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.IMYCCELERATED RIDSPROCESSING)

REGULATORY INFORMATION DXSTRIBUTION SYSTEM(RIDS)DOCKETI05000244ACCESSION NBR:9407120310 DOC.DATE:94/06/30NOTARIZED:

NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.

Rochester Gas6ElectricCorp.RECIP.NAME RECIPXENT AFFILXATION JOHNSON,A.R.

DocumentControlBranch(Document ControlDesk)PNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).

05000244R

SUBJECT:

Forwardssummaryforpressurized thermalshockcalculation reGL92-01closout.IDISTRIBUTION CODE:A028DCOPXESRECEIVED:LTR ENCLSIZE:TTTLE:GenericLetter92-01Responses (ReactorVesselStructural Tntegrrty 1RECIPIENT IDCODE/NAME PD1-3PDINTERNAL:

NRR/DE/EMCB NRR/DRPE/PDI-1 NUDOCS-ABSTRACT OGC/HDS3RES/DE/MEB EXTERNAL:

NRCPDRCOPIESLTTRENCL11221111101111RECIPIENT IDCODE/NAME JOHNSON,A NRR/DORS/OGCB NRR/DRPWD/CBREGFIL01NSICCOPIESLTTRENCL221111101111D0CUNOTETOALLeRIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSI'ORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR15ENCL13

't1e ANDROCHESTER GASANDE'IECTRIC CORPORATION

~89FASTAVENUE,ROCHESTER, N.Y.146d9-0001 ROBERTC.MECREDYVicePrertdent June30,1994CtnnaNuctearProduction U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-3Washington, D.C.20555AREACODE7T6546-2700

Subject:

ResponsetoGenericLetter92-01RequestforClosureInformation R.E.GinnaNuclearPowerPlantDocketNo.50-244Ref.(a):LetterfromA.R.Johnson(NRC)toR.C.Mecredy(RG&E),GenericLetter(GL)92-01,Revision1,ReactorStructural Integrity",

datedApril12,1994(b):LetterfromR.C.Mecredy(RG&E)toA.R.Johnson(NRC),"GenericLetter92-01Revision1ReactorStructural Integrity ResponseforAdditional Information",

datedMay16,1994(c):LetterfromR.C.Mecredy(RG&E)toA.R.Johnson(NRC),"Analysis ofCapsule"S"fromtheRochester GasandElectricCorporation R.E.GinnaReactorVesselWCAP13902December1993",datedMarch29,1994

DearMr.Johnson:

Thereference (a)letterrequested information tosupportcloseoutofissuesaddressed inGenericLetter92-01.Specifically, itwasrequested thatdatalistedintwotablesattachedinthatreference beevaluated andupdated.asrequired.

Rochester GasandElectricCorporation (RG&E)provideditsinitialresponseinreference (b).Itistheintent'of thislettertocompleteRG&E'sresponse.

Thedataapplicable totheR.E.GinnareactorvesselareprovidedinTables1and2attached.,

Thesedatareflectresultsderivedfromthelatestsurveillance capsule(ref.c)andinformation derivedthroughtheB&WOwnersGroup.Theattacheddatasupersedes thedataprovidedinreference (b).t;TheB&WOwners'Grouphas,providedTopicalReportsBAW-2178PA andBAW-2192PA whichpresentequivalent marginanalysestoaddressconditions oflowupper-shelf energy.ThoughtheR.E.Ginnareactorvesseldoesnot,demonstrate lowuppershelfenergyforitslimitingSA-847'eld

material, RG&Eendorsestheresultsandconclusions ggesented inthesereportsandmaychoosetoapply9407120310 940M'0PDRADOCK05000244PPDRpgrP4ZD//K/A~~T ggS',

lrf thesereportstotheGinnareactorvesselshouldconditions laterwarrant.Verytrulyyours,RobertC.MecredyREJ5339xc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector Table1.R.E.Ginna--DataSummarforPressurized ThermalShockCalculation BeltlineMaterialUpperShellForgingInterm.ShellForgingHeatNo.123P118VA1 1258255VA1 ISNeut.FluenceatEOL/EFPY369E+183.68E+19s IRTN~F+305(a)=0)+203(ai=o)MethodofDetermin.

