ML18040B288

Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits

ML18040B288
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Site:	Susquehanna
Issue date:	01/12/1999
From:	PENNSYLVANIA POWER & LIGHT CO.
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ML18040A966	List: ML18040A965 ML18040B288
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NUDOCS 9901210326
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ReportingRequirementsD.O5.6ReportingRequirements5.6.5COLR(continued)XN-NF-81-58(P)(A)Supplements1and2Revision2"RODEX2FuelRodThermal-MechanicalResponseluationModel,"May1986.24.XN-NF-4(P)(A)."RODEX2A(BWR)FRodThermal-MechanicasponseEvaluationMo,"August1986.'V0LllQIOlC+d00aa0-~P00CLIVloChC25.26.27.2.30~17.el'N-NF-82-06(P)(A)aements2~4and5Revision1,"QualifiofExxonNuclearFuel'for.ExtendedBurnup,"ober8.XN-NF-85-92A)."ExxonNuclearaniumDioxide/oliniaIrradiationExamiionandThermalConduvity."November1986.-90-082(P)(A)Revision1andRevision1Supplement1,"ApplicationofANFDesignMethodoforFuelAssembl'yReconstitution,"May1995.ANF-91-048(P)(A)."AdvancedNuclearFuelsCorporationMethodologyforBoilingWaterReactorsEXEMBWREvaluationModel."January1993.-CC-33(P)(A)Supplement2,"HUXY:AGenerMulitupCodewith10CRF50A'eatupOption,"Janl.XN-CC-33(P)sion1.".eneralizedMult'tupCodewith10CFR50Appe'eatupionUsersManual,"November1975:XN-NF-80-19(P)(A).Volumes2.2A.2B;and2C"Exxon'uclearMethodologyforBoilingWaterReactors:EXEMBWRECCSEvaluationModel."September1982.XN-NF-80-19(P)(A).Volumes3Revision2"ExxonNuclearMethodologyforBoilingWaterReactorsThermex:ThermalLimitsMethodologySummaryDescription,"January1987.XN-NF-79-71(P)(A)Revision2,Supplements1,.2.and3."ExxonNuclearPlantTransientMethodologyforBoilingt"r61OmcontinuSUSQUEHANNA-UNIT25.0-24Amendment151990i2i0326990ii2PDRADQCK-05000388P'.PDR 0\PlnftP'tIC a'DistributionSheetDistri58.txt~/~PonePriority:NormalFrom:EsperanzaLomosbogActionRecipients:RidsNrrPMRSchaafRidsNrrLAMObrienRidsNrrDlpmLpdi1Copies:000OKOKOKInternalRecipients:RidsRgn1MailCenterRidsOgcRpRidsNrrWpcMailRidsNrrDssaSrxbRidsManagerRidsAcrsAcnwMai+Center+FILECENTER-01~ACRS000OKOKOKOKOK0OKPaperCopyPaperCopyExternalRecipients:NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003700504:1

Subject:

SSES,ProposedAmendment194,InclusionofMCPRSafetyLimitsinTechnicalSpecificationsSection2.1.1.2Body:ADAMSDISTRIBUTIONNOTIFICATION.ElectronicRecipientscanRIGHTCLICKandOPENthefirstAttachmenttoViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearchingforAccessionNumberML003700504.Page1 Distri58.txtA001-ORSubmittal:GeneralDistributionDocket:05000388Page2 RobertG.ByramSeniorVicePresidentandChiefNuclearOfficerTel.610.774.7502Fax610.774.5019E-mail:rgbyram@papl.cornPP&L,Inc.TwoNorthNinthStreetAllentovm,PA16101-1179Tel.610.774.5151IgIppMAR20,2000U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskMailStationOP1-17Washington,D.C.20555\SUSQUEHANNASTEAMELECTRICSTATIONPROPOSEDAMENDMENTNO.194TOLICENSENPF-22:MCPRSAFETYLIMITSPLA-5169DocketNo.50-388ThepurposeofthisletteristoproposechangestotheSusquehannaSteamElectricStationUnit2TechnicalSpecifications.ThisproposedchangeentailstheinclusionofUnit2Cycle11(U2C11)MCPRSafetyLimitsinSection2.1.1.2.ConsistentwiththepreviousUnit2reloadanalysis,theanalysismethodsdescribedinTechnicalSpecification5.6.5b.,asapprovedbytheNRC,areusedtogeneratetheSafetyLimitsandCoreOperatingLimitsfortheU2C11reload.EnclosureAtothisletteristhe"SafetyAssessment"supportingthischange.Enclosure8istheNoSignificantHazardsConsiderationsevaluationperformedinaccordancewiththecriteriaof10CFR50.92andtheEnvironmentalAssessment.EnclosureCtothislettercontainstheapplicablepageoftheSusquehannaSESUnit2TechnicalSpecifications,markedtoshowtheproposedchange.AttachmentDcontains"cameraready"versionoftherevisedTechnicalSpecificationpage.TheproposedchangehasbeenapprovedbytheSusquehannaSESPlantOperationsReviewCommitteeandreviewedbytheSusquehannaReviewCommittee.Toassistinyourreview,AttachmentEhasbeenprovided.AttachmentEprovidestheU2C11CoreComposition.

