ML17328A872
| ML17328A872 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/30/1988 |
| From: | BROWN B W, MUDLIN J D EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML17328A869 | List: |
| References | |
| CON-FIN-D-6022 EGG-SD-7798, NUDOCS 9102010173 | |
| Download: ML17328A872 (61) | |
Text
ATTACHMENT2EGG-SD-7798TECHNICALEVALUATIONREPORTONTHESECOND10-YEARINTERVALINSERVICEINSPECTIONPROGRAMPLAN:INDIANAANDMICHIGANELECTRICCOMPANY,DONALDC.COOKNUCLEARPLANTUNIT2,DOCKETNUMBER50-316B.W.BrownJ.D.MudlinPublishedJuly1988IdahoNationalEngineeringLaboratoryEGKGIdaho,Inc.IdahoFalls,Idaho83415Preparedfor:U.S.NuclearRegulatoryCommissionWashington,D.C.20555under~DOEContractNo.DE-AC07-76ID01570FINNo.D6022(Project5)9i02010i739iOi24PDRADQCK050003i5PPDRI I'EEIf ABSTRACTThisreportpresentstheresultsoftheevaluationoftheDonaldC.CookNuclearPlant,Unit2,Second10.-YearIntervalInserviceInspection(ISI)ProgramPlan,Change1,datedDecember1985,includingtherequestsforrelieffromtheAmericanSocietyofHechanicalEngineers(ASHE)BoilerandPressureVesselCodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.TheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlanisevaluatedinSection2ofthisreport.TheISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addendaofSectionXI,(b)acceptabilityofexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNuclearRegulatoryCommission's(NRC)previouspreserviceinspection(PSI)andISIreviews.TherequestsforrelieffromtheASHECoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthesecond10-yearinspectionintervalareevaluatedinSection3ofthisreport.Thisworkwasfundedunder:U.S.NuclearRegulatoryCommissionFINNo.06022,Project5OperatingReactorLicensingIssuesProgram,ReviewofISIforASHECodeClass1,2,and3Components IIIA SUHHARYTheLicensee,IndianaandHichiganElectricCompany,has-preparedtheDonaldC.CookNuclearPlant,Un'it2,Second10-YearIntervalInserviceInspection(ISI)ProgramPlantomeettherequirementsofthe1983Edition,Summer1983Addenda(83S83)oftheASHECodeSectionXIexceptthattheextentofexaminationforCodeClassIandCodeClass2pipingweldshasbeendeterminedbythe1974EditionthroughSummer1975Addenda(74S75)aspermittedandrequiredby10CFR50.55a(b).Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.TheinformationintheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,Change1,datedDecember1985,wasreviewed,includingthe.requestsforrelieffromtheASHECodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical."Asaresultofthisreview,aRequestforAdditionalInformation(RAI)wasprepareddescribingtheinformationand/orclarificationrequiredfromtheLicenseeinordertocompletethereview.BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,theLicensee'sresponsetotheNRC'sRAI,andtherecommendationsforthegrantingofrelieffromtheISIexamination'equirementsthathavebeendeterminedtobeimpractical,ithasbeenconcludedthattheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,Change1,datedDecember1985,isacceptableandincompliancewith10CFR50.55a(g)(4).
CONTENTSA~~BSTRACTo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ollS0UOARY~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~i~~~~~~~~~~~~~~~~~~~oii>~INTRODUCTION~~~~~,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~112.EVALUATIONOFINSERVICEINSPECTIONPROGRAMPLAN........................32.1DocumentsEvaluated.................................................32.2CompliancewithCodeRequirements...................................32.2.1CompliancewithApplicableCodeEditions....................32.2.2AcceptabilityoftheExaminationSample........2.2.3ExclusionCriteria.......................................42.2.4AugmentedExaminationCommitments...............................4.3Conclusions.........................................................42\3.EVALUATIONOFRELIEFREQUESTS....-.........................53.1Class1Components..................................................53.1.1ReactorPressureVessel.............................,...........53,1.1.1RequestforRelief1,ExaminationCategoryB-A,ItemB1.21,PressureRetainingCircumferentialHeadWeldsintheReactorPressureVessel...................53.1.1.2RequestforRelief2,ExaminationCategoryB-A,ItemB1.40,PressureRetainingMead-to-FlangeWeldintheReactorPressureVessel..............................7.1.2Pressurizer.....................................................833.1.2.1RequestforRelief3,ExaminationCategoryB-D,ItemB3.110,PressureRetainingNozzle-to-VesselWeldsinthePressurizer....................83.1.3HeatExchangersandSteamGenerators(Noreliefrequests)3.1.4PipingPressureBoundary(Noreliefrequests)3.1.5PumpPressureBoundary.........................................103.1.5.1RequestforRelief4,ExaminationCategoriesB-L-l,B-L-2,andB-G-1,Class1PumpCasingWeld,PumpCasingInternalSurface,andPumpFlangeSurface......,...........10 44L 3.1.6ValvePressureBoundary(Noreliefrequests)3.1.7General(Noreliefrequests).2Class2Components.................................................1333.2.1PressureVessels(Noreliefrequests)3.2.2Piping.................................-...-.....................133.2.2.1RequestforRelief5,ExaminationCategoryC-F,ItemC5.21,Class2Pipe-to-FluedHeadfields...3.2.2.2RequestforRelief6,ExaminationCategoryC-F,ItemC5.21,Class2P'.pe-to-FluedHeadfields...~~~~~~~~~~~~13~~~~~~~~~~~~153.2.3Pumps(Noreliefrequests)3.2.4Valves(Noreliefrequests)3.2.5General(Noreliefrequests)3.3Class3Components(Noreliefrequests)3.4PressureTests..................................................173.4.1Class1SystemPressureTests..................................173.4.1.1RequestforReliefP2(Part1of2),SystemHydrostaticTestofClass1PipingintheChemicalandVolumeControlSystem.........................173.4.1.2Request.forReliefP4,SystemHydrostaticTest'efClass1Pipinginthe'EmergencyCoreCoolingSy'tem........173.4.2Class2SystemPressureTests..................................193.4.2.1RequestforReliefPl,SystemHydrostaticTestofClass2PipingintheEmergencyCoreCoolingSystem........193.4.2.2RequestforReliefP2(Part2of2),SystemHydrostaticTestofClass2PipingintheChemicalandVolumeControlSystem.........................213.4.2.3RequestforReliefP3,SystemHydrostaticTestofClass2PipingintheChemicalandVolumeControlSyStelll~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3.4.2.4RequestforReliefP5,SystemHydrostaticTestofClass2PipingintheAuxiliarySpraytoReactorCoolantSystemandPressurizer,andChemicalandVolumeControlSystem........................3.4.3Class3SystemPressureTests(Noreliefrequests)".....21....23v
