ML17329A565

Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,Consisting of Westinghouse Topical Repts & Swri Repts.Proprietary WCAP-8047 Withheld (Ref 10CFR2.790)

ML17329A565
Person / Time
Site:	Cook
Issue date:	07/13/1992
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17329A566	List: ML17329A565 ML17329A567 ML17334B426
References
AEP:NRC:1173, GL-92-01, GL-92-1, NUDOCS 9207280249
Download: ML17329A565 (17)

Text

ACCELERATED DISTRIBUTIONDEMONSTFWTION SYSTEMREGULAT-iINFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9207280249 DOC.DATE:

92/07/13NOTARIZED:

YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.

IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.

DocumentControlBranch(Document ControlDesk)DOCKET0500031505000316

SUBJECT:

RespondstoGL92-01,rev 1rereactorvesselstrucuralintegrity.

Supporting info.IDISTRIBUTION CODE:A028DCOPIESRECEIVED:LTR ENCLSIZE:DTITLE:GenericLetter92-01Responses (ReactorVesselStructural Inegriy1SNOTES:/RECIPIENT IDCODE/NAME PD3-1LASTANG,JCOPIESLTTRENCL112.2RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11~ADINTERNAL:

NRRMCDONALDiD NUDOCS-ABSTRACT OGC/HDS2RES/DSIR/EIB EXTERNAL:

NRCPDR11011gPNSICNRR/DET/ECMB OC/LFMB'E~TEE~0122101111/I/jDQcpp-povVPjJgpp-/(q02gypp-lkff3gceP-85)~DNOTETOALL"RIDS"RECIPIENTS:

ADDITOTALNUMBEROFCOPIESREQUIRED:

LTTR14ENCL12PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDI IndianaMichiganPowerCompanyP.O.Box16631Coiumbus, OH43216RAEP:NRC:1173DonaldC.CookNuclearPlantUnits1and2DocketNo.50-315and50-316LicenseNo.DPR-58andDPR-74GENERICLETTER92-01,REVISION1REACTORVESSELSTRUCTURAL.

INTEGRITY U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyJuly13,1992

DearDr.Murley:

ThepurposeofthisletteristorespondtoGenericLetter92-01,Revision1.ThisGenericLetterwasissuedtoensurethatlicensees andpermitholdersarecomplying with10CFR50.60and10CFR50.61,andarefulfilling commitments madeinresponsetoGenericLetter88-11.Thereponsestothespecificquestions raisedinGenericLetter92-01fortheDonaldC.CookNuclearPlant,Units1and2,areprovidedintheenclosure tothisletter.Thisletterissubmitted pursuantto10CFR50.54(f)and,assuch,anoathofaffirmation isenclosed.

Sincerely, E.E.Fitzpatrick VicePresident dagEnclosure w/Attachments

~e9207280249 920713PDRADOCK050003l5PtDR~&ngi~i~

Dr.T.E.Murley2AEP:NRC:1173 cc:D.H.Williams, Jr.A.A.Blind-BridgmanJ.R.PadgettG.CharnoffNFEMSectionChiefA.B.Davis-RegionIIINRCResidentInspector

-Bridgman STATEOFOHIO)COUNTYOFFRANKLIN)

E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingResponsetoGenericLetter92-01andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief,Subscribed andsworntobeforemethisdayof19NOTARYPUBIC N

ENCLOSURE TOAEP:NRC:1173RESPONSES TOGENERICLETTER92-01QUESTIONS Enclosure toAEP:NRC:1173 AEP:NRC:1173 uestion1"Certainaddressees arerequested toprovidethefollowing information regarding AppendixHtoCFRPart50:Addressees whodonothaveasurveillance programmeetingASTME185-73,-79,or-82andwhodonothaveanintegrated surveillance programapprovedbytheNRC(seeEnclosure 2),arerequested todescribeactionstakenortobetakentoensurecompliance withAppendixHto10CFRPart50,Addressees whoplantorevisethesurveillance programtomeetAppendixHto10CFRPart50arerequested toindicatewhentherevisedprogramwillbesubmitted totheNRCstaffforreview.Ifthesurveillance programisnottoberevisedtomeetAppendixHto10CFRPart50,addressees azerequested toindicatewhentheyplantorequestanexemption fromAppendixHto10CFRPart50under10CFR50.60(b)."