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PLA-5169DocumentControlDeskPPLplanstoimplementtheproposedchangesinMay2001tosupportthestartupofU2C11operation.Therefore,werequestNRCcompleteitsreviewofthischangebyJanuary31,2001withthechangeseffectiveuponstartupfollowingtheUnit210'"RefuelingandInspectionOutage.AnyquestionsregardingthisrequestshouldbedirectedtoMr.M.H.Crowthersat(610)774-7766.Verytrulyyours,Attachmentscopy:NRCRegionIMr.R.G.Schaaf,NRCSr.ProjectManagerMr.S.Hansell,NRCSr.ResidentInspectorMr.W.P.Dornsife,PADEP BEFORETHEUNITEDSTATESNUCLEARREGULATORYCOMMISSIONIntheMatterofPPEcL,INC.DocketNo.50-388PROPOSEDAMENDMENTNO.194TOLICENSENPF-22:MCPRSAFETYLIMITSSUSQUEHANNASTEAMELECTRICSTATIONUNITNO.2Licensee,PPEcL,Inc.,herebyfilesarevisiontoproposedAmendmentNo.194toitsFacilityOperatingLicenseNo.NPF-22datedMarch23,1984.ThisamendmentcontainsarevisiontotheSusquehannaSESUnit2TechnicalSpecifications.PP&L,INC.BY:Sworntoandsubscribedbeforemethisgo~dayofge~,2000.NotaryPublicR.ByrmS.Vice-PrsidentandChiefNuclearOfficerNOTARIALSEALJANlCEM.REESE,NotaryPublicCityotAllentown,LehighCounty,PA")JulyCorninimionExpiresJune11,200$

rt~f4~~Jt\rt ENCLOSUREATOPLA-5169SAFETYASSESSMENTMCPRSAFETYLIMITSBACKGROUNDSusquehannaSteamElectricStationUnit2,Cycle11willcontainSPCATRIUMŽ-10fuel.TheATRIUMY"'-10fueldesignisa10x10latticedesignwhichcontains83fulllengthfuelrods,8partlengthfuelrods,andacentralwaterchannel.TheMCPRSafetyLimitsforU2C11supportCoreThermalPowersupto3493MWt,whichisa1.5%increaseoverU2C10(3441MWt).Theanalysiswasperformedatthe3493MWtpowerleveltosupportlicenseamendmentstobeproposedinMay2000foranincreaseintheRatedThermalPowerlevelforSSESUnit2.SiemensPowerCorporationhasdevelopedtheANFB-10criticalpowercorrelationwhichisapplicabletotheATRIUMŽ-10fuelassemblies(TechnicalSpecification5.6.5b.19).ANFB-10isbasedonalargeamountofcriticalpowertestdataontheATRIUMY"'-10deslgil.TheMCPRSafetyLimitanalysisisperformedonacyclespecificbasissincethecoredesignchanges&omcycletocycle.TheU2C11MCPRSafetyLimitwascalculatedbySiemensPowerCorporation(SPC)usingtheNRCapprovedmethodsdescribedinTechnicalSpecification5.6.5b.5.DescritionoftheProosedChaneTheproposedUnit2TechnicalSpecificationchangesconsistof:(1)ReviseSection2.1.1.2toreflecttheU2C11MCPRSafetylimits.TheMCPRSLvaluesare1.12fortwo-loopoperationand1.14forsingle-loopoperation.TheNRC-approvedtopicalreportscontainedinSection5.6.5oftheTechnicalSpecificationscontainthemethodologyusedtoensuresafeoperationofUnit2withATRIUMŽ-10fuel.

