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
PRXORXTY1CELERATED RIDSPROCESSING)
)~~REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9508230314 DOC.DATE:95/08/16NOTARIZED:
YESFACIL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.50-389St.LuciePlant,Unit2,FloridaPower6LightCo.AUTH.NAMEAUTHORAFFILIATION SAGER,D.A.
FloridaPowerSLightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKETg05000335P05000389
SUBJECT:
Forwardsresponses toGL92-01,Rev 1,Suppl1,"RVStructural Integrity."
Utilconsiders submittal completeresponsetorequestsinGLsupplement.
DISTRIBUTION CODE:A028DCOPIESRECEIVED:LTR IENCLISIZE:/7TITLE:GenericLetter92-01,Rev1,Suppl1Responses (ReactorVesselStructNOTES:RECIPIENT IDCODE/NAME PD2-1PDINTERNAL:
ACRSNRR/DE/EMCB NUDOCS-ABSTRACT RES/DE/MEB EXTERNAL:
NOACCOPIESLTTRENCL116622111111RECIPIENT IDCODE/NAME NORRIS,JNZER~O;5NRR/'DEGAS ADI-1OGC/HDS3NRCPDRCOPIESLTTRENCL11111110NNOTETOALL"RZDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR17ENCL16 CIt FloridaPower&LightCompany,P.O.Box128,FortPierce,FL34954-0128 August16,1995L-95-23210CFR50.410CFR50.54(f)IU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555RE:St.LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructural Integrity GenericLetter92-01Revision1SulementResonseTheFloridaPowerandLightCompany(FPL)responses toGenericLetter(GL)92-01,Revision1,Supplement 1,ReactorVesselStructural Integrity,
'forSt.LucieUnits1and2areattached.
TheNuclearRegulatory Commission (NRC)issuedNRCGL92-01R1S1onMay19,1995,torequirelicensees toidentify, collect,andreportanynewdatapertinent toanalysisofstructural integrity oftheirreactorpressurevessel(RPV).Italsorequiresanassessment oftheimpactofthisnewdataonRPVintegrity analysesrelativetotherequirements of10CFR50.60,10CFR50.61,Appendices GandHto10CFR50,andanypotential impactonlowtemperature overpressure (LTOP)limitsorpressure-temperature (P/T)limits.TheGenericLettersupplement requested licensees toprovidearesponsetoitem1within90daysanditems2through4withinsixmonths.(1)Provideadescription ofthoseactionstakenorplannedtolocatealldatarelevanttothedetermination ofRPVIntegrity, oranexplanation ofwhytheexistingdatabaseisconsidered completeaspreviously submitted.
(2)Provideanassessment ofanychangeinbest-estimate chemistry basedonconsideration ofallrelevantdata.(3)Provideadetermination oftheneedforuseoftheratioprocedure inaccordance withtheestablished Position2.1ofRegulatory Guide1.99,Revision2,forthoselicensees that.usesurveillance datatoprovideabasisfortheRPVintegrity evaluation.
95082303i.4t.9508l6PDRADOCK05000335PPDRanFPLGroupcompanY St.'Lucie Units1and2DocketNos.50-335and50-389ReactorVesselStructural Integrity GenericLetter92-01Revision1SulementResonseL-95-232(4)Provideawrittenreportonanynewlyacquireddataasspecified above.Inaddition, includetheresultsofanynecessary revisions totheevaluation ofRPVintegrity inaccordance withtherequirements of10CFR50.60,10CFR50.61,Appendices GandHto10CFRPart50,andanypotential impactontheLTOPorP/TlimitsintheTechnical Specifications oracertification thatpreviously submitted evaluations remainvalid.Revisedevaluations andcertifications shouldincludeconsideration ofPosition2.1ofRegulatory Guide1.99,Revision2,asapplicable, andanynewdata.Thisletterandthetwoattachments providetheFPLresponsetoNRCrequestsitems1,2,3,and4forSt.LucieUnits1and2.FPLhaspreviously undertaken severalinitiatives toensurethatall"relevant" andlimitingdataforthedetermination ofreactorvesselintegrity forSt.LucieUnits1and2iscompleteaspreviously submitted.
FPLconsiders theattachments ofthissubmittal ourcompleteresponsetotherequestsintheGenericLetterSupplement.
