ML17228B248
| ML17228B248 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/16/1995 |
| From: | SAGER D A FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, L-95-232, NUDOCS 9508230314 | |
| Download: ML17228B248 (26) | |
Text
PRXORXTY1CELERATEDRIDSPROCESSING))~~REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9508230314DOC.DATE:95/08/16NOTARIZED:YESFACIL:50-335St.LuciePlant,Unit1,FloridaPower6LightCo.50-389St.LuciePlant,Unit2,FloridaPower6LightCo.AUTH.NAMEAUTHORAFFILIATIONSAGER,D.A.FloridaPowerSLightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKETg05000335P05000389
SUBJECT:
ForwardsresponsestoGL92-01,Rev1,Suppl1,"RVStructuralIntegrity."UtilconsiderssubmittalcompleteresponsetorequestsinGLsupplement.DISTRIBUTIONCODE:A028DCOPIESRECEIVED:LTRIENCLISIZE:/7TITLE:GenericLetter92-01,Rev1,Suppl1Responses(ReactorVesselStructNOTES:RECIPIENTIDCODE/NAMEPD2-1PDINTERNAL:ACRSNRR/DE/EMCBNUDOCS-ABSTRACTRES/DE/MEBEXTERNAL:NOACCOPIESLTTRENCL116622111111RECIPIENTIDCODE/NAMENORRIS,JNZER~O;5NRR/'DEGASADI-1OGC/HDS3NRCPDRCOPIESLTTRENCL11111110NNOTETOALL"RZDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR17ENCL16 CIt FloridaPower&LightCompany,P.O.Box128,FortPierce,FL34954-0128August16,1995L-95-23210CFR50.410CFR50.54(f)IU.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555RE:St.LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructuralIntegrityGenericLetter92-01Revision1SulementResonseTheFloridaPowerandLightCompany(FPL)responsestoGenericLetter(GL)92-01,Revision1,Supplement1,ReactorVesselStructuralIntegrity,'forSt.LucieUnits1and2areattached.TheNuclearRegulatoryCommission(NRC)issuedNRCGL92-01R1S1onMay19,1995,torequirelicenseestoidentify,collect,andreportanynewdatapertinenttoanalysisofstructuralintegrityoftheirreactorpressurevessel(RPV).ItalsorequiresanassessmentoftheimpactofthisnewdataonRPVintegrityanalysesrelativetotherequirementsof10CFR50.60,10CFR50.61,AppendicesGandHto10CFR50,andanypotentialimpactonlowtemperatureoverpressure(LTOP)limitsorpressure-temperature(P/T)limits.TheGenericLettersupplementrequestedlicenseestoprovidearesponsetoitem1within90daysanditems2through4withinsixmonths.(1)ProvideadescriptionofthoseactionstakenorplannedtolocatealldatarelevanttothedeterminationofRPVIntegrity,oranexplanationofwhytheexistingdatabaseisconsideredcompleteaspreviouslysubmitted.(2)Provideanassessmentofanychangeinbest-estimatechemistrybasedonconsiderationofallrelevantdata.(3)ProvideadeterminationoftheneedforuseoftheratioprocedureinaccordancewiththeestablishedPosition2.1ofRegulatoryGuide1.99,Revision2,forthoselicenseesthat.usesurveillancedatatoprovideabasisfortheRPVintegrityevaluation.95082303i.4t.9508l6PDRADOCK05000335PPDRanFPLGroupcompanY St.'LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructuralIntegrityGenericLetter92-01Revision1SulementResonseL-95-232(4)Provideawrittenreportonanynewlyacquireddataasspecifiedabove.Inaddition,includetheresultsofanynecessaryrevisionstotheevaluationofRPVintegrityinaccordancewiththerequirementsof10CFR50.60,10CFR50.61,AppendicesGandHto10CFRPart50,andanypotentialimpactontheLTOPorP/TlimitsintheTechnicalSpecificationsoracertificationthatpreviouslysubmittedevaluationsremainvalid.RevisedevaluationsandcertificationsshouldincludeconsiderationofPosition2.1ofRegulatoryGuide1.99,Revision2,asapplicable,andanynewdata.ThisletterandthetwoattachmentsprovidetheFPLresponsetoNRCrequestsitems1,2,3,and4forSt.LucieUnits1and2.FPLhaspreviouslyundertakenseveralinitiativestoensurethatall"relevant"andlimitingdataforthedeterminationofreactorvesselintegrityforSt.LucieUnits1and2iscompleteaspreviouslysubmitted.FPLconsiderstheattachmentsofthissubmittalourcompleteresponsetotherequestsintheGenericLetterSupplement.FPLisparticipatinginindustryeffortstoaddressthechemicalvariabilityofitsnon-limitingweldstoeliminateanydiscrepancyintheNRCandindustrydatabases.ThiseffortisexpectedtobecompleteandisscheduledtobesubmittedtotheNRCbySeptember1(1997.TheattachedinformationisprovidedpursuanttotherequirementsofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f).Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,QiD.A.erVicesidentSt.Lc'ePlantDAS/GRMAttachmentscc:StewartD.Ebneter,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant l'w St."LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructuralIntegrityGenericLetter92-01Revision1SulementResonseL-95-232STATEOFFLORIDA))COUNTYOFST.LUCIESS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlantfortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;'hathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.D.A.ger'STATEOFFLORIDACOUNTYOF~TLLIUCTheforegoininstrumentwasacknowledgedbefore'ethist(OdayofbyD.A.Sager,whoispernallyknowntomeandwhodidtakeanoath.~&re+~s,+NameofNotaryPublicMyCommissionexpiresCommissionNo.KARENVkSt'.Q:a=.MYCOMNSSIONfCC8M926EXP1RESAPI918,1998BONOFOTHRUTROYFAIHRIIRANCE,INC.
LNJI)]O'I)~W,[~eliUIIbII St.LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructuralIntegrityGenericLetter92-01RevisioSulementResonseL-95-232Attachment1ResponsetoNRCGL92-01Revision1Supplement1ForSt.Luci.eUnit1 RIEI Attachment1Page1of7ResponsetoNRCGL92-01Supplement1St.LucieUnit1BackgroundTheStLucieUnit1reactorpressurevessel(RPV)wasdesignedandmanufacturedbyCombustionEngineeringInc.(CE).Theweldwiresusedtofabricatethebeltlineweldswerecopper(Cu)coatedandoneheatofwirehadaB-4modifiednickel(Ni)alloyadditioninthewroughtwire.TheremainingbeltlineweldwireswereoflowNicontent.NoRPVbeltlineweldsutilizedsupplementalcoldNiwireadditionsduringfabrication.WithlowNiweldsfabricatedwithoutcoldwireNiadditions,theNivariabilityisverylowandcomparabletothatofplatematerial.LimitingRPVMaterialsforEOLRT~,P/TlimitcurvesandLTOP.AsaresultoftheCucoatedweldwireandmodifiedNicontentofoneoftheweldheats,theStLucieUnit1RPVisweldlimitedfor10CFR50.61RT~,atendoflife(EOL)andforthecurrentpressuretemperature(P/T)limitcurvesandlowtemperatureoverpressureprotection(LTOP)analysis.TheSt.LucieUnit1limitingbeltlineweldheatis305424withLinde1092fluxandhadpreviouslybeenidentifiedbyFPLasthesameheatandfluxlotusedtofabricateaBeaverValleyUnit1RPVbeltlineweldaswellasitsRPVsurveillancetestprogram.Twosourcesofdatawereknowntobeavailabletodeterminethebestestimateweldchemistryofthisweld;theoriginalCEweldqualification'ndtheBeaverValleyUnit1surveillanceprogram~.FPLsubmittedthisbestestimateweldchemistryinitsinitialresponsetoGL92-01.FortheSt.LucieUnit1RPV:thehighestRT~atendoflicense(EOL)is227'FaslistedintheNRCRVID4and"AtypicalWeldMaterialInReactorPressureVesselWelds"CEResponsetoI&EBulletin78-12,June8,1979,SectionVIII,Page23,LabgD8160."AnalysisofCapsuleWfromDuquesneLightCo.BeaverValleyUnit1ReactorVesselRadiationSurveillanceProgram",WestinghouseElectricCorp.,Nov.1988,WCAP-12005.FPLLetter,L-92-189,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",W.H.BohlketoNRC,July1,1992."