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{{#Wiki_filter:ATTACHMENT1PROPOSEDTIKHNICMSPECIFICATI(NDiARK8607150139860708PDRADOCK05000335PPDR DESIGNFEATURESCONTROLELEMENTASSEMBLIES5.3.2Thereactorcoreshallcontain73fulllengthandnopartlengthcontrolelementassemblies.ThecontrolelementassembliesshallbedesignedandmaintainedinaccordancewiththeoriginaldesignprovisionscontainedinSection4.2.3.2of,theFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.4REACTORCOOLANTSYSTEMDESIGNPRESSUREANDTEMPERATURE5.4.1Thereactorcoolantsystemisdesignedandshallbemaintained:a.InaccordancewiththecoderequirementsspecifiedinSection5.2oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements,b..Forapressureof2485psig,andc.Foratemperatureof650'F.exceptforthepressurizerwhichis700'F.VOLUME5.4.2Thetotalwaterandsteamvolumeofthereactorcoolantsystemis11,100+180cubicfeetataexainalTof567F.5.5EMERGENCYCORECOOLINGSYSTEMS5.5.1TheemergencycorecoolingsystemsaredesignedandshallbemaintainedinaccordancewiththeoriginaldesignprovisionscontainedinSection6.3oftheFSARwithallowancefornormaldegradationpur-suanttotheapplicableSurveillanceRequirements.5.6FUELSTORAGECRITICALITYg<<(+ORg++Ti<~5g)~~gIIAgIIAIENTuelstorageracksaredesignedandshallbewithacenter-to-cenfnotcesbetweenfuelassembliesplacedacs.e1storageracksaresa11bemaintainedwithacenter-to-centerST.LUCIE-UNIT15-5AmendmentNo. | |||
OESIGNFEATURESCRITICALITYContinuedn12.53inchesbetweenfuelassembliesplacedinthestoraThesespaclaKfequivalenttoc0.95withepoolfilledwithunboratedwa.Kof<uestheconserva-tiveassumptionsasdescribedintheFSAR.Inaddition,fuelinthestorageaveaU-235loaln5gramsofV-235perentimeteroffuelassembly(<anenricEnentopercentU-235).DRAINAGE5.6.2Thefuelpoolisdesignedandshallbemaintainedtopreventinadvertentdrainingofthepoolbelowelevation56feet.CAPACITY5.6.3Thespentfuelpoolisdesignedandshallbemaintainedwithastoragecapacitylimitedtonomorethan728fuelassemblies.5.7SEISMICCU5SIFICATION15.7.1Thosestructures,systemsandcomponentsidentifiedasseismicClassIinSection3.2.1oftheFSARshallbedesignedandmaintainedtotheoriginaldesignprovisionscontainedinSection3.7oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.8METEOROLOGICALTOWERLOCATION5.8.1TheeeteorologicaltowerlocationshallbeasshownonFigure5.1-1.5.9COMPONENTCYCLEORTRANSIENTLIMITS5.9.1ThecomponentsidentifiedinTable5.9-1aredesignedandshallbemaintainedwithinthecyclicortransientlimitsofTable5.9-1.ST.LUCIE-UNIT15-6AmendmentNo.34 Ae+ee~a~~A5.6FUELSTORAGECRITICALITY5.6.1a.Thespentfuelstorageracksaredesignedandshallbemaintainedwith:l.Akeffequivalenttolessthanorequalto0.95withthestoragepoolfilledwithunboratedwater,whichincludestheconservativeassumptionsasdescribedinSection9.1oftheFSAR.2.Acenter-to-centerdistanceofnotlessthan12.53inchesbetweenfuelassembliesplacedinthestorageracks.3.Aboronconcentrationgreaterthanorequalto1720ppm.Inaddition,fuelinthestoragepoolshallbeaU-235enrichmentoflessthanorequalto4.0weightpercent.b.ThenewfuelstorageracksaredesignedfordrystorageofunirradiatedfuelassemblieshavingaU-235enrichmentlessthanorequalto4.0weightpercent,whilemaintainingakeffoflessthanorequalto0.98underthemostreactivecondition. | |||
