ML17328A871

Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan:Indiana & Michigan Electric Co, DC Cook Nuclear Plant,Unit 1.

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: ML17328A868 ML17328A870 ML17328A871 ML17328A872
References
CON-FIN-D-6022 EGG-SD-7799, NUDOCS 9102010172
Download: ML17328A871 (49)

Text

ATTACHMENT 1EGG-SD-7799 TECHNICAL EVALUATION REPORTONTHESECOND10-YEARINTERVALINSERVICE INSPECTION PROGRAMPLAN:INDIANAANDMICHIGANELECTRICCOMPANY,DONALDC.COOKNUCLEARPLANT,UNIT1,DOCKETNUMBER50-315B.W.BrownJ.D.MudlinPublished July1988IdahoNationalEngineering Laboratory EG&GIdaho,Inc.IdahoFalls,Idaho83415Preparedfor:U.S.NuclearRegulatory Commission Washington, D.C.20555underDOEContractNo.DE-AC07-76ID01570 gFINNo.06022(Project5)9102010172 910124PDRADOCK05000315PPDR ABSTRACTThisreportpresentstheresultsoftheevaluation oftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection (ISI),ProgramPlan,Change1,datedDecember1985,including therequestsforrelieffromtheAmericanSocietyofMechanical Engineers (ASHE)BoilerandPressureVesselCodeSectionXIrequirements whichtheLicenseehas'determined tobeimpractical.

TheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlanisevaluated inSection2ofthisreport.TheISIProgramPlanisevaluated for(a)compliance withtheappropriate edition/addenda ofSectionXI,(b)acceptability ofexamination sample,(c)exclusion

criteria, and(d)compliance withISI-related commitments identified duringtheNuclearRegulatory Commission's (NRC)previouspreservice inspection (PSI)andISIreviews.The.requestsfor-relieffromtheASHECoderequirements whichtheLicenseehasdetermined tobeimpractical forthesecond10-yearinspection intervalareevaluated inSection3ofthisreport.Thisworkwas,funded under:U.S,NuclearRegulatory Commission FINNo.D6022,Project5Operating ReactorLicensing IssuesProgram,ReviewofISIforASHECodeClass1,2,and3Components 11 SUHHARYTheLicensee, IndianaandHichiganElectricCompany,haspreparedtheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection (ISI)ProgramPlanto.meettherequirements ofthe1983Edition,Summer1983Addenda(83S83)oftheASHECodeSectionXIexceptthattheextentofexamination forCodeClass1andCodeClass2pipingweldshasbeendetermined bythe1974EditionthroughSummer1975Addenda(74S75)aspermitted andrequiredby10CFR50.55a(b).

Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.Theinformation intheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,Change1,datedDecember1985,wasreviewed, including therequestsforrelieffromtheASHECodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical.

Asaresultofthisreview,aRequestforAdditional Information (RAI)wasprepareddescribing theinformation and/orclarification requiredfromtheLicenseeinordertocompletethereview.BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,theLicensee's responsetotheNRC'sRAI,andtherecommendations forthegrantingofrelieffromtheISIexamination requirements thathavebeendetermined tobeimpractical, ithasbeenconcluded thattheDonaldC.CookNuclearPlant,Unit1,Second10-Year'ntervalISIProgramPlan,Change1,datedDecember1985,isacceptable andincompliance with10CFR50.55a(g)(4).

I1I CONTENTSABSTRACT~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o1iSUHMARY...........................................

......................i>i INTRODUCTION...........................................................1 12.EVALUATION OFINSERVICE INSPECTION PROGRANPLAN........................3 2.1Documents Evaluated..................................;..............3 2.2Compliance withCodeRequirements...............

..........:......3 2.2.1Compliance withApplicable CodeEditions........................3 2.2.2Acceptability oftheExamination Sample..............:..........4 2P'2.3Exclusion Crsteria..............................................4 2.2.4Augmented Examination Commitments.......;...

...................4 2.3Conclusions.........................................................4 03.EVALUATION OFRELIEFREQUESTS.......................................5 3.1Class1Components.

..............................................5 3.1.1ReactorPressureVessel(Noreliefrequests) 3.1.2Pressurizer (Noreliefrequests) 3.1.3HeatExchangers andSteamGenerators (Noreliefrequests) 3.1.4PipingPressureBoundary(Noreliefrequests) 3.1.5PumpPressureBoundary...................

..................5 3.1.5.1RequestforRelief1,Examination Categories B-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,Examination CategoryC-ItemC5.21,Class2Pipe-to-Flued HeadWelds.iv I'IIthA3 3.2.2.2RequestforRelief3,Examination CategoryC-F,ItemC5.21,Class2Pipe-to-Flued HeadWelds...............10 3.2.3'umps (Noreliefrequests) 3.2.4Valves(Noreliefrequests) 3.2.5General(Noreliefrequests) 3.3Class3Components (Noreliefrequests)

.4PressureTests.....................................................

1233.4.1Class1SystemPressureTests..................................12 3.4.1.1RequestforReliefP2(Part1of2),System.Hydrostatic TestofClass1PipingintheChemicalandVolumeControlSystem..................................12 3.4.1.2RequestforReliefP4,SystemHydrostatic TestofClass1PipingintheEmergency CoreCoolingSystem........

133.4.2Class2SystemPressureTests..................-.............

..143.4.2.1RequestforReliefPl,SystemHydrostatic TestofClass2PipingintheEmergency CoreCoolingSystem........

143.4.2.2RequestforReliefP2(Part2of2),SystemHydrostatic Test.ofClass2PipingintheChemicalandVolumeControlSystem...........................

3.4.2.3RequestforReliefP3,SystemHydrostatic TestofClass2PipingintheChemicalandVolumeControl~~~~16ystem.....................................................

16S3.4:2.4RequestforReliefP5,SystemHydrostatic TestofClass2PipingintheAuxiliary SpraytoReactorCoolantSystemandPressurizer, andChemicalandVolumeControlSystem..........

