View source for GNRO-2017/00009, Proposed Alternative with 10 CFR 50.55a(z)(1), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines

{{Adams
| number = ML17074A625
| issue date = 03/15/2017
| title = Proposed Alternative with 10 CFR 50.55a(z)(1), Use of Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines
| author name = Nadeau J
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000416
| license number = NPR-029
| contact person = 
| case reference number = GNRO-2017/00009
| document type = Letter type:GNRO, Operating Procedures
| page count = 27
}}

=Text=
{{#Wiki_filter:*Entergy GNRO-2017/00009 March 15,2017 u.s.Nuclear Regulatory Commission Attn: DocumentControlDesk Washington,DC20555-0001 Entergy-Operations, Inc.P.O.Box 756Port-Gibson,MS39150JamesNadeau Regulatory Assurance ManagerTel.(601)437-2103 

==SUBJECT:==

==DearSirorMadam:==

Proposed Alternativewith10CFR 50.55a(z)(1),UseofBoiling Water ReactorVesseland Internals Project (BWRVIP)GuidelinesatGrandGulf Nuclear StationGrandGulf Nuclear Station DocketNo.50-416LicenseNo.
NPF-29 Pursuantto10CodeofFederal Regulations (CFR)50.55a(z)(1), Entergy herebyrequestsan alternativeforGrandGulf NuclearStation(GGNS), specific portionsofthe American Society of Mechanical Engineers(ASME)Boilerand PressureVesselCode,SectionXI,"Rulesfor service Inspection of NuclearPowerPlant Components,"onthebasisthatthe proposed alternative provides an acceptablelevelof qualityandsafety.Entergyis requesting an alternativetoASMESectionXI,2007Edition throughthe2008Addenda,Table IWB-2500-1, Examination CategoriesB-N-1andB-N-2,ItemNos.B13.10,whichrequires examination of accessibleareasofthe reactor vessel interior each in-service inspection
('-$1)intervalbytheVT-3 method(B-N-1),B13.20 examination of accessible interior attachmentweldswithinthe beltlineregioneachintervalbytheVT-1 method(B-N-2),B13.30, examination of accessible interior attachmentweldsbeyondthe beltlineregioneachintervalbytheVT-3 method(B-N-2),andB13.40, examination of accessible surfacesoftheweldedcore support structureeachintervalbytheVT-3 method(B-N-2).Thisreliefrequestis associatedwithGGNSfourth 10-yearlSIinterval,whichis currently scheduledtobeginonJune2,2017 andendsonJune 1,2027.ThelSICodeofRecordforthefourthintervalisASMESectionXI,2007edition throughthe2008 Addenda.EntergyrequestNRCStaffreviewand approvalofthis proposed GGNS alternativeonorbeforeMarch23,2018.
GNRO-2017/00009Page2of3Therearenoregulatory commitmentsmadeinthissubmittal.Ifyouhaveany questionsorrequireadditionalinformation,pleasecontactJamesNadeauat 601-437-2103.
Regulatory Assurance Manager IN:sgd 

==Attachment:==
Enclosure1:Enclosure2:
Enclosure3:
Proposed AlternativeRequestin Accordancewith10CFR50.55a(z)(1)
ComparisonofASMECodeSectionXITableIWB-2500-1andVessel Attachment Welds ComparisonofASMESectionXICodeExamination RequirementstoBWRVIP Examination RequirementsGrandGulf ReactorVesselInternalInspectionHistorycc:with Attachment and EnclosuresMr.JohnP.Boska,Project ManagerPlantLicensingBranch 1-1DivisionofOperating Reactor LicensingOfficeof NuclearReactorRegulation U.S.Nuclear Regulatory CommissionMailStop 0-8-C2Washington,DC20555 GNRO-2017/00009Page3of3cc:without Attachment and EnclosuresMr.KrissKennedy Regional Administrator,RegionIVU.S.Nuclear Regulatory Commission1600EastLamar BoulevardArlington,TX76011-4511 U.S.Nuclear Regulatory CommissionATTN:Mr.SivaLingam, NRR/DORL (w/2)MailStop OWFN/8 B111555RockvillePikeRockville,MD 20852-2738NRCSeniorResident InspectorGrandGulf Nuclear StationPortGibson,MS39150Dr.MaryCurrier,M.D.,M.P.HStateHealthOfficer Mississippi DepartmentofHealthP.O.Box1700Jackson,MS 39215-1700 Email: mary.currier@msdh.ms.gov GNRO-2017/00009 Attachment Attachment to GNRO-2017/00009 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1)
GNRO-2017/00009 Attachment Entergy Nuclear Operations, Inc.GrandGulf NuclearStation(GGNS),Unit1UseofBoiling Water ReactorVesseland Internals Project (BWRVIP)GuidelinesinLieuof SpecificASMECode RequirementsFourthInterval In-service Inspection(lSI)Program Request No.GG-ISI-020 Proposed Alternative Request in Accordancewith10CFR50.55a(z)(1)
-AcceptableLevelof Quality and Safety-1.ASMECode Component(s)
AffectedCodeClass:
Examination Category: Item Number(s):Unit/Inspection Interval Applicability:
American Society of Mechanical Engineers (ASME)CodeClass1 B-N-1 (Interior of ReactorVessel),B-N-2(WeldedCore Supports Structures and Interior AttachmentstoReactorVessel)B13.10(VesselInterior),B13.20 (Interior Attachments withinBeltlineRegion),B13.30 (Interior AttachmentsbeyondBeltlineRegion),andB13.40(Core Support Structure)GGNS,Unit1,4th 10-yearlSIIntervalstartingJune2,2017andendingonJune1,2027 2.Applicable Code Requirement(s)ASMESectionXICode,2007Edition throughthe2008Addenda,requiresthe examinationofcomponents,withintheReactor PressureVessel.These examinations are includedinTable IWB-2500-1, Examinations CategoriesB-N-1andB-N-2and identifiedwiththe followingItemNumbers:*ItemNo.B13.10-Examine accessibleareasofthereactorvessel interior eachperiodbytheVT-3method(B-N-1)*ItemNo.B13.20-Examine accessible interior attachmentweldswithinthebeltlineregioneachintervalbytheVT-1method(B-N-2)*ItemNo.B13.30-Examinethe accessible interior attachmentweldsbeyondthebeltlineregioneachintervalbytheVT-3 method (B-N-2)*ItemNo.B13.40-Examine accessible surfacesoftheweldedcore support structureeachintervalbytheVT-3 method (B-N-2)These examinations are performed to assess the structural integrityofthereactorvesselinterior,its welded attachmentsandtheweldedcore support structurewithintheboiling waterreactorpressurevessel.Page1of7 GNRO-2017/00009 Attachment3.ReasonforRequestEntergyisrequestingNRC authorizationofthis proposed alternativetotheASMESectionXICoderequirementsprovidedaboveonthebasisthattheuseoftheBWRVIP guidelines discussedbelowwillprovidean acceptablelevelof qualityandsafety.TheBWRVIPInspectionandEvaluation(I&E) guidelines have recommended aggressive specificinspectionsbyBWR operators to completely identifymaterialconditionissueswithBWRcomponents.Awealthofinspectiondatahasbeen gatheredduringthese inspectionsacrosstheBWRindustry.TheBWRVIPI&E