ML17331B274

Application for Amend to License DPR-74,revising 3/4.4.9.1 Re Heatup & Cooldown Curves to Reflect Recent Reactor Vessel Matl Surveillance Capsule Reanalysis,Per Direction of Reg Guide 1.99,Rev 2

ML17331B274
Person / Time
Site:	Cook
Issue date:	02/22/1994
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17331B276	List: ML17331B274 ML17331B277
References
RTR-REGGD-01.099, RTR-REGGD-1.099 AEP:NRC:0894U, AEP:NRC:894U, NUDOCS 9403040281
Download: ML17331B274 (12)

Text

ACCELERATEDDI.TPJBUTIONDEMONSTATIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9403040281DOC.DATE:94/02/22NOTARIZED:YESDOCKETFACIL:50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

ApplicationforamendtolicenseDPR-74,revising3/4.4.9.1reheatup&cooldowncurvestoreflectrecentreactorvesselmatlsurveillancecapsulereanalysis,perdirectionofRegGuide1.99,Rev2.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTESRECXPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNAL:NRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2EXTERNAL:NRCPDRCOPIESLTTRENCL1122111111111011RECIPXENTIDCODE/NAMEPD3-1PDNRR/DORS/OTSBNRR/DRPWNRR/DSSA/SRXB08/LFJ7CBREGFXLE01NSXCCOPIESLTTRENCL11111111101111DDRDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR16ENCL14DD tIIkCCl nC'IindianaMichigan~PowerCompanyP.O.Box16631Columbus,OH43216AEP:NRC:0894UDonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICALSPECIFICATIONAMENDMENTREQUESTTOUPDATETHEUNIT2HEATUPANDCOOLDOWNCURVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyFebruary22,1994

DearDr.Murley:

ThisletteranditsattachmentsconstituteanapplicationforamendmenttoTechnicalSpecification3/4.4.9.1forDonaldC.CookNuclearPlantUnit2.Specifically,werequestthattheplantheatupandcooldowncurvesbechangedtoreflecttherecentreactorvesselmaterialsurveillancecapsulereanalyseswhichwasperformedbyWestinghouseElectricCorporationperthedirectionprovidedinRegulatoryGuide(R/G)1.99,Rev.2.Thereasonsfortheproposedchangeandourproposeddeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92(c),arecontainedinAttachment1tothisletter.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Theresultsofthecapsulereanalyses(WCAP-13515),performedbyWestinghouse,weresubmittedinourletterdatedMarch12,1993,underAEP:NRC:0894T,ReactorVesselMaterialSurveillanceReports.Thisreportwasusedtogeneratetheheatupandcooldowncurvesfor15EFPY.ThesecurvesarebeingsubmittedinthislettertoreviseFigures3.4-2and3.4-3ofTechnicalSpecification3/4.4.9.1,PressureandTemperatureLimitsfortheReactorCoolantSystem.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantL-.-'P40304028i940222PDR4DOCK05000316P Dr.T.E.Murley-2-AEP:NRC:0894Uincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TherevisedheatupandcooldowncurvesinAttachment3havebeenevaluatedagainstandreflectthecriteriaof10CFR50,AppendixG,ParagraphIV.A.2.TheimpactofthisT/SchangerequestonourLTOPsetpointhasbeenevaluated,andthecurrentLTOPsetpointwasnotrevisedasitisvalidupto15EFPY.Toimplementtherevisedheatupandcooldownlimitsinanorderlyfashion,weareproposingtoinstitutethesenewheatupandcooldownlimitsduringtherefuelingwindow(Mode6)oftheupcomingCycle9-10refuelingoutage,priortotheunitreturningtoMode5.WepresentlyanticipatetheoutagetobeginasearlyasAugust5,1994;therefore,werequestthatyourreviewofthesechangesbecompletedbySeptember4,1994.TheproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandbytheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.J.R.PadgettoftheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Thisletterissubmittedpursuantto10CFR50.30(b)and,assuch,anoathstatementisattached.Sincerely,E.EDFitztrickVicePresidentcadAttachmentscc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett STATEOFOHIO)COUNTYOFFRANKLIN)E.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationAmendment'equesttoUpdatetheUnit2HeatupandCooldownCurves,andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethis~~dayof,19NOTARPUBLICRITAD.HILLNOTARYPUBLIC.STATEOfOHIO Attachment1toAEP:NRC:0894U10CFR50.92DETERMINATIONFORPROPOSEDCHANGESTOTHEDONALDCCOOKNUCLEARPLANTUNIT2TECHNICALSPECIFICATIONS Attachment1toAEP:NRC:0894UPage11.0SECTIONSCHANGEDUnit2TechnicalSpecification(T/S)3.4.9.1Figure3.4-2,ReactorCoolantSystemHeatupLimitations,andFigure3.4-3,ReactorCoolantSystemCooldownLimitationsarebeingchanged.Also,thebasesforTechnicalSpecification3/4.4.9arebeingupdatedtoreflecttheanalysesperformedbyWestinghouse,andtheextendedtimeframeof15EFPY.2.0EXTENTOFCHANGESWeareproposingtochangetheheatupandcooldowncurvesshowninFigures3.4-2,and3.4-3,aswellasthebasesforthosespecifications,toreflectanextendedtimeframeof15EFPY.3'CHANGESREUESTEDTheT/SchangesfoundinAttachments2and3arebasedonimplementationofR/G1.'99,Revision2.ThefollowingUnit2T/Spagesareimpactedbythischange:Page3/44-25Page3/44-26PageB3/44-6PageB3/44-104.0DISCUSSIONPaes344-25and344-26Figures3.4-2and3.4-3aretheheatupandcooldown(P-T)limitcurvesforUnit2.Thesecompositecurvesreflecttheadjustedreferencetemperatureofthemostlimitingmaterialattheendof15EFPY,andarebasedonthefollowingconsiderations.Intermediateshellplate,C5556-2,isthelimitingmaterialasdeterminedbyposition1ofR/G1.99,Revision2,withaCuandNicontentof0.15%and0.57%,respectively.2~ThefluencevaluescontainedinTable6-14ofWestinghouseWCAP-13515,"AnalysisofCapsuleUfromIndianaMichiganPowerCompany,CookNuclearPlantUnit2ReactorVesselRadiationSurveillanceProgram",datedFebruary1993.ThisreportwassubmittedasanattachmenttoletterAEP:NRC:0894T,datedMarch12,1993.

