ML17264A194

Provides Pressurized Thermal Shock Assessment for Reactor Pressure Vessel Limiting Circumferential Weld for Review & Approval

ML17264A194
Person / Time
Site:	Ginna
Issue date:	10/11/1995
From:	MERCREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	JOHNSON A R NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510180239
Download: ML17264A194 (9)

Text

I7PRIORITY3y(ACCELERATEDRZDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9510180239DOC.DATE:95/10/11NOTARIZED:NOFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterGAUTH.NAMEAUTHORAFFILIATIONMERCREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONJOHNSON,A.R.

SUBJECT:

Providespressurizedthermalshockassessmentforreactorpressurevessellimitingcircumferentialweldforreview&approval.DISTRIBUTIONCODE:A049DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:ThermalShocktoReactorVesselDOCKET05000244P0RNOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244RECIPIENT1DCODE/NAMEPD1-1PDINTERNAL:AEOD/DOANRR/DEOGC/HDS3RES/DE/MEB/MESRES/DSR/RPSBRGN1ADMSTREXTERNAL:NOAC~+t'g5'3/~iCOPIESLTTRENCL11101011111111RECIPIENTIDCODE/NAMEJOHNSOF1NRR/DSSA/SRXBRESDERES/DSIR/EIBRES/DST/PRABNRCPDRCOPIESLTTRENCL1'1111111111NNOTE,TOALL"RZDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D8(415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEEDITOTAL,NUMBEROFCOPIESREQUIRED:LTTR15ENCL13 04 ANDROCHE/TERGASANDELECTRICCORPORATION~89FASTAYENLIE,ROCHESTER,N.Y.Idio-000IAREACODE716Sd6-2700ROBERTC.MECREDYVicePresidentNvcleorOperotions,October11,1995U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-1Washington,D.C.20555

Subject:

PressurizedThermalShockAssessmentforGinnaReactorVesselR.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromAllenR.Johnson(NRC),toRobertC.Mecredy(RG&E),"SummaryofMeetingwithRochesterGasandElectricCorporationonMay16,1995-PressurizerThermalShockAssessmentofReactorVessels,"datedJune5,1995.

DearMr.Johnson:

ThepurposeofthiscorrespondenceistoprovideRochesterGasandElectricCorporation's(RG&E)pressurizedthermalshock(PTS)assessmentfortheR.E.Ginnareactorpressurevessel(RPV)limitingcircumferentialweldforyourreviewandapproval.Theassessment,aspresentedintheattached,isprovidedinresponsetothereferencedletterandisbasedontheguidanceprovidedin10CFR50.61andRegulatoryGuide1.99revision2.Asprovidedforbythisguidance,theRG&EassessmentincludestheuseoftheresultsoftheRPVsurveillancecapsuleprogram.AstheattachedPTSdeterminationshows,theGinnaRPVcanbeexpectedtooperatepasttheendoflicense(EOL)of2009withoutexceedingthePTSscreeningcriterionof10CFR50.61forthelimitingcaseweld.Verytrulyyours,RobertC.MecredyREJtl,393i.70jgJ95i0180239'st5lOiiPDRADOCK05000244PPDRpyre+p8'K/prtl.

xcMr'.AllenR.Johnson(MailStop14B2)ProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATTACHMENTR.E.GinnaReactorVesselEOLPTSAssessmentDiscussionThepurposeofthisassessmentistoshowthattheexpectedreferencetemperaturePTS(RT~,)atEOLfortheGinnaRPVlimitingweldremainsbelowthescreeningcriteriawhenusingsurveillanceprogramdata.ThelimitingmaterialfortheGinnaRPVistheintermediatetolowershellweldhavingweldwireheatnumber61782.ThematerialusedforthesurveillancecapsuleprogramisweldwireSA-1036havingmaterialheatnumber61782whichhasbeendeterminedtobeacceptableforuseasasurveillancematerial+.ThedeterminationofthereferencetemperatureforRT~fortheRPV-PTSassessmentusesthe10CFR50.61(b)(3)plantspecificsurveillanceprogrammethodwhichincludesthesurveillancedataadjustmentsperRegulatoryGuide1.99revision2position2,where:(1)RTpgg=I+M+aRTggg(2)I=initialRT~~~(4)~RT~Y=referencetemperatureshift">

