ML17263A718

Forwards Summary for Pressurized Thermal Shock Calculation Re GL 92-01 Closeout

ML17263A718
Person / Time
Site:	Ginna
Issue date:	06/30/1994
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	JOHNSON A R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
GL-92-01, GL-92-1, NUDOCS 9407120310
Download: ML17263A718 (10)

Text

PR.IC)R.IMYCCELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDXSTRIBUTIONSYSTEM(RIDS)DOCKETI05000244ACCESSIONNBR:9407120310DOC.DATE:94/06/30NOTARIZED:NOFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterGAUTH.NAMEAUTHORAFFILIATIONMECREDY,R.C.RochesterGas6ElectricCorp.RECIP.NAMERECIPXENTAFFILXATIONJOHNSON,A.R.DocumentControlBranch(DocumentControlDesk)PNOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244R

SUBJECT:

ForwardssummaryforpressurizedthermalshockcalculationreGL92-01closout.IDISTRIBUTIONCODE:A028DCOPXESRECEIVED:LTRENCLSIZE:TTTLE:GenericLetter92-01Responses(ReactorVesselStructuralTntegrrty1RECIPIENTIDCODE/NAMEPD1-3PDINTERNAL:NRR/DE/EMCBNRR/DRPE/PDI-1NUDOCS-ABSTRACTOGC/HDS3RES/DE/MEBEXTERNAL:NRCPDRCOPIESLTTRENCL11221111101111RECIPIENTIDCODE/NAMEJOHNSON,ANRR/DORS/OGCBNRR/DRPWD/CBREGFIL01NSICCOPIESLTTRENCL221111101111D0CUNOTETOALLeRIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSI'ORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR15ENCL13

't1e ANDROCHESTERGASANDE'IECTRICCORPORATION~89FASTAVENUE,ROCHESTER,N.Y.146d9-0001ROBERTC.MECREDYVicePrertdentJune30,1994CtnnaNuctearProductionU.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-3Washington,D.C.20555AREACODE7T6546-2700

Subject:

ResponsetoGenericLetter92-01RequestforClosureInformationR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromA.R.Johnson(NRC)toR.C.Mecredy(RG&E),GenericLetter(GL)92-01,Revision1,ReactorStructuralIntegrity",datedApril12,1994(b):LetterfromR.C.Mecredy(RG&E)toA.R.Johnson(NRC),"GenericLetter92-01Revision1ReactorStructuralIntegrityResponseforAdditionalInformation",datedMay16,1994(c):LetterfromR.C.Mecredy(RG&E)toA.R.Johnson(NRC),"AnalysisofCapsule"S"fromtheRochesterGasandElectricCorporationR.E.GinnaReactorVesselWCAP13902December1993",datedMarch29,1994

DearMr.Johnson:

Thereference(a)letterrequestedinformationtosupportcloseoutofissuesaddressedinGenericLetter92-01.Specifically,itwasrequestedthatdatalistedintwotablesattachedinthatreferencebeevaluatedandupdated.asrequired.RochesterGasandElectricCorporation(RG&E)provideditsinitialresponseinreference(b).Itistheintent'ofthislettertocompleteRG&E'sresponse.ThedataapplicabletotheR.E.GinnareactorvesselareprovidedinTables1and2attached.,Thesedatareflectresultsderivedfromthelatestsurveillancecapsule(ref.c)andinformationderivedthroughtheB&WOwnersGroup.Theattacheddatasupersedesthedataprovidedinreference(b).t;TheB&WOwners'Grouphas,providedTopicalReportsBAW-2178PAandBAW-2192PAwhichpresentequivalentmarginanalysestoaddressconditionsoflowupper-shelfenergy.ThoughtheR.E.Ginnareactorvesseldoesnot,demonstratelowuppershelfenergyforitslimitingSA-847'eldmaterial,RG&Eendorsestheresultsandconclusionsggesentedinthesereportsandmaychoosetoapply9407120310940M'0PDRADOCK05000244PPDRpgrP4ZD//K/A~~TggS',