.4.4General...........................;............................2533.4.4.1RequestforReliefP2,SystemHydrostaticTestofClass1and2PipingintheChemicalandVolumeControlSystem.......................-.............3.5General(Noreliefrequests)'~~~~~~~~25~CONCLUSIONo~~~~i~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~t~~~~~~o2745REFERENCES........;....................................;..............28 TECHNICALEVALUATIONREPORTONTHESECOND10-YEARINTERVALINSERVICEINSPECTIONPROGRAMPLAN:INDIANAANDMICHIGANELECTRICCOMPANY,DONALDC.COOKNUCLEARPLANT,UNIT2,DOCKETNUMBER50-3161.INTRODUCTIONThroughouttheservicelifeofawater-coolednuclearpowerfacility,10CFR50.55a(g)(4)(Reference1)requiresthatcomponents(includingsupports)whichareclassifiedasAmericanSocietyofHechanicalEngineers(ASHE)BoilerandPressureVesselCodeClass1,Class2,andClass3meettherequirements,exceptthedesignandaccessprovisionsandthepreserviceexaminationrequirements,setforthintheASHECodeSectionXI,"Rulesfo'InserviceInspectionofNuclearPowerPlantComponents,"(Reference2)totheextentpracticalwithinthelimitationsofdesign,geometry,andmaterialsofconstructionofthecomponents.Thissectionoftheregulationsalsorequiresthatinserviceexaminationsofcomponentsandsystempressuretestsconductedduringthesecond120-monthinspectionintervalshallcomplywiththerequirementsin'thelatesteditionandaddendaoftheCodeincorporatedbyreferencein10CFR50.55a(b)onthedate12monthspriortothestartofthesecond120-monthinspectioninterval,subjecttothelimitationsandmodificationslistedtherein.Thecomponents(includingsupports)maymeetrequirementssetforthinsubsequenteditionsandaddendaofthisCodewhichareincorporatedbyre'ferencein10CFR50.55a(b)subjecttothelimitationsandmodificationslistedtherein.TheLicensee,IndianaandHichiganElectricCompany,haspreparedtheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalInserviceInspection(ISI)ProgramPlan,Change1(Reference3),tomeettherequirementsofthe1983Edition,Summer1983Addenda(83S83)oftheASMECodeSectionXIexceptthattheextentofexaminationforCodeClass1andCodeClass2pipingweldshasbeendeterminedbythe1974EditionthroughSummer1975Addenda.(74S75)aspermittedandrequiredby10CFR50.55a(b).Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.Asrequiredby10CFR50.55a(g)(5),ifthelicenseedeterminesthatcertainCodeexaminationrequirementsareimpracticalandrequestsrelieffromthem, If'\Et thelicenseeshallsubmitinformationandjustificationstotheNuclearRegulatoryCommission(NRC)tosupportthatdetermination.Pursuantto10CFR50.55a(g)(6),theNRCwillevaluatethelicensee'sdeterminationsunder10CFR50.55a(g)(5)thatCoderequirementsareimpractical.TheNRCmaygrantreliefandmayimposealternativerequirementsthataredeterminedtobeauthorizedbylaw,willnotendangerlifeorpropertyorthecommondefenseandsecurity,andareotherwiseinthepublicinterest,givingdueconsiderationtotheburdenuponthelicenseethatcouldresultiftherequirementswereimposedonthefacility.TheinformationintheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,wasreviewed,includingtherequestsforrelieffromtheASHECodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.ThereviewoftheISIProgramPlanwasperformedusingtheStandardReviewPlansofNUREG-0800(Reference4),Section5.2.4,"ReactorCoolantBoundaryInserviceInspectionsandTesting",andSection6.6,"InserviceInspectionofClass2and3Components."InaletterdatedFebruary2,1987(Reference5),theNRCrequestedadditionalinformationthatwasrequiredinordertocomplete,thereviewoftheISIProgramPlan.TherequestedinformationwasprovidedbytheLicenseeinsubmittalsdatedApril10,1987(Reference6)andJune1,1987(Reference7).TheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlanisevaluatedinSection2ofthisreport.TheISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addendaofSectionXI,(b)acceptabilityofexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNRC'spreviouspreserviceinspection(PSI)andISIreviews.TherequestsforreliefareevaluatedinSection3ofthisrport.Unlessotherwisestated,referencestotheCoderefertotheASMECode,SectionXI,1983EditionincludingAddendathroughSummer1983.Specificinservicetest(IST)programsforpumpsandvalvesarebeingevaluatedinotherreports.
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~~I'I2.EVALUATIONOFINSERVICEINSPECTIONPROGRAMPLANThisevaluationconsistedofareviewoftheapplicableprogramdocumentstodeterminewhetherornottheyareincompliancewiththeCoderequirementsandanylicenseconditionspertinenttoISIactivities.This'sectiondescribesthesubmittalsreviewedandtheresultsofthereview.2.1ocumentsEvaluatedReviewhasbeencompletedonthefollowinginformationprovidedbytheLicensee:(a)DonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985;(b)Letter,datedApril10,1987,Licensee'sresponsetotheNRC'sRAI;and(c)Letter,datedJune1,1987,informationtheLicenseecommittedtointheApril10,1987letter.2.2ComliancewithCodeReuirements2.2.1ComliancewithAlicableCodeEditionsTheInserviceInspectionProgramPlanshallbebasedontheCodeeditionsdefinedin10CFR50.55a(g)(4)and10CFR50.55a(b).BasedonthestartingdateofJuly1,1986,theCodeapplicabletothesecondintervalISIprogramisthe1980EditionwithAddendathroughMinter1981.AsstatedinSection1ofthisreport,theLicenseehaswrittentheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,throughChange1,tomeettherequirementsofthe1983Edition,Summer1983AddendaoftheCodeexceptthattheextentofexaminationforCodeClass1andCodeClass2pipingweldshasbeendeterminedbythe1974EditionthrouohSummer1975Addendaaspermittedandrequiredby10CFR50.55a(b).Theuseof8~S83wasapprovedbytheNRCinaletterdatedJanuary15,1986(Reference8).3 I'Ci'hA 2.2.2AccetabilitoftheExaminationSamleInservicevolumetric,surface,andvisualexaminationsshallbeperformedonASMECodeClass1,2,and3componentsandtheirsupportsusingsamplingschedulesdescribed.,inSectionXIoftheASMECodeand10CFR50.55a(b).SamplesizeandweldselectionhavebeenimplementedinaccordancewiththeCodeandappeartobecorrect.2.2.3ExclusionCriteriaThecriteriausedtoexcludecomponentsfromexamination-shallbeconsistentwithParagraphsIWB-1220,IWC-1220,IWC-1230,IWD-1220,and10CFR50.55a(b).TheexclusioncriteriahavebeenappliedbytheLicenseeinaccordancewiththeCodeasdiscussedintheISIProgramPlanandappeartobecorrect.2.2.4AumentedExaminationCommitmentsThefollowingaugmentedexaminationswill.beimplementedduringthesecond..10-yearinspectioninterval:(a)TheLicenseehascommittedtovolumetricallyexaminea7.5%sampleofweldsintheContainmentSpraySystem.(b)ExaminationsfortheReactorPressureVesselare,incompliancewithRegulatoryGuide1.150,"UltrasonicTestingofReactorVesselWeldsDuringPreserviceardInserviceExamination"(Reference9).(c)AugmentedexaminationsperRegulatoryGuide1.14,"ReactorCoolantPumpFlywheelIntegrity"(Reference10)..2.3ConclusionsBasedonthe'reviewofthedocumentslistedabove,itisconcludedthattheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,isacceptableandincompliancewith10CFR50.55a(g)(4).
