ML17227A497

Forwards Response to GL 92-01,Rev 1, Reactor Vessel Structural Integrity.

ML17227A497
Person / Time
Site:	Saint Lucie
Issue date:	07/01/1992
From:	BOHLKE W H FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, L-92-189, NUDOCS 9207080119
Download: ML17227A497 (35)

Text

ACCELERATEDDISTRIBUTIONDEMONSTRATIONSYSTEMr,REGULAT..INFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9207080119DOC.DATE:92/07/01NOTARIZED:YESFACIT:50-335St.LuciePlant,Unit1,FloridaPower&LightCo."50-389St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATIONBOHLKE,W.H.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

ForwardsresponsetoGL92-01,Rev1,"ReactorVesselStructuralIntegrity."DISTRIBUTIONCODE:ROOIDCOPIESRECEIVED:LTRiENCLQSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:DOCKET0500033505000389RECIPIENTIDCODE/NAMEPD2-2LANORRISiJINTERNAL:ACRSNRR/DOEA/OTSB11NRR/DST/SELB7ENRR/DST/SRXB8EOCLFEXTERNAL:NRCPDRgyp7+gO~8IgrQlQt~~E/I('u4COPIESLTTRENCL112266111111101111RECIPIENTIDCODE/NAMEPD2-2PDNRR/DET/ESGBNRR/DST8E2NRR/DST/SICB8H7NUDOCS-ABSTRACTOGC/HDS3RES/DSIR/EIBNSICCOPIESLTTRENCL1111111111101111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!ggSTOTALNUMBEROFCOPIESREQUIRED:LTTR&3-ENCL P.O.Box14000,JunoBeach,FL33408-0420L-92-18910CFR50.410CFR50.54(f)U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555JUL-1i992RE:St.LucieUnits1and2DocketNo.50-335and50-389GenericLetter92-01Revision1ResonseTheFloridaPowerandLightCompany(FPL)responsetorevision1ofGenericLetter92-01"ReactorVesselStructuralIntegrity,10CFR50.54(f)"forSt.LucieUnits1and2isattached.OnMarch6,1992theNRCissuedthisgenericletteraspartofanNRCprogramtoevaluatereactorvesselintegrity,toensurelicenseesarecomplyingwith10CFR50.60and10CFR50.61,andtoconfirmcommitmentsmadeinresponsetoGenericLetter88-11.TheattachedinformationisprovidedpursuanttotherequirementsofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f).Pleasecontactusifthereareanyquestionsaboutthissubmittal.'erytrulyyours,W.H.BohlkeVicePresidentNuclearEngineeringandLicensingWHB/GRM/kwcc:StewartD.Ebneter,RegionalAdministrator,Region.II,USNRCSeniorResidentInspector,USNRC,St.LuciePlantDAS/PSL4724-929207080ii992070iPDRADOCK,05000335PPDRanFPLGroupcompany~D-j3fPd~8.~/is+

St.LucieUnits1and2DocketNo.50-335and50-389GenericLetter92-01Revision1ResonseSTATEOFFLORIDA))COUNTYOFPALMBEACH)ss~W.H.Bohlkebeingfirstdulysworn,deposesandsays:ThatheisVicePresident,NuclearEngineeringandLicensingfortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.H.BohlkeSTATEOFFLORIDACOUNTYOFQTheforegoinginstrumentwasacknowledgedbeforemethis~dayof,19R2.byW.H.Bohlke,whoispersonallyknowntomeandwhoid(didnot)takeanoath.Q.dNameofNoryPublicNotaryPublic,StateofFloridaMyComm.Exp.Feb.18,1995MyCOmmiSSiOneXpireSBondsdthruPICHARDlns.AgencyCommissionNo.00