FPLisparticipating inindustryeffortstoaddressthechemicalvariability ofitsnon-limiting weldstoeliminate anydiscrepancy intheNRCandindustrydatabases.
Thiseffortisexpectedtobecompleteandisscheduled tobesubmitted totheNRCbySeptember 1(1997.Theattachedinformation isprovidedpursuanttotherequirements ofSection182aoftheAtomicEnergyActof1954,asamended,and10CFR50.54(f).
Pleasecontactusifthereareanyquestions aboutthissubmittal.
Verytrulyyours,QiD.A.erVicesidentSt.Lc'ePlantDAS/GRMAttachments cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant l'w St."Lucie Units1and2DocketNos.50-335and50-389ReactorVesselStructural Integrity GenericLetter92-01Revision1SulementResonseL-95-232STATEOFFLORIDA))COUNTYOFST.LUCIESS~D.A.Sagerbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlantfortheNuclearDivisionofFloridaPower&LightCompany,theLicenseeherein;'hathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
D.A.ger'STATEOFFLORIDACOUNTYOF~TLLIUCTheforegoininstrument wasacknowledged before'ethist(OdayofbyD.A.Sager,whoispernallyknowntomeandwhodidtakeanoath.~&re+~s,+NameofNotaryPublicMyCommission expiresCommission No.KARENVkSt'.Q:a=.MYCOMNSSION fCC8M926EXP1RESAPI918,1998BONOFOTHRUTROYFAIHRIIRANCE, INC.
LNJI)]O'I)~W,[~eliUIIbII St.LucieUnits1and2DocketNos.50-335and50-389ReactorVesselStructural Integrity GenericLetter92-01RevisioSulementResonseL-95-232Attachment 1ResponsetoNRCGL92-01Revision1Supplement 1ForSt.Luci.eUnit1 RIEI Attachment 1Page1of7ResponsetoNRCGL92-01Supplement 1St.LucieUnit1Background TheStLucieUnit1reactorpressurevessel(RPV)wasdesignedandmanufactured byCombustion Engineering Inc.(CE).
Theweldwiresusedtofabricate thebeltlineweldswerecopper(Cu)coatedandoneheatofwirehadaB-4modifiednickel(Ni)alloyadditioninthewroughtwire.Theremaining beltlineweldwireswereoflowNicontent.NoRPVbeltlineweldsutilizedsupplemental coldNiwireadditions duringfabrication.
WithlowNiweldsfabricated withoutcoldwireNiadditions, theNivariability isverylowandcomparable tothatofplatematerial.
LimitingRPVMaterials forEOLRT~,P/TlimitcurvesandLTOP.AsaresultoftheCucoatedweldwireandmodifiedNicontentofoneoftheweldheats,theStLucieUnit1RPVisweldlimitedfor10CFR50.61RT~,atendoflife(EOL)andforthecurrentpressuretemperature (P/T)limitcurvesandlowtemperature overpressure protection (LTOP)analysis.
TheSt.LucieUnit1limitingbeltlineweldheatis305424withLinde1092fluxandhadpreviously beenidentified byFPLasthesameheatandfluxlotusedtofabricate aBeaverValleyUnit1RPVbeltlineweldaswellasitsRPVsurveillance testprogram.Twosourcesofdatawereknowntobeavailable todetermine thebestestimateweldchemistry ofthisweld;theoriginalCEweldqualification'nd theBeaverValleyUnit1surveillance program~.
FPLsubmitted thisbestestimateweldchemistry initsinitialresponsetoGL92-01.FortheSt.LucieUnit1RPV:thehighestRT~atendoflicense(EOL)is227'FaslistedintheNRCRVID4and"Atypical WeldMaterialInReactorPressureVesselWelds"CEResponsetoI&EBulletin78-12,June8,1979,SectionVIII,Page23,LabgD8160."Analysis ofCapsuleWfromDuquesneLightCo.BeaverValleyUnit1ReactorVesselRadiation Surveillance Program",
Westinghouse ElectricCorp.,Nov.1988,WCAP-12005.FPLLetter,L-92-189, "St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",
W.H.BohlketoNRC,July1,1992."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 1Page2of7corresponds tothelimitingweldheat305424.DuetothelowNicontentoftheremaining weldheats,theRVIDEOLRT~oftheseweldsaremorethan100'Fbelowthatofthelimitingweldandbelowallofthesixbeltlineplates.AllsixbeltlineplateshaveRVIDEOLRT~values ofbelow200'F.Activities toIdentifRelevantDataandSourcesWestinghouse OwnersGroupRPVDATADatabase:
TheWestinghouse OwnersGroup(WOG)Materials andChemistry Subcommittee hascompiledadatabase, RPVDATA,ofallinformation relevanttoreactorvesselintegrity thatisavailable fromWestinghouse ElectricCorporation docketedGL92-01responses andpreviousEPRIdatabases onreactorvesselintegrity.