guidelinesfocusonspecificand susceptible components, specify appropriate inspectionmethodscapableofidentifyingreal anticipated degradation mechanisms,andrequiredreexaminationatconservativeintervals.Incontrast,theASMESectionXICode requirementswerepreparedbeforetheBWRVIPinitiativeandhavenotevolvedwithBWR inspection experience.4.Proposed AlternativeandBasisforUse Proposed AlternativePursuantto10CFR50.55a(z)(1),Entergyrequests authorizationtoutilizethe alternativerequirementsof BWRVIP Guidelinesinlieuofthe requirementsofASMESectionXI.The proposed alternativeisdetailedinEnclosure1,Table1,"ComparisonofASMECodeSectionXITableIWB-2500-1ExaminationCategoryB-N-1andB-N-2 RequirementstoBWRVIP Guidance Requirements,"thatshowsacomparisonbetweentheexistingASMESectionXICodeandBWRVIP requirementsthatwillbeusedunderthisalternative.Specifically,Entergywillsatisfythe Examination CategoryB-N-1andB-N-2 requirementsatGGNSasdescribedinEnclosure1,Table1in accordancewithBWRVIP guidelinesinlieuoftheassociatedASMESectionXICode requirements, including examination method, examinationvolume,frequency,training,successiveandadditional examinations, flaw evaluations,andreporting.Notallofthe components addressedbytheBWRVIP guidelines are componentsthatrequireASMESectionXICode examinations,butthe particular guidelinesthatare applicabletoASMESectionXICode componentsarelistedbelowalongwiththe BWRVIP-94 AdministrativeGuidethatGGNSwilluseto implementthisalternative:
BWRVIP-03 BWRVIP-18-R1-A BWRVIP-25 BWRVIP-26-A BWRVIP-27-A BWRVIP-38Page2of7"BWRVesselandInternalsProject,ReactorPressureVesseland Internal Examination Guidelines""BWRCoreSprayInternalsInspectionandFlawEvaluation Guidelines""BWRCorePlate InspectionandFlawEvaluation Guidelines"BWRTopGuide InspectionandFlawEvaluation Guidelines"BWR StandbyLiquidControl System/CorePlatedPInspectionandFlawEvaluation Guidelines""BWRShroud Support InspectionandFlawEvaluation Guidelines" GNRO-2017/00009 Attachment BWRVIP-41-R3"BWRJetPump Assembly InspectionandFlawEvaluation Guidelines BWRVIP-47-A"BWRLowerPlenum InspectionandFlawEvaluation Guidelines BWRVIP-48-A(1)"VessellD Attachment Weld InspectionandFlawEvaluation Guidelines"BWRVIP-76-R1-A (2)"BWRCoreShroud InspectionandFlawEvaluation Guidelines" BWRVIP-94"BWRVesseland InternalsProject"Program Implementation Guide" BWRVI P-1 OO-A (2)"Updated AssessmentoftheFracture Toughness of Irradiated StainlessSteelforBWRCoreShrouds" Notes:(1)Currently,therearenoexisting BWRVIP guidelinesorASMESectionXICode requirementsregardingthe feedwater spargersexceptfor BWRVIP-48-A which governsinspectionofreactorvesselinternal attachmentwelds,namelythe feedwater spargerbrackets.GGNSwill continuetouse NUREG-0619onthe feedwater sparger piping,spacerbrackets,pins,endbrackets,flowholesand spargerteeweldsoutsideofthis request.(2)Ifflaw evaluationsarerequiredfor BWRVIP-76-R1-A examinations,thefracture toughnessvaluesofBWRVIP-1 OO-Awillbeutilized.
BWRVIP-138 BWRVIP-139 BWRVIP-183"BWRVIPUpdatedJetPumpBeam InspectionandFlawEvaluation""BWRVessel Internals Project, Steam-Dryer InspectionandFlaw Evaluation Guidelines""BWRVessel InternalsProject,TopGuideGridBeamInspectionandFlawEvaluation Guidelines" Note:(1)Althoughthese BWRVIP guidelinesarenotpartofthisrequesttheyareusedatGGNS.Enclosure1,Table1 comparescurrentASMESectionXI,Table IWB-2500-1, Examination Category B-N-1andB-N-2 requirementswiththeabove current BWRVIP guideline requirements,asapplicable,toGGNS.Inadditiontotheitemsin Enclosure1,Table1adetailedTable2,"Vessel AttachmentWelds-FabricatedEitherfrom E-308/E-309 (Furnace Sensitized)
Austenitic StainlessSteelorInconel182Material,"listsspecificvessel attachment welds, fabricatedwiththesematerials,thathaveanincreasedconcernforcracking,with inspectionresults,andthatare currently examined under Examination CategoryB-N-2/BWRVIPandwillmeetthe inspection strategyfoundinSection3of BWRVIP-48-AandBWRVIP-38.Page3of7 GNRO-2017/00009 Attachment When implementing the guidance of BWRVIP-94 as requirementstousethisrequestGGNSwillmeetthe following paragraph:
'When BWRVIP guidelines are approvedbytheExecutive Committeeandareinitiallydistributed,or subsequentlyrevised,eachutilityshallmodifytheirvesseland internals program documentation toreflectthenew requirements and implement the guidancewithintworefuelingoutages,unlessa differentscheduleisidentifiedbytheBWRVIPatthetimeof document distribution.
Implementationmeansnotonly incorporating the requirementsintotheutilityprogram,butalsoperformingtheinitialor baseline inspection and evaluation requirements.Asaminimum,theBWRVIP guidelineslistedinSection3.2.21whichhavebeenreviewedand approvedbytheBWRVIPExecutive Committeewillbe implementedwithintworefueling outagesoftheapprovaldateoftheExecutiveCommittee,unlessa differentscheduleisidentifiedbytheBWRVIPatthetimeof document distribution.ChangestoNRCapprovedBWRVIP guidelinesthatareless conservativethanthoseapprovedbytheNRCshallbe implementedonlyafterNRC approvesthechanges."NRC approved" generallymeanspublicationofa
"-A" document or equivalent."Therefore,wheretherevisedversionofaBWRVIP inspection guideline continuestoalsomeetthe requirementsoftheversionoftheBWRVIP inspection guidelinethatformsthesafetybasisfortheNRC authorized proposed alternativetothe requirementsof10CFR50.55a,itmaybe implemented.
Otherwise,therevised guidelineswillonlybe implementedafterNRCapprovaloftherevisedBWRVIPguidelinesora plant-specificrequestforan alternativehasbeen approved.Enclosure1,Table1representsthemostcurrentcomparisonatthetimeofthisrequest.
Any deviationsfromthereferencedBWRVIP guidelinesforthedurationoftheproposedalternativewillbe appropriately documented and communicatedtotheNRC,pertheBWRVIPDeviationDispositionProcess.Intheeventthat conditionsareidentifiedthatrequirerepairor replacementandthe componentiswithin the jurisdictionofASMESectionXICode(welded attachmentstotheRPVorCoreSupportStructure),therepairor replacement activitieswillbe performed in accordancewithASMESectionXI,ArticleIWA-4000.
Subsequent examinationswillbein accordancewiththe applicableBWRVIPguideline.BasisforUseBWRsnowexaminereactor internals in accordancewithBWRVIP guidelines.
