L-MT-12-018, Fifth Ten-Year Inservice Inspection Plan

Fifth Ten-Year Inservice Inspection Plan

ML12060A298
Person / Time
Site:	Monticello
Issue date:	02/28/2012
From:	O'Connor T Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-12-018
Download: ML12060A298 (79)

Text

@ Xcel EnergyB February 28,2012 Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 L-MT-12-018 10 CFR 50.55a(g)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22

Subject:

Fifth Ten-Year lnservice Inspection Plan Pursuant to 10 CFR 50.55a(g)(5)(i), Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy, the licensee for the Monticello Nuclear Generating Plant (MNGP), submits its fifth ten-year interval lnservice lnspection (ISI) Program Plan (enclosure). This IS1 Plan for the fifth ten-year interval begins September 1, 2012, and, pursuant to 10 CFR 50.55a(g)(4)(ii) and 10 CFR 50,55a(b)(2), will comply with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with the 2008 Addenda and 10 CFR 50.55a.

Should you have questions regarding this letter, please contact Mr. Randy Rippy at (61 2) 330-691 1.

Summarv of Commitments

/'

ew commitments and no revisions to existing commitments.

Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure

Document Control Desk Page 2 cc:

Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC

ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT INSERVICE INSPECTION (ISI) PLAN REVISION 0 FIFTH TEN-YEAR INSPECTION INTERVAL 76 pages follow

Monticello Nuclear Generating Plant sth Interval lnservice Inspection Plan XCEL Energy, Inc.

NSP-Minnesota 414 Nicollet Mall Minneapolis, M N 55401 Monticello Nuclear Generating Plant lnservice lnspection (ISI) Plan Revision 0 Fifth Ten-Year lnspection Interval September 1,2012 through May 31,2022 Commercial Service Date June 30,1971 Monticello Nuclear Generating Plant 2807 West Highway 75 Monticello, Minnesota 55362 Rev. 0 Page i See PCR-01319580 for Approvals

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RECORDOFREVISIONS Page Rev.*

0

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RECORDOFREVISIONS SummaryofChanges,PlanRevision0 ThisistheinitialissueoftheFifthIntervalInserviceInspection(ISI)Plan

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Contents

1.0 INTRODUCTION

.................................................................................................................................1 2.0 BackgroundforPlan/ScheduleDevelopment...................................................................................6 3.0 ApplicationCriteriaandCodeCompliance.......................................................................................6 4.0 ExaminationPersonnel/Procedures...............................................................................................16 5.0 ReportingofAssociatedSectionXIPrograms.................................................................................16 6.0 AugmentedandOwnerPrograms..................................................................................................16 7.0 LicenseRenewalAgingManagementPlansandCommitments.....................................................20 8.0 SourceDocuments..........................................................................................................................22

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Background:

10CFR50.55arequiresthataninserviceinspection(ISI)programbedevelopedat10year(120month) intervals.TheISIProgramispreparedandmaintainedbyXcelEnergyInc.fortheMonticelloNuclear GeneratingPlant.ThisprogramhasbeendevelopedtocomplywiththeAmericanSocietyofMechanical Engineers (ASME)Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components and implementstherequirementsofUpdatedSafetyAnalysisReport(USAR)13.4.610CFR50.55aInservice InspectionandTestingPrograms.TheInserviceTesting(IST)Programismaintainedseparatelyfrom thisprogramandissubmittedunderseparatecover.TheContainmentInspectionProgram,asallowed by10CFR50.55a(g)(6)(ii)(B),isnotsubmitted,itisavailableattheplantsiteforauditandreview.The SnubberProgramandBoilingWaterReactorInternalsProject(BWRVIP)Programarealsomaintained separatelyfromthisplan.Thisplanisdevelopedtoensurethefollowing:

1) ConformancetoTitle10,Section50.55aoftheCodeofFederalRegulations(10CFR50.55a)

2) Conformancetothe2007Editionwiththe2008AddendaofSectionXIoftheAmericanSociety ofMechanicalEngineers(ASME)BoilerandPressureVesselCode

3) ConformancetotheXcelEnergyInc.CorporatePoliciesandProcedures

4) TheproperASMESectionXICoderequiredexaminations,tests,andadministrativeprocedures areimplemented

5) The proper ASME Code request for alternatives and relief requests are submitted to and approvedbytheregulatoryauthority

6) Theproperexamination,testandrepair/replacementrecordsandreportsaremaintainedand submitted Thefollowingdescriptionsprovidethelocationofthefollowingprograms:

Repair/Replacement Program is contained in Administrative Work Instruction (AWI) 4AWI09.04.03ASMESectionXIRepair/ReplacementProgram.

Containment Inservice Inspection Program is contained in a separate document titled ContainmentInserviceInspectionPlan(IWEPlan)

System Pressure Testing Program is contained in 4 AWI09.04.02 System and Component PressureTestingProgram

SnubberProgramiscontainedinEWI08.02.01SnubberProgram

BoilingWaterReactorVesselInternalsProject(BWRVIP)ProgramiscontainedinEWI08.01.01 BoilingWaterReactorVesselInternalsProjectAdministrativeManual

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TheASMESectionXIInserviceInspectionProgramiscomprisedofsevenparts:ISIPlan(Introduction andSourceDocuments),AppendixACodeCases,AppendixBReliefRequests,AppendixC.1Listof ISI Boundary Drawings (These drawings outline the Quality Group Classifications, (A, B, and C)),

Appendix C.2 List of ISI Isometrics (These drawings delineate the ASME Section XI components or itemsthatareincludedintheexaminationprogram),AppendixDExaminationScheduleTables,and AppendixERiskInformedLivingProgramUpdates.

5thTenYearInterval TheMonticello5thTenYearInserviceInspectionIntervalisthefirstintervalintotheextendedlicense period.Theregulationsin10CFR50.55a(g)(4)establishtheeffectiveASMECodeeditionandaddenda to be used by licensees for performing inservice inspections of components (including supports).

Paragraph50.55a(g)(4)(ii)requirestheuseofthelatesteditionandaddendathathasbeenincorporated by10CFR50.55a(b),oneyearpriortothebeginningofeach120monthISIinterval.Thisisconsidered theCodeofRecord.TheCodeofFederalRegulationineffectoneyearpriortothebeginningoftheFifth Intervalwas76FR36232withaneffectivedateofJuly21,2011.ThisCFRincorporated,byreference, theASMESectionXI,2007Editionwiththe2008Addendainparagraph(b)(2)withconditions.Asstated inthisCFR,the5thTenYearISIProgramisbasedonthe2007Editionwiththe2008Addendaofthe ASME,BoilerandPressureVesselCode,SectionXI.However,thefollowingconditionsarealsorequired tobemetalongwithSectionXI:

1) 10CFR50.55a(b)(2)(xii),theprovisionsinIWA4660,UnderwaterWeldingofSectionXI,1997 Addendathroughthelatesteditionandaddendaincorporatedbyreferenceinparagraph(b)(2) ofthissection,arenotapprovedforuseonirradiatedmaterial.

2) 10CFR50.55a(b)(2)(xiv),licenseesapplyingthe1999Addendathroughthelatesteditionand addenda incorporated by reference in paragraph (b)(2) of this section may use the annual practicerequirementsinVII4240ofAppendixVIIofSectionXIinplaceofthe8hoursofannual handsontrainingprovidedthatthesupplementalpracticeisperformedonmaterialorwelds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. In either case, training used must be completed no earlier than 6 months prior to performingultrasonicexaminationsatalicenseesfacility.

3) 10CFR50.55a(b)(2)((xviii),requiresthatLevelIandIInondestructiveexaminationpersonnelbe recertifiedona3yearintervalinlieuofthe5yearintervalspecifiedinIWA2314(a)&(b)ofthe 1999Addendathroughthelatesteditionandaddendaincorporatedbyreferenceinparagraph (b)(2)ofthissection.

4) 10 CFR 50.55a(b)(2)(xix), does not approve the provisions in IWA4520(b)(2) and IWA4521 allowing the use of ultrasonic examination for radiographic examination specified in the ConstructionCode.

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5) 10 CFR 50.55a(b)(2)(xx)(B), requires that the implementation of IWA4540(a)(2) of the 2002 Addendawhenperformingsystemleakagetestsafterrepair/replacementactivitiesperformed byweldingorbrazingonapressureretainingboundary.

IWA4520(a)(2)ofthe2002Addendastates:Thefollowingrequirementsshallbemet(a)the nondestructiveexaminationmethodologyandacceptancecriteriaofthe1992Editionorlaterof SectionIIIshallbemetpriortoreturntoservice,(b)theOwnersRequirementsshallbemetprior toreturntoservice,and(c)asystemleakagetestshallbeperformedinaccordancewithIWA 5000

6) 10 CFR 50.55a(b)(2)(xxii), prohibits the use of IWA2220 allowing the use of ultrasonic examinationasasurfaceexamination.

7) 10 CFR 50.55a(b)(2)(xxiii), prohibits the use of the provisions found in IWA4461.4.2 for eliminatingmechanicalprocessingofthermallycutsurfaces.

8) 10CFR50.55a(b)(2)(xxv),prohibitstheuseofIWA4340MitigationofDefectsbyModification

9) 10CFR50.55a(b)(2)(xxvi),requirestheuseofthe1998Edition,IWA4540(c)forpressuretesting ofClass1,2,&3mechanicaljointsafterarepair/replacementactivity.

IWA4540(c) of the 1998 Edition states: Mechanical joints made in installation of pressure retainingitemsshallbepressuretestedinaccordancewithIWA5211(a).Mechanicaljointsfor componentconnections,piping,tubing(exceptheatexchangertubing),valves,andfittings,NPS 1andsmaller,areexemptfromthepressuretest.

10) 10CFR50.55a(b)(2)(xxvii),requiresinsulationremovalfrom174PHor410stainlesssteelstuds orboltsagedatatemperaturebelow1100°ForhavingaRockwellMethodChardnessvalue above30,andfromA286stainlesssteelstudsorboltspreloadedto100,000psiorhigheron thosesystemsboratedforcontrollingreactivitywhenconductingpressuretests.ForMonticello thiswouldonlybeapplicabletotheStandbyLiquidControlSystem.

11) 10 CFR 50.55a(b)(2)(xxviii), requires the following when using Nonmandatory Appendix A, A4300(b)(1)Equation(2):

ForR<0,UKIdependsonthecrackdepth(a),andtheflowstress(f).theflowstressis definedbyf=1/2(ys+ult),whereysistheyieldstrengthandultistheultimatetensile strengthinunitsksi(MPa)andaisinunitsin.(mm).For2<R<0andKmax-Kmin<0.8X 1.12f(a),S=1andUKI=Kmax.ForR<2andKmax-Kmin<0.8X1.12f(a),S=1and UKI=(1R)Kmax/3.ForR<0andKmax-Kmin>0.8X1.12f(a),S=1andUKI=Kmax-Kmin.

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12) 10CFR50.55a(b)(xxix),prohibitstheuseofNonmandatoryAppendixRRiskInformed InspectionRequirementsforPipingwithoutpriorapprovalbytheNRC.

TheISIIntervalbeginsonSeptember1,2012andisscheduledtoendonMay31,2022.Theinspection periodsarescheduledasfollows:

1stPeriod:FromSeptember1,2012toAugust31,2015 (3years) 2ndPeriod:FromSeptember1,2015toAugust31,2019 (4years) 3rdPeriod:FromSeptember1,2019toMay31,2022 (2years9months)

InaccordancewithASMESectionXI,IWB2430(c)(3),thatportionofaninspectionintervaldescribedas aninspectionperiodmaybereducedorextendedbyasmuchas1year.Thisadjustmentshallnotalter therequirementsforschedulinginspectionintervals.

4thTenYearInterval TheMonticello4thTenYearInserviceInspectionIntervalwasslightlylessthan120monthstoregaina portionofthetimeperiodassociatedwithanextensionofthe3rdInterval,whichhadbeenextended throughMay31,2003(LMT03004).The3rdIntervaloverlappedthe4thIntervalaspermittedbyIWA 2430(d)(1),(2),(3),and(4).The4thIntervalstartdatewasMay1,2003andendedAugust31,2012(the 3rdperiodwasextendedasallowedbyIWA2430(d)(1)).Fiverefuelingoutageswerescheduledduring the4thInterval.TheCodeofRecordforthe4thIntervalwasthe1995Editionwiththe1996Addendaof ASMESectionXI.

3rdTenYearInterval TheMonticello3rdTenYearInserviceInspectionIntervalcoveredthetimeperiodbetweenJune1,1992 throughMay31,2003.Theintervalwasextended12monthsperIWA2430(LetterstotheNRCinMay 2002andJanuary2003providingnotificationof3rdIntervalextensioninitiallythroughMarch8,2003 (M2002057).TheCodeorRecordforthe3rdIntervalwasthe1986EditionofASMESectionXI.

2ndTenYearInterval The Monticello 2nd TenYear Inservice Inspection Interval covered the time period between June 30, 1981throughMay30,1992.The2ndIntervalwasextendedinaccordancewithIWA2400duetothe RecirculationPipereplacementprojectthatresultedinanelevenmonthshutdownin1984.TheCodeof Recordforthe2ndIntervalwasthe1977EditionwiththeSummer1978AddendaofASMESectionXI.

1stTenYearInterval TheMonticello1stTenYearInspectionIntervalcoveredtheperiodbetweenJune30,1971throughJune 29,1981.Atthebeginningofthe1stInterval,therulesspecifiedin10CFR50.55aaddressedonlythose componentswithinthereactorcoolantpressureboundary(RCPB)andrequiredlicenseestoupdatethe EditionandAddendaofASMECode,SectionXIeachInspectionPeriod(i.e.,every40months).In1976, 10CFR50.55awasamendedtorequireplantswithoperatinglicensestoexamineandtestcomponents

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thatwereclassifiedasASMECodeClass2and3.Thisprovisionoftheregulationwastoapplyatthe startoftheregular40monthperiod.In1979,10CFR50.55awasagainamendedtoendorsethe1978 Edition with the Summer 1978 Addenda of ASME Code,Section XI. This amendment changed the requirementforupdatingoftheISIProgramtoonceevery120months.Becauseoftherulesinaffect duringthe1stInterval,MNGPwascommittedtothreeeditionsoftheASMECode,SectionXI.These editionswerethe(1)1971EditionwiththeSummer1972Addenda,(2)1971EditionwiththeSummer 1973Addenda,and(3)1974EditionwiththeSummer1975Addenda.