Resonsetouestion1Unit1TheUnit1ReactorVesselMaterialSurveillance Programwasdeveloped inaccordance withASTME-185-70, andisdocumented inWestinghouse WCAP-8047 (Section1,page1-1).Thisreportdocuments thepre-irradiation testingofthereactorvesselmaterials andcompliance withAppendixGofASMECodeSectionIII.Webelievethatthesurveillance programnotedinWCAP-8047 isincompliance withAppendixHtoCFRpart50.AcopyofthisreportisincludedasAttachment 1.Unit2TheUnit2ReactorVesselMaterialSurveillance Programwasdeveloped inaccordance withASTME-185-73, andisdocumented inWestinghouse WCAP-8512 (Section1,page1-1).Thisreportdocuments thepre-irradiation testingofthereactorvesselmaterials andcompliance withAppendixGofASMECodeSectionIII.Webelievethatthesurveillance programnotedinWCAP-8512 isincompliance withAppendixHto10CFRpart50.AcopyofthisreportisincludedasAttachment 2.uestion2.a"Certainaddressees arerequested toprovidethefollowing information regarding AppendixGto10CFRPart50; Enclosure toAEP;NRC:1173 AEP:NRC;1173 Addressees ofplantsforwhichtheCharpyuppershelfenergyispredicted tobelessthan50foot-pounds attheendoftheirlicensesusingtheguidanceinParagraphs C.1.2orC.2.2inRegulatory Guide1.99,Revision2,arerequested toprovidetotheNRCtheCharpyuppershelfenergypredicted forDecember16,1991,andfortheendoftheircurrentlicenseforthelimitingbeltlineweldandtheplateorforgingandarerequested todescribetheactionstakenpursuanttoParagraphs IV.A.1orV.CofAppendixGto10CFRPart50,"Resonsetouestion2.aUnit1Asidentified intheUnit1CapsuleUAnalysis-WCAP 12483(Section1,page1;Section5.2,Tables5-1through5-6andFigures5-1to5-5),allmaterials exhibitanuppershelfenergylevelgreaterthan50ft-lbsforplantoperation through32effective fullpoweryears(EFPY).WCAP12483wassubmitted totheNRCwithourletterAEP:NRC:0894M datedJune20,1990andisincludedasAttachment 3.Unit2Asidentified inUnit2CapsuleXAnalysis-SWRI Report06-8888(Section1,page2;Section4.3,page36,Tables4.19-4,22 andFigures5through8),allmaterials exhibited anaverageCharpyuppershelfenergygreaterthan50ft-lbsatafluenceof1.002x10n/cmfor12EFPY.Theuppershelfenergyof50ft-lbsisnotexpectedtobeexceededbasedon32EFPYfluenceprojections (page52).SWRIReportNo.06-8888wassubmitted totheNRCwithourletterAEP;NRC:0894I datedJune11,1987andisincludedasAttachment 4.Unit2Capsule'UwasremovedinMay1992,andwillbeanalyzed.

ResultsofthisanalysiswillincludeupdatedCharpyprojections to32EFPY.uestion2.b.1"Addressees whosereactorvesselswereconstructed toanASMECodeearlierthantheSummer1972Addendaofthe1971Editionarerequested todescribetheconsideration giventothefollowing materialproperties intheirevaluations performed pursuantto10CFR50.61andParagraph III.Aof10CFRPart50,AppendixG.

Enclosure toAEP;NRC:1173 AEP:NRC:1173 TheresultsfromallCharpyanddropweighttestsforallunirradiated beltlinematerials, theunirradiated reference temperature foreachbeltlinematerial, andthemethodofdetermining theunirradiated reference temperature fromtheChazpyanddropweighttest."Resonsetouestion2.b.1Unit1TheCookNuclearPlantUnit1reactorvesselwasconstructed tothe1965Editionthrough1966WinterAddenda,CodeCases1332-2,1358,1339-2,1335,1359-1,1338-3,and1336oftheASMEBoilerandPressureVesselCode,SectionIII,ClassA.Acopyoftheapplicable UFSARpagesisincludedasAttachment 5.TheresultsoftheCharpyanddropweighttestsforallunirradiated beltlinematerials andthemethodofdetermining theirunirradiated reference temperature ispresented inWCAP8047(Section3.0),"ReactorVesselMaterialSurveillance Program."

