubmittaldatedJuly26,1991whereinthefuelwaspermittedtodecayfor168inlieuofthedecayperiodof100hourspresentlyrequested.Thatcomparisonshowsdifferencesof2.6to2.7E6BTU/Hr.inlieuofthedifferencesyoushowof0.71to0.86E6BTU/Hr.Justifyyourcalculations.A2.Thereductioninthereactorholdtimewillincreasethedecayheatofthefreshlydischargedfuelassembliesonly,thedecayheatfrompreviouslydischargedfuelsisnotaffectedbythechangeinholdtime.However,thefreshfueldecayheataccountsforlessthan508ofthetotalheatgeneration.Additionally,HoltecReportHI-941183incorporateschangestotherefuelingschedulewhichreducethedecayheatcontributionofthepreviouslydischargedfuel.Refuelingschedulechangesincludedusingactualrefuelingoutagedurationsandassemblydischargeburnups.Actualrefuelingoutagelengthswerelongerthanforecastedandactualassemblydischargeburnupswerelowerthatpreviouslyassumed.Thesefactorstendtodecreasethedecayheatcontributionofthepreviouslydischargedfuel.Thereductioninthedecayheatofthepreviouslydischargedfuelservestolimittheincreaseinthetotaldecayheatgenerationrate.Q3.ExplainwhetheryouhavedeviatedfromTable2.1ofHoltecreportHi-941183inusingthenumberofthosedischarged ATTACHMENT1TOAEP'NRC'1202APage2assembliesanddatesofdischargesincalculatingtheheatgenerationofthespentfuelassembliesstoredinthespentfuelpool.Forexample,youstatedthatyoucalculatedtheheatgenerationfor80fuelassembliesinanormaldischargebatchinlieuof76showninTable2.1.A3.ThedecayheatcalculationsinHoltecReportHI-941183aredevisedtoprovideanupperboundtoanyactualdischargescenarios.ThecalculationofthedecayheatgenerationfromallpreviouslydischargedfuelsisbasedontherefuelingscheduleofTable2.1.However,thenormaldischargebatchfromUnit1containsmoreassembliesthandoesUnit2.Toprovideananalysisthatboundsallnormaldischargescenarios,thefinaldischargebatchsizewasassumedtobetheUnit1batchsizeof80assemblies.Thisassumptionservestoincreasetheconservatismoftheanalysis.4.ProvidethedecayheatgenerationratefortheassembliesdepositedinthepoolforeachdischargecycleusedinyourcalculationsforCases3and4.Ifyoudonotusethedi'schargesandcycleEFPDshowninTable2.1explainthemethodusedand)ustifyitsapplication.A4.Thedecayheatgenerationratesforfuelfromeachpreviousdischargecyclearesummarizedbelow.ItwasconservativelyassumedthattheEFPDforallpreviouslydischargedfuelassemblieswas1260days.CycleUnit1DecayHeat(BTUr)182106184518Unit2DecayHeat(BTUHr)23939128582218934223215519718119899023215530692820441726170229366129788227315930511810287631300294311751325017335871358785 ATTACHMENT1TOAEP:NRC:1202APage3121316171819202122232432441433707734853436119737325738592039978941426143416047214956682077304629818353587853708453847144003924221004679285981761078164Q5.Discussbriefly,youroperationofthespentfuelpooltrainsinanormalreload.A5.Thespentfuelpoolcoolingsystem(SFPCS)isnotdirectlyassociatedwitheitherplantstartup,normaloperation,orshutdown.Itisoperatedwhenthereisaneedtolowerthepoolwatertemperatureorwhenthereisaneedtoclarifyorpurifythepoolwater.Bothsituationsaredependentuponfuelloadingofthepoolandupontheelapsedtimethatthespentfuelhasbeeninthepool.TodateonlyoneSFPCStrainhasbeenneededatanypointintimetokeepthepooltemperaturebelowthehightemperaturealarmsetpointof125F.AnevaluationshallbeperformedpriortoeachfullcoreoffloadtoassurethatoneSFPCStrainissufficienttokeepthepoolbulkwatertemperaturebelowthatwhichisacceptable.

ATTACHMENT2TOAEP:NRC:1202AREVISEDSAFETYANALYSISPERFORMEDBYHOLTECINTERNATIONAL