ML17334B471
| ML17334B471 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/16/1993 |
| From: | FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17331A288 | List: |
| References | |
| AEP:NRC:1181, NUDOCS 9304220175 | |
| Download: ML17334B471 (207) | |
Text
ACCELERATF/iDOCUii'll5'l'ISTRLBUTlOYSYSTEMREGULAINFORMATION"DZSTRZBUTZOtOYSTEN(RZDSlACCESSIONNBR:9304220175DOC.DATE:93/04/16NOTARIZED:YESDOCKETIFACIL:50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAME.AUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana!;MichiganEleRECIP.NAMERECIPIENTAFFILIATIONMURLEYFTEDDocumentControlBranch(DocumentControlDesk)DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRJENCLgSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:Jfp~.~pk7~RECIPIENTCOPIESRECIPIENTIDCODE/NAMELTTRENCLIDCODE/NAMEPD3-1LA11PD3-1PDDEAN,N22.,COPIESLTTRENCL11
SUBJECT:
ApplicationforamendtoLicense-DPR-74,requestingrelieffromTSsurveillancesuntilrefuelingoutage,currentlyscheduledtobeginon940806.e~jINTERNAL:NRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2EXTERNAL:NRCPDR111111111011NRR/DORS/OTSBNRR/DSSA/SCSBNRR/DSSA/SRXBOCE01NSIC111011101111NOTETOALL"R1DS"REClPlEHTS:PLEASEHELPUSfOREDUCEWASTE!CONlAClTllEDOCU).'EYTCOii'TR(>!D!:.~V,ROOMP1.37(EXT.504-20o5)TOEL!MIYATEYOURHA."lEFROliD]STRiliUTlONLiSTSFORDOCU!4EYl'SYOUDOi"l'T)REED!TOTALNUMBEROFCOPIESREQUIRED:LTTR16ENCL13 l
IndianaMichiganPowerCompanyP.O.Box16631Columbus~".iH43216IIHtMSlHSlsvaamramauePOUFFEDonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74SURVEILLANCEINTERVALEXTENSIONFORUNIT2CYCLE9AEP:NRC:1181U.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555AttnrT.E.MurleyApril16,1993
DearDr.Murley:
ThisletterconstitutesanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnit2.Specifically,werequestanextensionforcertainsurveillanceswhichtheT/SsrequiretobeperformedbeginningJanuary2,1994.WearerequestingrelieffromtheseT/SrequirementsuntiltheUnit2refuelingoutage,whichiscurrentlyscheduledtobeginAugust6,1994.Manyofthesesurveillancescanonlybeperformedduringshutdown;therefore,toavoidunnecessaryshutdownoftheplant,weaskthatyourreviewofthisrequestbeperformedonanexpeditedbasisandthatyourespondtousbyDecember1,1993.AdescriptionoftheproposedchangesandouranalysisconcerningsignificanthazardsconsiderationsarecontainedinAttachment1tothisletter.Theproposed,revisedT/SpagesarecontainedinAttachment2.TheexistingT/Spages,markedtoreflecttheproposedchanges,arecontainedinAttachment3.Alloftherequestedsurveillanceextensionsareassociatedwithsurveillancesnormallyperformedduringrefuelingoutages.Thecurrentcyclewillbelengthenedapproximatelyfivemonthsduetoaplannedpowerreductiontoapproximately70%ofratedthermalpower,whichistobegininMay1993andremainineffectuntiltheendofthe.cycle.ThepurposeofextendingthecycleistoseparatetherefuelingoutagesbetweenUnit1'(whichisscheduledforrefuelinginJanuary,1994)andUnit2.9304220i759304ibPDRADOCK050003ibg0l Dr.T.E.MurleyAEP:NRC:1181Duringthelastrefuelingoutage,whichwasextendedapproximatelysixmonthsduetoturbine-generatorrotorvibrations,aneffortwasmadetore-performasmanysurveillancesaspossible.AsignificantnumberofT/Ssurveillances(approximately70)werere-performed,reducingthenumberofsurveillancesforwhichwearerequestingextensions.However,oureffortswereconstrainedbecauseUnit1wasinarefuelingoutageatthesametime.SomeoftheTechnicalSpecificationpagesaffectedbythissubmittalarepagesforwhichchangesarependingduetopriorsubmittals.Theproposedchangescontainedinthissubmittalareinadditiontoourpreviousrequestsanddonotsupersedethem.Thepagesincludedinthiscategoryandtheapplicablepriorsubmittalswhichhavenotyetbeenprocessedareprovidedinthetablebelow:LetterNumberDateTSPaeNumbersAEP:NRC:1131AApril19,1991AEPsNRC:1178September24,1992AEP:NRC:1143May1,19923/44-333/46-143/47-2063/47-40Inaccordancewith10CFR50.92(c),ourevaluationofthechangesindicatesnosignificanthazardsbecausethesechangesdonot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;(2)createthepossibil'ityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninthemarginofsafety.TheseproposedchangeshavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommitteeandbytheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.
Dr.T.E.MurleyAEP:NRC:1181Thisletterissubmittedpursuantto10CFR50.54(f)and,assuch,anoathstatementisenclosed.Sincerely,E.E.FitpatrickVicePresidentdrAttachmentscc!A.A.Blind-BridgmanJ.R.PadgettG.CharnoffA.B.Davis-RegionIIINRCResidentInspector-BridgmanNFEMSectionChief
~'Dr.T.E.MurleyAEPsNRC:1181bc:S.J.BrewerD.H.Malin/K.J.TothM.L.Horvath-BridgmanJ.B.ShinnockW.G.Smith,Jr.W.M.Dean,NRC-Washington,D,C.AEP:NRC!1181DC-N-6015.1
~C~STATEOFOHIOCOUNTYOFFRANKLINE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationsChangesProposedinLetterAEPsNRC:1181andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethisdayof19NOTARYPUBLICRITAD.HILLNOTARYPUBLIC.STATEOFOHIO TENSILEWOLWOL005WOLTENSILECNARPYCNARPY~EYERI.OCRCHARPYCNARPYCHARPYCHARPYCHARPYICHARPYCHARPYCHARPYCNARPYCAPSULEUNT-12NTllIRf-l2Nf.72NT-72IOI-71NT-71IOf-70NT7010f69HT69068HT-68MHT-67IOf-66NT-6610f-65NT-6WCflHT6910f-63HT-63fN-62HT-62Of-61NT-61HH-72NL-48NH-70-f16NK-71NL&7NII-69-f15HK-67KL&3KH-66HL~2KH-65KL-91HKHfl-62III63HH-61SPECIMENCODE:MT-PLATEC552I-2(TRANSVERSE)KL-PLATF.C552I-2(LONGITUDINAL)MW-WELDMETALMH-WELDHEATAFFECTEDZONEQgyERYURECARO>isoavailable0~ApertureCaE'dFigure4-2CapsuleUDiagramShowingLocationofSpecimens,ThermalMonitorsandDosimeters
SECTION5.0TESTINGOFSPECIHENSFROMCAPSULEU5.1OverviewThepost-irradiationmechanicaltestingoftheCharpyV-notchandtensilespecimenswasperformedattheWestinghouseScienceandTechnologyCenterhotcellwithconsultationbyWestinghousePowerSystemspersonnel.Testingwasperformedinaccordancewith10CFR50,AppendicesGandH~~,ASTHSpecificationE185-82~~,andWestinghouseRemoteHetallographicFacility(RHF)ProcedureRHF8402,Revision2asmodifiedbyRHFProcedures8102,Revision1'and8103,Revision1.Uponreceiptofthecapsuleatthehotcelllaboratory,thespecimensandspacerblockswerecarefullyremoved,inspectedforidentificationnumber,andcheckedagainstthemasterlistinWCAP-8512~~.Nodiscrepancieswerefound.Examinationofthetwolow-meltingpoint579'F(304'C)and590'F(310'C)eutecticalloysindicatednomeltingofeithertypeofthermalmonitor.Basedonthisexamination,themaximumtemperaturetowhichthetestspecimenswereexposedwaslessthan579'F(304'C).TheCharpyimpacttestswereperformedperASTHSpecificationE23-88~~andRHFProcedure8103,Revision1onaTinius-OlsenHodel74,358Jmachine.Thetup(striker)oftheCharpymachineisinstrumentedwithaGRC830Iinstrumentationsystem,feedinginformationintoanIBHXTcomputer.Withthissystem,load-timeandenergy-timesignalscanberecordedinadditiontothestandardmeasurementofCharpyenergy(ED).Fromtheload-timecurveshowninAppendixA,theloadofgeneralyielding(PGy),thetimetogeneralyielding(tGY),themaximumload(PH),andthetimetomaximumload(tH)canbedetermined.Undersometestconditions,asharpdropinloadindicativeoffastfracturewasobserved.Theloadatwhichfastfracturewasinitiatedisidentifiedasthefastfractureload(PF),andtheloadatwhichfastfractureterminatedisidentifiedasthearrestload(PA).5-1 Theenergyatmaximumload(EM),wasdeterminedbycomparingtheenergy-timerecordandtheload-timerecord.Theenergyatmaximumloadisroughlyequivalenttotheenergyrequiredtoinitiateacrackinthespecimen.~*Therefore,thepropagationenergyforthecrack(E')isthedifference.betweenthetotalenergytofracture(ED)and'theenergyatmaximumload.Theyieldstress(ay)wascalculatedfromthethree-pointbendformulahavingthefollowingexpression:ay=PG~*[L/[B*(W-a)*C])whereLdistancebetweenthespecimensupportsintheimpacttestingmachine;Bthewidthofthespecimenmeasuredparalleltothenotch;Wheightofthespecimen,measuredperpendicularlytothenotch;a-notchdepth.TheconstantCisdependentonthenotchflankangle(P),notchrootradius(p),andthetypeofloading(i.e.,purebendingorthree-pointbending).Inthree-pointbendingaCharpyspecimeninwhichP45'ndp-0:010",Equation1isvalidwithC1.21.Therefore(forL-4W),oy=PGy*[L/[B*(W-a)*1.21])-[3.3PGyW]/[B(W-a)](2)FortheCharpyspecimens,B=0.394in.,W-0.394in.,anda-0.079in.Equation2thenreducesto:Gy=33.3xPGy(3)whereoyisinunitsofpsiandPGyisinunitsoflbs.Theflowstresswascalculatedfromtheaverageoftheyieldandmaximumloads,alsousingthethree-pointbendformula.Percentshearwasdeterminedfrompost-fracturephotographsusingtheratio-of-areasmethodsincompliancewithASTHSpecificationA370-89[].Thelateralexpansionwasmeasuredusingadialgagerigsimilartothatshowninthesamespecification.5-2 Tensiontestswereperformedona20,000-poundInstronModel1115,split-consoletestmachine,perASTMSpecificationE8-89b~~andE21-79(1988)~~,andRMFProcedure8102,RevisionI.Allpullrods,grips,andpinsweremadeofInconel718hardenedtoHRC45.Theupperpullrodwasconnectedthroughauniversaljointtoimproveaxialityofloading.Thetestswereconductedataconstantcrossheadspeedof0.05inchesperminutethroughoutthetest.Extensionmeasurementsweremadewithalinearvariabledisplacementtransducer(LVDT)extensometer.Theextensometerknifeedgeswerespring-loadedtothespecimenandoperatedthroughspecimenfailure.Theextensometergagelengthis1.00inch.TheextensometerisratedasClassB-2perASTME83-85~II~.Elevatedtesttemperatureswereobtainedwithathree-zoneelectricresistancesplit-tubefurnacewitha9-inchhotzone.Alltestswereconductedinair.Becauseofthedifficultyinremotelyattachingathermocoupledirectlytothespecimen,thefollowingprocedurewasusedtomonitorspecimentemperature.Chromel-alumelthermocoupleswereinsertedinshallowholesinthecenterandeachendofthegagesectionofadummyspecimenandineachgrip.Inthetestconfiguration,withaslightloadonthespec'imen,aplotofspecimentemperatureversusupperandlowergripandcontrollertemperatureswasdevelopedovertherangeofroomtemperatureto550'F(288'C).Theuppergripwasusedtocontrolthefurnacetemperature.Duringtheactualtestingthegriptemperatureswereusedtoobtaindesiredspecimentemperatures.Experimentsindicatedthatthismethodisaccurateto+2'F.Theyieldload,ultimateload,fractureload,totalelongation,anduniformelongationweredetermineddirectlyfromtheload-extensioncurve.Theyieldstrength,ultimatestrength,andfracturestrengthwerecalculatedusingtheoriginalcross-sectionalarea.Thefinaldiameterandfinalgagelengthweredeterminedfrompost-fracturephotographs.Thefractureareausedtocalculatethefracturestress(truestressatfracture)andpercentreductioninareawascomputedusingthefinaldiametermeasurement.5-3 5.2Char-NotchImactTestResultsTheresultsoftheCharpyV-notchimpacttestsperformedonthevariousmaterialscontainedinCapsuleU,whichwasirradiatedto1.58x10n/cm(E>1.0MeV),arepresentedinTables5-1through5-4andarecomparedwithunirradiatedresults~~asshowninFigures5-1through5-4.Thetransitiontemperature'increasesanduppershelfenergydecreasesfortheCapsuleUmaterialsaresummarizedinTable5-5.IrradiationofthereactorvesselintermediateshellplateC5521-2Charpyspecimensorientedwiththelongitudinalaxisofthespecimenparalleltothemajorrollingdirectionoftheplate(longitudinalorientation)to1.58x10n/cm(E>1.0MeV)at550'F(Figure5-1)resultedina30ft-lbtransitiontemperatureincreaseof95'Fandina50ft-lbtransitiontemperatureincreaseof110'F.Thisresultedina30ft-lbtransitiontemperatureof120'Fanda50ft-lbtransitiontemperatureof165'F(longitudinalorientation).TheaverageUpperShelfEnergy(USE)oftheintermediateshellplateC5521-2Charpyspecimens(longitudinalorientation)resultedinaenergydecreaseof16ft-lbafterirradiationto1.58x10n/cm(E>1.0MeV)at550'F.ThisresultsinanaverageUSEof111ft-lb(Figure5-1).IrradiationofthereactorvesselintermediateshellplateC5521-2Charpyspecimensorientedwiththelongitudinalaxisofthespecimennormaltothemajorrollingdirectionoftheplate(transverseorientation)to1.58x10n/cm2(E>1.0MeV)at550'F(Figure5-2)resultedina30ft-lbtransitiontemperatureincreaseof130'Fandina50ft-lbtransitiontemperatureincreaseof135'F.Thisresultedina30ft-lbtransitiontemperatureof160'Fanda50ft-lbtransitiontemperatureof205'F(transverseorientation).5-4 TheaverageUSEoftheintermediateshellplateC5521-2Charpyspecimens(transverseorientation)resultedinanenergydecreaseof14ft-lbafterirradiationto1.58x10n/cm(E>1.0MeV)at550'F.ThisresultedinanaverageUSEof72ft-lb(Figure5-2).IrradiationofthereactorvesselcoreregionweldmetalCharpyspecimensto1.58x10n/cm(E>1.0MeV)at550'F(Figure5-3)resultedina75'Fincreasein30ft-lbtransitiontemperatureanda50ft-lbtransitiontemperatureincreaseof40'F.Thisresultedina30ft-lbtransitiontemperatureof85'Fandthe50ft-lbtransitiontemperatureof110'F.TheaverageUSEofthereactorvesselcoreregionweldmetalresultedinanenergydecreaseof6ft-lbafterirradiationto1.58x10n/cm(E>1.0MeV)at550'F.ThisresultedinanaverageUSEof71ft-lb(Figure5-3).IrradiationofthereactorvesselweldHeat-Affected-Zone(HAZ)metalspecimensto1.58x10n/cm(E>1.0MeV)at550'F(Figure5-4)resultedina30ft-lbtransitiontemperatureincreaseof105'Fanda50ft-lbtransitiontemperatureincreaseof110'F.Thisresultedina30ft-lbtransitiontemperatureof45'Fandthe50ft-lbtransitiontemperatureof80'F.TheaverageUSEofthereactorvesselweldHAZmetalexperiencedanenergydecreaseof33ft-lbafteri}radiationto1.58x10n/cm(E>1.0MeV)at550'F.ThisresultedinanaverageUSEof82ft-lb(Figure5-4).ThefractureappearanceofeachirradiatedCharpyspecimenfromthevariousmaterialsisshowninFigures5-5through5-8andshowanincreasinglyductileortougherappearancewithincreasingtesttemperature.Acomparisonofthe30ft-lbtransitiontemperatureincreasesanduppershelfenergydecreasesforthevariousD.C.CookUnit2surveillancematerialswithpredictedvaluesusingthemethodsofNRCRegulatoryGuide1.99,Revision2~~ispresentedinTable5-6.Comparisonofthe30ft-lbtransition5-5 temperatureincreasefor'heintermediateshellplateC5521-2(transverseorientation)is33'FgreaterthantheRegulatoryGuideprediction.However,theNRCRegulatoryGuide1.99,Revision2requiresa2sigmaallowanceof34'Fbeaddedtothepredictedreferencetransitiontemperaturetoobtainaconservativeupperboundvalue.Thus,thereferencetransitiontemperatureincreaseisboundedbythe2sigmaallowanceforshiftprediction.ThiscomparisonindicatesthatthetransitiontemperatureincreasesandtheuppershelfenergydecreasesoftheIntermediateShellPlateC5521-2(longitudinalorientation)andsurveillanceweldresultingfromirradiationto1.58x10n/cm(E>1.0MeV)arelessthantheRegulatoryGuidepredictions.ThiscomparisonalsoindicatesthattheuppershelfenergydecreaseoftheintermediateshellplateC5521-2(transverseorientation)resultingfromirradiationto1.58x10n/cm(E>1.0HeV)islessthantheRegulatoryGuideprediction.Theendoflicense(32EFPY)RTNDTvaluesforalltheD.C.CookUnit2beltlineregionmaterialsareshowninTable5-7.ThesevalueswerepredictedusingRegulatoryGuide1.99,Revision2methodologyandareprojectedtobewithintheRegulatorylimits.PhotographsofthecharpyandtensilespecimensbeforetestingareshowninAppendixB.5.3TensionTestResultsTheresultsofthetensiontestsperformedonthevariousmaterialscontainedinCapsuleUirradiatedto1.58x10n/cm(E>1.0HeV)arepresentedinTable5-8andarecomparedwithunirradiatedresults~~asshowninFigures5-9and5-10.5-6 rTheresultsofthetensiontestsperformedontheintermediateshellplateC5521-2(transverseorientation)indicatedthatirradiationto1.58x10n/cm(E>1.0MeV)at550'Fcausedlessthana18ksiincreaseinthe0.2percentoffsetyieldstrengthandlessthana16ksiincreaseintheultimatetensilestrengthwhencomparedtounirradiateddata~~(Figure5-9).Theresultsofthetensiontestsperformedonthereactorvesselcoreregionweldmetalindicatedthatirradiationto1.58x10n/cm(E>1.0MeV)at550'Fcausedlessthana9ksiincreaseinthe0.2percentoffsetyieldstrengthandlessthana8ksiincreaseintheultimatetensilestrengthwhencomparedtounirradiateddata~~(Figure5-10).ThefracturedtensionspecimensfortheIntermediateShellPlateC5521-2materialareshowninFigure5-11,whilethefracturedspecimensfortheweldmetalareshowninFigure5-12.Theengineeringstress-straincurvesforthetensiontestsareshowninFigures5-13and5-14.05.4Wede0eninLoadinSecimensPerthesurveillancecapsuletestingprogramwiththeIndianaMichiganPowerCompany,theWOLspecimenswillnotbetestedandwillbestoredattheWestinghouseScienceandTechnologyCenter.5-7 TABLE5-1CHARPYV-NOTCHIMPACTDATAFORTHED.C.COOKUNIT2INTERMEDIATESHELLPLATEC5521-2IRRADIATEDAT550F,FLUENCE1.58x10ngcm2(E>1.0Mey)TemperatureImpactEnergyLateralExpansion~SemieNo.~F~C~ft-ib~J~mile~mmLon'tudinalOrientationShearML45ML48ML42ML44ML41ML43ML46ML4775(24)100(38)125(52)175(79)200(93)225(107).250(121)300(149)14(19)27(37)35(47)62(84)55{75)103(140)114(155)115(156)102327'242507982(0.25)10{0.58)20(0.69)30(1.07)50{1.07)50(1.27)90(2.01)100(2.08)100MT62MT61MT66MT71MT64MT72MT70MT69MT63MT68MT67MT6525(-4)50(10)75(24)125(52)150(66)175(79)200(93)215(102)225(107)250(121)275(135)300(149)TransverseOrientation5(7)214(19)1217(23)1019(26)1625(34)2133(45)2837(50)3039(53)3363(85)5267(91)5472(98)5077(104)58(0.05)5(0.30)10(0.25)15(0.41)30(0.53)35(0.71)40(0.76)45(0.84)65(1.32)95(1.37)100(1,27)100(1,47)1005-8 TABLE5-2CHARPYV=NOTCHIMPACTDATAFORTHED.C.COOKUNIT2REACTORVESSELWELDMETALANDHAZMETALIRRADIATEDAT550'F,FLUENCE1.58x10n/cm(E>1.0MeV)~SamleNo.Temperature('F)('C)ImpactEnergy(R-1b)(J)WeldMetalLateralExpansion(mils)(mm)Shear(~c)MW70MW64MW71iiIW68MKV63MAV61MW72MW65MW66MW62MW67MW69MH67MH63MH71MH69MH72MH70MH62MH64MH61MH65MH68MH66-100255075100125150175185200250-2525506575100125150175200225250(-23)(-18)(-4)(10)(24)(38)(52)(66)(79)(85)(93)(121)(-32)(-4)(10)(18)(24)(38)(52)(66)(79)(93)(107)(121)23(31)29(39)17(23)21(28)26(35)42(57)60(81)71(96)47(64)62(84)78.(106)74(100)HAZMetal4(5)21(28)48(65)18(24)64(87)39(53)118(160)72(98)83(113)103(140)74(100)69(94)16261421203750573949626221030194432715561715366(0.41)(0.66)(0.36)(0.53)(0.51)(0.94)(1.27)(1.45)(0.99)(1.24)(1.57)(1.57)(0.05)(0.25)(0.76)(0.48)(1.12)(0.81)(1.80)(1.40)(1.55)(1.80)(1.35)(1.68)2535304060808510085100100100103555309050100.951001001001005-9 TABLE5-3INSTRUMENTEDCHARPYIMPACTTESTRESULTSFORTHED.C.COOKUNIT2INTERMEDIATESHELLPLATEC5521-2IRRADIATEDAT550'F,FLUENCE1.58x10n/cm(E>1.0MeV)SampleNcehesTestCharpyTempEnergy~s'ft-1hNormalizedEnerCharpyMaximumEd/AEm/Aft-lbiniesProp.Ep/AYieldLoad~lbsTimeMaximumTimetotoYieldLoadMaximum~csee~lhs~cseeFractureLoad~lhsArrestYieldFloeLoadStressStress~lhs~ksi~ksiLonitudinalOrientationML45ML48ML42ML44ML41ML43ML46ML47751410027125351756220055225103250114300115113642171672821244992414431228293089182349261474850157258321521684779372236703945346737313262326531260.1439290.1446000.2942580.1447350.2841390.1445070.1445460.1440710:200.380.380.530.380.540.540.3839294600425845633887**6388583847921340**124127122137131136115136124131108129108130104120TransverseOrientationMT62MT61MT66MT71MT64MT72MT70MT69MT63MT68MT67MT65255501475171251915025175332003721539225632506727572300774011313715320126629831450754058062012778848124156128153236221222223283549105771107360038252969338127231935839733593288305131531103438170368116132890.100.140.140.210.140.130.280.140.150.140.160.1413194154427331874194427340964158.4457.4212424942510.140.220.250.240.320.380.390.380.540.540.540.54131941544273318741944273409641584225**5512651320215772083215125333236374012012912713499102112126114128122129109124112130109125101121105123*Fullyductilefracture.Noarrestload.0 TABLE5-4ArrestYieldFlowLoadStressStress~lbs~ksi~ksiINSTRUMENTEDCHARPYIMPACTTESTRESULTSFORTHED.C.COOKUNIT2MELDMETALANDHEAT-AFFECTED-ZONE(HAZ)METAL,IRRADIATEDAT550'F,FLUENCE1.58x10n/cm(E>1.0MeV)NormalizedEneriesTestCharpyCharpyMaximumPropYieldTimeMaximumSampleTempEnergyEd/AEm/AEp/ALoadtoYieldLoadNumber~r~ft-1bft-lbin~lbs~mesc~lbsWeldMetalMW70MW64MW71MW68MW63MW61MW72MW65MW66MW62MW67MW69-1002550751001251501751852002502329172126426071476278741852341371692093384835723784996285961331068385131151239235221231250231521275484791872443371582693783653898389137763847365537123323351133973280375432830.140.140.140.260.140.260'40.140'40.130.280.144576448241054021443043594581453544044232444042730.310.280.230.300.320.420.540.540.500.540.620.544576448241054021443043594581440477846797894116184631252*810129141129139125131128131121134123134110131117134113130109125125136109125HAZMetalMH67MH63MH71MH69MH72MH70MH62MH64MH61MH65MH68MH66-25255065751001251501752002252504214818643911872831037469321693871455153149505806688295965561547166581621143012402432531872281712222187354200649340425576409328964332737973653391029703352399136223642306633300.100.210.140.140.140.210.160.220.140.150.170.145-111133348645573834453036184355475646624799398142870.170.230.380.200.370.380.530.540.540.540.500.521133348644203834450036184756****14685821269713802954*4056*323511111312613912112413014099109111128133145120138121140102117111126*Fullyductilefracture.Noarrestload.