ComponentSelection:

With the exception of Class 1 and 2 piping welds, components were selected and scheduled using criteriainthe2007Editionwiththe2008AddendaofASMESectionXIand10CFR50.55a(g),except wherereliefhasbeengrantedbytheNuclearRegulatoryCommission(NRC).

SelectionofClass1and2pipingweldsinASMECategoriesBF,BJ,CF1andCF2arebasedonCode CaseN716AlternativePipingClassificationandExaminationRequirements.

CodeEditionSummary:

Thecodeeditionsimplementedinthe5thIntervalISIProgramaresummarizedbelow:

Class1(QualityGroupA) 2007Editionwiththe2008Addenda Class1PipingWelds(QualityGroupA)

CodeCaseN716(ReliefRequestRR003)

Class2(QualityGroupB) 2007Editionwiththe2008Addenda Class2PipingWelds(QualityGroupB)

CodeCaseN716(ReliefRequestRR003)

Class3(QualityGroupC) 2007Editionwiththe2008Addenda MC(MetalContainment) 2001Editionwiththe2003Addenda MandatoryAppendixVIII 2001EditionuntilJanuary21,2013atwhichtime the2007Editionwiththe2008Addendawillbe implemented 10CFR50.55a(g)(4)(ii)allowsupto18months delaytoupdatetheAppendixVIIIprogram PressureTestingProgramforClass1,2,and3 2007Editionwiththe2008Addenda PressureTestingProgramforClassMC 2001Editionwiththe2003Addenda PressureTestingProgramforRepair/Replacements 2007Editionwiththe2008Addenda 10CFR50.55a(b)(2)(xx)(B)specifiestheuseofthe 2002Addenda,IWA4540(a)(2)after repair/replacementactivitiesperformedby weldingorbrazingonapressureboundary PressureTestingClass1,2,&3MechanicalJoints 10CFR50.55a(b)(2)(xxvi)specifiestheuseofthe 1998Edition,IWA4540(c)aftera repair/replacementactivity Repair/ReplacementProgram 2007Editionwiththe2008Addenda (Ref.RR007forClassMCComponents)

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2.0 BackgroundforPlan/ScheduleDevelopment The examination plan and schedule were developed from ASME Code requirements, RiskInformed Methodology,individualcomponentexaminationhistoryandplantschedulingneedssuchasoptimizing insulationremovalandscaffoldingneeds.Duringthe2ndInterval,asubstantialnumberofcomponent replacementsandalterationsweremade(e.g.therecirculationpipingreplacement).Theintentofthe 5thIntervalistobeconsistentwiththepreviousintervals,totheextentpractical.SinceClass1(Category BFandBJ)andClass2(CategoryCF1andCF2)pipingweldswereexaminedpertheRIISIPlaninthe 4thInterval,thecorrelationistothe4thIntervalonly.

3.0 ApplicationCriteriaandCodeCompliance ASMESectionXI ThefollowingprovidesasummaryoftheapplicationofASMECode,SectionXI,2007Editionwiththe 2008AddendatotheMonticelloNuclearGeneratingPlant,TenYearProgramfortheFifthInspection Interval. The application and distribution of examinations for this interval is based upon the requirementsasdefinedinIWB2411,IWC2411,IWD2411,andIWF2410ofSectionXI.AppendixD containstheexaminationschedulefortheFifthIntervalandissummarizedbyASMECategoryandItem Number.

EXAMINATIONCATEGORYBA,PRESSURERETAININGWELDSINREACTORVESSEL Reactor vessel examinations are scheduled on the reactor pressure vessel to meet the alternative requirementsofreliefrequestRR001ExtensionofPermanentRelieffromVolumetricExaminationof ReactorPressureVesselCircumferentialShellWeldsfortheRenewedOperatingLicenseTerm.This alternative,previouslyapprovedforpermanentuseunder4thInterval10CFR50.55aRequestNo.17,is basedontheBoilingWaterReactorVesselInternalsProject(BWRVIP)reportBWRVIP05BWRReactor PressureVesselShellWeldInspectionRecommendations,andBWRVIP74,BWRVesselandInternals Project,BWRReactorPressureVesselInspectionandEvaluationGuidelinesforLicenseRenewal.This alternativeprovisionissummarizedbelow:

The examination requirements of ASME Code Section XI, Table IWB25001, Examination CategoryBA,ItemNo.B1.12,fortheRPVlongitudinalshellweldswillbeperformedasrequired totheextentpossible.

The examination requirements for Item No. B1.11, RPV circumferential shell welds will be limitedtothesegmentoftheweldthatintersectswiththelongitudinalweld.

TheexaminationrequirementforcircumferentialweldVCBB1,inlieuoftheintersectionwith thelongitudinalweldapproximately2to3percentoftheweldatanaccessiblelocationwillbe completed.

The examination may be performed from either the internal inside diameter surface or the externaloutsidediametersurface.

ExaminationofallremainingportionsoftheRPVcircumferentialweldswillbedeferredthrough therenewedoperatinglicensetermasapprovedbyRequestforAlternativeRR001.

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ExaminationswillbecompletedinaccordancewithAppendixVIIIofthe2007Editionwiththe 2008Addenda.

EXAMINATION CATEGORY BB, PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS ThisexaminationcategorydoesnotapplytotheMonticelloNuclearGeneratingPlant

EXAMINATIONCATEGORYBD,FULLPENETRATIONWELDEDNOZZLESINVESSELS Thecategoryappliestothereactorpressurevessel.Thefullpenetrationweldednozzlesarescheduled in accordance with relief request RR002 Alternative to NozzletoVessel Weld and Inner Radius Examinations.ThealternativerequestedtheuseofCodeCaseN702whichreducesthenumberof NozzletoVessel Welds and Inner Radii to 25%, including at least one nozzle from each system and nominalpipesize.Thiscodecaseexcludestherecirculationsuction,feedwater,andcontrolroddrive returnlinenozzles.TheBottomHeadDrainNozzleisexemptperIWB1220(c).Theexaminationvolume requiredisperCodeCaseN6131whichreducesthevolumefromt/2to1/2inch.

EXAMINATIONCATEGORYBF,PRESSURERETAININGDISSIMILARMETALWELDSINVESSELNOZZLES ThiscategoryaddressesNozzletoSafeEndWeldsandPipingWelds.MonticellohasdevelopedaCode CaseN716RIISIProgram.AllExaminationCategoryBFweldshavebeenrecategorizedasRAweldsin accordancewithCodeCaseN716.UseofCodeCaseN716willbesubmittedtotheNRCviaRequestfor AlternativeRR003.Therefore,noexaminationsareinitiallyscheduledtobeperformedperExamination CategoryBF.Thereare2refuelingoutagesinthefirstperiodofthe5thInterval;eithertheriskbased scope, contingent on approval by the NRC, or the inspection scope required by IWB2500 will be completepriortocompletingthesecondoutageofthefirstperiod.

EXAMINATIONCATEGORYBG1,PRESSURERETAININGBOLTING,GREATERTHAN2INDIAMETER TheexaminationoftheReactorVesselBoltingwillbedeferredtotheendoftheintervalandperformed inthe3rdPeriod.ForvolumetricexaminationofRecirculationPumpStuds,oneoftwosetsofreactor recirculation pump studs is selected for volumetric examination. For the visual examination of the flangesurfaceandnuts,bushingsandwashers,oneofthereactorrecirculationpumpswillbeexamined onlyifdisassembledandexaminedunderExaminationCategoryBL2.

ThismeetstheExaminationCategoryBG1examinationrequirementsinthe2007Editionwiththe2008 AddendaofSectionXI.

EXAMINATIONCATEGORYBG2,PRESSURERETAININGBOLTING,2ANDLESSINDIAMETER Thiscategoryincludesthereactorvesselheadcoolingflangebolts,reactorvesseltopheadflangebolts, flangeboltsontheMainSteam,RecirculationDrain,RPVHeadVent,BottomHeadDrain,andResidual HeatRemovalsystems.InadditionthiscategoryincludesvalveboltingoftheCoreSpray,MainSteam, Feedwater, Residual Heat Removal, and Recirculation Systems. Examinations will be conducted as requiredinTableIWB25001inthe2007Editionwiththe2008AddendaofSectionXI.Thisboltingwill

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onlybeexaminedwhentheassociatedconnectionsaredisassembled.Forboltingotherthanpiping, bolting examinations will be required only when the associated component is examined under ExaminationCategoryBL2orBM2.Forboltingonpipingsystems,theexaminationwillbeperformed ononlyoneoftheboltedconnectionamongagroupofboltedconnectionsthataresimilarindesign, size,function,andservice.Examinationwillbeperformedonlywhentheflangeisdisassembled.

EXAMINATIONCATEGORYBJ,PRESSURERETAININGWELDSINPIPING Thiscategoryaddressespipingwelds.MonticellohasdevelopedaCodeCaseN716RIISIprogram.All ExaminationCategoryBJWeldshavebeenrecategorizedasRAweldsinaccordancewithCodeCase N716. Use of Code Case N716 will be submitted to the NRC via Request for Alternative RR003.

Therefore,noexaminationsareinitiallyscheduledtobeperformedperExaminationCategoryBJ.There are2refuelingoutagesinthefirstperiodofthe5thInterval;eithertheriskbasedscope,contingenton approvalbytheNRC,ortheinspectionscoperequiredbyIWB2500willbecompletepriortocompleting thesecondoutageofthefirstperiod.

EXAMINATIONCATEGORYBK,WELDEDATTACHMENTSFORVESSELS,PIPING,PUMPS,ANDVALVES ExaminationCategoryBKoftheASMECode,SectionXI,2007Editionwiththe2008Addendarequires examinationofweldedattachments.Forthereactorpressurevesselweldedattachments,footnote4 allowsformultiplevesselsofsimilardesign,function,andservice,onlyoneweldedattachmentofonly oneofthemultiplevesselsshallbeselectedforexamination.Forsinglevessels,onlyoneattachment weldshallbeselected.Theattachmentselectedshallbeanattachmentundercontinuousloadduring thenormalsystemoperation.TheRPVhasfiveweldedattachmentswiththevesselskirtbeingselected forexamination.

For piping, pumps, and valves, inspection of 10% of the total population of welded attachments associatedwiththecomponentsupportsselectedforexaminationunderIWF2510shallbeexamined.

10%ofallpipingandpumpweldedattachmentsassociatedwiththecomponentsupportsselectedfor examinationunderIWF2510wasselectedforexamination.Thereareatotalof144supports;39of thosesupportshavebeenselectedforexaminationunderIWF2510.Ofthosesupportsselectedfor examination only 12 have welded attachments; 10% or 2 would require examination. There are 2 reactorrecirculationpumpswhichhave3supportseach.Threesupportsononepumpareselectedfor examination,andall3supportshaveweldedattachments;10%or1weldedattachmentisrequiredto beexamined.TheAreactorrecirculationpumpisselectedforexamination.

EXAMINATIONCATEGORYBL2,PUMPCASINGS ThiscategoryinvolvesonlytheReactorRecirculationPumpsandrequiresavisualexaminationonthe pumpcasinginternalsurfaceswhenthepumpisdisassembled.Theexaminationislimitedtoonepump.

Nopumpisscheduledfordisassemblysonopumpshavebeenselected;howevertherequirementwill bemetduringtherepair/replacementand/ormaintenanceactivitythatisperformedoneitherofthe pumps.

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EXAMINATIONCATEGORYBM2,VALVEBODIES This category involves the valves that exceed NPS 4 in the Core Spray, Main Steam, High Pressure CoolantInjection,Feedwater,ResidualHeatRemoval,andRecirculationSystems.Thiscategoryrequires examinationofonevalveineachgroupofvalvesthatareofthesamesize,constructuraldesign,and manufacturingmethod,andthatperformssimilarfunctionsinthesystem.Thevalveshavebeendivided into14GroupswiththeschedulingnotesofBB,EE,FF,GG,HH,II,JJ,KK,LL,NN,OO,PP,QQ,andRR.

However,thisexaminationisonlyrequiredwhenavalveisdisassembledformaintenance,repair,or volumetricexamination.Novalvebodyinternalsurfaceshavebeenselected.Thisrequirementwillbe metduringthemaintenanceorrepair/replacementactivity.