8II.MaterialValuesUsedA.RPVmaterialheat617821~I=themeanofthetestvaluesi=1nwhere:1oF(()1i=-38'F)nn=2~I=-19.5'Fando',=18.5'F2~3~4~5~fluence9EOL=3.68E19("Chemistry(')Cu=~25Ni=.54CF('):167.6oFM=2ltr~+e,~wheree,=18.5'F(II.A.1)and14oF(4)~M=46.4'FB.SurveillanceCapsulesWeldSA10361~~RTNDVRTS5.56E181.15E191.97E193.87E19140oF165oF150oF205oF2~3~MeanValueChemistry+(')+:Cu=.214Ni=.505CF>>:150'oF IXX.Ca'lculationsA.Chemistryfactorratio<4>:CFofRPV(II.A.4above)-:CFofcapsule(II.B.3above)~Ratio=167.6=1.11150.9B.BestfitCF<"1.Summingadjustedcapsule~RTNDTAdjustedVRTS140165150205X1.11X1.11X1.11X1.11155.4183.2166.5227.62~DeterminesumoffluencefactorxadjustedaRT~~wherefluencefactor(ff)=f<"~CasuleFFAdjusted~RTmProductVRTS0.8361.0391.1851.349155.4183.2166.5227.6sum=129.9.190.3197.3307.824.53~Summingsquaresofcapsulesfluencefactors(FF)forusingfluencefactorvaluesfromII.B.1:~casuleVRTS0.8361.0391.1851.349sum=0.6991.0801.4051.8205.0044SumofadjustedaRTNT-:sumofsquaresoffluence824.5(XII.B.2)-:5.004(III.B.3)=164.8F C.'RT~~forsurveillancefit9EOLEOLgRT~~(CF)frogs-oioi~owheref=3.68(I.B.4)x3.68'164.8F)(1.338)=220.5D.RTrrs~EOLRT~=I+M+aRTNg~-19~5F(II.A.1)+46.4F(II.A.5)+220.5(III.C)247.4oFIV.ResultsTheRT~valueatEOLfortheR.E.Ginnavesselis247.4F.Thisis52.64FbelowthePTSscreeningcriteriondescribedin10CFR50.61.

REFERENCES:

(1)BAW1803Revision1,"CorrelationsforPredictingtheEffectsofNeutronRadiationonLinde80Submerged-ArcWelds."(2)WCAP-13902,"AnalysisofCapsuleSfromtheRochesterGasandElectricCorporationR.e.GinnaReactorVesselRadiationSurveillanceProgram,"datedDecember1993.(3)CodeofFederalRegulations,10CFR50.61,"FractureToughnessRequirementsforProtectionAgainstPressurizedThermalShockEvents."(4)RegulatoryGuide1.99,revision2,"RadiationEmbrittlementofReactorVesselMaterials."(5)BAW1920P,"AnalysisofCapsuleDB1-LG1,"October1986.(6)LettertoRogerW.KoberfromMortonB.Fairtile,"SafetyEvaluationbytheOfficeofNuclearReactorRegulationRelatedtoAmendmentNo.15toFacilityOperatingLicenseNo.DPR-18RochesterGasandElectricCorporationR.E.GinnaNuclearPowerPlantDocketNo.50-244,"datedJune12(1986.(7)BAW-1500,"Chemistryof177-FAB&WOwner'sGroupReactorVesselBeltlineWelds,"September1978.(8)10CFR50.61,"Fracturetoughnessrequirementsforprotectionagainstpressurizedthermalshockevents."(9)BAW-2121P,"ChemicalCompositionofB&WFabricatedReactorVesselBeltlineWelds,"April1991.