TA8LE5-5EFFECTOF550FIRRADIATIONTO1.58x10n/cm(E>1.0HeV)ONTHENOTCHTOUGHNESSPROPERTIESOFTHED.C.COOKUNIT2REACTORVESSELSURVEILLANCEHATERIALSAverage30ft-lb('I)TransitionTemperature(F)Average35milLateralExpansionTemperature(F)Average50ft-lb('1)TransitionTemperature(F)AverageEnergyAbsorptionatFullShear(ft-lb)HaterialUnirradiatedIrradiatedATUnirradiatedIrradiated4TUnirradiatedIrradiatedATUnirradiatedIrradiatedd(ft-lb)PlateC5521-2(Longitudinal)25120955015010055165110127111-16PlateC5521-2(Transverse)3016013070190120702051358672-14MeldHetal108575501005070110407771-6HAZHetal-6045105-4085125-308011011582-33(1)"AVERAGE"isdefinedasthevaluereadfromthecurvefittedthroughthedatapointsoftheCharpytests(Figures5-1through5-4).y5-12 TABLE5-6COMPARISONOFTHED.C.COOKUNIT2SURVEILLANCEMATERIAL30FT-LBTRANSITIONTEMPERATURESHIFTSANDUPPERSHELFENERGYDECREASESWITHREGULATORYGUIDE1.99REVISION2PREDICTIONS30ft-lbTransitionTem.ShiftUerShelfEnerDecreaseMaterialFluencePredicted(a)MeasuredCapsule10n/cm('F)('F)Predicted(a)Measured(>)(>)PlateC5521-2(Longitudinal)0.2640.6831.061.5855778897559095951620222413191913PlateC5521-2(Transverse)0.2640.6831.061.5855778897801001031301620222414201916WeldMetal0.2640.6831.061.5845637280405070751518212349108HAZMetal0.2640.6831.061.5850707210513211229(a)RegulatoryGuide1.99,Revision25-13 TABLE5-7PROJECTEDENDOFLICENSE(32EFPY)RTNDTANDUPPERSHELFENERGYVALUESFORD.C.COOKUNIT2BELTLINEREGIONMATERIALSPERREGULATORYGUIDE1.99,REVISION2MATERIALDESCRIPTIONRTNDTFUPPERSHELFENERGYft-lbsIntermediateShellPlate,C5556-2IntermediateShellPlate,C5521-2216171(171)7666LowerShellPlate,C5540-2LowerShellPlate,C5592-11001284752IntermediateShellLongitudinalWelds90(56)(locatedat10'zimuth)62LowerShellLongitudinalWelds(locatedat90'zimuth)84(50)62CircumferentialMeld102(67)62Notenumbersin()arebaseduponsurveillancecapsuledata.5-14 TABLE5-8TENSILEPROPERTIESFORTHED.C.COOKUNIT2REACTORVESSELSURVEILLANCEMATERIALSIRRADIATEDAT550'FTO1.58x10n/ctn(E)1.0MeV)MaterialSampleNumberTestTemp.~F0.2%YieldUltimateFractureFractureFractureUniformTotalReductionStrengthStrengthLoadStressStrengthElongationElongationinArea~ksi~ksi.~ki~ksi.~ksi.PlatePlateMTllMT1215055079.570.397.493.73.603.65172.0131.873.374.410.59.620.116.75744WeldWeldMW11MW12'2555082.575.996.892.73.203.50173.9190.265.271.39.08.119.517.163585-15
(~C)-150-100-500501001502001008060c%40031008060>C4020016014000I0tl'F~0UNIRRADIATED~IRRADIATED<550'F),FLUENCEI58xIOn/cd1.51.00.5020012010080560402000No'F~~~160120-8040-200-1000100200300400TEMPERATURE('f)Figure5-1.CharpyV-NotchImpactPropertiesforD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(LongitudinalOrientation)5-16
(~C)-150-100-50050100150200100806040200001008060'C40200120Ic9'F~t0NIIRRADIATED~IRRADIATED(550'F),FLUEHCEl58xIOn/cn~2.52.01.51.00.516010080I604020l35'F013I'F~~1208040-200-1000100200300400500TEMPLRATURL('f)Figure5-2.CharpyV-NotchImpactPropertiesforD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(TransverseOrientation)5-17 (C)-150-100-5005010015020010080604p20000~0~~1008060>C4020012050F0~0UNIRRADIATED~IRRADIATED(550'F),FLUENCE!50xIOn/cn2.51.51.00.516010080I60400i0'F00T5F0~120804p-200-1000100200300400500TEMPERATURE('F')Figure5-3.CharpyV-NotchImpactPropertiesforD.C.CookUnit2ReactorVesselSurveillanceWeldMetal5-18
('C)-150-100-5005010015020010080K60~400081008060OC40200002oS~Ol25'I'~004~1.51.00,51601401200UNIRRADIATED~IRRADIATED(550'F),ELUEhEEI$8xIOn/cn~002001601008060LJ40,20o000~ll9'I'~00~~1208040-200-1000100200300400TEMPERATURE(f)Figure5-4.CharpyV-NotchImpactPropertiesforD.C.CookUnit2ReactorVesselWeldHeat-Affected-ZoneNetal5-19 ML45ML48ML42ML41ML43ML46ML47Figure5-5.CharpyImpactSpecimenFractureSurfacesforD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(LongitudinalOrientation)5-20 MT62MT61MT66MT71tfI*r!'iMT64MT72MT69&NWBSNWWsst<.qIItqw(!i~4~AM+%38!!!!!!hMT63MT68MT67MT65Figure5-6.CharpyImpactSpecimenFractureSurfacesforD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(TransverseOrientation)5-21 MW70MW64MW71MW68MW63MW61MW72MW65S<hI)-ca)iMW66MW62MW67MW69Figure5-7.CharpyImpactSpecimenFractureSurfacesforD.C.CookUnit2ReactorVesselSurveillanceWeldNetal5-22 MH67MH63MH71MH69MH72MH62MH64tycholaMH61MH65MH68MH66Figure5-8.CharpyImpactSpecimenFractureSurfacesforD.C.CookUnit2ReactorVesselWeldHeat-Affected-ZoneMetal5-23 12011010050100('C)150200250300800700g80cn7060504080ULTIMATETEHSILESTRENGTH02%YIELDSTRENGTHQQUNIRRADIATED4~IRRADIATEDAT550'F,FLUENCEL50xIOg'cn600'004003007060950-40g3020REDUCTIONINAREATOTALELONGATION10UNIFORHONGATION100200300400TEMPERATURE('F)500FigUre5-9.TensilePropertiesforD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(TransverseOrientation)5-24 120110100Q90g80cn7050('C)100150200250300Il.TIMATETENSILESTRENGTH2+D2%YIELDSTRENGTH8007006005004004080b,0UNIRRADIATED4~IRRADIATEDAT550F,FLUENCEL58xI019n/cn2REDUCTIONINAREA30060~50UNIFORMELONGATIII10TOTALETION100200300400TEMPERATURE('F)500Figure5-10.TensilePropertiesforD.C.CookUnit2ReactorVesselSurveillanceWeldHetal5-25 889SpecimenMT11150'FSpecimenMT12550'FFigure5-11.FracturedTensileSpecimensfromD.C.CookUnit2ReactorVesselIntermediateShellPlateC5521-2(TransverseOrientation)5-26 SpecimenMW11125'FSpecimenMW12550'FFigure5-12.FracturedTensileSpecimensfromD.C.CookUnit2ReactorVesselSurveillanceWeldMetal5-27 100.0090.0080.0070.006o.oo50.00h40.0030.0020.0010.000.000.00.10.STRAIN,IN/INMT11150F0.20100.0090.0080.0070.0060.00(050.00IM40.0030.0020.0010.000.000.00.040.080.12STRAIN,IN/INMT12550F0.16Figure5-13.EngineeringStress-StrainCurvesforPlateC5521-2TensileSpecimensNTllandHT12(TransverseOrientation)5-28 100.0090.0080.0070.0060.005000IM40.0030.0020.0010.000.000.00.040.080.12STRAIN,IN/INMW11125F0.160.20100.0090.0080.0070.006o.oo50.00le40.0030.0020.0010.000.000.00.040.080.12STRAIN,IN/INMW12550F8.160.20Figure5-14.EngineeringStress-StrainCurvesforWeldMetalTensileSpecimensNWllandMW125-29 SECTION6.0RADIATIONANALYSISANDNEUTRONDOSIMETRY6.1IntroductionKnowledgeoftheneutronenvironmentwithinthereactorpressurevesselandsurveillancecapsulegeometryisrequiredasanintegralpartofLWRreactorpressurevesselsurveillanceprogramsfortworeasons.First,inordertointerprettheneutronradiation-inducedmaterialpropertychangesobservedinthetestspecimens,theneutronenvironment(energyspectrum,flux,fluence)towhichthetestspecimenswereexposedmustbeknown.Second,inordertorelatethechangesobservedinthetestspecimenstothepresentandfutureconditionofthereactorvessel,arelationshipmustbeestablishedbetweentheneutronenvironmentatvariouspositionswithinthereactorvesselandthatexperiencedbythetestspecimens.Theformerrequirementisnormallymetbyemployingacombinationofrigorousanalyticaltechniquesandmeasurementsobtainedwithpassiveneutronfluxmonitorscontainedineachofthesurveillancecapsules.Thelatterinformationisderivedsolelyfromanalysis.Theuseoffastneutronfluence(E>1.0MeV)tocorrelatemeasuredmaterialspropertieschangestotheneutronexposureofthematerialforlightwaterreactorapplicationshastraditionallybeenacceptedfordevelopmentofdamagetrendcurvesaswellasfortheimplementationoftrendcurvedatatoassessvesselcondition.Inrecentyears,however,ithasbeensuggestedthatanexposuremodelthataccountsfordifferencesinneutronenergyspectrabetweensurveillancecapsulelocationsandpositionswithinthevesselwallcouldleadtoanimprovementintheuncertaintiesassociatedwithdamagetrendcurvesaswellastoamoreaccurateevaluationofdamagegradientsthroughthepressurevesselwall.Becauseofthispotentialshiftawayfromathresholdfluencetowardanenergydependentdamagefunctionfordatacorrelation,ASTHStandardPracticeE853,"AnalysisandInterpretationofLightWaterReactor6-1 SurveillanceResults,"recommendsreportingdisplacementsperironatom(dpa)alongwithfluence(E>1.0MeV)toprovideadatabaseforfuturereference.TheenergydependentdpafunctiontobeusedforthisevaluationisspecifiedinASTMStandardPracticeE693,"CharacterizingNeutronExposuresinFerriticSteelsinTermsofDisplacementsperAtom."TheapplicationofthedpaparametertotheassessmentofembrittlementgradientsthroughthethicknessofthepressurevesselwallhasalreadybeenpromulgatedinRevision2totheRegulatoryGuide1.99,"RadiationDamagetoReactorVesselMaterials."ThissectionprovidestheresultsoftheneutrondosimetryevaluationsperformedinconjunctionwiththeanalysisoftestspecimenscontainedinsurveillanceCapsuleU.Fastneutronexposureparametersintermsoffastneutronfluence(E>1.0MeV),fastneutronfluence(E>0.1Mev),andironatomdisplacements(dpa)areestablishedforthecapsuleirradiationhistory.Theanalyticalformalismrelatingthemeasuredcapsuleexposuretotheexposureofthevesselwallisdescribedandused=toprojecttheintegratedexposureofthevesselitself.Alsouncertaintiesassociatedwiththederivedexposureparametersatthesurveillancecapsuleandwiththeprojectedexposureofthepressurevesselareprovided.6.2DiscreteOrdinatesAnalsisAplanviewofthereactorgeometryatthecoremidplaneisshowninFigure4-1.Eightirradiationcapsulesattachedtothethermalshieldareincludedinthereactordesigntoconstitutethereactorvesselsurveillanceprogram.Thecapsulesarelocatedatazimuthalanglesof4.0,40.0',140.0,176.0',184.0,220.0,320.0,and356.0relativetothecorecardinalaxesasshowninFigure4-1.AplanviewofasurveillancecapsuleholderattachedtothethermalshieldisshowninFigure6-1.Thestainlesssteelspecimencontainersare1.0inchsquareandapproximately38inchesinheight.Thecontainersarepositionedaxiallysuchthatthespecimensarecenteredonthecoremidplane,thusspanningthecentral3feetofthe12-foothighreactorcore.6-2 Fromaneutrontransportstandpoint,thesurveillancecapsulestructuresaresignificant.Theyhaveamarkedeffectonboththedistributionofneutronfluxandtheneutronenergyspectruminthewaterannulusbetweenthethermalshieldandthereactorvessel.Inordertoproperlydeterminetheneutronenvironmentatthetest'pecimenlocations,thecapsulesthemselvesmustbeincludedintheanalyticalmodel.Inperformingthefastneutronexposureevaluationsforthesurveillancecapsulesandreactorvessel,twodistinctsetsoftransportcalculationswerecarriedout.Thefirst,asinglecomputationintheconventionalforwardmode,wasusedprimarilytoobtainrelativeneutronenergydistributionsthroughoutthereactorgeometryaswellastoestablishrelativeradialdistributionsofexposureparameters(P(E>1.0Mev),P(E>=0.IMev),anddpa)throughthevesselwall.Theneutronspectralinformationwasrequiredfortheinterpretationofneutrondosimetrywithdrawnfromthesurveillancecapsuleaswellasforthedeterminationofexposureparameterratios;i.e.,dpa/P(E>1.0MeV),withinthepressurevesselgeometry.Therelativeradialgradientinformationwasrequiredtopermittheprojectionofmeasuredexposureparameterstolocationsinteriortothepressurevesselwall;i.e.,theI/4T,I/2T,and3/4Tlocations.Thesecondsetofcalculationsconsistedofaseriesofadjointanalysesrelatingthefastneutronflux(E>1.0MeV)atsurveillancecapsulepositions,andseveralazimuthallocationsonthepressurevesselinnerradiustoneutronsourcedistributionswithinthereactorcore.Theimportancefunctionsgeneratedfromtheseadjointanalysesprovidedthebasisforallabsoluteexposureprojectionsandcomparisonwithmeasurement.Theseimportancefunctions,whencombinedwithcyclespecificneutronsourcedistributions,yieldedabsolutepredictionsofneutronexposureatthelocationsofinterestforeachcycleofirradiation;andestablishedthemeanstoperformsimilarpredictionsanddosimetryevaluationsforallsubsequentfuelcycles.Itisimportanttonotethatthecyclespecificneutronsourcedistributionsutilizedintheseanalysesincludednotonlyspatialvariationsoffissionrateswithinthereactorcore;but,alsoaccountedfortheeffectsofvaryingneutronyield6-3 perfissionandfissionspectrumintroducedbythebuild-inofplutoniumasthetburnupofindividualfuelassembliesincreased.Theabsolutecyclespecificdatafromtheadjointevaluationstogetherwithrelativeneutronenergyspectraandradialdistributioninformationfromtheforwardcalculationprovidedthemeansto:l.Evaluateneutrondosimetryobtainedfromsurveillancecapsulelocations.2.Extrapolatedosimetryresultstokeylocationsattheinnerradiusandthroughthethicknessofthepressurevesselwall.3.Enableadirectcomparisonofanalyticalpredictionwithmeasurement.4.Establishamechanismforprojectionofpressurevesselexposureasthedesignofeachnewfuelcycleevolves.TheforwardtransportcalculationforthereactormodelsummarizedinFigures4-1and6-1wascarriedoutinR,8geometryusingtheDOTtwo-dimensionaldiscreteordinatescode~5~andtheSAILORcross-sectionlibrary~~.TheSAILORlibraryisa47groupENDFB-IVbaseddatasetproducedspecificallyforlightwaterreactorapplications.IntheseanalysesanisotropicscatteringwastreatedwithaP3expansionofthecross-sectionsandtheangulardiscretizationwasmodeledwithanSBorderofangularquadrature.Thereferencecorepowerdistributionutilizedintheforwardanalysiswasderivedfromstatisticalstudiesoflong-termoperationofWestinghouse4-loopplants.Inherentinthedevelopmentofthisreferencecorepowerdistributionistheuseofanout-infuelmanagementstrategy;i.e.,freshfuelonthecoreperiphery.Furthermore,fortheperipheralfuelassemblies,a2auncertaintyderivedfromthestatisticalevaluationofplanttoplantandcycletocyclevariationsinperipheralpowerwasused.Sinceitisunlikelythatasinglereactorwouldhaveapowerdistributionatthenominal+2u6-4 levelforalargenumberoffuelcycles,theuseofthisreferencedistributionisexpectedtoyieldsomewhatconservativeresults.AlladjointanalyseswerealsocarriedoutusinganS8orderofangularquadratureandtheP3cross-sectionapproximationfromtheSAILORlibrary.Adjointsourcelocationswerechosenatseveralazimuthallocationsalongthepressurevesselinnerradiusaswellasthegeometriccenterofeachsurveillancecapsule.Again,thesecalculationswereruninR,8geometrytoprovideneutronsourcedistributionimportancefunctionsfortheexposureparameterofinterest;inthiscase,P(E>1.0MeV).Havingtheimportancefunctionsandappropriatecoresourcedistributions,theresponseofinterestcouldbecalculatedas:R(r,8)-frf8fE)(r,8,E)S(r,8,E)rdrd8dEwhere:R(r,8)=P(E>1.0MeV)atradiusrandazimuthalangle8Adjointimportancefunctionatradius,r,azimuthalangle8,andneutronsourceenergyE.S(r,8,E)-Neutronsourcestrengthatcorelocationr,8andenergyE.Althoughtheadjointimportancefunctionsusedintheanalysiswerebasedonaresponsefunctiondefinedbythethresholdneutronflux(E>1.0MeV),priorcalculationshaveshownthat,whiletheimplementationoflowleakageloadingpatternssignificantlyimpact-themagnitudeandthespatialdistributionoftheneutronfield,changesintherelativeneutronenergyspectrumareofsecondorder.Thus,for,agivenlocationtheratioofdpa/P(E>1.0MeV)isinsensitivetochangingcoresourcedistributions.IntheapplicationoftheseadjointimportancefunctionstotheDCCookUnit2reactor,therefore,theirondisplacementrates(dpa)andtheneutronflux(E>0.1MeV)werecomputedonacyclespecificbasisbyusingdpa/It)(E.>1.0MeV)andP(E>0.1MeV)/P(E>1.0MeV)ratiosfromtheforwardanalysisinconjunctionwiththecyclespecificIl')(E>1.0MeV)solutionsfromtheindividualadjointevaluations.6-5 ThereactorcorepowerdistributionusedintheplantspecificadjointcalculationswastakenfromthefuelcycledesignreportsforthefirsteightoperatingcyclesofDCCookUnit2[17through19]SelectedresultsfromtheneutrontransportanalysesareprovidedinTables6-1through6-5.Thedatalistedinthesetablesestablishthemeansforabsolutecomparisonsofanalysisandmeasurementforthecapsuleirradiationperiodandprovidethemeanstocorrelatedosimetryresultswiththecorrespondingneutronexposureofthepressurevesselwall.InTable6-1,thecalculatedexposureparameters[P(E>1.0MeV),4(E>0.1MeV),anddpa]aregivenatthegeometriccenterofthetwosymmetricsurveillancecapsulepositionsforboththedesignbasisandtheplantspecificcorepowerdistributions.Theplantspecificdata,basedontheadjointtransportanalysis,aremeanttoestablishtheabsolutecomparisonofmeasurementwithanalysis.Thedesignbasisdataderivedfromtheforwardcalculationareprovidedasapointofreferenceagainstwhichplantspecificfluenceevaluationscanbecompared.SimilardataisgiveninTable6-2forthepressurevesselinnerradius.Again,thethreepertinentexposureparametersarelistedforboththedesignbasisandtheCycles1through8plantspecificpowerdistributions.Itisimportanttonotethatthedataforthevesselinnerradiusweretakenattheclad/basemetalinterface;and,'hus,representthemaximumexposurelevelsofthevesselwallitself.Radialgradientinformationforneutronflux(E>1.0MeV),neutronflux(E>0.1MeV),andironatomdisplacementrateisgiveninTables6-3,6-4,and6-5,respectively.Thedata,obtainedfromtheforwardneutrontransportcalculation,arepresentedonarelativebasisforeachexposureparameteratseveralazimuthallocations.ExposureparameterdistributionswithinthewallmaybeobtainedbynormalizingthecalculatedorprojectedexposureatthevesselinnerradiustothegradientdatagiveninTables6-3through6-5.6-6 Forexample,theneutronflux(E>1.0MeV)atthe1/4Tpositiononthe45'zimuthisgivenby:PI/4T(45').i$(220.27,45')F(225.75,45')where:p~/4T(45')Projectedneutronfluxatthe1/4Tpositiononthe45'zimuth4(220.27,45')Projectedorcalculatedneutronfluxatthevesselinnerradiusonthe45'zimuth.F(225.75,45')=RelativeradialdistributionfunctionfromTable6-3.SimilarexpressionsapplyforexposureparametersintermsofP(E>O.lMeV)anddpa/sec.6.3NeutronDosimetrThepassiveneutronsensorsincludedin.theDCCookUnit2surveillanceprogramarelistedinTable6-6.AlsogiveninTable6-6aretheprimarynuclearreactionsandassociatednuclearconstantsthatwereusedintheevaluationoftheneutronenergyspectrumwithinthecapsuleandthesubsequentdeterminationofthevariousexposureparametersofinterest[III(E>1.0Mev),P(E>O.lMeV),dpa].TherelativelocationsoftheneutronsensorswithinthecapsulesareshowninFigure4-2.Theiron,nickel,copper,andcobalt-aluminummonitors,inwireform,wereplacedinholesdrilledinspacersatseveralaxiallevelswithinthecapsules.Thecadmium-shieldedneptuniumanduraniumfissionmonitorswereaccommodatedwithinthedosimeterblocklocatednearthecenterofthecapsule.6-7 TheuseofpassivemonitorssuchasthoselistedinTable6-6doesnotyieldadirectmeasureoftheenergydependentfluxlevelatthepointofinterest.Rather,theactivationorfissionprocessisameasureoftheintegratedeffectthatthetime-andenergy-dependentneutronfluxhasonthetargetmaterialoverthecourseoftheirradiationperiod.Anaccurateassessmentoftheaverageneutronfluxlevelincidentonthevariousmonitorsmaybederivedfromtheactivationmeasurementsonlyiftheirradiationparametersarewellknown.Inparticular,thefollowingvariablesareofinterest:Thespecificactivityofeachmonitor.Theoperatinghistoryofthereactor.Theenergyresponseofthemonitor.Theneutronenergyspectrumatthemonitorlocation.Thephysicalcharacteristicsofthemonitor.Thespecificactivityofeachof-theneutronmonitorswasdeterminedusingestablishedASTMprocedures[20through33].Followingsamplepreparationandweighing,theactivityofeachmonitorwasdeterminedbymeansofalithium-driftedgermanium,Ge(Li),gammaspectrometer.TheirradiationhistoryoftheDCCookUnit2reactorduringCyclesIthrough8wasobtainedfromNUREG-0020,"LicensedOperatingReactorsStatusSummaryReport"fortheapplicableperiod.TheirradiationhistoryapplicabletoCapsuleUisgiveninTable6-7.MeasuredandsaturatedreactionproductspecificactivitiesaswellasmeasuredfullpowerreactionratesarelistedinTable6-8.ReactionratevalueswerederivedusingthepertinentdatafromTables6-6and6-7.ValuesofkeyfastneutronexposureparameterswerederivedfromthemeasuredreactionratesusingtheFERRETleastsquaresadjustmentcode~~.The6-8 FERRETapproachusedthemeasuredreactionratedataandthecalculatedneutronenergyspectrumatthethecenterofthesurveillancecapsuleasinputandproceededtoadjustapriori(calculated)groupfluxestoproduceabestfit(inaleastsquaressense)tothereactionratedata.Theexposureparametersalongwithassociateduncertaintieswherethenobtainedfromtheadjustedspectra.IntheFERRETevaluations,alog-normalleast-squaresalgorithmweightsboththeapriorivaluesandthemeasureddatainaccordancewiththeassigneduncertaintiesandcorrelations.Ingeneral,themeasuredvaluesfarelinearlyrelatedtothefluxPbysomeresponsematrixA:(s,)f(s)(~)ZAgiggwhereiindexesthemeasuredvaluesbelongingtoasingledatasets,gdesignatestheenergygroupand~delineatesspectrathatmaybesimultaneouslyadjusted.Forexample,RZ1gigrelatesasetofmeasuredreactionratesR;toasinglespectrumPbythemultigroupcrosssectiono;g.