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment1Page2of7correspondstothelimitingweldheat305424.DuetothelowNicontentoftheremainingweldheats,theRVIDEOLRT~oftheseweldsaremorethan100'Fbelowthatofthelimitingweldandbelowallofthesixbeltlineplates.AllsixbeltlineplateshaveRVIDEOLRT~valuesofbelow200'F.ActivitiestoIdentifRelevantDataandSourcesWestinghouseOwnersGroupRPVDATADatabase:TheWestinghouseOwnersGroup(WOG)MaterialsandChemistrySubcommitteehascompiledadatabase,RPVDATA,ofallinformationrelevanttoreactorvesselintegritythatisavailablefromWestinghouseElectricCorporationdocketedGL92-01responsesandpreviousEPRIdatabasesonreactorvesselintegrity.Theinformationincludedinthedatabaseisfromoriginalfabricationrecords,reactorvesselsurveillanceprogramtesting,andothersupplementaltestingperformedbyWestinghouse.FPLreviewedthisdatabaseandidentifiedother"sister"plantsthatcontainidenticalreactorvesselweldheats,andthatwouldberelevanttothedeterminationofreactorvesselintegrityforSt.LucieUnit1.Twootherplantswereidentifiedashavingtheidenticalweldheat(305424)astheSt.LucieUnit.1limitingweld.However,allofthisdatahadpreviouslybeenincorporatedintothecurrentbestestimatechemistrydetermination.AdditionalsisterplantswerenotedfortheotherlowNiweldheatsbutnonew"relevant"datawouldmaketheseweldsmorelimitingthanweldheat305424forSt.LucieUnitl.NRCReactorVesselIntegrityDatabase(RVID):FPLreceivedtheinitialpublicissueoftheNRCReactorVesselIntegrityDatabase~(RVID).FPLhasreviewedthisdatabasetoidentifyadditional"sister"plantsthatcontainidenticalreactorvesselweldheatsandthatwouldberelevanttothedeterminationofreactorvesselintegrityforSt.LucieUnit1.Onenewplantwasidentifiedbuttheweldwasoutofitsbeltlinesothelicenseeusedanon-measured,upperboundNivalueof1.004,whichwasnotconsideredrelevantforthislowNiweldwire.NoothernewplantswereidentifiedthathadnotbeenpreviouslyidentifiedbytheWOGRPVDATAdatabase.CEOG-ReactorVesselWorkingGroup:TheCombustionEngineeringOwnersGroup(CEOG)hasformedtheReactorVesselWorkingGroup(RVWG)toaddresstheissueofweldchemistryvariabilityforCEfabricatedreactorvesselwelds.This"ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment1Page3of7taskwillfocusoncompilingdatafromoriginalfabricationrecords,researchdatafiles,andlogbookscompiledbyCE.Inaddition,thetaskwillcompiledatafromsurveillancetestandsupplementaltestresultsbyCE,otherNSSSsuppliers,andutilities.TherelevantdatawillbeusedtodetermineabestestimatechemistryforeachweldheatfabricatedbyCE.FPLisparticipatinginthiseffortwhichisexpectedtotakeaminimumof18monthstocomplete~plusanadditional6monthstoassessthesignificanceofthenewdata.Thelengthofthisscheduledoesnotimpactsafetybecausethelimitingweldheat(305424)forSt.LucieUnit1hasalreadybeendeterminedusingthebestestimatechemistryofallthecurrentlyavailableandrelevantdata.TheremainingweldsarelowNiweldsandwouldnotbecomemorelimitingthanheat305424,therefore,wouldnotbedirectly"pertinent"toevaluationofreactorvesselintegrityforSt.LucieUnit1.ResponsestoNRCGL92-01Supplement17Questions:NRCReuest1:ProvideadescriptionofthoseactionstakenorplannedtolocatealldatarelevanttothedeterminationofRPVintegrity,oranexplanationofwhytheexistingdatabaseisconsideredcompleteaspreviouslysubmitted.FPLResonse1:TheSt.LucieUnit1RVPisweldlimitedforthedeterminationofreactorvesselintegrity.ThelimitingmaterialfordeterminingRPVIntegrityisthebeltlineweldheat305424withanEOLRT~3of227'F.Thebestestimatechemistryforthisweldheatwasdeterminedfromallavailabledata,includingtheoriginal,CEweldqualificationandasisterCEOwnersGroupLetterCEOG-95-390,"CEOGReactorVesselWorkingGroupActivities...",DavidSagertoU.S.NuclearRegulatoryCommission,July27,1995.GenericLetter(GL)92-01,Revision1,Supplement1"ReactorVesselStructuralIntegrity",NRCtoallholdersoflicensednuclearpowerreactors;May19,1995."