These guidelineshavebeenwrittento addressthesafety significantvesselinternal componentsandtoexamineandevaluatetheexaminationresultsforthese components using appropriatemethodsand reexaminationfrequencies.TheBWRVIPhas establishedareportingprotocolfor examinationresultsanddeviations.TheNRChasagreedwiththeBWRVIP approachinprincipleandhasissuedSafety Evaluationsformanyofthese guidelines (References1-10).InsupportofthisrequestGGNSemploysanOnline NobleChem&#x17d;(OLNC)formitigatingIGSCCinBWRInternals.Themost currentcycletodate ElectrochemicalPotential(ECP)isshownhereasfollows:
Cycle=21:theaverageECPmV(SHE)is
-487.7withaminimumof-499mV(SHE)andamaximum422mV(SHE).GGNSdoesnotmeasuremolarratio,but calculatesthevalueusing BWRVIP-202,BWRVIA,forRadiolysisandECPAnalysis,Version3.1.Threevaluesare developedatthebeginningofthecycle;BOC(BeginningofCycle),MOC(MiddleofCycle),andEOC(EndofCycle).Thevaluesselectedarefromtheupper downcomerlocationwhichis consideredthemost conservativelocationbytheBWRVIPandthusthevaluesare:Page4of7 GNRO-2017/00009 AttachmentBOCMolarRatio=6.2MOCMolarRatio=5.9EOCMolarRatio=4.1GGNSdoes measureMolarRatioand valuesaremuchhigher
(-240)SinceGGNSusesOLNC, catalystloadingisnot applicableandthe availability of HWC/HWC+NMCAduringnormal operationislistedbelow:Cycle19Cycle20Cycle21 93.5 0/0 98.4 0/0 91.7%thru 9/16 For specific activitiesthatarerequiredrelatedto leakage assessment in BWRVIP-18-R1-A,Section5.13,BWRVIP-41-R3,Section5.1.3,andBWRVIP-76-R1-A,a plant-specific integrated leakage assessment has been performed for assumedcracksasnoknown cracksrelatedto leakage are identifiedinEnclosure3,"GrandGulf ReactorVesselInternal Inspection History." Therefore,GGNShas assumedleakageforflawsintheCore SprayA,R,C,P,F,M,andH,KweldsalongwiththeJetPumpRS-1,RS-2,RS-3,IN-1,IN-2,MX-2,DF-1,DF-2,DF-3,AD-2, RS-6/7, and RS-8/9 welds.Inthecontextofthe integrated leakage assessmentoverone 24-monthcycle,theleakagethroughtheCoreSprayweldsis conservatively calculatedtobe0.0 gallonsperminute(gpm)withanallowablelimitof323.3gpm.FortheJetPumpDF-2welds,the leakage was calculatedtobe0.0gpmwithanallowablelimitof174.7gpm.FortheLPCI coupling,thereisa leakagevalueof4.194gpmduetoanidentifiedflaw.TheGGNS SAFER/GESTR-LOCA analysis assumed115gpm leakageinCoreSpraywelds,soaddingtheleakageoftheJetPumpweldsDF-2of0.0gpmalongwiththe postulatedflawsintheCoreShroudof22.37gpm(GIN 2017-00028)andtheLPCI couplingof4.194gpm,the combinedleakagewouldincreasethePeak Cladding Temperature (PCT)approximately 0.0 degrees Fahrenheit (OF).ThisisbecauseGGNS currently analyzeswithrelaxed parametersof115gpmpercore spraylineand860gpmperLPCIinjection line.The plant-specific integrated leakage assessment concluded that postulated leakagethroughtheCoreShroudatallH3,H4,H6AandH7 combined with leakageintheJetPumpDF-2weldandCoreSpraypipingwould increasethePCT analyzedintheGGNS SAFER/GESTR-LOCA analysis by approximately 0.0 of,orfrom 1712&deg;F to 1712&deg;Fbutstillbelowthe10CFR50.46(b) regulatorylimitof2200 of.The assessment, using conservative assumptions and BWRVIP methodology, demonstratedthatleakagefromthesereactor pressure vessel internalsovera24monthcycleresultsina0
%increasePCT.Thisisbecausethe Appendix K analysis currentlyusesrelaxed parameters of 7000'gpm versus7115gpmpercorespraylineand6660gpm versus7450gpmperLPCIline.
As additional justification, Enclosure 2,"ComparisonofASMESectionXICode Examination RequirementstoBWRVIP ExaminationRequirements,"provides specific examples that compare the inspection requirementsofASMESectionXICodeItem NumbersB13.10,B13.20,B13.30,andB13.40inTable2500-1,tothe inspection requirementsinthe BWRVIP documents.
Specific BWRVIP documents arePage5of7 GNRO-2017/00009 Attachmentprovidedasexamples.This comparisonalsoincludesa discussionoftheinspectionmethodsandwheretheyareapplied.Therefore,basedonthe Safety Evaluationsofmanyofthe guidelinesandthe comparisons performed demonstratingtheuseofthese guidelinesabove,Entergy concludesthatthis alternativerequesttothesubjectASMESectionXICode requirementswillavoid unnecessary inspections,whileinsomecasesconservingradiologicaldose,becausethe inspectionswillnowbe focusedonthemostrecentandactual BWR experienceavailable.Thus,thisrequestwhen authorizedwillprovidean acceptablelevelofqualityandsafetyandwillnot adverselyimpactthehealthandsafetyofthepublic.5.DurationofProposed Alternative Upon authorizationbyNRC,thisrequestforan alternativetousetheBWRVIP GuidelinesinlieuofASMESectionXICode requirementswillbe implementedduringthe4th10-yearlSIIntervalbeginningonJune2,2017andendingon,June1,2027,(whichwillincludeaportionoftheperiodofextendedoperationwhenapprovedbyNRCfrom November2,2024totheendofthe4th Interval).6.PrecedentsTheNRCStaffhas authorizedsimilarrequestsforthefollowing licenseesandalsofortheGGNS3rdyearlSIInterval.*Cooper NuclearStation,SERDocketNo.50-298,CACNo.ME6366, February16,2016(ADAMSAccessionNo.ML 16034A479)*RiverBend NuclearStation,SERDocketNo.50-458,TACNo.MF1867,May 30,2014, SupplementedwithSER Correction on November13,2014(ADAMS AccessionNo.ML 14183A086)*GrandGulf NuclearStation,Unit1,SERDocketNo.50-416,TACNo.MF3678,August1,2014 (ADAMS AccessionNo.ML 14184A782) 7.References1.LetterUSNRCtoBWRVIP,dated January30,2012(ML 113620684),"FinalSafetyEvaluationforElectricPowerResearchInstituteBoiling WaterReactorVesselandInternalsProjectTechnicalReport1016568, BWRVIP-18,Revision1:BWRCoreSpray InternalsInspectionandFlaw Evaluation Guidelines"(TACNo.ME2189)"2.LetterUSNRCtoBWRVIP,dated December19,1999,"SafetyEvaluationofBWRVesselandInternalsProject,BWRCorePlate InspectionandFlawEvaluation Guidelines (BWRVIP-25)," (ADAMS Accession Nos.ML993620267 and ML993620274)3.LetterUSNRCtoBWRVIP,datedAugust 29,2005,"NRCApprovalLetterof BWRVIP-26-A,"BWRVesselandInternalsProjectBoiling WaterReactorTopGuide InspectionandFlawEvaluation Guidelines", (ADAMS Accession Nos.ML043290158 and ML052490550).Page6of7 GNRO-2017/00009 Attachment4.LetterUSNRCtoBWRVIP,datedJune 10,2004, ProprietaryVersionofNRCStaffReviewof BWRVIP-27-A,"BWR StandbyLiquidControl System/CorePlateDPInspectionandFlawEvaluation Guidelines", (ADAMS Accession No.ML041700446).5.LetterUSNRCtoBWRVIP,datedJuly 24,2000,"FinalSafetyEvaluationofthe"BWRVesselandInternalsProject,BWRShroud Support InspectionandFlawEvaluation Guidelines (BWRVIP-38),"EPRIReportTR-108823(TACNO.M99638)"6.LetterUSNRCtoBWRVIP,dated February 4,2001,"FinalSafetyEvaluationofthe"BWRVesselandInternalsProject,BWRJetPump Assembly InspectionandFlawEvaluation Guidelines41),"(TACNO.