ASMESectionXICategoryBM2 Class1ValveGroups Valve Group Valves (drawing,valveID)

SYS Size Constructural Design Manufacturing Method Function 1(BB)

ISI1314233A,V4 ISI1314234A,V4 ISI1314235A,V4 ISI1314236A,V4 MST 18 AnchorDarling

GateValve Cast Isolation

Containment (Outboard)(OB) 2(EE)

ISI1314233A,V3 ISI1314234A,V3 ISI1314235A,V3 ISI1314236A,V3 MST 18 Atwood&

Morrill

WyePattern GlobeValve Cast Isolation

Containment (Inboard)(IB) 3(FF)

ISI1314233A,V1 ISI1314233A,V2 ISI1314234A,V1 ISI1314234A,V2 ISI1314235A,V1 ISI1314235A,V2 ISI1314236A,V1 ISI1314236A,V2 MST 6

TargetRock Corp

SRVModel67F SafetyRelief Valve Cast

Overpressure Protection

SafetyReliefValve 4(GG)

ISI1314252A,V2 ISI1314252A,V3 ISI1314253A,V2 ISI1314253A,V3 CFW 14 AnchorDarling

SwingCheck Valve Cast Isolation

Containment(IB/OB) 5(HH)

ISI1314252A,V1 ISI1314253A,V1

CFW 14 AnchorDarling

GateValve Cast

Isolation

Loop 6(II)

ISI97005A,V1 ISI97005A,V2 ISI97006A,V1 ISI97006A,V2 REC 28 Crane

GateValve Cast Isolation

Loop 7(JJ)

ISI1314242A,V1

HPC 8

Velan

GateValve Forged Isolation

Containment(IB)

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ASMESectionXICategoryBM2 Class1ValveGroups Valve Group Valves (drawing,valveID)

SYS Size Constructural Design Manufacturing Method Function 8(KK)

ISI1314242A,V2 HPC 8

Flowserve GateValve Cast Isolation

Containment(OB) 9(LL)

ISI1314231A,V1 ISI1314231A,V3 ISI1314226A,V1 ISI1314226A,V3 CSP 8

AnchorDarling

GateValve Cast Isolation

Loop Containment(OB) 10(NN)

ISI1314231A,V2 ISI1314226A,V2 CSP 8

Atwood&

Morrill

TestableCheck Valve Cast Isolation

Containment(IB)

11(OO)

ISI97003A,V1 ISI97003A,V3

RHR 18 AnchorDarling

GateValve Cast Isolation

Loop Containment(OB)

12(PP)

ISI97004A,V1 ISI97004A,V3 RHR 16 AnchorDarling

GateValve Cast Isolation

Loop Containment(OB)

13(QQ)

ISI97003A,V2 ISI97004A,V2

RHR 16 Atwood&

Morrill

TestableCheck Valve Cast Isolation

Containment(IB) 14(RR)

ISI97003B,V1 ISI97003B,V2 ISI97003B,V3

RHR 18 AnchorDarling

GateValve Cast Isolation

Loop Containment(IB/OB)

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EXAMINATIONCATEGORIESBN1,BN2ANDBN3 Tobetterdefinewhattheseexaminationcategoriesconsistofitisimportanttoreviewthebasisforthe developmentofthecategory.ApapertitledDevelopmentofInServiceInspectionSafetyPhilosophy for U.S.A Nuclear Power Plant by S.H. Bush and R.R. MacCary was reviewed which defined the philosophy behind the development of the Inspection Category N in the 1971 Edition of the ASME SectionXICode.Thispaperstated:

ThespecialexaminationcategoryNcoverstheexaminationoftheinteriorsurfacesand internalcomponentsofthereactorvessel;itisconsideredoneofthemostcritical examinationrequirementsintheA.S.M.ESectionXICode.Amongtheconsiderations contributingtothedevelopmentofthisexaminationcategorywerethereported experiencesanddifficultiesencounteredintheoperatingfacilities.Theseinterior examinationareasshouldassure:

a. Inspectionofallinternalsupportattachmentsweldedtothereactorvesselwhose failurecouldresultinreactorcoredisarrangement.

b. Discoveryofanyloosepartswhichmighthaveaccumulatedatthebottomofthe reactorvesselduringservice.

c. Detectionofunduewearasaresultofflowinducedvibrationsofcomponentsofthe reactorcorestructure.

d. Verificationoftheoverallstructuralintegrityofthecorestructure,including supplementaryinternalcomponentssuchasmoistureseparators,material surveillancecapsules,instrumentation,andreactorcontrolrodassemblyguides.

The 2007 Edition with the 2008 Addenda does not have a Category N but now has three categoriesapplicabletoaBoilingWaterReactor(BWR)suchasMonticello,CategoryBN1,BN 2andBN3.TheabovebasisforCategoryNinthe1971EditionofSectionXIisinterpretedas follows:

Item (a) above is interpreted to be addressed by the VT1 and VT3 visual examinations for Examination Category BN2, Item Numbers B13.20 and B13.30 Interior Attachments within andbeyondthebeltlineregion.

Item(b)aboveisinterpretedtobeaddressedbytheVT3visualexaminationforExamination CategoryBN1,ItemNumberB13.10,VesselInteriorcoveringspacesaboveandbelowthe reactorcore.

Item(c)aboveisinterpretedtobeaddressedbytheVT3visualexaminationforExamination CategoryBN2,ItemNumberB13.40CoreSupportStructure,exceptthatthesupplementary componentswerenotincludedwhentheExaminationCategoriesBN1,BN2,BN3orBI1 replacedtheformerExaminationCategoryNinthe1974Edition.Thereactorvesselinterior surfaces referred to in the former Examination Category N were addressed by Examination Category BI1 in the 1974 Edition as sample clad patches which was eliminated in the Summer1976Addenda.

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EXAMINATIONCATEGORYBN1,INTERIOROFREACTORVESSEL This category involves the examination of spaces above and below the reactor core that are made accessible by removal of components during normal refueling outages. These examinations will be conductedeachinspectionperiod.BasedontheexplanationabovethiswouldonlybeperformingaVT 3visualexaminationlookingforloosepartsorFME.

ThismeetstheExaminationCategoryBN1examinationrequirementsinthe2007Editionwiththe2008 AddendaofSectionXI.

EXAMINATIONCATEGORYBN2,WELDEDCORESUPPORTSTRUCTURESANDINTERIORATTACHMENTS TOREACTORVESSELS These examinations will be deferred until the third period as allowed by Table IWB25001. These examinationsincludetheinteriorweldedattachmentsforvesselinternalcomponentsaswellasthose weldedcoresupportstructures.TheweldedattachmentswithinthebeltlineregionwillreceiveaVisual, VT1examinationandtheweldedattachmentsoutsidethebeltlineregion willreceiveaVisual,VT3 examination.

ThismeetstheExaminationCategoryBN2examinationrequirementsinthe2007Editionwiththe2008 AddendaofSectionXI.

EXAMINATIONCATEGORYBN3,REMOVALBLECORESUPPORTSTRUCTURES ThisexaminationcategoryisnotapplicabletotheMonticelloNuclearGeneratingPlant.

EXAMINATION CATEGORY BO, PRESSURE RETAINING WELDS IN CONTROL ROD DRIVE AND INSTRUMENTNOZZLEHOUSINGS Thisexaminationcategoryrequiresavolumetricorsurfaceexaminationof10%ofperipheralcontrol drivehousingsduringtheinspectioninterval.Thereare24peripheralcontrolroddrivesonthereactor vesselbottomhead.Tomeetthecategoryexaminationrequirements2welds(upperandlowerweld) on3oftheperipheralcontrolroddrivehousingswillbeselectedforexamination.

ThismeetstheExaminationCategoryBOexaminationrequirementsinthe2007Editionwiththe2008 Addenda.

EXAMINATIONCATEGORYBP,ALLPRESSURERETAININGCOMPONENTS ThepressuretestingprogramatMonticellomeetstherequirementsofASMECode,SectionXI,2007 Editionwiththe2008AddendaforClass1Systems.Detailsofthecomponentlistingarecontainedin thesurveillanceprocedurefortheClass1SystemLeakageTest.

EXAMINATIONCATEGORYBQ,STEAMGENERATORTUBING ThisexaminationcategoryisnotapplicabletotheMonticelloNuclearGeneratingPlant.

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EXAMINATIONCATEGORYCA,PRESSURERETAININGWELDSINPRESSUREVESSELS ThiscategoryappliestotheResidualHeatRemovalHeatExchangers(AandB).Note3inTableIWC 25001, Examination Category CA states In the case of multiple vessels of similar design, size, and service(suchassteamgenerators,heatexchangers),therequiredexaminationsmaybelimitedtoone vesselordistributedamongvessels.Bothoftheheadweldsandtheshellweldswereselectedonone oftheResidualHeatRemovalHeatExchangers.BothRHRHeatExchangershaveaShellCoverFloating Head,thereforeItemNumberC1.30isnotapplicabletoMGNP.

ThismeetstheExaminationCategoryCAexaminationrequirementsinthe2007Editionwiththe2008 Addenda.

EXAMINATIONCATEGORYCB,PRESSURERETAIINGNOZZLEWELDSINVESSELS This category applies to the Residual Heat Removal Heat Exchangers. Note 1 in Table IWC25001, Category CB, excludes manways and handholes. Note 3 require that nozzles selected initially for examinationshallbereexaminedovertheservicelifeofthecomponenttotheextentpractical.Note4 allowthatinthecaseofmultiplevesselsofsimilardesign,size,andservicetherequiredexaminations maybelimitedtoonevesselordistributedamongthevessels.Twonozzleswereselectedononeofthe ResidualHeatRemovalHeatExchangers.

ThismeetstheExaminationCategoryCBexaminationrequirementsinthe2007Editionwiththe2008 Addenda.

EXAMINATIONCATEGORYCC,WELDEDATTACHMENTSFORVESSELS,PIPING,PUMPS,ANDVALVES ExaminationCategoryCCoftheASMECodeSectionXI,2007Editionwiththe2008Addendarequires examination of Welded Attachments. For vessel attachments Note 4 allows for multiple vessels of similardesign,function,andservice,onlyoneweldedattachmentofonlyoneofthemultiplevessels shallbeselectedforexamination.Forsinglevessels,onlyoneweldedattachmentshallbeselectedfor examination.Theweldedattachmentselectedshallbeanattachmentundercontinuousloadduring normal system operation or an attachment subject to a potential intermittent load during normal systemoperationifanattachmentundercontinuousloaddoesnotexist.Aweldedattachmentonone oftheResidualHeatRemovalHeatExchangerswasselectedforexamination.

Forpipingpumpsandvalves,inspectionof10%ofthetotalpopulationofintegralweldedattachments associatedwiththecomponentsupportsselectedforexaminationunderIWF2510isrequired.10%of all piping and pump welded attachments associated with the component supports selected for examinationunderIWF2510wasselectedforexamination.Therearetwopipingweldedattachments thatdonotrequireexamination(Ref.IWC25001,ExaminationCategoryCC,Note(b))astheydonot providesupport.Thereareatotalof268pipingsupportsofwhich42pipingsupports(15%)havebeen selectedforexaminationunderIWF2510.Ofthose42pipingsupportsselectedforexaminationunder IWF2510,14haveweldedattachments,therefore10%or2weldedattachmentsonpipingsupports requireexamination.Thereareatotalofsixpumpsthathaveweldedattachments(4RHRand2CS

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pumps);onlytwooftheassociatedpumpsupportswillbeselectedforexaminationunderIWF2510.

Both of these pump supports have welded attachment, therefore 10% of 2 is 1 pump welded attachmentrequiresexamination.

ThismeetstheExaminationCategoryCCexaminationrequirementsinthe2007Editionwiththe2008 AddendaofSectionXI.

EXAMINATIONCATEGORYCD,PRESSURERETAININGBOLTINGGREATERTHAN2INDIAMETER ThisexaminationcategorydoesnotapplytotheMonticelloNuclearGeneratingPlant.

EXAMINATION CATEGORIES CF1, PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGHALLOYPIPING ThiscategoryaddressesClass2stainlesssteelpipingwelds.MonticellohasdevelopedaCodeCaseN 716 RIISI program. All Examination Category CF1 welds have been recategorized as RA welds in accordancewithCodeCaseN716.UseofCodeCaseN716willbesubmittedtotheNRCviaRequestfor AlternativeRR003.Therefore,noexaminationsareinitiallyscheduledtobeperformedperExamination CategoryCF1.Thereare2refuelingoutagesinthefirstperiodofthe5thInterval;eithertheriskbased scope, contingent on approval by the NRC, or the inspection scope required by IWB2500 will be completepriortocompletingthesecondoutageofthefirstperiod.

EXAMINATIONCATEGORYCF2,PRESSURERETAININGWELDSINCARBONORLOWALLOYSTEELPIPING ThiscategoryaddressesClass2carbonsteelpipingwelds.MonticellohasdevelopedaCodeCaseN716 RIISI program. All Examination Category CF2 welds have been recategorized as RA welds in accordancewithCodeCaseN716.UseofCodeCaseN716willbesubmittedtotheNRCviaRequestfor AlternativeRR003.Therefore,noexaminationsareinitiallyscheduledtobeperformedperExamination CategoryCF1.Thereare2refuelingoutagesinthefirstperiodofthe5thInterval;eithertheriskbased scope, contingent on approval by the NRC, or the inspection scope required by IWB2500 will be completepriortocompletingthesecondoutageofthefirstperiod.

EXAMINATIONCATEGORYCH,ALLPRESSURERETAININGCOMPONENTS ThepressuretestingprogramatMonticellomeetstherequirementsofASMECode,SectionXI,2007 Editionwiththe2008AddendaforClass2Systems.Detailsofthecomponentlistingarecontainedin theindividualsurveillanceproceduresfortheClass2SystemLeakageTests.

EXAMINATIONCATEGORYDA,WELDEDATTACHMENTSFORVESSELS,PIPING,PUMPS,ANDVALVES ExaminationCategoryDAoftheASMECodeSectionXI,2007Editionwiththe2008Addendarequires examination of welded attachments on those systems that are determined to be most subject to corrosion,suchastheweldedattachmentsoftheServiceWaterorEmergencyServiceWatersystems.

Forweldedattachmentsofpiping,pumps,andvalves,a10%sampleshallbeselectedforexamination.

Thispercentagesampleshallbeproportionaltothetotalnumberofnonexemptweldedattachments connectedtothepiping,pumps,andvalvesineachsystemsubjecttotheseexaminations.Theonly

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Class3systematMonticellothatisnotexemptfromexaminationandconsideredsubjecttocorrosionis theResidualHeatRemovalServiceWaterSystem.Thereareatotalof99supports,ofwhich14have attachments.10%ofthose14or2weldedattachmentarerequiredtobeexamined.

EXAMINATIONCATEGORYDB,ALLPRESSURERETAININGCOMPONENTS ThepressuretestingprogramatMonticellomeetstherequirementsofASMECode,SectionXI,2007 Editionwiththe2008AddendaforClass3Systems.Detailsofthecomponentlistingarecontainedin theindividualsurveillanceproceduresfortheClass3SystemLeakageTests.

EXAMINATIONCATEGORYFA,SUPPORTS Examination Category FA of the ASME Code Section XI, 2007 Edition through the 2008 Addenda requires 25% of Class 1 Piping Supports, 15% of Class 2 Piping Supports, and 10% of Class 3 Piping Supportstobeexaminedduringtheinspectioninterval.Formultiplecomponentsotherthanpiping, within a system of similar design, function, and service, the supports of only one of the multiple componentsarerequiredtobeexamined.Thesupportshavebeenseparatedbytypeasdefinedin Note (1) to Examination Category FA. A letter designation has been added to the Item Number to clearly identify each support by type. Twentyfive percent (25%) of the Class 1 supports have been selectedandareproratedbytypeandsystem.Fifteenpercent(15%)oftheClass2supportshavebeen selectedandareproratedbytypeandsystem.Tenpercent(10%)oftheClass3supportshavebeen selectedandareproratedbytypeandsystem.