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment1Page4of7plantsurveillanceweld,andisconsideredcompleteaspreviouslysubmitted.Thegirthweldisheat90136andisthesurveillanceweldforSt.LucieUnit1.ThisweldhasanEOLRTFof80'F'uetothelowNicontent.AthroughsectionchemicalanalysiswasperformedonthissurveillancetestblockbytheCEOG.ThisanalysismatchedtheCucontentpreviouslyreportedandconfirmedthelowNicontentoftheweld,however,notall"relevant"datahasbeenusedtodeterminethebestestimatechemistryforthisheat.Onceallthedataisusedtodeterminethebestestimatechemistryforheat90136,asdescribedabove'ntheCEOGRVWG,itwillnotbecomemorelimitingthanthecurrentlimitingweldheatforSt.LucieUnit1.InitialuppershelfenergiesandRT>>Tvalueshavebeendeterminedfromthesurveillanceweldsforbothheats305424and90136.ThisinformationhasbeenprovidedintheearlierresponsestoGL92-01"~".Theremainingbeltlineheats34B009andA8746wereusedintheintermediateshellaxialweldsandhaveanEOLRT~of120'F".TheseheatshavepreviouslybeenstudiedbytheCEOGtodeterminethebestestimatechemistryandwereupdatedintheresponsetoGL92-01RAI".Nonewinformationisexpectedthatcouldmaketheseweldsmorelimitingthanheat305424.10FPLLetter,L-92-189,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",W.H.BohlketoNRC,July1,1992."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.121314FPLLetter,L-92-189,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",W.H.BohlketoNRC,July1,1992.FPLLetter,L-93-286,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",D.A.SagertoNRC,November15,1993."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.FPLLetter,L-93-286,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",D.A.SagertoNRC,November15,1993.
JII Attachment1Page5of7FPLisparticipatingintheCEOGRVWGefforttoaddresstheissueofweldchemistryvariabilityforCEfabricatedreactorvesselwelds.ThistaskasdescribedabovewillcompileallrelevantdatatodetermineabestestimatechemistryforeachweldheatfabricatedbyCE.Thescheduledcompletionofthiseffortisaminimumof18monthsplusanadditional6months(September1,1997)toassessthesignificanceofthenewdata.Thelengthofthisscheduledoesnotimpactsafetybecausethelimitingweldheat(305424)forSt.LucieUnit1hasalreadybeendeterminedusingthebestestimatechemistryofallthecurrentlyavailablerelevantdata.TheremainingweldsarelowNiweldsandwouldnotbecomemorelimitingthanheat305424.Therefore,theremainingweldswouldnotbedirectly"pertinent"toevaluationofreactorvesselintegrityforSt.LucieUnit1.NRCReuest2:Provideanassessmentofanychangeinbest-estimatechemistrybasedonconsiderationofallrelevantdata.FPLResonse2:ThelimitingmaterialfordeterminingRPVintegrityforSt.LucieUnit1isthebeltlineweld305424.AreviewoftheNRCRVZDandWOGRPVDATAdatabasesshownoadditionaldatathathasnotalreadybeenusedindeterminingthebestestimatechemistrybeingusedforSt.LucieUnit1.SincenochangeisexpectedtothebestestimatechemistryfortheSt.LucieUnit1limitingreactorvesselweldmaterial,therewillbenoimpactrelativetoreactorvesselstructuralintegrity.ShouldanynewbestestimatechemistryisidentifiedfortheSt.LucieUnit1beltlinematerials,itwillbereportedbySeptember1,1997,afterthecompletionoftheCEOGRVWGtaskdescribedabove.NRCReuest3:ProvideadeterminationoftheneedforuseoftheratioprocedureinaccordancewiththeestablishedPosition2.1ofRegulatoryGuide1.99,Revision2,forthoselicenseesthatusesurveillancedatatoprovideabasisfortheRPVintegrityevaluation.FPLResonse3:ThedeterminationofvesselintegrityfortheSt.LucieUnit1reactorvesselmaterialshasbeenmadeusingthebest