M99870)"7.LetterUSNRCtoBWRVIP,dated September 1,2005,"NRC ApprovalLetterofBWRVIP-47-A,"BWRVesselandInternalsProjectBoiling WaterReactorLowerPlenumInspectionandFlawEvaluation Guidelines".(ADAMS Accession Nos.ML043290026 and ML052490537).8.LetterUSNRCtoBWRVIP,datedJuly 25,2005,"NRCApprovalLetterofBWRVIP-48-A,"BWRVesselandInternalsProjectVessel 10 AttachmentWeldInspectionandFlawEvaluationGuideline".(ADAMS AccessionNos.ML 12214A522 and ML052130284).9.LetterUSNRCtoBWRVIP,datedJuly 28,2006,"S afetyEvaluationofthe"BWRVesselandInternalsProject,BWRCoreShroudWeld InspectionandEvaluation Guidelines (BWRVIP-76)" 1 o.LetterUSNRCtoBWRVIP,dated November1,2007,"NRCApprovalLetterwith Comment for BWRVIP-100-A,BWRVesseland InternalsProject,Updated AssessmentoftheFractureToughnessofIrradiatedStainlessSteelforBWRCoreShrouds,"(ADAMS Accession No.ML073050135)Page7of7 GNRO-2017/00009 Enclosure1to Attachment ComparisonofASMECodeSectionXITableIWB-2500-1andVessel Attachment WeldsTABLE1-ComparisonofASMECodeSectionXITableIWB-2500-1 Examination CategoryB-N-1andB-N-2 Requirements to BWRVIP Guidance Requirements (1)
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Fre:qu&#xa2;ll c y",i)(:icvmellt
.
-B13.10ReactorVesselInteriorAreasoftheRPVaboveandbelowthecoremade accessibleduringanormalrefuel.
VT-3EachPeriodNoneWhilethereisnotaspecificBWRVIP Guideline that addressesthescopeofB-N-1,the examinations performedbyBWRVIP-18,25,26,27,41, 47,138 provideageneral overviewofthereactor interiorwhichmaybe considered representativeoftheB-N-1scope..
B13.20InteriorAttachmentswithinBeltline-RiserBraces Accessible Welds VT-1Each10-year I BWRVIP-48-A,IntervalTable3-2RiserBrace Attachment EVT-1100%infirst12years,25%during each subsequent 6 years Lower Surveillance BWRVIP-48-A, I Bracket Attachment SpecimenHolderBracketsTable3-2 I B13.30 I Interior Attachments Accessible Welds VT-3Each10-year BWRVIP-48-A, I Bracket AttachmentbeyondBeltline-SteamintervalTable3-2DryerHold-downBracketsGuideRodBrackets I IIBWRVIP-48-A, AttachmentTable3-2SteamDryerSupport BWRVIP-48-A, I Bracket Attachment BracketsTable3-2FeedwaterSparger BWRVIP-48-A, Bracket Attachment BracketsTable3-2Page1of3VT-1Each 10-Year Interval VT-3 I Each 10-Year IntervalVT-3Each 10-Year Interval EVT-1 I Each 10-Year IntervalEVT-1Each 10-Year Interval GNRO-2017/00009Enclosure1to Attachment
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",':orype'?>;CoreSprayPiping Brackets I I IBWRVIP-48-A, I Bracket Attachment EVT-1Every4 RefuelingTable3-2 Cycles Upper Surveillance BWRVIP-48-A, Bracket Attachment VT-3Each10-Year Specimen Holder BracketsTable3-2 IntervalShroudSupport BWRVIP-38,WeldH-9 EVT-1 or UT I Maximumof6years(WeldH9)3.1.3.2,forEVT-1, MaximumFigures3-2of10yearsforUTand3-5 B13.40 I IntegrallyWeldedCore Accessible I VT-3 Each 10-year BWRVIP-38, Shroud supportEVT-1orUTBasedon as-found Support Structure Surfaces interval 3.1.3.2,weldsH8andH9 (2)conditions,toaFigures3-2 including gussets maximum6yearsforand3-5onesideEVT-1,10yearsforUTwhere accessibleCoreShroud Horizontal WeldsCoreShroudVertical WeldsCoreShroudRepairs (3)
R1-A,2.2 R1-A,2.3 R1-A,3.5WeldsH1-H7as applicable Vertical Welds as applicable Tie-Rod RepairUTorEVT-1IBasedon as-found conditions,toa maximumof10yearsforUTwhen inspectedfrombothsidesoftheweldsEVT-1orUT I Maximum10yearsforUTbasedon inspection of horizontal weldsVT-3IIn accordance with designer recommendations per BWRVIP-76 R1 Notes:(1)Thistableprovidesonlyan overviewofthe requirements.Formoredetails,refertoASMESectionXI,TableIWB-2500-1andthe appropriateBWRVIPDocument.Page2of3 GNRO-2017/00009 Enclosure1to Attachment (2)In accordance with AppendixAof BWRVIP-38,asite specific evaluation will determine the minimum required weld lengthtobe examined.(3)No repairshavebeen performedonthecore shroud.TABLE2-Vessel AttachmentWelds-FabricatedEitherfrom E-308/E-309 (Furnace Sensitized)
Austenitic Stainless SteelorInconel182Material
'<'
<illJetPumpRiserBrace I(FurnaceSensitized)
I BWRVIP-48-A INoindicationshavebeenidentified;norepairshavebeen(B13D001-JPB01A1Bto 12A1B)AusteniticStainlessSteal requiredSteamDryerHoldDown Bracket(B13D001-SHD01to06)CoreSprayPipingBracket(B13D001-CS1Uto6UandB13D001-CS1Lto6L)SteamDryerSupportBracket(B13D001-SL1to6)GuideRodBracket(B13D001-GB1and2)FeedwaterSpargerBracket(B13D001-FW01to12)ShroudSupportWelds(H9)ShroudSupportLeg(H12)Page3of3(FurnaceSensitized)
IBWRVIP-48-AAusteniticStainlessSteal Inconel182 BWRVIP-48-A Inconel182 BWRVIP-48-A Inconel182 BWRVIP-48-A Inconel182BWRVIP-48-A Inconel182 BWRVIP-38 Inconel182 BWRVIP-38Noindicationshavebeenidentified;norepairshavebeen requiredNoindicationshavebeenidentified;norepairshavebeen requiredNoindicationshavebeenidentified;norepairshavebeen requiredNoindicationshavebeenidentified;norepairshavebeen requiredNoindicationshavebeenidentified;norepairshavebeen requiredNoindicationshavebeendetected;norepairshavebeen requiredAlthoughnotrequiredbytheBWRVIP-38,intheirfinalsafetyevaluationoftheBWRVIP-38theNRCrequiresinspectionoftheshroudsupportlegwelds(H12)whenappropriateinspectiontoolingand methodologies aredeveloped.AtGrandGulfweldsH8andH9are structurallyadequate;therefore,supportleginspectionisnotrequired.
GNRO-2017/00009Enclosure2to Attachment  ComparisonofASME SectionXICode Examination Requirements to BWRVIP Examination RequirementsThefollowingdiscussionprovidesa comparisonofthe examination requirementsprovidedinASMESectionXICodeItemNumbers B1*3.10,B13.20,B13.30,andB13.40inTable IWB-2500-1,tothe examinationrequirementsintheBWRVIP guidelines.
Specific BWRVIP guidelinesareprovidedasexamplesforcomparisons.Thiscomparisonalsoincludesa discussionofthe examination methods.1.Code Requirement-B13.10-ReactorVessel Interior AccessibleAreas(B-N-1)ASMESectionXICoderequiresaVT-3 examinationofreactorvessel accessibleareas,whicharedefinedasthespacesaboveandbelowthecoremade accessibleduringnormalrefuelingoutages.The frequencyofthese examinations is specifiedasthefirstrefuelingoutage,andatintervalsof approximately3years,duringthefirstinspectioninterval,andeachperiodduringeach successive1O-yearInspectionInterval.Typically,these examinations are performedeveryotherrefuelingoutageoftheInspectionInterval.This examination requirementisa non-specific requirementthatisa departurefromthetraditionalSectionXIexaminationsofweldsandsurfaces.Assuch,this requirementhasbeen interpretedandsatisfied differentlyacrossthe domesticfleet.Thepurposeofthe examinationisto identifyrelevantconditionssuchasdistortionor displacementofparts,loose,missing,or fractured fasteners;foreignmaterial,corrosion,erosion,or accumulation of corrosionproducts,wear,andstructural degradation.Portionsofthevarious examinationsrequiredbythe applicable BWRVIP Guidelinesrequireaccesstoaccessibleareasofthereactorvesselduringeachrefuelingoutage.