(Inthiscase,FERRETalsoadjuststhecross-sections.)Thelog-normalapproachautomaticallyaccountsforthephysicalconstraintofpositivefluxes,evenwiththelargeassigneduncertainties.IntheFERRETanalysisofthedosimetrydata,thecontinuousquantities(i.e.,fluxesandcross-sections)wereapproximatedin53groups.ThecalculatedfluxesfromthediscreteordinatesanalysiswereexpandedintotheFERRETgroupstructureusingtheSAND-IIcode~~.ThisprocedurewascarriedoutbyfirstexpandingtheapriorispectrumintotheSAND-II620groupstructureusingaSPLINEinterpolationprocedureforinterpolationinregionswheregroupboundariesdonotcoincide.The620-point.spectrumwastheneasilycollapsed6-9 tothegroupschemeusedinFERRET.Thecross-sectionswerealsocollapsedintothe53energy-groupstructureusingSANDIIwithcalculatedspectra(asexpandedto620groups)asweightingfunctions.ThecrosssectionsweretakenfromtheENDF/B-Vdosimetryfile.Uncertaintyestimatesand53x53covariancematriceswereconstructedforeachcrosssection.Correlationsbetweencrosssectionswereneglectedduetodataandcodelimitations,butareexpectedtobeunimportant.Foreachsetofdataorapriorivalues,theinverseofthecorrespondingrelativecovariancematrixMisusedasastatisticalweight.Insomecases,asforthecrosssections,amultigroupcovariancematrixisused.Moreoften,asimpleparameterizedformisused:2MggRN+RgRgPggwhereRNspecifiesanoverallfractionalnormalizationuncertainty(i.e.,completecorrelation)forthecorrespondingsetofvalues.ThefractionaluncertaintiesRspecifyadditionalrandomuncertaintiesforgroupgthatarecorrelatedwithacorrelationmatrix:I2P,(I-8)b',+8exp[~~~]9999272Thefirsttermspecifiespurelyrandomuncertaintieswhilethesecondtermdescribesshort-rangecorrelationsoverarange7(8specifiesthestrengthofthelatterterm).Fortheaprioricalculatedfluxes,ashort-rangecorrelationof76groupswasused.Thischoiceimpliesthatneighboringgroupsarestronglycorrelatedwhen8iscloseto1.Stronglong-rangecorrelations(oranticorrelations)werejustifiedbasedoninformationpresentedbyR.E.Maerker~~.Maerker'sresultsarecloselyduplicatedwhen76.Fortheintegralreactionratecovariances,simplenormalizationandrandomuncertai.ntieswerecombinedasdeducedfromexperimentaluncertainties.6-10 ResultsoftheFERRETevaluationoftheCapsuleUdosimetryaregiveninTable6-9.ThedatasummarizedinTable6-9indicatedthatthecapsulereceivedanintegratedexposureof1.58x10n/cm2(E>1.0MeV)withanassociatedeuncertaintyof+8X.Alsoreportedarecapsuleexposuresintermsoffluence(E>0.1MeV)andironatomdisplacements(dpa).SummariesofthefitIoftheadjustedspectrumareprovidedin"-Table6-10.Ingeneral,excellentresultswereachievedinthefitsoftheadjustedspectrumtotheindividualexperimentalreactionrates.TheadjustedspectrumitselfistabulatedinTable6-11fortheFERRET53energygroupstructure.AsummaryofthemeasuredandcalculatedneutronexposureofCapsuleUispresentedinTable6-12.Theagreementbetweencalculationandmeasurementfallswithin+8Xforallfastneutronexposureparameterslisted.Thethermalneutronexposurecalculatedfortheexposureperiodundepredictedthemeasuredvaluebyapproximatelyafactoroftwo.NeutronexposureprojectionsatkeylocationsonthepressurevesselinnerradiusaregiveninTable6-13.Alongwiththecurrent(8.65EFPY)exposurederivedfromtheCapsuleUmeasurements,projectionsarealsoprovidedforanexposureperiodof16EFPYandtoendofvesseldesignlife(32EFPY).Intheevaluationofthefutureexposureofthereactorpressurevesseltheexposureratesaveragedoverthefirsteightcyclesofoperationwereemployed.InthecalculationofexposuregradientsforuseinthedevelopmentofheatupandcooldowncurvesfortheDCCookUnit2reactorcoolantsystem,exposureprojectionsto16EFPYand32EFPYwerealsoevaluated.Databasedonbothafluence(E>1.0MeV)slopeandaplantspecificdpaslopethroughthevesselwallareprovidedinTable6-14.InordertoaccessRTNDTvs.fluence6-11 trendcurves,dpaequivalentfastneutronfluencelevelsforthe1/4Tand3/4Tpositionsweredefinedbytherelations~'I/4/)='I(I()(44(I())(I/4/)='I(II)(I(I())UsingthisapproachresultsinthedpaequivalentfluencevalueslistedinTable6-14.InTable6-15updatedleadfactorsarelistedforeachoftheDCCookUnit2surveillancecapsules.Thesedatamaybeusedasaguideinestablishingfuturewithdrawalschedulesfortheremainingcapsules.Inordertoprovideaconsistentdatabaseforcomparisonwithmeasuredshiftdata,thedosimetrysetsfrompreviouslywithdrawnsurveillancecapsules(X,Y,andT)werere-evaluatedusingthepreviouslydescribedleastsquaresadjustmentmethodologyalongwithcurrentreactioncross-sectionsandnucleardata.Theresultsofthosere-evaluationswereasfollows:FLUENCE[E>1.0MeV]CapsuleXCapsuleYCapsuleT1.O6X10>>6.83X102.64Xlol8ThelouncertaintyassociatedwitheachofthesefluenceevaluationsisSX.6-12
~00~0gg~~
TABLE6-1CALCULATEDFASTNEUTRONEXPOSUREPARAMETERSATTHESURVEILLANCECAPSULECENTERItI(E>1.0MeV)~ncm~sec2P(E>O.IMev)~ncm~sec2IronDisplacementRatedasec4.0'0.0'.0'0.0'.0'0.0'ESIGNBASIS2.82X10109.05X10108.15X103.04X10114.58X10lll.ssxlo-'0CYCLE1CYCLE2CYCLE3CYCLE4CYCLE5CYCLE6CYCLE7CYCLE82.12X106.682.29X106.622.21X105.462.19X105.47224X1010493193X10105192.12xlo'.04.7o1.66X10104.76X1010xlo'0xlo'0xlo'0X1010xloloX1010xlo'06.13X10106.62X10106.39X10106.33X10106.47xlo'05.58X10106.13X10104.80X10102.24X1O"2.22X10111.83X10111.84X1O"1.66X1O"1.74XIO"1.58X10111.60X10113.43X10113.71X10113.58X10113.55X10113.63X10-11313X10-113.43X10112.69X10111.14xlo-101.13X10109.34X10-119.35X10-118.43X10118.87X10118.04X1018.14X10-11 TABLE6-2CALCULATEDFASTNEUTRONEXPOSURERATESATTHEPRESSUREVESSELCLAD/BASEMETALINTERFACEE>I.OMeVnc~sec0.0'5.0'0.0'5.0'ESIGNBASIS6.43X10091.36X10101.72X10102.60X1010CYCLE1CYCLE2CYCLE3CYCLE4CYCLE5CYCLE6CYCLE7CYCLE86.34X10096.74X10096.43X10096.58xlo096.50X1009587xlp09639X104.92X1091.O1X1O'01.03X10109.59X10104X10109.54X10099.46X10099.99X10097.4oxlo091.26X101.94X10101.24X10101.92X10101.06X10101.60Xlolo1.11X10101.63X10109.83X101.46X101.02X101.53X10109.63X10091.41X10109.53X101.42X10E>0.1MeVncm2~sec0.0'5.0'0.0'5.0'ESIGNBASIS2.11X103.41X104.34X106.96X10CYCLE1CYCLE2CYCLE3CYCLE4CYCLE5CYCLE6CYCLE7CYCLE81.59X10101.69X10101.61X101.65X10101.63X10101.47X1011.60X101.23X10102.54X10103.18X105.04X1059Xlpl0312Xlplp499Xlplp2.41X10102.67X10104.16X10102.61X102.80X104.24X102.39X10102.48X10103.80X10102.37X10102.57X10103.98X1010251X1010243X1010367X1010186xlplo24pxlplp369Xlpl06-15 TABLE6-2(Continued)CALCULATEDFASTNEUTRONEXPOSURERATESATTHEPRESSUREVESSELCLAD/BASEMETALINTERFACEIronAtomDislacementRatedasec0.0'5.0'0.0'5.0'ESIGNBASIS1.37X10112.19X10112.73X104.26X10CYCLE1CYCLE2CYCLE3CYCLE4CYCLE5CYCLE6CYCLE7CYCLE81.03X10111.63X10-111.10X101.66X1011p5Xlp-ll154Xlp-ll1.07X10111.67X1011p6Xlp-ll154Xlp-llg57Xlp-12152Xlp-ll1.04X10111.61X10118.02X1021.19X1011ppXlp-ll3p8Xlp-llg7Xlp-ll3p5Xlp-ll1.69X10112.54X1076Xlp-ll25gXlp-ll1.56X1012.32X10111.62X10112.43X101153Xlp-ll224Xlp-ll1.52X102.26X10116-16 TABLE6-3RELATIVERADIALDISTRIBUTIONSOFNEUTRONFLUX(E>1.0MeV)WITHINTHEPRESSUREVESSELWALLRadius~cm0'5'0'5'20.27(1)220.64221.66222.99224.31225.63226.95228.28229.60230.92232.25233.57234.89236.22237.54238.86240.19241.51242.17(2)1.000.9770.8840.7580.6410.5370.4480.3720.3090.2550.2110.1740.1430.1170.09610.07830.06350.05110.04831.000.9780.8870.7620.6440.5400.4510.3730.3100.2570.2120.1750.1440.1180.09630.07830.06320.05010.04691.000.9790.8890.7650.6480.5450.4550.3790.3150.2610.2160.1780.1470.1210.09890.08070.06560.05190.04871.000.9770.8850.7560.6370.5340.4430.3670.3030.2500.2060.1690.1380.1130.09120.07360.05840.04540.0422NOTES:1)BaseMeta1InnerRadius2)BaseMeta1OuterRadius6-17 TABLE6-4hRELATIVERADIALDISTRIBUTIONSOFNEUTRONFLUX(E>0.1HeV)WITHINTHEPRESSUREVESSELWALLRadius~cmpo15'0'5'20.27(1)220.64221.66222.99224.31225.63226.95228.28229.60230.92232.25233.57234.89236.22237.54238.86240.19241.51242.17(2)1.001.001.000.9650.9160.8610.8030.7460.6890.6330.5780.5250.4740.4240.3750.3280.2830.2390.2291.001.000.9960.9580.9060.8490.7900.7320.6750.6190.5650.5130.4630.4140.3670.3220.2770.2320.2201.001.001.000.9680.9190.8650.8090.7520.6950.6400.5860.5340.4830.4330.3850.3380.2920.2450.2321.001.000.9940.9530.8980.8380.7770.7170.6570.6000.5440.4900.4370.3870.3380.2910.2440.1960.183NOTES:1)BaseMetalInnerRadius2)BasePetalOuterRadius6-18 TABLE6-5RELATIVERADIALDISTRIBUTIONSOFIRONDISPLACEMENTRATE(dpa)WITHINTHEPRESSUREVESSELWALLRadius0015'0'5'20.27(1)220.64221.66222.99224.31225.63226:95228.28229.60230.92232.25233.57234.89236.22237.54238.86240.19241.51242.17(2)1.000.9830.9130.8180.7280.6470.5740.5100.4530.4020.3560.3150.2770.2430.2120.1820.1550.1310.1251.000.9830.9140.8190.7280.6460.5730.5070.450.0.3990.3530.3120.2750.2410.2100.1810.1540.1280.1221.000.9840.9180.8270.7390.6590.5870.5230.4660.4140.3680.3270.2890.2540.2220.1920.1640.1370.1301.000.9830.9150.8200.7300.6470.5730.5070.4490.3970.3490.3070.2690.2330.2010.1700.1410.1130.106NOTES:1)BaseMeta1InnerRadius2)BaseMeta1OuterRadius6-19 TABLE6-6NUCLEARPARAMETERSFORNEUTRONFLUXMONITORSMonitorMaterialReactionofInterestTargetWeightFractionResponse~RaneProductHalf-LifeFissionYield~XCopperIronNickelUranium-238*Cu(n,e)CoFe4(n,p)HnNi58(n,p)Co58U238(nf)Cs1370.69170.05820.68301.0E>4.7MeVE>1.0MeVE>1.0MeVE>0.4HeV5.272yrs312.2-days70.90days30.12yrs5.99Neptunium-237*Np(n,f)CsCobalt-Aluminum*Co(n,y)CoCobalt-AluminumCo(n,y)Co1.0E>0.08MeV30.12yrs0.0015-:E>0.015MeV5.272yrs0.00150.4ev>E>0.015HeV5.272yrs6.50*Denotesthatmonitoriscadmiumshielded.
TABLE6-.7MONTHLYTHERMALGENERATIONDURINGTHEFIRSTEIGHTFUELCYCLESOFTHEDCCOOKUNIT2REACTOR3/784/785/786/787/788/789/7810/7811/7812/781/792/793/794/795/796/797/798/799/7910/79ll/7912/79l/802/803/804/805/806/807/808/809/8010/8011/8012/801/812/813/814/815/816/817/818/8153096521821653969136547812470831529472217877922311198482382476056224071422205622483455216426914493470225816425136902266726152234600584404220940324187992354329248325021876111408949249659423937831414143014887582505373227168410538770449803237420217758772338703THERMALGENERATION~MONTNW-hTHERMALGENERATIONMW-h243071428478424358482517865229594421961908335552391274251693723311682496782101151722413322293400157531103415342242228253360224282342461540185146117113733436372693211188161453959383687435731235476733977000417277341526325725423846056182059199361108271484IIONTII9/8110/8111/8112/811/822/823/824/825/826/827/828/829/8210/8211/8212/821/832/833/834/835/836/837/838/8329/83210/8311/8312/8321/8422/8423/844/845/846/847/8418/8429/84210/842ll/84212/8411/8512/852THERMALGENERATIONTHMW-h246148824495232532441245162310490026063901632491372641201934720436401360957000098098020340551973118201457919742082039056203932517760491596034565732080553184977014097631485651012580921973726199508820398141900060203846614326390000rMON3/854/855/856/857/858/859/8510/8511/8512/851/862/863/864/865/866/867/868/869/8610/8611/8612/861/872/873/874/875/876/877/878/879/8710/8711/8712/871/882/883/884/885/886/887/888/8880NTH0000007752602288800253045012973152508038215583024521432493553235581724543078611302282581253406724528832165049176722200001338296188793525330402110364224178224471362495857241016624351505909072357045251913119127202474282244252712191689/8810/8811/8812/881/892/893/894/895/896/897/898/899/8910/8911/8912/891/902/903/904/905/906/907/908/909/9010/90ll/9012/901/912/913/914/915/916/917/918/919/9110/91ll/9112/911/922/92THERMALGENERATION~MII-h6-21 TABLE6-8MEASUREDSENSORACTIVITIESANDREACTIONRATESMonitorandxialLocationMeasuredActivitydissec-mSaturatedActivitydissec-mCapsuleCenterReactionRate~IIPNULiUCu-63(n,a)Co-60Top-MiddleMiddleBottom-MiddleAverage1.23x1051.23x1051.24x1051.23x1052.67x1052.67x1052.70x1052.68x1053.94x1017Fe-54(n,p)Mn-54TopTop-MiddleMiddleBottom-MiddleBottomAverage9.19x1059.45x1059.50x1058.59x1059.30x1059.21x1052.15x1062.21x1062.22x1062.01x1062.18x1062.15x1063.64x10-15Ni-58(n,p)Co-58TopMiddleBottomAverage3.93x1063.93x1063.96x1063.94x1063.21x1073.21x1073.24x1073.22x1075.41x1015U-238(n,f)Cs-137(Cd)Middle4.88x1052.94x1061.94x10146-22 TABLE6-8MEASUREDSENSORACTIVITIESANDREACTIONRATES-cont'dMonitorandxialLocationMeasuredActivitydissec-mSaturatedActivitydissec-mCapsuleCenterReactionRate~IIPNUCLEUSNp-237(n,f)Cs-137(Cd)Middle4.26x1062.57x1071.61x1013Co-59(n,y)Co-60TopBottomAverage1.88x1071.74x1071.81x1074.09x1073.78x1073.94x1072.70x1012Co-59(n,y)Co-60(Cd)Bottom32x1061.59x107120x10-126-23 TABLE6-9SUMMARYOFNEUTRONDOSIMETRYRESULTSTIMEAVERAGEDEXPOSURERATESP(E>1.0MeV){'n/cm2-sec}4(E>0.1MeV)(n/cm2-sec}dpa/sec4(E<0.414eV)(n/cm2-sec}5.78x10102.00x10119.78x10-116.29x1010+15X+10X+20X(E>1.0MeV)(n/cm2}4(E>0.1MeV)(n/cm2}dpaINTEGRATEDCAPSULEEXPOSURE1.58x105.46x102.67x102+15X+10X4'E<0414eV)(n/cm2}1.72x1019+20XNOTE:Tota1IrradiationTime=8.65EFPY6-24 TABLE6-10COMPARISONOFMEASUREDANDFERRETCALCULATEDREACTIONRATESATTHESURVEILLANCECAPSULECENTERReactionpeas~edAdjustedCalcuationCu-63(n,a)Co-60Fe-54(n,p)Mn-54Ni-58(n,p)Co-58U-238(n,f)Cs-137(Cd)Np-237(n,f)Cs-137(Cd)Co-59(n,y)Co-60Co-59(n,y)Co-60(Cd)3.94xl0173.64xl0155.41xl0151.94xlo-'41.6lx10132.70x10121.20xl0123.94x10173.74x10155.28xl0151.93xl0141.61xl0132.69X10-121.20x10121.001.030.981.001.001.001.006-25 TABLE6-11ADJUSTEDNEUTRONENERGYSPECTRUMATTHESURVEILLANCECAPSULECENTERGroupEnergyAdjusyedFlux(Mev)(n/cm-sec)GroupEnergy(Mev)Addus/edFlux(n/cm-sec)12345678910ll121314151617181920212223242526271.73xl011.49xl011.35xl011.16xl01l.ooxlol8.61x1007.4lx1006.07xl004.97x1003.68xl002.87xl002.23xl001.74xl001.35xl00l.llxl008.2lx1016.39xlO14.98x1013.88x10I3.02xlO11.83x101l.llxlO16.74xlO24.09x1022.55xlO21.99xlO21.50xlO23.36x1068.20xl063.76x1079.5lx1072.29xl084.llxl089.86xl081.42xl092.92x1093.69xl097.37xl099.24x109,1.21x10101.22xl0102.08xl0102.22x10102.18x10101.55xl0102.05xl0102.27x10102.16xl0101.71xl0101.23xl0107.42xl098.90xl094.83xl096.52xl09282930~31323334353637383940414243444546474849505152539.12x1035.53x1033.36x1032.84x1032.40xlO32.04xlO31.23xlO37.49xlO44.54xlO42.75x1041.67xlO41.0lxlO46.14x1053.73xlO52.26xlO51.37xlO5832xlO65.04xlO63.06xlO61.86xlO61.13x1066.83xlO74.14x1072.51x1071.52x1079.24xlO88.36xl091.05xl0103.25xl093.09x1092.98x1098.60xl098.31xl097.99xl097.73x1098.15xl098.85xl098.8lxl098.79xl098.66xl098.48xl098.31x1098.02xl097.55xl097.18x1096.72xl095.29xl096.28x1091.03xl0101.05xl0101.05x10103.16x1010NOTE:Tabulatedenergylevelsrepresenttheupperenergyofeachgroup.6-26 0TABLE6-12COMPARISONOFCALCULATEDANDMEASUREDEXPOSURELEVELSFORCAPSULEUCalculatedMeasured~CMC(E>1.0MeV)(n/cm)4(E>O.1MeV)(n/cm)1.49x10195.01xIO>>1.58x10195.46x10190.940.92dpa2.55x1022.67x1020.96%(E<0.414eV){n/cm)8.84x10181.72x10190.516-27 TABLE6-13NEUTRONEXPOSUREPROJECTIONSATKEYLOCATIONSONTHEPRESSUREVESSELCLAD/BASEHETALINTERFACE8.65EFPY(E>1.0Hev)[n/cm2](E>O.lHeV)[n/cm2]IronAtomDisplacements[dpa](E>1.0Hev)[n/cm2]C(E>O.lHeV)[n/cm2]IronAtomDisplacements[dpa](E>1.0Hev)[n/cm2](E>O.lHeV)[n/cm2]IronAtomDisplacements[dpa]45'.65X10'84.48X1016.12X1016.95X1017.79X101.21X1012.92X103.93X104.46X104.91X107.39X1016.0EFPY15'0'5'.31X10184.51X10185.12X10185.72X10188.58X1018.8.28X10181.13X10191.29X101.44X10192.23X10195.40X107.26X1038.24X109.09X101.36X1032.0EFPY45'.63X109.02X101.02X101.14X101.71X101.66X102.26X102.56X102.87X104.45X101.08X1021.45X1021.64X1021.81X1022.72X10 TABL14NEUTRONEXPOSUREVALUESFORUSEINTHEGENERATIONOFHEATUP/COOLDOWNCURVESNEUTRONFLUENCEE>1.0HeVSLOPE(n/cm)16EFPY~daSLOPE(equivalentn/cm2)Surface~14T~34TSurface~14T~34T0010'5'0'5'.31x10184.51xlp5.12x10185.72x108.58x10181.75xlp2.40x10182.72x10183.07x10184.51x103.61x10174.96x10175.63x10176.46x10179.01x10173.31x10184.51xlp5.12x10185.72x108.58x10'.12x10182.88x10183.27x10183.73x105.49xlpl7.69x10171.04x10181.18x10181.38x10181.90x10NEUTRONFLUENCEE>1.0HeVSLOPE(n/cm)32EFPY~daSLOPE(equivalentn/cm2)Surface~14T34TSurface14T~34T0010'5'0'56.63x109.02x101.02x101.14x10'91.71x103.51x10184.80x10185.45xlp6.15x10189.02x10187.22x10179.92x10171.13x10181.29x10181.80x10186.63x109.P2x1P181.02x10'91.14x10191.71x104.24x1018x1P186.54x10187.46x1P181.10x10'91.54x10182.07x10182.35x10182.77x10183.79x10186-29 TABLE6-15UPDATEDLEADFACTORSFORDCCOOKUNIT2SURVEILLANCECAPSULES~CasuleLeadFactorTXUYSVWZ344(a)341(c)340(d)344(b)130(d)1.30(d)1.30(d)1.30(d)(a)PlantspecificevaluationbasedonendofCycle1calculatedfluence.(b)PlantspecificevaluationbasedonendofCycle3calculatedfluence.(c)PlantspecificevaluationbasedonendofCycle5calculatedfluence.(d)PlantspecificevaluationbasedonendofCycle8calculatedfluence.6-30 SECTION7.0SURVEILLANCECAPSULEREMOVALSCHEDULEThefollowingremovalschedulemeetsASTME185-82andisrecommendedforfuturecapsulestoberemovedfromtheD.C.CookUnit2reactorvessel:CapsuleCapsuleLocationLead(deg.)FactorRemovalTime()EstimatedFluence(n/cm2)4032022014043561841763.443.443.443.441.301.301.301.301.08(Removed)3.24(Removed)5.27(Removed)8.65(Removed)32StandbyStandbyStandby2.64x6.83x1.06x1.58x2.22X10(Actual)10(Actual)10(Actual)1019(Actual)10'9(a)EffectiveFullPowerYears(EFPY)fromplantstartup.7-1 SECTION
8.0REFERENCES
