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{{#Wiki_filter: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
{{#Wiki_filter:RIDRIWY1CELERATED RIDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9505240165 DOC.DATE:
95/05/19NOTARIZED:
YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichigan'ower Co.(formerly Indiana&MichiganElePRECIP.NAME RECIPIENT'AFFILIATION DocumentControlBranch(Document ControlDesk)R


==SUBJECT:==
==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,.950519PDRADQCK05000315P''DR f
Application foramendstolicensesDPR-58&DPR-74,revising TSsection3.7.1.1,Table 3.7-1&basesreturbinecyclesafetyvalves.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR JENCL/SIZE:TITLE:ORSubmittal:
U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1213Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.884j~E.E.FitzpatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS~~DAYOF1995NotaryPublicehAttachmentsCC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett  
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNA~LECELEBOilNRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:
~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.  
NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC,PDRCOPIESLTTRENCL11'11111111D0uY'OTETOALLRIDS"RECIPIEYTS:
PLEASEIIELPUSTOREDUCEiVASTE!COYTACT'I'I IEDOCUifEYT CONTROLDESK,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'1213 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnits1and2.TECHNICAL SPECIFICATION CHANGEREQUEST,SECTION3.7,1.1,TABLE3.7-1,ANDTHEBASESFORSECTION3.7.1.1(TURBINECYCLE-SAFETYVALVES)Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing tomodifyT/S3.7.1.1,Table3.7-1,andtheassociated basesdescription.
ThechangesmodifythepowerrangeneutronfluxhighsetpointinresponsetoanissueraisedinWestinghouse NuclearSafetyAdvisoryLetter(NSAL)94-001,andprovideclarification oftheexistingactionstatements inT/SSection3.7.1.1.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Attachment 4containsacopyoftheWestinghouse NSAL94-001.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
9505240165,.950519 PDRADQCK05000315P''DR f
U.S.NuclearRegulatory Commission Page2AEP:NRC:1213 Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.884j~E.E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS~~DAYOF1995NotaryPublicehAttachments CC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett  
~Jr+>~~rPt1I ATTACHMENT 1TOAEP'NRC'1213 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1213 Page1DESCRIPTION OFCHANGESTheproposedamendment totechnical specification (T/S)3.7.1.1makesthefollowing specificchangestotheCookNuclearPlantunits1and2T/Ss:Table3.7-1istobemodifiedtoreflectthecorrected valuesfortheneutronfluxhighsetpoints (setpoints) tobeusedintheeventthatoneormoremainsteamsafetyvalves(MSSVs)aredetermined tobeinoperable, asprovidedinWestinghouse NuclearSafetyAdvisoryLetter(NSAL)94-001.AcopyofthisletterisprovidedasAttachment 4.2.ThebasesforSection3.7.1.1aretobemodifiedtoreflectthecorrected methodology fordeveloping thesetpoints.
3.TheACTIONstatement oftheT/SistoberevisedtoclarifywhatactionsarerequiredinMODES1,2,and3whenmainsteamsafetyvalvesaredeclaredinoperable.
Specifically, ACTIONa.willapplyonlytoMODES1and2andwillreferthereadertoACTIONb.whentherequirements forcontinued operation inMODES1and2cannotbemet.ACTIONstatement b.ismodifiedtoallow3or4loopoperation inMODE3.Italsoclarifies thattheunitshouldbeinHOTSHUTDOWN(insteadofCOLDSHUTDOWN) whentheotherrequiredactionsarenotaccomplished.
REASONSFORCHANGESANDJUSTIFICATION FORCHANGESCHANGESTOTABLE3.7-1ANDBASESFOR3.7.1.1WewerenotifiedbyWestinghouse inNuclearSafetyAdvisoryLetter(NSAL)94-001thatthepresentmethodology forcalculating thesetpoints whenoneormoreMSSVsareinoperable isnotconservative.
Thepresentmethodology includesanassumption thatthemaximumallowable initialpowerleveliscalculated basedonalinearfunctionoftheavailable MSSVreliefcapacity.
Undercertainconditions, andwithtypicalsafetyanalysisassumptions, alossofload/turbine triptransient atpart-power conditions mayresultinoverpressurization ofthemainsteamsystemwhenoperating inaccordance withthesetpoints calculated bythismethodology.
Therevisedmethodology presented byWestinghouse intheNSALwasusedtodetermine conservative setpoints.