3.EVALUATIONOFRELIEFREQUESTSTherequestsforrelieffromtheASHECoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthesecond10-yearinspectionintervalareevaluatedinthefollowingsections.3.1ClassComonents3.1.1ReactorPressureVessel3.1.1.1ReuestforReliefxaminationateor-AItemPressureRetaininCircumferentialHeadWeldsintheReactorPressureVesselCodeReuirement:SectionXI,TableIWB-2500-1,ExaminationCategory.'B-A,Ii'emB1.21requiresa100/volumetricexaminationofthelengthofonecircumferentialheadweldintheReactorPressureVessel(RPV)asdefinedbyFigureIWB-2500-3.Licensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredvolumetricexaminationofclosureheaddollarplateweld2-CHC-02andlowerheaddollarplateweld2-LHC-01oftheRPV.icensee'sProosedAlternativeExamination:TheLicenseestatesthat,in'lieuofthevolumetricexaminationrequirementsofSectionXI,thereactorvesselclosureandlowerheadswillreceiveareactorcoolantsystemleakagetestandVT-2visualexaminationeach10-yearinterval.TheseexaminationsareconductedpertherequirementsofASHESectionXI,CategoryB-P.Additionally',theaccessiblelengthofoneclosureheadmeridional.weld(whichintersectstheclosureheaddollarplateweld)isvolumetricallyexaminedpertherequirementsofASHESectionXI,CategoryB-A.BasedontheaboveandtheavailabilityoftheReactorCoolantSystemLeakageDetectionSystem,theLicenseestatesthattheoveralllevelofplant Esafetywillnotbereducedbytheproposedreliefrequest.icensee'sBasisforReuestinRelief:TheLicenseestatesthataccesslimitati'onsprevent,volumetricexaminationofeitherof.thesubjectwelds.Theclosureheaddollarplateweldhaslimitedaccessibilityforultrasonicexaminationduetoitslocationamongthereactorvesselcontrolroddrive(CRD)housings.UnliketheUnitIclosurehead(whichwasfabricatedbyadifferentmanufacturer),theaccessibleportionsoftheUnit2closureheaddollarplateweldarefurtherobstructedbyinterferencewiththeCRDshroud.Therefore,noareasofthisweldareaccessibleforvolumetricexaminationbyultrasonics,andtheCRDpenetrationsandshroudprecludefilmplacementforradiographicvolumetricexamination.Interferencewiththeinstrumentationtubesmakesthelowerheaddollarplateweldtotallyinaccessibleforexaminationwiththe'remoteinspectiondevice.~valuation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingswhichshowtheexaminationlimitationsandobstructions.DuetotheCRDshroudandtheclusterofCRDpenetrationsintheclosurehead,accesstotheclosureheadcircumferentialweldisnotpossible.Thevolumetricexaminationofthebottomheadcircumferentialweldisprecludedbytheadjacentinstrumentationtubes.Therefore,theCode-requiredvolumetricexaminationoftheseweldsisimpracticaltoperform.ThevisualexaminationforevidenceofleakageperformedduringsystemhydrostatictestswillprovidereasonableassuranceofthecontinuedinservicestructuralintegrityoftheRPVcircumferentialheadwelds.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCode-requiredvolumetricexaminationofthesubjectdollarplateweldsisimpractical.Compliancewiththe specificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.1.1.2ReuestforReliefxaminationCateorB-AternB1.40resureRetaininHead-to-FlaneWeldintheReactorPressureVesselgdi:iNI,Th1I.5>>-,E*CategoryB-A,ItemBl.40requiresa100%volumetricandsurfaceexaminationofthehead-to-flangeweldsoftheRPVasdefinedbyFigureIWB-2500-5.Licensee'sCodeReliefRevest:Reliefisrequestedfromexamining100%oftheCode-requiredvolumeofclosurehead-to-flangeweld2-CHC-01intheRPV.Licensee'sProosedAlternativeExamination:None.TheLicenseestatesthatthesubjectweldwillreceivea96%volumetricexaminationandthefull.Code-requiredsurfaceexamination.Licensee'sBasisforReuestinaRelief:TheLicenseestatesthatapproximately4%oftheweldcannotbeexaminedultrasonicallyduetophysicalinterferencewiththethreeclosureheadliftin9lugs.Evaluation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingwhichshowstheexaminationlimitations.Thevolumetricexaminationofthesubjectweld,totheextentrequiredbytheCode,isimpracticalbecauseofthelocationoftheclosureheadliftinglugswithrespecttotheweld.Asignificantpercentage(96%)oftheinservicevolumetricexamination,asrequiredbytheCode,willbeperformed.Failuretoperforma100%inserviceexaminationofthisweld7
~Q/7Ip1Al4 lI'willnotsignificantlyaffectassuranceofstructuralintegrity.Conclusions:Basedontheaboveevaluation,itisconcludedthatthefullSectionXIsurfaceexaminationandthelimitedSectionXIvolumetricexaminationofthesubjectweldensuresanacceptablel'evelofinservicestructuralintegrityandthatcompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincrease'inthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedas-requested.3.1.2.1ReuestforRelief3ExaminationCateorB-DItem83.110PressureRetaininNozzle-to-VesselWeldsinthePressurizer0CodeReuirement:SectionXI,TableIWB-2500-1,ExaminationCategoryB-O,ItemB3.110requiresa100%volumetricexaminationofallnozzle-to-vesselweldsinthepressurizerasdefinedbyFigureIWB-2500-7.icensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredvolumetricexaminationfromonthe'weldsurfaceandfromthenozzlesideoftheweld(14"surgenozzle-to-lowerheadweld2-RC-21).icensee'sProosedAlternativeExamination:TheLicensee,statesthat,inlieuoftherequirementsofSectionXI,theCode-requiredfull-veeultrasonicexaminationwillbeperformedfromthevesselsideonly,andasupplementalsurfaceexaminationwillbeperformed.Thispropo'sedalternativeexaminationwasusedinthefirst10-yearinterval.Ouringthesecond10-yearinterval,thepressurizerwill