3.4.3Class3SystemPressureTests(Noreliefrequests) 3.4.4General.....

~~~~~~~~~~~~~~~~18.203.4.4.1RequestforReliefP2,SystemHydrostatic TestofClass1and2Pipingin,theChemicalandVolumeControlSystem,;.........

..............................20 3.5General(Noreliefrequests)

~CONCLUSIONo~~'t~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~2345oREFRENCcSo~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ii~~~i24I E'III<~1 TECHNICAL EVALUATION REPORTONTHE'SECOND10-YEARINTERVALINSERVICE INSPECTION PROGRAHPLAN:INDIANAANDHICHIGANELECTRICCOHPANY,DONALDC.COOKNUCLEARPLANT,UNIT1,DOCKETNUHBER50-3151.INTRODUCTION Throughout theservicelifeofawater-cooled nuclearpowerfacility, 10CFR50.55a(g)(4)

(Reference 1)requiresthatcomponents (including supports) whichareclassified asAmericanSocietyofHechanical Engineers

,(ASHE)BoilerandPressureVesselCodeClass1,Class2,andClass3meettherequirements, exceptthedesignandaccessprovisions andthepreservice examination requirements, setforthintheASHECodeSectionXI,"RulesforInservice Inspection ofNuclearPowerPlantComponents,"

(Reference 2)totheextentpractical withinthelimitations ofdesign,geometry, andmaterials ofconstruction ofthecomponents.

Thissectionoftheregulations alsorequiresthatinservice examinations ofcomponents andsystempressuretestsconducted duringthesecond120-month inspection intervalshallcomplywiththerequirements inthelatesteditionandaddendaoftheCodeincorporated byreference in10CFR50.55a(b) onthedate12monthspriortothestartofthesecond120-month inspection

interval, subjecttothelimitations andmodifications listedtherein.Thecomponents (including supports) maymeet.requirements setforthinsubsequent editionsandaddendaofthisCodewhichareincorporated'y reference in10CFR50,55a(b) subjecttothelimitations andmodifications listedtherein.TheLicensee, IndianaandHichiganElectricCompany,haspreparedtheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection (ISI)ProgramPlan,Change1(Reference 3),tomeettherequirements ofthe1983Edition,Summer1983Addenda(83S83)oftheASHECodeSectionXIexceptthattheextentofexamination forCode,Class1andCodeClass2pipingweldshasbeendetermined bythe1974EditionthroughSummer1975Addenda(74S75)aspermitted andrequiredby10CFR50.55a(b).

Thesecond10-yearintervalbeganJuly1,1986andendsJune30,1996.Asrequiredby10CFR50.55a(g)(5),

ifthelicenseedetermines thatcertainCodeexamination requirements areimpractical andrequestsrelieffromthem, thelicenseeshallsubmitinformation andjustifications totheNuclearRegulatory Commission (NRC)tosupportthatdetermination.

Pursuantto10CFR50.55a(g)(6),

theNRCwillevaluatethelicensee's determinations under10CFR50.55a(g)(5) thatCoderequirements areimpractical.

TheNRCmaygrantreliefandmayimposealternative requirements thataredetermined tobeauthorized bylaw,willnotendangerlifeorpropertyorthecommondefenseandsecurity, andare.otherwise inthepublicinterest, jivingdueconsideration totheburdenuponthelicenseethatcouldresultiftherequirements wereimposedonthefacility.

/Theinformation intheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,wasreviewed, including therequestsforrelieffrom'theASMECodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical.

ThereviewoftheISIProgramPlanwasperformed usingtheStandardReviewPlansofNUREG-0800 (Reference 4),Section5.2.4,"ReactorCoolantBoundaryInservice Inspections andTesting",

andSection6.6,"Inservice Inspection ofClass2and3Components."

InaletterdatedFebruary2,1987(Reference 5),theNRCrequested additional information thatwasrequiredinordertocompletetherevie'woftheISIProgramPlan:Therequested information wasprovidedbytheLicenseeinsubmittals datedApril10,1987(Reference 6)andJune1,1987(Reference 7).TheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlanisevaluated inSection2ofthisreport.TheISIProgramPlanisevaluated for(a)compliance withtheappropriate edition/addenda ofSectionXI,(b)acceptability ofexamination sample,(c)exclusion

criteria, and(d)compliance withISI-related commitments identified duringtheNRC'spreviouspreservice inspection (PSI)andISIreviews.Therequestsforreliefareevaluated inSection3ofthisreport.Unlessotherwise stated,references totheCoderefertotheASMECode,SectionXI,1983Editionincluding AddendathroughSummer1983.Specificinservice test(IST)programsforpumpsandvalvesarebeingevaluated inotherreports.

Fa 2.EVALUATION OFINSERVICE INSPECTION PROGRAMPLANThisevaluation consisted ofareviewoftheapplicable programdocuments todetermine whetherornottheyareincompliance with,theCoderequirements andanylicenseconditions pertinent toISIactivities.

Thissectiondescribes thesubmittals reviewedandtheresultsofthereview.2.1Docume'nt valuatedReviewhasbeencompleted onthefol',owing information providedbytheLicensee:

(a)DonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985;(b)Letter,datedApril10,1987,Licensee's responsetotheNRC'sRAI;and(c)Letter,datedJune1,1987,information theLicenseecommitted tointheApril10,-1987letter.2.2ComliancewithCodeReuirements 2.2.1ComliancewithAlicableCodeditionsTheInservice Inspection ProgramPlanshallbebasedontheCodeeditionsdefinedin10CFR50.55a(g)(4) and10CFR50.55a(b).

BasedonthestartingdateofJuly1,-1986,theCodeapplicable tothesecondintervalISIprogramisthe1980EditionwithAddendathroughWinter1981.AsstatedinSection1ofthisreport,theLicenseehaswrittentheDonaldC.CookNuclearP'.ant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,tomeettherequirements ofthe1983Edition',