1.J.A.Davidson,etal.,"AmericanElectricPowerCompanyDonaldC.CookUnitNo.2ReactorVesselRadiationSurveillanceProgram",WCAP-8512,November1975.2.CodeofFederalRegulations,10CFR50,AppendixG,"FractureToughnessRequirements",andAppendixH,"ReactorVesselMaterialSurveillanceProgramRequirements,"U.S.NuclearRegulatoryCommission,Washington,D.C.3.RegulatoryGuide1.99,ProposedRevision2,"RadiationDamagetoReactorVesselMaterials",U.S.NuclearRegulatoryCommission,Hay1988.4.SectionIIIoftheASMEBoilerandPressureVesselCode,AppendixG,"ProtectionAgainstNonductileFailure."5.ASTME208,"StandardTestMethodforConductingDrop-WeightTesttoDetermineNil-DuctilityTransitionTemperatureofFerriticSteels."6.ASTHE185-82,"StandardPracticeforLight-WaterCooledNuclearPowerReactorVessels,E706(IF)."7.ASTHE23-88,"StandardTestMethodsforNotchedBarImpactTestingofMetallicMaterials."8.ASTHA370-89,"StandardTestMethodsandDefinitionsforMechanicalTestingofSteelProducts."9.ASTME8-89b,"StandardTestMethodsofTensionTestingofMetallicMaterials."10.ASTHE21-79(1988),"StandardPracticeforElevatedTemperatureTensionTestsofMetallicMaterials."8-1 ll.ASTME83-85,"StandardPracticeforVerificationandClassificationofExtensometers."12.SwRIProjectNo.02-5928,"ReactorVesselMaterialSurveillanceProgramforDonaldC.CookUnitNo.2AnalysisofCapsuleT",E.B.Norris,September16,1981.013.SwRIProjectNo.06-7244-002,"ReactorVesselMaterialSurveillanceProgramforDonaldC.CookUnitNo.2AnalysisofCapsuleY",E.B.Norris,February1984.14.SwRIProjectNo.06-8888,"ReactorVesselMaterialSurveillanceProgramforDonaldC.CookUnitNo.2AnalysisofCapsuleX",P.K.NairandM.L.Williams,Hay1987.15.R.G.Soltesz,R.K.Disney,J.Jedruch,andS.L.Ziegler,"NuclearRocketShieldingMethods,Modification,UpdatingandInputDataPreparation.Vol.5-Two-DimensionalDiscreteOrdinatesTransportTechnique",WANL-PR(LL)-034,Vol.5,August1970.16."ORNLRSCIDataLibraryCollectionDLC-76SAILORCoupledSelf-Shielded,47Neutron,20Gamma-Ray,P3,CrossSectionLibraryforLightWaterReactors".17.AEPLetterRBB88-005/4,R.B.Bennett(AEP)toH.C.Walls(Westinghouse),January29,1988.18.AEPFAX,G.John(AEP)toS.L.Anderson(Westinghouse),October6,1992.19.B.J.Johansen,et.al.,"NuclearParametersandOperationsPackagefortheDonaldC.CookNuclearPlant(Unit2,Cycle8)",WCAP-12651,October1990.(Proprietary)20.ASTMDesignationE482-89,"StandardGuideforApplicationofNeutronTransportMethodsforReactorVesselSurveillance",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.8-2 21.ASTMDesignationE560-84,"StandardRecommendedPracticeforExtrapolatingReactorVesselSurveillanceDosimetryResults",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.22.ASTHDesignationE693-79,"StandardPracticeforCharacterizingNeutronExposuresinFerriticSteelsinTermsofDisplacementsperAtom(dpa)",inASTMStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.23.ASTMDesignationE706-87,"StandardMasterMatrixforLight-WaterReactorPressureVesselSurveillanceStandard",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.24.ASTMDesignationE853-87,"StandardPracticeforAnalysisandInterpretationofLight-WaterReactorSurveillanceResults",inASTMStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.25.ASTHDesignationE261-90,"StandardMethodforDeterminingNeutronFlux,Fluence,andSpectrabyRadioactivationTechniques",inASTMStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.26.ASTMDesignationE262-86,"StandardMethodforMeasuringThermalNeutronFluxbyRadioactivationTechniques",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.27.ASTMDesignationE263-88,"StandardMethodforDeterminingFast-NeutronFluxDensitybyRadioactivationofIron",inASTMStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.28.ASTHDesignationE264-87,"StandardMethodforDeterminingFast-NeutronFluxDensitybyRadioactivationofNickel",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.8-3 29.ASTMDesignationE481-86,"StandardMethodforMeasuringNeutron-FluxDensitybyRadioactivationofCobaltandSilver",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.30.ASTMDesignationE523-87,"StandardMethodforDeterminingFast-NeutronFluxDensitybyRadioactivationofCopper",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.31.ASTHDesignationE704-90,"Standard.MethodforMeasuringReactionRatesbyRadioactivationofUranium-238",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.32.ASTMDesignationE705-90,"StandardMethodforMeasuringFast-NeutronFluxDensitybyRadioactivationofNeptunium-237",inASTHStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.33.ASTMDesignationE1005-84,"StandardMethodforApplicationandAnalysisofRadiometricMonitorsforReactorVesselSurveillance",inASTMStandards,Section12,AmericanSocietyforTestingandMaterials,Philadelphia,PA,1991.34.F.A.Schmittroth,FERRETDataAnalsisCore,HEDL-THE79-40,HanfordEngineeringDevelopmentLaboratory,Richland,WA,September1979.35.W.N.HcElroy,S.BergandT.Crocket,AComuter-AutomatedIterativeMethodofNeutronFluxSectraDeterminedbFoilActivation,AFWL-TR-7-41,Vol.I-IV,AirForceWeaponsLaboratory,KirklandAFB,NM,July1967.36.EPRI-NP-2188,"DevelopmentandDemonstrationofanAdvancedMethodologyforLWRDosimetryApplications",R.E.Maerker,etal.,1981.
APPENDIXALoad-TimeRecordsforCharpySpecimenTestsA-0 Wi-P~=MAXIMUMLOADP-FRACTURELQaOPGY.NGENERALYIELOLQAOIIIIIIIItGYjIIIIIIIIIIII.I.IIIPA*ARRESTLQAOmairivEb'igureA-1.Ideali.oad-timerecord CIv'EN2"U"DQiL45NL45g~aa~D~8I~6TILE2+4(lCEC>3024.0'iEN2U"OCIRA8N48~DeBIo6TItK2e4(ttSEC>3I24+0FigureA-2.Load-timerecordsforSpecimensML45andML48'
'EN2'U"OCttt42orC9CUwl.De8I~62e4TIttE<ttSEC>3024+0XI2"u'Cttt.44~DI6TItK2e4CtCEC>3024m0FigureA-3.Load-timerecordsforSpecimensML42andML44 CleE12"UOCt1L.4101.41w~C9~Do81~6T11K2e4(tSEC>3024.0'A02'U"DCtL43Plg~O0(U8~D~81+624TI%(NSEC>3e24m0FigureA-4.Load-timerecordsforSpecimensML41andML43
- E<<2"U"OCttL46g~oRCIeD~81~6TIttE2e<(tSEC)3e24.0CIEI2'U"ge~D~81e6TIttE2e4CtSEC)3024e0FigureA-5.Load-timerecordsforSpecimensML46andML47
~CNT62NT62eD~81.6TINE2,4<tSEC)3e24,0CIQNUNOCNT6INT6ICl~D~8I~6TINE2,4CtSEC)3e24o0FigureA-6.Load-timerecordsforSpecimensMT62andMT61 lgI2%USttT66Pl~~oroDo81~6Tlt1E<tCEC)2+43o24e0CllOX12'U"g~arS0GiCL'CI~D~81~6T1tK2+4CNSEC)3024e0FigureA-7.Load-timerecordsforSpecimensMT66andMT71 OCNT64HT64~8I6TilKRe4CNSEC)30R4+0'iEIR"Ui+67itKRe4(ICEC)30R4m0FigureA-8.Load-timerecordsforSpecimensMT64andMT72
'E02OU>>OcttT70ttTPOrarQOlPOl~4~p~8I~6L4TIttECtCKC)3024e0vEN2"U"OCttT69ttT69gcoorgOlCO~D~8I~62e4TItK.<tSEC)3t24e0FigureA-9.Load-timerecordsforSpecimensMT70andMT69
'EN2"UDMT63tlT63CCOCUDD~D<<8I~6TIttE2e4(CEC)3124e0CI%0aI2"UOCttT68gEOoWC9IcUO~D~~8I~62+4TIttECHSEC)3024,0FigureA-10.Load-timerecordsforSpecimensMT63andMT68
~EgeiuNT67C)~D1.6TINEReh<NSEC)308ho0Xia"uNT65g~oC9IcUo~De8Ie6TINE8+4(!CEC)3og4.0FigureA-ll.Load-timerecordsfor.SpecimensM'Z67andMT65
'EIIQNUNIIII70XIDo8le6TltlEBo4(tlSEC)3084e0CI181QNOCt0I64IDI64gcoe~XCI~D~81.68+4.TItIE<IISEC)3084m0FigureA-12.Load-timerecordsforSpecimensMW70andMW64
'EN2"U".OCtNl71.e81~6TlttE2o4(NSEC)3124m0XN2'U"<<81~624TI%(tCEC)3024+0FigureA-13,Load-timerecordsforSpecimensMW71andMW68 o~iENR"U"OCMtt63ttll63PloCUo~D~81~6TittERe4(tCEC)3t24e0~DXNRUOCtttt61tNt61COo~De81~6TINERo4<tSEC)3024o0FigureA-14.Load-timerecordsforSpecimensMW63andMW61 OQSU%OCtCl78C9~D~8I+6TItKRe4<NSEC)3o84e0OX18U"g~oXD~81.6TIlKRo4<tLXC)3084+0FigureA-15.Load-timerecordsforSpecimensMW72andMW65
'EtJR"U"OCt0J66NJJ66oaAJ.D.81.6R.4TiNE(NSEC>30R4.0uEttR"U"OCNJJ6RAJ~4O~D.8i+6TINERo4CNSEC)30R40FigureA-16.Load-timerecordsforSpecimensMW66andMW62 PloIDCl0(UaCl~8I+62+4TINE<ttSEC)3.24.0CI'E<<2U"OCtSI69Nt69hoQcUDCU~D~8I.62.4TIlK<tCEC)3024,0FigureA-17.Load-timerecordsforSpecimensMW67andMW69 olEIIQNUNOCtIK67tQt67g~oDAI~IDAl.D~81.6TlttERl4(ttSEC)3084.0~EIQIIUNOcttK63ttK63a~oClC9DAI5lD.81.62.4TIE(ttSEC)3.24.0FigureA-18.Load-timerecordsforSpecimensMH67andMH63 vEN2"U"PlWoIDC9oDo8I~62+4TINE(NSEC>3@24~0XN2U"OCNH69Ntt69g~'CU~4O~Do81.62,4TINECNSEC>3124.0FigureA-19.Load-timerecordsforSpecimensMH71andMH69 N2"U"Oct1H72r~oCJJC9C-iCIJEZoCU,81.62o4TIttECtCEC)3.24e0ZN2Ug~omCJJC9OCUcZCICU~D.81,6TltCE2.4CtSEC)3024.0FigureA-20.Load-timerecordsforSpecimensMH72andMH70 v'Ett2"UOCtN62t%62xoO.De81.6TIttE2.4(NSEC)3t24.0'IEtt2HU$OCt%64ttH64"aC9oD8l,6TIttE2+4(ttSEC)3.24.0FigureA-21.Load-timerecordsforSpecimensMH62andMH64
'eiENB"U"OCNH61NH61olEa0INa0O.D.81.62ehTINE<NSEC)3084.0'ENR"U"OCNH65o~D~8Io6TINER.h(t5EC)3084.0FigureA-22.Load-timerecordsforSpecimensMH61andMH65 g2NUN0Ct%68W68aNaoD.81~62.4TllC<ICEC)4.0'EN2"U"OCt%66A<66eD~81~62e4TllC(NSEC)3024o0FigureA-23.Load-timerecordsforSpecimensMH68andMH66 APPENDIXBPhotographsofCharpy,TensileandWOLSpecimensPriortoTestingB-0 FigureB-1.CharpyimpactspecimensML45,ML48,ML42,andML44fromIntermediateShellPlateC5521-2(longitudinalorientation)beforetesting.B-IRM-28359 FigureB-2.CharpyimpactspecimensML41,ML43,ML46,andML47fromIntermediateShellPlateC5521-2(longitudinalorientation)beforetesting.B-2RM-28360 FigureB-3.CharpyimpactspecimensMT62,MT61,MT66,MT71,MT64,andMT72fromIntermediateShellPlateC5521-2(transverseorientation)beforetesting.8-3RM-28361 FigureB-4.CharpyimpactspecimensMT70,MT69,MT63,MT68,MT67,andMT65fromIntermediateShellPlateC5521-2(transverseorientation)beforetesting.RM-28362 FigureB-5.CharpyimpactspecimensMW70,MW64,MW71,MW68,MW63,andMW61fromtheweldmetal,beforetesting.B-5RM-28363 FigureB-6.CharpyimpactspecimensMW72,MW65,MW66,MW62,MW67,andMW69fromtheweldmetal,beforetesting.B-6RM-28364 FigureB-7.CharpyimpactspecimensMH67,MH63,MH71,MH69,MH72,andMH70fromtheheat-affectedzone(HAZ),beforetesting.B-7RM-28365 FigureB-8.CharpyimpactspecimensMH62,MH64,MH61,MH65,MH68,andMH66fromtheheat-affectedzone(HAZ),beforetesting.B-8RM-28366 FigureB-9.TensilespecimensMTllandMT12fromD.C.CookUnit2reactorvesselIntermediateShellPlateC5521-2(transverseorientation)beforetesting.B-9RM-28367 FigureB-10.TensilespecimensMWllandMW12fromD.C.CookUnit2reactorvesselweldbeforetesting.B-10RM-28368 FigureB-11.WOLspecimensMW5,MW6,MW7andMW8,fromD.C.CookUnit2reactorvessel.Thespecimenswerenottested,butstoredforfuturereference,B-11RM-28369 APPENDIXCHeatupandCooldownLimitCurvesforNormalOperationC-0 TABLEOFCONTENTSSectionTitle~acae1INTRODUCTIONC-42FRACTURETOUGHNESSPROPERTIESC-43CRITERIAFORALLOWABLEPRESSURE-TEMPERATURERELATIONSHIPSC-54HEATUPANDCOOLDOWNLIMITCURVES5ADJUSTEDREFERENCETEMPERATUREC-8C-106REFERENCESC-24 LISTOFILLUSTRATIONS~FiereTitle~~Pa<ac1D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst32EFPY(WithoutMarginsForInstrumentationErrors)C-162D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst32EFPY(WithMarginsof10'Fand60psigForInstrumentationErrors)C-173D.C.CookUnit2ReactorCoolantSystemCooldown(CooldownRatesupto100'F/hr)LimitationsApplicablefortheFirst32EFPY(WithoutMarginsForInstrumentationErrors)C-184D.C.CookUnit2ReactorCoolantSystemCooldown(CooldownRatesupto100'F/hr)LimitationsApplicablefortheFirst32EFPY(WithMarginsof10'Fand60psigForInstrumentationErrors)C-195D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60F/hr)ApplicablefortheFirst15EFPY(WithoutMarginsForInstrumentationErrors)C-20D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst15EFPY(WithMarginsof10'Fand60psigForInstrumentationErrors)C-217D.C.CookUnit2ReactorCoolantSystemCooldown(CooldownRatesupto100'F/hr)LimitationsApplicablefortheFirst15EFPY(WithoutMarginsForInstrumentationErrors)C-22C-2 LISTOFILLUSTRATIONScontinuedFiciureTitlePacae8D.C.CookUnit2ReactorCoolantSystemCooldown(CooldownRatesupto100'F/hr)LimitationsApplicablefortheFirst15EFPY(WithHarginsof10'Fand60psigForInstrumentationErrors)C-23LISTOFTABLESTableTitle~PaeD.C.CookUnit2ReactorVesselToughnessTable(Unirradiated)C-11SummaryofAdjustedReferenceTemperature(ART)at1/4Tand3/4TLocationfor32EFPYC-123SummaryofAdjustedReferenceTemperature(ART)at1/4Tand3/4TLocationfor15EFPYC-13CalculationofAdjustedReferenceTemperaturesforLimitingD.C.CookUnit2ReactorVesselHaterial-IntermediateShellPlate,C5556-2for32EFPYC-145CalculationofAdjustedReferenceTemperaturesforLimitingD.C.CookUnit2ReactorVesselHaterial-IntermediateShellPlate,C5556-2for15EFPYC-15C-3 1.INTRODUCTIONHeatupandcooldownlimitcurvesarecalculatedusingthemostlimitingvalueofRTNDT(referencenil-ductilitytemperature)forthereactorvessel.ThemostlimitingRTNDTofthematerialinthecoreregionofthereactorvesselisdeterminedbyusingthepreservicereactorvesselmaterialfracturetoughnesspropertiesandestimatingtheradiation-inducedhRTNDT.RTNDTisdesignatedasthehigherofeitherthedropweightnil-ductilitytransitiontemperature(NDTT)orthetemperatureatwhichthematerialexhibitsatleast50ft-lbofimpactenergyand35-millateralexpansion(normaltothemajorworkingdirection)'minus60'F.RTNDTincreasesasthematerialisexposedtofast-neutronradiation.Therefore,tofindthemostlimitingRTNDTatanytimeperiodinthereactor'slife,ARTNDTduetotheradiationexposureassociatedwiththattimeperiodmustbeaddedtotheoriginalunirradiatedRTNDT.TheextentoftheshiftinRTNDTisenhancedbycertainchemicalelements(suchascopperandnickel)presentinreactorvesselsteels.TheNuclearRegulatoryCommission(NRC)haspublishedamethodforpredictingradiationembrittlementinRegulatoryGuide1.99Rev.2(RadiationEmbrittlementofReactorVesselMaterials)~~.RegulatoryGuide1.99,Revision2isusedforthecalculationofRTNDTvaluesat1/4Tand3/4Tlocations(Tisthethicknessofthevesselatthebeltlineregion).2.FRACTURETOUGHNESSPROPERTIESTheunirradiatedRTNDTvaluesforthebeltlineregionmaterialsintheD.C.CookUnit2reactorvesselwereestablishedusingtheguidanceprovidedinNUREG-0800,BranchTechnicalPosition,NTEB5-2~~,andsubarticaleNB-2331oftheASHEBoilerandPressureVesselCode,SectionIII~~.Thepre-irradiationfracture-toughnesspropertiesoftheD.C.CookUnit2reactorvesselarepresentedinTablel.C-4 3.CRITERIAFORALLOWABLEPRESSURE-TEMPERATURERELATIONSHIPSTheASMEapproachforcalculatingtheallowablelimitcurvesforvariousheatupandcooldownratesspecifiesthatthetotalstressintensityfactor,KI,forthecombinedthermalandpressurestressesatanytimeduringheatuporcooldowncannotbegreaterthanthereferencestressintensityfactor,KIR,forthemetaltemperatureatthattime.KIRisobtainedfromthereferencefracturetoughnesscurve,definedinAppendixGtotheASMECode~~.TheKIRcurveisgivenbythefollowingequation:KIR=26.78+1.223exp[0.0145(T-RTNDT+160)]whereKIR=referencestressintensityfactorasafunctionofthemetaltemperatureTandthemetalreferencenil-ductilitytemperatureRTNDTTherefore,thegoverningequationfortheheatup-cooldownanalysisisdefinedinAppendixGoftheASMECode~~asfollows:CKIM+KIT<KIRwhere(2)KIM-stressintensityfactorcausedbymembrane(pressure)stressKIT=stressintensityfactorcausedbythethermalgradientsKIR=functionoftemperaturerelativetotheRTNDTofthematerial=2.0forLevelAandLevelBservicelimits=1.5forhydrostaticandleaktestconditionsduringwhichthereactorcoreisnotcriticalAtanytimeduringtheheatuporcooldowntransient,KIRisdeterminedbythemetaltemperatureatthetipofthepostulatedflaw,theappropriatevalueforRTNDT,andthereferencefracturetoughnesscurve.Thethermalstressesresultingfromthetemperaturegradientsthroughthevesselwallarecalculatedandthenthecorresponding(thermal)stressintensityfactors,KIT,fortheC-5 referenceflawarecomputed.Fromequation2,thepressurestressintensityfactorsareobtainedand,fromthese,theallowable.pressuresarecalculated.Forthecalculationoftheallowablepressureversuscoolanttemperatureduring,cooldown,thereferenceflawofAppendixGtotheASHECodeisassumedtoexistattheinsideofthevesselwall.Duringcooldown,thecontrollinglocationoftheflawisalwaysattheinsideofthewallbecausethethermalgradientsproducetensilestressesattheinside,whichincreasewithincreasingcooldownrates.Allowablepressure-temperaturerelationsaregeneratedforbothsteady-stateandfinitecooldownratesituations.Fromtheserelations,compositelimitcurvesareconstructedforeachcooldownrateofinterest.Theuseofthecompositecurveinthecooldownanalysisisnecessarybecausecontrolofthecooldownprocedureisbasedonthemeasurementofreactorcoolanttemperature,whereasthelimitingpressureisactuallydependentonthematerialtemperatureatthetipoftheassumedflaw.Duringcooldown,theI/4TvessellocationisatahighertemperaturethanthefluidadjacenttothevesselID.Thiscondition,ofcourse,isnottrueforthesteady-statesituation.Itfollowsthat,atanygivenreactorcoolanttemperature,thebTdevelopedduringcooldownresultsinahighervalueofKIRattheI/OTlocationforfinitecooldownratesthanforsteady-stateoperation.Furthermore,ifconditionsexistsothattheincreaseinKIRexceedsKIT,thecalculatedallowablepressureduringcooldownwillbegreaterthanthesteady-statevalue.TheaboveproceduresareneededbecausethereisnodirectcontrolontemperatureattheI/4Tlocationand,therefore,allowablepressuresmayunknowinglybeviolatediftherateofcoolingisdecreasedatvariousintervalsalongacooldown'amp.Theuseofthecompositecurveeliminatesthisproblemandensuresconservativeoperationofthesystemfortheentirecooldownperiod.Threeseparatecalculationsarerequiredtodeterminethelimitcurvesforfiniteheatuprates.Asisdoneinthecooldownanalysis,allowablepressure-temperaturerelationshipsaredevelopedforsteady-stateconditionsaswellasC-6 finiteheatuprateconditionsassumingthepresenceofa1/4Tdefectattheinsideofthewallthatalleviatethetensilestressesproducedbyinternalpressure.Themetaltemperatureatthecracktiplagsthecoolanttemperature;therefore,theK1Rforthe1/4TcrackduringheatupislowerthantheK1Rforthe1/4Tcrackduringsteady-stateconditionsatthesamecoolanttemperature.Duringheatup,especiallyattheendofthetransient,conditionsmayexistsothattheeffectsofcompressivethermalstressesandlowerK1R'sdonotoffseteachother,andthepressure-temperaturecurvebasedonsteady-stateconditionsnolongerrepresentsalowerboundofallsimilarcurvesforfiniteheatuprateswhenthe'1/4Tflawisconsidered.Therefore,bothcaseshavetobeanalyzedinordertoensurethatatanycoolant-temperaturethelowervalueoftheallowablepressurecalculatedforsteady-stateandfiniteheatupratesisobtained.Thesecondportionoftheheatupanalysisconcernsthecalculationofthepressure-temperaturelimitationsforthecaseinwhicha1/4Tdeepoutsidesurfaceflawisassumed.Unlikethesituationatthevessel,insidesurface,thethermalgradientsestablishedattheoutsidesurfaceduringheatupproducestresseswhicharetensileinnatureandthereforetendtoreinforceanypressurestressespresent.Thesethermalstressesaredependentonboththerateofheatupandthetime(orcoolanttemperature)alongtheheatupramp.Sincethethermalstressesattheoutsidearetensileandincreasewithincreasingheatuprates,eachheatupratemustbeanalyzedonanindividualbasis.Followingthegenerationofpressure-temperaturecurvesforboththesteadystateandfiniteheatupratesituations,thefinallimitcurvesareproducedby.constructingacompositecurvebasedonapoint-by-pointcomparisonofthesteady-stateandfiniteheatupratedata.Atanygiventemperature,theallowablepressureistakentobethelesserofthethreevaluestakenfromthecurvesunderconsideration.Theuseofthecompositecurveisnecessarytosetconservativeheatuplimitationsbecauseitispossible'forconditionstoexistwherein,overthecourseoftheheatupramp,thecontrollingconditionswitchesfromtheinsidetotheoutside,andthepressurelimitmustatalltimesbebasedonanalysisofthemostcriticalcriterion.C-7 