~\I St.LucieUnits1and2DocketNo.50-335and50-389GenericLetter92-01Revision1ResonseRESPONSETONRCGL92-01FORST~LUCIEUNIT2uestion1CertainaddresseesarerequestedtoprovidethefollowinginformationregardingAppendixHto10CFRPart50:AddresseeswhodonothaveasurveillanceprogrammeetingASTME185-73,79,or-82andwhodonothaveanintegratedsurveillanceprogramapprovedbytheNRCarerequestedtodescribe'actionstakenortobetakentoensurecompliancewithAppendixHto10CFRPart50.AddresseeswhoplantorevisethesurveillanceprogramtomeetAppendixHto10CFRPart50arerequestedtoindicatewhentherevisedprogramwillbesubmittedtotheNRCforreview.IfthesurveillanceprogramisnottoberevisedtomeetAppendixH.to10CFRPart50,addresseesarerequestedtoindicatewhentheyplantorequestanexemptionfromAppendixHto10CFRPart50under10CFR50.60(b).Thecurrent(1983)versionofAppendixHto10CFRPart50reads:ThatpartofthesurveillanceprogramconductedpriortothefirstcapsulewithdrawalmustmeettherequirementsoftheeditionoftheASTME185thatiscurrentontheissuedatetowhich-thereactorvesselwaspurchased.LaterversionsoftheASTMstandardmaybeused,butincludingonlythoseeditionsthrough1982.ForeachcapsulewithdrawalafterJuly26,1983,thetestproceduresandreporting,requirementsmustmeettherequirementsofASTME185-82totheextentpracticalfortheconfigurationofthespecimensinthecapsule.ForeachcapsulewithdrawalpriortoJuly26,1983eitherthe1973,the1979,orthe1982EditionofASTME185maybeused.TheSt.LucieUnit2reactorvesselwasdesignedtothe1971EditionthroughtheSummerof1972AddendaoftheASMECode.TheSt.LucieUnit2ReactorVesselSurveillanceProgramwasdesignedtoASTME185-73.Inaddition,thematerialsselectedforthesurveillanceprogramarethemostlimitingmaterial.Testingoftheonlycapsuleremovedtodate,capsuleW-83,wasconductedinaccordancewithE185-82.TheSt.LucieUnit2surveillanceprogramcomplieswith10CFR50,AppendixH.Nofurtheractionisrequired.

t uestion2.aCer'tainaddresseesarerequestedtoprovidethefollowinginformationregardingAppendixGto10CFRPart50:AddresseesofplantsforwhichtheCharpyuppershelfenergyispredictedtobelessthan50foot-poundsattheendoftheirlicensesusingtheguidanceinParagraphC.1.2orC.2.2inRegulatoryGuide1.99,Revision2,arerequestedtoprovidetotheNRCtheCharpyuppershelfenergypredictedforDecember16,1991,andfortheendoftheircurrentlicenseforthelimitingbeltlineweldandtheplateorforgingandarerequestedtodescribetheactionstakenpursuanttoParagraphsIV.A.1orV.CofAppendixGto10CFRPart50.Resonse2.aTheSt.LucieUnit2reactorvesselwasbuiltatatimewhentheinfluenceofcoppercontentonir'radiationembrittlementwasbecomingbetterdefined.Applyingtheselowcoppervaluesfromthe2St.LucieUnit2reactorvesselbeltlinematerialstotheRegulatoryGuide1.99,Revision2predictionforCharpyuppershelfenergy(USE),doesnotresultinanyofthebeltlinematerialsfallingbelow50ft.-lbs.USEatorbeforetheendofthecurrentoperatinglicense.Belowisatableshowingthepredictedendoflicense(EOL)uppershelfenergyatthe1/4Tlocationforthelimitingbeltlinematerial.AllmaterialpropertyvaluesareasreportedintheSt.LucieUnit2FSAR<')unlessotherwisenoted.MATERIALINITIALUSEft-Ibg'rsasvcrsc)0CuEOL1/4THacacc(a/cm')REGGUIDE1.99REDUCTIONEOLUSEft-1bPlateM-605-1IntermediatetoLowerShellGirthWeld(101-171)1050.111.83x10'~0.071.83x1023424%8187'helimitingbeltlineweldfortheSt.LucieUnit2istheintermediatetolowershellgirthweld(101-171),andisintheSt.LucieUnit2ReactorVesselSurveillanceProgram.ThelimitingbeltlineplateistheM-605-1plateandiscontainedintheSt.LucieUnit2ReactorVesselSurveillanceProgram.uestion2.bAddresseeswhosereactorvesselswereconstructedtoanASMECodeearlierthantheSummer1972Addendaofthe1971Editionarerequestedtodescribetheconsiderationsgiventothefollowing materialpropertiesintheirevaluationsperformedpursuantto10CFR50.61andParagraphIII.Aof10CFRPart50,AppendixG:(1)TheresultsfromallCharpyanddropweighttestsforall2unirradiatedbeltlinematerials,andtheunirradiatedreferencetemperatureforeachbeltlinematerial,andthemethodfordeterminingtheunirradiatedreferencetemperaturefromtheCharpyanddropweighttest;(2)Theheattreatmentreceivedbyallbeltlineandsurveillancematerials;(3)Theheatnumberforeachbeltlineplateorforgingandtheheatnumberofwire.andfluxlotnumberusedtofabricateeachbeltlineweld;(4)Theheatnumberforeachsurveillanceplateorforgingandheatnumberofwireandfluxlotnumberusedtofabricatethesurveillanceweld;(5)Thechemicalcomposition,inparticulartheweightinpercentofcopper,nickel,phosphorous,andsulphurforeachbeltlineandsurveillancematerial;and(6)TheheatnumberofthewireusedfordeterminingtheweldandchemicalcompositionifdifferentthanItem(3)above.Resonse2.bTheSt.LucieUnit2reactorvesselwasdesignedtothe1971EditionthroughtheSummerof1972AddendaoftheASMESectionIIICode.Althoughnotrequiredtorespondtothisquestionbecauseofthevesseldesigndate,allthematerialpropertiesrequestedinQuestion2.barereportedintheSt.LucieUnit2FSAR+andinthelatest10CFR50.61PTSreport+.AddresseesarerequestedtoprovidethefollowinginformationregardingcommitmentsmadetorespondtoGL88-11:(A)Howtheembrittlementeffectsofoperatingatanirradiationtemperature(coldlegorrecirculationsuctiontemperature)below525'F.wereconsidered.InparticularlicenseesarerequestedtodescribeconsiderationgiventodeterminingtheeffectoflowerirradiationtemperatureonthereferencetemperatureandontheCharpyuppershelfenergy.(B)Howtheirsurveillanceresults,onthepredictedamountofembrittlementwereconsidered.