ExaminationofCoreSprayPipingandSpargersTopGuide (BWRVIP-26-A),JetPumpWeldsand Components (BWRVIP-41-R3), Interior Attachments (BWRVIP-48-A),CoreShroudWelds (BWRVIP-76-R1-A), ShroudSupport(BWRVIP-38)andLowerPlenum Components (BWRVIP-47-A)providessuchaccess.Locatingandexaminingspecificweldsand componentswithinthereactorvesselareasabove,below(ifaccessible),andsurroundingthecore(annulusarea)entails accessbyremotecamera systems that essentially performs equivalent VT-3 examinationoftheseareasorspacesasthespecificweldor component examinationsareperformed.Thisprovidesan equivalentmethodofvisual examinationonamorefrequentbasisthanthatrequiredbytheASMESectionXI.Evidenceofwear, structural degradation, loose,missing,or displacedparts,foreignmaterials,and corrosionproductbuildupcanbe,andhasbeenobservedduringthecourseof implementingtheseBWRVIP examination requirements.Therefore,thespecified BWRVIP Guideline requirementsmeetorexceedthe subject Code requirementsforexaminationmethodand frequencyofthe interiorofthereactorvessel.
Accordingly,theseBWRVIP examination requirementsprovidean acceptablelevelof qualityandsafetyascomparedtothesubjectASMESectionXICode requirements.2.Code Requirement-B13.20-Interior AttachmentsWithintheBeltline(B-N-2)TheASMESectionXICoderequiresaVT-1 examination of accessiblereactorinteriorsurface attachmentweldswithinthebeltlineeach 10-yearinterval.Intheboilingwaterreactor,thisincludesthejetpumpriser brace welds-to-vesselwallandthelower surveillance specimen support bracket welds-to-vesselwall.Incomparison,the BWRVIPrequiresthesame examinationmethodand frequencyforthelowersurveillancePage1of4 GNRO-2017/00009Enclosure2to Attachment specimen support bracketwelds,and requiresanEVT-1 examinationonthe remaining attachment weldsinthebeltlineregioninthefirst12years,andthen 25%duringeach subsequent6years.Thejetpumpriserbrace examination requirements are providedbelowtoshowa comparisonbetweentheASMESectionXICodeandthe BWRVIP examination requirements.
ComparisontoBWRVIP Requirements-JetPumpRiserBraces (BWRVIP-41-R-3 and BWRVIP-48-A)*TheASMESectionXICode requiresa100%VT-1 examinationofthejetpumpriser brace-to-reactorvesselwallpadweldseach1O-yearinterval.*TheBWRVIPrequiresanEVT-1 examinationofthejetpumpriser brace-to-reactorvesselwallpadweldsthefirst12yearsandthen 25%duringeach subsequent6years.*BWRVIP-48-A specifically defines the susceptibleregionsofthe attachmentthataretobeexamined.TheASMESectionXICodeVT-1 examination is conducted to detect discontinuities and imperfections on the surfaces of components, including such conditionsascracks,wear, corrosion,orerosion.TheBWRVIP EnhancedVT-1(EVT-1)is conducted to detect discontinuities and imperfectionsonthesurface of componentsandis additionally specified to detect potentiallyverytight cracks characteristicoffatigue and inter-granular stress corrosion cracking(IGSCC),the relevant degradation mechanismsforthese components.
General wear, corrosion,orerosion although generallynota concern for inherently tough, corrosion resistant stainlesssteelmaterial,wouldalsobe detectedduringthe process of performing aBWRVIPEVT-1 examination.TheASMESectionXICode 2007 Edition throughthe2008Addenda,VT-1visual examination methodrequiresthataletter characterwithaheightof0.044inchescanberead.The BWRVIPEVT-1visual examinationmethodrequiresthesame0.044inch resolutiononthe examination surface and additionally the performanceofa cleaning assessment and cleaning as necessary.
Whilethejetpumpriserbrace configuration varies dependingonthevessel manufacturer, BWRVIP-48-A includes diagramsforeach configuration and prescribes examinationforeach configuration including GGNS.Thecalibration standardsusedfor BWRVIP EVT-1 examsutilizethesameASMESectionXICodecharacters,thus assuringatleast equivalent resolution comparedtotheCode.
AlthoughtheBWRVIP examinationmaybeless frequent,itisamore comprehensive method.Therefore, the enhanced flaw detection capabilityofanEVT-1,withaless frequent examination schedule provides an acceptablelevelofqualityand safetytothat providedbytheASMESectionXICode.3.Code Requirement-B13.30-Interior AttachmentBeyondtheBeltlineRegion(B-N-2)TheASMESectionXICode requiresaVT-3 examination of accessible reactor interior surface attachmentweldsbeyondthebeltlineeach1O-yearinterval.Intheboiling waterreactor,this includesthecorespray piping primary and supplemental support bracket welds-to-vesselwall,the upper surveillance specimen support bracket welds-to-vesselwall,the feedwater sparger support bracket welds-to-reactorvesselwall,thesteamdryer support and hold-down bracket welds-to-reactorvesselwall,theguiderod support bracket weld-to-reactorvesselwall,the shroud support plate-to-vesselwall,andshroud support gussets.BWRVIP-48-Arequiresasa minimumthesameVT-3 examination methodastheCodeforsomeofthe interior attachmentweldsbeyondthebeltlineregion,andinsomecases specifies an enhanced visual examination techniqueEVT-1forthesewelds.Forthose interior attachmentweldsthathavethesame3methodof examination,thesamescopeof examination (accessiblewelds),thesame examinationPage2of4 GNRO-2017/00009Enclosure2to Attachment frequency(each10yearinterval)andASMESectionXIflaw evaluationcriteria,thelevelof quality andsafetyprovidedbythe BWRVIP requirements are equivalenttothat providebytheASMESectionXICode.FortheCoreSpray support bracket attachmentwelds,thesteam dryer support bracket attachment welds, the feedwater sparger support bracket attachmentwelds,andtheshroud support plate-to-vesselwelds,asapplicable,theBWRVIP GuidelinesrequireanEVT-1 examinationatthesame frequencyastheASMESectionXICode,oratamore frequent rate.Therefore, the BWRVIP requirementsprovidethesamelevel of quality and safetytothat providedbytheASMESectionXICode.TheCoreSpraypiping bracket-to-vessel attachmentweldisusedasan example for comparison betweentheCodeandBWRVIP examination requirements as discussed below.Comparison to BWRVIP Requirements-CoreSpraypiping Bracket Welds (BWRVIP-48-A)*TheASMESectionXICode examination requirementisaVT-3 examinationofeachweldevery10 years.*TheBWRVIP examination requirementisanEVT-1forthecore spray piping bracket attachmentweldswitheachweld examinedeveryfourcycles(8yearsforunitswithatwoyearfuelcycle).The BWRVIP examination methodEVT-1has superior flaw detectionandsizing capability, the examination frequency is greaterthantheCode requirements,andthesameflaw evaluation criteriaareused.*TheCodeVT-3 examination is conducted to detect component structural integrity by ensuring the componentsgeneralconditionis acceptable.
An enhancedEVT-1is conductedtodetect discontinuities and imperfectionsonthe examination surfaces, including such conditionsastightcrackscausedbyIGSCCorfatigue,the relevant degradation mechanismsforBWRinternal attachments.