Theinformation includedinthedatabaseisfromoriginalfabrication records,reactorvesselsurveillance programtesting,andothersupplemental testingperformed byWestinghouse.
FPLreviewedthisdatabaseandidentified other"sister"plantsthatcontainidentical reactorvesselweldheats,andthatwouldberelevanttothedetermination ofreactorvesselintegrity forSt.LucieUnit1.Twootherplantswereidentified ashavingtheidentical weldheat(305424)astheSt.LucieUnit.1limitingweld.However,allofthisdatahadpreviously beenincorporated intothecurrentbestestimatechemistry determination.
Additional sisterplantswerenotedfortheotherlowNiweldheatsbutnonew"relevant" datawouldmaketheseweldsmorelimitingthanweldheat305424forSt.LucieUnitl.NRCReactorVesselIntegrity Database(RVID):FPLreceivedtheinitialpublicissueoftheNRCReactorVesselIntegrity Database~
(RVID).FPLhasreviewedthisdatabasetoidentifyadditional "sister"plantsthatcontainidentical reactorvesselweldheatsandthatwouldberelevanttothedetermination ofreactorvesselintegrity forSt.LucieUnit1.Onenewplantwasidentified buttheweldwasoutofitsbeltlinesothelicenseeusedanon-measured, upperboundNivalueof1.004,whichwasnotconsidered relevantforthislowNiweldwire.Noothernewplantswereidentified thathadnotbeenpreviously identified bytheWOGRPVDATAdatabase.
CEOG-Reactor VesselWorkingGroup:TheCombustion Engineering OwnersGroup(CEOG)hasformedtheReactorVesselWorkingGroup(RVWG)toaddresstheissueofweldchemistry variability forCEfabricated reactorvesselwelds.This"ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 1Page3of7taskwillfocusoncompiling datafromoriginalfabrication records,researchdatafiles,andlogbookscompiledbyCE.Inaddition, thetaskwillcompiledatafromsurveillance testandsupplemental testresultsbyCE,otherNSSSsuppliers, andutilities.
Therelevantdatawillbeusedtodetermine abestestimatechemistry foreachweldheatfabricated byCE.FPLisparticipating inthiseffortwhichisexpectedtotakeaminimumof18monthstocomplete~
plusanadditional 6monthstoassessthesignificance ofthenewdata.Thelengthofthisscheduledoesnotimpactsafetybecausethelimitingweldheat(305424)forSt.LucieUnit1hasalreadybeendetermined usingthebestestimatechemistry ofallthecurrently available andrelevantdata.Theremaining weldsarelowNiweldsandwouldnotbecomemorelimitingthanheat305424,therefore, wouldnotbedirectly"pertinent" toevaluation ofreactorvesselintegrity forSt.LucieUnit1.Responses toNRCGL92-01Supplement 17Questions:
NRCReuest1:Provideadescription ofthoseactionstakenorplannedtolocatealldatarelevanttothedetermination ofRPVintegrity, oranexplanation ofwhytheexistingdatabaseisconsidered completeaspreviously submitted.
FPLResonse1:TheSt.LucieUnit1RVPisweldlimitedforthedetermination ofreactorvesselintegrity.