Forsupports,otherthanpipingsupports,thecomponentshavebeenscheduledasfollows:

ReactorVesselSupportSkirt HighPressureCoolantInjectionPump OneCoreSprayPump OneRecirculationPump OneResidualHeatRemovalHeatExchanger OneResidualHeatRemovalPump

EXAMINATIONCATEGORYRA ThealternativeCodeCaseN716,RIISIProgramforpiping,asdescribedintheforthcomingRequestfor Alternative RR003, will be utilized. The RIISI Program will be substituted for the Examination CategoriesBF,BJ,CF1,andCF2inaccordancewith10CFR50.55a(3)(i)byalternativelyprovidingan acceptablelevelofqualityandsafety.Theweldsareselectedinaccordancewiththefinalcalculation provided by Structural Integrity Associates, Inc. (SI) Calculation 1000515.302, N716 Evaluation for Monticello.Thecalculationrequires67weldstobeexaminedvolumetrically.

TheN716programcontains96weldsthataresusceptibletoFAC.CodeCaseN716referstotheutility FACProgramforweldssusceptibletoFAC.ThereforealloftheweldsthathaveaFAConlymechanism areassignedR1.20.IfithasFACalongwithanotherdegradationmechanismthentheitemnumberfor

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thenonFACdegradationmechanismisassigned.Itshouldbenotedthat3RWCUweldswereselected astheRWCUsystemwasdeterminedtobeHighSafetySignificant(HSS)whichrequires10%ofthetotal populationtobeselected.The3weldschosenarealsosusceptibletoFACasadegradationmechanism; howevertheseweldswereselectedwithnodegradationmechanismandassignedCodeItemNo.R1.20.

4.0 ExaminationPersonnel/Procedures

Inservice Inspection examination procedures and personnel certifications will meet the requirements specified in the 2007 Edition with the 2008 Addenda on January 21, 2013. The implementation of Appendix VIII to the 2001 Edition will continue until January 21, 2013 which is allowed by 10 CFR 50.55a(g)(4)(ii).

5.0 ReportingofAssociatedSectionXIPrograms

The Section XI Repair/Replacement Program, Containment Inservice Inspection Program, and System Pressure Testing Program are administered under separate program documents. Although these programsareadministeredseparately,theactivitiesbytheRepair/ReplacementProgram,Containment Inservice Inspection Program, and System Pressure Testing Program, are reported in the Inservice InspectionSummaryReportorOwnersActivityReportfollowingeachrefuelingoutage.

6.0 AugmentedandOwnerPrograms

6.1 AugmentedPrograms TheISIPlanalsocontainscertainnoncodeitemstobeexaminedorexaminationbeyondthatdescribed inASMESectionXI.TheseaugmenteditemsincludeNRCrequiredorlicenseinitiatedexaminationson thefollowingcomponents:

6.1.1 NUREG0619BWRControlRodDriveReturnLineNozzleCrackingPostModification SourceDocument:RAC00988 Associated Document: Commitment M83165A, Letter dated 04/27/1995 (M1995092, JRR03336)toNRRinformingthemofmissedinspectionsin1993/1994.

Purpose:

TheCRDNozzlewascutandcappedinresponsetoNUREG0619issues.TheCRD ReturnLinewasreroutedtotheReactorWaterCleanupSystem.Thisinspectionistoassure integrityofthereroutedpipingattheteeonIsometricNX1314249A,LineREW63DC.

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Scope:TheweldsinspectedareW11,W12andW13onISIISONCISI51.

Method:Volumetricexaminationmethodsarerequiredandshallincludebasemetaltoadistance ofonepipewallthicknessor1/2whicheverisgreateronbothsidesoftheweld.

IndustryCodeorStandards:ASMESectionXItotheextentpractical.

Frequency:Everyrefuelingoutage.

AcceptanceCriteriaorStandard:ASMESectionXI,IWC3500.

RegulatoryBasis:NRCCommitmentM83165A.

6.1.2 Modification79Z018RWCUReturnLineModification SourceDocument:NUREG0619BWRFeedwaterNozzleandControlRodDriveReturnLine NozzleCracking:ResolutionofGenericTechnicalActivityA10(TechnicalReport)

AssociatedDocument:StructuralIntegrityAssociates,IncCalculationPackageRiskInformed ISICodeCaseN578ApplicationtoNMCPlantsFileNo.NMC01301.

Purpose:

TheRWCUreturnlinewasreroutedtobedistributedequallybetweenthetwo feedwaterlines.Themodificationassuresthatfeedwatertoallfournozzleswillbewarmedat lowflowratesbythehighertemperatureRWCUreturnwater.Themodificationreducedthe feedwaternozzleusagefactorsby15%30%.Duringstartupandshutdownitispossibleforthe alternatingstresstoexceedtheendurancestrengthofcarbonsteel.Becauseofthesmall amountoftimeattheseconditionsitisbelievedthatthermalfatiguewillnotbeaproblemat theRWCUconnectiontothefeedwaterlineshoweveritwasrecommendedthatthefeedwater linesdownstreamoftheHPCIandRCICconnectionsandtheHPCIandRCIClinesdownstreamof theRWCUlinebeinspectedbyUTduringeachrefuelingoutage.Sincetheimplementationof theModification,theRiskedInformedISIProgramforthe4th10yearintervalevaluatedtheHPCI toFeedwaterconnectionandfoundthatitwasnotsusceptibletothermalfatigue.Inaddition, theFeedwaterlinesthemselvesareevaluatedundertheRIISIProgramandareselectedin accordancewiththatprogramandnotasanAugmentedProgram.Therefore,theonlywelds nowexaminedunderModification79Z018aretheRCIClinesshownbelow.

Scope:TheweldsinspectedareW1,W2,W3,W4,W12,andW12AonISIISONCISI37.

Method:Volumetricexamination.

IndustryCodeorStandards:ASMESectionXItotheextentpractical.

Frequency:Everyrefuelingoutage.

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AcceptanceCriteriaorStandard:ASMESectionXI,IWC3500.

RegulatoryBasis:None.

6.1.3 HighEnergyLineBreak SourceDocument:MEB31asamendedbyGenericLetter(GL)8711RelaxationinArbitrary IntermediatePipeRuptureRequirements AssociatedDocument:NUREG3.6.2DeterminationofRuptureLocationsandDynamicEffects Associated with the Postulated Rupture of Piping, NUREG0800, 5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing, and UFSAR Appendix I Evaluation of HighEnergyLineBreaksOutsideContainment

Purpose:

InSeptember1987,theNRCissuedGL8711whichwouldallowutilitiestoeliminate theconsiderationoftheenvironmentalanddynamiceffectsofarbitraryintermediatepipe breaksprovidedthattherequirementsofBranchTechnicalPosition34(formerlyBTPMEB31),

Revision2weremet.

Scope:Theweldsinspectedare:

W1,W2,W3,onISIISOISI1314231A, W6,W7,W8onISIISOISI1314226A, W16,W17onISIISOISI1314242A, W29,W29A,W30,W31,W32onISIISOISI1314233A, W12,W13,W14onISIISOISI768A, W29,W30,W31,W32,W33onISIISOISI1314234A, W29,W30,W31,W32,W33,W34onISIISOISI1314235A, W31,W32,W33,W34,W35onISIISOISI1314236A, W13,W14onISIISO1314243A, W24,W25onISIISOISI97003B, W1,W2onISIISOISI97004A, W1,W2onISIISOISI97003A W25,W26onISIISOISI73880A.

Method:Volumetricexamination.

IndustryCodeorStandards:ASMESectionXIIWA2400 Frequency:Onceperinterval.

AcceptanceCriteriaorStandard:ASMESectionXI,IWB3500

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RegulatoryBasis:GL8711.

6.2 OwnerElectedExaminations

InadditiontotheaboveidentifiedAugmentedExaminations,thereareexaminationsperformed duetointernalcommitments.Theseitemsareexaminedtotheextentpracticalinaccordance withtheSectionXICode,2007Editionwiththe2008Addenda,notaspartoftheRIISIProgram.

ReliefRequestswillnotbesubmittedforthesenoncodeexamsifSectionXICoderequirements cannotbemet.Noncodeexamsarealsosubjecttochangewithoutpriornotificationtothe NRC. These are identified as Owner Elected Examination. The following Owner Elected Examinationsareperformed:

6.2.1 OE23699StandbyLiquidControlTank Source Document: OE23699 Initiation of Reactor Shutdown required by Technical Specification3.1.7ActionC.1 AssociatedDocument:AR01064168

Purpose:

TheexternaloperatingexperiencefromQuadCitiesStationindicatedthattheStandby LiquidControlTankhadapinholeleakthatwasnotdeterminedtomakethetankinoperableper ASMECoderequirements.TheQuadCitiesStandbyLiquidControlTankisconstructedwith Type304stainlesssteel.ForType304stainlesssteeltankmaterial,themostlikelycauseof externalstresscorrosioncrackingisanexposuretochloridesorotherhalogencontaining solution,whichcanleadtotransgranularstresscorrosioncracking(TGSCC).TheMonticello SBLCTankisalsomadeofstainlesssteelandissusceptibletothesamemechanism.This inspectionistoverifythestructuralintegrityofthetank.

Scope:TheSBLCTankinsidesurfaces.

Method:VisualVT3examinationofthetankinteriorsurfaces.

IndustryCodeorStandards:None.

Frequency:Everyinterval.

AcceptanceCriteriaorStandard:ASMESectionXI,IWC3500.

RegulatoryBasis:None.

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7.0 LicenseRenewalAgingManagementPlansandCommitments This document supports the implementation of the following License Renewal Aging Management ProgramsandCommitments:

7.1 Programs PBD/AMP004, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic StainlessSteel(CASS)Program PBD/AMP022,PrimaryContainmentInServiceInspectionProgram PBD/AMP024,ASMESectionXI,SubsectionIWF PBD/AMP033,ASMESectionXIInserviceInspection,SubsectionIWB,IWC,andIWD PBD/AMP034,ReactorHeadClosureStuds PBD/AMP035,BWRVesselIDAttachmentWeldsProgram PBD/AMP036,BWRFeedwaterNozzle PBD/AMP037,BWRControlRodDriveReturnNozzle PBD/AMP038,BWRStressCorrosionCrackingProgram PBD/AMP039,BWRPenetrationsProgram NRC Commitments M05008A, M05009A, M05010A, M05011A, M05020A, M05021A, and M05022A

7.2 LicenseRenewalCommitments

7.2.1 ClassMCSupports

SourceDocument:USARAppendixK,K2.1.3

AssociatedDocument:PBD/AMP024,CommitmentM05011A

Purpose:

As required by License Renewal Commitment M05011A, Class MC Supports will be examinedpertherequirementsofSubsectionIWF.

Scope:100%ofthefollowingClassMCSupportsareincludedinanaugmentedprogramandwill beexaminedeachinspectioninterval:

Torus/RingHeaderSeismicRestraints DrywellMaleandFemaleStabilizers ShieldStabilizers TorusColumns TorusSaddles VentSystemSupports

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DowncomerBracing

Method:VisualVT3Examination

IndustryCodeorStandards:ASMESectionXI,SubsectionIWF

Frequency:100%eachinterval

AcceptanceCriteriaorStandard:ASMESectionXI,IWF3410

RegulatoryBasis:NRCCommitmentM05011AandUSARAppendixK

7.2.2 SmallBoreClass1Piping

SourceDocument:USAR,AppendixK,K2.1.2

Associated Document: PBD/AMP033, NRC Letter dated May 10, 2011 Monticello Nuclear GeneratingPlant(MNGP),ExaminationofClass1SmallBorePipingButtWelds

Purpose:

AsrequiredbyLicenseRenewaltomanageagingeffects,examinationofSmallBore Piping(Ref.USARAppendixK,SectionK2.1.2)hasbeenaddedasanaugmentedprogramtothe ISIPlan.

Scope: The weld population includes W2 through W7 on ISI Drawing ISI786A and W32 through W34 on ISI Drawing ISI74215A. The exams are performed in support of License RenewalandSHALLbeperformedthroughtheRenewedLicenseperiodofextendedoperation.

The base scope of approximately 10% of the population will be examined during each ISI interval.

Method:AugmentedvolumetricexaminationsofweldsareperformedonClass1stainlesssteel smallborepipingbuttwelds>NPS2to<NPS4.TheweldvolumeapplicabletoCategoryBFor BJ will be used for the examination. Welds will be examined to the extent practical. If limitationsareencounteredthatdonotpermitcoverageofessentially100%,a10CFR50.55a request(reliefrequest)isnotrequired.

Industry Code or Standard: Examination personnel SHALL be qualified to ASME Section XI, AppendixVIIIasspecifiedintheISIPlan.

Frequency:10%eachinterval

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Acceptance Standard: Welds will be evaluated in accordance with IWB3000 requirements applicabletoCategoryBForBJ

RegulatoryBasis:LicenseRenewalCommitmentperUSARAppendixK

7.2.3 FeedwaterNozzles

SourceDocument:USAR,AppendixK,K2.1.8

AssociatedDocument:PBD/AMP036

Purpose:

As required by License Renewal Commitments, M05021A, to manage aging effects, Reactor Vessel Feedwater Nozzle examinations will be performed in accordance with the requirements of General Electric Report NE523A710594A, Rev. 1 (Ref. USAR Appendix K, SectionK2.1.8).

Scope:FeedwaterNozzles

Method: Volumetric examinations of specified zones in accordance with ASME Section XI AppendixVIII.

IndustryCodeorStandard:ASMESectionXI

Frequency:Eachinterval

AcceptanceCriteriaorStandard:ASMESectionXI,IWB3512

RegulatoryBasis:USARAppendixK,K2.1.8

8.0 SourceDocuments

Thefollowingreferencedsourcedocumentsdescribedandlistedbelowarebasisdocumentsusedand applicabletotheMonticello5thIntervalISIPlan.