Therefore,withtheEVT-1 examinationmethod,thesame examination scope (accessiblewelds),an increased examination frequency(8yearsinsteadof10years)insomecases,thesameflaw evaluationcriteria(SectionXI),thelevelof quality and safety providedbythe BWRVIP criteria is superiorthanthatprovidedbytheCode.4.Code Requirement-B13.40-Integrally Welded Core Support Structures (B-N-2)TheASMESectionXICoderequiresaVT-3 examination of accessible surfacesoftheweldedcoresupport structureeach1 a-yearinterval.Intheboiling waterreactor,theweldedcore support structure has primarily been consideredtheshroud support structure, including the shroud support plate (annulusfloor)the shroud supportring,the shroud supportwelds,the shroud support gussets.Inlaterdesigns,theshrouditselfis consideredpartoftheweldedcore support structure.
Historically, this requirementhasbeen interpreted and satisfied differently acrosstheindustry.The proposed alternate examinationreplacesthisASMESectionXICode requirement with specific BWRVIP guidelines that examine susceptible locationsforknownrelevant degradation mechanisms.
Comparison to BWRVIP Requirements-BWRShroud Support (BWRVIP-38)*TheASMESectionXICode requiresaVT-3of accessible surfaceseach1 a-year interval.Page3of4 GNRO-2017/00009Enclosure2to Attachment*TheBWRVIPrequiresasaminimumthesame examinationmethod(VT-3)astheASME Section XICodeforintegrallyweldedCore SupportStructures,andfor specificareas,requireseitheranenhancedvisual examination technique(EVT-1)or volumetric examination (UT).BWRVIPrecommended examinations of integrallyweldedcore support structuresarefocusedonthe known susceptibleareasofthisstructure,includingtheweldsand associatedweldheataffectedzones.Asaminimum,thesameor superior visual examination techniqueisrequiredfor examinationatthesame frequencyastheASMESectionXICode examination requirements.Inmanylocations,theBWRVIPguidelinesrequirea volumetric examinationofthe susceptibleweldsata frequencyidenticaltotheASMESectionXICoderequirement.Forotherintegrallyweldedcore supportstructurecomponents,theBWRVIPrequiresanEVT-1orUTofcoresupportstructures.Thecoreshroudisusedasan example for comparisonbetweentheASMESectionXICodeandBWRVIP examination requirementsasshownbelow.ComparisontoBWRVIP Requirements-BWRCoreShroud ExaminationandFlawEvaluationGuideline (BWRVIP-76-R1-A)*TheASMESectionXICoderequiresaVT-3 examination of accessible surfacesevery10years.*TheBWRVIPrequiresanEVT-1 examinationfromtheinsideandoutsidesurfacewhereaccessibleor ultrasonic examinationofeachcoreshroud circumferentialweldthathasnotbeen structurallyreplacedwithashroudrepairata calculated"endofinterval"(EOI)thatwillvary dependingupontheamountofflawspresent,butnottoexceedtenyears.TheBWRVIP recommended examinations specify locationsthatareknowntobe vulnerabletoBWR relevant degradation mechanismsratherthan"all accessible surfaces".TheBWRVIP examinationmethods(EVT-1orUT)are superiortotheASMESectionXICoderequiredVT-3 examinationforflawdetectionand characterization.TheBWRVIP examination frequency is equivalenttoormore frequent thantheexamination frequencyrequiredbytheASMESectionXICode.The superiorflawdetectionand characterizationcapability,withan equivalentormore frequent examination frequencyandthecomparableflawevaluationcriteria,resultsintheBWRVIPcriteriaprovidingalevelof qualityandsafetyequivalenttoorsuperiortothatprovidedbytheCode requirements.Page4of4 GNRO-20 17/00009Enclosure3to Attachment GrandGulf ReactorVesselInternal Inspection HistoryCoreShroud Shroud SupportPage1 of 9Spring1995Spring1998Spring2004Fall2005Spring2014Spring2016Spring1992Spring1995Fall1996Spring1998Fall2002 UT UT UT UT UT UT VT-1 VT-3 VT-1 UT VT-1BaselineperBWRVIP-01.AllaccessibleareasofH3,H4,H6AandH7.Noindications.AllaccessibleareasofH3,H4,H6A,H7.No indications.15.1%ofH3LowerSideand34.6%ofH4.Dueto equipmentfailuresthis examinationwasdeferredtonextoutage.44%ofH3LowerSide,56.6%H4BothSides,17.3%H6ABothSidesand
@20%H7BothSides.Oneindicationwith characteristicsassociatedwith IGSCC/IASCCwasdetectedonthelowersideoftheH4weld.Indicationis1.11"inlength.Dueto disassemblyoftheJP11mixer,aVT-3examination was performedonaccessibleareasofH10,H11andH12.Noindications.17.8%UpperSideand16.5%Lower SideofH6A18.8%UpperSideand21.6%LowerSideofH7 No indications identified81.3%UpperSideand80.0%LowersideofH373.4%UpperSideand73.4%LowerSideofH4 Two indicationsweredetectedonthelowersideoftheH3weld.Indicationswereatotalof4.33"inlength.OneadditionalindicationwasdetectedontheuppersideoftheH4weldwithalengthof1.19".Eachindicationhad characteristicsassociatedwith EGSCC/IASCC.Shroudshellweld.Noindications.(SIL572)
SSHAC@180&deg;.Noindications.SectXI.Period3of1O-yrinterval.RF05/6 Attachmentweldstovesselandshroudplatetoshroudweld.Noindications.10.7%oftotal circumferenceofH8(shroudsupportplatetoshroudweld)and15.4%ofH9(shroudsupportplatetovesselweld).Noindications.
SSAHC@0&deg;.Noindications.
GNRO-2017/00009 Enclosure3to Attachment
,::>.........*:..'.'*......,:,..:...:............::..Component Inspection Date:"'.Inspection**
Resu Its..../..:.I****,..,..--....>........:......: ,...,.Fall2005VT-1SSAHC@0&deg;.Noindications.Spring2007 EVT-115%ofthetopofH8and18.5%ofthetopofH9.
No indicationswerenoted.Fall2008 VT-1 SSAHC@0&deg;.Noindications.Spring2012 EVT-1Morethan10%ofthetopofbothH8andH9wasinspected.No indicationswerenoted.Spring2014EVT-1SSAHC
@0&deg;.No indications noted.CoreSpraySpring1998EVT-1Allaccessiblepipinglocations.Noindications.
PipingFall1999 EVT-1AllaccessibleP2,P2a,P3a,P5.25%ofremainingpipinglocations.Noindications.Spring2001EVT-1AllaccessibleP2,P2a,P3a,P5.25%ofremainingpipinglocations.Noindications.Fall2002 EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocations.Noindications.Spring2004EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocations.Noindications.Fall2005EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocations.Noindications.Spring2007EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocations.Noindications.Fall2008EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpiping.locations.Noindications.Spring2010 EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocationswiththeexceptionofP3a(L)-270&deg;,P3a(R)-90&deg;andP3a(L)-90&deg;(Ref.
CR-GGN-2013-06541).Noindications.Spring2012 EVT-1Alltargetwelds(P3aandP5)with25%ofremainingpipinglocationswiththeexceptionofP3a(L)-270&deg; IP3a(R)-270&deg;andP3a(R)-90&deg;(Ref.
CR-GGN-2013-06541).EVT-1Indication discoveredonP8Aas documentedonINR GGNS-IVVI-12-02Spring2014VT-1/VT-3/Alltargetwelds(P3aandP5)with25%ofremainingEVT-1pipinglocations.Indication discoveredonP8Awasinspectedwithnochangeinindication.Nootherindicationsdiscovered.Page2of9 GNRO-2017/00009 Enclosure3to Attachment
'InspectiorfResults Spring 2016 EVT-1 All targetwelds(P3aandP5)with25%of remaining piping locations.Noother indications discovered.CoreSprayFall1996 VT-3AugmentedexamperIE80-13.Noindicationsnoted.