Thelimitingmaterialfordetermining RPVIntegrity isthebeltlineweldheat305424withanEOLRT~3of227'F.Thebestestimatechemistry forthisweldheatwasdetermined fromallavailable data,including theoriginal, CEweldqualification andasisterCEOwnersGroupLetterCEOG-95-390, "CEOGReactorVesselWorkingGroupActivities...",
DavidSagertoU.S.NuclearRegulatory Commission, July27,1995.GenericLetter(GL)92-01,Revision1,Supplement 1"ReactorVesselStructural Integrity",NRC toallholdersoflicensednuclearpowerreactors; May19,1995."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 1Page4of7plantsurveillance weld,andisconsidered completeaspreviously submitted
.Thegirthweldisheat90136andisthesurveillance weldforSt.LucieUnit1.ThisweldhasanEOLRTFof80'F'uetothelowNicontent.Athroughsectionchemicalanalysiswasperformed onthissurveillance testblockbytheCEOG.ThisanalysismatchedtheCucontentpreviously reportedandconfirmed thelowNicontentoftheweld,however,notall"relevant" datahasbeenusedtodetermine thebestestimatechemistry forthisheat.Onceallthedataisusedtodetermine thebestestimatechemistry forheat90136,asdescribed above'ntheCEOGRVWG,itwillnotbecomemorelimitingthanthecurrentlimitingweldheatforSt.LucieUnit1.InitialuppershelfenergiesandRT>>Tvalueshavebeendetermined fromthesurveillance weldsforbothheats305424and90136.Thisinformation hasbeenprovidedintheearlierresponses toGL92-01"~".Theremaining beltlineheats34B009andA8746wereusedintheintermediate shellaxialweldsandhaveanEOLRT~of120'F".Theseheatshavepreviously beenstudiedbytheCEOGtodetermine thebestestimatechemistry andwereupdatedintheresponsetoGL92-01RAI".Nonewinformation isexpectedthatcouldmaketheseweldsmorelimitingthanheat305424.10FPLLetter,L-92-189, "St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,Response",
W.H.BohlketoNRC,July1,1992."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, 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,ResponsetoRequestforAdditional Information (RAI)",D.A.SagertoNRC,November15,1993."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.FPLLetter,L-93-286, "St.LucieUnits1and2DocketNo.50-335and50-389,GenericLetter92-01,Revision1,ResponsetoRequestforAdditional Information (RAI)",D.A.SagertoNRC,November15,1993.
JII Attachment 1Page5of7FPLisparticipating intheCEOGRVWGefforttoaddresstheissueofweldchemistry variability forCEfabricated reactorvesselwelds.Thistaskasdescribed abovewillcompileallrelevantdatatodetermine abestestimatechemistry foreachweldheatfabricated byCE.Thescheduled completion ofthiseffortisaminimumof18monthsplusanadditional 6months(September 1,1997)toassessthesignificance ofthenewdata.Thelengthofthisscheduledoesnotimpactsafetybecausethelimitingweldheat(305424)forSt.LucieUnit1hasalreadybeendetermined usingthebestestimatechemistry ofallthecurrently available relevantdata.Theremaining weldsarelowNiweldsandwouldnotbecomemorelimitingthanheat305424.Therefore, theremaining weldswouldnotbedirectly"pertinent" toevaluation ofreactorvesselintegrity forSt.LucieUnit1.NRCReuest2:Provideanassessment ofanychangeinbest-estimate chemistry basedonconsideration ofallrelevantdata.FPLResonse2:Thelimitingmaterialfordetermining RPVintegrity forSt.LucieUnit1isthebeltlineweld305424.AreviewoftheNRCRVZDandWOGRPVDATAdatabases shownoadditional datathathasnotalreadybeenusedindetermining thebestestimatechemistry beingusedforSt.LucieUnit1.Sincenochangeisexpectedtothebestestimatechemistry fortheSt.LucieUnit1limitingreactorvesselweldmaterial, therewillbenoimpactrelativetoreactorvesselstructural integrity.
Shouldanynewbestestimatechemistry isidentified fortheSt.LucieUnit1beltlinematerials, itwillbereportedbySeptember 1,1997,afterthecompletion oftheCEOGRVWGtaskdescribed above.NRCReuest3:Provideadetermination oftheneedforuseoftheratioprocedure inaccordance withtheestablished Position2.1ofRegulatory Guide1.99,Revision2,forthoselicensees thatusesurveillance datatoprovideabasisfortheRPVintegrity evaluation.
