ML17328A871
| ML17328A871 | |
| 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-7799, NUDOCS 9102010172 | |
| Download: ML17328A871 (49) | |
Text
ATTACHMENT1EGG-SD-7799TECHNICALEVALUATIONREPORTONTHESECOND10-YEARINTERVALINSERVICEINSPECTIONPROGRAMPLAN:INDIANAANDMICHIGANELECTRICCOMPANY,DONALDC.COOKNUCLEARPLANT,UNIT1,DOCKETNUMBER50-315B.W.BrownJ.D.MudlinPublishedJuly1988IdahoNationalEngineeringLaboratoryEG&GIdaho,Inc.IdahoFalls,Idaho83415Preparedfor:U.S.NuclearRegulatoryCommissionWashington,D.C.20555underDOEContractNo.DE-AC07-76ID01570gFINNo.06022(Project5)9102010172910124PDRADOCK05000315PPDR ABSTRACTThisreportpresentstheresultsoftheevaluationoftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInserviceInspection(ISI),ProgramPlan,Change1,datedDecember1985,includingtherequestsforrelieffromtheAmericanSocietyofMechanicalEngineers(ASHE)BoilerandPressureVesselCodeSectionXIrequirementswhichtheLicenseehas'determinedtobeimpractical.TheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlanisevaluatedinSection2ofthisreport.TheISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addendaofSectionXI,(b)acceptabilityofexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNuclearRegulatoryCommission's(NRC)previouspreserviceinspection(PSI)andISIreviews.The.requestsfor-relieffromtheASHECoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthesecond10-yearinspectionintervalareevaluatedinSection3ofthisreport.Thisworkwas,fundedunder:U.S,NuclearRegulatoryCommissionFINNo.D6022,Project5OperatingReactorLicensingIssuesProgram,ReviewofISIforASHECodeClass1,2,and3Components11 SUHHARYTheLicensee,IndianaandHichiganElectricCompany,haspreparedtheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInserviceInspection(ISI)ProgramPlanto.meettherequirementsofthe1983Edition,Summer1983Addenda(83S83)oftheASHECodeSectionXIexceptthattheextentofexaminationforCodeClass1andCodeClass2pipingweldshasbeendeterminedbythe1974EditionthroughSummer1975Addenda(74S75)aspermittedandrequiredby10CFR50.55a(b).Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.TheinformationintheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,Change1,datedDecember1985,wasreviewed,includingtherequestsforrelieffromtheASHECodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.Asaresultofthisreview,aRequestforAdditionalInformation(RAI)wasprepareddescribingtheinformationand/orclarificationrequiredfromtheLicenseeinordertocompletethereview.BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,theLicensee'sresponsetotheNRC'sRAI,andtherecommendationsforthegrantingofrelieffromtheISIexaminationrequirementsthathavebeendeterminedtobeimpractical,ithasbeenconcludedthattheDonaldC.CookNuclearPlant,Unit1,Second10-Year'ntervalISIProgramPlan,Change1,datedDecember1985,isacceptableandincompliancewith10CFR50.55a(g)(4).
I1I CONTENTSABSTRACT~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o1iSUHMARY.................................................................i>iINTRODUCTION...........................................................112.EVALUATIONOFINSERVICEINSPECTIONPROGRANPLAN........................32.1DocumentsEvaluated..................................;..............32.2CompliancewithCodeRequirements.........................:......32.2.1CompliancewithApplicableCodeEditions........................32.2.2AcceptabilityoftheExaminationSample..............:..........42P'2.3ExclusionCrsteria..............................................42.2.4AugmentedExaminationCommitments.......;......................42.3Conclusions.........................................................403.EVALUATIONOFRELIEFREQUESTS.......................................53.1Class1Components...............................................53.1.1ReactorPressureVessel(Noreliefrequests)3.1.2Pressurizer(Noreliefrequests)3.1.3HeatExchangersandSteamGenerators(Noreliefrequests)3.1.4PipingPressureBoundary(Noreliefrequests)3.1.5PumpPressureBoundary.....................................53.1.5.1RequestforRelief1,ExaminationCategoriesB-L-1,B-.L-2,andB-G-1,ReactorCoolantPumpCasingWeld,PumpCasingInternalSurface,andPumpFlangeSurface.....~..53.1.6ValvePressureBoundary(Noreliefrequests)3,1.7General(Noreliefrequests)3.2Class2Components.................................................~93.2.1PressureVessels(Noreliefrequests)3A.i.2P>p>ng........................................9~~~~~~~~~~~~~~~93.2.2.1RequestforRelief2,ExaminationCategoryC-ItemC5.21,Class2Pipe-to-FluedHeadWelds.iv I'IIthA3 3.2.2.2RequestforRelief3,ExaminationCategoryC-F,ItemC5.21,Class2Pipe-to-FluedHeadWelds...............103.2.3'umps(Noreliefrequests)3.2.4Valves(Noreliefrequests)3.2.5General(Noreliefrequests)3.3Class3Components(Noreliefrequests).4PressureTests.....................................................1233.4.1Class1SystemPressureTests..................................123.4.1.1RequestforReliefP2(Part1of2),System.HydrostaticTestofClass1PipingintheChemicalandVolumeControlSystem..................................123.4.1.2RequestforReliefP4,SystemHydrostaticTestofClass1PipingintheEmergencyCoreCoolingSystem........133.4.2Class2SystemPressureTests..................-...............143.4.2.1RequestforReliefPl,SystemHydrostaticTestofClass2PipingintheEmergencyCoreCoolingSystem........143.4.2.2RequestforReliefP2(Part2of2),SystemHydrostaticTest.ofClass2PipingintheChemicalandVolumeControlSystem...........................3.4.2.3RequestforReliefP3,SystemHydrostaticTestofClass2PipingintheChemicalandVolumeControl~~~~16ystem.....................................................16S3.4:2.4RequestforReliefP5,SystemHydrostaticTestofClass2PipingintheAuxiliarySpraytoReactorCoolantSystemandPressurizer,andChemicalandVolumeControlSystem..........3.4.3Class3SystemPressureTests(Noreliefrequests)3.4.4General.....