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~~(C)Ifameasuredincreaseinreferencetemperatureexceedsthemean-plus-twostandarddeviationspredictedbyRegulatoryGuide1.99,Revision2,orifameasureddecreaseinCharpyuppershelfenergyexceedsthevaluepredictedusingtheguidanceinParagraphC.1.2inRegulatoryGuide1.99,Revision2,thelicenseeisrequestedtoreporttheinformationanddescribetheeffectofthesurveillanceresultsontheadjustedreferencetemperatureandCharpyuppershelfenergyforeachbeltlinematerialaspredictedforDecember,16,1991,andfortheendofitscurrentlicense.Resonse3.aTheSt.LucieUnit2reactorvesselhasnotoperatedbelow525'F.,asmeasuredbythecoldlegtemperature,forasignificantperiodoftime.Thecumulatedtimeandneutronfluenceaccumulatedatcriticaloperationsbelow525'F.isconservativelyestimatedtobelessthan8effectivefullpowerhoursorsignificantlybelow1x10'/cm.Sincetheresultantfluenceissignificantlybelow1x10'/cm,theeffectofthislowtemperatureirradiationontheadjustedreferencetemperatureanduppershelfisnegligible.Resonse3.bFloridaPower&LightCo.respondedtotheNRCGenericLetter88-11withL-88-498<4>forboththeSt.LucieUnits1and2reactorvessels.ThatletterstatedthattheP/TlimitcurveswereintheprocessofbeingrevisedandwouldusethelatestRegulatoryGuide1.99,Revision2methodsforcalculationofadjustedreferencetemperature.OnFebruary7,1990@,FloridaPower&LightCo.submittedAmendmentNo.46forSt.LucieUnit2,revisingtheP/TlimitcurvesandLTOPsetpointanalyses.ThecalculationofadjustedreferencetemperatureusedthepredictionmethodologyinRegulatoryGuide1.99,Revision2,Position1.1.Thispositionwasusedbecauseonlyonecapsulehasbeenpulledfromthefourcapsuleprogram.TwoormorecrediblesurveillancedatapointsareneededtobaseadjustedreferencetemperaturepredictiononactualdataperRegulatoryGuide1.99,Revision2,Position2.1.ActualSurveillancedatafromSt.LucieUnit2hasshownthattheRegulatoryGuide1.99,Revision2doesconservativelyoverpredicttheshiftinadjustedreferencetemperatureforthelimitingplateandlimitingweldmaterial.ThustheRegulatoryGuidepredictionofadjustedreferencetemperaturefortheSt.LucieUnit2beltlinematerialusedintheP/TlimitandLTOPanalysisisconservativeandboundingwhenactualsurveillancedataisconsidered.OnAugust21,1990,theNRCissuedaletterthatsaidthereviewoftheP/Tlimitcurves(Amendment46),wereacceptable,whichcompletedthereviewofthe88-11issueforSt.LucieUnit.2.

I' Resonse3.cThemeasuredreferencetemperaturefortheSt.LucieUnit2surveillancecapsulemateriallimitingplateandlimitingintermediatetolowershellgirthweldfromcapsuleW-83+havebothexhibitedanincreaseinadjustedreferencetemperaturewhichwaslessthanpredictedbyRegulatoryGuide1.99,Revision2.ThemeasureddropinuppershelfenergyfortheSt.LucieUnit2limitingbasemetalandlimitingweldmetalfromcapsuleW-83+waslessthanpredictedbyRegulatoryGuide1.99,Revision2.