PrpCI' receiveareactorcoolantsystemleakagetestandVT-2visualexaminationeachrefuelingoutage,andareactorcoolantsystemhydrostatictestand'T-2visualexaminationonceduringtheinterval.TheseexaminationswillbeconductedpertherequirementsofASHESectionXI,ExaminationCategoryB-P.icensee'sBasisforRuestinRelief:TheLicenseestatesthatinterferencewiththenozzlebl.endradiuspreventscontactoftheultrasonicsearchunit.BasedontheaboveandtheavailabilityoftheReactorCoolantSystemLeakageDetectionSystem,theLicenseestatesthattheoveralllevelofplantsafetywillnotbereducedbyperformingtheproposedalternativeexamination.5~~Evaluation:TheLicensee'ssubmittalhasbeenreviewed,includingthesketchofthepressurizersurgenozzle.Becausethenozzleblendradiuspreventspropercontactofthetransduceronthenozzlesideoftheweldandontheweldcrown,thevolumetricexaminationofthesubjectweld,totheextentrequiredbytheCode,isimpractical.Atleast505oftheCode-requiredvolumeofthesubjectweldwillbeexamined.Conclusions:Basedontheaboveevaluation,itisconcludedthatthepartialSectionXIvolumetricexaminationandthesupplementalsurfaceexamination,alongwiththevisualexaminations,ensureanacceptablelevelofinservicestructuralintegrityandthatcompliancewiththespecificrequirementsofSectionXIwouldresultinhardship'runusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.1.3HeatExchanoersandSteamGenerators(Noreliefrequests)3.1.4PiincPressureBoundar(Noreliefrequests) 0I!"f 3.1.5PumPressureBoundar3.1.5.1ReuestforRelief4ExaminationCateorisB--1B--2and-G-ReactorCoolantPumCasinWeldPumCasinnternalSurfaceandPumFlaneSurfaceCodeReuirement:SectionXI,TableIWB-2500-1,ExaminationCategoryB-L-l,ItemB12.10requiresa100%volumetricexaminationofthepressureretainingpumpcasingweldsasdefinedbyFigureIWB-2500-16.SectionXI,TableIWB-2500-1,ExaminationCategoryB-L-2,ItemB12.20requiresa100%visual(VT-3)examinationoftheinternalsurfacesofClass1pumpcasings.SectionXI,TableIWB-2500-1,ExaminationCategoryB-G-1,ItemB6.190requiresa100%visual(VT-1)examinationoftheflangesurfacesofClass1pumpswhenconnectionisdisassembled.Examinationincludes1inchannularsurfaceofflangesurroundingeachstud.Licensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredvolumetricexaminationofpumpcasingweld1-RCPandfromperformingtheCode-requiredvisualexaminationsoftheinternalsurfacesofthepu..pcasingsandthesurfacesofthepumpflanges.icensee'sProo'dAlternativexamination:TheLicenseestatesthat,inlieuoftherequirementsofSectionXIforcategoriesB-L-1andB-L-2,avisualexamination(VT-2)willbeperformedontheexternalsurfacesofonepumpduringthehydrostaticpressuretests.Inaddition,asurfaceexaminationwillbeperformedonthispumpontheaccessibleexternalsurfaceoftheweld.Ifapumphastobedisassembledformairtenance,visualexaminationswillbemadeoftheinternal10 14surfaces(VT-3)andtheflangesurface(VT-1)tosatisfythe8-L-2andB-G-1Coderequirements.TheLicenseestatesthattheneedforthevolumetricexaminationaccordingtotheB-L-1requirementwillbereevaluatedatthattime.icensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubstantialradiationexposurethatinspectionpersonnelwillincurandthesubstantialcostsinvolveddonotjustifythepossibleinformationthatmightbe,gainedabouttheweldandadjacentbasemetal.ThepumpcasingismadefromASHESA-351,GradeCF-SN,acastausteniticstainlesssteelthathasalonghistoryofsatisfactoryserviceinhandlingfluids.Thecasingwasmadeintwosectionstofacilitatethecastingprocess,andthetwoJsections.arewe.'tdedtogetherwithamatchingfillermaterial.Thematerialhasgoodfracturetoughness,andunlikeferriticsteels,isnotsubjecttofracturepreventioncriteria.Volumetricandinternalcasingvisualexaminationwillrequirecompletedisassemblyofthepump.Disassemblyofthepump,storageoftheinternals,andplacementoffilmforthemanyradiographicexposuresthatwillberequired,willexposepersonneltosubstantialradiation.Fromexperienceatothernuclearplantsexaminingreactorcoolantpumps,personnelexposurecouldbeintherangebetween35to100man-rem.Flushingorshieldingwouldnotbeexpectedtosignificantlyreduceradiationlevels.Basedoncostsincurredbyothernuclearplants,thispumpexaminationisestimatedtocostabout5500,000,whichdoesnotincludecostsassociatedwithunitunavailabilityshouldthisexaminationrequireextendinganoutage.TheCode-".equiredexaminationwillrequiredisassemblyo,apumpunderadverseconditionswherethereisapossibilityofcausingdamagetothepumpinternals.Thereisnootlerreasontodisassembleanyofthesepumpsotherthantoperformthese11 pIIJ examinations.Thisexaminationwillalsorequirehandlingthereactorvesselupperinternalassemblyanadditionaltime,astheupperinternalswillhavetobeputbackintothereactorvesseltominimizeairborneradiationduringthepumpexamination.Basedontheforegoing,andthefactthatCodereliefwasgrantedfortheD.C.Cookreactorcoolantpumpsforthefirstinterval;aswassimilarlygrantedforreactor.'oolantpumpsinothernuclearplants,theLicenseebelievesthattheradiationexposureandcostsforthisexaminationdonotjustifyperformingthevolumetricandvisualexaminationstomeettherequirementsofCategoriesB-L-I,B-L-2,and.B-G-I.Evaluation:Thevisualexaminationistodeterminewhetherunanticipatedseveredegradationofthecasingisoccurringduetophenomenasuchaserosion,corrosion,orcracking.However,previousexperienceduringexaminationofpumpsatotherplantshasnotshownanysignificantdegradationofpumpcasings.Theconceptofvisualexaminationifthepumpisdisassembledformaintenanceisacceptable.Ifthepumpisdisassembledformaintenance,theCode-requiredvolumetricexaminationofthepumpcasingweldshouldalsobeperformed.Thedisassemblyofthepumpssolelyforthepurposeofinspectionisamajoreffortand,inadditiontothepossibilityofadditionalwearordamagetotheinternalsurfacesofthepumps,couldresultinlargeamountsofradiationexposuretopersonnel.However,ifoneof,thepumpsisdisassembledformaintenance,thecasingweld,internalsurfaces,andflangesurfacewouldbeexamined,inwhichcasereliefwouldnotberequiredforthatparticularpump.~Conclusions:Basedon,theaboveevaluation,itisconcludedthatcompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthat:(a)TheLicensee'sproposal12 IC'Eg toperformthevisualexaminationoftheinternalsurfaces(VT-3)andtheflangesurface(VT-1)ofthepumps,whenevertheyaremadeaccessibleduetodisassemblyformaintenance,shouldbeaccepted,providedthattheCode-requiredvolumetricexaminationofthepumpcasingweldisalsoperformed;and(b)Reliefshouldbegrantedattheendoftheintervalifoneofthesubjectpumps,forwhichthevisualandvolumetricexaminationsarerequired,hasnotbeendisassembledformaintenance.'