~~~~~~~~~~~~~~~~18.203.4.4.1RequestforReliefP2,SystemHydrostaticTestofClass1and2Pipingin,theChemicalandVolumeControlSystem,;.......................................203.5General(Noreliefrequests)~CONCLUSIONo~~'t~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~2345oREFRENCcSo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ii~~~i24I E'III<~1 TECHNICALEVALUATIONREPORTONTHE'SECOND10-YEARINTERVALINSERVICEINSPECTIONPROGRAHPLAN:INDIANAANDHICHIGANELECTRICCOHPANY,DONALDC.COOKNUCLEARPLANT,UNIT1,DOCKETNUHBER50-3151.INTRODUCTIONThroughouttheservicelifeofawater-coolednuclearpowerfacility,10CFR50.55a(g)(4)(Reference1)requiresthatcomponents(includingsupports)whichareclassifiedasAmericanSocietyofHechanicalEngineers,(ASHE)BoilerandPressureVesselCodeClass1,Class2,andClass3meettherequirements,exceptthedesignandaccessprovisionsandthepreserviceexaminationrequirements,setforthintheASHECodeSectionXI,"RulesforInserviceInspectionofNuclearPowerPlantComponents,"(Reference2)totheextentpracticalwithinthelimitationsofdesign,geometry,andmaterialsofconstructionofthecomponents.Thissectionoftheregulationsalsorequiresthatinserviceexaminationsofcomponentsandsystempressuretestsconductedduringthesecond120-monthinspectionintervalshallcomplywiththerequirementsinthelatesteditionandaddendaoftheCodeincorporatedbyreferencein10CFR50.55a(b)onthedate12monthspriortothestartofthesecond120-monthinspectioninterval,subjecttothelimitationsandmodificationslistedtherein.Thecomponents(includingsupports)maymeet.requirementssetforthinsubsequenteditionsandaddendaofthisCodewhichareincorporated'yreferencein10CFR50,55a(b)subjecttothelimitationsandmodificationslistedtherein.TheLicensee,IndianaandHichiganElectricCompany,haspreparedtheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInserviceInspection(ISI)ProgramPlan,Change1(Reference3),tomeettherequirementsofthe1983Edition,Summer1983Addenda(83S83)oftheASHECodeSectionXIexceptthattheextentofexaminationforCode,Class1andCodeClass2pipingweldshasbeendeterminedbythe1974EditionthroughSummer1975Addenda(74S75)aspermittedandrequiredby10CFR50.55a(b).Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.Asrequiredby10CFR50.55a(g)(5),ifthelicenseedeterminesthatcertainCodeexaminationrequirementsareimpracticalandrequestsrelieffromthem, thelicenseeshallsubmitinformationandjustificationstotheNuclearRegulatoryCommission(NRC)tosupportthatdetermination.Pursuantto10CFR50.55a(g)(6),theNRCwillevaluatethelicensee'sdeterminationsunder10CFR50.55a(g)(5)thatCoderequirementsareimpractical.TheNRCmaygrantreliefandmayimposealternativerequirementsthataredeterminedtobeauthorizedbylaw,willnotendangerlifeorpropertyorthecommondefenseandsecurity,andare.otherwiseinthepublicinterest,jivingdueconsiderationtotheburdenuponthelicenseethatcouldresultiftherequirementswereimposedonthefacility./TheinformationintheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,wasreviewed,includingtherequestsforrelieffrom'theASMECodeSectionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.ThereviewoftheISIProgramPlanwasperformedusingtheStandardReviewPlansofNUREG-0800(Reference4),Section5.2.4,"ReactorCoolantBoundaryInserviceInspectionsandTesting",andSection6.6,"InserviceInspectionofClass2and3Components."InaletterdatedFebruary2,1987(Reference5),theNRCrequestedadditionalinformationthatwasrequiredinordertocompletetherevie'woftheISIProgramPlan:TherequestedinformationwasprovidedbytheLicenseeinsubmittalsdatedApril10,1987(Reference6)andJune1,1987(Reference7).TheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlanisevaluatedinSection2ofthisreport.TheISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addendaofSectionXI,(b)acceptabilityofexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNRC'spreviouspreserviceinspection(PSI)andISIreviews.TherequestsforreliefareevaluatedinSection3ofthisreport.Unlessotherwisestated,referencestotheCoderefertotheASMECode,SectionXI,1983EditionincludingAddendathroughSummer1983.Specificinservicetest(IST)programsforpumpsandvalvesarebeingevaluatedinotherreports.
Fa 2.EVALUATIONOFINSERVICEINSPECTIONPROGRAMPLANThisevaluationconsistedofareviewoftheapplicableprogramdocumentstodeterminewhetherornottheyareincompliancewith,theCoderequirementsandanylicenseconditionspertinenttoISIactivities.Thissectiondescribesthesubmittalsreviewedandtheresultsofthereview.2.1Docume'ntvaluatedReviewhasbeencompletedonthefol',owinginformationprovidedbytheLicensee:(a)DonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985;(b)Letter,datedApril10,1987,Licensee'sresponsetotheNRC'sRAI;and(c)Letter,datedJune1,1987,informationtheLicenseecommittedtointheApril10,-1987letter.2.2ComliancewithCodeReuirements2.2.1ComliancewithAlicableCodeditionsTheInserviceInspectionProgramPlanshallbebasedontheCodeeditionsdefinedin10CFR50.55a(g)(4)and10CFR50.55a(b).BasedonthestartingdateofJuly1,-1986,theCodeapplicabletothesecondintervalISIprogramisthe1980EditionwithAddendathroughWinter1981.AsstatedinSection1ofthisreport,theLicenseehaswrittentheDonaldC.CookNuclearP'.ant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,tomeettherequirementsofthe1983Edition',Summer1983AddendaotheCodeexceptthattheextentofexaminationforCodeClassIandCodeClass2pipingweldshasbeendeterminedbythe1974EditionthroughSummer1975Addendaaspermittedandrequiredby10C.'R50.55a(b).Theuseof83SS3wasapprovedbytheNRCinaletterdatedJanuarv15,1986(Reference8).