1 REFERENCELIST(1)FloridaPower&LightCo.,St.LuciePlantUnit2,UpdatedFinalSafetyAnalysisReport,Chapter5.0(2)'nalysisof.CapsuleW-83,FloridaPower&LightCo.,St.LuciePlantUnit2,Babcock&Wilcox,September1985,BAW-1880(3)FPLLetter,L-86-25,St.LucieUnit210CFR50.61-PTSReport,C.0.WoodytoNRC,January23,1986(4)FPLLetter,L-88-498,St.LucieUnits1and2ResponsetoGenericLetter88-11,W.F.ConwaytoNRC,November23,1988(5)FPLLetter,L-90-46,St.LucieUnit2ProposedLicenseAmendment,P/TLimitsandLTOPAnalysis,J.H.GoldbergtoNRC,February7,1990

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St;LucieUnits1and2DocketNo.50-335and50-389GenericLetter92-01Revision1ResonseRESPONSETONRCGL92-01FORST~LUCIEUNIT1uestion1CertainaddresseesarerequestedtoprovidethefollowinginformationregardingAppendixHto10CFRPart50:AddresseeswhodonothaveasurveillanceprogrammeetingASTME185-73,79,or-82andwhodonothaveanintegratedsurveillanceprogramapprovedbytheNRCarerequestedtodescribeactionstakenortobetakentoensurecompliancewithAppendixHto10CFRPart50.AddresseeswhoplantorevisethesurveillanceprogramtomeetAppendixHto10CFRPart50arerequestedtoindicatewhentherevisedprogramwillbesubmittedtotheNRCforreview.IfthesurveillanceprogramisnottoberevisedtomeetAppendixHto10CFRPart50,addresseesarerequestedtoindicatewhentheyplantorequestanexemptionfromAppendixHto10CFRPart50under10CFR50.60(b).Resonse1Thecurrent(1983)versionofAppendixHto10CFRPart50reads:ThatpartofthesurveillanceprogramconductedpriortothefirstcapsulewithdrawalmustmeettherequirementsoftheeditionoftheASTME185thatiscurrentontheissuedatetowhichthereactorvesselwaspurchased.LaterversionsoftheASTMstandardmaybeused,butincludingonlythoseeditionsthrough1982.ForeachcapsulewithdrawalafterJuly26,1983,thetestproceduresandreportingrequirementsmustmeettherequirementsofASTME185-82totheextentpracticalfortheconfigurationofthespecimensinthecapsule.ForeachcapsulewithdrawalpriortoJuly26,1983eitherthe1973,the1979,orthe1982EditionofASTME185maybeused.ASTME185wasoriginallyissuedin1961andwasrevisedin1966,1970,1973,1979and1982.AppendixHto10CFRPart50,whichwasfirstpublishedin1973,outlinestherequirementsforcompliancewiththepertinentversionofASTME185.TheSt.LucieUnit1reactorvesselwasdesignedtothe1965EditionthroughtheWinterof,1967AddendaoftheASMECode.TheSt.LucieUnit1surveillanceprogrammeetsASTME185-1970,whichwasthestandardinplaceatthetimethesurveillanceprogramwasdesigned.ThisprogramisdescribedintheSt.LucieUnit1FSAR"'.Aspartofthe 4

~~licensingprocess,theAtomicEnergyCommissionreviewedtheSt.LucieUnit1surveillanceprogramandconcludedthattheessentialmaterialsurveillancerequirementsofASTME185-73andAppendixHof10CFRPart50weremet~).TestingofthesurveillancecapsuleremovedafterJuly26,1983wasconductedinaccordancewithE185-82.BasedonthefavorableSafetyEvaluation+,anexemptionto'AppendixHof10CFRPart50isnotnecessary.uestion2.aCertainaddresseesarerequestedtoprovidethefollowinginformationregardingAppendixGto10CFRPart50:AddresseesofplantsforwhichtheCharpyuppershelfenergyispredictedtobelessthan50foot-poundsattheendoftheirlicensesusingtheguidanceinParagraphC.l.2orC.2.2inRegulatoryGuide1.99,Revision2,arerequestedtoprovidetotheNRCtheCharpyuppershelfenergypredictedforDecember16,1991,andfortheendoftheircurrentlicenseforthelimitingbeltlineweldandtheplateorforgingandarerequestedtodescribetheactionstakenpursuanttoParagraphsIV.A.1orV.CofAppendixGto10CFRPart50.Resonse2.aThepredictionofuppershelfenergyforreactorvesselbeltlinelimitingweldandplateisverymaterialandplantspecific.UsingRegulatoryGuide1.99,Revision2forpredictions,theSt.LucieUnit1vesselbeltlinematerialsarenotpredictedtofallbelow50foot-poundsuppershelfenergy(USE)atorbeforetheendofthecurrentoperatinglicense.Belowisatableshowingthepredictedendoflicense(EOL)uppershelfenergyatthe1/4Tlocationforthelimitingbeltlinematerial.MATERIALPlateC-5935-2(C 2)INITIALUSEft-lbg'ransverse)103')%Cu0.15EOL1/4THucace(n/cm')2.01x10'~REGGUIDE1.99'tREDUCTION284EOLUSEft-lb74.2LowerShellLongWelds(3203AgBgC)IntermediatetoLowerShellGirthWeld(9-203)112<4)144>>0.300.231.27x10'~2.01x10'~444424'2.783.5*St.LucieUnit1limitingbeltlinematerial**St.LucieUnit1surveillancematerial (IlWlfJ/p<'