Finally,the1983Amendmentto10CFR50~4~hasarulewhichaddressesthemetaltemperatureoftheclosureheadflangeandvesselflangeregions.ThisrulestatesthatthemetaltemperatureoftheclosureflangeregionsmustexceedthematerialRTNDTbyatleast120'Ffornormaloperationwhenthe'ressureexceeds20percent'fthepreservicehydrostatictestpressure(621psigwithoutmarginsforinstrumentationerrorand561psigwithmarginsforD.C.CookUnit2).Table1indicatesthatthelimitinginitialRTNDTof30'FoccursinthevesselflangeofD.C.CookUnit2,sotheminimumallowabletemperatureofthisregionis150'Fexcludingmarginsforinstrumentationerrorand160'Fwithmargins.TheselimitsareshowninFigures1through8wheneverapplicable.4.HEATUPANDCOOLDOWNLIMITCURVESLimitcurvesfornormalheatupandcooldownoftheprimaryreactorpressurevesselhavebeencalculatedusingthemethodsdiscussedinSection3.Ifpressurereadingsaremeasuredatotherlocationsthanthelimitingbeltlineregion,'hepressuredifferencesbetweenthepressuretransmitterandthelimitingbeltlineregionmustbeaccountedforwhenusingthepressure-temperaturelimitcurvesherein.Theindicatedpressureandtemperaturelabelsprovidedonthecurvesrelatetothelimitingbeltlineregionofthereactorvessel.Figures1,2,5and6containtheheatupcurvesfor60'F/hr.Figures3,4,7and8containthecooldowncurvesupto100'F/hr.Figures1and3areapplicableforthefirst32EFPYofoperationandincludenomarginsforpossibleinstrumentationerrors.Figures2and4areapplicableforthefirst32EFPYofoperationandincludemarginsof10'Fand60psigforpossibleinstrumentationerrors.Figures5and7areapplicableforthefirst15EFPYofoperationandincludenomarginsforpossibleinstrumentationerrors.Figures6and8areapplicableforthefirst15EFPYofoperationandincludemarginsof10'Fand60psigforpossibleinstrumentationerrors.ThecurrentD.C.CookUnit2lowtemperatureoverpressureprotectionsystem(LTOP)setpointsarevaliduptothe15EFPYpressure-temperaturelimitcurves.C-8 The32EFPYpressure-temperaturelimitcurvescannotbeusedwiththecurrentLTOPsetpoints.AllowablecombinationsoftemperatureandpressureforspecifictemperaturechangeratesarebelowandtotherightofthelimitlinesshowninFigures1through8.Thisisinadditiontoothercriteriawhichmustbemetbeforethereactorismadecritical.TheleaklimitcurveshowninFigures1,2,5and6representsminimumtemperaturerequirementsattheleaktestpressurespecifiedbyapplicablecodesI~~.TheleaktestlimitcurvewasdeterminedbymethodsofReferences2and4.ThecriticalitylimitcurveshowninFigure1,2,5and6,specifiespressure-temperaturelimitsforcoreoperationtoprovideadditionalmarginduringactualpowerproductionasspecifiedinReference4.Thepressure-temperaturelimitsforcoreoperation(exceptforlowpowerphysicstests)arethatthereactorvesselmustbeatatemperatureequaltoorhigherthantheminimumtemperaturerequiredfortheinservicehydrostatictest,andatleast40'Fhigherthantheminimumpressure-temperaturecurveforheatupandcooldowncalculatedasdescribedinSection3.ThemaximumtemperaturefortheinservicehydrostatictestfortheD.C.CookUnit2reactorvesselfor32EFPYis348'Fwithmarginsforinstrumentationerrorsand335'Fwithoutmarginsforinstrumentationerrors.Averticallineat348Fand335Fonthepressure-temperaturecurves(withandwithoutmargins),intersectingacurve40'Fhigherthanthepressure-temperaturelimitcurve,constitutesthelimitforcoreoperationforthereactorvessel.ThemaximumtemperaturefortheinservicehydrostatictestfortheD.C.CookUnit2reactorvesselfor15EFPYis324'Fwithmarginsforinstrumentationerrorsand311'Fwithoutmarginsforinstrumentationerrors.Averticallineat324'Fand311'Fonthepressure-temperaturecurves(withandwithoutmargins),intersectingacurve40'Fhigherthanthepressure-temperaturelimitcurve,constitutesthelimitforcoreoperationforthereactorvessel.Figures1through8definelimitsforensuringpreventionofnonductilefailurefortheD.C.CookUnit2reactorvessel.C-9 5.ADJUSTEDREFERENCETEMPERATUREFromRegulatoryGuide1'.99'ev.2[1]theadjustedreferencetemperature(ART)foreachmaterialinthebeltlineisgivenbythefollowingexpression:ART=InitialRTNDT+hRTNDT+Margin(3)InitialRTNDTisthereferencetemperaturefortheunirradiatedmaterialasdefinedinparagraphNB2331ofSectionIIIoftheASMEBoilerandPressureVesselCode.IfmeasuredvaluesofinitialRTNDTforthematerialinquestionarenotavailable,genericmeanvaluesforthatclassofmaterialmaybeusediftherearesufficienttestresultstoestablishameanandstandarddeviationfortheclass.hRTNDTisthemeanvalueoftheadjustmentinreferencetemperaturecausedbyirradiationandshouldbecalculatedasfollows:[CF]f(0.28-0.101ogf)NDT(4)TocalculatehRTNDTatanydepth(e.g.,at1/4Tor3/4T),thefollowingformulamustfirstbeusedtoattenuatethefluenceatthespecificdepth.(depthX)surface(-.24x(5)wherex(ininches)isthedepthintothevesselwallmeasuredfromthevesselclad/basemetalinterface.Theresultantfluenceisthenputintoequation(4)tocalculateARTNDTatthespecificdepth.CF('F)isthechemistryfactor,obtainedfromReference1.AllmaterialsinthebeltlineregionofD.C.CookUnit2wereconsideredforthelimitingmaterial.RTNDTat1/4Tand3/4TaresummarizedinTables2and3for32and15EFPYrespectively.FromTables2and3,itcanbeseenthat'helimitingmaterialistheintermediateshellplateC5556-2forheatupandcooldowncurvesapplicableupto32and15EFPY.SamplecalculationsfortheRTNDTfor32and15EFPYareshowninTables4and5.
TABLE1D.C.COOKUNIT2REACTORVESSELTOUGHNESSTABLE(Unirradiated)MaterialDescriptionClosureHeadFlange,4437-V-1VesselFlange,4436-V-2CU(X)NII-RTNDT(a)(>)('F)-20(b)30(b)IntermediateShell,C5556-2IntermediateShell,C5521-2*0.150.570.1250.585838LowerShell,C5540-2LowerShell,C5592-1O.ll0.140.640.59-20-20IntermediateandLowerShellLong.andGirthWeldSeams(Ht.S3986,Linde124,FluxLotNo.0934)*0.0520.967-35*Xweightcopperandnickelcontentaremeanvaluesbasedontheavailablechemistrytestresultsasindicatedbelowa.TheinitialRTNDT(I)valuesfortheplatesandweldsaremeasuredvaluesbasedonactualdata.b.Tobeusedforconsideqggflangerequirementsforheatup/cooldowncurvesl~.MaterialPlate,C5521-2DataSourceOriginalMillTestReportSurveillanceProgram[1]MeanvalueCopper~wtX.0.140.110.125Nickel~wt.X0.580.580.58WeldOriginalMillTestReportSurveillanceProgram[1]SurveillanceProgram[1]Meanvalue0.050.0550.050.0520.970.970.960.967 TABLE2SUMMARYOFADJUSTEDREFERENCETEMPERATURE(ART)AT1/4Tand3/4TLOCATIONFOR32EFPY~Comonent32EFPYRTNpTat1//4T',~34T'IntermediateShellPlate,C5556-2IntermediateShellPlate,C5521-2201159(158)171135(129)LowerShellPlate,C5540-2Lower.ShellPlate,C5592-1891146886Intermed.ShellLongitudinalWelds(a)LowerShellLongitudinalWelds(b)80924568CircumferentialWeld92(64)68(40)RTNpTnumberswithin()arebasedonchemistryfactorcalculatedusingcapsuledata.(a)Intermediateshelllongitudinalweldsarelocatedat10'b)Lowershell'ongitudinalweldsarelocatedat90'-12 TABLE3SUMMARYOFADJUSTEDREFERENCETEMPERATURE(ART)AT1/4Tand3/4TLOCATIONFOR15EFPY~Comonent15EFPYRTNDTat~l4T'~34TFIntermediateShellPlate,C5556-2IntermediateShellPlate,C5521-2178141(137)150118(110)LowerShellPlate,C5540-2LowerShellPlate,C5592-173935467Intermed.ShellLongitudinalWelds(a)LowerShellLongitudinalWelds(b)524020llCircumferentialWeld77(49)41(28)RTNDTnumberswithin()arebasedonchemistryfactorcalculatedusingcapsuledata.I(a)Intermediateshelllongitudinalweldsarelocatedat10'b)Lowershelllongitudinalweldsarelocatedat90'-13 TABLE4CALCULATIONOFADJUSTEDREFERENCETEMPERATURESFORLIMITINGD.C.COOKUNIT2REACTORVESSELMATERIAL-INTERMEDIATESHELLPLATE,C5556-2FOR32EFPYParameterReulatorGuide1.99-Revision232EFPY~14T~34TChemistryFactor,CF('F)Fluence,f(10n/cm)()FluenceFactor,ff108.351.0271.007108.350.37030.725ARTNDT=CFxff('F)InitialRTNpT,I('F)Margin,H('F)(b)1095834795834Revision2toRegulatoryGuide1.99AdjustedReferenceTemperature,ART=InitialRTNpT+ARTNDT+Margin201*171********************************************************************************(a)Fluence,f,isbaseduponfsurf(10n/cm,E>1Hev)=1.71at32EFPY.TheD.C.CookUnit2reactorvesselwallthicknessis8.5inchesatthebeltlineregion.(b)Marginiscalculatedas,H=2[uI+e~].ThestandarddeviationfortheinitialRTNpTmarginterm,oI,isassumedtobeO'FsincetheinitialRTNpTisameasuredvalue.ThestandarddeviationforARTNDTterm,o>,is17'Fforthebasemetal,exceptthato~neednotexceed0.5timesthemeanvalueofhRTNDT.*Limitingvalueusedindevelopmentofheatupandcooldownlimitcurves.
TABLE5CALCULATIONOFADJUSTEDREFERENCETEMPERATURESFORLIMITINGD.C.COOKUNIT2REACTORVESSELMATERIAL-INTERMEDIATESHELLPLATE,C5556-2FOR15EFPYReulatorGuide1.99-Revision215EFPYParameter14T~34TChemistryFactor,CF('F)Fluence,f(10n/cm)()FluenceFactor,ff108.350.4830.797108.350.17420.537ARTNDT=CFxff('F)86'8InitialRTNDTI(F)5858Margin,M('F)34,.34*******************************************************************************Revision2toRegulatoryGuide1.99AdjustedReferenceTemperature,ART=InitialRTNDT+hRTNDT+Margin178*150*(a)Fluence,f,isbaseduponfsurf(10n/cm,E>lMev)0.804at15EFPY.TheD.C.CookUnit2reactorvesselwallthicknessis8.5inchesatthebeltlineregion.(b)Marginiscalculatedas,H-2[O'I+a~].ThestandarddeviationfortheinitialRTNDTmarginterm,o'I,isassumedtobeO'FsincetheinitialRTNDTisameasuredvalue.ThestandarddeviationforhRTNDTterm,o~,is17'Fforthebasemetal,exceptthata<neednotexceed0.5timesthemeanvalueofARTNDT.*Limitingvalueusedindevelopmentofheatupandcooldownlimitcurves.
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEOIATESHELLPLATE,C5556-2LIMITINGARTAFTER32EFPY:'/4T,201'F3/4T,171'F25002250LEAKTESTLMIT2000175015001250a.1000750500UNACCEPTABLEOPERATIONHEATUPRATEUPto60'F/HRACCEPTABLEOPERATIONCRlTICALlTYLIMITBASEDONINSERVICEHYDROSTATICTESTTEMPERATURE(335F}FORTHESERVICEPERIODUPTO32EFPY250'050100150200250300350400450500INOICATEOTEMPERATURE(OEG.F)Figurel.D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr}ApplicablefortheFirst32EFPY(WithoutMarginsForInstrumentationErrors)
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER32EFPY:'/4T,201'F3/4T,171'F25002250:LEAKTESTLIMIT2000175015001250g1000Ch,,WI750500250UNACCEPTABLEOPERATIONHEATUPRATEUPto60'F/HRACCEPTABLEOPERATIONCRITICALITYLIMITBASEDONINSERVICEHYDROSTATICTESTTEMPERATURE(347F)FORTHESERVICEPERIOD,UPTO32EFPY050100150200250300350400450500INOICATEOTFMPERATURE(OEG.F')Figure2.D.C.'ookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst32EFPY(WithMarginsof10'Fand60psigForInstrumentationErrors)
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER32EFPY:1/4T,201'FI'-3/4T,171'F25002250200017501500w1250g1000OLJI=750O2:500250COOLDOWNRATESF/HR0204060100UNACCEPTABLEOPERA'EONACCEPTABLEOPERATION050100150200250300350400450500.INDICATEDTEMPERATURE(DEG.F)Figure3.D.C.CookUnit2ReactorCoolantSystemCooldown(Cooldownratesupto100'F/hT)LimitationsApplicablefortheFirst32EFPY(WithoutMarginsForInstrumentationErrors)
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER32EFPY:1/4T,201F3/4T,171'F25002250200017501500w1250L,1000UNACCEPTABLEOPERATIONACCEPTABLEOPERATIONO4JIOZ750500250COOLDOWNF/HR02040601000050100150200250300350400<50500INOICATEOTEMPERATURE(OEG.F')Figure4.D.C.CookUnit2ReactorCoolantSystemCooldown(Cooldownratesupto100'F/hr)LimitationsApplicablefortheFirst32EFPY(WithMarginsof10'Fand60psigforInstrumentationErrors)
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER15EFPY:1/4T,178'Fh">'r3/4T150F25002250LEAKTESTLIMK'00017501500NCLw1250a.1000CiLJI750oX500250UNACCEFIABLEOPERATIONHEAIUPRAKUPtoN'F1HRACCEFI'ABLEOPERA'IIONCRIIICALITYLIMITBASEDONINSERVICEHYDROSTATICTEST'IEMPIHtATUREg1lF)FORTHESERVICEPERIODUPTO15EFPY050100150200250300350400450500INDICATED,TEMPERATURE(DEG.F)Figure5.D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst15EFPY(WithoutMarginsForInstrumentationErrors)C-20 MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGART'FTER15EFPY:1/4T,178'F3/4T,150'F25002250LEAKTESTLIMIT200017501500UNACCEPrABLEOPERATION12501000OI750Cl500250HEATUPRA1EUP60oF/HRACCEPI'ABLEOPERA%IONCRITICALITYLIMITBASEDONINSERVICEHYDROSTATICTEST'IEMPERATURE(324%)FORTHESERVICEPERIODUP'IOISEFPY050100150200250300350400450500INOICATEDTEMPERATURE(BEG.F)Figure6.D.C.CookUnit2ReactorCoolantSystemHeatupLimitations(Heatuprateupto60'F/hr)ApplicablefortheFirst15EFPY(WithMarginsof10'Fand60psigForInstrumentationErrors)
MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER15EFPY:1/4T,178'F'.'I3/4T,150'F250022502000175015004I1250a.1000OI750O5002500204060100UNACCBFrABLBOPERATIONACCEPTABLEOPBRAIION050100150200250300350400450500INDICATEDTEIAPERATURE(DEC.F)Figure7.D.C.CookUnit2ReactorCoolantSystemCooldown(Cooldownratesupto100'F/hr)LimitationsApplicablefortheFirst15EFPY(WithoutMarginsForInstrumentationErrors)C-22 MATERIALPROPERTYBASISLIMITINGMATERIAL:INTERMEDIATESHELLPLATE,C5556-2LIMITINGARTAFTER15EFPY:1/4T,178'F3/4Ts150F250022502000175015001250a.1000750ClX500250UNACCEPI'ABLEOPERATIONCOOLDO%NRATES'F/HR0204060IOQACCEFI'ABLEOPERATION050100150200250300350400450500INDICATKDTKLIPKRATURK(DKG.F')Figure8.D.C.CookUnit2ReactorCoolantSystemCooldown(Cooldownratesupto100'F/hr)LimitationsApplicablefortheFirst15EFPY(WithMarginsof10'Fand60psigforInstrumentationErrors)C-23 6.REFERENCES1RegulatoryGuide1.99,Revision2,"RadiationEmbrittlementofReactorVesselMaterials,"U.S.NuclearRegulatoryCommission,May,1988.2"FractureToughnessRequirements,"BranchTechnicalPositionMTEB5-2,Chapter5.3.2inStandardReviewPlanfortheReviewofSafetyAnalysisReportsforNuclearPowerPlants,LWREdition,NUREG-0800,1981.3ASMEBoilerandPressureVesselCode,SectionIII,Division1-Appendixes,"RulesforConstructionofNuclearPowerPlantComponents,AppendixG,ProtectionAgainstNonductileFailure,"pp.558-563,1986Edition,AmericanSocietyofMechanicalEngineers,NewYork,1986.4CodeofFederalRegulations,10CFR50,AppendixG,"FractureToughnessRequirements,"U.S.NuclearRegulatoryCommission,Washington,D.C.,FederalRegister,Vol.48No.104,May27,1983.5LetterReport,MT-SMART-090(89),"D.C.CookUnit2ReactorVesselHeatupandCooldownLimitCurvesforNormalOperation",N.K.Ray,April1989.6WCAP-8512,"AmericanElectricPowerCompanyDonaldC.CookUnitNo.2ReactorVesselRadiationSurveillanceProgram",J.A.Davidson,etal.,November1975.7"FractureToughnessRequirementsforProtectionAgainstPressurizedThermalShockEvents",10CFRPart50,Vol.58,No.94,May15,1991.C-24
.ATTACHMENTIDATAPOINTSFORHEATUPANDCOOLDOWNCURVES(WithoutMarginsforInstrumentationErrors)ThedatapointsusedinthedevelopmentoftheheatupandcooldowncurvesshowninFiguresIand3arecontainedontheattachedcomputerprintoutsheets.C-25 AMP60DEG-F/HRHEATUPREG.GUIDE1.99,REV.2WITHOUTMARGIN09/28/92THEFOLLOWINGDATAWERECALCULATEOFORTHEINSERVICEHYDROSTATICLEAKTEST.MINIMUMINSERVICELEAKTESTTEMPERATURE(32.000EFPY)PRESSURE(PSI)TEMPERATURE(DEG,F)3142485335PRESSURE(PSI)PRESSURESTRESS(PSI)214441.5K1M(PSISQRTIN)89745248526645112505 AMP,60DEG-F/HRHEATUPREG.,GUIDE1.99~,REV.2WITHOUT,MARGIN,.'>;.:>C,COMPOSITECURVEPLOTTEDFORHEATUPPROFILE2HEATUPRATE(S)(DEG.F/HR)K60.009/28/92'IMIRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTHw(1"AOWIN)T:-,*'NDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDTEMPERATURE(DEG.F)12345686.00090.00095.000100.000105.000"110.000-44~4.Rh~~8:&-436z64--';:-.--,::;.,",,21'85,00022-190.00025205.000~.-""i;26,,"210.000INDICATEDPRESSURE(rSI)513.04S24.65537.13550.71565.38.'681.19..7'...115.0008':120.0009125.00010130.00011135.00012.'40.000.13-,,146.00014".-15Q;OQO15155.00016160.00017165.00018'170.00019.'75.00020-.18Q.OQOC433.80":.'.:~::,';:,:~~~"27'.215000,'.,':,>698.11-34'2~.>'.',"'4~i'8""'220000:';6'16'45435.5329225.000636.06437.7730230.000657.31440.8531235.000680.15444'.72'.-',,";-".:.'"32,'..."-'240.000.,;--'-.704;60"...:449.38".':;;:=~33',.245.000'".,-',.-'730.85'454,73';..5'c,'.34"4>250,000"-..::.?-'759.-27..-'.460.8435255.000789.61467.6336260.000822.35475.1837265.000857.45483.45',:,.'8..,270.000-::.":-.,;.895.10492.53-~.39:27S.-OOO-.'";935~62502.30INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG,F)(PSI)?40280;000'h-':.978,92.',41285:000=-':'.102S.5242290.0001075.5643295.0001129.2844300.0001186.8045'-,305;,000",',248.53.46,h',310';.OQO..:h::".1314.7047,.;-'31S..OQQ.':>->-1385,56,48320.0001461.5549325.0001542.8750,330.000,1629.8551'-.,;.'35'.000-'1723:05'2:;34Q;OOQ;-';.:::;:1822.90.-53""'45'.OQQ:::'-.>'924.6454350.0002020.0755355.0002121.9156360.0002230.6357.'--'.;365.000',.2346".74=58-,:.:370;QOO",.:::,-2470,52-?'P??-h=.h>>'X5 DDLDOWNCURVESREG.GUIDE1.99,REV.2WITHOUTMARGIN09/28/92THEFOLLOWINGDATAWEREPLOTTEDFORCDOLDOWNPROFILE1(STEADY-STATECDDLDDWN)IRRADIATIONPERIODR32.000EFPYEARSFLAWDEPTH~ADWINTINDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)1234567891011121314151617181985,00090.00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000150.000155.000160.000165.0001VO.OOO175.000492.98495.89499.02502.38505.99509.88514,06518.55523.38528.57534.15540.05546,50553.44560.90568.91577.54586.68596.6420212223242526272829303132333435363738180.000185.000190.000195.000200.000205.000210.000215.000220.000225.000230.000235.000240.000245,000250.000255.000260.000265.0002?0.000607.36618.87631.24644.42658.74674.1'I690.49?08,28727.34747.75769.81V93.38e1&.e4846.11875.34907.00940.84977.141016.15394041424344454647484950515253545556275.000280~000285.000290.000295.000300.000305.000310.000315.000320.000325.000330.000335.000340.000345.000350.000355.000360.0001058.28'1103.351151.781203.561259.451319.451383.701452.621526.551605.821690.701781.VV1&79.211983,422094.782214.282341.47247V.36 AMPCODLOOWNCURVESREG.GUIDE1.99,REV.2WITHOUTMARGIN09/28/92THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE2(20OEG-F/HRCOOLDOWN)IRRADIATIONPERIOD~32.000EFPYEARSFLAWDEPTH~ADWINTINDIGATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(rSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)~INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(rSI)23456789101112131485.00090.00095.000100.000105.000110.000115.0QO120.OQQ125.000130.000135.000140.000145.000150.000449.12452,03455.19458.58462.27466.23470-52475.13480.13485.49491.30497.44504.19511.431516171819202122.2324252627155.000160.000165.000170.000175.000180.000185.OOQ1SO.QOO195.000200.000205.000210.000215.000519.26527,68536.76546.42556.96568.28580.49593.50607.65622.87639.12656.75675.7328293031323334353637383S40220,000225,000230.000235.000240.000245.000250.000255.000260.000265.000270.000275.000280-0006S5.99717.97741.44766.88794.05823.42854.93888.77925.12964.441006.491051.771100.35IPD%O ODLDOWNCURVESREG.GUIDE:1,99,REV.2WITHOUTMARGINIRRADIATIONPERIOD=32.000EFPYEARSFLAW'EPTH~AOWINT0,0THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE3(40DEG-F/HRCOOLDOWN)09/28/92hC,INDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURE(DEG.F)(PSI)(DEG.F)(PSI}85,QOO404.27,.-..;.:.:,15155.000"476.972.;...9Q.OOO407.14~,".".'5,';.]6,.',160.000"...485.84'395.000410.3417165.000495.354100.000413.7918170.000505.685105.000417.5619175.000516.856110.000421.62.,20180.000.528.867,115,000.426.04'.-','.,"21,.185.000..'.:541.74.8',.'120.00Q'-430.80..'.:"'22-..-.