1,('f 2.2.2AccetabilitoftheExaminationSamleInservicevolumetric,surface,andvisualexaminationsshallbeperformedonASMECodeClass1,2,and3componentsandtheirsupportsusingsamplingschedulesdescribedinSectionXIoftheASNECodeand10CFR50.55a(b).SamplesizeandweldselectionhavebeenimplementedinaccordancewiththeCodeandappeartobecorrect.2.2.3xclusionCriteriaThecriteriausedtoexcludecomponentsfromexaminationshallbeconsistentwithParagraphsIWB-1220,IMC-1220,IWC-1230,IWD-1220,and10CFR50.55a(b).TheexclusioncriteriahavebeenappliedbytheLicenseeinaccordancewiththeCodeasdiscussedintheISIProgramPlanandappeartobecorrect.2.2.4AugmentedExaminationCommitmentsThefollowingaugmentedexaminationswillbeimplementedduringthesecond10-yearinspectioninterval:(a)TheLicenseehascommittedtovolumetricallyexaminea7.5i'ampleofweldsintheContainmentSpraySystem.(b)ExaminationsfortheReactorPressureVesselareincompliancewithRegulatoryGuide1.150,"UltrasonicTestingofReactorVesselWeldsDuringPreserviceandInserviceExamination"(Reference9).(c)AugmentedexaminationsperRegulatoryGuide1.14,"ReactorCoolantPumpFlywheelIntegrity"(Reference10).2.3ConclusionsBasedonthereviewofthedocumentslistedabove,itisconcludedthattheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,isacceptableandincompliancewith10CFR50.55a(g)(4).
10~0(yg\
'.EVALUATIONOFRELIEFREQUESTSTherequestsforrelieffromtheASMECoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthesecond10-yearinspectionintervalareevaluatedinthefollowingsections.3.1lassComonent3.1.1ReactorPressureVessel(Noreliefrequests)3.l.2~i(II1ift.)3.1.3HeatExchanersandSteamGenerators(Noreliefrequests)3.1.4PiinPressur'eBoundar(Noreliefrequests)3.1;5PumPressureBoundar3.1.5.1RevestforReliefIExaminationCatepries8--I8-L-2andB-G-IReactorCoolantPumCasinoMeldPumCasinoInternalSurface'ndPumFlaneSurfaceCodeReuirement:SectionXI,TableIWB-2500-1,ExaminationCategoryB-L-I,Item812.10requiresa100%volumetricexaminationofthepressureretainingpumpcasingweldsasdefinedbyFigureIWB-2500-16.SectionXI,TableIWB-2500-1,ExaminationCategoryB-L-2,Item812.20requiresa100%visual(VT-3)examinationoftheinternalsurfacesofClass1pumpcasings.SectionXI,TableIWB-2500-.',ExaminationCategoryB-G-1,Item86.190requiresa100%visual(VT-1)examinationoftheflangesurfacesofClass1pumpswhenconnectionisdisassembled.Examinationincludes.1',nchannularsurfaceofflangesurroundingeachstud.
Licensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredvolumetricexaminationofpumpcasingweld1-RCPandfromperformingtheCode-requiredvisualexaminationsoftheinternalsurfacesofthepumpcasingsandthesurfacesofthepumpflanges.iensee'sProo'sedAlternativexamination:TheLicenseestatesthat,'nlieuofthe'requirementsofSectionXIforcategoriesB-L-1andB-L-2,avisualexamination(VT-2)willbeperformedon.theexternalsurfacesofonepumpduringthehydrostaticpressuretests.Inaddition,asurfaceexaminationwillbeperformedonthispumpontheaccessibleexternalsurfaceoftheweld.Ifapumphastobedisassembledformaintenance,visualexaminationswillbemadeoftheinternalsurfaces(VT-3)andtheflangesurface(VT-1)tosatisfytheB-L-2andB-G-1Coderequirements.TheLicenseestatesthattheneedforthevolumetricexaminationaccordingtotheB-L-1requirementwillbereevaluatedatthattime.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubstantialradiationexposurethatinspectionpersonnelwillincurandthesubstantialcostsinvolveddonotjustifythepossibleinformationthatmightbegainedabouttheweldandadjacentbasemetal.ThepumpcasingismadefromASNESA-351,GradeCF-SH,acastausteniticstainlesssteelthathasalonghistoryofsatisfactoryserviceinhandlingfluids.Thecasingwasmadeintwosectionstofacilitatethecastingprocess,andthetwosectionsareweldedtogetherwithamatchingfillermaterial.Thematerialhasgoodfracturetoughness,andunlikeferriticsteels,isnotsubjecttofracturepreventioncriteria.Volumetricandinternalcasingvisualexaminationwillrequirecompletedisassemblyofthepump.Disassemblyofthepump,s.orageoftheinternals,andplacementoffilmforthemany IhI