Sparger Spring 1998EVT-1/CS-Accessibleareasofspargers,teeboxes,bracketsand VT-1supports.Brokentackwelds
@CapScrew7 A.Fall1999VT-1/VT-3UpperSparger-Accessibleareasofspargers,teeboxes,bracketsandsupports.Noindicationsnoted.Fall2002VT-1/VT-3Allcoresprayspargertargetweldsandallaccessibleareasofthelowerspargerwelds.Noindicationsnoted.AllaccessibleareasofCoreSprayBrackets(SB).Brokentackwelds
@CapScrew7Apreviously reported.Fall 2005VT-1/VT-3Allcoresprayspargertargetweldsandallaccessibleareasoftheupperspargerwelds.Accessibleareasof CoreSpraySpargerBrackets(SB).Noindicationsnoted.Brokentackwelds
@CapScrew7Apreviouslyreported.AdditionalbrokentackweldidentifiedatCapScrew15C.Fall2008EVT-1/VT-1Allcoresprayspargertargetweldsandallaccessibleareasofthelowerspargerwelds.AccessibleareasofCoreSpraySpargerBrackets(SB).Noindicationsnoted.Brokentackwelds
@CapScrew7Aand15Cpreviouslyreported.
Spring 2010 VT-1 Performed examinations of previous indications at Cap Screw7Aand15C.No changes noted.Spring2012EVT-1/VT-1Allcore spray sparger targetweldsandall accessibleareasofthe upper sparger welds.AccessibleareasofCoreSpray Sparger Brackets(SB)were inspectedwithno indications.
Performed examinations of previous indicationsatCapScrew7Aand15C.No changesnoted.Tackweld, indications on alignment sleeve documentedonINR GGNS-IVVI-12-03andINR GGNS-IVVI-12-05.Spring2014EVT-1/VT-1 Performed examination of previous indications at Cap Screw7Aand15Candtackweld indications on alignmentsleeve.No discernible changesnotedon the indications.Page3of9 GNRO-2017/00009Enclosure3to Attachment Component...Irlspectiorr ResultsSpring2016EVT-1/VT-1PerformedVT-1examinationsofpreviousindicationsatCapScrew7Aand15C.Nodiscernablechangesnotedontheindications.PerformedVT-1examinationsofaccessibleareasofthelowerspargerwelds,andaccessibleareasofCoreSpraySpargerBrackets(SB)wereinspectedwithnoindications.Indicationofrolledmetallocatedon172 0 LowerBossPad.BoltthreadingprotrudingfrombacksideofBracket12Bolt"0".
Top Guide (Rim,Fall1996 VT-3Accessiblesurfacesandfasteners.Noindications etc.)noted.Spring2001 VT-3Accessiblesurfacesandfasteners.Noindications noted.Spring2007VT-3Accessiblesurfacesandfasteners.Noindications noted.Spring2012 EVT-1Accessiblesurfacesandfasteners.IndicationdocumentedunderINRGGNS-IVVI-12-06.CorePlate(Rim,Fall1996VT-3SectionXI,undercoreplate.Whereaccesswas etc.)providedinRF08,cameraworkwasperformed.Noindicationsnoted.Spring2007 VT-3Accessiblesurfacesoftheshroudsupportstructure.Noindicationsnoted.
SLC N/AN/AN/A Jet PumpFall1996UTUTperformedonJPbeams.Twobeamscrackedin AssemblyRF06andallwerereplacedwithUnit2spares.NoUTexamsweredoneinRF07.RF08changedoutallbeamswiththenewGEdesign.Spring1998Fall1999Spring2001Fall2002Page4of9EVT-1/VT-3AccessibleareasofRS-3weldonJP0102,JP0304andJP0506.VT-3onflowrestrictiononJP 09,10,11and24.Noindicationsnoted.EVT-1AccessibleareasofRS-3weldatJP07/08,JP09/10andJP11/12.Noindicationsnoted.EVT-1AccessibleareasofRS-1andRS-2weldsonJP01/02.Noindicationsnoted.EVT-1AllrequiredlocationsforJP0304andJP0910.ExaminationexceptionsareRB-1b,RB-1d,RB2a-dforJP0304;welds OF-1forJP03andJP04;OF-3forJP03andJP10;IN-1andIN-2forJP04;IN-2for JP1 O.Noindicationsnoted.
GNRO-2017/00009 Enclosure3to AttachmentSpring2004EVT-1/VT-1CompletedremainingexaminationsonJP0304and0910.Completedbaselineon50%oflowandmediumprioritylocationsand100%ofhighpriority(RS-3)locations.IdentifiedandinspectedanadditionalRS-1weldatJP0910andinspectedadditionalweldattheDF-3location.TheadditionalweldattheDF-3locationwasidentifiedintheFall2002outage(DF-3a).Noindicationsnoted.
Jet Pump Assembly (continued)
CRD Guide TubesPage5of9Fall2005Spring2007Fall2008Spring2010Spring2012Spring2014Spring2016Fall1996 EVT-1EVT-1/UT EVT-1 EVT-1 UTEVT-1/VT-1/VT-3EVT-1/VT-1 VT-3Wedgeexaminationswerecompletedon12jetpumps.Wedgeexamshavebeencompletedonalljetpumpswithnoindications.ExaminedoneIN-1andIN-2locationwithnoindicationsnoted.Wedgeexaminationperformedon4wedgesdueto disassemblyofJetPumpsinpreviousoutages.EVT-1wasperformedontheRiserBracetovesselweld(5locations).UTperformedon21of24JetPumpbeams.ThreebeamshavebeenreplacedwithnewbeamsanddonotrequireUTatthistime.PerformedexaminationsonJetPumpwedges1thru12.Nowearwasidentified;howeverslightwearwasnotedonwedgerodsJP01,JP02,JP05,JP06,JP07andJP09.Noadditionalexamswere performed.Completedbaselineexaminations(148locations).PerformedadditionalinspectionsofJetPumpWedges(12)andRiserBraces(12)duetoLaguna Verde DE.Noindicationswerenoted.UTperformedon21of24JetPumpbeams.ThreebeamshavebeenreplacedwithnewbeamsanddonotrequireUTatthistime.Noindicationsnoted.EVT-1NT-1performedon39locationsJetPumpRiserandDiffuserWeldswithnoindications.VT-3performedoneight(8)sensinglineswithnoindications.VT-1wasperformedonall24jetpumpwedgeswith2indicationsfoundontheStelliteCladdingofJetPumps#5and#16.IndicationsdocumentedunderINRGGNS-IVVI-14-01R1.VT-1wasperformedon2jetpumpwedgesthathadindicationinpreviousoutage.Nochangeswerenoted.EVT-1performedon50locationsJetPumpRiserandDiffuserWeldswithnoindications.8guidetubes.When accessibilitypermits.Noindicationsnoted.
GN RO-20 17/00009Enclosure3to Attachment"""2".\,:..,
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';Spring1998 VT-334CRGT-1exams completedwithno indications noted.Spring2001 VT-312guidetubes.12FS/GT-ARPIN-1andCRGT-1.
Accessible portionsofCRGT-2(2places).