Thisguidanceprovidesamethodtocalculate themaximumpowerlevelthatwillprovidesufficient heatremovalcapability duringoperation withthegivennumberofinoperable MSSVs.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.
Attachment 1toAEP:NRC:1213 Page2CHANGESTOACTIONSTATEMENT Aspresently written,theACTIONstatements ofT/S3.7.1.1requirethatthepowerrangeneutronfluxhighsetpointbereduced(toaccountfordecreased heatremovalcapability) whenoneormoreoftheMSSVsisdeclaredinoperable inMODES1,2,and3.Theneutronfluxhighsetpointisnotaproperconstraint forMODE3operation, sincenooperation atpowercantakeplaceduringthisMODE.Therefore, ACTIONa.hasbeenrewritten toproviderequirements foroperation onlyinMODES1and2withfourreactorcoolantloops.Ascurrently written,ACTIONb.permitscontinued operation withinoperable MSSV'sprovidedthereactortripbreakersareopened;however,thewordingissuchthatthisprovision isspecifically providedonlyforthecaseofthreereactorcoolantloopsinoperation.
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.}}
ThepurposeoftheMSSVsistoremoveenergysuchthatanoverpressurization ofthesecondary sidedoesnotoccur.Withthebreakersopen,theprincipal concernistheremovalofdecayheat.Becauseenergyremovalcapability isenhancedwithadditional reactorcoolantloopsinoperation, theT/Ssaspresently writtenareoverlyrestrictive.
Weareproposing tomodifyACTIONb.toallowoperation withinoperable MSSVsinMODE3withaminimumofthreereactorcoolantloopsinoperation.
Thischangecorrectsanoversight inthepresentversionoftheT/Ss.BothACTIONa.andACTIONb.presently requiretheapplicable unittobeinCOLDSHUTDOWN(MODE5)iftherequirements oftheACTIONarenotmet.Thisrequirement inACTIONa.hasbeenchangedtonotethatatransition fromACTIONa.toACTIONb.isrequiredifotherspecified actionsarenottaken.ACTIONb.hasbeenrevisedtorequiretheunittoultimately beinHOTSHUTDOWN(MODE4)iftheotheractionsarenottaken.T/S3.7.1appliesonlyinMODES1,2,and3;therefore, thecurrentdirection togotoCOLDSHUTDOWN(MODE5)isconsidered tobeinappropriate.
10CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.
Attachment 1toAEP:NRC:1213 Page3Criterion 1Correction ofthesetpointmethodology doesnotrepresent acredibleaccidentinitiator.
Thenewmethodology reducestheallowable powerlevelsetpoints andisconservative comparedtothepresently evaluated setpoints.
Theconsequences ofanypreviously evaluated accidentarenotadversely affectedbythisactionbecausethedecreaseinthesetpoints resulting fromthenewcalculational methodology willensurethattheMSSVsarecapableofrelieving thepressureattheallowable powerlevels.Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Correcting.
theoverlyrestrictive actionstatements ofT/S3.7.1doesnotinvolveasignificant increaseintheprobability ofanaccident.
Theproposedchangesmodifyexistingtexttomoreaccurately reflecttheintention oftherestrictions imposedbytheactionstatements.
Thechangesdonotcreateanysituation thatwouldinitiateacredibleaccidentsequence.
Criterion 2ThechangeinTable3.7-1reducestheallowable powerlevelsthatcanbeachievedintheeventthatoneormoremainsteamsafetyvalve(s)isinoperable.
Thischangeisaresultofvendorguidancetocorrectanerrorintheexistingmethodology usedtodetermine thesetpoints forthepowerlevel.Changingthemethodology usedtodetermine thesetpoints, andloweringthesetpoints themselves, donotcreateanewcondition thatcouldleadtoacredibleaccident.
Therefore, itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theactionstatements remainineffecttoperformtheintendedfunctionofprotecting theplant'ssecondary sidewhenthemainsteamsafetyvalvesareinoperable.
Theyhaveonlybeenmodifiedtocorrecttheoverlyrestrictive languagethatspecifies when,ineachMODE,specificactionsmustbetaken.Therefore, theproposedchangedoesnotcreateanewordifferent typeofaccident.
Criterion 3Themarginofsafetypresently providedisnotreducedbytheproposedchangeinthesetpoints.
Thechangewillcorrectthelimitingpowerlevelsthataretobeimplemented whenMSSVsareinoperable.
Thisactiondoesnotadversely affectthemarginthat Attachment 1toAEP:NRC:1213 Page4waspreviously allocated fortheabilityoftheMSSVstorelievesecondary sidepressure.
Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety.Themarginofsafetyisalsonotsignificantly reducedbytheproposedchangetotheactionstatements oftheT/S.Theproposedrevisionclarifies whenspecificactionsaretobetakeninresponsetoinoperable mainsteamsafetyvalves.Thechangesdonotdecreasetheeffectiveness oftheactionstobetaken;therefore, theydo'notsignificantly reduceanymarginofsafety.}}