FPLResonse3:Thedetermination ofvesselintegrity fortheSt.LucieUnit1reactorvesselmaterials hasbeenmadeusingthebest Attachment 1Page6of7estimatechemistry withouttheuseofsurveillance data,therefore theratioprocedure isnotused.NRCReuest4:Submitawrittenreportproviding anynewlyacquireddataasspecified aboveand(1)theresultsofanynecessary revisions totheevaluation ofRPV"integrity inaccordance withtherequirements of10CFR50.60,10CFR50.61,Appendices GandHto10CFRPart50,andanypotential impactontheLTOPorP/TlimitsintheTechnical Specifications or(2)acertification thatpreviously submitted evaluations remainvalid.Revisedevaluations andcertifications shouldincludeconsideration ofPosition2.1ofRegulatory Guide1.99,Revision2,asapplicable, andanynewdata.FPLResonse4:Thepreviously submitted LTOPanalysisandP/TlimitscurvesintheTechnical Specifications werebasedontheSt.LucieUnit1limitingweld305424whichhadthehighest1/4Tand3/4TadjustedRT>>Yfortheperiodofapplicability.
Sincenonewinformation iscurrently available forthelimitingweldmaterials thisanalysisremainsvalid.Theuppershelfenergy(USE)valuesfortheweldmaterials reportedfortheSt.LucieUnit1reactorvesselareallinaccordance withthe10CFR50AppendixGlimitof50ft-lbsatEOLaspreviously submitted intheresponses totheGL92-01'andarebasedonactualsurveillance dataorconservative genericestimates.
==
Conclusion:==
ThecompleteresponsetotheNRCGenericLetter92-01supplement 1questions 1through4areprovidedabove.ThisGLisconsidered completeforSt.LucieUnit1sincethelimitingmaterial(weldheat305424)bestestimatechemistry wasdetermined fromallknownindustryavailable dataforthatheat.However,FPLisparticipating intheCEOGRVWGtasktodetermine bestestimateFPLLetter,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,ResponsetoRequestforAdditional Information (RAI)",D.A.SagertoNRC,November15,1993.
w~I Attachment 1Page7of7chemistry valuesforallCEweldmaterials.
Anychangesinbestestimatechemistry forthenon-limiting reactorvesselbeltlineweldswillbereportedbySeptember 1,1997.Theschedulefordetermining changestothebestestimateweldchemistry forthenon-limiting welds(weldheats90136and34B009/A8746) shouldhavenoeffectondetermination ofreactorvesselintegrity duetothelowNicontentandsincetheyaregreaterthan100'FbelowtheEOLRT~'fthelimitingweldheat305424."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 2Page3of5Responses toNRCGL92-01Supplement 1Questions:
NRCReuest1:Provideadescription ofthoseactionstakenorplannedtolocatealldatarelevanttothedetermination ofRPVIntegrity, oranexplanation ofwhytheexistingdatabaseisconsidered completeaspreviously submitted.
FPLResonse1:TheSt.LucieUnit2ReactorVesselisalowCulowNiweldfabricated vessel.Thelimitingmaterialfordetermining RPVIntegrity isthebeltlineplatematerial.
AreviewoftheNRCRVIDandWOGRPVDATAdatabases shownoidentical matchofheatsforthelimitingplatematerials, therefore, nonewdataisexpected.
Theoriginaldatasubmitted intheresponses toGL92-0167forthislimitingplatematerialwasbasedonactual,CMTRdataandcompletematerialpropertytests.Therefore, thedataisconsidered completeaspreviously submitted.
ThemostlimitingweldmaterialhasanEOLRT~of47'Fwhichisgreaterthan200'Fbelowthe10CFR50.61screening criteriaandgreaterthan100Fbelowthelimitingplate8.Theweldmaterialistherefore notpertinent indeterminations ofreactorvesselintegrity.
Additionally, thethreesisterplantsidentified ashavingidentical weldheatsasSt.LucieUnit2arenotlimitedbytheseweldheatsbutareallplatelimitedandhaveEOLRT~Bvaluesover100'Fbelowthe10CFR50.61screening criteria.