No indications noted.Fall2002 EVT-1 CRGT-2&3(10places).FS/GT-ARPIN-1(2places).No indications noted.CRD GuideSpring2008 EVT-1 Completed baselineexamson10CRDGuide TubesTubes.No indicationswerenoted.(continued)
Dry TubesSpring1998 VT-311guidetubes.Noindicationsnoted.Fall2002 VT-1Accessibleareasof6LPRMdrytubes.Noindications noted.Spring2007 VT-1Accessibleareasof14SRM/IRMand7LPRMS.Noindicationsnoted.Fall2008 VT-1Performedinspectionson24LPRMdrytubes.NoindicationsnotedSpring2010 VT-1Performedexamson14SRM/IRMdrytubes.Fourdrytubeshadindications.Spring2012 VT-1 Performed inspectionson5LPRMdrytubes.Replacedfourdrytubesthathad indications inSpring2010.No indications noted.Spring2014 VT-1 Performedexamson10SRM/IRMdrytubesand identifiedtwodrytubeswith indications.SRMFwasreplacedduringthisoutageandwasoneofthedrytubeswithan indication.
Indications documented under INR GGNS-IVVI-14-03.Spring2016 VT-1 Performedexamson8SRM/IRMand5LPRMdrytubes.OneIRMandfourLRPMdrytubeswerereplaced.No recordable indicationswerenoted.
InstrumentFall1996VT-3No indications.
Penetrations VessellDFall1996VT-1/VT-3SectionXIevery10yearson Attachment welds.Brackets Otherpartsof bracketsongeneralVT-3exam.
No indications.Spring2004VT-1SectionXIJetPump attachmentweldsattwo locations was inspected.Noindications.Page6 of 9 GNRO-2017/00009 Enclosure3to AttachmentFall2005Spring2007Spring20.14VT-1/VT-3SectionXIGSPipingBrackets,FWSpargerEndBrackets,GuideRodBrackets(upper),SteamDryer Brackets, SurveillanceSampleBracketsand attachmentweldsatJP1112.Dueto disassembly oftheJP11mixeran examinationwasperformedatoneShroudSupportStubweld.Noindications.VT-1/VT-3SectionXIJetPump attachmentweldsat5locations.VT-3ofaccessibleareasofH9.No indications noted.EVT-1/VT-3 Inspections were performedfour(4)SteamDryer SupportBracketdueto indicationsontheSteamDryerSeismicBlocks.Nodiscerniblechanges.
VessellD Brackets (continued)
LPCI CouplingPage7of9Spring2016Spring1996Spring1998Fall1999Spring2001Fall2002Fall2005Spring2007Fall2008Spring2010VT-1/VT-3/
EVT-1 VT-1 EVT-1 VT-1 VT-1 EVT-1 VT-1 EVT-1 EVT-1 EVT-1 InspectionswereperformedonSteamDryerSupportBrackets,SteamDryerHold-downBrackets, FeedwaterSpargerBracketsand Surveillance SpecimenHolderBrackets.Nodiscerniblechanges.VT-1onLPGI
@Az.141&deg;duetoapreviousloosepartsimpactconcern.Noindications.AllchosenweldsonLPGIcouplings
@Az.39&deg;and 141 0.Noindications.Allaccessibleareas
@219&deg;.VT-1onLPGI
@Az.141&deg;duetoapreviousloosepartsimpactconcern.Noindications.VT-1onLPGI
@Az.141&deg;duetoapreviousloosepartsimpactconcern.Noindications.Allaccessibleareas
@Az.39&deg;.Noindications.1onLPGI@Az.141&deg;duetoapreviousloosepartsimpactconcern.Noindications.VT-1onLPGI
@Az.141&deg;duetoapreviousloosepartsimpactconcern.Noindications.VT-1onall accessibleareasofLPGI
@141&deg;.ExtraweldwaslocatedonthestrutassemblyatallLPGIlocations.No indications noted.EVT-1 performedontheextrawelds(6-4a)thatwerenotedduringRF15ateachLPGIstrut.No indicationswerenoted.ExamswereperformedonLPGI
@219&deg;.No indicationswerenoted.
GNRO-2017/00009 Enclosure3to Attachment Steam Dryer Steam Dryer (continued)
Spring 2016 Spring 2007 Fall 2008 Spring 2010 Spring 2012 Spring 2014 Spring 2016 EVT-1 VT-1 VT-1 VT-1 Various VT-1 VT-1 Exams were performedonLPGI@39&deg;.No indicationswerenoted.CompletedBWRVIP-139examination.Crackedtackweldswerenotedonall (4)liftinglugs.Nomovementwasnoted.Elevenindications(IGSCC)wereidentifiedonthedryeruppersupportring.Noindicationswerelongerthan 3 Y2".ExaminedareasidentifiedduringRF15.Additionalcrackwasnotedonaliftinglugandadditionlinearindication(1"Ig.)wasidentifiedontheUpperSupport Ring.Examinedpreviousindications(crackedtackweldsatliftinglugsandIGSCCcrackingontheuppersupportring).Nochangeswerenoted.
Steam Dryer replaceddueto Extended Power Uprate Performed inspectionsonall accessibleweldson the interior and exteriorofthedryer.
Indications were identified on SeismicBlocks,TieRodBolting and Lower Guide Bracket.Indications documented under INR GGNS-IVVI-14-06andINR 14-07.Performed inspectionsonall accessible welds on the interior and exteriorofthedryer.
Indications were identified on Seismic Support Blocks.Indications documented under INR 02.Dissimilar Metal Spring 2007 Welds on Reactor NozzlesFall2008Page8 of 9 UT UT N1A-KB NozzletoSafeEnd Weld N2A-KB NozzletoSafeEnd Weld N2K-KB NozzletoSafeEndWeld K2M-KB NozzletoSafeEnd Weld K2N-KB NozzletoSafeEndWeld K9A-KB NozzletoSafeEnd Weld N9A-KGSafeEndtoSafeEndExt.
No recordable indications noted.N5B-KB NozzletoSafeEnd Weld N5B-KGSafeEndtoSafeEndExt.
N4A-KB NozzletoSafeEnd Weld N4F-KB NozzletoSafeEndWeld N4B-KB NozzletoSafeEndWeld No recordable indications.
GNRO-2017/00009 Enclosure3to AttachmentSpring2010 DissimilarMetalSpring2012 Welds on Reactor Nozzles (continued)Spring2016 Reactor BottomSpring2012 Drain Line Lower PlenumSpring2016Page9of9 UT UT UT UT VT-3N02B-KBNozzletoSafeEndWeldN02C-KBNozzletoSafeEndWeldN02D-KBNozzletoSafeEndWeldN02E-KBNozzletoSafeEnd WeldN06A-KBNozzletoSafeEndWeld N06A-KCSafeEndtoExtension N09B-KBNozzletoSafeEndWeldNorecordableindications.N01B-KBNozzletoSafeEndWeldN02F-KBNozzletoSafeEndWeld N02G-KBNozzletoSafeEndWeldN02H-KBNozzletoSafeEndWeldN02J-KBNozzletoSafeEndWeldN04C-KBNozzletoSafeEndWeldN04D-KBNozzletoSafeEndWeldN05A-KBNozzletoSafeEndWeldN05A-KCSafeEndtoExtensionN06B-KBNozzletoSafeEndWeld N06B-KCSafeEndtoExtensionN06C-KBNozzletoSafeEndWeldN06C-KCSafeEndtoExtensionN09A-KBNozzletoSafeEndWeldCrackwas discoveredinN06B-KBweldandweldoverlaywas completedsatisfactorily.Ref.
2012-06386.N02M-KBNozzletoSafeEndWeldN02N-KBNozzletoSafeEndWeldN05B-KBNozzletoSafeEndWeldN05B-KCSafeEndtoExtensionN06B-KBWeldOverlayN10-KCSafeEndtoPipeCapWeldNochangesinoriginalrecordableindicationforKBWeldNootherrecordable indicationsTwo2"drainlineswereinspectedpertheFlow AcceleratedCorrosionProgram.Degradation documentedinCalculation MC-Q1111-12004.
Next scheduled inspectionsareRF23andRF29,resectivel.LowerplenuminspectionsperformedwithCell32-33and28-29removed.Norecordableindications.}}