IRTyppPlantSpecificPlantSpecificChemistry Factor223.616.26MethodofDetermin.

CFRG1.99Table2Calculated

%CuO.3S'07mLowerShellForgingSA-1101UStoISCirc.WeldSA-847IStoLSCirc.WeldSA-848LStoDutch.Circ.Weld125P666VA1 7124961782617823.68E+19i 3.72E+18i 3.68E+19~

N/A+40'.(a)=0)+10(a)=0)55(a,=19.7)5$(a,=19.7)PlantSpecificPlantSpecificGenericGeneric27.80173.56714719s14719sCalculated 0.05'alculated 0.26"Calculated 0.25"Calculated 0.25>>

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

Subject:

ReactorVesselStructural Integrity, 10CFR50.54(f),

ResponsetoGenericLetter92-01,Revision1,R.E.GinnaNuclearPowerPlant.2.Valuesdetermined fromWCAP-13902 andWCAP-13893.

3.Valuesdetermined fromdatainMaterialTestReport.4.Valuedetermined fromdatainEPRINP-373.5.MeanvaluefromdatainBAW-1803, Revision1.6.Chemistry Factorsforforging125S255VA1 andforging125P666VA1 weredetermined usingREGsurveillance dataasreportedinWCAP-13902 andWCAP13893.7.Chemistry FactorforweldmetalSA-1101wasdetermined usingTP3surveillance dataforweldmetalSA-1101.TheTP330ft-lbtransition temperature shiftdatawereobtainedfromBAW-1803, Revision1,whilethefluencedataforthecapsuleswereobtainedfromBAW-1803, Revision1andNUREGCR-3319,Revision1.8.Chemistry FactorforweldmetalSA-847andweldmetalSA-848wasdetermined usingBGWOGsurveillance dataforweldmetalSA-1135andREGsurveillance dataforweldmetalSA-1036.Thesesurveillance weldswerefabricated withthesamewireheatasweldmetalSA-847andweldmetalSA-848.TheBGWOGsurveillance datawereobtainedfromBAW-1803, Revision1.TheREGsurveillance datawereobtainedfromWCAP-13902.

9.Nodataavailable forthismaterial, therefore, 0.35%isspecified asdefinedinRegulatory Guide1.99,Revision2~10.ValuesobtainedfromBAW-2150.

11.ValuesobtainedfromBAW-2121P.

12.ValuesobtainedfromBAW-1500.

Table2.R.E.Ginna--DataSummarforUer-ShelfEnerCalculation BeltlineMaterialUpperShellForgingInterm.ShellForgingLowerShellForgingSA-1101UStoISCirc.WeldSA-847IStoLSCirc.WeldSA-848LStoDutch.Circ.WeldHeatNo.123P118VA1 1258255VA1 125P666VA1 712496178261782MaterialTypeSA-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-ShelfEnerCalculation NOTES:I1.Valuesdetermined usingRegulatory Guide1.99,Revision2,guidelines.

2.USEissuecoveredbytheapprovedequivalent marginsanalysisintheTopicalReportsBAW-2192PA andBAW-2178PA.

3.ValuesobtainedfromBAW-2192PA 4.Notapplicable duetofluencebeingbelowthreshold 5.Unirradiated USEis65%oftheUSEfromalongitudinal orientedspecimens asdefinedinMTEB5-2.6.Unirradiated USEisdetermined usingdatafromotherplantswithsimilarmaterials tothebeltlinematerial(BAW-1803, Table3-5).7.Valuesdetermined usingcapsulesurveillance resultsWCAP-13902 N~4PC