tIIIATTACHMENT2SafetyEvaluationfora~ProaedChangetotheSt.UucieUnitlTechnicalU-235.In1977arequesttoamendtheSt.Lucie,Unit1OperatingLicenseforincreasedspentfuelstoragewassubmittedtotheNRC.ByletterdatedMarch28,1978,theCommissionapprovedAmendment22totheFacilityOperatingLicenseDPR-67whichallowedthemodificationtothespentfuelpoolstoragefacility.Themodificationconsistedofrerackingthespentfuelpoolwith(HI-CAPTM)fuelstorageracksdesignedandmanufacturedbyCombustionEngineering.Thesenewracksincreasedthestoragecapacityfran310fuelassanbliesto728fuelassanbliesinthespentfuelpool.ThesafetyevaluationperformedinsupportoftherequesttoamendtheSt.LucieUnit1OperatingLicensetoallowrerackingofthespentfuelpooladdressedthefollowing:1.StructuralandSeismicAnalysis2.NuclearCriticalityAnalysis3.ThermalHydraulicAnalysis4.AccidentAnalyses5.RadiationExposures Thecriticalityanalysiswasperformedfora3.7w/oU-235fuelenrichnent(linearloadingof41.45gms/anU-235).ItwasdeterminedthattheproposedmodificationtotheUnit1spentfuelpoolwouldbeacceptablebecausetheresultsoftheaboveanalysiswerewithinacceptablelimits.Asaresult,theCriticalityTechnicalSpecification(5.6.1)wasupdatedtoreflectthecentertocenterspacingofthemodifiedracks(12.53inchesminimumspacing)andthemaximumallowableenrichmentof41.45gramsofU-235peraxialcentimeteroffuelassembly.ArequestwasforwardedtotheNRCinOctober1979toamendtheUnit1operatinglicenseforincreasingthefuelassemblyenrichmentTechnicalESpecification(5.3.1)from3.1w/oU-235toamaximumenrichmentof3.7w/oU-235.TheanalysissubmittedinsupportofthisIicenseamendmentconsistedofperformingcriticalityanalysesofthehighcapacityspentfuelracks,newfuelracks,fuelinspectionelevator,upenderandfueltransfertube.Theresultsofthatsafetyanalysisshowedthatwithalimitingfeedenrichmentof3.7w/oU-235themultiplicationfactorforthevariousstructuresanalyzeddidnotexceedthelimitingmultiplicationfactorsof0.98foroptimummoderationand0.95forfullyfloodedconditionsforthenewfuelstorageracksand0.95forthespentfuelracksandfuelhandlingstructures.Itwasdecided,basedondiscussionsbetweenNRCandFPIstaff,thatthespecificationofreloadfuelenrichmentalonedoesnotuniquelydeterminenorlimits,thevaluesofreactorcoreparametersimportanttosafety.Therefore,thedecisionwasmadetodeletetheenrichnentlimitoffueltobeusedinthereloadcore(whichusedtobe3.1w/oU-235)from TechnicalSpecification5.3.1.The3.7w/oU-235enrichnentlimitwasaddedtothefuelstorageTech.Spec.(5.6.1).ThisadditiontoTech.Spec.5.6.1didnotchangetheexistinglimitbutratherclarifieditintermsoffuelenrichment(weightpercent).ByletterdatedJanuary23,1980,theCaanissionapprovedAmendment34totheFacilityOperatingIicenseDPR-67whichdeletedthe3.7w/oU-235referencedinTech.Spec.5.3.1andaddedthe3.7weightpercentvaluetotheCriticalityTechnicalSpecification(5.6.1).Withthisapplication,FPLisrequestingapprovaltoincreasethemaximumenrichmentspecificationoftheCriticalityTechnicalSpecification(5.6.1)atSt.LucieUnit1to4.0w/oU-235(axialU-235loadingof43.91g/cm).Themotivationforthisproposedincreaseistoallowincreasedflexibilityinfuelmanagementandtoaccommodatestorageofhigherenrichmentsforpossibleuseinfuturecycles.TheanalysisperformedinsupportofthisproposedchangecanbefoundinAppendix1.Asummaryoftheresultsofthatanalysisarediscussedinthenextsectionoftnisreport.Safe~EvaluationTheanalysisoftheproposedincreaseinfuelenrichmenthasbeenaccanplishedusingcurrentacceptedcodesandstandardsasspecifiedintheSafetyAnalysisReport.Calculationsperformedforthehandlingandstorageof4.0w/oU-235enrichedfuelassembliesindicatethattheapplicablecriticalityacceptancecriteriaaremet.Theevaluationwasperformedfornaturaluraniumaxialblanketfuelwithamaximumcentralfuelregionenrichmentof4.0w/oU-235.Itisimportanttonotethatthenaturaluraniumaxialblanketswereneglectedandhence,theanalysisisboundingforboth4.0w/oU-235enrichedfuelwithandwithoutaxialblankets. | |||