radiographicexposuresthatwillberequired,willexposepersonneltosubstantialradiation.Fromexperienceatothernuclearplantsexaminingreactorcoolantpumps,personnelexposurecouldbeintherangebetween35to100man-rem.Flushingorshieldingwouldnotbeexpectedtosignificantlyreduceradiationlevels.Basedoncostsincurredbyothernuclearplants,thispumpexaminationisestimatedtocostabout$500,000,whichdoesnotincludecostsassociatedwithunitunavailabilityshouldth'isexaminationrequireextendinganoutage.TheCode-requiredexaminationwillrequiredisassemblyofapumpunderadverseconditionswherethereisapossibilityofcausingdamagetothepumpinternals.Thereisnootherreasontodisassembleanyofthesepumpsotherthantoperformtheseexaminations.Thisexaminationwillalsorequirehandlingthereactorvesselupperinternalassemblyanadditionaltime,astheupperinternalswillhavetobeputbackintothereactorvesseltominimizeairborneradiationduringthepumpexamination.Basedontheforegoing,andthefactthatCodereliefwasgrantedfortheD.C.Cookreactorcoolantpumpsforthefirstinterval,aswassimilarlygrantedforreactorcoolantpumpsinothernuclearplants,theLicenseebelievesthattheradiationexposureandcostsforthisexaminationdonotjustifyperformingthevolumetricandvisualexaminationstomeettherequirementsofCategoriesB-L-l,B-L-2,andB-G-I.Evaluation:Thevisualexaminationistodeterminewhetherunanticipatedseveredegradationofthecasingisoccurringduetophenomenasuchaserosion,corrosion,orcracking.However,previousexperienceduringexaminationofpumpsatotherplantshasnotshownanysignificantdegradationofpumpcasings.Theconceptofvisualexaminationifthepumpisdisassembledformaintenanceisacceptable.Ifthepumpisdisassembledfor maintenance,theCode-requiredvolumetricexaminationofthepumpcasingweldshouldalsobeperformed.Thedisassemblyofthepumpssolelyforthepurposeofinspectionisamajoreffortand,inadditiontothepossibilityofadditionalwear.'rdamagetotheinternalsurfacesofthepumps,couldresultinlargeamountsofradiationexposuretopersonnel.However,ifoneofthepumpsisdisassembledformaintenance,thecasingweld,internalsurfaces,andflangesurfacewouldbeexamined,inwhichcasereliefwouldnotberequiredfor'thatparticularpump.Conclusions:Basedontheaboveevaluation,itisconcludedthatcompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthat:(a)TheLicensee'sproposaltoperformthevisualexaminationoftheinternalsurfaces(VT-3)andtheflangesurface(VT-I)ofthepumps,whenevertheyaremadeaccessibleduetodisassemblyformaintenance,shouldbeaccepted,providedthattheCode-r'equiredvolumetricexaminationofthepumpcasingweldisalsoperformed;and(b)Reliefshouldbegrantedattheendoftheintervalifoneofthesubjectpumps,forwhichthevisualandvolumetricexaminationsarerequired,hasnotbeendisassembledformaintenance.3.1.6:ValvePressureBoundar(Noreliefrequests)3.1.7General(Noreliefrequests) 3.2Class2Comonents3.2.1PressureVessels(Noreliefrequests)3.2.2~Piin3.2.2.1euestforRelief2ExaminationCateorC-FternC5.lassPie-to-FluedHeadWeldsCodeReuirement:SectionXI,TableIWC-2500-1,Examinat)onCategoryC-F,ItemC5.21requiresa100%%usurfaceandvolumetricexaminationofthepressureretainingcircumferentialweldsinClass2piping,greaterthanI/2inchnominalwallthickness,asdefinedbyFigureIWC-2500-7.icensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredsurfaceandvolumetricexaminationofpipe-to-fluedheadweld01SintheFeedwaterSystemandLfluedhead-to-pipeweld12FintheMainSteamSystem.Licensee'sProosedAlternativexamination:TheLicenseestatesthat,inlieuoftherequirementsofSectionXI,thefirstaccessibleweldoutsideeachpenetrationwillbeexaminedwiththeCode-requiredsurfaceandvolumetricexaminations.Thisproposedalternativeexaminationwasusedinthefirst10-yearinterval.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubjectweldsaretotallyenclosedwithinapenetrationsleeve,andareinaccessibleforexamination.Sincetheinaccessiblepipe-to-fluedheadweldthicknessissubstantiallyheavierthanthe.proposedalternativeweldtobeexaminedandtheyareexposedtothesameenvironment,theoveralllevelofplantsafetywillnotbereducedbyperformingthealternativeexamination.
