ML17332A763

Application for Amends to Licenses DPR-58 & DPR-74,revising TS Section 3.7.1.1,Table 3.7-1 & Bases Re Turbine Cycle Safety Valves

ML17332A763
Person / Time
Site:	Cook
Issue date:	05/19/1995
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A764	List: ML17332A763 ML17332A765
References
AEP:NRC:1213, NUDOCS 9505240165
Download: ML17332A763 (11)

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RIDRIWY1CELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9505240165DOC.DATE:95/05/19NOTARIZED:YESDOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichigan'owerCo.(formerlyIndiana&MichiganElePRECIP.NAMERECIPIENT'AFFILIATIONDocumentControlBranch(DocumentControlDesk)R

SUBJECT:

ApplicationforamendstolicensesDPR-58&DPR-74,revisingTSsection3.7.1.1,Table3.7-1&basesreturbinecyclesafetyvalves.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRJENCL/SIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNA~LECELEBOilNRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRC,PDRCOPIESLTTRENCL11'11111111D0uY'OTETOALLRIDS"RECIPIEYTS:PLEASEIIELPUSTOREDUCEiVASTE!COYTACT'I'IIEDOCUifEYTCONTROLDESK,ROOhiPI-37IEXT.504-DOS3)TOELIlhfI%ATEYOURXAXfEFROifDISTRIDU'I'IOYLIS'I'SI'ORDOCUzfEX'I'SYOUDOY"I'lL'D!TOTALNUMBEROFCOPIESREQUIRED:LTTR'2ENCL11 IndianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216FIMay19,1995AEP:NRC'1213DocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2.TECHNICALSPECIFICATIONCHANGEREQUEST,SECTION3.7,1.1,TABLE3.7-1,ANDTHEBASESFORSECTION3.7.1.1(TURBINECYCLE-SAFETYVALVES)Thisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2.Specifically,weareproposingtomodifyT/S3.7.1.1,Table3.7-1,andtheassociatedbasesdescription.ThechangesmodifythepowerrangeneutronfluxhighsetpointinresponsetoanissueraisedinWestinghouseNuclearSafetyAdvisoryLetter(NSAL)94-001,andprovideclarificationoftheexistingactionstatementsinT/SSection3.7.1.1.Attachment1providesadetaileddescriptionoftheproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Attachment4containsacopyoftheWestinghouseNSAL94-001.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.9505240165,.950519PDRADQCK05000315PDR f

U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1213Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.884j~E.E.FitzpatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS~~DAYOF1995NotaryPublicehAttachmentsCC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett

~Jr+>~~rPt1I ATTACHMENT1TOAEP'NRC'1213DESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICALSPECIFICATIONS Attachment1toAEP:NRC:1213Page1DESCRIPTIONOFCHANGESTheproposedamendmenttotechnicalspecification(T/S)3.7.1.1makesthefollowingspecificchangestotheCookNuclearPlantunits1and2T/Ss:Table3.7-1istobemodifiedtoreflectthecorrectedvaluesfortheneutronfluxhighsetpoints(setpoints)tobeusedintheeventthatoneormoremainsteamsafetyvalves(MSSVs)aredeterminedtobeinoperable,asprovidedinWestinghouseNuclearSafetyAdvisoryLetter(NSAL)94-001.AcopyofthisletterisprovidedasAttachment4.2.ThebasesforSection3.7.1.1aretobemodifiedtoreflectthecorrectedmethodologyfordevelopingthesetpoints.3.TheACTIONstatementoftheT/SistoberevisedtoclarifywhatactionsarerequiredinMODES1,2,and3whenmainsteamsafetyvalvesaredeclaredinoperable.Specifically,ACTIONa.willapplyonlytoMODES1and2andwillreferthereadertoACTIONb.whentherequirementsforcontinuedoperationinMODES1and2cannotbemet.ACTIONstatementb.ismodifiedtoallow3or4loopoperationinMODE3.ItalsoclarifiesthattheunitshouldbeinHOTSHUTDOWN(insteadofCOLDSHUTDOWN)whentheotherrequiredactionsarenotaccomplished.REASONSFORCHANGESANDJUSTIFICATIONFORCHANGESCHANGESTOTABLE3.7-1ANDBASESFOR3.7.1.1WewerenotifiedbyWestinghouseinNuclearSafetyAdvisoryLetter(NSAL)94-001thatthepresentmethodologyforcalculatingthesetpointswhenoneormoreMSSVsareinoperableisnotconservative.ThepresentmethodologyincludesanassumptionthatthemaximumallowableinitialpowerleveliscalculatedbasedonalinearfunctionoftheavailableMSSVreliefcapacity.Undercertainconditions,andwithtypicalsafetyanalysisassumptions,alossofload/turbinetriptransientatpart-powerconditionsmayresultinoverpressurizationofthemainsteamsystemwhenoperatinginaccordancewiththesetpointscalculatedbythismethodology.TherevisedmethodologypresentedbyWestinghouseintheNSALwasusedtodetermineconservativesetpoints.ThisguidanceprovidesamethodtocalculatethemaximumpowerlevelthatwillprovidesufficientheatremovalcapabilityduringoperationwiththegivennumberofinoperableMSSVs.Thesenewsetpoints,alongwiththerevisedmethodology,aretoreplacetheexistingtextinTable3.7-1andthebasesforSection3.7.1.1intheCookNuclearPlantT/Ss.