Revision as of 07:02, 29 June 2018

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  American Electric Power icon.png
Issue date: 05/19/1995
From: FITZPATRICK E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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Text

RIDRIWY1CELERATED RIDSPROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9505240165 DOC.DATE:

95/05/19NOTARIZED:

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

IndianaMichigan'ower Co.(formerly Indiana&MichiganElePRECIP.NAME RECIPIENT'AFFILIATION DocumentControlBranch(Document ControlDesk)R

SUBJECT:

Application foramendstolicensesDPR-58&DPR-74,revising TSsection3.7.1.1,Table 3.7-1&basesreturbinecyclesafetyvalves.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR JENCL/SIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNA~LECELEBOilNRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:

NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC,PDRCOPIESLTTRENCL11'11111111D0uY'OTETOALLRIDS"RECIPIEYTS:

PLEASEIIELPUSTOREDUCEiVASTE!COYTACT'I'I IEDOCUifEYT CONTROLDESK,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'1213 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:

DonaldC.CookNuclearPlantUnits1and2.TECHNICAL SPECIFICATION CHANGEREQUEST,SECTION3.7,1.1,TABLE3.7-1,ANDTHEBASESFORSECTION3.7.1.1(TURBINECYCLE-SAFETYVALVES)Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing tomodifyT/S3.7.1.1,Table3.7-1,andtheassociated basesdescription.

ThechangesmodifythepowerrangeneutronfluxhighsetpointinresponsetoanissueraisedinWestinghouse NuclearSafetyAdvisoryLetter(NSAL)94-001,andprovideclarification oftheexistingactionstatements inT/SSection3.7.1.1.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Attachment 4containsacopyoftheWestinghouse NSAL94-001.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.

9505240165,.950519 PDRADQCK05000315PDR f

U.S.NuclearRegulatory Commission Page2AEP:NRC:1213 Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.884j~E.E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS~~DAYOF1995NotaryPublicehAttachments CC:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector

-BridgmanJ.R.Padgett

~Jr+>~~rPt1I ATTACHMENT 1TOAEP'NRC'1213 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:1213 Page1DESCRIPTION OFCHANGESTheproposedamendment totechnical specification (T/S)3.7.1.1makesthefollowing specificchangestotheCookNuclearPlantunits1and2T/Ss:Table3.7-1istobemodifiedtoreflectthecorrected valuesfortheneutronfluxhighsetpoints (setpoints) tobeusedintheeventthatoneormoremainsteamsafetyvalves(MSSVs)aredetermined tobeinoperable, asprovidedinWestinghouse NuclearSafetyAdvisoryLetter(NSAL)94-001.AcopyofthisletterisprovidedasAttachment 4.2.ThebasesforSection3.7.1.1aretobemodifiedtoreflectthecorrected methodology fordeveloping thesetpoints.

3.TheACTIONstatement oftheT/SistoberevisedtoclarifywhatactionsarerequiredinMODES1,2,and3whenmainsteamsafetyvalvesaredeclaredinoperable.

Specifically, ACTIONa.willapplyonlytoMODES1and2andwillreferthereadertoACTIONb.whentherequirements forcontinued operation inMODES1and2cannotbemet.ACTIONstatement b.ismodifiedtoallow3or4loopoperation inMODE3.Italsoclarifies thattheunitshouldbeinHOTSHUTDOWN(insteadofCOLDSHUTDOWN) whentheotherrequiredactionsarenotaccomplished.

REASONSFORCHANGESANDJUSTIFICATION FORCHANGESCHANGESTOTABLE3.7-1ANDBASESFOR3.7.1.1WewerenotifiedbyWestinghouse inNuclearSafetyAdvisoryLetter(NSAL)94-001thatthepresentmethodology forcalculating thesetpoints whenoneormoreMSSVsareinoperable isnotconservative.

Thepresentmethodology includesanassumption thatthemaximumallowable initialpowerleveliscalculated basedonalinearfunctionoftheavailable MSSVreliefcapacity.

Undercertainconditions, andwithtypicalsafetyanalysisassumptions, alossofload/turbine triptransient atpart-power conditions mayresultinoverpressurization ofthemainsteamsystemwhenoperating inaccordance withthesetpoints calculated bythismethodology.

Therevisedmethodology presented byWestinghouse intheNSALwasusedtodetermine conservative setpoints.

Thisguidanceprovidesamethodtocalculate themaximumpowerlevelthatwillprovidesufficient heatremovalcapability duringoperation withthegivennumberofinoperable MSSVs.Thesenewsetpoints, alongwiththerevisedmethodology, aretoreplacetheexistingtextinTable3.7-1andthebasesforSection3.7.1.1intheCookNuclearPlantT/Ss.