l4 J'valuation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingwhichshowstheexa'minationobstructions.TheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldsareimpracticaltoperformbecausetheseweldsarelocatedinsidecontainmentpenetrationsandarecompletelyinaccessible.BecausethefirstaccessibleweldoutsideeachpenetrationwillreceivetheCode-requiredsurfaceandvolumetricexaminations,samplesizeismaintained.Thesubjectweldscanonlybeexaminedbyinspectingforevidenceofleakageduringsystemhydrostatictests.Althoughthesecontainmentpenetrationweldscannotbevieweddirectly,theLicenseeshouldconductvisualexaminationsforevidenceofleakageinthevicinityoftheseweldswhenthehydrostaticpressuretestsareperformed.Bd'hb1i,<<ilddthattheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldsareimpracticaltoperformandthattheproposedalternativeexaminationensuresanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequestedprovidedthatvisualexaminationsareperformedonthetwocontainmentpenetrationassemblieswhen'eakageandhydrostatictestsareconductedinaccordancewithIWA-5000.3.2.2.2ReuestforRelief3ExaminationCateorC-FItemC5.21lassPie-to-FluedHeadWeldsCodeReuirement;SectionXI,TableIWC-2500-1,ExaminationCategoryC-F,ItemC5.21requiresa100/surfaceandvolumetricexaminationofthepressureretainingcircumferentia'.weldsinClass2piping,greaterthanI/2inchnominalwallthickness,asdefinedbyFigureIWC-2500-7.10 icensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredsurfaceandvolumetricexaminationsofpipe-to-fluedheadweldIOFintheMainSteamSystem.icensee'sProosedAlternativexamination:TheLicenseestatesthat,inlieuoftherequirementsofSectionXI,oneadjacentweldinonemainsteamline.willbeexaminedwiththeCode-requiredsurfaceandvolumetricexaminations.Thisproposedalternativeexaminationwasusedinthefirst10-yearinterval.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubjectweldisinaccessibleduetothelargepipewhiprestraintwhichsurroundstheweld.andadjacentarea.Volumetricexaminationbyultrasonicsisimpracticalbecausetheweldcannotbereach'edforpositioningandhandlingthetransducer,andradiographyisimpracticalbecausetheexposurewouldhavetobemadethroughtherestraint.Surfaceexaminationisimpracticalbecausetheweldisnotreadilyaccessibleforapplicationandremovalofpenetrantormanipulationofmagneticparticleequipment.Removalofthepipewhiprestraintswouldrequiretorchcutting2400and2700-lbsectionsthataresupportedfromabove.Theserviceconditionstowhichanadjacentweldisexposedshouldbenearlyidenticaltothatoftheinaccessibleweld,ardthustheoveralllevelofplantsafetywillnotbereducedbyperformingtheproposedalternativeexamination.Evaluation:TheLicensee'ssubmittalhasbeenreviewed,includingthedrawingwhichshowstheexaminationobstructions.TheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldareimpracticalbecausethisweld(andadjacentarea)issurroundedbyalargewhiprestraintandiscompletelyinaccessible.BecauseanadjacentweldwillreceivetheCode-requiredsurfaceandvolumetric
examinations,samplesizeismaintained.Thesubjectweldcanbeexaminedonlybyinspectingforevidenceofleakageduringsystemhydrostatictests.Althoughthiscontainmentpenetrationweldcannotbevieweddirectly,.theLicenseecouldconductvisualexaminationsforevidenceofleakageinthevicinityofthisweldwhenthehydrostaticpressuretestsareperformed.d1<<:Bddd1d,ddiddthattheCode-requiredsurfaceandvolumetricexaminationsofthesubjectweldareimpracticalandthattheproposedalternativeexaminationensuresanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequestedprovidedthatvisualexaminationsforevidenceofleakageareperformedinthevicinityofthecoveredweldwhentheCode-requiredleakageandhydrostatictestsareconducted.3.2.3~Pums(Noreliefrequests)3.2.4Valves(Nureliefrequests)'.2d5General(Noreliefrequests)3.3Class3Comonents(Noreliefrequests)3.4PressureTests3.4.1Class1SstemPressure.Tests3.4.1.1RevestforReliefP2Partof2SystemHdrostaticTestofClass]PiinaintheChemicalandVolumeControlSstemNOTE;SeetheevaluationofthisrequestforreliefinSection3,4.4.1.12 I
3.4.1;2RvestforReliefP4SstemHdrstaticTestofClas1iinintheEmerencCoreCoolinSstemCodeReuirement:SectionXI,ArticleIWB-5000requiresthat,foranoperatingpressureof2235psig,theClass1pipingbetestedatapressureof2458psig.icensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClass1pipingsectionsintheEmergencyCoreCoolingSystemattherequiredtestpressureof2458psig:ValvesIH0-51,SI-142LI-BoronInjectionLoopNo.1ValvesIH0-52,SI-142L2-BoronInjectionLoopNo.2ValvesIH0-53,SI-142L3-BoronInjectionLoopNo.3ValvesIH0-54,SI-142L4-BoronInjectionLoopNo.4icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.ThetestwillbeperformedduringHode3withtheRCSpressureat2280psigandtemperaturegreaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockcheckvalvesSI-142L1throughL4closed;therefore,maximumpressurewillbe2280psig.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesectionsofthepipingsystemupstreamofcheckvalvesSI-142L1-throughL4cannotbetestedatapressureof2458psigwithoutmakingtemporarymodifications(blockingthevalvedisc)tokeepthecheckvalvesclosed.Sincethepipingsectionsarepartoftheprimarysystem,plantpersonnelwillbesubjectedtosubstantialradiationexposureandcontaminationinordertocarryoutsuchmodificationsforthetest..Theproposedtestpressureishigherthanthe2235psignominaloperatingpressureinthesubjectsectionsofpiping,eachapproximately44to55feetlong.13