-.190'000",.555.71,9125.000435.9823195.000570.8010130.000441.4924200.000586.9111135.000447.5425205.000604.4312-;140.000,454.06.,',"",:;.,"'".26,',,210.000:.,'23.28,13-:"145.000-;-:461.,12"'.i",."27,"'.',215.'000:,'i'643;47.'1415Q.OQO-68.73INDICATEDTEMPERATURE(DEG.F)28,220.00029..225.00Q'0230.00031235.00032240.00033245.00034-'250.00035255.00036260-00037265.00038270F00039,."275.0004Q,"'&0;000,,INDICATEDPRESSURE(rSI)665".35-'88;7?.714.14741.31770.69802.22'36.07"872.54,911.96954.24999.65i1048.51:".'101':.03nIED;-;,'.?c5 AMPCODLDOWNCURVESREG.GUIDE1.99,REV.2WITHOUtMARGIN09/28/92THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDDWNPROFILE4(60DEG-F/HRCDOLDOWN)IRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTH~AOWINTINDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI}INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)1234567891011121385,00090.00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145,0QO358.24361.20364.41367.93371.80375.99380.56385.5Q390.89396.71403.05409.83417.27141516171819202'1222324252615Q.000155.000160.000165.000170.000175.000180.000185.000190.000195.000200.000205.000210.000425.29433.99443.30453.48464.44476.32489.12502.88517.80533.93551.19569.96590,0527282930313233343536373839215.000220.000225.000230.000235.000240.000245.000250.0QQ255.000260.000265.000270.000275,000611.88635.24660.61687.75717.21748.73782.71819,44858.89901.34947.04S96.211049.09 COOLOOWNCURVESREG.GUIDE-1,99,REY.2.WITHOUTMARGINTHEFOLLOWINGDATAWEREPLOTTEDFORCOOLOOWNPROFILE5(100DEG-F/HRCOOLDOWN)09/28/92IRRADIATIONPERIOD<32.000EFPYEARS",-.FLAMDEPTHAOWINT?INDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEOTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(OEG.F)(PSI),,(OEG.F)(PSI),(DEG.F)(PSI)1',85,000'62,'50,"::,,':;;;:;~:,14,150;000-'36.15';~27.h',2.15,000',.551'.052-'90.000,.-'.265F58""':,"'".5."::i15'155.'000,';.345,99,-';-'h,"."'28,;h-'.220;OOQ'578,41',395.000269.0116160.000356.6329225.000607.884100.000272.7517165.000368.1630230.000639.625105,000276.9018170.000380.6631235.000674.056110.000281.41;',:.":;::;.:-19175.000:'394.26;-',32,.240.000'11;017115.000.286,36.;;;.,-;,.":.".',20'180.000;-.408-.87'.--:33'45.000-';750;898,'120,000'=,=:291,76.-'..;",:,'.,'-';.2t";185.000'".'.',.;;-424.79-'..,':..',,..34;.,',,';:250..'000,-.793.84-,9125.000297.70~22190.000441.9135255.000840.1710130.000304.1323195.000460.5336260.000890.0411135.000311.1824200.000480.6337265,000943.8312?;,:'140.000:-.;.-.",.:,318.82<:,h-..?K~'.":i"'25"'05;000'.';',.502".30,:..:,.;,:':-"38,';j270,'OOO,','.1001.60,';."'-13'"'.'",,L45OOO,:;~-'-'*'"";-,327'2"*.',"'"";"',,"26",',','210'000-","".',.'25'6,""::?i'i":,'",'c,'",'"""",'.'.';""..",'c."",.:.'"'h>.'""',,'.,'l:iwc,IM?.hh5h ATTACHMENT2DATAPOINTSFORHEATUPANDCOOLDOWNCURVES(WithMarginsof10'Fand60psigforInstrumentationErrors)ThedatapointsusedinthedevelopmentoftheheatupandcooldowncurvesshowninFigures2and4arecontainedontheattachedcomputerprintoutsheets.C-33 AMP60DEG-F/HRHEATUPREG.GUIDE1.99.REV.2WITHMARGINS10/12/92THEFOLLOWINGDATAWERECALCULATEDFORTHEINSERVICEHYDROSTATICLEAKTEST.MINIMUMINSERVICELEAKTESTTEMPERATURE(32.000EFPY)PRESSURE(PSI)TEMPERATURE(DEG.F)3262485347PRESSURE(PSI)PRESSURESTRESS1.5K1M(PSI)(PSISO.RT.IN.)2208892529248527288115366 AMP60DEG-F/HRHEATUPREG.GUIDE1.99,REV.2WITHMARGINS10/12/92COMPOSITECURVEPLOTTEDFORHEATUPPROFILE2HEATUPRATE(S)(DEG.F/HR)IRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTH>(1"AOWIN)Ti>0.0INDIGATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)123456789101112131415161718192085.00090.00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000'150.000155.000160.000165.000170.000175.000180.000~f669373.80374.12375.53377.77380.85384.72389.38394.73400.84407.63415.18423.4537$gO21,22232425262728293031323334353637383940185.000190.000195.000200.000205.000210.000215.000220.000225.000230.000235.000240.000245.000250.000255.000260.000265.000270.000275.000280.000432.53442.30453.04464.65477.13490.71505.38521.19538.11556.45576.06597.31620.15644.60670.85699.27729.61762.35797.45835.104142434445464748495051525354555657585960285.000290.000295.000300.000305.000310.000315.000320.000325.000330.000335.000340.000345.000350.000355.000360.000365.000370.000375.000380.000875.52918.92965.521015.561069.281126.801188.531254.701325.561401.551482.871569.851663.051762.901869.461979.872082.952193.342311.052436.53 OOLDDWNCURVESREG.GUIDE1.99.REV.2WITHMARGINS10/12/92THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE1IRRADIATIONPERIOD<32.000EFPYEARSFLAWDEPTH%AOWINT(STEADY-STATECOOLDOWN)INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(PSI)23456789101112131415161718192085.OOQ90.00095.000100.000105.000110.000115.OOQ120.000125.000130.000135.000140.000145.000150.000155.000160.000165.000170.000175.000180.000428.34430.89433.55436.50439.67443.08446.75450.69454.93459.49464.39469.65475.32481.30487.85494.89502.45510.59519.34528.622122232425262728293031.32'33343536373839185.QQO190.000195.000200.000205.000210.000215.000220.000225.000230.000235.000240.000245.000250.000255.000260.000265.000270.000275.000538.72549.59561.28573.70587.20601.72617.30633.95651.99671.20692.05714.40738.34764.15791.84821.50853.59887.92924.794041424344454647484950'1.52535455565758280.000'85.000290.000295.000300.000305.000310.000315.000320.000325.000330.000335.000340.000345.000350.000355.000360.000365.000370.000964.381006.911052.621101.741154.52121'I.181271.921336.951407.011481.901562.301648.491740.741839.561945.082058.162178.952308.092445.60 AMPCOOLDDWNCURVESREG.GUIDE1.99,REV.2WITHMARGINSTHEFOLLOWINGDATAWEREPLOTTEDFORCODLDDWNPROFILE2(20DEG-F/HRCODLDOWN)IRRADIATIONPERIOD~32.000EFPYEARSFLAWDEPTH%ADWINT10/12/92INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDTEMPERATURE(OEG.F)INDICATEDPRESSURE(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE.(DEG.F)(PSI)23456789101112131485.00090.00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000150.000384.45386.97389.72392.68395.89399.33403.08407.10411.46416.14421.21426.65432.55438.79151617181920-21~'-'2232425262728155.000160.000165.000170.000175.000~180.000185.000190.000195.000200.000205.000210.000215.000220.000445.63452.99460.94469.47478.59488.50499.19510.68523.07536.28550.64566.08582.58600.472930313233343536373839404142225.000230.000235.000240.000245.000250.000255.000260.000265.000270.000275.000280.000285F000290.000619.71640.29662.57686.41712.18'?39.80769.45801.54835.91872.80912.49955.141001.021050.33ICa)
CODLODWNCURVESREG.GUIDE1.99,REV.2WITHMARGINSTHEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE3(40DEG-F/HRC(i::LDOWN)IRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTH~AOWINT10/12/92INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPIRATUREPRESSUR1'ILG.F)(PSI)23456789101112131485.00090.00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000150.000339.64342,16.--344.92347.84351.09354.60358.43362.55367.04371.88377.14382.73388.88395.501516171819202122232425262728155.000160.000165.000170.000175.000180.000185.000190.000195.000200.000205.000210.000215.000220.000402.68410.40418.77427.77437.43447.91459.25471.45484.53498.71514.02530.37548.16567.272930313233343536373839404142225.000230.000235.000240.000245.000250.000255.000260.000265.000270.000275.000280.000285.000290.000587.78609.98633.75659.48687.07716.71748.86783.24820.25860.04903.09949.17998.741051.84ICO AMPCOOLDDWNCURVESREG.GUIDE1.99,REV.2WITHMARGINSTHEFOLLOWINGDATAWEREPLOTTEDFORCOOLODWNPROFILE4(60DEG-F/HRCOOLODWN)IRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTH~AOWINT10/12/92INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(PSI)INDICATEOINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(PSI)123456789101112131485,00090~00095.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000150.000293.63296.15298.93301.94305.21308.80312.73316.99321.64326.66332.14338.05344.50351.381516171819202122232425262728155.000160.000165.000170.000175.000180.000185.000190.000195.000200.000205.000210.000215.000220.000358.94367.08375.92385.38395.72406.85418.91431.91445.88461.02477.29494.93513.98534.3729303132333435363738394041225.000230.000235.000240.000245.000250.000255.000260~000265.000270.000275.000280.000285.000556.53580.24605.99633.53663.40695.43729.92767.02807.21850.25896.63946.47'1000.17ICALD COOLDDWNCURVESREG.GUIDE1.99,REV.2WITHMARGINSTHEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE5(100DEG-F/HRCOOLI.iN)IRRADIATIONPERIOD=32.000EFPYEARSFLAWDEPTH%ADWINT10/12/92INDICATEDTEMPERATURE(DEG.F)INDICATEDPRESSURE(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)INDICATEDINDICATEDTEMPERATUREPRESSURE(DEG.F)(PSI)123456789101112131485.00090.000S5.000100.000105.000110.000115.000120.000125.000130.000135.000140.000145.000150.000197.87200.43203.30206.44209.94213.76217.98222.64227.61233.10239.14245.69252.86260.6215161718192021222324252627155.000160.000165.000170.000.175.000180.000185.000190.000195.000200.000205.000210.000215.000269.06278.24288.24299.05310.76323.47337.28352.12368.29385.67404.59424.99447.0028293031323334353637383940220.00~225.0Cii230.000235.000240.000246.000250.000265.000260.000265.000270.000276.000280.000470.82496.49524.26554.18586.40621.20658.85699.35742.94789.96840.55895.10953.54nIlD ATTACHMENT3DATAPOINTSFORHEATUPANDCOOLDOWNCURVES(WithoutMarginsforInstrumentationErrors)ThedatapointsusedinthedevelopmentoftheheatupandcooldowncurvesshowninFigures5and7arecontainedontheattachedcomputerprintoutsheets.
~THFOLLOWINGDATAWEREPLOTTEDFORCOOLOOWNPROFILE1(STEADY-STATECOOLOOWN)IRRADIATIONPERIOD~15.000,EFP,YEARS,INDICATEDINDICATEOINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(DEGF)(PSI)(OEGF)(PSI)395.000517.6220180.000670.9637265.0001193.0621185.000687.0938270.0001248.065,.105.000,,527.5022,,190,000.,704,6239275.0001307,039125.000552.0125210.000788.4943295.0001589.4810130.000559.3627215.000813.6144300.0001673.05135.000567.2628220.000840.4645305.0001763.0615155.000605.1532240.000969.6049325.0002189.5716160.000616.5033245.0001008.2750330.0002315.4217,165.000.628,.7034,250,000,.1049.65,51335.0002449.49 THEFOLLOWINGDATAMEREPLOTTEDFORCOOLDOWNPROFILE2(20DEG-F/HRCOOLDOWN),xIRRADIATIONPERIOD~h15,000EFPYEARSINDICATEDINDICATEDINDICATEDINDICATED.INDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE395.000475.1015155.000566.7827215.000789.014100.000479'.9916160.000578.7928220.000817.935...105,0003,485,30,17165,000,591,6129225,000,848,869125.000510.8321185.000653.8733245.000998.1910130.000518.5222190.000672.5334250.0001042.7411135.000,,526.82,9....23.,,195.000692,4935.,255,0001090.58,nI\bCYXvh982hh(4vX'M0hvwh4Xh2'X05080XNY(kX'4e/XkkvXh49khXNWhfNN)hvXXN2(X'hh.0kX4077hXXXkvX'v774Xv THEFOLLOWINGDATAWEREPLOTTEDFORCOOLOOWNPROFILE3(40DEG-F/HRCOOLDOWN),.,IRRADIATIONPERIOD,15,.000,EFPYEARS,,INDICATEDINDICATEDINDICATEDINDICATED,INDICATEOINDIGATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(DEG.F,),,(PSI),...,(OEG,F),(PSI},,(.)(395.000431.6815155.000528.0627215.000765.794100.000436.7416160.000540.69...,5105.000,,442,17,.,17,,165,000554.46,29225,000,830.059125.000468.9521185.000620.8733245.000990.9210130.000477.0322190.000640.6934250.0001038.9111,135.000,,485.77,.23,195,000662.2235255.0001090.58 THEFOLLOWINGDATAWEREPLOTTEDFORCOOLOOWNPROFILE4(60DEG-F/HRCOOLDOWN),,IRRADIATIONPERIOD=15.000EFPYEARS..INDICATEDINDICATEDINDICATEOINDICATEDINDICATEDINOICATEOTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(DEG.F),...(PSI)...,,.,(OEG.F),(PSI},...(OEG.F,)(PSI)395.000387.3015155.000489.0026210.000712.864100.000392.5616160.000502.4727215.000743.835105.000398~3017165~000517~1428220.000777.159125.000426.3421185.000588.0732240.000938.5010130.000434.8622190.000609.4733245.000986.8011135.000,,444.03.,23.,,195,.000632,5434,250.0001038.71 THEFOLLOWINGGATEWEREPLOTTEDFOROOOLOOWNPROFILEE(IOOOEG-F/HROOOLPOWN),IRRADIATION,PERIOD,>...15,000EFPYEARS...,INDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE,,(DEG,F),L(PSI),,,...(DEG,F)(PSI,}(DEG.F)(PSI)395.000295.4614150.000395.6425205.000635.734100.000301.2215"155.000.409.9726210.000669.415105.000307.55,16,,160.000425.5027215.000705.629125.000338.8520180.000501.3231235.000880.9110130.000,348.4321185.000524.3232240.000933.5511135.000358.88,,22,...,L190,000549.0233.245.000990.30, COMPOSITECURVEPLOTTEDFORHEATUPPROFILE2HEATUPRATE(S)(DEG.F/HR)~60.0IRRADIATIONPERIODm15.000EFP,,YEARSINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE395.000464.7421185.000572.8639275.0001147.474100.000460.1722190.000588.7140280.0001206.005,105,000457,67.23.,195,000.605,98419125.000462~0227215.000689~2745305.0001569.4410130.000466.0028220.000714.3246310.0001658.28,135,.000.47,1,04,,29,,.,225;000..741;08..47,3,15,.0001753,,2715155.000500.2433245.000870.1351335.0002203.3716160.000509.8434250.000908.5752340.0002325.8217,165.000,,520.,41,35,,255.,000949,.85,,53...,.345.000,,2448.35nI ATTACHMENT4DATAPOINTSFORHEATUPANDCOOLDOWNCURVES(WithMarginsof10'Fand60psigforInstrumentationErrors)ThedatapointsusedinthedevelopmentoftheheatupandcooldowncurvesshowninFigures6and8arecontainedontheattachedcomputerprintoutsheets.C-48
~THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE.1(STEADY-STATECOOLDOWN),IRRADIATIONPERIOD=415,000EFPYEARSINDICATEDINDIGATEDINDICATEDINDICATEDINDICATEDINDICATEOTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(PEG.F)(PSI),,(OEG,F),(PSI).,,(OEG.F)(PSI,)39500044908211850005957939275000113306*4100.000453.2022190.000610.9640280.0001188.065105.000,,457162,,23,,195,000,,,,627..0941285.0001247,.039125.000478.8127215.000705.2845305.0001529.4810130.000485.1728220.000728.4946310.0001613.0511135.000.492.0129225.000..753.6147315.0001703.0615155.000524.8933245.000873.8251335.0002129.5716160.000534.5934250.000909.6052340.0002255.4217,.165.000,,545.15,,35...255.000,,948,.27,53345,.0002389.,49 THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE2(20DEG-F/HRCOOLDOWN)IRRADIATIONPERIOD,>,,15,.000,EFP,YEARSINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE..(OEG,.F,),(PSI)...(DEG.,F),(PSI)(DEG.F)(PSI)395.000406.3416160.000495.6228220.000702.274100.000410.5417165.000506.7829225.000729.015105.000415.1018170.000518.7930230.000757.93~9125.000437.0622190.000576.4934250.000896.7410130.000443.6823195.000593.8735255.000938.1911135.000~450.8324200.000612.5336260.000982.74OI THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE3(40DEG-F/HRCOOLDOWN),.IRRADIATION,PERIOD,=.,15,000,EFPYEARSINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE(OEG.F)(PSI),.(OEG.~F,(PSI)2.616160.000456.2228220.000676.8617165.000468.0629225.000705.795,105,000...,,,371;68.....,18,.170.000,480...,6930230.000,736.739125.000394.5322190.000542.3234250.000886.2010130.000401.4523195.000560.8735255.000930.9211,135.000.,408,,95,,24200,.000,,580,.69...36,260,.000,978.91PlIVl8 THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE4(60DEG-F/HRCOOLOOWN)IRRADIATION,PERIOD~,15,000EFPYEARS'.;yg':,'":.':':'~."":"'";",",;;-'~"."':"""-""":,"~'"$":-'."'~"":..':".g:.".""'rS~i4'NDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE,,,(DEG,F)...(PSI,),,...,,...,...,(DEG.F),,(PSI).(DEG,F)....(PSI),395.000317.9615155.000404.7827215.000623.974100.000322.4316160.000416.4128220.000652.865105.000327.3017165.000429.0029225.000683.839125.000351.1821185.000489.9333245.000833.6610130.000358.4522'I90.000508.3234250.000878.50135.000,,366.34,,23195,000528.0735255.000926.80IQl
~THEFOLLOWINGDATAWEREPLOTTEDFORCOOLDOWNPROFILE5(100DEG-F/HRCOOLDOWN)~IRRADIATIONPERIOD,,~,15,,000EFPYEARS,INDICATEDINDICATEDINDICATEDINDICATEDINDICATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE~(PEG.F)(PSI),,,(OEG,.,F)(PSI)<OEG.F395.000225.3215155.000322.3827215.000575.734100.000230.1416160.000335.6428220.000609.415...105.,000.235.46,,,17,.,165,.000349,97299125.000261.9121185.000420.1633245.000820.9110130.000269.9922190.000441.3234250.000873.5511135.,000,.278.8523195.000464.32,35255,000930.30 COMPOSITECURVEPLOTTEDFORHEATUPPROFILE2HEATUPRATE(S)(OEG.F/HR)2260.0~IRRADIATION,PERIOD<15,0009EFP,YEARS,INDICATEOINDIGATEDINDICATEDINDICATEDINDIGATEDINDICATEDTEMPERATUREPRESSURETEMPERATUREPRESSURETEMPERATUREPRESSURE,(DEG.F)(PSI)....(DEG.F)(PSI)(DEG.F)(PSI)395.000420.9822190.000498.0640280.0001032.734100.000411.4223195.000512.8641285.0001087.475105.000,,404,74,,24,,200,000v528,,71v42290,.000,,1146.009125.000397.2728220.000606.1546310.0001426.2210130.000399.0329225.000629.2747315.0001509.44vv"4r;.~-:;"..m"5~-vry"4..w"".v.3.y40yr2v4rV.5vrr444yv4va""y4"*44vr"~~""...~.:.v,%~~~.v.::.awerr15155.000423.5634250.000774.2452340.0002019.6016'l60.000'31.6235255.000810.1353345.0002143.3717,,,165.000,440124,0..6.,36,,260.,000.,..4848...57v,.,7544,350,0009,2265.82,Vl
9304220175Attachment1toAEP:NRC:1181Reasonsand10CFR50.92SignificantHazardsEvaluationsforChangestotheTechnicalSpecificationsforDonaldC.CookNuclearPlantUnit:2
,f Attachment1toAEP:NRC:1181Page1Asdiscussedinthecoverletter,thepurposeofthisproposedamendmentistopreventasurveillanceoutagebeforeournextrefuelingoutage,currentlyscheduledtobeginAugust6,1994.Thissubmittalrequestsextensionsforsurveillancesthatmustbeperformedduringshutdownorthatpresentsuchoperationaldifficultythatperformingthesurveillanceisnotpracticalatpower.WeproposetoaddthefollowingTechnicalSpecification(T/S)toSection4.0oftheT/Ss.4.0.8Byspecificreferencetothis.section,thosesurveillanceswhichmustbeperformedonorbeforeAugust13,1994,andaredesignatedas18-monthor36-monthsurveillances(orrequiredasoutage-relatedsurveillancesundertheprovisionsofSpecification4.0.5)maybedelayeduntiltheendofthecycle9-10refuelingoutage.Forthesespecificsurveillancesunderthissection,thespecifiedtimeintervalsrequiredbySpecificati'on4.0.2willbedeterminedwiththenewinitiationdateestablishedbythesurveillancedateduringtheUnit21994refuelingoutage.DescritionofChaneDueDateWereferencethisSpecificationbyfootnoteinallsurveillancesthatrequirethisextension.ThisfootnotewillbeapplicabletothefollowingT/Sswiththeindicatedsurveillanceduedate.DatesgivenincludethegraceperiodallowedbyT/S4.0.2.(1)4.3.1.1.34.3.2.1.3Delaytime-responsetestingforreactortripandengineeredsafetyfeaturesinstrumentation01/02/94limitingduedate(2)4.5.1.d4.5.2.e4.6.2.1.c4.6.2.2.c4.6.3.1.24.7.1.2.e4.7.1.2.f4.7.3.l.b4.7.4.l.b4.7.5.1.e.24.7.6.l.d.3DelaytestingforequipmentresponsetoESFsignals(safetyinjection,containmentpressurehigh-high,containmentisolationphaseAandBandpurgeexhaust)04/15/94limitingduedate(3)Table4.3-2<,Item6.d4.7'.2.e4.7.1.2.fDelayauxiliaryfeedwatersystemtestingincludingchannelfunctionaltestingoflossofmainfeedwaterpumpsignal05/05/94.