AcopyofthisreportisincludedasAttachment 1,Unit2TheCookNuclearPlantUnit2reactorvesselwasconstructed tothe1968Editionthrough1968SummerAddenda,CodeCase1335-4oftheASMEBoilerandPressureVesselCode,SectionIII,ClassA.Acopyoftheapplicable UFSARpagesisincludedasAttachment 5.TheresultsoftheCharpyanddropweighttestsforallunirradiated beltlinematerials andthemethodofdetermining theunirradiated reference temperature ispresented inWCAP8512(Section3,0),"ReactorVesselMaterialSurveillance Program,"

Reference 2.AcopyofthisreportisincludedasAttachment 2.uestion2.b.2"Theheattreatment receivedbyallbeltlineandsurveillance materials."

Resonsetouestion2.b.2Unit1Theheattreatment receivedbyallbeltlinematerials isidentified inaletterfromJ.Tillinghast totheNRCdatedNovember7,1977,AcopyofthisletterisincludedasAttachment

6.

4 Enclosure toAEP;NRC:1173 AEP:NRC:1173Theheattreatment receivedbyallsurveillance materials isidentified inWCAP-8047 (Appendix A),andaletterfromJ.Tillinghast totheNRCdatedNovember7,1977.Copiesofthesedocuments areincludedasAttachments 1and6,respectively.

Unit2Theheattreatment receivedbyallbeltlinematerials isidentified inUnit2FSARAppendixQAmendment 77datedJuly1977.AcopyofthisdocumentisincludedasAttachment 7.Theheattreatment receivedbyallsurveillance materials isidentified intheWCAP8512(Appendix A),andUnit2FSARAppendixQAmendment 77datedJuly1977.Copiesofthesedocuments areincludedasAttachments 2and7,respectively.

uestion2.b.3"Theheatnumberforeachbeltlineplateorforgingandtheheatnumberofwireandfluxlotnumberusedtofabricate eachbeltlineweld."Resonsetouestion2.b.3Unit1Theheatnumberforeachbeltlineplateandtheheatnumberofwireandfluxlotnumberusedtofabricate eachbeltlineweldarepresented inaletterfromJ.Tillinghast totheNRCdatedNovember7,1977.AcopyofthisdocumentisincludedasAttachment 6.Additional supporting information waspreviously providedinourletterAEP:NRC:0097C datedJuly3,1979whichresponded toI&EBulletin78-12,"Atypical WeldMaterialinReactorPressureVesselWelds".AcopyofthisdocumentisincludedasAttachment 8.Unit2Theheatnumberforeachbeltlineplateandtheheatnumberofwireandfluxlotnumberusedtofabricate eachbeltlineweldarepresented inUnit2FSARAppendixQAmendment 77datedJuly1977.AcopyofthisdocumentisincludedasAttachment 7.Additionally, supporting information wasprovidedinourletterAEP:NRC:0097 datedJune1,1979whichresponded toZ&EBulletin78-12,"Atypical WeldMaterialinReactorPressureVesselWelds."AcopyofthisdocumentisincludedasAttachment

9.

~~M'L Enclosure toAEP:NRC:1173 AEP:NRC:1173uestion2.b.4"Theheatnumberforeachsurveillance plateorforgingandtheheatnumberofwireandfluxlotnumberusedtofabricate thesurveillance weld."Resonsetouestion2.b.4Unit1Theheatnumberforeachsurveillance plateandheatnumberofwireandfluxlotnumberusedtofabricate thesurveillance weldsarepresented inWCAP8047(Appendix A),aletterfromJ.Tillinghast totheNRCdatedNovember7,1977,andaletterfromWestinghouse toAEPSCdatedJune14,1985.Copiesofthesedocuments areincludedasAttachments 1,6and10,respectively.