~~Calculationsperformedforthespentfuelracksindicatethatunderworstcredibleconditions,theneutronmultiplicationfactoris0.918keffatthe95%confidencelevel.Thisvalueisconsiderablylowerthanthe0.95safetycriterialimitasspecifiedinReference2oftheSafetyAnalysisReport.Calculationsperformedforthenewfuelstorageareaatvariousdegreesofmoderation(includingfullflooding)indicatethatthelimitingkeffoccursforamoderatorvoidfractionbetween0.90and0.95andisestimatedtobeabout0.925atthe95%confidencelevel.Thisvalueisalsoconsiderably,lowerthanthesafetycriterialimitof0.98specifiedinANS-N18.2.Criticalitycalculationswerealsoperformedforthefuelhandlingstructures.Themostreactivesituation,i.e.theonethatproducedthehighestreactivity,involvedthefuelelevatorwhenitwasassumedthatoneassemblywasintheelevatorandoneadditionalas'semblywaslocatedfour(4)inchesedgetoedgefran,theelevatorassembly.Theresultingkefffranthisscenariois0.924atthe95%confidencelevel.Basedonthis,itisconcludedthatthefuelelevator,upenderandtransfertubewillaeetthesafetycriterialimitofkeff<0.95.TheNoSignificantHazardsEvaluationIofthisproposedTechnicalSpecificationchangecanbefoundinthenextsectionofthisevaluation.References1.R.E.Uhrig(FPf)toV.Stello(NRC)Re:St.fucieUnit1,DocketNo.50-335,ProposedAmendmenttoFacilityOperatingl,icenseDPR-67,L-77-273,dated8/31/77. | |||
4 2.R.E.Uhrig(FPL)toV.Stello(NRC)Re:St.LucieUnit1,DocketNo.50-335,ProposedAmerdmenttoFacilityOperatingLicenseDPR-67,L-79-282dated10/4/79. | |||
IEVAKlM!I@i Withthisapplication,FPLisrequestingapprovaltoincreasethemaxiaaxnU-235enrichmentandlinearloadingspecifiedinTechnicalSpecification(5.6.1)fromthecurrentlylicensed<3.7w/oU-235(axialloadingof<41.45g/cm)to<4.0w/oU-235(axialloading<43.91g/cm)atSt.LucieUnitl.Anevaluationofthisrequesthasbeenperformedtodemonstratethatnosignificanthazardsconsiderationexists,basedonacanparisonwiththecriteriaof10CFR50.92(C).Thefollowingevaluationdemonstrates(byreferencetotheanalysiscontainedintheattachedSafetyAnalysisReport)thattheproposedamendmenttoincreasetheenrichnentspecificationdoesnotexceedanyofthethreesignificanthazardsconsideration.1.Therequestedchangedoesnotincreasetheprobabilityorconsequencesofaccidentspreviouslyanalyzed.Sincetheconfigurationoftheplantandthemodeofoperationremainunchanged,theprobabilityofaccidentspreviouslyanalyzedremainsunchanged.FPLhasidentifiedthefollowingpotentialaccidentscenarioswhoseconsequenceswouldbeaffectedbytheproposedchange.A.Afuelassemblydropinthespentfuelpool.B.Lossofspentfuelpoolcoolingsystemandmakeup.C.Spentfuelcaskdrop. | |||
ForA,thecriticalityacceptancecriterionisnotviolatedasidentifiedinSection3.3oftheSafetyAnalysisReport.TheradiologicalconsequencesofthistypeofaccidentareboundedbythefuelhandlingaccidentanalyzedintheFSARbecausethisapplicationisnotintendedforextendedburnupoperation.Inparticular,theassumptionsusedintheFSARfuelhandlingaccident(i.e.burnup,fractionalrelease,etc)arestillboundingforthehigherenrichedfuelassemblies.Basedonthisdiscussion,itisconcludedthattheproposedamendmentwillnotresultinanincreaseoftheprobabilityorconsequencesfrcmthepreviouslyevaluatedfuelhandlingaccident.TheconsequencesofB,"lossofspentfuelcoolingsystemandmakeup"willnotbeaffectedsincethisapplicationisnotintendedtoqualifythefuelforextendedburnupoperation.TheincreaseinU-235enrichmentlinearloadingwillnotaffectthedecayheatcharacteristicsofthe.fuelassemblyorthepreviousFSARevaluation(Section9.1.3)ofthelossofspentfuelcoolingsystemandmakeup.Basedonthis,itisconcludedthattheproposedincreaseintheU-235enrichmentlinearloadingwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheconsequencesofC,"aspentfuelcaskdrop",willnot.beaffectedbyanincreaseinlinearloadingsincethisapplicationisnotintendedtoqualifythefuelforextendedburnupnoristheconfigurationofthestorageracksbeingaltered.Therefore,theconsequencesofacaskdropaccidentarestillboundedbythepreviouslyevaluatedFSARChapter15caskdropanalysis.In | |||
~~conclusion,theproposedamenchentwillnotresultinanincreaseoftheprobabilityorconsequencesofanaccidentpreviouslyevaluatedforacaskdrop.Basedontheabovefindings,'theproposedamendmenttoincreasethemaximumallowableU-235linearloadingandcorrespondingenrichmentdoesnotresultinanincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.2.The"requestedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluatedbecausetheplantconfigurationandthemannerinwhichitisoperatedremainthesame.Theproposedchangedoesnotconstituteanychangeintheproceduresforplantoperationorhardware.Inaddition,FPjhasevaluatedtheproposedtechnicalspecificationchangesinaccordancewiththeguidanceoftheNRCpositionpaperentitled"OTPositionforReviewandAcceptanceofSpentFuelStorageandHandlingApplications",andappropriateIndustryCodesandStandardsaslistedintheReferencesectionoftheSafetyAnalysisReport.Basedonthisevaluation,FPIfindsthattheproposedtechnicalspecificationchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfrananyaccidentpreviouslyevaluated.3.Theproposedchangedoesnotinvolveasignificantreductioninamarginofsafety.AsdescribedintheattachedSafetyAnalysisReport,thenewfuelstoragerackcalculatedkeffof0.925(95%confidencelevel)isconsiderablylowerthantheestablishedacceptancecriteriaof<0.98keff.The0.918keff(95%confidence IAI level)calculatedforthespentfuelpooland0.924keff(95%confidencelevel)calculatedforthefuelhandlingstructuresisalsoconsiderablylowerthantheestablishedacceptancecriteriaof<0.95keff.Itisimportanttonotethattheabovecalculatedneutronmultiplicationfactorsincludeal1thene'cessarybiasesanduncertainties.Asnotedabove,therequiredacceptancecriteria(<0.98keffunderoptimummoderationconditionsand<0.95underfullyfloodedconditionsforthenewfuelstorageracks,<0.95keffforthespentfuelpoolandfuelhandlingstructures)havebeenadheredtointhecriticalityanalysisperformedinsupportofthisproposedtechnicalspecificationchange.Specificallythe0.02b,keffand0.05k,keffcriticalitymarginofsafetyrequiredforthenewfuelstorageareaunderoptimummoderationandfullyfloordedconditionsrespectively,andthe0.05BkeffcriticalitymarginofsafetyrequiredforthespentfuelstorageareaandfuelhandlingstructureshavebeenmaintainedasspecifiedintheattachedSafetyAnalysisReport.Basedonthepreviousdiscussion,theproposedanendaanttoincreasethefuelstorageU-235linearloadingandcorrespondingenrichmentwillnotinvolveasignificantreductioninthemarginofsafetyfornuclearcriticality.Insumnary,FPThasdeterminedthattheproposedtechnicalspecificationchangedoesnotinvolveasignificanthazardconsiderationasdiscussedin10CFR50.92.BasedontheattachedSafetyAnalysis,itisconcludedthatthehealthandsafetyofthepublicwillnotbeendangeredbytheproposedchange. | |||