/valuation:Becausethesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithoutextensivetemporaryvalvemodifications,the..Codetestpressurerequirementisimpractical.Thevisualinspectionofthepipingduringthepressuretestaswellasthevolumetricexaminationrequirementsforselectedweldsinthesystemwillprovideadequateassuranceofthecontinuedstructuralintegrityofthepiping.ThedifferenceintherequiredtestpressureandthatproposedbytheLicenseedoesnotwarrantimpositionoftheCoderequirement.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthe'evelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.2Class2SstemPressureTests3.4.2.1ReuestforReliefPSstemHdrostaticTestofClass2PiinointheEmerencCoreCoolinSstemCodeReuirement:SectionXI,ArticleIWC-5000requiresthat,forasystemdesignpressureof2485psig,theClass2pipingbetestedatapressureof2733psig.icensee'sCodeReliefReuet:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClass2pipingsectionsintheEmergencyCoreCoolingSystemattherequiredtestpressureof2733psig:(a)AccumulatorNo.1DischargePiping-ValvesIH0-110,SI-166-1,IRV-115,andSI-168-1;14 lg~,'UJq'l (b)AccumulatorNo.2DischargePiping-ValvesIH0-120,SI-166-2,IRV-125,andSI-168-2;(c)AccumulatorNo.3DischargePiping-ValvesIH0-130,SI-166-3,IRV-135,andSl-168-3;and(d)AccumulatorNo.4DischargePiping-ValvesIH0-140,SI-166-4,IRV-145,andSI-168-4.icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.Thetestwillbeperformedduring.Mode3withtheRCSpressure.at2280psigandtemperaturegreaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalves(SI-166-1,-2,-3,and-4)closed,therefore,limitingmaximumpressureto2280psig.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesectionofpipingupstreamofcheckvalvesSI-166-1through4cannotbetestedatapressureof2733psigwithoutmakingextensivetemporarymodificationstokeepthevalvesclosed.Themodificationswouldrequire:(a)disas'semblyofthevalves,(b)weldingoftemporaryblocks(onthedownstreamside)insidethevalvebodiestoholda"jackscrew"typearrangementtokeepthevalveclosed,(c)removalofthetemporaryblockingdevicesfromthevalvesaftertesting,and(d)performingnecessarynondestructivetestingtoensuretheintegrityofthevalvebodiesbeforereturningthemtoservice.ThepipingdownstreamofthesevalvesispartoftheRHRSystemandcarriesradioactivefluidduringnormaloperation.Therefore,plantpersonnelwillbesubjectedtosubstantialradiationexposureandradioactivecontaminationinordertocarry.outany.modificationsforthetest.Evaluation:Thesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithouteitherextensivetemporaryvalvemodificationsoroverpressurizingtheClass1sectionsofconnectedpiping.15
\I~i Becauseofthis,thetestpressurerequirementisimpracticaltoattain.Thesectionsofpipingwillbesubjectedtoa'ressureslightlyhigherthannormaloperatingpressureandatatemperaturehigherthanthatrequired,bytheCode.Thevisualinspectionofthepipingduringthepressuretestaswellasthevolumetricexaminationrequirementsforselectedweldsinthesystemwill'provideadequateassuranceofthecontinuedstructuralintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.2.2ReuestforReliefP2Part2of2SstemHdrostaticTestoFClass2PiinintheChemicaland'olumeControlSstemNOTE:SeetheevaluationofthisrequestforreliefinSection3.4.4.1.3.4.2.3RevestforReliefP3SstmHdrostaticTestofClass2PiinintheChemicalandVolumControlSstemCodeReuirement:SectionXI,ArticleIMC-5000requiresthat,foradesignpressureof2485psig,theClass2pipingbehydrostaticallypressuretestedatapressureof3106psig.Licensee'sCodeReliefReuest:ReliefisrequestedfromperformingtheCode-requiredhydrostaticpressuretestofthe16 aLetdownLines(ValvesQRV-112,QRV-160,QRV-161,andQRV-162)intheChemicalandVolumeControlSystem(ReactorLetdownandCharging)attherequiredtestpressureof3106psig.icensee'sProosedAlternativexamination:TheLicenseestatesthatthesubjectsectionofpipingwillbetestedatapressureof2280psigduringNode3usingRCSpressure.ValvesQRV-illandQRV-112willbeopenedwithQRV-160;QRV-161,andQRV-162closed.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatthesubjectsectionofpipingcannotbetestedatapressureof3106psigwithout(a)usingaspareone-inchpluggedconnectioninUnit1pipinglocateddownstreamofinstrumentQTA-160intheregenerative.heatexchangerroom,whichisconsideredahighradiationarea,and(b)modification,sincenotestconnectionexistsinUnit2piping.Thispipingcarriesradioactivefluidduringnormaloperation;therefore,plantpersonnelwillbesubjecttosubstantialradiationexposureandcontamination',nordertomodify/addatestconnection.Asanalternative,extendingthetestboundarytoQCR-301wasconsidered.ThiswouldinvolveusingQPX-301locatedonthedownstreampipingoutsidethe.regenerativeheatexchangerroomasatestconnection.ThisalternativewasalsorejectedbecausevalveQCR-301andtheflangeboltedtotheinletflangeofsafetyvalveSV-051areinthe600-lbclasswhichcannotwithstandtheabovetestpressure.~valuatior:Thesystem'sdesigndidnotincludeatestconnectiontoallowpressurizingtotheCodetestpressureorpipiengandvalvesratedappropriatelytoaccommodatetherequiredpressureatotherisolationpointsinthesystem.InordertocomplywiththeCoderequirement,theLicenseewouldhavetoinstallatestconnectionoroverpressurizelowerratedpipingandcomponents.Therefore,theCoderequirementis17 impractical.TheLicensee'sproposedalternativetestwillsubjectthepipingtoapressureslightlyhigherthannormaloperatingpressure.TherequiredvisualinspectionofthepipingatthetestpressureandotherrequiredNDEoftheweldsinthesystemwillprovideadequateassuranceofthecontinuedstructuralintegrityofthepiping.Conclusions:Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNOErequirements,willensureanacceptablelevelofinservicestructuralintegrity.Compliancewiththespecific.requirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.2.4RevestforReliefP5SystemHdrostaticTestofClass2PiinintheAuxiliarSratoReactorCoolantSstemandPressurizerandChemicalandVolumeControlSstemCodeReuirement:SectionXI,ArticleIMC-5000requiresthat,foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.Licensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredhydrostaticpressuretestoftheClass2pipingsectionsdescribedbythefollowingpipingboundariesattherequiredtestpressureof3419psig:ValvesQRV-51CS-326ValvesQRY-61CS-322ValvesQRV-62.Licensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2800psigusinga"stemblock"tokeepvalveQRV-51closed.