~0ThelimitingbeltlineweldfortheSt.LucieUnit1vesselisidentifiedasthelowershelllongitudinalweldseams.TheseweldserumswerefabricatedwiththewireheatandfluxlotidentifiedinTable2.FloridaPower6LightCo.hasalsoidentifiedthatthisexactCEfabricatedweldiscontainedintheDuquesneLightBeaverValleyUnit1ReactorVesselSurveillanceProgram<".TheunirradiatedinitialtransverseUSEdatafromtheBeaverValleyUnit1surveillanceprogramisusedintheabovecalculation.InitialpropertydataforCEfabricatedweldsisconsideredtobetransferablebetweenvesselssinceitisafunctionofmaterialtypeandfabricationhistorywithoutinfluencebyreactordesigner.FloridaPowerErLightCo.,inconjunctionwiththeCombustionEngineeringOwners'roup,hassubmittedareport<@totheNRCoutlininganapproachtointegratetheirradiateddatalikethatfromtheBeaverValleyUnit1intotheSt.LucieUnit1ReactorVesselSurveillanceProgram.uestion2.bAddresseeswhosereactorvesselswereconstructedtoanASMECodeearlierthantheSummer1972Addendaofthe1971Editionarerequestedtodescribetheconsiderationsgiventothefollowingmaterialpropertiesintheirevaluationsperformedpursuantto10CFR50.61andParagraphIII.Aof10CFRPart50,AppendixG:(1)TheresultsfromallCharpyanddropweighttestsforallunirradiatedbeltlinematerials,andtheunirradiatedreferencetemperatureforeachbeltlinematerial,andthemethodfordeterminingtheunirradiatedreferencetemperaturefromtheCharpyanddropweighttest;(2)Theheattreatmentreceivedbyallbeltlineandsurveillancematerials;(3)Theheatnumberforeachbeltlineplateorforgingandtheheatnumberofwireandfluxlotnumberusedtofabricateeachbeltlineweld;(4)Theheatnumberforeachsurveillanceplateorforgingandheatnumberofwireandfluxlotnumberusedtofabricatethesurveillanceweld;(5)Thechemicalcomposition,inparticulartheweightinpercentofcopper,nickel,phosphorous,andsulphurforeachbeltlineandsurveillancematerial;and(6)TheheatnumberofthewireusedfordeterminingtheweldandchemicalcompositionifdifferentthanItem(3)above.Resonse2.b.1TheSt.LucieUnit1vesselwasbuilttoASMESectionIII1965EditionthroughtheWinterof1967Addenda.Fracturetoughness