.1.6ValvePressureBoundar(Noreliefrequests)3.1.7General(Noreliefrequests),3.2Class2Comonents3.2.1PressureVessels(Noreliefrequests)3.2.2~Piin3.2.2.1ReuestforRelief5ExaminationCateaorC-FItemC5.21Class2Pie-to-FluedHeadMeldsCodeReuirement:SectionXI,TableIWC-2500-1,ExaminationCategoryC-F,ItemC5.21requiresa100%surfaceandvolumetricexaminationofthepressureretainingcircumferentialweldsinClass2piping,greaterthanI/2inchnominalwallthickness,asdefinedbyFigureIMC-2500-7.icensee'sCodeReliefReues:ReliefisrequestedfromperformingtheCode-requiredsurfaceandvolumetricexaminationofpipe-to-fluedheadweld16SintheFeedwaterSystemandfluedhead-to-pipeweld13FintheHainSteamSystem.Licensee'sProposedAlternativeExamination:TheLicensee,.statesthat,inlieuoftherequirementsofSectionXI,the,13 firstaccessibleweldoutsideeachpenetrationwillbeexaminedwiththeCode-requiredsurfaceandvolumetricexaminations.Thisproposedalternativeexaminationwasusedinthefirst10-yearinterval.icensee'sBasisforRevestiRelief:TheLicenseestatesthatthesubjectweldsaretotallyenclosedwithinapenetrationsleeve,andareinaccessibleforexamination.Sincetheinaccessiblepipe-to-fluedheadweldthicknessissubstantiallyheavierthantheproposedalternativeweldtobeexaminedandtheyareexposedtothesameenvironment,theoveralllevelofplantsafetywillnotbereducedbyperformingthealternativeexamination.Evaluation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingwhichshowstheexaminationobstructions.TheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldsareimpracticalbecausetheseweldsarelocatedin'sidecontainmentpenetrationsandarecompletelyinaccessible.BecausethefirstaccessibleweldoutsideeachpenetrationwillreceivetheCode-requiredsurfaceandvolumetricexaminations,samplesizeismaintained.Thesubjectweldscanonlybeexaminedbyinspectingforevidenceofleakageduringsystemhydrostatictests.Althoughthesecontainmentpenetrationweldscannotbevieweddirectly,theLicenseeshouldconductvisualexaminationsforevidenceofleakageinthevicinityoftheseweldswhenthehydrostaticpressuretestsareperformed.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldsareimpracticalandthatthe.proposedalternativeexaminationensuresanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelof14
'l~lflo qualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequestedprovidedthatvisualexaminationsareperformedonthetwocontainmentpenetrationassemblieswhenleakageandhydrostatictestsareconductedinaccordancewithIWA-5000.3.2.2.2RevestforRelief6xaminationCateorC-F.ItemC5.Class2Pie-to-FluedHeadWeldsCodeReuirement:SectionXI,TableIWC-2500-1,ExaminationCategoryC-F,ItemC5.21requiresa100%surfaceandvolumetricexaminationofthepressureretainingcircumferentialweldsinClass2piping,greaterthanI/2inchnominalwallthickness,asdefinedbyFigureIWC-2500-7.icensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredsurfaceandvolumetricexaminationsofpipe-to-fluedheadweld11FintheHainSteamSystem.icensee'sProosedAlternativeExamination:TheLicenseestatesthat,inlieuoftherequirementsofSectionXI,oneadjacentweldinonemainsteamlinewillbeexaminedwiththeCode-requiredsurfaceandvolumetricexaminations.Thisproposedalternativeexaminationwasusedinthefirst10-yearinterval.icensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubjectweldisinaccessibleduetothelargepipewhiprestraintwhichsurroundstheweldandadjacentarea.Volumetricexaminationbyultrasonicsisimpracticalbecausetheweldcannotbereachedforpositioningandhandlingthetransducer,andradiographyisimpracticalbecausetheexposurewouldhavetobemadethroughtherestraint.Surfaceexaminationisimpracticalbecausetheweldisnotreadilyaccessibleforapplicationandremovalofpenetrantor manipulationofmagneticparticleequipment.Removalofthepipewhiprestraintswouldrequiretorchcutting2400and2700-lbsectionsthataresupportedfromabove.Theservicecondi.tionstowhichanadjacentweldisexposedshouldbenearlyidenticaltothatoftheinaccessibleweld,andthustheoveralllevelofplantsafetywillnotbereducedbyperformingtheproposedalternativeexamination.evaluation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingwhichshowstheexaminationobstructions.TheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldareimpracticalbecausethisweld(andadjacentarea)issurroundedbyalargewhiprestraintandiscompletelyinaccessible.BecauseanadjacentweldwillreceivetheCode-requiredsurfaceandvolumetricexaminations,samplesizeismaintained.Thesubjectweldcanbeexaminedonlybyinspectingforevidenceofleakageduringsystemhydrostatictests.Althoughthiscontainmentpenetrationweldcannotbevieweddirectly,theLicenseecouldconductvisualexaminationsforevidenceofleakageinthevicinityofthisweldwhenthehydrostaticpressuretestsareperformed.Conclusions;Basedontheaboveevaluation,itisconcludedthattheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldareimpracticalandthattheproposedalternativeexaminationensuresanacceptablelevelofinservicestructuralintegrity.Compliancewiththespecificrequirementsof'SectionXIwouldresultinhardshiporunusual,difficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequestedprovidedthatvisualexaminationsforevidenceofleakageareperformedinthevicinityofthecoveredweldwhentheCode-requiredleakageandhydrostatictestsareconducted.]6 3.2.3~Pums(Noreliefrequests)3.2'Valves(Noreliefrequests)3.2.5General(Noreliefrequests)3.3Class3Comonents(Noreliefrequests)3.4PressureTests3.4.1ClassSstemPressureTests3.4.1.1ReuestforReliefP2Part1of2SstemHdrostaticTestofClass1PiinintheChemicalandVolumeControlSstemNOTE:SeetheevaluationofthisrequestforreliefinSection3.4.4.1.3.4.1.2ReuestforReliefP4SstemHdrostaticTestofClass1PiinintheEmerencCoreCoolinSstemCodeReuirement:SectionXI,ArticleIWB-5000requiresthat,foranoperatingpressureof2235psig,theClass1pipingbetestedatapressureof2458psig.icensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClass1pipingsectionsintheEmergencyCoreCoolingSystemattherequiredtestpressureof2458psig:ValvesIH0-51,ValvesIH0-52,ValvesIH0-53,ValvesIH0-54,SI-142L1-BoronInjectionSI-142L2-BoronInjectionSI-142L3-BoronInjectionSI-142L4-BoronInjectionLoopNo.1LoopNo.2LoopNo.3LoopNo.417 4glII.
icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.ThetestwillbeperformedduringNode3withtheRCSpressureat2280psigandtemperaturegreaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockcheckvalvesSI-142LIthroughL4closed;therefore,maximumpressurewillbe2280psig.icensee'sasisforReuetinR1f:TheLicenseestatesthatthesectionsofthepipingsystemupstreamofcheckvalvesSI-142LIthroughL4cannotbetestedatapressureof2458psigwithoutmakingtemporarymodifications(blockingthevalvedisc)tokeepthecheckvalvesclosed.Sincethepipingsectionsarepartoftheprimarysystem,plantpersonnelwillbesubjectedtosubstantialradiationexposureandc'ontaminationinordertocarryoutsuchmodificationsforthetest.Theproposedtestpressureishigherthanthe2235psignominaloperatingpressureinthesubjectsectionsofpiping,eachapproximately44to55feetlong.Evaluation:Becausethesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithoutextensivetemporaryvalvemodifications,theCodetestpressurerequirementisimpractical.Thevisualinspectionofthepiping-duringthepressuretestaswellasthevolumetricexaminationrequirementsforselectedweldsinthesystemwillprovideadequateassuranceofthecontinuedstructuralintegrityofthepiping.ThedifferenceintherequiredtestpressureandthatproposedbytheLicenseedoesnotwarrantimpositionoftheCoderequirement.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNOErequirements,willensureanacceptablelevelofinservicestructuralintegrity.Compliancewiththespecific18
'lIr requirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3;4.2ClassSstemPressureTests3.4.2.1ReuestforReliefPlSstemHdrostaticTetofClass2PiinintheEmerencCoreColinSternCodeReuirement:SectionXI,ArticleIWC-5000requiresthat,forasystemdesignpressureof2485psig,theClass2pipingbetestedatapressureof2733psig.Licensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClass2pipingsectionsintheEmergencyCoreCoolingSystemattherequiredtestpressureof2733psig:(a)AccumulatorNo.1DischargePiping-ValvesIM0-110,SI-166-1,IRV-155,andSI-168-1;(b)AccumulatorNo.2DischargePiping-ValvesIM0-120,SI-166-2,IRV-165,andSI-168-2;(c)AccumulatorNo.3DischargePiping-ValvesIM0-130,SI-166-3,IRV-175,andSI-168-3;and(d)AccumulatorNo.4DischargePiping-ValvesIH0-140,SI-166-4,IRV-185,andSI-168-4.icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.ThetestwillbeperformedduringMode3withtheRCSpressureat2280psigandtemperaturegreater'hanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalves(SI-166-1,-2,-3,and-4)closed,therefore,limitingmaximumpressureto2280psig.19 FFFFFC~D icensee'sBasisforReuestinRelief:TheLicenseestatesthatthesectionofpipingupstreamofcheckvalvesSI-166-1through4cannotbetestedatapressureof2733psigwithoutmakingextensivetemporarymodificationstokeepthevalves.closed.Themodificationswouldrequire:(a)disassemblyofthevalves,(b)weldingoftemporaryblocks(onthedownstreamside)insidethevalvebodiestoholda"jackscrew"typearrangementtokeepthevalveclosed,(c)removalofthetemporaryblockingdevicesfromthevalvesaftertesting,and(d)performingnecessarynondestructivetestingtoensuretheintegrityofthevalvebodiesbeforereturningthemteservice.Thepipingdownstreamofth'esevalvesispart'ofth'RHRSystemandcarriesradioactivefluidduringnormaloperation.Therefore,plantpersonnelwillbesubjectedtosubstantialradiationexposureandradioactivecontaminationinordertocarryoutanymodificationsforthetest.Evaluation:Thesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithouteitherextensivetemporaryvalvemodificationsoroverpressurizingtheClassIsectionsofconnectedpiping.Becauseofthis,thetestpressurerequirementisimpracticaltoattain.ThesectionsofpipingwillbesubjectedtoapressureslightlyhigherthannormaloperatingpressureandatatemperaturehigherthanthatrequiredbytheCode.Thevisualinspectionofthepipingduringthepressuretestaswellasthevolumetricexaminationrequirementsforselectedweldsinthesystemwillprovideadequateassuranceof-thecontinuedstructuralintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticaland'thatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelofinservicestructuralintegrity.Compliancewiththespecific20 CI'pt4i requirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.2.2RevestforReliefP2Par2fSstemHdrostaticTestofClassPiinintheChemicalandVolumeControlSstemNOTE:Seetheevaluationofthisrequestforreliefin'ection3.4.4.1.3.4.2.3ReuestforReliefP3SstemHdrostaticTestofClass2PiinintheChemicalandVolumeControlSstemCodeReuirement:SectionXI,ArticleIWC-5000requiresthat,foradesignpressureof2485psig,theClass2pipingbehydrostaticallypressuretestedatapressureof3106psig.Licensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredhydrostaticpressuretestoftheLetdownLines(ValvesQRV-112,QRV-160,QRV-161,andQRV-162)intheChemicalandVolumeControlSystem(ReactorLetdownandCharging)attherequiredtestpressureof3106psig.icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionofpipingwillbetestedatapressureof2280psigduringHode3usingRCSpressure.Valve'sQRV-111andQRV-112willbeopenedwithQRV-160,QRV-161,andQRV-162closed.Licensee'sBasisforReouestinaRelief:TheLicenseestatesthatthesubjectsectionofpipingcannotbetestedatapressureof,3106psigwithout(a)usingaspareone-inchpluggedconnectioninUnit1pipinglocateddownstreamofinstrumentQTA-160intheregenerativeheatexchangerroom,21 