Unit2Theheatnumberforeachsurveillance plateandheatnumberofwireandfluxlotnumberusedtofabricate thesurveillance weldsarepresented inWCAP8512(Appendix A),andUnit2FSARAppendixQAmendment 77,datedJuly1977,Copiesofthesedocuments areincludedasAttachments 2and7,respectively.

uestion2.b.5"Thechemicalcomposition, inparticular theweightinpercentofcopper,nickel,phosphorous, andsulfurforeachbeltlineandsurveillance material."

Resonsetouestion2.b.5Unit1Thechemicalcomposition foreachbeltlinematerialisidentified inaletterfromJ.Tillinghast totheNRCdatedNovember7,1977.AcopyofthisdocumentisincludedasAttachment 6.Additional supporting information waspreviously providedinourletterAEP:NRC;0097C datedJuly3,1979whichresponded toIGEBulletin78-12,"Atypical WeldMaterialinReactorPressureVesselWelds".AcopyofthisdocumentisincludedasAttachment 8.Thechemicalcomposition ofthesurveillance materialisidentified inWCAP8047(Appendix A),andinaletterfromJ.Tillinghast totheNRCdatedNovember7,1977.Copiesofthesedocuments areincludedasAttachments 1and6,respectively.

Enclosure toAEP:NRC:1173 Unit2-6-AEP:NRC:1173Thechemicalcomposition foreachbeltlinematerialisidentified inUnit2FSARAppendixQAmendment 77,datedJuly1977,AcopyofthisdocumentisincludedasAttachment 7.Additionally, supporting information wasprovidedinourletterAEP:NRC:0097 datedJune1,1979whichresponded toI&EBulletin78-12,"Atypical WeldMaterialinReactorPressureVesselWelds."AcopyofthisdocumentisincludedasAttachment 9.Thechemicalcomposition ofthesurveillance materialisidentified inWCAP8512(Appendix A),andtheUnit2FSARAppendixQAmendment 77datedJuly1977.Copiesofthesedocuments areincludedasAttachments 2and7,respectively.

uestion2.b.6"Theheatnumberofthewireusedfordetermining theweldmetalchemicalcomposition ifdifferent thanItem(3)above."Resonsetouestion2.b.6Unit1Asidentified inAttachment 6,thecircumferential girthseamweldbetweentheintermediate andlowershell(limiting weld)wasfabricated withweldwireheatnumberIP3571andLinde1092fluxlotnumber3958.Thechemicalanalysisforthiswire/flux combination hasbeenidentified inaletterfromWestinghouse toAEPSCdatedJune14,1985.ThisisincludedhereasAttachment 10.Thisletterwassubmitted totheNRCwithoursubmittal AEP:NRC:0894C.

Additional supporting information waspreviously providedinourletterAEP:NRC:0097C datedJuly3,1979whichresponded toI&EBulletin78-12,"Atypical WeldMaterialinReactorPressureVesselWelds".AcopyofthisdocumentisincludedasAttachment 8.Unit2SeeresponsetoQuestion2,b.(3)a.---'."Addressees arerequested toprovidethefollowing information regarding commitments madetorespondtoGL88-11:

Enclosure toAEP:NRC:1173 AEP:NRC:1173 Howtheembrittlement effectsofoperating atanirradiation temperature (coldlegorrecirculation suctiontemperature) below525'Fwereconsidered.

Xnparticular licensees arerequested todescribeconsideration giventodetermining theeffectoflowerirradiation temperature onthereference temperature andontheCharpyuppershelfenergy,"Resonsetouestion3.aUnit1CookNuclearPlantUnit1hasonlyoperatedatanirradiation temperature (coldleg)below525'FforCycles11and12.Theapproximate coldlegtemperature forCycles11and12was518'FandwastheresultofourReducedTemperature andPressure(RTP)programthatwasinitiated afterCycle10.TheRTPprogramwasinitiated toreducetheoperating temperatures andpressures withtheintentofreducingsteamgenerator U-tubestresscorrosion cracking.