Attachment1toAEP:NRC:0894UPage2PaesB344-6andB344-10ThePressure-TemperaturebasesareproposedtobemodifiedtoreflecttheUnit2CapsuleUAnalysis,aspresentedinWestinghouseWCAP-13515.5.0NOSIGNIFICANTHAZARDSDETERMINATIONWehaveevaluatedtheproposedT/Ss,andhavedeterminedthatitshouldnotrepresentasignificanthazardsconsiderationbasedonthecriteriaestablishedin10CFR50.92(c).OperationoftheCookNuclearPlantinaccordancewiththeproposedamendmentwillnot:(1)Involveasinificantincreaseintherobabilitorconseencesofanaccidentreviouslevaluated.TheproposedchangestotheP-TcurvesarebeingupdatedasaresultoftheUnit2CapsuleUanalysis,WCAP-13515.TheanalysiswasrequiredpertheremovalscheduleestablishedinTable4.4-5oftheCookNuclearPlantTechnicalSpecifications.TheanalysiswasperformedbasedonguidancefromR/G1.99,Revision2.Thechangeonlyinvolvesarevisedtimeframeformaterialqualificationfrom12EFPYto15EFPYassupportedbytheaforementionedWestinghouseanalysis.Therefore,weconcludethatthechangeswillnotinvolveasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillthechangesinvolveasignificantreductioninamarginofsafety.(2)Createtheossibilitofanewordifferentkindofaccidentfromanreviouslanalzed.Theproposedchangesdonotinvolveanyphysicalmodificationstotheplant.Therefore,thechangesshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyanalyzedorevaluated.

Attachment1toAEP:NRC:0894UPage3(3)InvolveasinificantreductioninamarinofsafetSeetheresponseto(1)above.6.0PENDINGTSsPROPOSALSIMPACTINGTHISSUBMITTALTherearecurrentlynootherT/Ssproposalsunderreviewthatwouldimpactthissubmittal.

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