ENCLOSUREATOPLA-5169SAI'KTYANALYSISExcessivethermaloverheatingofthefuelrodcladdingcanresultincladdingdamageandthereleaseoffissionproducts.Inordertoprotectthecladdingagainstthermaloverheatingduetoboilingtransition,theThermalPower,HighPressureandHighFlowSafetyLimit(Section2.1.1.2oftheSusquehannaSESUnit2TechnicalSpecification)wereestablished.ThechangestoSection2.1.1.2reflectthechange&omtheU2C10MCPRSafetyLimitstotheU2C11MCPRSafetyLimitsfortwo-loopoperationandsingle-loopoperation.NUREG-0800,StandardReviewPlanSection4.4,specifiesanacceptable,conservativeapproachtodefinethisSafetyLimit.Specifically,aMinimumCriticalPowerRatio(MCPR)valueisspecifiedsuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationorAnticipatedOperationalOccurrences(AOOs).Boilingtransitionispredictedusingacorrelationbasedontestdata(i.e.,aCriticalPowerCorrelation).TheSafetyLimitMCPRcalculationaccountsforvariousuncertaintiessuchasfeedwaterflow,feedwatertemperature,pressure,powerdistributionuncertainties,anduncertaintyintheCriticalPowerCorrelation.TheproposedSafetyLimitMCPRvalues(two-loopandsingle-loop)werecalculatedusingSPC'sNRCapprovedlicensingmethodswiththeANFB-10correlationforATRIUMŽ-10fuel.InputtotheU2C11MCPRSLanalysis,providedbyPPL,coveredplantoperationuptoaratedcorethermalpowerof3493MWt.Therefore,theanalysisboundsU2C11operationuptothisCoreThermalPower,whichisa1.5%increaseinpoweroverU2C10(3441MWt).HTheproposedSafetyLimitMCPRs(two-loopandsingle-loop)assurethatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationoranticipatedoperationaloccurrences.TheMCPRSafetyLimitanalysisisthefirstinaseriesofanalysesthatassurethenewcoreloadingforU2C11isoperatedinasafemanner.PriortothestartupofU2C11,otherlicensinganalysesareperformedtodeterminechangesinthecriticalpowerratioasaresultofanticipatedoperationaloccurrences.TheseresultsarecombinedwiththeMCPRSafetylimitvaluesproposedheretogeneratetheMCPRoperatinglimitsintheU2C11COLR.OtheranalysesandevaluationsareperformedwhichareindependentofMCPR(e.g.,MechanicalDesignanalyses,LOCA,etc.)andalsoresultinlimitswhichgointotheU2C11COLR.AftercompletionoftheCOLR,areloadSafetyEvaluationiswrittenwhichprovidesthesafetybasis(i.e.,nounreviewedsafetyquestion)forthenewU2C11coreloading,theU2C11COLR,theU2C11FSARchanges,andanyotherevaluations/changesasaresultofthenewU2C11coreconfiguration.Therefore,theproposedactiondoesnotinvolveanincreaseintheprobabilityoranincreaseinconsequencesofanaccidentpreviouslyevaluatedintheSAR.

ENCLOSUREATOPLA-5169Asalludedtoabove,theMCPRSafetyLimitanalysisandtheU2C11coreloadingwhichitsupportsdoesnotdirectlyorindirectlyaffectanyplantsystem,equipment,orcomponent(otherthanthecoreitself)andthereforedoesnotaffectthefailuremodesofanyofthese.Thus,theproposedchangesdonotcreatethepossibilityofapreviouslyunevaluatedoperatorerrororanewsinglefailure.Therefore,theproposedchangesdonocreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Asdiscussedabove,sincetheproposedchangesdonotaffectanyplantsystem,equipment,orcomponent(otherthanthecoreitself),theproposedchangewillnotjeopardizeordegradethefunctionoroperationofanyplantsystemorcomponentgovernedbyTechnicalSpecifications.TheproposedMCPRSafetyLimitsdonotinvolveasignificantreductioninthemargin,ofsafetyascurrentlydefinedintheBASESoftheapplicableTechnicalSpecificationsections,becausetheMCPRSafetyLimitscalculatedforU2C11preservetherequiredmarginofsafety.Operatorperformanceandproceduresareunaffectedbytheseproposedchangessincethechangesareessentiallytransparenttotheoperatorsandplantprocedures,anddonotchangethewayinwhichtheplantisoperated.FollowinguseofthemethodologytoanalyzetheUnit2Cycle11coredesignandfutureUnit2reloads,thereloadcyclespecificresultsareincorporatedintotheFSARviaanFSARchangenotice.Therearenootherimpactsonlicensingdocumentsand/orcommitments.CONCLUSIONSNRCapprovaloftheproposedchangedoesnotinvolveanyreductioninthemarginofsafety.