Summer1983AddendaotheCodeexceptthattheextentofexamination forCodeClassIandCodeClass2pipingweldshasbeendetermined bythe1974EditionthroughSummer1975Addendaaspermitted andrequiredby10C.'R50.55a(b).

Theuseof83SS3wasapprovedbytheNRCinaletterdatedJanuarv15,1986(Reference 8).

1,('f 2.2.2AccetabilitoftheExamination SamleInservice volumetric, surface,andvisualexaminations shallbeperformed onASMECodeClass1,2,and3components andtheirsupportsusingsamplingschedules described inSectionXIoftheASNECodeand10CFR50.55a(b).

Samplesizeandweldselection havebeenimplemented inaccordance withtheCodeandappeartobecorrect.2.2.3xclusionCriteriaThecriteriausedtoexcludecomponents fromexamination shallbeconsistent withParagraphs IWB-1220, IMC-1220, IWC-1230, IWD-1220, and10CFR50.55a(b).

Theexclusion criteriahavebeenappliedbytheLicenseeinaccordance withtheCodeasdiscussed intheISIProgramPlanandappeartobecorrect.2.2.4Augmented Examination Commitments Thefollowing augmented examinations willbeimplemented duringthesecond10-yearinspection interval:

(a)TheLicenseehascommitted tovolumetrically examinea7.5i'ample ofweldsintheContainment SpraySystem.(b)Examinations fortheReactorPressureVesselareincompliance withRegulatory Guide1.150,"Ultrasonic TestingofReactorVesselWeldsDuringPreservice andInservice Examination" (Reference 9).(c)Augmented examinations perRegulatory Guide1.14,"ReactorCoolantPumpFlywheelIntegrity" (Reference 10).2.3Conclusions Basedonthereviewofthedocuments listedabove,itisconcluded thattheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalISIProgramPlan,throughChange1,datedDecember1985,isacceptable andincompliance with10CFR50.55a(g)(4).

10~0(yg\

'.EVALUATION OFRELIEFREQUESTSTherequestsforrelieffromtheASMECoderequirements whichtheLicenseehasdetermined tobeimpractical forthesecond10-yearinspection intervalareevaluated inthefollowing sections.

3.1lassComonent3.1.1ReactorPressureVessel(Noreliefrequests) 3.l.2~i(II1ift.)3.1.3HeatExchanersandSteamGenerators (Noreliefrequests) 3.1.4PiinPressur'e Boundar(Noreliefrequests) 3.1;5PumPressureBoundar3.1.5.1RevestforReliefIExamination Catepries8--I8-L-2andB-G-IReactorCoolantPumCasinoMeldPumCasinoInternalSurface'ndPumFlaneSurfaceCodeReuirement:

SectionXI,TableIWB-2500-1, Examination CategoryB-L-I,Item812.10requiresa100%volumetric examination ofthepressureretaining pumpcasingweldsasdefinedbyFigureIWB-2500-16.

SectionXI,TableIWB-2500-1, Examination CategoryB-L-2,Item812.20requiresa100%visual(VT-3)examination oftheinternalsurfacesofClass1pumpcasings.SectionXI,TableIWB-2500-.',

Examination CategoryB-G-1,Item86.190requiresa100%visual(VT-1)examination oftheflangesurfacesofClass1pumpswhenconnection isdisassembled.

Examination includes.1',nchannularsurfaceofflangesurrounding eachstud.

Licensee's CodeReliefRevest:Reliefisrequested fromperforming theCode-required volumetric examination ofpumpcasingweld1-RCPandfromperforming theCode-required visualexaminations oftheinternalsurfacesofthepumpcasingsandthesurfacesofthepumpflanges.iensee'sProo'sedAlternative xamination:

TheLicenseestatesthat,'nlieuofthe'requirements ofSectionXIforcategories B-L-1andB-L-2,avisualexamination (VT-2)willbeperformed on.theexternalsurfacesofonepumpduringthehydrostatic pressuretests.Inaddition, asurfaceexamination willbeperformed onthispumpontheaccessible externalsurfaceoftheweld.Ifapumphastobedisassembled formaintenance, visualexaminations willbemadeoftheinternalsurfaces(VT-3)andtheflangesurface(VT-1)tosatisfytheB-L-2andB-G-1Coderequirements.

TheLicenseestatesthattheneedforthevolumetric examination according totheB-L-1requirement willbereevaluated atthattime.Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesubstantial radiation exposurethatinspection personnel willincurandthesubstantial costsinvolveddonotjustifythepossibleinformation thatmightbegainedabouttheweldandadjacentbasemetal.ThepumpcasingismadefromASNESA-351,GradeCF-SH,acastaustenitic stainless steelthathasalonghistoryofsatisfactory serviceinhandlingfluids.Thecasingwasmadeintwosectionstofacilitate thecastingprocess,andthetwosectionsareweldedtogetherwithamatchingfillermaterial.

Thematerialhasgoodfracturetoughness, andunlikeferriticsteels,isnotsubjecttofractureprevention criteria.

Volumetric andinternalcasingvisualexamination willrequirecompletedisassembly ofthepump.Disassembly ofthepump,s.orageoftheinternals, andplacement offilmforthemany IhI radiographic exposures thatwillberequired, willexposepersonnel tosubstantial radiation.

Fromexperience atothernuclearplantsexamining reactorcoolantpumps,personnel exposurecouldbeintherangebetween35to100man-rem.Flushingorshielding wouldnotbeexpectedtosignificantly reduceradiation levels.Basedoncostsincurredbyothernuclearplants,thispumpexamination isestimated tocostabout$500,000,whichdoesnotincludecostsassociated withunitunavailability shouldth'isexamination requireextending anoutage.TheCode-required examination willrequiredisassembly ofapumpunderadverseconditions wherethereisapossibility ofcausingdamagetothepumpinternals.

Thereisnootherreasontodisassemble anyofthesepumpsotherthantoperformtheseexaminations.