lrf thesereportstotheGinnareactorvesselshouldconditionslaterwarrant.Verytrulyyours,RobertC.MecredyREJ5339xc:U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector Table1.R.E.Ginna--DataSummarforPressurizedThermalShockCalculationBeltlineMaterialUpperShellForgingInterm.ShellForgingHeatNo.123P118VA11258255VA1ISNeut.FluenceatEOL/EFPY369E+183.68E+19sIRTN~F+305(a)=0)+203(ai=o)MethodofDetermin.IRTyppPlantSpecificPlantSpecificChemistryFactor223.616.26MethodofDetermin.CFRG1.99Table2Calculated%CuO.3S'07mLowerShellForgingSA-1101UStoISCirc.WeldSA-847IStoLSCirc.WeldSA-848LStoDutch.Circ.Weld125P666VA17124961782617823.68E+19i3.72E+18i3.68E+19~N/A+40'.(a)=0)+10(a)=0)55(a,=19.7)5$(a,=19.7)PlantSpecificPlantSpecificGenericGeneric27.80173.56714719s14719sCalculated0.05'alculated0.26"Calculated0.25"Calculated0.25>>

Table1.cont.R.E.Ginna--DataSummarforPressurizedThermalShockCalculationsNOTES:1.ValuesfromJuly2,1992letterfromR.C.Mecredy(RGGE)toA.R.Johnson(USNRC)

Subject:

ReactorVesselStructuralIntegrity,10CFR50.54(f),ResponsetoGenericLetter92-01,Revision1,R.E.GinnaNuclearPowerPlant.2.ValuesdeterminedfromWCAP-13902andWCAP-13893.3.ValuesdeterminedfromdatainMaterialTestReport.4.ValuedeterminedfromdatainEPRINP-373.5.MeanvaluefromdatainBAW-1803,Revision1.6.ChemistryFactorsforforging125S255VA1andforging125P666VA1weredeterminedusingREGsurveillancedataasreportedinWCAP-13902andWCAP13893.7.ChemistryFactorforweldmetalSA-1101wasdeterminedusingTP3surveillancedataforweldmetalSA-1101.TheTP330ft-lbtransitiontemperatureshiftdatawereobtainedfromBAW-1803,Revision1,whilethefluencedataforthecapsuleswereobtainedfromBAW-1803,Revision1andNUREGCR-3319,Revision1.8.ChemistryFactorforweldmetalSA-847andweldmetalSA-848wasdeterminedusingBGWOGsurveillancedataforweldmetalSA-1135andREGsurveillancedataforweldmetalSA-1036.ThesesurveillanceweldswerefabricatedwiththesamewireheatasweldmetalSA-847andweldmetalSA-848.TheBGWOGsurveillancedatawereobtainedfromBAW-1803,Revision1.TheREGsurveillancedatawereobtainedfromWCAP-13902.9.Nodataavailableforthismaterial,therefore,0.35%isspecifiedasdefinedinRegulatoryGuide1.99,Revision2~10.ValuesobtainedfromBAW-2150.11.ValuesobtainedfromBAW-2121P.12.ValuesobtainedfromBAW-1500.

Table2.R.E.Ginna--DataSummarforUer-ShelfEnerCalculationBeltlineMaterialUpperShellForgingInterm.ShellForgingLowerShellForgingSA-1101UStoISCirc.WeldSA-847IStoLSCirc.WeldSA-848LStoDutch.Circ.WeldHeatNo.123P118VA11258255VA1125P666VA1712496178261782MaterialTypeSA-336A508-2A508-2Linde80SAWLinde80SAWLinde80SAW1/4TUSEatEOL78.8'2.694.2'MA>50ft-lbs~N/A41/4TNeutronFluenceatEOL2.71E+18~2.49E+19'~2.49E+19'~2.71E+18~2.49E+191'1.00E+17~Unirrad.USE11791114707070MethodofDetermin.Unirrad.USEMTEB5-2:65%(Matl.Cert.)MTEB5-2~:65%(Surv.Matl.)MTEB5-2:65%Surv.Matl.Generic~Generic~Generic~

Table2.cont.R.E.Ginna--DataSummarforUer-ShelfEnerCalculationNOTES:I1.ValuesdeterminedusingRegulatoryGuide1.99,Revision2,guidelines.2.USEissuecoveredbytheapprovedequivalentmarginsanalysisintheTopicalReportsBAW-2192PAandBAW-2178PA.3.ValuesobtainedfromBAW-2192PA4.Notapplicableduetofluencebeingbelowthreshold5.UnirradiatedUSEis65%oftheUSEfromalongitudinalorientedspecimensasdefinedinMTEB5-2.6.UnirradiatedUSEisdeterminedusingdatafromotherplantswithsimilarmaterialstothebeltlinematerial(BAW-1803,Table3-5).7.ValuesdeterminedusingcapsulesurveillanceresultsWCAP-13902 N~4PC