Attachment1Page6of7estimatechemistrywithouttheuseofsurveillancedata,thereforetheratioprocedureisnotused.NRCReuest4:Submitawrittenreportprovidinganynewlyacquireddataasspecifiedaboveand(1)theresultsofanynecessaryrevisionstotheevaluationofRPV"integrityinaccordancewiththerequirementsof10CFR50.60,10CFR50.61,AppendicesGandHto10CFRPart50,andanypotentialimpactontheLTOPorP/TlimitsintheTechnicalSpecificationsor(2)acertificationthatpreviouslysubmittedevaluationsremainvalid.RevisedevaluationsandcertificationsshouldincludeconsiderationofPosition2.1ofRegulatoryGuide1.99,Revision2,asapplicable,andanynewdata.FPLResonse4:ThepreviouslysubmittedLTOPanalysisandP/TlimitscurvesintheTechnicalSpecificationswerebasedontheSt.LucieUnit1limitingweld305424whichhadthehighest1/4Tand3/4TadjustedRT>>Yfortheperiodofapplicability.Sincenonewinformationiscurrentlyavailableforthelimitingweldmaterialsthisanalysisremainsvalid.Theuppershelfenergy(USE)valuesfortheweldmaterialsreportedfortheSt.LucieUnit1reactorvesselareallinaccordancewiththe10CFR50AppendixGlimitof50ft-lbsatEOLaspreviouslysubmittedintheresponsestotheGL92-01'andarebasedonactualsurveillancedataorconservativegenericestimates.Conclusion:ThecompleteresponsetotheNRCGenericLetter92-01supplement1questions1through4areprovidedabove.ThisGLisconsideredcompleteforSt.LucieUnit1sincethelimitingmaterial(weldheat305424)bestestimatechemistrywasdeterminedfromallknownindustryavailabledataforthatheat.However,FPLisparticipatingintheCEOGRVWGtasktodeterminebestestimateFPLLetter,L-92-189,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",W.H.BohlketoNRC,July1,1992.16FPLLetter,L-93-286,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",D.A.SagertoNRC,November15,1993.
w~I Attachment1Page7of7chemistryvaluesforallCEweldmaterials.Anychangesinbestestimatechemistryforthenon-limitingreactorvesselbeltlineweldswillbereportedbySeptember1,1997.Theschedulefordeterminingchangestothebestestimateweldchemistryforthenon-limitingwelds(weldheats90136and34B009/A8746)shouldhavenoeffectondeterminationofreactorvesselintegrityduetothelowNicontentandsincetheyaregreaterthan100'FbelowtheEOLRT~'fthelimitingweldheat305424."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment2Page3of5ResponsestoNRCGL92-01Supplement1Questions:NRCReuest1:ProvideadescriptionofthoseactionstakenorplannedtolocatealldatarelevanttothedeterminationofRPVIntegrity,oranexplanationofwhytheexistingdatabaseisconsideredcompleteaspreviouslysubmitted.FPLResonse1:TheSt.LucieUnit2ReactorVesselisalowCulowNiweldfabricatedvessel.ThelimitingmaterialfordeterminingRPVIntegrityisthebeltlineplatematerial.AreviewoftheNRCRVIDandWOGRPVDATAdatabasesshownoidenticalmatchofheatsforthelimitingplatematerials,therefore,nonewdataisexpected.TheoriginaldatasubmittedintheresponsestoGL92-0167forthislimitingplatematerialwasbasedonactual,CMTRdataandcompletematerialpropertytests.Therefore,thedataisconsideredcompleteaspreviouslysubmitted.ThemostlimitingweldmaterialhasanEOLRT~of47'Fwhichisgreaterthan200'Fbelowthe10CFR50.61screeningcriteriaandgreaterthan100Fbelowthelimitingplate8.Theweldmaterialisthereforenotpertinentindeterminationsofreactorvesselintegrity.Additionally,thethreesisterplantsidentifiedashavingidenticalweldheatsasSt.LucieUnit2arenotlimitedbytheseweldheatsbutareallplatelimitedandhaveEOLRT~Bvaluesover100'Fbelowthe10CFR50.61screeningcriteria.GenericLetter(GL)92-01,Revision1,Supplement1"ReactorVesselStructuralIntegrity",NRCtoallholdersoflicensednuclearpowerreactors;May19,1995..FPLLetter,L-92-189,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",W.H.BohlketoNRC,July1,1992.FPLLetter,L-93-286,"St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditionalInformation(RAI)",D.A.SagertoNRC,November15,1993."ReactorVessel,IntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