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~~testswereperformedonallthebeltlinematerialsusedtofabricatetheSt.LucieUnit1vessel.Wheretestingwasnotdonein"accordancewiththeSummer1972Addendaofthe1971EditionofASMEIII,theNRCStandardReviewPlan(NUREG-0800)BranchTechnicalPosition-MTEB5-2wasusedtoestimatethetoughnesspropertiesforplatematerial.Weldpropertieswerebasedongenericvaluesaslistedinthecurrent10CFR50.61PTSrule.Table1showsthedropweighttestsandRT~~valuesfortheSt.LucieUnit1beltlineplatematerialaswellasthemethodusedtodeterminethesevalues.Table2showsthedropweighttestand,RT~~valuesforthebeltlineweldmaterial.Resonse2.b.2TheheattreatmentforboththeSt.LucieUnit1vesselbeltlineplate,materialandsurveillanceplatematerialconsistedofaustenitizationat1600F.+25OF.forfourhours,waterquenchedandtempeiedat1225'F.+25'F.forfourhours.TheASMECodequalificationsandsurveillancetestplatesreceivedasubsequent1150'F.+25'F.stressrelieffor40hoursandfurnacecooledto600'F.+.Thesurveillanceweldmentreceiveda40hourstressreliefof1100'F.to1150'F.">><'>Stressreliefheattreatmentforthevesselbeltlinematerialswas1150'F.+25'F.Theactualtimeattemperatureforthespecificbeltlineweldsdependsonitsfabricationsequence.Theintermediateandlowerlongitudinalweldsreceiveda40hourstressrelieftreatmentwhilethe.intermediatetolowergirthseamreceived18hoursatstressrelieftemperature<~.Inconclusion,thetestmaterialsusedtoestablishbeltlinefracturetoughnesspropertieshavebeenheattreatedtoberepresentativeofthereactorvesselbeltlinematerials.Resonse2.b.3TheheatnumberforeachbeltlineplatefortheSt.LucieUnit1vesselislistedinTable1.ThewireheatnumberandfluxlotforeachbeltlineweldfortheSt.LucieUnit1vesselislistedinTable2.Resonse2.b.4TheSt.LucieUnit1surveillanceplateandweldmaterialarelistedinTables1and2andareidentifiedbyfootnoteb.Resonse2.b.5ThechemistryvaluesfortheSt.LucieUnit1vesselbeltlinematerialsarelistedinTables1and2.

4.'a'all Resonse2.b.6Thhchemistryforeachbeltlineplatewastakenfromtheactualplatematerial.AllweldheatchemistriesweretakenfromtheactualweldwireheatnumberwiththeexceptionofthenickelvaluereportedfortheintermediateshelllongitudinalseamsinTable2.ThisvaluewasestimatedbyCEbasedonagroupofhighmanganese,molybdenum,lownickel,B-4weldwire<'".Nonickeladditionwasusedwiththisweld.uestion3AddresseesarerequestedtoprovidethefollowinginformationregardingcommitmentsmadetorespondtoGL88-11:(A)Howtheembrittlementeffectsofoperatingatanirradiationtemperature(coldlegorrecirculationsuctiontemperature)below525'F.wereconsidered.InparticularlicenseesarerequestedtodescribeconsiderationgiventodeterminingtheeffectoflowerirradiationtemperatureonthereferencetemperatureandontheCharpyuppershelfenergy.(B)Howtheirsurveillanceresultsonthepredictedamountofembrittlementwereconsidered.(C)Ifameasuredincreaseinreferencetemperatureexceedsthemean-plus-twostandarddeviationspredictedbyRegulatoryGuide1.99,Revision2,orifameasureddecreaseinCh'arpyuppershelfenergyexceedsthevaluepredictedusingtheguidanceinParagraphC.1.2inRegulatoryGuide1.99,Revision2,thelicenseeisrequestedtoreporttheinformationanddescribetheeffectofthesurveillanceresultsontheadjustedreferencetemperatureandCharpyuppershelfenergyforeachbeltlinematerialaspredictedforDecember16,1991,andfortheendofitscurrentlicense.Resonse3.aTheSt.LucieUnit1reactorvesselhasnotoperatedbelow525'F.asmeasuredbythecoldlegtemperatureforasignificantperiodoftime.Thetotalcumulativetimeandreactorfluenceaccumulatedatcriticaloperationsbelow525'F..isconservativelyestimatedtobelessthaneighteffectivefull-powerhoursorsignificantlylessthan1x10"n/cmSincetheresultantfluenceissignificantlybelow1x10'/cmgtheeffectofthislowtemperatureirradiationonthereferencetemperatureanduppershelfisnegligible.Additionally,theSt.LucieUnit1SurveillanceCapsuleReportshavebothrepresentativeplate,weldmaterial,andSRMmaterial,allofwhichhaveexhibitedlesstransitionshiftthatpredictedbyRegulatoryGuide1.99, CsAII Revision2++asdescribedinResponse3c.Therefore,thereisnoevidenceindicatingtheadverseaffectassociatedwithlowtemperatureirradiationfortheSt.LucieUnit1reactorvessel.Resonse3.bFloridaPower&LightCo.respondedtotheNRCGenericLetter88-11withL-88-498+forboththeSt.LucieUnits1and2reactorvessels.ThatletterstatedthattheP/TlimitcurveswereintheprocessofbeingrevisedandwouldusethelatestRegulatoryGuide1.99,Revision2methodsforcalculationofadjustedreferencetemperatureofthereactorvesselbeltlinematerials.OnDecember5g1989FloridaPower6LightCo.submittedAmendmentNo.104"+forSt.LucieUnit1,revisingtheP/TlimitcurvesandLTOPsetpointanalyses.ThecalculationofadjustedreferencetemperatureusedthepredictionmethodologyinRegulatoryGuide1.99,Revision2,Position1.1,becausetheSt.LucieUnit1surveillancecapsuledatadoesnot.meetthecredibilityrequirementofhavingthelimitingweldmaterialinitsprogram.ThesurveillancedatahasshownthattheRegulatoryGuide1.99,Revision2doesconservativelyoverpredicttheshiftinadjustedreferencetemperatureforthelimitingplate,girthweldandSRMmaterial.Thus,theRegulatoryGuidepredictionofadjustedreferencetemperatureforthelimiting-beltlinematerialusedintheP/TlimitcurveandLTOPanalysesisconservativeandboundingwhenactualsurveillancedataisconsidered.OnJune12,1990,theNRCissuedaletterthatsaidthereviewofthenewP/Tlimitcurves(Amendment104)wereacceptable,whichcompletedthereviewofthe88-11issueforSt.LucieUnit1.Resonse3.cTwosurveillancecapsuleshavebeenremovedandtestedfromtheSt.LucieUnit1reactorvessel.Thecapsulestestedtodatecoveranoperationtimespanfromstart-upthroughpartof1990.ThemeasuredreferencetemperaturefortheSt.LucieUnit1surveillancecapsulemateriallimitingplate,intermediatetolowershellgirthweldandSRMmaterialexhibitedanincreaseinadjustedreferencetemperaturewhichwaslessthanpredictedbyRegulatoryGuide1.99,Revision2.MeasuredreferencetemperaturefortheSt.LucieUnit1limitingweldmaterialthathasbeenirradiatedintheBeaverValleyUnit1surveillanceprogramhasexhibitedincreaseswithinthemeanplustwostandarddeviationspredictedbyRegulatoryGuide1.99,Revision2.FloridaPower6rLightCo.hasplanstosubmitthisdataanditsapplicabilitytotheSt.Lucie'nit1surveillanceprogrampendingreviewofReference8.Themeasureddropinuppershelfenergy(USE)fortheSt.LucieUnit1limitingbasematerialfromthefirstsurveillancecapsuleexceededtheRegulatoryGuide1.99,Revision2valueby34and24forthetransverseandlongitudinalorientationrespectively.Testresultsfromsecondcapsulewithhigherfluenceindicatedthe