Thisexamination willalsorequirehandlingthereactorvesselupperinternalassemblyanadditional time,astheupperinternals willhavetobeputbackintothereactorvesseltominimizeairborneradiation duringthepumpexamination.

Basedontheforegoing, andthefactthatCodereliefwasgrantedfortheD.C.Cookreactorcoolantpumpsforthefirstinterval, aswassimilarly grantedforreactorcoolantpumpsinothernuclearplants,theLicenseebelievesthattheradiation exposureandcostsforthisexamination donotjustifyperforming thevolumetric andvisualexaminations tomeettherequirements ofCategories B-L-l,B-L-2,andB-G-I.Evaluation:

Thevisualexamination istodetermine whetherunanticipated severedegradation ofthecasingisoccurring duetophenomena suchaserosion,corrosion, orcracking.

However,previousexperience duringexamination ofpumpsatotherplantshasnotshownanysignificant degradation ofpumpcasings.Theconceptofvisualexamination ifthepumpisdisassembled formaintenance isacceptable.

Ifthepumpisdisassembled for maintenance, theCode-required volumetric examination ofthepumpcasingweldshouldalsobeperformed.

Thedisassembly ofthepumpssolelyforthepurposeofinspection isamajoreffortand,inadditiontothepossibility ofadditional wear.'rdamagetotheinternalsurfacesofthepumps,couldresultinlargeamountsofradiation exposuretopersonnel.

However,ifoneofthepumpsisdisassembled formaintenance, thecasingweld,internalsurfaces, andflangesurfacewouldbeexamined, inwhichcasereliefwouldnotberequiredfor'thatparticular pump.Conclusions:

Basedontheaboveevaluation, itisconcluded thatcompliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended that:(a)TheLicensee's proposaltoperformthevisualexamination oftheinternalsurfaces(VT-3)andtheflangesurface(VT-I)ofthepumps,whenevertheyaremadeaccessible duetodisassembly formaintenance, shouldbeaccepted, providedthattheCode-r'equired volumetric examination ofthepumpcasingweldisalsoperformed; and(b)Reliefshouldbegrantedattheendoftheintervalifoneofthesubjectpumps,forwhichthevisualandvolumetric examinations arerequired, hasnotbeendisassembled formaintenance.

3.1.6:ValvePressureBoundar(Noreliefrequests) 3.1.7General(Noreliefrequests) 3.2Class2Comonents3.2.1PressureVessels(Noreliefrequests) 3.2.2~Piin3.2.2.1euestforRelief2Examination CateorC-FternC5.lassPie-to-Flued HeadWeldsCodeReuirement:

SectionXI,TableIWC-2500-1, Examinat)on CategoryC-F,ItemC5.21requiresa100%%usurfaceandvolumetric examination ofthepressureretaining circumferential weldsinClass2piping,greaterthanI/2inchnominalwallthickness, asdefinedbyFigureIWC-2500-7.

icensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required surfaceandvolumetric examination ofpipe-to-flued headweld01SintheFeedwater SystemandLfluedhead-to-pipe weld12FintheMainSteamSystem.Licensee's ProosedAlternative xamination:

TheLicenseestatesthat,inlieuoftherequirements ofSectionXI,thefirstaccessible weldoutsideeachpenetration willbeexaminedwiththeCode-required surfaceandvolumetric examinations.

Thisproposedalternative examination wasusedinthefirst10-yearinterval.

Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesubjectweldsaretotallyenclosedwithinapenetration sleeve,andareinaccessible forexamination.

Sincetheinaccessible pipe-to-flued headweldthickness issubstantially heavierthanthe.proposedalternative weldtobeexaminedandtheyareexposedtothesameenvironment, theoveralllevelofplantsafetywillnotbereducedbyperforming thealternative examination.

l4 J'valuation:

TheLicensee's submittal hasbeenreviewed, including thedrawingwhichshowstheexa'mination obstructions.

TheCode-required surfaceandvolumetric examinations ofthesubjectweldsareimpractical toperformbecausetheseweldsarelocatedinsidecontainment penetrations andarecompletely inaccessible.

Becausethefirstaccessible weldoutsideeachpenetration willreceivetheCode-required surfaceandvolumetric examinations, samplesizeismaintained.

Thesubjectweldscanonlybeexaminedbyinspecting forevidenceofleakageduringsystemhydrostatic tests.Althoughthesecontainment penetration weldscannotbevieweddirectly, theLicenseeshouldconductvisualexaminations forevidenceofleakageinthevicinityoftheseweldswhenthehydrostatic pressuretestsareperformed.

Bd'hb1i,<<ilddthattheCode-required surfaceandvolumetric examinations ofthesubjectweldsareimpractical toperformandthattheproposedalternative examination ensuresanacceptable levelofinservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested providedthatvisualexaminations areperformed onthetwocontainment penetration assemblies when'eakageandhydrostatic testsareconducted inaccordance withIWA-5000.

3.2.2.2ReuestforRelief3Examination CateorC-FItemC5.21lassPie-to-Flued HeadWeldsCodeReuirement; SectionXI,TableIWC-2500-1, Examination CategoryC-F,ItemC5.21requiresa100/surfaceandvolumetric examination ofthepressureretaining circumferentia'.

weldsinClass2piping,greaterthanI/2inchnominalwallthickness, asdefinedbyFigureIWC-2500-7.

10 icensee's CodeReliefRevest:Reliefisrequested fromperforming theCode-required surfaceandvolumetric examinations ofpipe-to-flued headweldIOFintheMainSteamSystem.icensee's ProosedAlternative xamination:

TheLicenseestatesthat,inlieuoftherequirements ofSectionXI,oneadjacentweldinonemainsteamline.willbeexaminedwiththeCode-required surfaceandvolumetric examinations.

Thisproposedalternative examination wasusedinthefirst10-yearinterval.

Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesubjectweldisinaccessible duetothelargepipewhiprestraint whichsurrounds theweld.andadjacentarea.Volumetric examination byultrasonics isimpractical becausetheweldcannotbereach'edforpositioning andhandlingthetransducer, andradiography isimpractical becausetheexposurewouldhavetobemadethroughtherestraint.

Surfaceexamination isimpractical becausetheweldisnotreadilyaccessible forapplication andremovalofpenetrant ormanipulation ofmagneticparticleequipment.

Removalofthepipewhiprestraints wouldrequiretorchcutting2400and2700-lbsectionsthataresupported fromabove.Theserviceconditions towhichanadjacentweldisexposedshouldbenearlyidentical tothatoftheinaccessible weld,ardthustheoveralllevelofplantsafetywillnotbereducedbyperforming theproposedalternative examination.

Evaluation:

TheLicensee's submittal hasbeenreviewed, including thedrawingwhichshowstheexamination obstructions.

TheCode-required surfaceandvolumetric examinations ofthesubjectweldareimpractical becausethisweld(andadjacentarea)issurrounded byalargewhiprestraint andiscompletely inaccessible.

BecauseanadjacentweldwillreceivetheCode-required surfaceandvolumetric

examinations, samplesizeismaintained.

Thesubjectweldcanbeexaminedonlybyinspecting forevidenceofleakageduringsystemhydrostatic tests.Althoughthiscontainment penetration weldcannotbevieweddirectly,.

theLicenseecouldconductvisualexaminations forevidenceofleakageinthevicinityofthisweldwhenthehydrostatic pressuretestsareperformed.

d1<<:Bddd1d,dd iddthattheCode-required surfaceandvolumetric examinations ofthesubjectweldareimpractical andthattheproposedalternative examination ensuresanacceptable levelofinservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested providedthatvisualexaminations forevidenceofleakageareperformed inthevicinityofthecoveredweldwhentheCode-required leakageandhydrostatic testsareconducted.

3.2.3~Pums(Noreliefrequests) 3.2.4Valves(Nureliefrequests)

'.2d5General(Noreliefrequests) 3.3Class3Comonents(Noreliefrequests) 3.4PressureTests3.4.1Class1SstemPressure.

Tests3.4.1.1RevestforReliefP2Partof2SystemHdrostatic TestofClass]PiinaintheChemicalandVolumeControlSstemNOTE;Seetheevaluation ofthisrequestforreliefinSection3,4.4.1.12 I

3.4.1;2RvestforReliefP4SstemHdrstaticTestofClas1iinintheEmerencCoreCoolinSstemCodeReuirement:

SectionXI,ArticleIWB-5000requiresthat,foranoperating pressureof2235psig,theClass1pipingbetestedatapressureof2458psig.icensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofthefollowing Class1pipingsectionsintheEmergency CoreCoolingSystemattherequiredtestpressureof2458psig:ValvesIH0-51,SI-142LI-BoronInjection LoopNo.1ValvesIH0-52,SI-142L2-BoronInjection LoopNo.2ValvesIH0-53,SI-142L3-BoronInjection LoopNo.3ValvesIH0-54,SI-142L4-BoronInjection LoopNo.4icensee's ProosedAlternative Examination:

TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.Thetestwillbeperformed duringHode3withtheRCSpressureat2280psigandtemperature greaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockcheckvalvesSI-142L1throughL4closed;therefore, maximumpressurewillbe2280psig.Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesectionsofthepipingsystemupstreamofcheckvalvesSI-142L1-through L4cannotbetestedatapressureof2458psigwithoutmakingtemporary modifications (blocking thevalvedisc)tokeepthecheckvalvesclosed.Sincethepipingsectionsarepartoftheprimarysystem,plantpersonnel willbesubjected tosubstantial radiation exposureandcontamination inordertocarryoutsuchmodifications forthetest..Theproposedtestpressureishigherthanthe2235psignominaloperating pressureinthesubjectsectionsofpiping,eachapproximately 44to55feetlong.13

/valuation:

Becausethesystem'sdesigndoesnotpermitpressurizing thesectionsofpipingtotheCode-required pressurewithoutextensive temporary valvemodifications, the..Codetestpressurerequirement isimpractical.

Thevisualinspection ofthepipingduringthepressuretestaswellasthevolumetric examination requirements forselectedweldsinthesystemwillprovideadequateassurance ofthecontinued structural integrity ofthepiping.Thedifference intherequiredtestpressureandthatproposedbytheLicenseedoesnotwarrantimposition oftheCoderequirement.

==

Conclusions:==

Basedontheaboveevaluation, itisconcluded thattheCoderequirements areimpractical andthatthealternative testproposedbytheLicensee, inconjunction withtheotherNDErequirements, willensureanacceptable levelofinservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthe'evelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested.

3.4.2Class2SstemPressureTests3.4.2.1ReuestforReliefPSstemHdrostatic TestofClass2PiinointheEmerencCoreCoolinSstemCodeReuirement:

SectionXI,ArticleIWC-5000requiresthat,forasystemdesignpressureof2485psig,theClass2pipingbetestedatapressureof2733psig.icensee's CodeReliefReuet:Reliefisrequested fromperforming theCode-required hydrostatic testofthefollowing Class2pipingsectionsintheEmergency CoreCoolingSystemattherequiredtestpressureof2733psig:(a)Accumulator No.1Discharge Piping-ValvesIH0-110,SI-166-1, IRV-115,andSI-168-1; 14 lg~,'UJq'l (b)Accumulator No.2Discharge Piping-ValvesIH0-120,SI-166-2, IRV-125,andSI-168-2; (c)Accumulator No.3Discharge Piping-ValvesIH0-130,SI-166-3, IRV-135,andSl-168-3; and(d)Accumulator No.4Discharge Piping-ValvesIH0-140,SI-166-4, IRV-145,andSI-168-4.

icensee's ProosedAlternative Examination:

TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psig.Thetestwillbeperformed during.Mode3withtheRCSpressure.

at2280psigandtemperature greaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalves(SI-166-1,

-2,-3,and-4)closed,therefore, limitingmaximumpressureto2280psig.Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesectionofpipingupstreamofcheckvalvesSI-166-1through4cannotbetestedatapressureof2733psigwithoutmakingextensive temporary modifications tokeepthevalvesclosed.Themodifications wouldrequire:(a)disas'sembly ofthevalves,(b)weldingoftemporary blocks(onthedownstream side)insidethevalvebodiestoholda"jackscrew"typearrangement tokeepthevalveclosed,(c)removalofthetemporary blockingdevicesfromthevalvesaftertesting,and(d)performing necessary nondestructive testingtoensuretheintegrity ofthevalvebodiesbeforereturning themtoservice.Thepipingdownstream ofthesevalvesispartoftheRHRSystemandcarriesradioactive fluidduringnormaloperation.

Therefore, plantpersonnel willbesubjected tosubstantial radiation exposureandradioactive contamination inordertocarry.outany.modifications forthetest.Evaluation:

Thesystem'sdesigndoesnotpermitpressurizing thesectionsofpipingtotheCode-required pressurewithouteitherextensive temporary valvemodifications oroverpressurizing theClass1sectionsofconnected piping.15

\I~i Becauseofthis,thetestpressurerequirement isimpractical toattain.Thesectionsofpipingwillbesubjected toa'ressure slightlyhigherthannormaloperating pressureandatatemperature higherthanthatrequired, bytheCode.Thevisualinspection ofthepipingduringthepressuretestaswellasthevolumetric examination requirements forselectedweldsinthesystemwill'provide adequateassurance ofthecontinued structural integrity ofthepiping.Conclusions:

Basedontheaboveevaluation, itisconcluded thattheCoderequirements areimpractical andthatthealternative testproposedbytheLicensee, inconjunction withtheotherNDErequirements, willensureanacceptable levelofinservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested.

3.4.2.2ReuestforReliefP2Part2of2SstemHdrostatic TestoFClass2PiinintheChemicaland'olume ControlSstemNOTE:Seetheevaluation ofthisrequestforreliefinSection3.4.4.1.3.4.2.3RevestforReliefP3SstmHdrostatic TestofClass2PiinintheChemicalandVolumControlSstemCodeReuirement:

SectionXI,ArticleIMC-5000requiresthat,foradesignpressureof2485psig,theClass2pipingbehydrostatically pressuretestedatapressureof3106psig.Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic pressuretestofthe16 aLetdownLines(ValvesQRV-112,QRV-160,QRV-161,andQRV-162)intheChemicalandVolumeControlSystem(ReactorLetdownandCharging) attherequiredtestpressureof3106psig.icensee's ProosedAlternative xamination:

TheLicenseestatesthatthesubjectsectionofpipingwillbetestedatapressureof2280psigduringNode3usingRCSpressure.

ValvesQRV-illandQRV-112willbeopenedwithQRV-160;QRV-161,andQRV-162closed.Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesubjectsectionofpipingcannotbetestedatapressureof3106psigwithout(a)usingaspareone-inchpluggedconnection inUnit1pipinglocateddownstream ofinstrument QTA-160intheregenerative.

heatexchanger room,whichisconsidered ahighradiation area,and(b)modification, sincenotestconnection existsinUnit2piping.Thispipingcarriesradioactive fluidduringnormaloperation; therefore, plantpersonnel willbesubjecttosubstantial radiation exposureandcontamination

',nordertomodify/add atestconnection.

Asanalternative, extending thetestboundarytoQCR-301wasconsidered.

ThiswouldinvolveusingQPX-301locatedonthedownstream pipingoutsidethe.regenerative heatexchanger roomasatestconnection.

Thisalternative wasalsorejectedbecausevalveQCR-301andtheflangeboltedtotheinletflangeofsafetyvalveSV-051areinthe600-lbclasswhichcannotwithstand theabovetestpressure.

~valuatior:

Thesystem'sdesigndidnotincludeatestconnection toallowpressurizing totheCodetestpressureorpipiengandvalvesratedappropriately toaccommodate therequiredpressureatotherisolation pointsinthesystem.InordertocomplywiththeCoderequirement, theLicenseewouldhavetoinstallatestconnection oroverpressurize lowerratedpipingandcomponents.

Therefore, theCoderequirement is17 impractical.

TheLicensee's proposedalternative testwillsubjectthepipingtoapressureslightlyhigherthannormaloperating pressure.

Therequiredvisualinspection ofthepipingatthetestpressureandotherrequiredNDEoftheweldsinthesystemwillprovideadequateassurance ofthecontinued structural integrity ofthepiping.Conclusions:

Basedontheaboveevaluation, itisconcluded thattheCoderequirements areimpractical andthatthealternative testproposedbytheLicensee, inconjunction withtheotherNOErequirements, willensureanacceptable levelofinservice structural integrity.

Compliance withthespecific.

requirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested.

3.4.2.4RevestforReliefP5SystemHdrostatic TestofClass2PiinintheAuxiliarSratoReactorCoolantSstemandPressurizer andChemicalandVolumeControlSstemCodeReuirement:

SectionXI,ArticleIMC-5000requiresthat,foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.Licensee's CodeReliefRevest:Reliefisrequested fromperforming theCode-required hydrostatic pressuretestoftheClass2pipingsectionsdescribed bythefollowing pipingboundaries attherequiredtestpressureof3419psig:ValvesQRV-51CS-326ValvesQRY-61CS-322ValvesQRV-62.Licensee's ProosedAlternative Examination:

TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2800psigusinga"stemblock"tokeepvalveQRV-51closed.

+"IlegE<.

icensee's BasisforReuestinRelief:TheLicenseestatesthat,inordertoperformthepressuretestofthesesectionsofpiping,valveHARV-51hastobeusedasanisolation valve.This1500-lbclass,air-operated controlvalveisdesignedtowithstand testpressureof3419psigintheopenposition.

However,itcannotbeusedasanisolation valvebecauseitwasdesignedforadifferential pressureof1200psig.Thevalvecannotbekeptclosedduringpressuretestingat3419psigwithoutextensive, temporary rigging.Themodification wouldrequire:(a)removaloftheairoperatorandinstallation ofa"strongback"tokeepthevalveclosedduringtesting,(b)removalofthe"strongback"afterthetesting,and(c)reinstallation oftheairoperatoronthevalveandrestoring thevalvetooperablecondition beforereturning toservice.Thevalveislocatedinsidetheregenerative heatexchanger room,whichisaveryhighradiation areaandplantpersonnel wouldbesubjected toradiation exposureoffivetosevenman-rems.

Asanalternative, thepossibility ofusingafreezesealplugdownstream ofHARV-51wasconsidered.

Thiswouldinvolveextensive workingtimeclosetothepressurizer sprayvalves,whichareinahighradiation area.Thisalternative was",ejectedbeauseplantpersonnel wouldbesubjecttoanevenhigherradiation eXposureof8.5man-remsduringformation, monitoring, andremovalofthefreezesealplug.Evaluation:

TheabovepipingsystemcannotbetestedtoASHECoderequirements withoutmodifying thesystemand/orexposingpersonnel tolargeamountsofradiation.

TheproposedtestCpressureishigherthanthenormaloperating pressureof2235psigintheapproximately 30-foot-long sectionofpipingforwhichCodereliefisrequested.

Theproposedtes+pressureis25llabovethenormaloperating pressure.

Thus,thetestprovidesreasonable assurance oftheintegrity ofthepiping.19 Clli:Bdthbii,<<<*1ddthattheCoderequirements areimpractical andthatthealternative testproposedbytheLicensee, inconjunction with.theotherNDErequirements, willensure*anacceptable levelofinservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityaridsafety.Therefore, itisrecommended thatreliefbegrantedasrequested.

3.4.3Class3SstemPressureTests(Noreliefrequests) 3.4.4General3.4.4.1ReouestforReliefP2SstemMdrostatic TestoFClass1and2PiinintheChemicalandVolumeControlSstemCodeReuirement:

SectionXI,ArticleIWB-5000requiresthat,foranoperating pressureof2235psig,theClass1pipingbetestedatapressureof2458psig.SectionXI,ArticleIWC-5000requiresthat,foradesignpressureof2735psig,theClass2pipingbetestedatapressureof3419psig.icensee's CodeReliefRevest:Reliefisrequested fromperforming theCode-required hydrostatic testofthefollowing Class1and2pipingsectionsintheChemicalandVolumeControlSystem(Reactor'Letdown andCharging) attheCode-required testpressures of2458and3419psig:(a)Class1piping:Two-inchAuxiliary SprayPiping-ValvesHARV-SlandCS-325;(b)Class2piping:NormalChargingLoop4ColdLeg-ValvesgRY-62,CS-328L4, CS-326,andCS-327;20 (c)Class2piping:Alternate ChargingLine'oLoop1ColdLeg-ValvesHARV-61andCS-328L1.

icensee's ProosedAlternative Examination:

TheLicenseestatesthatthesubjectsectionsofpipingwillbetestedatapressureof2280psigatatemperature above100'F.Thetestwillbeperformed duringMode3withtheReactorCoolantSystem(RCS)pressureat2280psigandtemperature greaterthanorequalto500'F.TheRCSpressurewillbeusedtoblockthecheckvalvesCS-329L1, CS-329L4, andCS-325closed;therefore, maximumpressurewillbe2280psig.Licensee's BasisforReuestinRelief:TheLicenseestatesthatcheckvalvesCS-328L1, CS-328L4, andCS-325arelocatedonthecharginglinesto'heRCSSystem.Thesevalvesmustbedisassembled andtemporarily modifiedtoblockthemclosedinordertoperformtherequiredhydrostatic tests,andplant"personnel willbeexposedtohighradiation andradioactive contamination duringthemodification.

Theproposedtestpressureishigherthan2235psignominaloperating pressureinthesectionofpipingbetween23and115feetlongforwhich'elief isrequested.

fvaluation:

Thesystem'sdesigndoesnotpermitpressurizing thesectionsofpipingtotheCode-required pressurewithouteitherextensive temporary valvemodifications oroverpressurizing theClass1sectionsofconnected piping.Becauseofthis,theCode-required testpressureisimpractical toattain.Thesectionsofpipingwillbesubjected toapressureslightlyhigherthannormaloperating pressureandatatemperature higherthanthatrequiredbytheCode.Thevisual,i'nspection ofthepipingduringthepressuretest,aswellasthevolumetric examination requirements forselectedweldsinthesystems,willprovideadequateassurance ofthecontinued structural integrity ofthepiping.21 j

==

Conclusions:==

Basedontheaboveevaluation, itisconcluded thattheCoderequirements areimpractical andthatthealternative testproposedbytheLicensee, inconjunction withtheotherNDErequirements, willensureanacceptable levelof'inservice structural integrity.

Compliance withthespecificrequirements ofSectionXIwouldresultinhardshiporunusualdifficulties withoutacompensating increaseinthelevelofqualityandsafety.Therefore, itisrecommended thatreliefbegrantedasrequested.

3.5Genera1(Noreliefrequests) 22 gPIQ 4.CONCLUSION Pursuantto10CFR50.55a(g)(6),