+"IlegE<.
icensee'sBasisforReuestinRelief:TheLicenseestatesthat,inordertoperformthepressuretestofthesesectionsofpiping,valveHARV-51hastobeusedasanisolationvalve.This1500-lbclass,air-operatedcontrolvalveisdesignedtowithstandtestpressureof3419psigintheopenposition.However,itcannotbeusedasanisolationvalvebecauseitwasdesignedforadifferentialpressureof1200psig.Thevalvecannotbekeptclosedduringpressuretestingat3419psigwithoutextensive,temporaryrigging.Themodificationwouldrequire:(a)removaloftheairoperatorandinstallationofa"strongback"tokeepthevalveclosedduringtesting,(b)removalofthe"strongback"afterthetesting,and(c)reinstallationoftheairoperatoronthevalveandrestoringthevalvetooperableconditionbeforereturningtoservice.Thevalveislocatedinsidetheregenerativeheatexchangerroom,whichisaveryhighradiationareaandplantpersonnelwouldbesubjectedtoradiationexposureoffivetosevenman-rems.Asanalternative,thepossibilityofusingafreezesealplugdownstreamofHARV-51wasconsidered.Thiswouldinvolveextensiveworkingtimeclosetothepressurizersprayvalves,whichareinahighradiationarea.Thisalternativewas",ejectedbeauseplantpersonnelwouldbesubjecttoanevenhigherradiationeXposureof8.5man-remsduringformation,monitoring,andremovalofthefreezesealplug.Evaluation:TheabovepipingsystemcannotbetestedtoASHECoderequirementswithoutmodifyingthesystemand/orexposingpersonneltolargeamountsofradiation.TheproposedtestCpressureishigherthanthenormaloperatingpressureof2235psigintheapproximately30-foot-longsectionofpipingforwhichCodereliefisrequested.Theproposedtes+pressureis25llabovethenormaloperatingpressure.Thus,thetestprovidesreasonableassuranceoftheintegrityofthepiping.19 Clli:Bdthbii,<<<*1ddthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwith.theotherNDErequirements,willensure*anacceptablelevelofinservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityaridsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.4.3Class3SstemPressureTests(Noreliefrequests)3.4.4General3.4.4.1ReouestforReliefP2SstemMdrostaticTestoFClass1and2PiinintheChemicalandVolumeControlSstemCodeReuirement:SectionXI,ArticleIWB-5000requiresthat,foranoperatingpressureof2235psig,theClass1pipingbetestedatapressureof2458psig.SectionXI,ArticleIWC-5000requiresthat,foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.icensee'sCodeReliefRevest:ReliefisrequestedfromperformingtheCode-requiredhydrostatictestofthefollowingClass1and2pipingsectionsintheChemicalandVolumeControlSystem(Reactor'LetdownandCharging)attheCode-requiredtestpressuresof2458and3419psig:(a)Class1piping:Two-inchAuxiliarySprayPiping-ValvesHARV-SlandCS-325;(b)Class2piping:NormalChargingLoop4ColdLeg-ValvesgRY-62,CS-328L4,CS-326,andCS-327;20 (c)Class2piping:AlternateChargingLine'oLoop1ColdLeg-ValvesHARV-61andCS-328L1.icensee'sProosedAlternativeExamination:TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psigatatemperatureabove100'F.ThetestwillbeperformedduringMode3withtheReactorCoolantSystem(RCS)pressureat2280psigandtemperaturegreaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalvesCS-329L1,CS-329L4,andCS-325closed;therefore,maximumpressurewillbe2280psig.Licensee'sBasisforReuestinRelief:TheLicenseestatesthatcheckvalvesCS-328L1,CS-328L4,andCS-325arelocatedonthecharginglinesto'heRCSSystem.Thesevalvesmustbedisassembledandtemporarilymodifiedtoblockthemclosedinordertoperformtherequiredhydrostatictests,andplant"personnelwillbeexposedtohighradiationandradioactivecontaminationduringthemodification.Theproposedtestpressureishigherthan2235psignominaloperatingpressureinthesectionofpipingbetween23and115feetlongforwhich'eliefisrequested.fvaluation:Thesystem'sdesigndoesnotpermitpressurizingthesectionsofpipingtotheCode-requiredpressurewithouteitherextensivetemporaryvalvemodificationsoroverpressurizingtheClass1sectionsofconnectedpiping.Becauseofthis,theCode-requiredtestpressureisimpracticaltoattain.ThesectionsofpipingwillbesubjectedtoapressureslightlyhigherthannormaloperatingpressureandatatemperaturehigherthanthatrequiredbytheCode.Thevisual,i'nspectionofthepipingduringthepressuretest,aswellasthevolumetricexaminationrequirementsforselectedweldsinthesystems,willprovideadequateassuranceofthecontinuedstructuralintegrityofthepiping.21 j
==
Conclusions:==
Basedontheaboveevaluation,itisconcludedthattheCoderequirementsareimpracticalandthatthealternativetestproposedbytheLicensee,inconjunctionwiththeotherNDErequirements,willensureanacceptablelevelof'inservicestructuralintegrity.CompliancewiththespecificrequirementsofSectionXIwouldresultinhardshiporunusualdifficultieswithoutacompensatingincreaseinthelevelofqualityandsafety.Therefore,itisrecommendedthatreliefbegrantedasrequested.3.5Genera1(Noreliefrequests)22 gPIQ 4.CONCLUSIONPursuantto10CFR50.55a(g)(6),ithasbeendeterminedthatcertainSectionXIrequiredinserviceexaminationsareimpracticaltoperform.Inthesecases,theLicenseehasdemonstratedthateithertheproposedalternativeswouldprovideanacceptablelevelofqualityandsafetyorthatcompliancewiththerequirementswouldresultinhardshipsorunusual\difficultieswithoutacompensatingincreaseinthelevelof.quality'.andsafety.Thistechnicalevaluationreporthasnotidentifiedanypracticalmethod'bywhichtheexistingDonaldC.CookNuclearPlant,Unit1,canmeetallthespecificinserviceinspectionrequirementsofSectionXIoftheASHECode.RequiringcompliancewithalltheexactSectionXIrequiredinspectionswouldrequireredesignofasignificantnumberofplantsystems,sufficientreplacementcomponentstobeobtained,installationofthenewcomponents,andabaselineexaminationofthesecomponents.Evenaftertheredesignefforts,completecompliancewiththeSectionXIexaminationrequirementsprobablycouldnotbeachieved.Therefore,itisconcludedthatthepublicinterestisnotservedbyimposinacertainprovisionsofSectionXIoftheASthECodethathavebeendeterminedtobeimpractical.Pursuantto10CFR50.55a(g)(6),reliefisallowedfromtheserequiremertswhichareimpracticaltoimplement.Thedevelopmentofneworimprovedexaminationtechniqueswillcontiruetobemonitored.Asimprovementsintheseareasareachieved,theNRCmayrequirethatthesetechniquesbeincorporatedinthenextinspectionintervalISIprogramplanexaminationrequirements.BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInserviceInspectionProgramPlan,Change1,datedDecember1985,theLicensee'sresponsestotheNRC'sRequestforAdditionalInformation,andtherecommendationsforgrantingrelieffromtheISIexaminationrequirementsthathavebeendeterminedtobeimpractical,ithasbeenconcludedthattheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInserviceInspectionProgramPlan,Change1,datedDecember1965,isacceptablandincompliancewith10CFR50.55a(g)(4).