GenericLetter(GL)92-01,Revision1,Supplement 1"ReactorVesselStructural Integrity",
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,ResponsetoRequestforAdditional Information (RAI)",D.A.SagertoNRC,November15,1993."ReactorVessel,Integrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
St.'Lucie Units1and2L-95-232DocketNos.50-335and50-389ReactorVesselStructural Integrity GenericLetter92-01Revision1SulementResonseAttachment 2ResponsetoNRCGL92-01Revision1Supplement 1ForSt.LucieUnit2 At' Attachment 2Page1of5ResponsetoNRCGL92-01Supplement 1St.LucieUnit2Background TheStLucieUnit2reactorpressurevessel(RPV)wasdesignedandmanufactured byCombustion Engineering Inc.(CE).
TheRPVwasfabricated aftertheeffectsofcopper(Cu)onirradiation embrittlement wereknown.Theweldwiresusedtofabricate thebeltlineweldswerelowinCucontentandwerenotCucoated.TheweldwireswerealsolowinNickel(Ni)contentandtheweldsdidnotutilizesupplemental coldNiwireadditions duringfabrication.
WithlowCuandlowNiweldsfabricated withoutcoldwireNiadditions, thechemicalvariability isverylowandcomparable tothatofplatematerial.
LimitingRPVMaterials forEOLRT~,P/TlimitcurvesandLTOP.AsaresultofthelowCuandlowNiwelds,theStLucieUnit2RPVisplatelimitedfor10CFR50.61RT~atendoflife(EOL)andisplatecontrolling forthecurrentpressuretemperature (P/T)limitcurvesandlowtemperature overpressure protection (LTOP)analysis.
FortheSt.LucieUnit2RPV:thehighestRT~,atendoflicense(EOL)is163'F(morethan100'Fbelowthescreening criteria),
forplatematerial; thehighestRT~,atEOLis47'forbeltlineweldmaterialsi.
WithlowEOLRTmvaluesandplatelimitingcriticalmaterial, noadditional information onournon-Cucoatednon-limitingbeltlineweldswillbe"relevant" fordetermining thestructural integrity ofthereactorvesselsinceitiscontrolled bytheplateproperties.
Activities toIdentifRelevantDataandSourcesWestinghouse OwnersGroupRPVDATADatabase:
TheWestinghouse OwnersGroup(WOG)Materials andChemistry Subcommittee hascompiledadatabase, RPVDATA,ofallinformation relevanttoreactorvesselintegrity thatisavailable fromWestinghouse ElectricCorporation docketedNRCGenericLetter(GL)92-01responses andpreviousEPRIdatabases onreactorvesselintegrity.
Theinformation includedinthedatabaseisfromoriginalfabrication records,reactorvesselsurveillance programtesting,andothersupplemental testingperformed byWestinghouse.
FPLhasreviewedthisdatabasetodetermine other"sister"plantsthatcontainidentical reactorvesselweldheatsandthatwouldbe"ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 2Page2of5relevanttothedetermination ofreactorvesselintegrity forSt.LucieUnit2.Threeplantswereidentified ashavingidentical weldheatsbutnoplantswereidentified ashavingidentical plateheats.NRCReactorVesselIntegrity Database(RVID):FPLreceivedtheinitialpublicissueoftheNRCReactorVesselIntegrity Database2 (RVID).FPLhasreviewedthisdatabasetoidentifyadditional "sister"plantsthatcontainidentical reactorvesselweldheatsandthatwouldberelevanttothedetermination ofreactorvesselintegrity forSt.LucieUnit2.Noplantswereidentified otherthanthethreepreviously identified bytheWOGRPVDATAdatabase.
CEOG-Reactor VesselWorkingGroup:TheCombustion Engineering OwnersGroup(CEOG)hasformedtheReactorVesselWorkingGroup(RVWG)toaddresstheissueofweldchemistry variability forCEfabricated reactorvesselwelds.Thistaskwillfocusoncompiling datafromoriginalfabrication records,researchdatafiles,andlogbookscompiledbyCE.Inaddition, thetaskwillcompiledatafromsurveillance test,supplemental testresultsby.CE,otherNSSSsuppliers, andutilities.
Therelevantdatawillbeusedtodetermine abestestimatechemistry foreachweldheatfabricated byCE.FPLisparticipating inthiseffortwhichisexpectedtotakeaminimumof18monthstocomplete'lus anadditional 6monthstoassessthesignificance ofanynewdata.Thelengthofthisscheduledoesnotimpactsafetybecausetheweldmaterials arenotlimitingandarenotdirectly"pertinent" toevaluation ofreactorvesselintegrity.