APPENDIX1 | |||
}} | }} |
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ATTACHMENT1PROPOSEDTIKHNICMSPECIFICATI(NDiARK8607150139860708PDRADOCK05000335PPDR DESIGNFEATURESCONTROLELEMENTASSEMBLIES5.3.2Thereactorcoreshallcontain73fulllengthandnopartlengthcontrolelementassemblies.ThecontrolelementassembliesshallbedesignedandmaintainedinaccordancewiththeoriginaldesignprovisionscontainedinSection4.2.3.2of,theFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.4REACTORCOOLANTSYSTEMDESIGNPRESSUREANDTEMPERATURE5.4.1Thereactorcoolantsystemisdesignedandshallbemaintained:a.InaccordancewiththecoderequirementsspecifiedinSection5.2oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements,b..Forapressureof2485psig,andc.Foratemperatureof650'F.exceptforthepressurizerwhichis700'F.VOLUME5.4.2Thetotalwaterandsteamvolumeofthereactorcoolantsystemis11,100+180cubicfeetataexainalTof567F.5.5EMERGENCYCORECOOLINGSYSTEMS5.5.1TheemergencycorecoolingsystemsaredesignedandshallbemaintainedinaccordancewiththeoriginaldesignprovisionscontainedinSection6.3oftheFSARwithallowancefornormaldegradationpur-suanttotheapplicableSurveillanceRequirements.5.6FUELSTORAGECRITICALITYg<<(+ORg++Ti<~5g)~~gIIAgIIAIENTuelstorageracksaredesignedandshallbewithacenter-to-cenfnotcesbetweenfuelassembliesplacedacs.e1storageracksaresa11bemaintainedwithacenter-to-centerST.LUCIE-UNIT15-5AmendmentNo.
OESIGNFEATURESCRITICALITYContinuedn12.53inchesbetweenfuelassembliesplacedinthestoraThesespaclaKfequivalenttoc0.95withepoolfilledwithunboratedwa.Kof<uestheconserva-tiveassumptionsasdescribedintheFSAR.Inaddition,fuelinthestorageaveaU-235loaln5gramsofV-235perentimeteroffuelassembly(<anenricEnentopercentU-235).DRAINAGE5.6.2Thefuelpoolisdesignedandshallbemaintainedtopreventinadvertentdrainingofthepoolbelowelevation56feet.CAPACITY5.6.3Thespentfuelpoolisdesignedandshallbemaintainedwithastoragecapacitylimitedtonomorethan728fuelassemblies.5.7SEISMICCU5SIFICATION15.7.1Thosestructures,systemsandcomponentsidentifiedasseismicClassIinSection3.2.1oftheFSARshallbedesignedandmaintainedtotheoriginaldesignprovisionscontainedinSection3.7oftheFSARwithallowancefornormaldegradationpursuanttotheapplicableSurveillanceRequirements.5.8METEOROLOGICALTOWERLOCATION5.8.1TheeeteorologicaltowerlocationshallbeasshownonFigure5.1-1.5.9COMPONENTCYCLEORTRANSIENTLIMITS5.9.1ThecomponentsidentifiedinTable5.9-1aredesignedandshallbemaintainedwithinthecyclicortransientlimitsofTable5.9-1.ST.LUCIE-UNIT15-6AmendmentNo.34 Ae+ee~a~~A5.6FUELSTORAGECRITICALITY5.6.1a.Thespentfuelstorageracksaredesignedandshallbemaintainedwith:l.Akeffequivalenttolessthanorequalto0.95withthestoragepoolfilledwithunboratedwater,whichincludestheconservativeassumptionsasdescribedinSection9.1oftheFSAR.2.Acenter-to-centerdistanceofnotlessthan12.53inchesbetweenfuelassembliesplacedinthestorageracks.3.Aboronconcentrationgreaterthanorequalto1720ppm.Inaddition,fuelinthestoragepoolshallbeaU-235enrichmentoflessthanorequalto4.0weightpercent.b.ThenewfuelstorageracksaredesignedfordrystorageofunirradiatedfuelassemblieshavingaU-235enrichmentlessthanorequalto4.0weightpercent,whilemaintainingakeffoflessthanorequalto0.98underthemostreactivecondition.