ASMEBPVCodeSectionXI,2007Editionwiththe2008Addenda 10CFR50.55a,IndustryCodesandStandards(76FR36232)

RegulatoryGuide1.147,Revision16,October2010 MonticelloInserviceInspectionLicenseeControlProgram,4AWI09.04.00 MonticelloASMESectionXIInserviceInspectionProgram,EWI09.0400

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GE Nuclear Services Information Letter, SIL. No. 483R2 CRD Cap Screw Crack Indications, September5,1992 GenericLetter8801&NUREG0313,Rev2(IGSCC(M88080A,M88082A)Note:AllMonticello weldsmeetNUREG0313,Rev2CategoryA MonticelloNotificationLettertoNRC,NotificationofExtensionof3rdTenYearInserviceTesting andInserviceInspectionIntervals,May30,2002 NRC Commitment M97025A, Response to LER 97004, Failure to Submit Relief Requests for LimitedInserviceInspectionExaminations,datedMarch24,1997.LimitedExaminationRelief Requestssubmittedwithin12months NUREG1865 Safety Evaluation Report, Related to the License Renewal of the Monticello NuclearGeneratingPlant,DocketNo.50263 NRCCommitmentM05008A(PassportAR00829849)-MNGPsitespecificadministrativework instructions will be applicable to both safety and nonsafety related systems, structures and components that are subject to an aging management review consistent with the current licensingbasisduringtheperiodofextendedoperation.

NRCCommitment M05009A(PassportAR00829851)-Sitedocumentsthatimplementaging managementactivitiesforlicenserenewalwillbeenhancedtoensurethatanARispreparedin accordance with plant procedures whenever nonconforming conditions are found (i.e., the acceptancecriteriaisnotmet)

NRCCommitment M05010A(PassportAR00829853)-Revisionswillbemadetoprocedures andinstructionsthatimplementoradministeragingmanagementprogramsand/oractivitiesfor thepurposeofmanagingtheassociatedagingeffectsforthedurationofextendedoperation NRC Commitment M05011A (Passport AR 0082985601) - The MNGP ASME Section XI, Subsection IWF Program will be enhanced to provide inspections of Class MC components consistentwithNUREG1801,ChapterIII,SectionB1.3 NRCCommitmentM05021A(PassportAR0082989301)-TheBWRFeedwaterNozzleProgram will be enhanced so the regions being inspected; examination techniques, personnel qualifications,andinspectionscheduleareconsistentwiththerecommendationsofGENE523 A710594Revision1 USAR Appendix K, Renewed Operating License - USAR Supplement, Items (K2.1.33, K2.1.3, K2.1.26,K2.1.1,K2.1.28,K2.1.11,K2.1.8,K2.1.7,K2.1.10,K2.1.9,andK5)

NRCLetterdated05/10/11ExaminationofClass1SmallBorePipingButtWelds NUREG1865, Safety Evaluation Report Related to the License Renewal of the Monticello Nuclear Generating Plant; dated October 2006 (SER sections 3.0.3.2.2, 3.0.3.2.3, 3.0.3.2.6, 3.0.3.2.7,3.0.3.2.8,3.0.3.2.9,3.0.3.2.10,3.0.3.1.6,3.0.3.1.7,3.0.3.1.8)

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AdoptionofCodeCases

ASMESectionXICodeCasesadoptedforISIandrelatedNDEactivitiesfortheFifthIntervalarelistedin TablesA.11,A.12,andA.13.CodeCasesrelatedtoRepair/Replacement,PressureTesting,and/or ContainmentProgrammaybelistedinTablesA.11,A.12,orA.13.TheuseofCodeCasesisin accordancewithASMESectionXI,(IWA2440orIWA4190),10CFR50.55a,andRegulatoryGuide1.147.

AspermittedbyASMESectionXIandRegulatoryGuide1.147or10CFR50.55a,ASMESectionXICode Casesmaybeadoptedandusedasdescribedbelow:

AdoptionofCodeCasesListedforGenericUseinRegulatoryGuide1.147 CodeCasesthatarelistedforgenericuseinthelatestrevisionofRegulatoryGuide1.147maybe includedintheISIProgramprovidedanyadditionalconditionsspecifiedintheRegulatoryGuidearealso incorporated.TableA.11identifiestheCodeCasesapprovedforgenericuseandadoptedfortheFifth Interval.

AdoptionofCodeCasesNotApprovedinRegulatoryGuide1.147 CertainCodeCasesthathavebeenapprovedbytheASMEBoardonNuclearCodesandStandardsmay nothavebeenreviewedandapprovedbytheNRCStaffforgenericuseandlistedinRegulatoryGuide 1.147.UseofsuchCodeCasesmayberequestedintheformofaRequestforAlternativein accordancewith10CFR50.55a(a)(3).Onceapproved,theseRequestsforAlternativeswillbeavailable foruseuntilsuchtimethattheCodeCasesareadoptedintoRegulatoryGuide1.147,atwhichtime compliancewiththeconditionscontainedintheRegulatoryGuideisrequired.

TableA.12identifiesthoseCodeCasesthathavebeenrequestedthroughRequestsforAlternatives.

ForconveniencetotheuserofthisISIProgram,theappropriateinternalcorrespondencenumberis providedtoassistintheirretrievalfromDocumentControl.AllotherRequestsforAlternativesand ReliefRequests(thosenotassociatedwithNRCapprovalofCodeCases)areaddressedinAppendixB.

AdoptionofCodeCasesMandatedby10CFR50.55a CodeCasesrequiredbyregulationin10CFR50.55aareincorporatedintotheISIProgramand implementedatthespecifiedschedule.CodeCasescurrentlyrequiredby10CFR50.55aareidentified inTableA.13.

UseofAnnulledCodeCases AspermittedbyRegulatoryGuide1.147,CodeCasesthathavebeenadoptedforuseinthecurrent intervalthataresubsequentlyannulledbyASME,maybeusedfortheremainderoftheinterval.

CodeCaseRevisions InitialadoptionofaCodeCaserequiresuseofthelatestrevisionofthatCodeCaselistedinRegulatory Guide1.147.However,ifanadoptedCodeCaseislaterrevisedandapprovedbytheNRC,theneither

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theearlierorlaterrevisionmaybeused.Anexceptiontothisprovisionwouldbetheinclusionofa conditiononthelaterrevisionnecessarytoenhancesafety.Inthissituation,theconditionimposedon thelaterrevisionmustbeincorporatedintotheprogram.

AdoptionofCodeCasesIssuedSubsequenttoFilingtheInserviceInspectionPlan CodeCasesissuedbyASMEsubsequenttofilingtheInserviceInspectionPlanwiththeNRCmaybe incorporatedwithintheprovisionsofRegulatoryGuide1.147byinitiatingarevisiontothisAppendix.

AnysubsequentCodeCasesshallbeincorporatedintotheprogramandidentifiedineitherTableA.11 orA.12,asapplicable,priortotheiruse.

CodeCasesnotapprovedforusebytheNRC CertainCodeCasesthathavebeenapprovedbytheASMEBoardonNuclearCodesandStandardshave beenreviewedandarenotapprovedbytheNRCStaffforgenericuse.TheseCodeCasesarelistedin RegulatoryGuide1.193,ASMECodeCasesNotApprovedforUse.However,theNRCmayapprove theiruseinspecificcases.CodeCaseslistedinRegulatoryGuide1.193willnotbeusedatMonticello withoutanapprovedRequestforAlternativeinaccordancewith10CFR50.55a(a)(3).Thosewillbe identifiedinAppendixB.

RegulatoryGuide1.147,Revision16ApprovedCodeCases TableA.11CodeCasesAdoptedfromRegulatoryGuide1.147 CodeCase Number Title NRCConditions N4321 RepairWeldingUsingAutomaticor MachineGasTungstenArcWelding (GTAW)TemperBeadTechnique None N5133 EvaluationCriteriaforTemporary AcceptanceofFlawsinModerate EnergyClass2or3Piping Therepairorreplacementactivitytemporarily deferredundertheprovisionsofthisCode Caseshallbeperformedduringthenext scheduledoutage.

N526 AlternativeRequirementsfor SuccessiveInspectionsofClass1and2 Vessels None N5861 AlternativeAdditionalExamination RequirementsforClasses1,2,and3 Piping,Components,andSupports None

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TableA.11CodeCasesAdoptedfromRegulatoryGuide1.147 CodeCase Number Title NRCConditions N5972 RequirementsforAnalyticalEvaluation ofPipeWallThinning (1) CodeCasemustbesupplementedbythe provisionsofEPRINuclearSafetyAnalysis CenterReport202LR2Recommendationsfor anEffectiveFlowAcceleratedCorrosion Program,April1999,fordevelopingthe inspectionrequirements,themethodof predictingtherateofwallthicknessloss,and thevalueofthepredictedremainingwall thickness.AsusedinNSAC202LR2,theterm shouldistobeappliedasshall(i.e.,a requirement)

(2) Componentsaffectedbyflowaccelerated corrosiontowhichthisCodeCaseareapplied mustberepairedorreplacedinaccordance withtheconstructioncodeorrecordand OwnersrequirementsoralaterNRCapproved editionofSectionIII,RulesforConstructionof NuclearPowerPlantComponents,ofthe ASMECode(Ref.7)priortothevalueoftp reachingtheallowableminimumwall thickness,tmin,asspecifiedin3622.1(a)(1)of thisCodeCase.Alternatively,useoftheCode CaseissubjecttoNRCreviewandapprovalper 10CFR50.55a(a)(3).

(3) ForClass1pipingnotmeetingthecriteriaof 3221,theuseofevaluationmethodsand criteriaissubjecttoNRCreviewandapproval per10CFR50.55a(a)(3).

(4) Forthosecomponentsthatdonotrequire immediaterepairorreplacement,therateof wallthicknesslossistobeusedtodeterminea suitableinspectionfrequencysothatrepairor replacementoccurspriortoreachingallowable minimumwallthickness,tmin (5) Forcorrosionphenomenonotherthanflow acceleratedcorrosion,useoftheCodeCaseis subjecttoNRCreviewandapproval.

Inspectionplansandwallthinningratesmaybe difficulttojustifyforcertaindegradation mechanismssuchasMICandpitting.

N600 TransferofWelder,WeldingOperator, Brazer,andBrazingOperator QualificationsBetweenOwners None

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TableA.11CodeCasesAdoptedfromRegulatoryGuide1.147 CodeCase Number Title NRCConditions N6061 SimilarandDissimilarMetalWelding UsingAmbientTemperatureMachine GTAWTemperBeadTechniquefor BWRCRDHousing/StubTubeRepairs.

Priortowelding,anexaminationofverification mustbeperformedtoensureproper preparationofthebasemetal,andthatthe surfaceisproperlycontouredsothatan acceptableweldcanbeproduced.The surfacestobewelded,andsurfacesadjacent totheweld,aretobefreefromcontaminants, suchas,rust,moisture,grease,andother foreignmaterialoranyotherconditionthat wouldpreventproperweldingandadversely affectthequalityorstrengthoftheweld.This verificationistoberequiredinthewelding procedures.

N6131 UltrasonicExaminationofPenetration NozzlesinVessels,Examination CategoryBD,ItemNos.B3.100and B3.90,ReactorNozzletoVesselWelds, Figs.IWB25007(a),(b),and(c).

None N639 AlternativeCalibrationBlockMaterial Chemicalrangesofthecalibrationblockmay varyfromthematerialsspecificationif(1)itis withinthechemicalrangeofthecomponent specificationtobeinspected,and(2)the phaseandgrainshapearemaintainedinthe samerangesproducedbythethermalprocess requiredbythematerialspecification.

N651 FerriticandDissimilarMetalWelding UsingSMAWTemperBeadTechnique WithoutRemovingtheWeldBead CrownfortheFirstLayer None N705 EvaluationCriteriaforTemporary AcceptanceofDegradationinModerate EnergyClass2or3VesselsandTanks None N735 SuccessiveInspectionsofClass1and2 PipingWelds None

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CodeCasesApprovedThroughRequestforAlternatives ThefollowingASMECodeCasesarenotcontainedinRegulatoryGuide1.147,Revision16andrequirea requestforalternativepriortoimplementation.SeeAppendixBofthisplanfortheapplicablerequests.

TableA.12-CodeCasesAdoptedViaNRCApprovedRequests CodeCase Number Title RequestforAlternative No.

N5325 Repair/ReplacementActivityDocumentationRequirements andInserviceInspectionSummaryReportPreparationand Submission RR006 N6612 AlternativeRequirementsforWallThicknessRestorationof Classes2and3CarbonSteelPipingforRawWaterService RR004 N702 AlternativeRequirementsforBoilingWaterReactor(BWR)

NozzleInnerRadiusandNozzletoShellWelds RR002 N716 AlternativePipingClassificationandExaminationRequirements RR003 N795 AlternativeRequirementsforBWRClass1SystemLeakageTest PressureFollowingRepair/ReplacementActivities RR005

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CodeCasesRequiredby10CFR50.55a The following ASME Code Cases are not contained in Regulatory Guide 1.147, Revision 16, but are mandatedin10CFR50.55a.

TableA.13-CodeCasesRequiredby10CFR50.55a CodeCase Number Title Notes NONE

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RELIEFREQUESTS Throughoutthisprogram,thetermreliefrequestisusedinterchangeablyreferringtosubmittalsto theNRCrequestingpermissiontodeviatefromeitheranASMESectionXIrequirement,a10CFR50.55a regulation,touseprovisionsfromlaterEditionsorAddendaofSectionXIapprovedbytheNRCas referencedin10CFR50.55a(b)ortouseprovisionsfromEditionsorAddendaofSectionXInotapproved bytheNRCasreferencedin10CFR50.55a(b).However,incommunicationswiththeNRCandwithin writtenrequeststodeviate,thetermsasdefinedbelowmustbeusedforclarityandtosatisfy10CFR 50.55a.SubmittalstotheNRCmustclearlyidentifywhichofthebelowrulesarebeingusedtorequest thedeviation.

TableB.11containsanindexofRequestforAlternativesandReliefRequestswritteninaccordancewith 10CFR50.55a(a)(3)and(g)(5).TheapplicableXcelEnergyInc.submittalandNRCSafetyEvaluation Report(SER)correspondencenumbersarealsoincludedforeachrequest.

RequestforAlternatives Whenseekinganalternativetotherulescontainedin10CFR50.55a(g),therequestissubmittedunder the provision of 10 CFR 50.55a(a)(3). Once approved by the Director, Office of Nuclear Reactor Regulation, the alternative may be incorporated into the ISI program. These types of requests are typicallyusedtorequestuseofCodeCases,CodeEdition,orAddendanotyetapprovedbytheNRC.