Attachment1toAEP:NRC:1181Page2(4)(5)(6)4.8.1.1.2.e4.8.1.24.4.11.34.7.4.1.bTable4.3-1>,Items7&84.3.2.1.2(P-12)Table4.3-2>,Item4.dTable4.3-6AItems5,6,7&8Table4.3-10,Items2,3,11Table4.3-1>,Items7,9,10&llTable4.3-2>,Iteml.d4.3.2.1.2(P-11)4.4.11.1.bDescritionofChaneDelaydieselgeneratortestingincludingreliefvalvetestingandessentialservicewatervalvetestingDelayRTDcalibrationsDelaypressurizerpressure&levelcalibrations,interlockfunctiontesting,andPORVcalibrationsDueDate03/25/94.limitingduedate04/28/9401/29/94(8)4.1.3.3(9)(10)4.5.2.d.14.5.3.14.7.7.l.aTable4.3-1<,Item54.3.1.1.2(P-6)(12)4.6.5.9(7)Table4.3-10,Item16DelayReactorVesselLevelIndicationSyst:emCalibrationDelayanalogrodpositionindicationfunctionaltestingDelayRHRauto-closureinterlocktestingDelayvisualinspectionofinaccessiblesnubbersDelayintermediaterangecalibrationandinterlockfunctionaltestingDelaydividerbarriersealinspection04/20/9405/03/9403/07/94.03/19/9401/17/9403/08/94(13)(14)4.7.9.2.b.lTable4.3-10,Item184.5.2.d.24.5.3.1Delaycontainmentwaterlevelcalibrationsand"sumpvisualinspection01/31/94limitingduedateDelayRCPfireprotectiontesting03/30/94(15)4.2.5.2Table4.3-1>,Items12&13Delayreactorcoolantflowcalibrations01/28/94 Attachment1toAEP:NRC:1181Page3(16)Table4.3-2>,Items9.a,9.b,9.c&9.dDescritionofChaneDelayESFManualTripActuatingDeviceOperationalTestDueDate04/15/94limitingduedate>Tables4.3-1and4.3-2refertoT/S4.3.1.1.1andT/S4.3.2.1.1,respectively.Adescriptionoftheproposedchanges,thereasonsforthechanges,andouranalysesconcerningsignificanthazardsconsiderationsforeachgroupofextensionrequestsaregivenintheremainderofthisattachment.ItisworthnotingthattwosimilarextensionrequestsfortheUnit2Cycle6-7outagewereapprovedbytheNRConDecember28,1987andFebruary29,1988viaAmendments97and99,respectively.Thesetwoamendmentsgrant:edextensionsfortheT/Ssdescribedingroups1through9and16,above.1and2'eact:orTriandESFResonseTestinWearerequestingextensionsforthetime-responsetestingrequiredbyT/Ss4.3.1.1.3and4.3.2.1.3forthereactortripandEngineeredSafet:yFeatures(ESF)instrumentationinT/STables3.3-1and3.3-3.Inaddition,wearerequestingextensionsforsurveillancerequirementsinvolvingequipmentthatactuatesonanESFsignal(seetablebelow).ThesesurveillancesinmanycasesinvolvethesameequipmentandareperformedinparttosatisfytheresponsetimetestingofT/Ss4.3.1.1.3and4.3.2.1.3.Theseadditionalsurveillances,theaffectedcomponents,andtherespectiveESFactuationsignalsareasfollows:It:em~TS2~4.5.l.d4.5.2.e4.6.2.1.cComonentsaccumulatorisolationvalvesECCSautomaticvalvescentrifugalchargingpumpsafetyinjectionpumpresidualheatremovalpumpcontainmentsprayautomaticvalvesandpumps~ESPSinalSISISISISIcontainmentpressurehigh-high4,6.4.6.2.2.c4.6.3.1.24.7.1.2.e,fspray,additivesystemautomaticvalvescontainmentisolationvalvescontainmentpurgeandexhaustvalvesauxiliaryfeedwaterautomaticvalvesandpumpstartingcontainment=pressurehigh-highPhaseAisolationPhaseBisolationcontainmentpurgeandexhaustisolationvariousSeeT/SGroup(3)
Attachment1toAEP:NRC:1181Page4Item~TS7.4.7.3.1.b8.4.7.4.1.b~GomonentscomponentcoolingwaterautomaticvalvesessentialservicewaterautomaticvalvesESFSialSISISeeT/SGroup(4)9.4.7.5.l.e.2controlroomventilation10.4.7.6.1.d.3ESFventilationSIPhaseAisolationcontainmentpressurehigh-highTheextensionsareneededfromJanuary2,1994(mostlimitingsurveillanceduedate),untiltheUnit2refuelingoutage.AttheCookPlant,responsetimetestingisperformedinseveralparts.Theportionsofcircuitryfromthetransmittertothebistable,fromthebistabletothemasterrelaycontact,andfromthemasterrelaycontacttoequipmentoperationaretestedseparately.TestingofthecompleteportionfromthetransmittertothemasterrelaycontactcannotbeperformedatpowerwithoutviolatingtheT/Ssoradverselyimpactingplantoperation,i.e.,reactortrip.T/Ss3.3.1.1,3.3.2.1and3.0.3requiretheplanttobeshutdownifsufficientreactortriporESFinstrumentationisnotoperable.Bothtrains(allchannels)ofthefunctionbeingtestedmustbetakenoutofserviceduringthistestbecausethesametestsignalgoesintobothtrains,whichgeneratesareactortripsignalorESFactuation.Shouldtheynotbeintest,eachsignalwouldinitiateprotectivefunctionssuchassafetyinjectionandcontainmentspray.Therefore,theportionofthetime-responsetestsfromthebistableuptothemasterrelaymustbedoneduringshutdown.However,testingfromthetransmittertothebistablecanbeperformedatpowerandwillbepriortoitssurveillanceduedate.Thebalanceoftheequipment,i.e.,fromthemasterrelaycontacttoequipmentoperation,istestedaspartofthesurveillanceslistedinthetableabove.Ofthesesurveillances,Items2through8arespecificallyrequiredbyT/Sstobeperformedduringshutdown.Items1,9and10arenotspecificallyprohibitedbyT/Ssfrombeingperformedatpower.However,todothistesting(aswellastheothertestinglistedinthetable)wouldrequireustoremoveanentiretrainofsafetyequipmentfromoperation(withtheexceptionofthespecificequipmentbeingtested).Becausethisremovesalayerofprotectionbuiltintotheplant,andbecauseitinvolvesoperatingtheplantinanabnormalconfiguration,itisnotconsideredprudenttoperformthistestingatpower.ThesurveillancehistoryoftheseESFsystemsshowsthatwehavenoreasontobelievethattheremaybeanyfailuresinmeetingtheT/Srequirementsduetoequipmentdegradationduringtheextensionperiod.Additionally,wenotethattheESFandreactorprotectionsystemchannelsaresubjectedtoaT/Srequiredsurveillanceprogramofchannelchecksandchannelfunctionaltests.Allrequiredchannelchecksandchannelfunctionaltestswillcontinuetobeperformed.Webelievetheseadditionaltestsprovide'ndicationoftheoperabilityofthesystems,andwouldprovideindicationofsignificantdegradation.
Attachment1toAEP:NRC:118110CFR50.92CriteriaPage5Per10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendment,doesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1Basedonourreviewofpasttestdata,andthefactthattheequipmentissubjecttoasurveillanceprogramwhichincludeschannelchecksandchannelfunctionaltests,webelievetheextensionswearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,aboveLastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccident,buttheresults,ofwhicharewithinlimitsestablishedasacceptable.Forthereasonsdetailedabove,webeliev'ethischangefallswithinthescopeofthisexample.Therefore,webelievethischangedoesnotinvolvesignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page63AuxiliaFeedwaterPumTestinT/STable4.3-2Item6.drequiresachannelfunctionaltestofthemotordrivenauxiliaryfeedwaterpumpstartonlossofmainfeedwaterpumpsignaltobeperformedonan18monthbasis.Toperformthi'stestingduringpoweroperationswouldinvolvetrippingatleastonemainfeedpump,whichwouldresultinareductionofpowerandcauseathermaltransienttobeimposedontheplant.T/Ss4.7.1.2.e&4.7.1.2.frequiretestingtodemonstratethatthemotor-andturbine-drivenauxiliaryfeedwaterpumpsstartandthattheassociatedautomaticvalvesactuatetotheircorrectpositionuponreceiptoftheappropriatesignalaslistedinT/STable4.3-2.PerT/Ss4.7.1.2.e&4.7.1.2.f,thistestingmustbeperformedduringshutdown.TheseextensionsareneededfromMay5,1994,untiltheUnit2refuelingoutage.Basedontheabove,wecannotperformthesesurveillanceswhileatpower.However,inpractice,theessentialportionsoftheseT/Ss(thatis,startupoftheauxiliaryfeedwaterpumpswhenrequiredandmovementofthevalvestotheircorrectposition)occurwhentheunittrips.ThelastreactortripoccurredonJuly2,1992.Priortestingexperiencewithregardtothesesurveillanceshasindicatednosignificantproblemswhenthesurveillance,wasperformed.Althoughwerecognizethatnotalltheactuationcircuitryhasbeenchallengedasaresultofthereactortrip,wefeelthatourrecentexperience,inconjunctionwiththeexcellenttesthistoryinthisarea,justifiesourrequesttoextendthesurveillanceinterval.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,(2)(3)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,orinvolveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Criterion1Page7Asdiscussedabove,portionsofthesystemhaveundergoneachallengeduetoarecentactuation(duringaunittrip).Thisfact,coupledwithourexcellenttesthistoryforthesesurveillances,leadsustobelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Vebelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolvesignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:11814DieselGeneratorTestinPage8Anextensionofthesurveillanceintervalisrequestedfor=thesurveillancerequirementsofT/S4.8.1.1.2.e.ThesesurveillancesarerequiredbyT/Sstobeperformedduringshutdown.Therequirementsincludesubjectingthedieseltoaninspectioninaccordancewithmanufacturer'srecommendations,aswellastestingtoverifythatthedieselgeneratoranditsassociatedcircuitryarecapableofenergizing,sequencingandsheddingtheemergencyloadsuponreceiptoftheappropriatesignal.AnextensionofthesurveillanceintervalisalsonecessaryforpartoftherequirementsofT/S4.8.1.2,since4.8.1.1.2isreferencedthere.TheextensionisneededfromMarch25,1994(limitingduedate),throughtheUnit2refuelingoutage.DuringthefourandahalfmonthperiodfromMarch25untilthestartoftheoutage,eachdieselgeneratorshouldaccumulate5additionalstartsand5-7additionalrunninghours.Theaffectthattheseadditionalstartswouldhaveonthedieselgeneratorsisbelievedtobeinsignificantbasedonthewearhistoryofeachmachine.Thus,webelievetheadditionalstartsdonotconstitutesufficientneedtoperformthesubjectsurveillancespriortotheproposedextendeddate.Thehistoryofdieselgeneratorrepairsfromthepastfewyearsdonotindicateanyproblemareaswhich,inourjudgement,wouldbesignificantlyaffectedbytheproposedsurveillanceintervalextension.Furthermore,conditionswhichhaverequiredmaintenanceonthedieselgeneratorshavebeencorrectedatthetimeofdiscoveryandhavenotrequireddeferraluntilanoutage(i.e,,weshouldnotbedeferringanysignificantmaintenanceitemsthroughtheextensionperiod).Currently,wehaveatrendingprogramfortheparametersmeasuredduringourT/Srequiredmonthlytesting.Thesetrendsarereviewedbyourdieselgeneratorsystemengineer.Ifanadversetrendbegantodevelop,thepreventive/correctivemeasureswouldbetakentopreventasignificantproblemfromoccurring.Also,areviewofprevioustestresultsdidnotindicateanyreasonstosuspectthatthedieselgeneratorassociatedcircuitry(i.e.,energizing,sequencing,andsheddingthevariousemergencyloads)wouldnotpassrequiredsurveillancetestswiththesurveillanceintervalextended.Basedontheabove,webelievethatthereisnoreasontosuspectthatthedieselgeneratorswouldnotbecapableofperformingtheirsafetyfunctionsasrequiredbytheT/Ss.Twootherextensionsrelatedtothedieselgeneratorsarealsonecessarytoavoidashutdown.ThesearefortherequirementsofT/Ss4.4.11.3and4.7.4.l.b.T/S4.4.11.3requirestestingoftheemergencypowersupplyforthepoweroperatedreliefvalves(PORVs)andtheirassociatedblockvalves.SincethistestinginvolvescyclingthePORVsandblockvalves,.itisgenerallyperformedduringshutdownandinconjunctionwiththedieselgeneratortestingrequirementsofT/S4.8.1.1.2.e,assuggestedbyT/S4.4.11.3.T/S4.7.4.1.binvolvestestingautomaticvalvesintheessentialservicewater(ESW)system.PerT/Ss,thissurveillancetestingmustbeperformedduringshutdown.SincesomeoftheESWvalveswhicharerequiredtobetestedinvolvecoolingwaterforthedieselgeneratoranditsassociatedequipment,thistestingisgenerallyconductedinconjunctionwiththedieselgeneratortestingofT/S4.8.1.1.2.TheextensionforboththeESWvalvesandthePORVemergencypowersupplyareneededfortheperiodofApril15,1994throughtheUnit2refuelingoutage.Previoustest Attachment1toAEP:NRC:1181Page9resultsdonotindicateanyreasontosuspectthatthevalvesandtheirassociatedcircuitrywouldnotpasstherequiredsurveillancewiththeextendedinterval.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1Forthediesel-generatormachinery,theextensionwillresultonlyinapproximately5additionalstartsand5to7additionalrunhours.Thisisconsideredinsignificantwithregardtothewearhistoryofeachmachine.Forthediesel-associatedcircuitry,theESWautomaticvalves,andthePORVemergencypowersupply,ourreviewofprevioustestdatahasnotindicatedanyreasontobelievetheequipmentwouldnotpasstherequiredsurveillancetestswiththeextendedinterval.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresult.inachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccident,buttheresultsofwhichareclearlywithinthelimitsestablishedasacceptable.Webelievethesechangesfallwithinthescopeofthisexample.Thereforewebelievethischangedoesnotinvolvesignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page105RTDCalibrationsExtensionsarerequestedforthecalibrationofresistancetemperaturedetectors(RTDs).TheextensionsareneededfromApril28,1994,untiltheUnit2refuelingoutage.TheT/SsurveillancesinvolvingtheRTDcalibrationarelistedbelow.Re'irement4.3.1.1.1,Table4.3-1,Item74.3.1.1.1,Table4.3-1,Item84.3.2.1.2(P-12)4.3.2.1.1,Table4.3-2,Item4.dOTATChannelCalibrationOPATChannelCalibrationTotalInterlockFunctionTestingSteamFlowinTwoSteamLines--HighCoincidentwithT,~--Low-LowChannelCalibration4.3.3.5.1Table4'-6A,Items5&7CalibrationofAppendixRRemoteShutdownMonitoringInstrumentationReactorCoolantLoops(2&4)Temperature(Cold)4.3.3.5.1Table4.3-6A,Items6&8CalibrationofAppendixRRemoteShutdownMonitoringInstrumentationReactorCoolantLoops(2&4)Temperature(Hot)4.3.3.6Table4.3-10,Item2CalibrationofPost-AccidentMonitoringReactorCoolantOutletTemperature-Tao>Channel4.3.3.6Table4.3-10,Item3CalibrationofPost-Accident:MonitoringReactorCoolantInletTemperature-Tco<zChannel4.3.3.6Table4.3-10,Item11CalibrationofPost-AccidentMonitoringReactorCoolantSystemSubcoolingMarginMonitorChannel
Attachment1toAEP:NRC:1181Page11Theextensionsrequestedinthiscategoryareforthecalibrationofthesensorsonly.ThecalibrationprocedurerequiresdatatobetakenatRCStemperaturesrangingfromapproximately250'Fthroughoperatingtemperatures.ThisprocedurecannotbeperformedatpowerbecauseofthelowtemperaturesnecessaryforthecalibrationandbecauseisothermalconditionsthroughouttheRCSarerequired.ThechannelsinvolvedwiththeRTDsaresubjecttoT/Srequiredchannelchecksand/orchannelfunctionaltests.Thistesting,whichwillcontinueduringtheextensionperiod,wouldbeexpectedtoprovideindicationofRTDdrift.Also,sincenarrowrangeRTDsfeedthehTcircuits,comparisonsofhT~tothecalorimetriccalculatedpowerorpowerrangedetectorsshouldshowdriftinthenarrowrangeRTDs.WehavefoundRTDsattheCookNuclearPlanttobeverystable,andhavenotexperiencedsignificantdriftingproblems.Forallofthesereasons,wehavenoreasontobelievethattheRTDswillnotremainoperableduringtheextensionperiod.10CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1),involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1TheRTDsattheCookNuclearPlanthavetraditionallybeenverystable.SeveralindependentinstrumentsareavailablewhichwouldallowustonoticedriftoftheRTDs.Also,channelsinvolvingtheRTDsaresubjecttoT/Srequiredchannelchecksand/orchannelfunctionaltests,whichwillcontinue,tobeperformedduringtheextensionperiod.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.
Attachment1toAEP:NRC:1181Page12Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescope'fthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:11816PressurizerPressure&LevelCalibrationsandPORVCalibrationsPage13Wearerequestinganextensionfortheperformanceofsomeofthepressurizerchannelcalibrations(pressurizerpressureinstrumentsNPS-153&NPP-153,andpressurizerlevelinstrumentNLP-153)andinterlocktestinginvolvingthepressurizerpressureinstrumentation.WearealsorequestingreliefforthecalibrationofthePORVs.TheextensionsareneededfromJanuary29,1994,untiltheUnit2refuelingoutage.TheaffectedT/Ssareasfollows:Reuirement4.3.1.1.1,Table4.3-1,Item7CalibrationforOTATReactorTrip.4.3.1.1~1,Table4.3-1,Item9CalibrationforPressurizerPressure-LowReactorTrip4.3.1.1.1,Table4.3-1,Item10CalibrationforPressurizerPressure-HighReactorTrip4.3.1.1.1,Table4.3-1,Item11CalibrationforPressurizerWaterLevel-HighReactorTrip4.3.2.1.1,Table4.3-2,Iteml.d~~~~~CalibrationforPressurizerPressure-LowESFActuation4.3.2.1.2(P-11)InterlockTotalFunctionTesting4.4.ll.l.bCalibrationofPowerOperatedReliefValvesPerformanceofthiscalibrationisnotconsideredtobeprudentatpowerduetotheconfigurationofthepressurizerpressureandlevelinstrumentation.Twoofthepressurizerpressureinstruments(NPS-153andNPP-153)shareacommonsensinglinewithoneofthepressurizerlevelinstruments(NLP-153).CalibratingeitherNPS-153orNPP-153posestheriskofperturbingthe,inputtotheothertransmitter,whichcouldresultinatrip.CalibratingNLP-153posestheriskofperturbingtheinputtoNPS-153andNPP-153transmitters,'hichalsocouldresultinatrip.Theexemption'forthePORVsisalsoneededbecausethecalibrationsmakeallthreePORVsinoperableatthesametime,whichiscontrarytotherequirementsofT/S3.4.11.Asdiscussedinthepreviousparagraph,certainchannelsofpressurizerpressureandlevelinstrumentationposeathreattotrippingthereactor.However,therearethreechannelsofpressurizerlevelinstrumentationandfourchannelsofpressurizerpressureinstrumentationofwhichtwolevelandtwopressurechannelsofinstrumentationcan,andwill,becalibratedasrequiredbytheTechnicalSpecifications.Thus,twoofthethreepressurizerlevelandtwoofthefour Attachment1toAEP:NRC:1181Page14pressurizerpressurechannelswillsatisfytheT/Ssurveillancerequirements.Also,theinstrumentationchannelsforwhichwearerequestingsurveillanceintervalextensionsaresubjecttoT/Srequiredchannelfunctionaltestingand/orchannelchecks.Thechannelfunctionaltestsweperformarefarmorestringentthanrequired.Thesetestsnotonlydemonstratechannelfunctionality,butalsoverifycalibrationoftripsetpoints,actuationsandalarms.Theonlyportionofthechannelthatisnottestedisthesensor,whichisqualitativelyverifiedduringchannelchecks.Thus,thetestingwewillcontinuetoperformwouldbeexpectedtoprovideindicationoftheoperabilityofthesystems,andwouldprovideindicationofsignificantdegradation.Lastly,wenotethatbasedonourreviewofthesurveillancehistory,webelievethisequipmentwillremainoperableduringtheextensionperiod.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:li(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1CompletingtherequiredT/Ssurveillancesontwoofthethreepressurizerlevelchannelsandtwoofthefourpressurizerpressurechannelswillensurethatthemajorityoftheequipmentiscalibratedasrequired.Also,theapplicablechannelfunctionaltestsandchannelchecksshouldensurethatthesesystemswillperformasdesigned.Additionally,basedonthesurveillancehistoryoftheequipment,webelievethattheequipmentwillremainoperableduring-theextensionperiod.Wethereforebelievetheextensionwearerequestingwillnotresultindeteriorationtotheextentthattheequipmentcannotperformitsintendedfunction.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginof.safety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,t'eextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.