tIIIATTACHMENT2SafetyEvaluationfora~ProaedChangetotheSt.UucieUnitlTechnicalU-235.In1977arequesttoamendtheSt.Lucie,Unit1OperatingLicenseforincreasedspentfuelstoragewassubmittedtotheNRC.ByletterdatedMarch28,1978,theCommissionapprovedAmendment22totheFacilityOperatingLicenseDPR-67whichallowedthemodificationtothespentfuelpoolstoragefacility.Themodificationconsistedofrerackingthespentfuelpoolwith(HI-CAPTM)fuelstorageracksdesignedandmanufacturedbyCombustionEngineering.Thesenewracksincreasedthestoragecapacityfran310fuelassanbliesto728fuelassanbliesinthespentfuelpool.ThesafetyevaluationperformedinsupportoftherequesttoamendtheSt.LucieUnit1OperatingLicensetoallowrerackingofthespentfuelpooladdressedthefollowing:1.StructuralandSeismicAnalysis2.NuclearCriticalityAnalysis3.ThermalHydraulicAnalysis4.AccidentAnalyses5.RadiationExposures Thecriticalityanalysiswasperformedfora3.7w/oU-235fuelenrichnent(linearloadingof41.45gms/anU-235).ItwasdeterminedthattheproposedmodificationtotheUnit1spentfuelpoolwouldbeacceptablebecausetheresultsoftheaboveanalysiswerewithinacceptablelimits.Asaresult,theCriticalityTechnicalSpecification(5.6.1)wasupdatedtoreflectthecentertocenterspacingofthemodifiedracks(12.53inchesminimumspacing)andthemaximumallowableenrichmentof41.45gramsofU-235peraxialcentimeteroffuelassembly.ArequestwasforwardedtotheNRCinOctober1979toamendtheUnit1operatinglicenseforincreasingthefuelassemblyenrichmentTechnicalESpecification(5.3.1)from3.1w/oU-235toamaximumenrichmentof3.7w/oU-235.TheanalysissubmittedinsupportofthisIicenseamendmentconsistedofperformingcriticalityanalysesofthehighcapacityspentfuelracks,newfuelracks,fuelinspectionelevator,upenderandfueltransfertube.Theresultsofthatsafetyanalysisshowedthatwithalimitingfeedenrichmentof3.7w/oU-235themultiplicationfactorforthevariousstructuresanalyzeddidnotexceedthelimitingmultiplicationfactorsof0.98foroptimummoderationand0.95forfullyfloodedconditionsforthenewfuelstorageracksand0.95forthespentfuelracksandfuelhandlingstructures.Itwasdecided,basedondiscussionsbetweenNRCandFPIstaff,thatthespecificationofreloadfuelenrichmentalonedoesnotuniquelydeterminenorlimits,thevaluesofreactorcoreparametersimportanttosafety.Therefore,thedecisionwasmadetodeletetheenrichnentlimitoffueltobeusedinthereloadcore(whichusedtobe3.1w/oU-235)from TechnicalSpecification5.3.1.The3.7w/oU-235enrichnentlimitwasaddedtothefuelstorageTech.Spec.(5.6.1).ThisadditiontoTech.Spec.5.6.1didnotchangetheexistinglimitbutratherclarifieditintermsoffuelenrichment(weightpercent).ByletterdatedJanuary23,1980,theCaanissionapprovedAmendment34totheFacilityOperatingIicenseDPR-67whichdeletedthe3.7w/oU-235referencedinTech.Spec.5.3.1andaddedthe3.7weightpercentvaluetotheCriticalityTechnicalSpecification(5.6.1).Withthisapplication,FPLisrequestingapprovaltoincreasethemaximumenrichmentspecificationoftheCriticalityTechnicalSpecification(5.6.1)atSt.LucieUnit1to4.0w/oU-235(axialU-235loadingof43.91g/cm).Themotivationforthisproposedincreaseistoallowincreasedflexibilityinfuelmanagementandtoaccommodatestorageofhigherenrichmentsforpossibleuseinfuturecycles.TheanalysisperformedinsupportofthisproposedchangecanbefoundinAppendix1.Asummaryoftheresultsofthatanalysisarediscussedinthenextsectionoftnisreport.Safe~EvaluationTheanalysisoftheproposedincreaseinfuelenrichmenthasbeenaccanplishedusingcurrentacceptedcodesandstandardsasspecifiedintheSafetyAnalysisReport.Calculationsperformedforthehandlingandstorageof4.0w/oU-235enrichedfuelassembliesindicatethattheapplicablecriticalityacceptancecriteriaaremet.Theevaluationwasperformedfornaturaluraniumaxialblanketfuelwithamaximumcentralfuelregionenrichmentof4.0w/oU-235.Itisimportanttonotethatthenaturaluraniumaxialblanketswereneglectedandhence,theanalysisisboundingforboth4.0w/oU-235enrichedfuelwithandwithoutaxialblankets.