RequestforAlternativesmustbeapprovedbytheNRCpriortotheirimplementationoruse.Withinthe provisionsof10CFR50.55a(a)(3)therearetwospecificmethodsofsubmittal:

10CFR50.55a(a)(3)(i)allowsalternativeswhenauthorizedbytheNRC,iftheproposed alternativeswouldprovideanacceptablelevelofqualityandsafety.Requestssubmittedunder theseprovisionsarenotrequiredtodemonstratehardshiporburden.

10CFR50.55a(a)(3)(ii)alsoallowsalternativeswhenauthorizedbytheNRC,ifcompliancewith thespecifiedrequirementswouldresultinhardshiporunusualdifficultywithoutacompensating increaseinthelevelofqualityandsafety.Whensubmittedunderthisprovision,theremustbe evidenceofunusualhardshipordifficulty.Typicallythishardshipwillbedoseorexcessive disassembly.

Itshouldbenotedthatduringthepubliccommentperiodoftheruletherewasacommentprovided thatquestionswhethertherequirementtohaverequestforalternativesappliedtobothoftheabove paragraphs.Itwaspointedoutthatunder(a)(3)(ii),alicenseemaynotknowthereisahardshipuntil afterattemptinganexamination.ThiswouldresultintheNRCbeingaskedtoverballyapprove alternativesonanexpeditedbasis.TheNRCdisagreedwiththiscommentandindicatedthatapproval wasrequiredpriortoimplementationofthealternative.Implementationisconsideredtooccuratthe timethelicenseeneedstorelyonthealternativetosatisfyASMEcoderequirements.Duringapublic meetingdiscussingtheimplementationofCodeCaseN7701,aclarificationquestionwasaskedDoes theNRCclarificationcontainedintherulemaking(36248)allowthealternativetobeperformedpriorto

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approvalaslongasitisnotcrediteduntiltheNRChasreviewedandapprovedtherequest?TheNRC respondedTheNRCclarificationcontainedintherulemaking(36248)allowsthealternativeinspection tobeperformedpriortoapprovalaslongastheinspectionisnotimplemented(creditedtosatisfythe inspectionrequirement)untiltheNRChasreviewedthealternativeinspectionandapprovedtherelief requestforthealternativeinspection(MO112240818).

ReliefRequestRequiredduetoImpracticalityorLimitedExaminations 10CFR50.55a(g)(5)(iii)and(iv)allowsrelieftoberequestedininstanceswhenaCoderequirementis deemed impractical with (iv) being specific to examination requirements that are determined to be impractical.Theprovisionsofthesetwoparagraphsaretypicallyusedtoaddressimpracticalitieslike limitedexaminationcoverage.Under10CFR50.55a(g)(5)(iii),reliefrequestsmustbeprovidedtothe NRCnolaterthan12monthsaftertheexpirationofthe120monthinspectionintervalforwhichreliefis sought.Under10CFR50.55a(g)(5)(iv),reliefrequestsforexaminationimpracticalitiesmustbeprovided totheNRCnolaterthan12monthsaftertheendoftheactive120monthinterval IncaseswheretheASMESectionXIrequirementsforinserviceinspectionareconsideredimpractical, XcelEnergyInc.willnotifytheNRCandsubmitinformationtosupportthedetermination,asrequiredby 10CFR50.55a(g)(5).ThesubmittalofthisinformationwillbereferredtoasaRequestforRelief.

RequeststouseLaterEditionandAddendaofASMESectionXI OnJuly28,2004,theNRCpublishedRegulatoryIssueSummary(RIS)200412,ClarificationonUseof LaterEditionsandAddendatoASMEOMCodeandSectionXIandRIS200416UseofLaterEditions andAddendatoASMECodeSectionXIforRepair/ReplacementActivities.TheseRISclarifytheNRC positiononusingEditionsandAddendaofSectionXI,inwholeorinpart,laterthanthosespecifiedin the ISI program or the R/R Program. If the desired Edition or Addenda are referenced in 10 CFR 50.55a(b)(2),therequestissubmittedfollowingtheguidanceoftheRIS.Thesetypesofrequestarenot requiredtodemonstratehardship,difficulty,orprovideevidenceofqualityandsafety.Theydoneedto ensurethatallrelatedrequirementsarealsoused.Requeststouseeditionand/oraddendaofASME Section XI that are referenced in 10 CFR 50.55a(b)(2) that are later than the initial Code of Record establishedfortheISIprogramshallbesubmittedundertheprovisionsof10CFR50.55a(g)(4)(iv).

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TableB.11 MonticelloNuclearGeneratingPlan FifthIntervalReliefRequests Relief Request ReliefRequestDescription XcelEnergyInc.

Correspondence NRCSER Correspondence RR001 ReactorVesselCircumferentialWelds LMT10014 (dated03/12/10)

(SERdated 02/08/11)

RR002 RequesttoUseCodeCaseN702 AlternativeRequirementsforBoiling WaterReactor(BWR)NozzleInnerRadius andNozzletoShellWelds,SectionXI, Division1 LMT11056 (dated09/28/11)

AwaitingNRCSER RR003 RequesttoUseCodeCaseN716 AlternativePipingClassificationand ExaminationRequirements Tobesubmittedat alaterdate

RR004 RequesttoUseCodeCaseN6612 AlternativeRequirementsforWall ThicknessRestorationofClass2and3 CarbonSteelPipingforRawWaterService Tobesubmitted withtheISIPlan

RR005 RequesttoUseCodeCaseN795 AlternativeRequirementsforBWRClass1 SystemLeakageTestPressureFollowing Repair/ReplacementActivities Tobesubmitted withtheISIPlan

RR006 RequesttoUseCodeCaseN5325 Repair/ReplacementActivity DocumentationRequirementsand InserviceInspectionSummaryReport PreparationandSubmission Tobesubmitted withtheISIPlan

RR007 RequestinAccordancewith10 CFR50.55a(g)(4)(iv)forRepair/Replacement Activities(IWEProgram)

LMT11056 (dated09/28/11)

AwaitingNRCSER

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ThefollowingtablecontainsalistoftheISIBoundaryDrawingsthatareusedinconjunctionwiththeISI ClassificationBasisDocumenttodefinetheboundariesoftheMonticellopipingsystemsthatare examinedinaccordancewithASMESectionXI.TheISIBoundaryDrawingsarelocatedinand maintainedinaccordancewithprocedurePEI010203.

BOUNDARY DRAWINGNO.

SYSTEM/DESCRIPTION 1.51 ISIIndexKey 1.52 MainSteam 1.53 Feedwater 1.54 ReactorCirculation 1.55 CoreSpray 1.56 ResidualHeatRemovalLoopA 1.57 ResidualHeatRemovalLoopB 1.58 HighPressureCoolantInjection(SteamSide) 1.59 HighPressureCoolantInjection(WaterSide) 1.510 ReactorCoreIsolationCooling(SteamSide) 1.511 ReactorCoreIsolationCooling(WaterSide) 1.512 StandbyLiquidControlSystem 1.513 PrimaryContainmentAtmosphericControl 1.514 EmergencyDieselGeneratorEmergencyServiceWater 1.515 EmergencyServiceWater 1.516 ResidualHeatRemovalServiceWater 1.517 HydraulicControlUnits 1.518 ControlRodDrive(ScramDischargeVolumePiping) 1.519 CompressedAir 1.520 DemineralizerWater&ReactorBuildingCoolingWater 1.521 ReactorWaterCleanup&LiquidRadwaste 1.522 TraversingIncoreProbe 1.523 ExcessFlowCheckValves 1.524 NotUsed 1.525 NotUsed 1.526 PrimaryContainmentSampling 1.527 ReactorVesselInstrumentation

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ThefollowingtablecontainsalistoftheISIIsometricDrawingsthatareusedforlocatingthe componentsand/orweldsthatareselectedtobeexaminedduringthecurrentinterval.TheISI IsometricDrawingsarelocatedinandmaintainedinaccordancewithPEI010204.

ISONO.

SYSTEM/DESCRIPTION CLASS1&2DRAWINGS ISIFig.0 ReactorVesselInterior ISIFig.1 ReactorVesselTopHead ISIFig.2 CRDLocationReactorVessel ISIFig.3 ReactorVesselBottomHead ISIFig.4 Circumferential&LongitudinalReactorVesselWelds ISIFig.5 ReactorVesselNozzles ISIFig.6 ReactorVesselBolting ISI1314217A ResidualHeatRemovalASuction ISI1314217B HighPressureCoolantInjection(Water)

ISI1314217C ResidualHeatRemovalBSuction ISI1314218A ResidualHeatRemovalB ISI1314118B ResidualHeatRemovalBDischarge ISI1314218C ResidualHeatRemovalBDischarge ISI1314219A HighPressureCoolantInjection(SteamSide)Discharge ISI1314219B ReactorCoreIsolationCooling(SteamSide)Discharge ISI1314220A CoreSprayASuction ISI1314220B CoreSprayBSuction ISI1314226A CoreSprayBDischarge ISI1314226B CoreSprayBDischarge ISI1314226C CoreSprayBDischarge ISI1314226D CoreSprayBDischarge ISI1314229A ReactorBuildingCoolingWater ISI1314231A CoreSprayADischarge ISI1314231B CoreSprayADischarge ISI1314231C CoreSprayADischarge ISI1314231D CoreSprayADischarge ISI1314233A MainSteamA ISI1314234A MainSteamB ISI1314235A MainSteamC ISI1314236A MainSteamD ISI1314237A ResidualHeatRemovalADischarge ISI1314237B ContainmentSpray(RHRA)

ISI1314237C ResidualHeatRemovalADischarge ISI1314237D ContainmentSpray(RHRA)

ISI1314237E ContainmentSpray(RHRA)

ISI1314240A HighPressureCoolantInjection(WaterSide)Discharge ISI1314240B HighPressureCoolantInjection(WaterSide)Discharge

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ISONO.

SYSTEM/DESCRIPTION ISI1314241A ReactorCoreIsolationCooling(WaterSide)Suction ISI1314242A HighPressureCoolantInjection(SteamSide)

ISI1314243A ReactorCoreIsolationCooling(SteamSide)

ISI1314248A ResidualHeatRemovalServiceWater ISI1314248B ResidualHeatRemovalServiceWater ISI1314249A ResidualHeatRemovalAShutdownCooling ISI1314251A ResidualHeatRemovalA ISI1314251B ResidualHeatRemovalB ISI1314251C ResidualHeatRemovalB ISI1314251D ResidualHeatRemovalB ISI1314252A FeedwaterC&D ISI1314253A FeedwaterA&B ISI1314262 FuelPoolEmergencyCooling ISI1314267 FuelPoolEmergencyCooling ISI16 JetPumpInstrumentNozzle ISI19 ReactorInstrumentNozzles ISI47 ReactorCoreIsolationCoolingPump&Turbine ISI48 ResidualHeatRemovalPumps ISI49 CoreSprayPumpSupports ISI73880A ReactorWaterCleanup ISI742091A RecirculationADrain ISI742101A RecirculationBDrain ISI74215A StandbyLiquidControl ISI782A ReactorHeadVent ISI782AA ReactorHeadVent ISI786A MainSteamCondensateLeakoff ISI790532A ResidualHeatRemovalHeatExchangerA ISI790532B ResidualHeatRemovalHeatExchangerB ISI821A ReactorBottomHeadDrain ISI829242A HighPressureCoolantInjectionPumps ISI829248A HighPressureCoolantInjectionTurbine ISI932681A ControlRodDriveScramHeaderA ISI932683A ControlRodDriveScramHeaderB ISI94699A PrimaryContainment&AtmosphericControl ISI94879A SparePenetrationX47 ISI94966A PrimaryContainment&AtmosphericControl ISI94966B ContainmentAirPurge ISI97003A ResidualHeatRemovalReturnLoopA ISI97003B ResidualHeatRemovalSupplyLoopA ISI97004A ResidualHeatRemovalReturnLoopA ISI97005A RecirculationLoopA ISI97005B RecirculationManifoldA

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ISONO.

SYSTEM/DESCRIPTION ISI97005C RecirculationPumpASupports ISI97006A RecirculationLoopB ISI97006B RecirculationManifoldB ISI97006C RecirculationPumpBSupports ISI97007A ReactorInstrumentNozzleN11B ISI97008A ReactorInstrumentNozzleN11A ISI97027A ResidualHeatRemovalEqualizer ISI105531A StandbyGasTreatment&ReactorPlenum ISI158074A TorusHardPipeVent CLASS3DRAWINGS NDISI100 ResidualHeatRemovalServiceWater NDISI101 ResidualHeatRemovalServiceWater NDISI102 ResidualHeatRemovalServiceWater NDISI103 ResidualHeatRemovalServiceWater NDISI104 ResidualHeatRemovalServiceWater NDISI105 ResidualHeatRemovalServiceWater NDISI106 ResidualHeatRemovalServiceWater NDISI107 ResidualHeatRemovalServiceWater NDISI108 ResidualHeatRemovalServiceWater NDISI109 ResidualHeatRemovalServiceWater NDISI110 ResidualHeatRemovalServiceWater NDISI111 ResidualHeatRemovalServiceWater CLASSMCDRAWINGS ISI829176 ClassMCSupports 1.581 DowncomerRestraints 1.582 VentLine&HeaderRestraints NH95932A RingHeaderSeismicRestraints(Bays14)

NH95932B RingHeaderSeismicRestraints(Bays58)

NH95932C RingHeaderSeismicRestraints(Bays912)

NH95932D RingHeaderSeismicRestraints(Bays1316)

NX829134A VentLine&Header NX829134C Downcomer,VentLine&HeaderSupports NONCODEAUGMENTED NCISI37 ReactorCoreIsolationCoolingFeedwater NCISI51 ControlRodDrivetoReactorWaterCleanup

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CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BA PressureRetainingWeldsinReactorVessel BA B1.11 ReactorVessel CircumferentialShell Welds Volumetric 4

1(1) 25%

AllWelds 1

0 0

BA B1.12 ReactorVessel LongitudinalShellWelds Volumetric 8

8 100%

AllWelds 0

0 8

BA B1.21 ReactorVessel CircumferentialHead Welds Volumetric 2

2 100%

Accessible LengthofAll Welds 0

0 2

BA B1.22 ReactorVessel MeridionalHeadWelds Volumetric 16 16 100%

Accessible LengthofAll Welds 0

0 16 BA B1.30 ReactorVesselShellto FlangeWeld Volumetric 1

1 100%

Weld 0

0 1(2)

BA B1.40 ReactorVesselHeadto FlangeWeld Volumetric andSurface 1

1 100%

Weld 0

0 1(2)

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CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CategoryTotal 32 29

1 0

28

NotesforCat.BA

Note1: RequestforAlternativeRR001wassubmitted03/12/10(LMT10014)touseBWRVIP05.NRCSafetyEvaluationReport wasissued02/08/11approvingthisalternative.Approximately2to3percentofeachcircumferentialweldshallbe examined.WeldsVCBA2,VCBB3,andVCBB4willbeexaminedwiththelongitudinalweldsattheintersectionpoint.