Attachment1toAEP:NRC:1181Page15Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples.(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangesthatmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexampleforthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page167ReactorVesselLevelIndicationSstemAnextensionisrequestedforthechannelcalibrationoftheReactorVesselLevelIndicationSystem(RVLIS)requiredbyT/STable4.3-10,Item16.Therequiredcalibrationcannotbeperformedatpowerbecauseworkmustbeperformedinthelowervolumeofcontainmentandreactorheadarea,whichareonlyaccessiblewhentheunitisshutdown.TheextensionisneededfromApril20,1994,untiltheUnit2refuelingoutage.RVLIShastwotrainsofindicationthataresubjectedtoT/Srequiredmonthlychannelcheckswhichwewillcontinuetoperformduringtheextensionperiod.Thesechannelchecksprovideindicationoftheoperabilityofthesystem,andwouldbeexpectedtoprovideindicationofsignificantdegradationofthesystem.Ourreviewofthemaintenancehistoryofthesystemgivesusnoreasontobelievethesystemwouldbeinoperableduringtheextensionperiod.Additionally,indicationofinadequatecorecoolingcanbeobtainedbyobservingcoreexitthermocouplereadingsorbycheckingthesubcoolingmarginmonitor.ThesearethemethodstheoperatorswouldhaveusedtoassessinadequatecorecoolingpriortohavingRVLIS.WealsonotethatthereareannunciatorswhichindicatefailureofRVLIS.Forthesereasons,webelievethattheextensionswearerequestingwillnotadverselyimpacttheabilityofthisequipmenttoperformitssafetyfunction.~~10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1Theequipmentissubject.tonormalsurveillanceswhichwouldbeexpected'toprovideindicationofsignificantdegradation.Also,otherinstrumentationisavailablewhichalsoprovidesindicationofinadequatecorecooling.Lastly,thepastmaintenancehistoryoftheequipmentgivesusnoreasontobelievethattheequipmentwouldbeinoperableduringtheextensionperiod.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.
F Attachment1toAEP:NRC:1181Page17Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Forthereasonsdetailedabove,webelieve'thischangefallswithinthescopeofthisexample.Therefore,webelievethischangedoesnotinvolvesignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page188RodPositionIndicationSstem,Thischangewoulddelayfunctionaltestingoftherodpositionindicator(RPI)channelsrequiredevery18monthsbyT/S4.1.3.3.TheextensionisneededfromMay3,1994,untiltheUnit2refuelingoutage.AlthoughT/S4.1.3.3isonlyapplicableinModes3,4,and5,webelievereliefisneededfromthisT/StocontinueoperationinModes1and2sinceT/S3/4.1.3.2requirestheRPIchannels,tobeoperableinthesemodes.ThesurveillanceweperformtosatisfyT/S4.1.3.3isactuallyacalibrationoftheRPIchannelsovertherodinsertionrange.Sincerodsmustbeinsertedtoperformthecalibration,itcannotbeperformedatpowerbecausetodosowouldviolatetherodinsertionlimitsofT/Ss3.1.3.5and3.1'.3.6.TheoperabilityoftheRPIchannelsisfunctionallyverifiedonceper12hoursperT/S4.1.3.2bycomparisontothedemandpositionindicationsystem.Also,duringthe31daysurveillancetosatisfyT/S4.1.3.1.2,therodsaremovedatleasteightstepsandtheRPImetersareverifiedtotrackwiththedemandposition.ThesecomparisonswouldbeexpectedtoindicatesignificantdegradationintheRPIchannels.Surveillancesthatindicatethecoreisperformingasdesignedareprovidedbytheincorefluxmaps,'whicharetakenatleastonceevery31effectivefullpowerdaystosatisfytherequirementsofT/Ss4.2.2.2(Fo(Z)),4.2.3(F~H)and4.2.1.4(AxialFluxDifferenceTargetBand).Coreperformanceisalsoindicatedbytheexcoredetectors,whichareusedtomeasurethequadrantpowertiltratioperT/S4.2.4andaxialfluxdifferenceperT/S4.2.1.1.a.Thesesurveillanceswouldbeexpectedtoindicatesignificantdiscrepanciesbetweenindicatedandactualrodposition.Lastly,sincetheT/SrequiredsurveillancesusedtoverifyoperabilityoftheRPIswillcontinuetobeperformedduringtheextensionperiod,thereisnoreasontobelievethatwewouldbeoperatingoutsidetheboundsofT/S3.1.3.2.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Page19Criterion1T/SrequiredcomparisonoftheRPIchannelstothedemandpositionindicationsystemwouldbeexpectedtoindicatesignificantdegradationintheRPIchannels.Inaddition,othersurveillancessuchasthedeterminationofthequadrantpowertiltratio,axialfluxdifferenceandincorefluxmappingsurveillances,provide...acomparisonofcoreperformancetodesignandwouldbeexpectedtoindicatesignificantdeviationsoftherodsfromtheirindicatedposition.SinceoperabilityoftheRPIswillcontinuetobedeterminedwithourT/Srequiredsurveillancesduringtheextensionperiod,thereisnoreasontobelievethatwewouldbeoperatingoutsidetheboundsofT/S3.1.3.2.Forthesereasons,webelievetheextensionwearerequestingw'illnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page209RHRAuto-ClosureInterlockWearerequestinganextensionfortheresidualheatremoval(RHR)auto-closureinterlocktestrequiredbyT/S4.5.2.d.l.AnextensionisalsorequestedforT/S4.5.3.1sinceitreferencesT/S4.5.2.TheextensionsareneededfromMarch7,1994,untiltheUnit2refuelingoutage.TheRHRauto-closureinterlockautomaticallyisolatestheRHRsystemfromtheRCSifRCSpressureisabove600psig.Inordertodemonstrateoperabilityoftheautoclosureinterlock,itisnecessarytoopentheRHRisolationvalvesinthecooldownlinefromthehotleginordertoverifythatthevalveswouldautomaticallyclosewiththeRCSpressureabove600psig.Thiscannotbeaccomplishedwiththeunitoperating(i.e.,withtheRCSfullypressurized)becauseitwouldresultinexposingtheRHRsystemtopressureshigherthantheRHRsafetyvalves'etpoints;Previoussurveillancetestinghasdemonstratedthattheauto-closureinterlockisveryreliable.Theprevioustestresultsgiveusnoreasontobelievetheauto-closureinterlockwouldbeinoperableduringtheextensionperiod.ThecalibrationfortheRCSwide-rangepressuretransmitters,whichprovideinputintotheinterlock,canbedoneatpowerandwillbeperformedbyitsSeptember9,1993duedate.Thus,theonlyportionoftheinterlockforwhichthesurveillanceswillnotbecurrentistheportionfromthebistableoftheRHRsuctionvalvesthroughvalveoperation.Additionally,wenotethatwhentheunitisoperating(i.e.,notonRHR),theRHRsuctionvalvesareclosedandproceduresrequirepowertoberemovedfromthevalveoperators.Thisprecludesinadvertentvalveopeningandthusalleviatestheneedfortheauto-closureinterlocktofunction.10CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Page21Criterion1Thesurveillancetesthistoryoftheauto-closureinterlockhasshownthatthesystemishighlyreliable,andgivesusnoreasontobelievetheequipmentwouldbeinoperableduringtheextensionperiod.Thewide-rangepressuretransmitters,whichprovideinputintotheauto-closureinterlock,willhaveacurrentcalibration.Additionally,wenotethatwhentheRHRsystemisnotinservice,powerisremovedfromthesuctionvalveoperators,thuspreventinginadvertentvalveopeningandeliminatingtheneedfortheauto-closureinterlock.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Vebelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page2210VisualInsectionofInaccessibleSnubbersThischangewoulddelayvisualinspectionsof,inaccessiblesnubbersrequiredbyT/S4.7.7.1.a.TheextensionisneededfromMarch19,1994,throughtheUnit2refuelingoutage.Theextensionisrequiredbecause,bydefinitioninT/S4.7.7.l.aandTable3.7-9,thesesnubbersareinaccessibleduringreactoroperation,thusrequiringtheinspectionstobeperformedduringshutdown.NotethatfunctionaltestingofsnubbersperT/S4.7.7.1.cisnotrequireduntilafterthescheduledrefuelingoutagestartdate.InthepasttenyearsofvisualinspectionsonUnit2inaccessiblesnubbers,wehavefoundonlyoneinoperablesnubber.Theinoperablesnubberwasdiscoveredduringthesteamgeneratoroutagein1988.Sincethen,fourvisualinspectionshavebeenperformedontheinaccessiblesnubbers,inwhichnonehavebeenfoundtobeinoperable.Basedontheseinspectionresults,weareallowedtoperformtheinspectionsatthemaximumallowedT/Sfrequencyof18months(125X).ItshouldbenotedthatwesubmittedarequestinourletterAEP:NRC:1143,datedMay1,1992topermanentlychangethesurveillanceintervalsforsnubbervisualinspections.ThesubmittalisbasedonguidancefromGenericLetter90-09,"AlternateRequirementsforSnubberVisualInspectionsIntervalsandCorrectiveActions."IfwecouldapplytheguidanceofGenericLetter90-09orourproposednewSpecificationsonourcurrentvisualinspectionresultsofinaccessible'nubbers,wewouldhaveuptothemaximum48monthintervalallowedforournextinspection.Thiswouldputourinspectionduedatebeyondthescheduledrefuelingoutagestartdate,thuseliminatingtheneedforthisextension.BasedonthehistoryofourinaccessiblesnubbersandontheguidanceofGenericLetter90-09,webelievetheinaccessiblesnubberswillremainoperableduringtheextensionperiod.10CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Page23Criterion1Oursurveillancehistoryofvisualinspectionsoninaccessiblesnubbershasfoundonlyoneinoperablesnubberinthepasttenyears.Also,ifGenericLetter90-09guidanceisapplied,oursurveillanceintervalwouldbe48months.Basedontheabove,wehavenoreasontobelievetheinaccessiblesnubberswillbeinoperableduringtheextensionperiod.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccident,butwheretheresultsarewithinthelimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Therefore,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page2411IntermediateRaneDetectorCalibrationsThischangewoulddelaythecalibrationoftheintermediaterange(IR)detectorsrequiredbyT/S4.3.1.1.1,Table4.3-1,Item5.Also,itwoulddelayinterlockfunctionaltestingofP-6requiredbyT/S4.3.1.1.2.TheseextensionsareneededfromJanuary17,1994,untiltheUnit2refuelingoutage.TheneedforthisextensionisbecausetheIRdetectorscannotbecalibratedwhileatpower.Thecalibrationrequiresthatatestsignalcoveringtherangeof10to10ampsbesuperimposedovertheexistingcurrent.SincethecurrentoftheIRdetectorsisinthe104ampsrangeduringpoweroperation,asuperimposedsignallessthanthatcouldnotbeobserved.Therefore,theIRdetectorscouldnotbecalibratedbelowtheactualcurrentatwhichweareoperating.PastoperatinghistoryinUnit2hasshownthattheIRdetectorshaveperformedwithoutseriousdegradation.Thereisnoreasontobelievethatthedetectorswouldbeinoperableduringtheextensionperiod.TheIRissubjectedtoaT/Srequiredchannelcheckevery12hours.TheIRcurrentsaretrendeddailyandnormalizedto25Xpowertoensurethatthehighfluxatlowpowertripsetpointsdonotbecomenonconservative.Throughthechannelchecksandtrendingprogram,itisexpectedthatanydegradationinanIRdetectorwouldbenoticed.Lastly,theprotectionprovidedbythesedetectorsisrequiredwhileshutdown,oratlowpower(approximatelylessthan10X)andnotatournormaloperatingpower.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluati'onoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Page25Criterion1OuroperatinghistoryoftheUnit2IRdetectorshaveshownthattheyarehighlyreliable,andgiveusnoreasontobelievetheywouldbeinoperableduringtheextensionperiod.OurchannelchecksandtrendingprogramwoulddetectdegradationinanIRdetector.Forthesereasons,webelievetheextensionwe.arerequestingwillnotresultinasignificantincreaseinthe,probabilityorconsequencesof"'apreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page2612DividerBarrierSealInsectionT/S4.6.5.9requiresavisualinspectionofatleast95Xof-theseal'sentirelength.Also,itrequiresthattwotestcouponsberemovedfromthesealfortestingtoensurethephysicalpropertiesarewithinspecifiedlimits.PerthisSpecification,theinspectionistobeperformedwhileshutdown.TheextensionsareneededfromMarch8,1994,untiltheUnit2refuelingoutage.Thedividerbarriersealisapassivedesignfeature,thusitisnotsubjectedtoanyoutsideforcesotherthantheenvironment.Duringthecycle7-8refuelingoutage,wereplaced100Xofthedividerbarrierseal.Oursubsequentinspection,duringthelastoutage,revealednodegradationoftheseal.Also,whenthetestcouponsweresubjectedtothetensilestrengthandelongationtests,theysatisfiedtheacceptablephysicalpropertyrequirements.Basedonthefactsthatthedividerbarriersealispassive,new,andhasshownnodegradation,webelievethereisnoreasontosuspectthatitwouldnotbeoperableduringtheextensionperiod.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1Thedividerbarriersealisapassivedesignfeaturewhichwasentirelyreplacedin1990.Oursubsequentinspectionrevealednodegradationtothesealandthephysicalpropertiesofthetestcouponswereacceptable.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.
Attachment1toAEP:NRC:1181Page27Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page2813ReactorCoolantPumRCPFireProtectionT/S4.7.9.2.brequiresthattheRCPsfireprotectionsystembefunctionallytestedevery18months.Inordertoperformthetest,theRCPfiredetectioninstrumentationrequiredperT/STable3.3-11andthefiresuppressionsystemrequiredbyT/S3.7.9.2mustbemadeinoperable,whichisnotconsideredprudentduringoperationoftheRCPs.Itisalsonotedthat,sincetheRCPsarelocatedinahighradiationarea,afirewatchcannotbeestablishedperActionStatementBofT/S3.7.9.2.Therefore,wewouldbeforcedtorelyonclosed'circuittelevisioncoverageasasubstituteforthecontinuousfirewatch.Intheeventthatacamerafailed,wewouldbeinnon-compliancewiththerequirementsofT/S3.7.9.2.TheextensionisneedfromMarch30,1994,untiltheUnit2refuelingoutage.BasedonthepastRCPsprinklersystemsurveillancehistory,thereisnoreasontobelievethatitwouldnotbecapableofperformingit'sintendedsafetyfunctionduringtheextensionperiod.Also,wehaveseismicallyqualifiedoilcollectionsystemsontheRCPs,installedinaccordancewith10CFR50,AppendixR.ThesesystemsaredesignedtomitigatetheeffectsofaRCPlubeoilleak.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1BasedontheRCPfireprotectionsystemsurveillancerecordthereisnoreasontobelievethatitwouldnotbecapableofperformingit'sintendedsafetyfunction.Additionally,itisnotedthattheRCPoilcollectionsystemisdesignedtomitigatetheeffectsof'RCPlubeoilleak.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.
Attachment1toAEP:NRC:1181Page29Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelieve'hischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page3014ContainmentWaterLevelInstrumentationandSumVisualInsectionT/S4.3.3.6,Item18requiresthatthecontainmentwaterlevelinstrumentationbecalibratedevery18months.T/S4.5.2.d.2requiresthatthesumpanditsinletsbesubjectedtoan18monthvisualinspection.Anextensionisalso"neededforT/S4.5.3.1sinceitreferencesT/S4.5.2.Thesesurveillancescannotbeperformedduringreactoroperationsincetheyrequireentryintothelowervolumeofcontainment.TheextensionsareneededfromJanuary31,1994(calibrations)andMarch21,1994(visual),untiltheUnit2refuelingoutage.Ourpasthistoryoncontainmentwaterlevelinstrumentationhasnotshownanysignificantdegradation.Thiswaterlevelinstrumentationisusedtomeasuretheamountofwateronthecontainmentfloorabovethesump.Normally,thereisnowateronthefloor.TheinstrumentationconsistsofRTDs,whichhaveshownstableoperationinthepast.Sincetheinstrumentshavea"live"zeropointonthescale,areadingofzeroorgreaterindicatesthattheinstrumentsareperformingcorrectly.Inaddition,therearetworedundantchannelsthataresubjectedtoT/Srequiredmonthlychannelchecksandthechannelscanbecomparedtoshowifdriftexists.Thereisnoreasontobelievethatthecontainmentwaterlevelinstrumentationwouldbeinoperableduringtheextensionperiod.Thevisualinspectionisperformedtoensurethatwehaveacleansystempriortostartup.Duringreactoroperation,entryintothecontainmentsumpareaisrestricted.Also,wehaveverystrictmaterialcontrolrequirementsforentryintocontainmentandattheendofanoutage,a"containmentcloseouttour"isperformedtoensurethatnomaterialisleftwithincontainment.Inaddition,performanceofvisualinspectionsfollowingreactoroperationhasshownthatverylittledebris,everaccumulatesinthesump.Thereisnoreasontobelievethatthesumporit'sinletswouldbecomeblocked.10CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.
Attachment1toAEP:NRC:1181Page31Criterion1Ourpasthistoryoncontainmentwaterlevelinstrumentationhasnotshownanysignificantdegradationoftheseinstruments.Typically,thereisnowateronthecontainmentfloorfortheinstrumentstomeasure;however,theinstrumentationiscalibratedtoreada"live"zerolevel.Also,wehavetworedundantchannelsthataresubjectedtomonthlychannelchecks,whichwouldshowifdriftexists.Therefore,thereisnoreasontobelievethatthecontainment'aterlevelinstrumentationwouldnotperformitsintendedfunctionduringtheextensionperiod.Thelikelihoodofasignificantamountofdebrisenteringthesumpisverylowbecausewehaveverystrictrequirementsformaterialcontrolinsidecontainment,restrictedaccessintothecontainmentsumparea,andaninspectionofcontainmentisperformedattheendofanoutage.Thereisnoreasontobelievethatthesumporitsinletscouldbecomeblockedduringtheextensionperiod.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreduction,inamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsby.providingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page3215ReactorCoolantFlowTransmitterCalibrationsT/S4.2.5.2andT/S4.3.1.1.1,Table4.3-1,Items12&13requirethereactorcoolant(RC)flowinstrumentationforeachlooptobecalibratedevery18months.Thesecalibrationsshouldnotbeperformedatpowerbecauseofthepossibilityofareactortrip.Eachsetoftransmitters(3perloop)hasacommonsensingline,whichwhenvalvingin(orout)oneofthetransmitterscouldcauseareduceddifferentialpressureinthe.othertwotransmitters.Thiscouldcauseareactortriponlowflowinoneloopsincethetwooutofthreetrip-logicwouldbesatisfied.TheextensionforthesesurveillancerequirementsareneededfromJanuary28,1994,untiltheUnit2refuelingoutage.PastsurveillancehistoryhasshownthattheRCflowchannelsareverystable;verylittleornodriftisfoundduringcalibrationandtheyhavealwaysbeenwithintheirallowablerange.Also,sincetherearethreechannelsperloop,driftwouldbeexpectedtobediscoveredduringtheT/Srequiredshiftlychannelchecksormonthlyfunctionalchecks.Sincethechannelshavebeenverystableandwehavethreechannelsperlooptoindicatedrift,thereisnoreasontobelievethatcontinuedoperationduringtheextensionperiodwouldcausetheinstrumentationtobecomeinoperable.10CFR5092CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)'involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindof'ccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1Ourreactorcoolantflowchannelshavebeenverystableinthepast.VehavethreechannelsperloopandperformT/Srequiredchannelchecksandfunctionaltestswhichshouldshowanyindicationofdrift.Therefore,thereisnoreasontobelievethatthereactorcoolantflowchannelswouldnotbeoperableduringtheextensionperiod.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.
Attachment1toAEP:NRC:1181Page33Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.
Attachment1toAEP:NRC:1181Page3416TriActuatinDevice0erationalTestinESFmanualactuationExtensionsarerequestedfortheTripActuatingDeviceOperationalTesting(ESFmanualactuationswitches)specifiedinT/S4.3.2.1.1,Table4.3-2,Items9.a,9.b,9.c,and9.d.ThesetestscannotbeperformedatpowersincetheywouldactuatetheESFfunctionsassociatedwiththeswitches(seetablebelow).TheextensionsareneededfromApril15,1994,throughtheUnit2refuelingoutage.Table4.3-2ItemNoDescrition9.aSafetyinjection(ECCS)FeedwaterIsolationReactorTrip(SI)ContainmentIsolationPhaseAContainmentPurgeandExhaustIsolationAuxiliaryFeedwaterPumpsEssentialServiceWaterSystem9.bContainmentSprayContainmentIsolationPhaseBContainmentAirRecirculationFan9.cContainmentIsolationPhaseAContainmentPurgeandExhaustIsolation9.dSteamLineIsolationThecircuitryassociatedwithmanualactuationofESFfunctionsissubjectedtoT/Srequiredchannelfunctionaltests,monthlyorbi-monthly.Theonlyportionofthechannelnottestedisthemanualactuationswitches.Previoussurveillancetestingoftheswitcheshaveshownthemtobehighlyreliable;infact,therehasneverbeenafailureofanyoftheESFmanualswitchesdetectedduringsurveillancetestingoftheswitchesineitherunit.Additionally,wenotethatthemanualcircuitryservesasabackuptoautomaticactuationchannels,whichinitiatethesameESFfunctions.TheautomaticchannelsaresubjectedtoT/Srequiredchannelchecksandchannelfunctionalteststoverifyoperability.
Attachment1toAEP:NRC:1181Page3510CFR50.92CriteriaPer10CFR50.92,aproposedamendmentwillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.Ourevaluationoftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion1ThesurveillancetesthistoryoftheESFmanualswitchesisexcellent,indicatingnofailuresoftheswitchesineitherunit.Themajorityofthemanualcircuitryissubjecttoachannelfunctionaltestonamonthlyorbi-monthlybasis.Thechannelfunctionaltestingwillcontinuetobeperformedduringthesurveillanceextensionperiod.Additionally,wenotethatthemanualcircuitryservesasabackuptoautomaticcircuitry,whichinitiatesthesameESFfunctions.Forthesereasons,webelievetheextensionwearerequestingwillnotresultinasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident,norwillitresultinasignificantreductioninamarginofsafety.Criterion2Thisextensionwillnotresultinachangeinplantconfigurationoroperation.Therefore,theextensionshouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanypreviouslyevaluatedoranalyzed.Criterion3SeeCriterion1,above.Lastly,wenotethattheCommissionhasprovidedguidanceconcerningthedeterminationofsignificanthazardsby,providingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityorconsequencesofapreviouslyevaluatedaccident,buttheresultsofwhicharewithinlimitsestablishedasacceptable.Webelievethischangefallswithinthescopeofthisexample,forthereasonscitedabove.Thus,webelievethischangedoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.