Attachment 1toAEP:NRC:1213 Page2CHANGESTOACTIONSTATEMENT Aspresently written,theACTIONstatements ofT/S3.7.1.1requirethatthepowerrangeneutronfluxhighsetpointbereduced(toaccountfordecreased heatremovalcapability) whenoneormoreoftheMSSVsisdeclaredinoperable inMODES1,2,and3.Theneutronfluxhighsetpointisnotaproperconstraint forMODE3operation, sincenooperation atpowercantakeplaceduringthisMODE.Therefore, ACTIONa.hasbeenrewritten toproviderequirements foroperation onlyinMODES1and2withfourreactorcoolantloops.Ascurrently written,ACTIONb.permitscontinued operation withinoperable MSSV'sprovidedthereactortripbreakersareopened;however,thewordingissuchthatthisprovision isspecifically providedonlyforthecaseofthreereactorcoolantloopsinoperation.

ThepurposeoftheMSSVsistoremoveenergysuchthatanoverpressurization ofthesecondary sidedoesnotoccur.Withthebreakersopen,theprincipal concernistheremovalofdecayheat.Becauseenergyremovalcapability isenhancedwithadditional reactorcoolantloopsinoperation, theT/Ssaspresently writtenareoverlyrestrictive.

Weareproposing tomodifyACTIONb.toallowoperation withinoperable MSSVsinMODE3withaminimumofthreereactorcoolantloopsinoperation.

Thischangecorrectsanoversight inthepresentversionoftheT/Ss.BothACTIONa.andACTIONb.presently requiretheapplicable unittobeinCOLDSHUTDOWN(MODE5)iftherequirements oftheACTIONarenotmet.Thisrequirement inACTIONa.hasbeenchangedtonotethatatransition fromACTIONa.toACTIONb.isrequiredifotherspecified actionsarenottaken.ACTIONb.hasbeenrevisedtorequiretheunittoultimately beinHOTSHUTDOWN(MODE4)iftheotheractionsarenottaken.T/S3.7.1appliesonlyinMODES1,2,and3;therefore, thecurrentdirection togotoCOLDSHUTDOWN(MODE5)isconsidered tobeinappropriate.

10CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.

Attachment 1toAEP:NRC:1213 Page3Criterion 1Correction ofthesetpointmethodology doesnotrepresent acredibleaccidentinitiator.

Thenewmethodology reducestheallowable powerlevelsetpoints andisconservative comparedtothepresently evaluated setpoints.

Theconsequences ofanypreviously evaluated accidentarenotadversely affectedbythisactionbecausethedecreaseinthesetpoints resulting fromthenewcalculational methodology willensurethattheMSSVsarecapableofrelieving thepressureattheallowable powerlevels.Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Correcting.

theoverlyrestrictive actionstatements ofT/S3.7.1doesnotinvolveasignificant increaseintheprobability ofanaccident.

Theproposedchangesmodifyexistingtexttomoreaccurately reflecttheintention oftherestrictions imposedbytheactionstatements.

Thechangesdonotcreateanysituation thatwouldinitiateacredibleaccidentsequence.

Criterion 2ThechangeinTable3.7-1reducestheallowable powerlevelsthatcanbeachievedintheeventthatoneormoremainsteamsafetyvalve(s)isinoperable.

Thischangeisaresultofvendorguidancetocorrectanerrorintheexistingmethodology usedtodetermine thesetpoints forthepowerlevel.Changingthemethodology usedtodetermine thesetpoints, andloweringthesetpoints themselves, donotcreateanewcondition thatcouldleadtoacredibleaccident.

Therefore, itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theactionstatements remainineffecttoperformtheintendedfunctionofprotecting theplant'ssecondary sidewhenthemainsteamsafetyvalvesareinoperable.

Theyhaveonlybeenmodifiedtocorrecttheoverlyrestrictive languagethatspecifies when,ineachMODE,specificactionsmustbetaken.Therefore, theproposedchangedoesnotcreateanewordifferent typeofaccident.

Criterion 3Themarginofsafetypresently providedisnotreducedbytheproposedchangeinthesetpoints.

Thechangewillcorrectthelimitingpowerlevelsthataretobeimplemented whenMSSVsareinoperable.

Thisactiondoesnotadversely affectthemarginthat Attachment 1toAEP:NRC:1213 Page4waspreviously allocated fortheabilityoftheMSSVstorelievesecondary sidepressure.

Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety.Themarginofsafetyisalsonotsignificantly reducedbytheproposedchangetotheactionstatements oftheT/S.Theproposedrevisionclarifies whenspecificactionsaretobetakeninresponsetoinoperable mainsteamsafetyvalves.Thechangesdonotdecreasetheeffectiveness oftheactionstobetaken;therefore, theydo'notsignificantly reduceanymarginofsafety.

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