St.'LucieUnits1and2L-95-232DocketNos.50-335and50-389ReactorVesselStructuralIntegrityGenericLetter92-01Revision1SulementResonseAttachment2ResponsetoNRCGL92-01Revision1Supplement1ForSt.LucieUnit2 At' Attachment2Page1of5ResponsetoNRCGL92-01Supplement1St.LucieUnit2BackgroundTheStLucieUnit2reactorpressurevessel(RPV)wasdesignedandmanufacturedbyCombustionEngineeringInc.(CE).TheRPVwasfabricatedaftertheeffectsofcopper(Cu)onirradiationembrittlementwereknown.TheweldwiresusedtofabricatethebeltlineweldswerelowinCucontentandwerenotCucoated.TheweldwireswerealsolowinNickel(Ni)contentandtheweldsdidnotutilizesupplementalcoldNiwireadditionsduringfabrication.WithlowCuandlowNiweldsfabricatedwithoutcoldwireNiadditions,thechemicalvariabilityisverylowandcomparabletothatofplatematerial.LimitingRPVMaterialsforEOLRT~,P/TlimitcurvesandLTOP.AsaresultofthelowCuandlowNiwelds,theStLucieUnit2RPVisplatelimitedfor10CFR50.61RT~atendoflife(EOL)andisplatecontrollingforthecurrentpressuretemperature(P/T)limitcurvesandlowtemperatureoverpressureprotection(LTOP)analysis.FortheSt.LucieUnit2RPV:thehighestRT~,atendoflicense(EOL)is163'F(morethan100'Fbelowthescreeningcriteria),forplatematerial;thehighestRT~,atEOLis47'forbeltlineweldmaterialsi.WithlowEOLRTmvaluesandplatelimitingcriticalmaterial,noadditionalinformationonournon-Cucoatednon-limitingbeltlineweldswillbe"relevant"fordeterminingthestructuralintegrityofthereactorvesselsinceitiscontrolledbytheplateproperties.ActivitiestoIdentifRelevantDataandSourcesWestinghouseOwnersGroupRPVDATADatabase:TheWestinghouseOwnersGroup(WOG)MaterialsandChemistrySubcommitteehascompiledadatabase,RPVDATA,ofallinformationrelevanttoreactorvesselintegritythatisavailablefromWestinghouseElectricCorporationdocketedNRCGenericLetter(GL)92-01responsesandpreviousEPRIdatabasesonreactorvesselintegrity.Theinformationincludedinthedatabaseisfromoriginalfabricationrecords,reactorvesselsurveillanceprogramtesting,andothersupplementaltestingperformedbyWestinghouse.FPLhasreviewedthisdatabasetodetermineother"sister"plantsthatcontainidenticalreactorvesselweldheatsandthatwouldbe"ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment2Page2of5relevanttothedeterminationofreactorvesselintegrityforSt.LucieUnit2.Threeplantswereidentifiedashavingidenticalweldheatsbutnoplantswereidentifiedashavingidenticalplateheats.NRCReactorVesselIntegrityDatabase(RVID):FPLreceivedtheinitialpublicissueoftheNRCReactorVesselIntegrityDatabase2(RVID).FPLhasreviewedthisdatabasetoidentifyadditional"sister"plantsthatcontainidenticalreactorvesselweldheatsandthatwouldberelevanttothedeterminationofreactorvesselintegrityforSt.LucieUnit2.NoplantswereidentifiedotherthanthethreepreviouslyidentifiedbytheWOGRPVDATAdatabase.CEOG-ReactorVesselWorkingGroup:TheCombustionEngineeringOwnersGroup(CEOG)hasformedtheReactorVesselWorkingGroup(RVWG)toaddresstheissueofweldchemistryvariabilityforCEfabricatedreactorvesselwelds.Thistaskwillfocusoncompilingdatafromoriginalfabricationrecords,researchdatafiles,andlogbookscompiledbyCE.Inaddition,thetaskwillcompiledatafromsurveillancetest,supplementaltestresultsby.CE,otherNSSSsuppliers,andutilities.TherelevantdatawillbeusedtodetermineabestestimatechemistryforeachweldheatfabricatedbyCE.FPLisparticipatinginthiseffortwhichisexpectedtotakeaminimumof18monthstocomplete'lusanadditional6monthstoassessthesignificanceofanynewdata.Thelengthofthisscheduledoesnotimpactsafetybecausetheweldmaterialsarenotlimitingandarenotdirectly"pertinent"toevaluationofreactorvesselintegrity.Infact,theSt.LucieUnit2reactorvesselbeltlineweldmaterialswillremaingreaterthan200FbelowthePTSscreeninglimitof270FasdocumentedintheRVID4."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.CEOwnersGroupLetterCEOG-95-390,"CEOGReactorVesselWorkingGroupActivities...",DavidSagertoU.S.NuclearRegulatoryCommission,July27,1995."ReactorVesselIntegrityDatabase-Version1.1",U.S.NuclearRegulatoryCommission,July1995.