'~

limitingplatelongitudinalmaterialhadnotexceededtheRegulatoryGuideprediction.ThemeasureddropinUSEfortheintermediatetolowershellgirthweldmaterialhasnotexceededtheRegulatoryGuideprediction.ThemeasureddropinUSEfortheSt.LucieUnit1limitingweldthathasbeenirradiatedintheBeaverValleyUnit1surveillanceprogramdidnotexceedthepredictionoftheRegulatoryGuideforallthreecapsulestestedtodate.ThemeasureddropinUSEfortheSRMplatematerialfromthesecondsurveillancecapsuleexceededtheRegulatoryGuidepredictionby10P.ThefirstcapsuledidnothaveSRMmaterialtoconfirmthisasa"credible"trend.AsnotedintheresponsetoResponse2.a,theendoflicense(EOL)uppershelfenergyforthelimitingplateisnotpredictedtoreach50foot-poundsatEOL.Ifanadditional34reductionwereappliedtotheRegulatoryGuide1.99,Revision2reductioninuppershelftocorrespondtothe34thatthemeasuredUSEexceededtheRegulatoryGuidepredictionfromthefirstcapsule,therewouldstillbeadequateUSEforthelimitingplateandtheEOLUSEwouldnotreach50foot-poundsasshownbelow(Case1).Thisadditional3>oreductionisoverlyconservative,sinceresultsfromthesecondcapsule-withhigherfluenceshowedUSEdroptobelessthantheRegulatoryGuideprediction.Applyinga10%penalty(fromtheSRMtestresults)tothepercentreductionfortheSt.LucieUnit1limitingplateshowsthattherewouldstillbeanUSEatEOLwhichisadequatelyabove50foot-pounds(Case2).ThisapproachisconsideredoverlyconservativesincetheactualUSEdecreaseforthevesselspecificlimitingplateandweldmaterialfromthesecondcapsule,whichyieldedtheSRMtestresult,werebothlessthanpredictedbyRegulatoryGuide1.99,Revision2.NoprojectionsweremadefortheplatematerialattheDecember16,1991datesincethefluenceisconsiderablylessthanthatattheEOL,andprojectionsatthistimewillobviouslynotdropbelowthe50foot-poundslimit.CASEMATERIALINITIALUSEIl-tb(1'raasvcrcc)%CuEQL1/4THa<<a<<c(a/cm')RG1.99'tREDUCTIONEOLUSEft-lbPlateC-5935-2(C 2)PlateC-5935-2(C 2)1031030.150.151x1028+3(31)2.01x10'8+10(38)71.163.9 i44>