ithasbeendetermined thatcertainSectionXIrequiredinservice examinations areimpractical toperform.Inthesecases,theLicenseehasdemonstrated thateithertheproposedalternatives wouldprovideanacceptable levelofqualityandsafetyorthatcompliance withtherequirements wouldresultinhardships orunusual\difficulties withoutacompensating increaseinthelevelof.quality'.and safety.Thistechnical evaluation reporthasnotidentified anypractical method'bywhichtheexistingDonaldC.CookNuclearPlant,Unit1,canmeetallthespecificinservice inspection requirements ofSectionXIoftheASHECode.Requiring compliance withalltheexactSectionXIrequiredinspections wouldrequireredesignofasignificant numberofplantsystems,sufficient replacement components tobeobtained, installation ofthenewcomponents, andabaselineexamination ofthesecomponents.

Evenaftertheredesignefforts,completecompliance withtheSectionXIexamination requirements probablycouldnotbeachieved.

Therefore, itisconcluded thatthepublicinterestisnotservedbyimposinacertainprovisions ofSectionXIoftheASthECodethathavebeendetermined tobeimpractical.

Pursuantto10CFR50.55a(g)(6),

reliefisallowedfromtheserequiremerts whichareimpractical toimplement.

Thedevelopment ofneworimprovedexamination techniques willcontiruetobemonitored.

Asimprovements intheseareasareachieved, theNRCmayrequirethatthesetechniques beincorporated inthenextinspection intervalISIprogramplanexamination requirements.

BasedonthereviewoftheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection ProgramPlan,Change1,datedDecember1985,theLicensee's responses totheNRC'sRequestforAdditional Information, andtherecommendations forgrantingrelieffromtheISIexamination requirements thathavebeendetermined tobeimpractical, ithasbeenconcluded thattheDonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection ProgramPlan,Change1,datedDecember1965,isacceptabl andincompliance with10CFR50.55a(g)(4).

Ih) 5.REFERENCES 1.CodeofFederalRegulations, Volume10;Part50.2.AmericanSocietyofHechanical Engineers BoilerandPressureVesselCode,SectionXI,Division1:1983EditionthroughSummer1983Addenda1974EditionthroughSummer1975Addenda3.DonaldC.CookNuclearPlant,Unit1,Second10-YearIntervalInservice Inspection ProgramPlan,Change1,datedDecember1985.4.NUREG-0800, StandardReviewPlans,Section5.2.4,"ReactorCoolantBoundaryInservice Inspection andTesting,"

andSection6.6,"Inservice Inspection ofClass2and3Components,"

July1981.5.Letter,February2,1987,B.J.Youngblood (NRC)toJ.E.Dolan[IndianaandHichiganElectricCompany(IHEC)],"RequestforAdditional Information forReviewoftheDonaldC.CookNuclearPlant,Units1and2,Second10-YearIntervalInservice Inspection ProgramPlans,Change1,datedDecember1985."6.Letter,April10,1987,H.P.Alexich(IHEC)toH.R.Denton(NRC),"Response toRequestforAdditional Information ontheISISecond10-Year'nterval MeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."7.Letter,June1,1987,M.P.Alexich(IHEC)toT.E.Hurley(NRC),"Response toRequestfor.Additional Information ontheISISecond10-YearIntervalWeldProgramfortheDonaldC.CookNuclearPlant,Units1and2."8.Letter,January15,1986,B.;J.Youngblood (NRC)toJ.E.Dolan(IHEC),"NRCApprovalforIndianaandHichiganElectricCompanytoUseASHECodeSectionXI,1983EditionwithSummer1983AddendafortheISI/ISTProgramfortheDonaldC.CookNuclearPlant,Units1and2."24 9..Regulatory Guide1.150,"Ultrasonic TestingofReactorVesselWeldsDuringPreservice andInservice Examinations,"

Revision1,datedFebruary1983.10.Regulatory Guide1.14,"ReactorCoolantPumpFlywheelIntegrity,"

Revision1,datedAugust'1975.25 1E'trEf:%(

711Cf01M~I5Ski11CUIIGT,STOI,STGTBIBUOGRAPHIC DATASHEETEGG-SD-7799 VLIIVCLEA11EOVLATOAV COMMISSIQM I15fOATIIVMSE1IAIVfkkfkfTIDCkkfVMflf,el~iSEEIMSTAUCTIQIISOM TIIE1EVE1555.TITLfAIIQ5VSTITLETechnical Evaluation ReportontheSecond10-YearIntervalInservice Inspection ProgramPlan:IndianaandHichiganElectricCo.,DonaldC.CookNuclearPlant,Unit1,DocketNumber50-3155LEAVE~LAIIILkDATE1EfOATCOMfLETED TEA1MOIeTM5AVT+01ISI July1988~D*TE15fo1TISSVEOB.W.Brown,J.D.HudlinTff1fQAMIMGOAGAIIIZATIOM MAMEAMDMAILIUGAOD155$llkfMffjMCkkrlEG&GIdaho,Inc.P.0.Box1625IdahoFalls,ID83415-2209 MOUTHJuly~,t1QIEGTITASA.'ITQAA vMITMMM4515fIII01G1AIITMVME51TEA1198810SfOIISOIIIIIG QAGAIIIZATIOII IIAV5AMOUAILIUGAQOIIESSllkf~ZMCkff1Haterials Engineering BranchOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555ISSVffLEMEVTkflv MOTE5FIN-D6022 (Propre'ct 5)II~TvfEOf15>OATTechnical

~.f5fIIQDCOVEfIEDIlkMVAM<<MM1$AESTAACTIowaorranThisreportpresentstheresultsoftheevaluation oftheDonaldC.CookNuclearPl,ant,Unit1,Second10-YearIntervalInservice Inspection (ISI)ProgramPlan,Change1,datedDecember1985,including therequestsforrelieffromtheAmericanSocietyofHechanical Engineers (ASHE)BoilerandPressureVesselCodeSect'ionXIrequirements whichtheLicenseehasdetermined tobeimpractical.

InSection2ofthisreport,theISIProgramPlanisevaluated for(a)compliance withtheappropriate edition/addenda ofSectionXI,(b)acceptability oftheexamination sample,(c)exclusion

criteria, and(d)compliance withISI-related commitments identified duringtheNuclearRegulatory Commission's (NRC)previouspreservice inspection (PSI)andISIreviews.TherequestsforrelieffromtheASHE'Code requirements whichtheLicenseehasdetermined tobeimpractical forthefirst10-yearinspection intervalareevaluated inSection3ofthisreport.I~OQCLIMEMT AMALT515~KETIVQ"DSIGESCAPTO15

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f4QEOTEAMSUnlimited I~5ECVAITVCLASSIfICATIDM Un'ssifiedjfkvIwortiUnclassified 111VMSfkGIkkGESIffklCE I