whichisconsideredahighradiationarea,and(b)modification,sincenotestconnectionexistsinUnit2piping.Thispipingcarriesradioactivefluidduringnormaloperation;therefore,plantpersonnelwillbesubjecttosubstantialradiationexposureandcontaminationinordertomodify/addatestconnection.Asanalternative,extendingthetestboundarytogCR-301wasconsidered.ThiswouldinvolveusinggPX-301locatedonthedownstreampipingoutsidetheregenerativeheatexchangerroomasatestconnection.ThisalternativewasalsorejectedbecausevalvegCR-301andtheflangeboltedtotheinletflangeofsafetyvalveSV-051areinthe600-lbclasswhichcannotwithstandtheabovetestpressure.evaluation:Thesystem'sdesigndidnotincludeatestconnectiontoallowpressurizingtotheCodetestpressureorpipingandvalvesratedappropriatelytoaccommodatetherequiredpressureatotherisolationpointsinthesystem.InordertocomplywiththeCoderequirement,theLicenseewouldhavetoinstallatestconnectionoroverpressurizelowerratedpipingandcomponents.Therefore,theCoderequirementisimpractical.TheLicensee'sproposedalternativetestwillsubjectthepipingtoapressureslightlyhigherthannormaloperatingpressure.TherequiredvisualinspectionofthepipingatthetestpressureandotherrequiredNDEoftheweldsinthesystemwillprovideadequateassuranceofthecontinued'structuralintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNOErequirements,willensureanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.22 Ot1"I'yfRe 3.4.2..4RevestforReliefP5SstemHdrostaticTestofClass2iininthAuxiliarratatorCoolantSsemandressurizerandChe'micalandVolumeControlSstem~di":ItlIl,ttl1III.A>>foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.icensee'sCodeRelief'ue:ReliefisrequestedfromperformingtheCode-requiredhydrostaticpressuretestoftheClass2pipingsectionsdescribedbythefollowingpipingboundariesattherequiredtestpressureof3419psig:ValvesQRV-51CS-326ValvesQRV-61CS-322ValvesQRV-62icensee'sProosedAlternativexamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2800psigusinga"stemblock"tokeepvalveQRV-51closed.icensee'sBasisforReuestinRelief:TheLicenseestatesthat,inordertoperformthepressuretestofthesesectionsofpiping,valveQRV-51hastobeusedasanisolationvalve.Thisl500-lbclass,air-operatedcontrolvalveisdesignedtowithstandtestpressureof3419psigintheopenposition.However,itcannotbeusedasanisolationvalvebecauseitwasdesignedforadifferentialpressureofl200psig.Thevalvecannotbekeptclosedduringpressuretestingat3419psigwithoutextensive,temporaryrigging.Themodificationwouldrequire:(a)removaloftheairoperatorandinstallationofa"strongback"tokeepthevalveclosedduringtesting,(b)removalofthe"strongback"afterthetesting,and(c)reinstallationoftheairoperatoronthevalveandrestoringthevalvetooperableconditionbeforereturningtoservice.Thevalveislocatedinsidethe23 l'r't regenerativeheatexchangerroom,whichisaveryhighradiationareaandplantpersonnelwouldbesubjectedtoradiationexposureoffivetosevenman-rems.Asanalternative,thepossibilityofusingafreezesealplugdownstreamofHARV-51wasconsidered.Thiswouldinvolveextensiveworkingtimeclosetothepressurizersprayvalves,whichareinahighradiationarea.Thisalternativewasrejected.becauseplantpersonnelwouldbesubjecttoanevenhigherradiationexposureofBa5man-remsduringformation,monitoring,andremovalofthefreezesealplug.~va1oation:TheabovepipingsystemcannotbetestedtoASHECoderequirementswithoutmodifyingthesystemand/orexposingpersonneltolargeamountsofradiation.Theproposedtestpressureishigherthanthenormaloperatingpressureof2235psigintheapproximately30-foot-longsectionofpipingforwhichCodereliefisrequested.Theproposedtestpressureis25%abovethenormaloperatingpressure.Thus,thetestprovidesreasonableassuranceoftheintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.3Class3SstemPressureTests(Noreliefrequests)24 p'
3.4.4General3.4.4.1RevestforReliefP2SstemHdrostaticTestofClass1and2PiininthehemicalandVolumontr1SstemCodeReuirement:SectionXI,ArticleIWB-5000requiresthat,foranoperatingpressureof2235psig,theClassIpipingbetestedatapressureof2458psig.SectionXI,ArticleIWC-5000requiresthat,foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.Licensee'sCodeReliefReues:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClassIand2pipingsectionsintheChemicalandVolumeControlSystem(ReactorLetdownandCharging)attheCode-requiredtestpressuresof2458and3419psig:'a)ClassIpiping:Two-inchAuxiliarySprayPiping-ValvesHARV-5landCS-325;(b)Class2piping:NormalChargingLoop4ColdLeg-ValvesgRV-62,CS-328L4,CS-326,andCS-327;(c)Class2piping:AlternateChargingLinetoLoopIColdLeg-ValvesHARV-61andCS-328Ll.Licensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psigatatemperatureabove100'F.ThetestwillbeperformedduringMode3withtheReactorCoolantSystem(RCS)pressure.at2280psigandtemperaturegreaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalvesCS-329Ll,CS-329L4,andCS-325closed;therefore,maximumpressurewillbe2280psig.25 M.y icensee'sBasisforReuestinRelief:TheLicenseestatesthatcheckvalvesCS-328L1,CS-328L4,andCS-325arelocatedonthecharginglinestotheRCSSystem.Thesevalvesmustbedisassembledandtemporarilymodifiedtoblockthemclosedinordertoperformtherequiredhydrostatictests,andplantpersonnelwillbeexposedtohighradiationandradioactivecontaminationduringthemodification.Theproposedtestpressureishigherthan2235psignominaloperatingpressureinthesectionofpipingbetween23and115feetlongforwhichreliefisrequested./valuation:Thesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithouteitherextensivetemporaryvalvemodificationsoroverpressurizingtheClass1sectionsofconnectedpiping.Becauseofthis,theCode-requiredtestpressureisimpracticaltoattain.ThesectionsofpipingwillbesubjectedtoapressureslightlyhigherthannormaloperatingpressureandatatemperaturehigherthanthatrequiredbytheCode.Thevisualinspectionofthepipingduringthepressuretest,aswellasthevolumetricexaminationrequirementsforselectedweldsinthesystems,willprovideadequateassuranceofthecontinuedstructuralintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.5Genera1(Noreliefrequests)26 