TheRTPprogramandassociated technical specification changesweresubmitted totheNRCwithourletterAEP:NRC:1067 datedOctober14,1988,andwereapprovedinanNRCSafetyEvaluation ReportdatedJune9,1989.AcopyoftheSafetyEvaluation ReportisincludedasAttachment 11.Asidentified inSection3.10.1.2ofWCAP11902,anevaluation ofthereratingimpactonreactorvesselintegrity forneutronembrittlement wasperformed andjudgednottohaveanysignificant impacton10CFRPart50,AppendixGrequirements.

ThisisinpartduetotheuseofthemodifiedlowleakagecoredesignsinUnit1sinceCycle8,Assuch,theUnit1fluenceprojections forendofvessellifehavedecreased fromearlierpredicted values'copyoftheapplicable WCAP11902pagesazeincludedasAttachment 12.Unit2CookNuclearPlantUnit2doesnotoperateatanirradiation temperature (coldleg)below525'F.TheUnit2coldlegtemperature is541'F,asidentified intheFSAR.Acopyoftheapplicable FSARpageisincludedasAttachment 13.Additionally, modifiedlowleakagecoreshavebeenusedinUnit2fromthesecondfuelcycle.Asaresult,theUnit2fluenceprojections forendofvessellifehaveremainedwellwithinearlierprojections.

Enclosure toAEP:NRC:1173 AEP:NRC:1173 uestion3.b"Howtheirsurveillance resultsonthepredicted amountofembrittlement wereconsidered."

Resonsetouestion3.bUnit1AEPSC'sresponsetoGenericLetter88-11,"NRCPositiononRadiation Embrittlement ofReactorVesselMaterials anditsImpactonPlantOperations,"

wassubmitted totheNRCinourletterAEP:NRC:0894K datedDecember5,1988.Thissubmittal waspreparedutilizing theresultsfrompreviously analyzedcapsulesandidentified actionstobetaken.Forinstance, CapsuleUwaspulledandanalyzedin1990andtheresultssubmitted totheNRCinourletterAEP:NRC:0894M datedJune20,1990.RevisedheatupandcooldowncurvesandLTOPcalculations weresubmitted totheNRCinoursubmittal letternumbersAEP:NRC:08940, AEP:NRC:0894/

andAEP:NRC:0894R.

Additionally, basedontheresultsoftheUnit1CapsuleUanalysis, aPTSevaluation wasperformed.

CopiesofAEPSC'sCapsuleUanalysis, responsetoGenericLetter88-11,andthePTSevaluation areincludedasAttachments 3,14,and15,respectively.

Unit2Asidentified forUnit1,AEPSC'sresponsetoGenericLetter88-11isbasedonresultsfrompreviously analyzedcapsules.

ThePTSevaluation forUnit2wasapprovedbytheNRCinanSERdatedMarch27,1987.Unit2CapsuleUwasremovedinMay1992andwillbeanalyzedwithinthenextyear.ResultsofthisanalysiswillbeusedtoupdateaUnit2RT~sevaluation, uestion3.c"Ifameasuredincreaseinreference temperature exceedsthemean-plus-twostandarddeviations predicted byRegulatory Guide1.99,Revision2,orifameasureddecreaseinCharpyuppershelfenergyexceedsthevaluepredicted usingtheguidanceinParagraph C.l.2inRegulatory Guide1.99,Revision2,thelicenseeisrequested toreporttheinformation anddescribetheeffectofthesurveillance resultsonthead]ustedreference temperature andCharpyuppershelfenergyforeachbeltlinematerialaspredicted forDecember16,1991,andfortheendofitscurrentlicense."

Enclosure toAEP:NRC:1173 AEP;NRC:1173 Resonsetouestion3.cUnit1NodatafromtheCookNuclearPlantreactorvesselmaterialsurveillance programexceedsthemean-plus-two standarddeviation boundpredicted byRegulatory Guide1.99Rev.2,RefertoAttachment 14(specifically refertopages3and4ofAttachment 2contained withinAttachment 14).Unit2NoCookNuclearPlantreactorvesselmaterialsurveillance programexceedsthemean-plus-two standarddeviation boundpredicted byRegulatory Guide1.99Rev.2.RefertoAttachment 14(specifically refertopages3and4ofAttachment 2contained withinAttachment 14).