VCBB1willbeexaminedthroughtheNozzleWindowN1A.

Note2: DeferralispermissibleinsuccessiveintervalsperNote5ofItemNumbersB1.30andB1.40if(a)nowelded repair/replacementactivitieshavebeenperformedeitheronshelltoflangeorheadtoflange;and(b)neithertheshellto flangeweldnorheadtoflangeweldcontainsidentifiedflawsorrelevantconditionsthatrequiresuccessiveinspectionin accordancewithIWB2420(b).

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CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BD FullPenetrationWeldedNozzlesinVessels BD B3.90 ReactorVesselNozzle toVesselWelds Volumetric 30(1) 16 55%(2)

Sameas1st Interval 5

6 5

BD B3.100 ReactorVesselNozzle InsideRadiusSection Volumetric 30(1) 16 55%(2)

Sameas1st Interval 5

6 5

CategoryTotal 58 32

10 12 10 NotesforCat.BD

Note1:BottomHeadDrainNozzle(N15)isinaccessibleandexemptedperIWB1220(c).

Note2:RequestforAlternative(RR002)usesCodeCaseN702forselectionofNozzletoVesselandInnerRadiusSectiononthe followingnozzles(N2,N3,N5,N6,andN8).Atotalof7nozzletovesselandinnerradiussectionswereselectedfor examinationunderRR002.TheCodeCaseallows25%tobeselectedforexaminationovertheinterval.RecirculationOutlet Nozzle(N1)didnotpassthecriteriaandthereforewasnotincludedinthe25%population.BWRFeedwaterandCRDNozzles areexcluded.

MonticelloNuclearGeneratingPlant

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BG1 PressureRetainingBolting,GreaterThan2in.(50mm)inDiameter BG1 B6.10 ReactorVesselClosure HeadNuts Visual,VT1 1(5) 1 100%

Sameasfor 1stinterval 0

0 1

BG1 B6.20 ReactorVesselClosure Studs Volumetric(4) 1(5) 1 100%

Sameasfor 1stinterval 0

0 1

BG1 B6.40 ReactorVesselThreads inFlange Volumetric 1(5) 1 100%

Sameasfor 1stinterval 0

0 1

BG1 B6.50 ReactorVesselClosure Washers,Bushings Visual,VT1 2(5)(6) 2 100%

Sameasfor 1stinterval 0

0 2

BG1 B6.180 PumpBoltsandStuds Volumetric(4) 2 1

50%(2)

Sameasfor 1stinterval 1

0 0

BG1 B6.190 PumpsFlangeSurface whenconnection disassembled Visual,VT1 2

0 0%(1)(3)

Sameasfor 1stinterval 0

0 0

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BG1 B6.200 PumpsNuts,Bushings, andWashers Visual,VT1 2

0 0%(1)(3)

Sameasfor 1stinterval 0

0 0

CategoryTotal 11 6

1 0

5 NotesforCat.BG1 Note1:NotRequiredunlessdisassembled Note2: Volumetricexaminationofboltingofheatexchangers,pump,orvalvesmaybeconductedononeheatexchanger,one pump,oronevalveamongagroupofheatexchangers,pumps,orvalvesthataresimilarindesign,type,andfunction.(Ref.

TableIWB25001,ExaminationCategoryBG1,Note3).TherearetwoReactorRecirculationPumpswith16studseach.

Therefore,onlyoneofthepumpswillbeexamined.

Note3:Forheatexchangers,piping,pumps,andvalves,visualexaminationsarelimitedtocomponentsselectedforexamination underExaminationCategoriesBB,BJ,BL2,andBM2.(Ref.TableIWB25001,ExaminationCategoryBG1,Note4)

Note4: Ifboltsorstudsareremovedforexamination,surfaceexaminationmeetingtheacceptancestandardsofIWB3515maybe substitutedforvolumetricexamination.

Note5: Thereareatotalof64reactorpressurevesselstuds,nuts,bushings,andwashers.Inadditionthereare64threadsin flangeligamentstoexamine.

Note6: ForItemNumberB6.50,therearetwoitems,oneforthewashersandoneforthebushings.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BG2 PressureRetainingBolting,2in.(50mm)andLessinDiameter BG2 B7.10 ReactorVesselBolts, Studs,andNuts Visual,VT1 2

0 0%(1)

Sameasfor 1stinterval(2) 0 0

0 BG2 B7.50 PipingBolts,Studs,and Nuts Visual,VT1 31 0

0%(1)(4)

Sameasfor 1stinterval(2) 0 0

0 BG2 B7.70 ValvesBolts,Studs,and Nuts Visual,VT1 42 0

0%(1)(5)

Sameasfor 1stinterval (2)(3) 0 0

0 CategoryTotal 75 0

0 0

0

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period

NotesforCat.BG2

Note1:Notrequiredunlessdisassembled Note2:Examinationisonlyrequiredonceperinterval Note3:Forcomponentsotherthanpiping,examinationsarelimitedtocomponentsselectedforexaminationunderExamination CategoriesBB,BL2,andBM2.(Ref.TableIWB25001,ExaminationCategoryBG2,Note2)

Note4:Examinationislimitedtoatleastonepipingflangeineachgroupofpipingflangesthatareofthesimilardesign,size, function,andserviceinthesystem.

Note5:OnlyonevalveofeachgroupofvalvesisrequiredasoutlinedinBM2

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BK WeldedAttachmentsforVessels,Piping,Pumps,andValves BK B10.10 PressureVesselsWelded Attachments Surface 5

1 20%(1)

Sameasfor 1stinterval 0

0 1

BK B10.20 PipingWelded Attachments Surface 44 2

4.5%(2)

Sameasfor 1stinterval 1

1 0

BK B10.30 PumpWelded Attachments Surface 6

1 16.7%(2)

Sameasfor 1stinterval 1

0 0

CategoryTotal 55 4

2 1

1 NotesforCat.BK Note1:Formultiplevesselsofsimilardesign,function,andservice,onlyoneweldedattachmentofonlyoneofthemultiplevessels shallbeselectedforexamination.Forsinglevessels,onlyoneweldedattachmentshallbeselectedforexamination.The weldedattachmentselectedforexamination,shallbeanattachmentundercontinuousloadduringnormaloperationoran attachmentsubjecttoapotentialintermittentloadduringnormaloperation.

Note2: Forpipingandpumps,asampleof10%oftheweldedattachmentsassociatedwiththecomponentsupportsselectedfor examinationunderIWF2510shallbeexamined.Thistenpercentsampleisequivalentto4.5%ofallpipingattachments and16.7%ofallpumpattachments.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BL2 PumpCasings BL2 B12.20 PumpsPumpCasing (BL2)

Visual,VT3 2

0 0%(1)(2)

Sameasfor firstinterval

0 0

0 CategoryTotal 2

0

0 0

0 NotesforCat.BL2

Note1:Examinationislimitedtoatleastonepumpineachgroupofpumpsperformingsimilarfunctionsinthesystem.

Note2:Notrequiredunlessdisassembled

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BM2 ValveBodies BM2 B12.50 ValveBody,Exceeding NPS4(DN100)(BM2)

Visual,VT3 43 0

0%(1)(2)(3)

Sameasfor firstinterval

0 0

0 CategoryTotal 43 0

0 0

0 Notesfor Cat.BM2

Note1:Examinationislimitedtoatleastonevalveineachgroupofvalvesthatareofthesamesize,constructuraldesign, manufacturingmethod,andthatperformsimilarfunctionsinthesystem.

Note2:Notrequiredunlessdisassembled Note3:Valveshavebeengroupedinto14categoriesusingschedulingnotesBB,EE,FF,GG,HH,II,JJ,KK,LL,NN,OO,PP,QQ,andRR.

Onefromeachgroupisrequiredtobeexaminedperinterval,ifdisassembled,totaling14valves.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BN1 InteriorofReactorVessel BN1 B13.10 ReactorVessel,Vessel Interior(BN1)

Visual,VT3 1

1 100%

Each inspection period(2) 1 1

1 CategoryTotal 1

1(1)

1 1

1 Notesfor Cat.BN1

Note1:Examinationofthisitemnumberisrequiredeachperiod. Becausetheseexaminationsareperformedeveryperiod,the numberrequiredduringtheintervalisthreetimesthenumberofcomponents.Inordertokeepthepercentagesaccurate, onlythenumberofcomponentsisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequiredtobe completedovertheinterval.

Note2:Examinationislimitedtothespacesaboveandbelowthecoremadeaccessiblebyremovalofcomponentsduringnormal refuelingoperationslookingforloosepartsorforeignmaterial.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BN2 WeldedCoreSupportStructuresandInteriorAttachmentstoReactorVessels BN2 B13.20 ReactorVessel(BWR)

InteriorAttachments WithinBeltlineRegion (BN2)

Visual,VT1 15 15 100%

Sameasfor 1stinterval 0

0 15 BN2 B13.30 ReactorVessel(BWR)

InteriorAttachments BeyondBeltlineRegion (BN2)

Visual,VT3 25 25 100%

Sameasfor 1stinterval 0

0 25 BN2 B13.40 CoreSupportStructure Visual,VT3 20 20 100%

Sameasfor 1stInterval 0

0 20 CategoryTotal 60 60

0 0

60 Notesfor Cat.BN2 None

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BO PressureRetainingWeldsinControlRodDriveandInstrumentNozzleHousings BO B14.10 ReactorVessel(BWR)

WeldsinControlRod DriveCRDHousing Volumetric orsurface 48 6

12.5%

10%

peripheral CRD housings(1) 0 0

6 CategoryTotal 48(2) 6(2)

0 0

6 NotesforCat.BO

Note1:Thereare24PeripheralCRDs,10%of24is3.

Note2:TherearetwoweldsperPeripheralCRD,thereforethetotalrequiredtobeexaminedistwicethenumberofCRDsselected forexamination.Thisresultsinatotalofsix(6)weldsbeingselectedforexaminationor12.5%oftotalpopulation.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period BP AllPressureRetainingComponents BP B15.10 Pressureretaining components(IWB 5222(a))

Visual,VT2 1

1(3) 100%

Each refueling outage(1) 2(3) 2(3) 0 BP B15.20 Pressureretaining components(IWB 5222(b))

Visual,VT2 1

1 100%

Onceper interval(2) 0 0

1 CategoryTotal 2

2

2 2

1 NotesforCat.BP

Note1:Thesystemleakagetest(IWB5220)shallbeconductedpriortoplantstartupfollowingareactorrefuelingoutage.

Note2:Thesystemleakagetest(IWB5220)oftheboundaryofIWB5222(b)shallbeperformedatorneartheendoftheinterval.

Note3:Becausetheseexaminationsareperformedeveryoutage,thenumberrequiredduringtheintervalisfourtimesthenumber ofproceduresscheduled.Inordertokeepthepercentagesaccurate,onlythenumberofproceduresscheduledisreflected inthecategorytotalandnotthetotalnumberofexaminationsrequiredtobecompletedovertheinterval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CA PressureRetainingWeldsinPressureVessels CA C1.10 PressureVesselsShell CircumferentialWelds Volumetric 4

2 50%(1)(2)

Each inspection interval 1

0 1

CA C1.20 PressureVesselsHead CircumferentialWelds Volumetric 4

2 50%(1)(3)

Each inspection interval 0

1 1

CategoryTotal 8

4

1 1

2

NotesforCat.CA

Note1:Theexaminationmaybelimitedtoonevesselamongthegroupofvesselsofsimilardesign,size,andfunction.(Ref.Table IWC25001,ExaminationCategoryCA,Note3)

Note2:Thereare2circumferentialshellweldsoneachRHRHX,requiringonly1RHRHXtobescheduledor2of4shellweldsare requiredtobeexaminedfor50%

Note3:Thereare2circumferentialheadweldsoneachRHRHX,requiringonly1RHRHXtobescheduledor2of4head circumferentialweldsarerequiredtobeexaminedfor50%.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CB PressureRetainingNozzleWeldsinVessels CB C2.31 NozzlesWithReinforcing PlateinVessels>1/2in.

(13mm)Nominal ThicknessReinforcing PlateWeldstoNozzle andVessel Surface 4

2 50%(1)

Each inspection interval 1

1 0

CB C2.33 NozzlesWithReinforcing PlateinVessels>1/2in.

(13mm)Nominal ThicknessNozzleto Shell(NozzletoHeador NozzletoNozzle)Welds WhenInsideofVesselIs Inaccessible Visual,VT2 4

2(3) 50%(1)(2)

Each inspection period 2

2 2

CategoryTotal 8

4

3 3

2

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period

NotesforCat.CB

Note1:Theexaminationmaybelimitedtoonevesselordistributedamongthegroupofvesselsofsimilardesign,size,andfunction.

(Ref.TableIWC25001,ExaminationCategoryCB,Note4)

Note2:Thetelltaleholeinthereinforcingplateshallbeexaminedforevidenceofleakagewhilevesselisundergoingthesystem leakagetest(eachperiod)asrequiredbyExaminationCategoryCH.