C'p) 4.CONCLUSIONPursuantto10CFR50.55a(g)(6),ithasbeendeterminedthatcertainSectionXIrequiredinserviceexaminationsareimpracticaltoperform.Inthesecases,theLicenseehasdemonstratedthateitherthe'proposedalternativeswouldprovideanacceptablelevelofqualityandsafetyorthatcompliancewiththerequirementswouldresultinhardshipsorunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.ThistechnicalevaluationreporthasnotidentifiedanypracticalmethodbywhichtheexistingDonaldC.CookNuclearPlant,Unit2,canmeetallthe.specificinserviceinspectionrequirementsofSectionXIoftheASIDECode.RequiringcompliancewithalltheexactSectionXIrequiredinspectionswouldrequireredesignofasignificantnumberofpl.antsystems,sufficientreplacementcomponentstobeobtained,installationofthenewcomponents,andabaselineexaminationoftheseromponents.Evenaftertheredesignefforts,completecompliancewiththeSectionXIexaminationrequirementsprobablycouldnotbeachieved.Therefore,itisconcludedthatthepublicinterestisnotservedbyimposingcertainprovisionsofSectionXIoftheASIDECodethathavebeendeterminedtobeimpractical.Pursuantto10CFR50.55a(g)(6),reliefisallowedfromtheserequirementswhichareimpracticaltoimplement.Thedevelopmentofneworimprovedexaminationtechniqueswillcontinuetobemonitored.Asimprovementsintheseareasareachieved,theNRCmayrequirethatthesetechniquesbeincorporatedinthenextinspectionintervalISIprogramplanexaminationrequirements.BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalInserviceInspectionProgramPlan,Change1,datedDecember1985,theLicensee'sresponsestotheNRC'sRequestforAdditionalInformation,andtherecommendationsforgrantingrelieffromtheISIexaminationrequirementsthathavebeendeterminedtobeimpractical,ithasbeenconcludedthattheDonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalInserviceInspectionProgramPlan,Change1,datedDecember1985,isacceptableandincompliancewith10CFR50.55a(o)(4).27
'40 5.REFERENCES1.CodeofFederalRegulations,Volume10,Part50.2.AmericanSocietyofMechanicalEngineersBoilerandPressureVesselCode,SectionXI,Division1:1983EditionthroughSummer1983Addenda1974EditionthroughSummer1975Addenda3.DonaldC.CookNuclearPlant,Unit2,Second10-YearIntervalInserviceInspectionProgramPlan,Change1,datedDecember1985.4.NUREG-0800,StandardReviewPlans,Section5.2.4,"ReactorCoolantBoundaryInserviceInspectionandTesting,"andSection6.6,"InserviceInspectionofClass2and3Components,"July1981.5.Letter,February2,1987,B.J.Youngblood(NRC)toJ.E.Dolan[IndianaandMichiganElectricCompany(IMEC)],"RequestforAdditionalInformationforReviewoftheDonaldC.CookNuclearPlant,Units1and2,Second10-YearIntervalInserviceInspectionProgramPlans,Change1,datedDecember1985."6.Letter,April10,1987,M.P.Alexich(IHEC)toH.R.Denton(NRC),"ResponsetoRequestforAdditionalInformationontheISISecond10-YearIntervalWeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."7.Letter,June1,1987,H.P.Alexich'(IHEC)toT.E.Murley(NRC),"ResponsetoRequestforAdditionalInformationontheISISecord10-YearIntervalWeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."8..Letter,January15,1986,B;J.Youngblood(NRC)toJ.E.Dolan(IMEC),"NRCApprovalforIndianaandMichiganElectricCompanytoUseASHECodeSectionXI,1983EditionwithSummer1983AddendafortheISI/ISTProgramfortheDonaldC.CookNuclearPlant,Units1and2."28
'a~
9.RegulatoryGuide1.150,"UltrasonicTestingofReactorVesselWeldsDuringPreserviceandInserviceExaminations,"Revision1,datedFebruary1983.10.RegulatoryGuide1.14,"ReactorCoolantPumpFlywheelIntegrity,"Revision1,datedAugust1975.29 gt RRCfQRM~IK54IRRCMIIQT,STOI.544$uxRUCLuaRKOULATQRVCQMMISSIOIIBIBUOGRAPHICDATASHEETIRKAORTVUMKKRIAf>>RMAAfTIDC.AAAVAIIVA.HAATIEGG-SD-77985!tIVSTRUCTIOVSQVT>>tRKVKR5tT.TITLK*VDSslKTITLKTechnicalEvaluationReportontheSecond10-YearIntervalInserviceInspectionProgramPlan:IndianaandMichiganElectricCo.,DonaldC.CookNuclearPlant,Unit2,DocketNumber50-316AUT>>OR1$1$.LtAVKKLAIIIITEARMORI>>1988July~QATKRKAORTISSUKD~OATSRKTQATCOMALKTKOB.W.Brown,J.D.MudlinT4KR1ORMIVOOROAVIZATIOVIIAMKAVOMAILIIIOAODR$55IIAf~CQCAfflEGEGIdaho,Inc.P.0.Box1625IdahoFalls,ID83415-2209MOIIT>>July4MOIKCT/TASICVTORAUIIITIIUMKKR~fIIIQROIIAM'IRUMKKRVKAR1988IO5fOhSORIVOORCAVIS*TIOVIMAM5AIIOMAILINGAQDR$55Il>>IMAfLeCAAIIMaterialsEngineeringBranchOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555IT5UffLKMKVTARVVOTKSFIN-D6022(Project5)11~,TrftOfRKPORTTechnical4,RKRIODCOVKRKDII>>f>>>>>>fffai1$AKSTRACTQ&>>>>W>>f>>fThisreportpresentstheresultsoftheevaluationoftheDonaldC.CookNuclearPl'ant,Unit2,Second10-YearIntervalInserviceInspection(ISI)ProgramPlan,Change1,datedDecember1985,includingtherequestsforrelieffromtheAmericanSocietyofMechanicalEngineers(ASME)BoilerandPressureVesselCodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.InSection2ofthisreport,theISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addenda.ofSectionXI,.(b)acceptabilityoftheexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNuclearRegulatoryCommission's(NRC)previouspreserviceinspection(PSI)andISIreviews.TherequestsforrelieffromtheASMECoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthefirst10-yearinspectionintervalareevaluatedinSection3ofthisreport.I~QCI'MtvrA>>AL>515~AKTIIOROSIDKSCRfTOA54IQKVTifltASiCAKV.KVQKCTKRM51$AVAILA~<L,T>STATKMKIITUnlimited'14SKC"Al~vCLA5$lfICATIQIIUncfassifiedIffv>>AA>>iUnclassified11>>UMKKAC>>AOKS1~~RICK PIJ~ti>4