~~Calculationsperformedforthespentfuelracksindicatethatunderworstcredibleconditions,theneutronmultiplicationfactoris0.918keffatthe95%confidencelevel.Thisvalueisconsiderablylowerthanthe0.95safetycriterialimitasspecifiedinReference2oftheSafetyAnalysisReport.Calculationsperformedforthenewfuelstorageareaatvariousdegreesofmoderation(includingfullflooding)indicatethatthelimitingkeffoccursforamoderatorvoidfractionbetween0.90and0.95andisestimatedtobeabout0.925atthe95%confidencelevel.Thisvalueisalsoconsiderably,lowerthanthesafetycriterialimitof0.98specifiedinANS-N18.2.Criticalitycalculationswerealsoperformedforthefuelhandlingstructures.Themostreactivesituation,i.e.theonethatproducedthehighestreactivity,involvedthefuelelevatorwhenitwasassumedthatoneassemblywasintheelevatorandoneadditionalas'semblywaslocatedfour(4)inchesedgetoedgefran,theelevatorassembly.Theresultingkefffranthisscenariois0.924atthe95%confidencelevel.Basedonthis,itisconcludedthatthefuelelevator,upenderandtransfertubewillaeetthesafetycriterialimitofkeff<0.95.TheNoSignificantHazardsEvaluationIofthisproposedTechnicalSpecificationchangecanbefoundinthenextsectionofthisevaluation.References1.R.E.Uhrig(FPf)toV.Stello(NRC)Re:St.fucieUnit1,DocketNo.50-335,ProposedAmendmenttoFacilityOperatingl,icenseDPR-67,L-77-273,dated8/31/77.
4 2.R.E.Uhrig(FPL)toV.Stello(NRC)Re:St.LucieUnit1,DocketNo.50-335,ProposedAmerdmenttoFacilityOperatingLicenseDPR-67,L-79-282dated10/4/79.
IEVAKlM!I@i Withthisapplication,FPLisrequestingapprovaltoincreasethemaxiaaxnU-235enrichmentandlinearloadingspecifiedinTechnicalSpecification(5.6.1)fromthecurrentlylicensed<3.7w/oU-235(axialloadingof<41.45g/cm)to<4.0w/oU-235(axialloading<43.91g/cm)atSt.LucieUnitl.Anevaluationofthisrequesthasbeenperformedtodemonstratethatnosignificanthazardsconsiderationexists,basedonacanparisonwiththecriteriaof10CFR50.92(C).Thefollowingevaluationdemonstrates(byreferencetotheanalysiscontainedintheattachedSafetyAnalysisReport)thattheproposedamendmenttoincreasetheenrichnentspecificationdoesnotexceedanyofthethreesignificanthazardsconsideration.1.Therequestedchangedoesnotincreasetheprobabilityorconsequencesofaccidentspreviouslyanalyzed.Sincetheconfigurationoftheplantandthemodeofoperationremainunchanged,theprobabilityofaccidentspreviouslyanalyzedremainsunchanged.FPLhasidentifiedthefollowingpotentialaccidentscenarioswhoseconsequenceswouldbeaffectedbytheproposedchange.A.Afuelassemblydropinthespentfuelpool.B.Lossofspentfuelpoolcoolingsystemandmakeup.C.Spentfuelcaskdrop.