ELOSUREBTOPLA-5169NOSIGNIFICANTHAZARDSCONSIDERATIONSANDENVIRONMENTAI.ASSESSMENTMCPRSAFETYLIMITSPPLhasevaluatedtheproposedTechnicalSpecificationchangeinaccordancewiththecriteriaspecifiedby10CFR50.92andhasdeterminedthattheproposedchangedoesnotinvolveasignificanthazardsconsideration.Thecriteriaandconclusionsofourevaluationarepresentedbelow.1.Theproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangesinMCPRSafetyLimitsdonotaffectanyplantsystemorcomponent(exceptthereactorcore)andthereforedoesnotincreasetheprobabilityofanaccidentpreviouslyevaluated.AUnit2Cycle11MCPRSafetyLimitanalysiswasperformedforPPLbySPC.ThisanalysisusedNRCapprovedmethodsasrequiredbySSESTechnicalSpecifications.ForUnit2Cycle11,thecriticalpowerperformanceoftheATRIUM'r"'-10fuelwasdeterminedusingtheNRCapprovedANFB-10correlation.Also,theanalysisforU2C11supportsaCoreThermalPowerof3493MWtwhichisa1.5%increaseoverU2C10(3441MWt).TheSafetyLimitMCPRcalculationsstatisticallycombineuncertaintiesonfeedwaterflow,feedwatertemperature,coreflow,corepressure,corepowerdistribution,anduncertaintiesintheCriticalPowerCorrelation.TheSPCanalysisusedcyclespecificpowerdistributionsandcalculatedMCPRvaluessuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationoranticipatedoperationaloccurrences.Theresultingtwo-loopandsingle-loopMCPRSafetyLimitsareincludedintheproposedTechnicalSpecificationchange.Thus,thecladdingintegrityanditsabilitytocontainfissionproductsarenotadverselyaffected.Itisthereforeconcludedthattheproposedchangedoesnotincreasetheconsequencesofanaccidentpreviouslyevaluated.

ELOSUREBTOPLA-51692.Theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Asdiscussedabove,theproposedchangestotheUnit2TechnicalSpecifications(MCPRSafetyLimits)donotaffectanyplantsystemorcomponentanddonotaffectplantoperation.TheconsequencesoftransientsandaccidentswillremainwithinthecriteriaapprovedbytheNRC.Therefore,theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccident&omanyaccidentpreviouslyevaluated.3.Theproposedchangedoesnotinvolveasignificantreductioninamarginofsafety.Sincetheproposedchangesdonotaffectanyplantsystemorcomponent,anddonothaveanyimpactonplantoperation,theproposedchangeswillnotaffectthefunctionoroperationofanyplantsystemorcomponent.TheconsequencesoftransientsandaccidentswillremainwithinthecriteriaapprovedbytheNRC.TheproposedMCPRSafetyLimitsdonotinvolveasignificantreductioninthemarginofsafetyascurrentlydefinedinthebasesoftheapplicableTechnicalSpecificationsections.Therefore,theproposedchangedoesnotinvolveasignificantreductioninthemarginofsafety.ENVIRONMENTALCONSKUKNCESAnenvironmentalassessmentisnotrequiredfortheproposedchangebecausetherequestedchangeconformstothecriteriaforactionseligibleforcategoricalexclusionasspecifiedin10CFR51.22(c)(9).Therequestedchangewillhavenoimpactontheenvironment.Theproposedchangedoesnotinvolveasignificanthazardsconsiderationasdiscussedabove.Theproposedchangedoesnotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsite.Inaddition,theproposedchangedoesnotinvolveasignificantincreaseintheindividualorcumulativeoccupationalradiationexposure.

ELOSURECTOPLA-5169ENCLOSURECTOPLA-5169TECHNICALSPECIFICATIONMARK-UPs SLs2.02.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1.Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10millionibm/hr::MCPRsh11be'llfortworecirculationloopoperation'ra.1forsingerecirculationloopoperation.1~+2.1.1.3'eactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiatedfuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe~1325psig.2'SLViolationsWithanySLviolation,thefollowingactionsshallbecompletedwithin2hours:2.2.1RestorecompliancewithallSLs;and'.2.2Insertallinsertablecontrolrods.SUSQUEHANNA-UNIT2TS/2.0-1Amendment154 ENLOSUREDTOPLA-5169ATTACHMENTDTOPIA-5169"CAMERA-READY"TKCHNICAI,SPECIFICATIONPAGES 2.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressure>785psigandcoreflow>10millionibm/hr:MCPRshallbe>1.12fortworecirculationloopoperationor~1.14forsinglerecirculationloopoperation.2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiatedfuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe<1325psig.2.2SLViolationsWithanySLviolation,thefollowingactionsshallbecompletedwithin2hours:2.2.1RestorecompliancewithallSLs:and2.2.2Insertallinsertablecontrolrods.SUSQUEHANNA-UNIT2TS/2.0-1Amendment ELOSUREETOPLA-5169ENCLOSUREKTOPLA-5169UNIT2CYCLE11CORKCOMPOSITIONikmih<YNNSPCATRIUMŽ10SPCATRIUMŽ-10SPCATRIUMŽ10FreshOnce-burnedTwice-burned300280184 0~~