Attachment1toAEP:NRC:1213Page2CHANGESTOACTIONSTATEMENTAspresentlywritten,theACTIONstatementsofT/S3.7.1.1requirethatthepowerrangeneutronfluxhighsetpointbereduced(toaccountfordecreasedheatremovalcapability)whenoneormoreoftheMSSVsisdeclaredinoperableinMODES1,2,and3.TheneutronfluxhighsetpointisnotaproperconstraintforMODE3operation,sincenooperationatpowercantakeplaceduringthisMODE.Therefore,ACTIONa.hasbeenrewrittentoproviderequirementsforoperationonlyinMODES1and2withfourreactorcoolantloops.Ascurrentlywritten,ACTIONb.permitscontinuedoperationwithinoperableMSSV'sprovidedthereactortripbreakersareopened;however,thewordingissuchthatthisprovisionisspecificallyprovidedonlyforthecaseofthreereactorcoolantloopsinoperation.ThepurposeoftheMSSVsistoremoveenergysuchthatanoverpressurizationofthesecondarysidedoesnotoccur.Withthebreakersopen,theprincipalconcernistheremovalofdecayheat.Becauseenergyremovalcapabilityisenhancedwithadditionalreactorcoolantloopsinoperation,theT/Ssaspresentlywrittenareoverlyrestrictive.WeareproposingtomodifyACTIONb.toallowoperationwithinoperableMSSVsinMODE3withaminimumofthreereactorcoolantloopsinoperation.ThischangecorrectsanoversightinthepresentversionoftheT/Ss.BothACTIONa.andACTIONb.presentlyrequiretheapplicableunittobeinCOLDSHUTDOWN(MODE5)iftherequirementsoftheACTIONarenotmet.ThisrequirementinACTIONa.hasbeenchangedtonotethatatransitionfromACTIONa.toACTIONb.isrequiredifotherspecifiedactionsarenottaken.ACTIONb.hasbeenrevisedtorequiretheunittoultimatelybeinHOTSHUTDOWN(MODE4)iftheotheractionsarenottaken.T/S3.7.1appliesonlyinMODES1,2,and3;therefore,thecurrentdirectiontogotoCOLDSHUTDOWN(MODE5)isconsideredtobeinappropriate.10CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificanthazardsconsiderationifthechangedoesnot:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety.

Attachment1toAEP:NRC:1213Page3Criterion1Correctionofthesetpointmethodologydoesnotrepresentacredibleaccidentinitiator.Thenewmethodologyreducestheallowablepowerlevelsetpointsandisconservativecomparedtothepresentlyevaluatedsetpoints.TheconsequencesofanypreviouslyevaluatedaccidentarenotadverselyaffectedbythisactionbecausethedecreaseinthesetpointsresultingfromthenewcalculationalmethodologywillensurethattheMSSVsarecapableofrelievingthepressureattheallowablepowerlevels.Basedontheseconsiderations,itisconcludedthatthechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Correcting.theoverlyrestrictiveactionstatementsofT/S3.7.1doesnotinvolveasignificantincreaseintheprobabilityofanaccident.Theproposedchangesmodifyexistingtexttomoreaccuratelyreflecttheintentionoftherestrictionsimposedbytheactionstatements.Thechangesdonotcreateanysituationthatwouldinitiateacredibleaccidentsequence.Criterion2ThechangeinTable3.7-1reducestheallowablepowerlevelsthatcanbeachievedintheeventthatoneormoremainsteamsafetyvalve(s)isinoperable.Thischangeisaresultofvendorguidancetocorrectanerrorintheexistingmethodologyusedtodeterminethesetpointsforthepowerlevel.Changingthemethodologyusedtodeterminethesetpoints,andloweringthesetpointsthemselves,donotcreateanewconditionthatcouldleadtoacredibleaccident.Therefore,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theactionstatementsremainineffecttoperformtheintendedfunctionofprotectingtheplant'ssecondarysidewhenthemainsteamsafetyvalvesareinoperable.Theyhaveonlybeenmodifiedtocorrecttheoverlyrestrictivelanguagethatspecifieswhen,ineachMODE,specificactionsmustbetaken.Therefore,theproposedchangedoesnotcreateanewordifferenttypeofaccident.Criterion3Themarginofsafetypresentlyprovidedisnotreducedbytheproposedchangeinthesetpoints.ThechangewillcorrectthelimitingpowerlevelsthataretobeimplementedwhenMSSVsareinoperable.Thisactiondoesnotadverselyaffectthemarginthat Attachment1toAEP:NRC:1213Page4waspreviouslyallocatedfortheabilityoftheMSSVstorelievesecondarysidepressure.Basedontheseconsiderations,itisconcludedthatthechangesdonotinvolveasignificantreductioninamarginofsafety.ThemarginofsafetyisalsonotsignificantlyreducedbytheproposedchangetotheactionstatementsoftheT/S.Theproposedrevisionclarifieswhenspecificactionsaretobetakeninresponsetoinoperablemainsteamsafetyvalves.Thechangesdonotdecreasetheeffectivenessoftheactionstobetaken;therefore,theydo'notsignificantlyreduceanymarginofsafety.