Note3:Becausetheseexaminationsareperformedeveryperiod,thenumberrequiredduringtheintervalisthreetimesthenumber ofcomponentsselectedforexamination.Inordertokeepthepercentagesaccurate,onlythenumberofcomponents selectedisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequiredtobecompletedoverthe interval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CC WeldedAttachmentsforVessels,Piping,Pumps,andValves CC C3.10 PressureVesselsWelded Attachments(1)

Surface 6

1 16.7%(2)

Each identified occurrence andeach inspection interval 1

0 0

CC C3.20 PipingWelded Attachments Surface 78(5) 2 2.6%(3)(4)

Each identified occurrence andeach inspection interval 1

0 1

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CC C3.30 PumpWelded Attachments Surface 6

1 16.7%(3)(4)

Each identified occurrence andeach inspection interval 0

1 0

CategoryTotal 90 4

2 1

1

NotesforCat.CC

Note1:Formultiplevesselsofsimilardesign,function,andservice,onlyoneweldedattachmentofonlyoneofthemultiplevessels shallbeselectedforexamination.Forsinglevessels,onlyoneweldedattachmentshallbeselectedforexamination.(Ref.

TableIWC25001,ExaminationCategoryCC,Note4)

Note2:Thereare3weldedattachmentsoneachHeatExchanger,therefore1of6weldedattachmentsarerequiredtobeexamined for16.7%

Note3:Forpipingandpumpweldedattachments,asampleof10%oftheweldedattachmentsassociatedwiththecomponent supportsselectedforexaminationunderIWF2510shallbeexamined.

Note4:Examinationisrequiredwhenevercomponentsupportmemberdeformationisidentified.(Ref.TableIWC25001, ExaminationCategoryCC,Note6)

Note5:Thereare80componentsinC3.20,but2ofthemdonotrequireexamination(Ref.TableIWC25001,Examination CategoryCC,Note1(b)).

MonticelloNuclearGeneratingPlant

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period CH AllPressureRetainingComponents CH C7.10 Systemleakagetest (IWC5220)

Visual, VT2(1) 11(2) 11(2)

Each inspection period 11(2) 11(2) 11(2)

CategoryTotal 11 11

11 11 11 NotesforCat.CH

Note1:VisualexaminationofIWA5240 Note2:Thereare11surveillanceproceduresthataddresseachsystem(loopofeachsystemasapplicable).Thesystemsincluded areSBLC,CoreSpray,RHR,HPCI,RCIC,Feedwater,CRDH,RWCU.Eachprocedureiscompletedeachperiod.Becausethese examinationsareperformedeveryperiod,thenumberrequiredduringtheintervalisthreetimesthenumberofprocedures scheduled.Inordertokeepthepercentagesaccurate,onlythenumberofproceduresscheduledisreflectedinthecategory totalandnotthetotalnumberofexaminationsrequiredtobecompletedovertheinterval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period DA WeldedAttachmentsforVessels,Piping,Pumps,andValves DA D1.20 PipingWelded Attachments Visual,VT1 14 2

10%(1)

Each identified occurrence andeach inspection interval(2) 0 1

1 CategoryTotal 14 2

0 1

1 NotesforCat.DA

Note1:Selectedsamplesofweldedattachmentsshallbeexaminedeachinspectioninterval.Allweldedattachmentsselectedfor examinationshallbethosemostsubjecttocorrosion,suchastheweldedattachmentsoftheServiceWaterorEmergency ServiceWatersystems.Forweldedattachmentsofpiping,a10%sampleshallbeselectedforexamination.Thispercentage sampleshallbeproportionaltothetotalnumberofnonexemptweldedattachmentsconnectedtothepipingineachsystem subjecttotheseexaminations.(Ref.TableIWD25001,ExaminationCategoryDA,Note3).

Note2:Examinationisrequiredwhenevercomponentsupportmemberdeformationisidentified.(Ref.TableIWD25001, ExaminationCategoryDA,Note4)

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period DB PressureRetainingComponents DB D2.10 SystemLeakageTest (IWD5220)

Visual,VT2 8(1) 8(1)

Each inspection period 8(1) 8(1) 8(1)

CategoryTotal 8

8

8 8

8 NoteforCat.DB

Note1:Thereare8surveillanceproceduresthataddresseachsystem(loopofeachsystemasapplicable).Thesystemsincludedare RHRServiceWater,EmergencyDieselEmergencyServiceWater,EmergencyServiceWater,HPCIandRCIC.Eachprocedure isscheduledeachperiod.Becausetheseexaminationsareperformedeveryperiod,thenumberrequiredduringtheinterval isthreetimesthenumberofproceduresscheduled.Inordertokeepthepercentagesaccurate,onlythenumberof proceduresscheduledisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequiredtobecompleted overtheinterval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period FA Supports FA F1.10a Class1PipingSupports OneDirectional Visual,VT3 49 12 (1)

Each inspection interval 4

4 5

FA F1.10b Class1PipingSupports Multidirectional Visual,VT3 31 8

(1)

Each inspection interval 3

3 2

FA F1.10c Class1PipingSupports ThermalMovement Visual,VT3 64 16 (1)

Each inspection interval 7

5 6

FA F1.10 TotalClass1Piping Supports Visual,VT3 144 36(2) 25%

Each inspection interval 14 12 13 FA F1.20a Class2PipingSupports OneDirectional Visual,VT3 123 19 (1)

Each inspection interval 6

6 7

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period FA F1.20b Class2PipingSupports Multidirectional Visual,VT3 78 12 (1)

Each inspection interval 6

3 3

FA F1.20c Class2PipingSupports ThermalMovement Visual,VT3 67 10 (1)

Each inspection interval 4

3 4

FA F1.20 TotalClass2Piping Supports Visual,VT3 268 41(2) 15%

Each inspection interval 16 12 14 FA F1.30a Class3PipingSupports OneDirectional Visual,VT3 69 7

(1)

Each inspection interval 2

2 3

FA F1.30b Class3PipingSupports Multidirectional Visual,VT3 29 3

(1)

Each inspection interval 1

1 1

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period FA F1.30c Class3PipingSupports ThermalMovement Visual,VT3 1

1 (1)

Each inspection interval 0

1 0

FA F1.30 Class3PipingSupports Visual,VT3 99 10(2) 10%

Each inspection interval 3

4 4

FA F1.40a Supportsotherthan PipingSupports-One Directional Visual,VT3 23 15 (3)

Each inspection interval 3

8 4

FA F1.40b Supportsotherthan PipingSupportsMulti directional Visual,VT3 6

3 (3)

Each inspection interval 1

0 2

FA F1.40c Supportsotherthan PipingSupports ThermalMovement Visual,VT3 10 7

(3)

Each inspection interval 1

2 4

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period FA F1.40 Supportsotherthan PipingSupports(Class 1,2,and3)

Visual,VT3 39 25 64%(4)

Each inspection interval(2) 5 10 10 CategoryTotal 550 112 (1)(2)

38 39 41 NotesforCat.FA Note1:Thetotalpercentagesampleshallbecomprisedofsupportsfromeachsystem,wheretheindividualsamplesizesare proportionaltothetotalnumberofnonexemptsupportsofeachtypeandfunctionwithineachsystem.(Ref.TableIWF 25001,ExaminationCategoryFA,Note2)

Note2:BasedonEngineeringJudgmentwiththeProrationbySystemandItemNumberasrequiredbyFootnote1above,thetotal numberofsupportsselectedforexaminationexceedsthenumberofsupportsrequired.Thenumberofsupportsselected arereflectedintheFirst,Second,andThirdPeriodcolumnswhereasthetotalnumberofsupportsrequiredisreflectedinthe RequiredtobeExaminationDuringtheIntervalcolumn.

Note3:Formultiplecomponentsotherthanpiping,withinasystemofsimilardesign,function,andservice,thesupportsofonlyone ofthemultiplecomponentsarerequiredtobeexamined.(Ref.TableIWF25001,ExaminationCategoryFA,Note3)

Note4:OneRPV(5supports),oneoftwoReactorRecirculationPumps(7supportseach(14total)),oneoffourRHRpumps(1 supporteach(4total)),oneoftwoRHRHeatExchangers(3supportseach(6total)),oneoftwoCSPumps(1supporteach(2 total)),oneHPCIPump(8supports).Therefore25of39componentsupportsarerequiredtobeexaminedfor64%.

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CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period RA RiskInformedPipingWelds RA R1.11 N716ElementsSubject toThermalFatigue Volumetric 101 19 18.8%(1)(3)(4)

Each Inspection Interval 10 2

7 RA R1.20s N716Elementsnot SubjecttoaDamage Mechanism Visual,VT2 257 20(2) 7.8%(2)

Each refueling outage 40 40 20 RA R1.20 N716Elementsnot SubjecttoaDamage Mechanism Volumetric 453 48 10.6%(1)(3)

Each Inspection Interval 14 22 12 CategoryTotal 811 87 11%

64 64 39

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CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period NotesforCat.RA

Note1:PercentagesweredeterminedusingSICalc1000515.302.

Note2:TheseweldsareSocketWelds<NPS2andrequireaVisual,VT2ExaminationeachrefuelingoutageperNote9ofCodeCase N716.Becausetheseexaminationsareperformedeveryoutage,thenumberrequiredduringtheintervalisfivetimesthe numberofcomponentsselectedforexamination.Inordertokeepthepercentagesaccurate,onlythenumberof componentsselectedisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequiredtobecompleted overtheinterval.

Note3:Theexaminationshallincludeanylongitudinalweldsatthelocationselectedforexamination.Thelongitudinalweld examinationrequirementsshallbemetforbothtransverseandparallelflawswithintheexaminationvolumedefinedfor theintersectingcircumferentialwelds.

Note4:ThelengthoftheexaminationvolumeshowninFig.IWB25008(c)shallbeincreasedbyenoughdistancetoincludeeach sideofthebasemetalthicknesstransitionorcounterboretransition.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period NUREG0619 BWRControlRodDriveReturnLineNozzleCrackingPostModification NC NCR95 068 Assureintegrityofthe reroutedpipingatthe teeonIsometricNX 1314249A(NCISI51),

LineREW63DC.

Volumetric 3

3(1) 100%

Each schedule outage 6

6 3

CategoryTotal 3

3

6 6

3 NoteforCat.

NUREG0619 Note1:CommitmentistoperformavolumetricexaminationofWeldsW11,W12,andW13eachscheduledoutage.Sothetotal numberofitemsrequiredisfivetimes(5scheduledoutagesinthe5th10yearinterval)thenumberofitems.Becausethese examinationsareperformedeveryoutage,thenumberrequiredduringtheintervalisfivetimesthenumberofcomponents selectedforexamination.Inordertokeepthepercentagesaccurate,onlythenumberofcomponentsselectedfor examinationisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequiredtobecompletedoverthe interval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period Mod79Z018 RWCUReturnLineModification NC NCR95 068 RCICweldsunder Modification79Z018as onISIISONCISI37.

Volumetric 6

6 100%

Every scheduled outage 12 12 6

CategoryTotal 6

6

12 12 6

NotesforCat.

Mod79Z018

Note1: CommitmentistoperformavolumetricexaminationofWeldsW1,W2,W3,W4,W12andW12A(ISONCISI37)each scheduledoutage.Sothetotalnumberofitemsrequiredisfivetimes(5scheduledoutagesinthe5th10yearinterval)the numberofitems.Becausetheseexaminationsareperformedeveryoutage,thenumberrequiredduringtheintervalisfive timesthenumberofcomponentsselectedforexamination.Inordertokeepthepercentagesaccurate,onlythenumberof componentsselectedforexaminationisreflectedinthecategorytotalandnotthetotalnumberofexaminationsrequired tobecompletedovertheinterval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period HELB HighEnergyLineBreak HELB RA GenericLetter8711 Volumetric 42 42(1) 100%

Every Inspection Interval 5

23 14 CategoryTotal 42 42

5 23 14 NoteforCat.HELB

Note1:Aminimumof10%ofthetotalpopulationisrequiredtobeselectedforexaminationunderCodeCaseN716.Actual numberselectedwas17orabout40%.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period OE23699 StandbyLiquidControlTank NC NCSAC VerifyStructural IntegrityoftheSBLC Tank Visual(1) 1 1

100%

Every inspection interval 0

1 0

CategoryTotal 1

1

0 1

0

NoteforOE23699

Note1:Requirementistoperformavisualexaminationofthetankinternalseveryinterval.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period LicenseRenewal M05011A ClassMCSupports LicenseRenewalAgingManagementPlansandCommitments FA F1.40a Supportsotherthan PipingSupports-One Directional Visual,VT3 6

6 100%

Each inspection interval 0

3 3

FA F1.40b Supportsotherthan PipingSupportsMulti directional Visual,VT3 166 166 100%

Each inspection interval 80 46 40 CategoryTotal 172 172

80 49 43

NotesforClassMC Supports

None

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period LicenseRenewal USARAppendixK (K2.1.1)

SmallBoreClass1Piping RA R1.20s Class1smallboreSS welds>NPS2and<NPS4 Volumetric(2) 10 2

10%(1)

Each inspection interval 0

1 1

CategoryTotal 10 2

10%

Each inspection interval 0

1 1

Notesfor AppendixK

Note1:Examine10%eachinspectioninterval(2weldswereselectedunderCodeCaseN716(RR003)).

Note2: ExamineinaccordancewithAppendixVIII.WeldVolumerequiredisspecifiedbyCategoryBForBJasapplicable.

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forApprovals

CodeCategorySummary Category Item Number Description Exam Method Numberof Components inItemNo.

Requiredto be Examined During Interval Examination Percentage Required Numberto beExamined inInterval Number tobe Examined inFirst Period Number tobe Examined inSecond Period Numberto be Examinedin Third Period LicenseRenewal M05020A M05021A M05022A FeedwaterNozzles BD B3.100 NozzleInnerRadius Sections Volumetric(2) 4 4

100%(1)

Each inspection interval 1

2 1

CategoryTotal 4

4

1 2

1 NotesforFW Nozzles Note1:Successiveintervalexaminationsshallbeapproximately10yearsfrompreviousexamination.

Note2:TherequiredexaminationvolumeisbasedonEPRIModelingReportIR200463andextendsbeyondthevolumespecifiedin FigureIWB25007(b).

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ThisisRevision0oftheMonticelloNuclearGeneratingPlant InserviceInspection(ISI)Planforthe5thTenYearInspectionInterval ThereforethereisnoRIISILivingProgramUpdateatthistime.