Attachment2Page4of5NRCReuest2:Provideanassessmentofanychangeinbest-estimatechemistrybasedonconsiderationofallrelevantdata.FPLResonse2:ThelimitingmaterialfordeterminingRPVintegrityisthebeltlineplatematerial.AreviewoftheNRCRVIDandWOGRPVDATAdatabasesshow.noidenticalmatchofheatsforthelimitingplatematerials,therefore,nonewdataisexpected.SincethereisnochangetothebestestimatechemistryfortheSt.LucieUnit2limitingreactorvesselplatematerial,therewillbenoimpactrelativetoreactorvesselstructuralintegrity.NRCReuest3:ProvideadeterminationoftheneedforuseoftheratioprocedureinaccordancewiththeestablishedPosition2.1ofRegulatoryGuide1.99,Revision2,forthoselicenseesthatusesurveillancedatatoprovideabasisfortheRPVintegrityevaluation.FPLResonse3:ThedeterminationofvesselintegrityfortheSt.LucieUnit2reactorvesselmaterialshasbeenmadeusingthebestestimatechemistrywithouttheuseofsurveillancedata.Onlyonesurveillancecapsulehasbeentestedfromthisunitandthereforeposition2andspecificallyposition2.1isnotapplicablefortheSt.LucieUnit2.NRCReuest4:Submitawrittenreportprovidinganynewlyacquireddataasspecifiedaboveand(1)theresultsofanynecessaryrevisionstotheevaluationofRPVintegrityinaccordancewiththerequirementsof10CFR50.60,10CFR50.61,AppendicesGandHto10CFRPart50,andanypotentialimpactontheLTOPorP/TlimitsintheTechnicalSpecificationsor(2)acertificationthatpreviouslysubmittedevaluationsremainvalid.RevisedevaluationsandcertificationsshouldincludeconsiderationofPosition2.1ofRegulatoryGuide1.99,Revision2,asapplicable,andanynewdata.
Attachment2Page5of5FPLResonse4:ThepreviouslysubmittedLTOPanalysisandP/TlimitscurvesintheTechnicalSpecificationswerebasedontheSt.LucieUnit2limitingintermediateshellplateM-605-1(A-8490-2).Thisplatehadthehighest1/4Tand3/4TadjustedRT~Yfortheperiodofapplicability.Sincenonewinformationisavailableforthelimitingplatematerials,thepreviouslysubmittedanalysisremainsvalid.TheuppershelfenergyvaluesfortheweldmaterialsreportedfortheSt.LucieUnit2reactorvesselareallinaccordancewiththe10CFR50AppendixGlimitof50ft-lbsatEOLaspreviouslysubmittedintheresponsetotheGL92-01andareidenticalorconservativelylowerthanthosevaluesreportedbythethreesisterplantsintheRVID.Conclusion:ThecompleteresponsetoNRCGenericLetter92-01,Revision1,Supplement1~,questions1through4areprovidedabove.TheresponsetothisGenericLetterisconsideredcompleteforSt.LucieUnit2.SinceFPLisparticipatingintheCEOGRVWGtasktodeterminebest.estimatechemistryvaluesforweldmaterials,anychangesinbestestimatechemistryforthenon-limitingreactorvesselbeltlineweldswillbereportedbySeptember1,1997.Theschedulefordeterminingchangestothebestestimateweldchemistrywillhavenoeffectondeterminationofreactorvesselintegrity.Theseweldsarenotlimitingmaterials,arebothlowinCuandNi,andaregreaterthan200'Fbelowthe10CFR50.61screeningcriteriaatEOL.GenericLetter(GL)92-01,Revision1,Supplement1"ReactorVesselStructuralIntegrity,"NRCtoallholdersoflicensednuclearpowerreactors;May19,1995.