Infact,theSt.LucieUnit2reactorvesselbeltlineweldmaterials willremaingreaterthan200FbelowthePTSscreening limitof270Fasdocumented intheRVID4."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.CEOwnersGroupLetterCEOG-95-390, "CEOGReactorVesselWorkingGroupActivities...",
DavidSagertoU.S.NuclearRegulatory Commission, July27,1995."ReactorVesselIntegrity Database-Version1.1",U.S.NuclearRegulatory Commission, July1995.
Attachment 2Page4of5NRCReuest2:Provideanassessment ofanychangeinbest-estimate chemistry basedonconsideration ofallrelevantdata.FPLResonse2:Thelimitingmaterialfordetermining RPVintegrity isthebeltlineplatematerial.
AreviewoftheNRCRVIDandWOGRPVDATAdatabases show.noidentical matchofheatsforthelimitingplatematerials, therefore, nonewdataisexpected.
Sincethereisnochangetothebestestimatechemistry fortheSt.LucieUnit2limitingreactorvesselplatematerial, therewillbenoimpactrelativetoreactorvesselstructural integrity.
NRCReuest3:Provideadetermination oftheneedforuseoftheratioprocedure inaccordance withtheestablished Position2.1ofRegulatory Guide1.99,Revision2,forthoselicensees thatusesurveillance datatoprovideabasisfortheRPVintegrity evaluation.
FPLResonse3:Thedetermination ofvesselintegrity fortheSt.LucieUnit2reactorvesselmaterials hasbeenmadeusingthebestestimatechemistry withouttheuseofsurveillance data.Onlyonesurveillance capsulehasbeentestedfromthisunitandtherefore position2andspecifically position2.1isnotapplicable fortheSt.LucieUnit2.NRCReuest4:Submitawrittenreportproviding anynewlyacquireddataasspecified aboveand(1)theresultsofanynecessary revisions totheevaluation ofRPVintegrity inaccordance withtherequirements of10CFR50.60,10CFR50.61,Appendices GandHto10CFRPart50,andanypotential impactontheLTOPorP/TlimitsintheTechnical Specifications or(2)acertification thatpreviously submitted evaluations remainvalid.Revisedevaluations andcertifications shouldincludeconsideration ofPosition2.1ofRegulatory Guide1.99,Revision2,asapplicable, andanynewdata.
Attachment 2Page5of5FPLResonse4:Thepreviously submitted LTOPanalysisandP/TlimitscurvesintheTechnical Specifications werebasedontheSt.LucieUnit2limitingintermediate shellplateM-605-1(A-8490-2).
Thisplatehadthehighest1/4Tand3/4TadjustedRT~Yfortheperiodofapplicability.
Sincenonewinformation isavailable forthelimitingplatematerials, thepreviously submitted analysisremainsvalid.Theuppershelfenergyvaluesfortheweldmaterials reportedfortheSt.LucieUnit2reactorvesselareallinaccordance withthe10CFR50AppendixGlimitof50ft-lbsatEOLaspreviously submitted intheresponsetotheGL92-01andareidentical orconservatively lowerthanthosevaluesreportedbythethreesisterplantsintheRVID.Conclusion:
ThecompleteresponsetoNRCGenericLetter92-01,Revision1,Supplement 1~,questions 1through4areprovidedabove.TheresponsetothisGenericLetterisconsidered completeforSt.LucieUnit2.SinceFPLisparticipating intheCEOGRVWGtasktodetermine best.estimate chemistry valuesforweldmaterials, anychangesinbestestimatechemistry forthenon-limiting reactorvesselbeltlineweldswillbereportedbySeptember 1,1997.Theschedulefordetermining changestothebestestimateweldchemistry willhavenoeffectondetermination ofreactorvesselintegrity.
Theseweldsarenotlimitingmaterials, arebothlowinCuandNi,andaregreaterthan200'Fbelowthe10CFR50.61screening criteriaatEOL.GenericLetter(GL)92-01,Revision1,Supplement 1"ReactorVesselStructural Integrity,"
NRCtoallholdersoflicensednuclearpowerreactors; May19,1995.