TABLE1~~STLUCIEUNIT1REACTORVESSELBELTLINEPLATEMATERIALLOCATIONIntermediateShellPlateIntermediateShellPlateIntermediateShellLowerShellLowerShell-LowerShellHEATNOA-4567-1B-9427-1A-4567-2C-5935-1C-5935-2C-5935-3CODEC 1C 2C 3C 1C 2C 3SCu(6)0.110.110.110.150.150.12%Ni(6)0.640.640.580.560.570.58p(6)0.0040.0040.0040.0060.0060.004gS(6)0.0130.0100.0120.0100.0100.010DROP(6)WEIGHTTEST('F.)0-30-30-1010b0RTmT(F')08papa20~20b08NA-NotAvailablea-DeterminedusingMTEB5-2b-SurveillanceProgramData(')

TABLE2ST.LUCIEUNIT1REACTORVESSELBELTLINEWELDMATERIALWELDLOCATIONHEATNOFLUXTYPEFLUXLOT%Cu%NiDROPWEIGHTTEST(oF.)RTxoT('F.)IntermediateShellLongSeam(2-203AgB,C)A8746/34B009Linde1243878/36880.12(11)0.20c0.018(11)0.017(12)NA-56aLowerShellLongSeam(3-203A,BgC305424Linde10923889030(12)p64(12)p013(12)0.010(~2)NA-56aIntermediatetoLowerShellGirthSeam(9-203)90136Linde009139990'3O.1,1b0.013bO.O12b-6ob-6obNA-NotAvailablea-GenericdataforCEsubmergedareandRef.9b-SurveillanceProgramData(')c-EstimatedNicontent(lownickelweldsusingLinde0091,1092and124Fluxper10CFR50.61typewire)(")

I REFERENCELIST"FloridaPower&LightCo.,St.LucieUnit1,UpdatedFinalSafetyAnalysisReport",Chapter5.0"SafetyEvaluationoftheSt.LuciePlantUnitNo.1",U.S.Atomic-EnergyCommission,DirectorateofLicensing,November8,1974,Section5.3(3)"FloridaPower&LightCo.St.LucieUnit1EvaluationofBaseLineSpecimens",CombustionEngineering,Inc.,October1984,TR-F-MCM-005(6)"AnalysisofCapsuleWfromtheDuquesneLightCo.BeaverValleyUnit1ReactorVesselRadiationSurveillanceProgram",WestinghouseElectricCorp.,November1988,WCAP-12005"FloridaPower&LightCo.St.LucieUnit1PostIrradiationEvaluationofReactorVesselSurveillanceCapsuleW-97",CombustionEngineering,Inc.,December1983,TR-F-MCM-004"SummaryReportonManufactureofTestSpecimensandAssemblyofCapsulesforIrradiationSurveillanceofHutchinsonIslandPlant-Unit1ReactorVesselMaterials",CombustionEngineering,Inc.,July1972,CENPD-39"AnalysisoftheCapsule104'romtheFloridaPower&LightCo.St.LucieUnit1ReactorVesselRadiationSurveillanceProgram",WestinghouseElectricCorp.,November1990,WCAP-12751(8)"ApplicationofReactorVesselSurveillanceDataforEmbrittlementManagement",ABB-CombustionEngineering,Inc.,November1991,CEN-405-P,Rev.1-P(10)FPLLetter,L-88-498,St.LucieUnits1and2ResponsetoGenericLetter88-11,W.F.ConwaytoNRC,November23,1988FPLLetter,L-89-408,St.LucieUnit1ProposedLicenseAmendment,P/TLimitsandLTOPAnalysis,J.H.GoldbergtoNRC,December5,1989(11)(12)"EvaluationofPressurizedThermalShockEffectsDuetoSmallBreakLOCA'swithLossofFeedwaterfortheCombustionEngineeringNSS",CombustionEngineeringOwnersGroup,December1981,CEN-189andCEN-189AppendixFFPLLetter,L-77-308,St.LucieUnit1ReactorVesselMaterialInformation,R.E.UhrigtoD.K.Davis,NRC,September30,1977 0C\ejI~~~l;,4~~yII,~IIIaII