ForA,thecriticalityacceptancecriterionisnotviolatedasidentifiedinSection3.3oftheSafetyAnalysisReport.TheradiologicalconsequencesofthistypeofaccidentareboundedbythefuelhandlingaccidentanalyzedintheFSARbecausethisapplicationisnotintendedforextendedburnupoperation.Inparticular,theassumptionsusedintheFSARfuelhandlingaccident(i.e.burnup,fractionalrelease,etc)arestillboundingforthehigherenrichedfuelassemblies.Basedonthisdiscussion,itisconcludedthattheproposedamendmentwillnotresultinanincreaseoftheprobabilityorconsequencesfrcmthepreviouslyevaluatedfuelhandlingaccident.TheconsequencesofB,"lossofspentfuelcoolingsystemandmakeup"willnotbeaffectedsincethisapplicationisnotintendedtoqualifythefuelforextendedburnupoperation.TheincreaseinU-235enrichmentlinearloadingwillnotaffectthedecayheatcharacteristicsofthe.fuelassemblyorthepreviousFSARevaluation(Section9.1.3)ofthelossofspentfuelcoolingsystemandmakeup.Basedonthis,itisconcludedthattheproposedincreaseintheU-235enrichmentlinearloadingwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheconsequencesofC,"aspentfuelcaskdrop",willnot.beaffectedbyanincreaseinlinearloadingsincethisapplicationisnotintendedtoqualifythefuelforextendedburnupnoristheconfigurationofthestorageracksbeingaltered.Therefore,theconsequencesofacaskdropaccidentarestillboundedbythepreviouslyevaluatedFSARChapter15caskdropanalysis.In
~~conclusion,theproposedamenchentwillnotresultinanincreaseoftheprobabilityorconsequencesofanaccidentpreviouslyevaluatedforacaskdrop.Basedontheabovefindings,'theproposedamendmenttoincreasethemaximumallowableU-235linearloadingandcorrespondingenrichmentdoesnotresultinanincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.2.The"requestedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluatedbecausetheplantconfigurationandthemannerinwhichitisoperatedremainthesame.Theproposedchangedoesnotconstituteanychangeintheproceduresforplantoperationorhardware.Inaddition,FPjhasevaluatedtheproposedtechnicalspecificationchangesinaccordancewiththeguidanceoftheNRCpositionpaperentitled"OTPositionforReviewandAcceptanceofSpentFuelStorageandHandlingApplications",andappropriateIndustryCodesandStandardsaslistedintheReferencesectionoftheSafetyAnalysisReport.Basedonthisevaluation,FPIfindsthattheproposedtechnicalspecificationchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfrananyaccidentpreviouslyevaluated.3.Theproposedchangedoesnotinvolveasignificantreductioninamarginofsafety.AsdescribedintheattachedSafetyAnalysisReport,thenewfuelstoragerackcalculatedkeffof0.925(95%confidencelevel)isconsiderablylowerthantheestablishedacceptancecriteriaof<0.98keff.The0.918keff(95%confidence IAI level)calculatedforthespentfuelpooland0.924keff(95%confidencelevel)calculatedforthefuelhandlingstructuresisalsoconsiderablylowerthantheestablishedacceptancecriteriaof<0.95keff.Itisimportanttonotethattheabovecalculatedneutronmultiplicationfactorsincludeal1thene'cessarybiasesanduncertainties.Asnotedabove,therequiredacceptancecriteria(<0.98keffunderoptimummoderationconditionsand<0.95underfullyfloodedconditionsforthenewfuelstorageracks,<0.95keffforthespentfuelpoolandfuelhandlingstructures)havebeenadheredtointhecriticalityanalysisperformedinsupportofthisproposedtechnicalspecificationchange.Specificallythe0.02b,keffand0.05k,keffcriticalitymarginofsafetyrequiredforthenewfuelstorageareaunderoptimummoderationandfullyfloordedconditionsrespectively,andthe0.05BkeffcriticalitymarginofsafetyrequiredforthespentfuelstorageareaandfuelhandlingstructureshavebeenmaintainedasspecifiedintheattachedSafetyAnalysisReport.Basedonthepreviousdiscussion,theproposedanendaanttoincreasethefuelstorageU-235linearloadingandcorrespondingenrichmentwillnotinvolveasignificantreductioninthemarginofsafetyfornuclearcriticality.Insumnary,FPThasdeterminedthattheproposedtechnicalspecificationchangedoesnotinvolveasignificanthazardconsiderationasdiscussedin10CFR50.92.BasedontheattachedSafetyAnalysis,itisconcludedthatthehealthandsafetyofthepublicwillnotbeendangeredbytheproposedchange.
APPENDIX1