Ih) 5.REFERENCES1.CodeofFederalRegulations,Volume10;Part50.2.AmericanSocietyofHechanicalEngineersBoilerandPressureVesselCode,SectionXI,Division1:1983EditionthroughSummer1983Addenda1974EditionthroughSummer1975Addenda3.DonaldC.CookNuclearPlant,Unit1,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[IndianaandHichiganElectricCompany(IHEC)],"RequestforAdditionalInformationforReviewoftheDonaldC.CookNuclearPlant,Units1and2,Second10-YearIntervalInserviceInspectionProgramPlans,Change1,datedDecember1985."6.Letter,April10,1987,H.P.Alexich(IHEC)toH.R.Denton(NRC),"ResponsetoRequestforAdditionalInformationontheISISecond10-Year'ntervalMeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."7.Letter,June1,1987,M.P.Alexich(IHEC)toT.E.Hurley(NRC),"ResponsetoRequestfor.AdditionalInformationontheISISecond10-YearIntervalWeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."8.Letter,January15,1986,B.;J.Youngblood(NRC)toJ.E.Dolan(IHEC),"NRCApprovalforIndianaandHichiganElectricCompanytoUseASHECodeSectionXI,1983EditionwithSummer1983AddendafortheISI/ISTProgramfortheDonaldC.CookNuclearPlant,Units1and2."24 9..RegulatoryGuide1.150,"UltrasonicTestingofReactorVesselWeldsDuringPreserviceandInserviceExaminations,"Revision1,datedFebruary1983.10.RegulatoryGuide1.14,"ReactorCoolantPumpFlywheelIntegrity,"Revision1,datedAugust'1975.25 1E'trEf:%(
711Cf01M~I5Ski11CUIIGT,STOI,STGTBIBUOGRAPHICDATASHEETEGG-SD-7799VLIIVCLEA11EOVLATOAVCOMMISSIQMI15fOATIIVMSE1IAIVfkkfkfTIDCkkfVMflf,el~iSEEIMSTAUCTIQIISOMTIIE1EVE1555.TITLfAIIQ5VSTITLETechnicalEvaluationReportontheSecond10-YearIntervalInserviceInspectionProgramPlan:IndianaandHichiganElectricCo.,DonaldC.CookNuclearPlant,Unit1,DocketNumber50-3155LEAVE~LAIIILkDATE1EfOATCOMfLETEDTEA1MOIeTM5AVT+01ISIJuly1988~D*TE15fo1TISSVEOB.W.Brown,J.D.HudlinTff1fQAMIMGOAGAIIIZATIOMMAMEAMDMAILIUGAOD155$llkfMffjMCkkrlEG&GIdaho,Inc.P.0.Box1625IdahoFalls,ID83415-2209MOUTHJuly~,t1QIEGTITASA.'ITQAAvMITMMM4515fIII01G1AIITMVME51TEA1198810SfOIISOIIIIIGQAGAIIIZATIOIIIIAV5AMOUAILIUGAQOIIESSllkf~ZMCkff1HaterialsEngineeringBranchOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555ISSVffLEMEVTkflvMOTE5FIN-D6022(Propre'ct5)II~TvfEOf15>OATTechnical~.f5fIIQDCOVEfIEDIlkMVAM<<MM1$AESTAACTIowaorranThisreportpresentstheresultsoftheevaluationoftheDonaldC.CookNuclearPl,ant,Unit1,Second10-YearIntervalInserviceInspection(ISI)ProgramPlan,Change1,datedDecember1985,includingtherequestsforrelieffromtheAmericanSocietyofHechanicalEngineers(ASHE)BoilerandPressureVesselCodeSect'ionXIrequirementswhichtheLicenseehasdeterminedtobeimpractical.InSection2ofthisreport,theISIProgramPlanisevaluatedfor(a)compliancewiththeappropriateedition/addendaofSectionXI,(b)acceptabilityoftheexaminationsample,(c)exclusioncriteria,and(d)compliancewithISI-relatedcommitmentsidentifiedduringtheNuclearRegulatoryCommission's(NRC)previouspreserviceinspection(PSI)andISIreviews.TherequestsforrelieffromtheASHE'CoderequirementswhichtheLicenseehasdeterminedtobeimpracticalforthefirst10-yearinspectionintervalareevaluatedinSection3ofthisreport.I~OQCLIMEMTAMALT515~KETIVQ"DSIGESCAPTO15'lfkbki&SILsT>STATEMEIIT1iOEMTlflfASloff~f4QEOTEAMSUnlimitedI~5ECVAITVCLASSIfICATIDMUn'ssifiedjfkvIwortiUnclassified111VMSfkGIkkGESIffklCE I