GNRO-2017/00034, Proposed Alternative Request for Forth Interval Inservice Inspection Program

Proposed Alternative Request for Forth Interval Inservice Inspection Program

ML17145A321
Person / Time
Site:	Grand Gulf
Issue date:	05/25/2017
From:	Nadeau J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2017/00034
Download: ML17145A321 (20)

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{{#Wiki_filter:* GNRO-2017/00034 May 25,2017 u.s.Nuclear Regulatory Commission Attn: DocumentControlDesk Washington, DC 20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150JamesNadeau Regulatory Assurance ManagerTel.(601)437-2103

DearSirorMadam:

Proposed Alternative RequestforForth Interval Inservice Inspection Program Grand Gulf Nuclear Station Docket No.50-416 License No.NPF-29 Pursuantto10CodeofFederal Regulations (CFR)50.55a(a)(z)(1), Entergy hereby requests an alternative for Grand Gulf Nuclear Station (GGNS)Inservice Inspection Program.This request is applicabletothe upcoming 4th ten-year inservice inspection interval starting December 1, 2017andendingon November1,2024.The detailsofthe10CFR 50.55a request are providedinthe attachment. The proposed relief request alternativeisfor performingtheASMECode required examinationson100%ofthe nozzle-to-vesselweldsand nozzle inner radius sectionsusingASMECodeCaseN-702. Entergy requestNRCStaff review and approvalofthis proposed GGNS alternativeonor beforeMarch23,2018.Thereareno regulatory commitments madeinthis submittal.Ifyouhaveany questionsorrequire additional information, please contact James Nadeau at 601-437-2103. Sincerely, James -/ec Regulatory Assurance Manager IN/sgd GNRO-20 17/00034Page2of2 Attachments:1.Proposed Alternative Request (GG-ISI-021)forFourthIntervalInservice Inspection Program 2.Attachment1toRelief GG-ISI-021, ResponsestoBWRVIP-108, Plant-Specific Applicability Criteriacc:with Attachment and EnclosuresMr.JohnP.Boska,Project ManagerPlantLicensingBranch 1-1Divisionof OperatingReactorLicensingOfficeof NuclearReactorRegulation U.S.Nuclear Regulatory CommissionMailStop 0-8-C2 Washington,DC20555cc:without Attachment and EnclosuresMr.KrissKennedy Regional Administrator,RegionIV U.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.HStateHealth Officer Mississippi DepartmentofHealthP.O.Box1700Jackson,MS 39215-1700 Email: marv.currier@msdh.ms.gov Attachment 1 to GNRO-2017/00034 Relief Request Number GG-ISI-021 GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of Quality and Safety-1.ASME Code Component(s) Affected Components/Numbers:1.ReactorPressureVessel(RPV) Nozzle-to-VesselWelds(seeTable1)2.RPVNozzleInsideRadius Sections(seeTable2)CodeClass:ExaminationCategory:

== Description:== ItemNumber(s):Unit/InspectionInterval Applicability:AmericanSocietyof Mechanical Engineers(ASME)SectionXICodeClass1 8-0, Full PenetrationWeldsofNozzlesinVessels1.RPV Nozzle-to-Vessel Welds2.RPVNozzleInsideRadius Sections 83.90 and 83.100GGNS,4th 10-yearlSIIntervalstarting December1,2017andendingon November1,2024,whichistheendoftheinitialGGNS 40-year operatinglicense(LicenseNo.NPF-29)that corresponds to the conditional failure probabilityfor40years(Ref.6). 2.Applicable Code Requirement(s)ASMESectionXI,2007Editionthroughthe2008 Addenda (Reference1),TableIW8-2500-1,Examination Category 8-0, Full Penetration WeldedNozzlesinVessels,(nozzle assemblies)requiresa volumetricexaminationofallRPVnozzleswithfull penetrationweldstothevesselshell(orhead)andintegrallycastnozzles,butexcludes manways and handholeseitherweldedtoor integrallycastinthevesselandexaminationofeach nozzle'sInsideradiussectionisrequiredeach1O-yearinterval.Theexaminationofthese nozzle assembliesaredetailedbytheitem numbersshownbelow.*ItemNo.83.90-Requiresa volumetric examination of Reactor VesselVesselWelds.*ItemNo.83.100-Requiresa volumetric examinationofReactorVesselNozzleInsideRadiusSections. GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (151)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR SO.SSa(z)(1) -Acceptable Level of Quality and Safety-Additionally,forthe ultrasonic examinations performedonthesenozzle assemblies,ASMESectionXI,AppendixVIII,"Performance Demonstration for Ultrasonic ExaminationSystems,"istobeimplemented;withthe2007Editionthroughthe2008 AddendaofSectionXI. 3.Reason for RequestForthe3rd10-yearlSIIntervalaminimumof 25%oftheClass1nozzle assembliespersystemandnominalpipesizewereexamined[exceptforthe Feedwater(N04)andControlRodDrive (N10)nozzleassembliesthatareexcludedfromtheCase].These examinations were performed in accordancewithASMECodeCase702(Reference2),basedon authorizationofthe3rdIntervalrequest GG-ISI-013(Reference3)byNRCSafetyEvaluationReport (Reference4)totheendofthe3rdInterval,whichis November30,2017.TheFederalRegisterNotice(FRN) published November5,2014, containstherulemakingthatamends10CFR50.55ato incorporatebyreference RegulatoryGuide(RG)1.147,Revision17,"InserviceInspectionCodeCase Acceptability,ASMESectionXI,Division1."Inordertocontinuethesame 25%samplingprovisionsofCodeCaseN-702forthe4thIntervaluntiltheendofthecurrent40-yearoperatinglicensethisrequestisrequiredbasedontheNRC conditiontouseCodeCaseN-702inNRC RegulatoryGuide1.147,Revision17,(Reference5).SeeSection5belowfortheconditionrequiredtouseCodeCaseN-702. 4.Proposed AlternativePursuantto10 CFR 50.55a(a)(z)(1),Entergyrequestsan alternative from performingtheASMECoderequired examinationson100%ofthe nozzle-to-vesselweldsandnozzleinnerradiussectionsidentifiedinTables1and2,respectively.Specifically,Entergy proposestoadoptASMECodeCaseN-702,whichallowsexaminationofaminimumof 25%ofthe nozzle-to-vesselweldsandnozzleinsideradiussections,includingatleastonenozzlefromeachsystemandnominalpipesizeduringthe4thinspectioninterval.Foreachoftheidentifiednozzle assembliesinTable3,boththe nozzle-to-vesselweldandtheinsideradiussectionforthatschedulednozzle assemblywillbeexamined.Duringthistimeframe,betweenthestartofthe4thIntervalandtheendofthe 40-yearinitial40year operating license, examinationswillbe distributedandscheduledasrequiredby IWB-2400andTableIWB-2411totheextentpractical.Thus,thiswillincludeonlyschedulingand performing examinationsforthe applicable nozzle assemblieslistedinTable3forthefirstandsecondinspectionperiodsofthe4thIntervaluptotheendoftheinitialGGNS operatinglicenseonNovember1,2024.Tosupportthisproposed alternative,resultsofprevious examinationsareshowninTables1and2basedonthe2nd Interval examinations performed in accordancewithASMESectionXIandthe3rdIntervalexaminationsofAlternativeRequest GG-ISI-013,whereASMECodeCaseN-702was authorizedforuseinReference4.Alltheindicationsnotedwererecordedand evaluated in accordancewiththeASMESectionXICodeofRecordforthe2ndand3rd intervals and determinedtobewithintheallowablelimitsof IWB-3000andassuchwereNOTreportable.TheactualUT examinations were performed in accordance with AppendixVIII.Basedonsizingandevaluationall recordable indicationslistedwerebelievedtobe geometricand/orfabricationrelated.Inaddition,noneoftherecorded indicationsrequiredrepair.RefertoTables1and2belowintheExamResultscolumnforthe disposition of indicationsforeach applicable nozzle assemblyexaminedatGGNS. GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, IncGrandGulf NuclearStation(GGNS),Unit1FourthInterval Inservice Inspection(lSI)ProgramRequestNo.GG-ISI-021 Proposed Alternative Request in Accordancewith10CFR 50.55a(z)(1) -AcceptableLevelof Quality and Safety-ASMESectionXIrequiresthatallthirtyfive(35)nozzle assemblieslistedinTables1and2beexaminedduringeachlSIinspectioninterval.Forthe2ndIntervalASMESectionXIappliedand100 %ofthenozzle assemblies were examined in accordancewithTable IW8-2500-1 Examination Category8-Dandforthe3rdIntervalaminimumof 25%ofthenozzle assembliesforeachsystemandpipesizewereexaminedusingASMECodeCaseN-702as authorized by Reference4.Table3 identifiesthosenozzle assembliestobescheduledandexaminedduringthe4th 10-yearlSIIntervalusingthis alternative request.However,becauseASMECodeCaseN-702excludesthesix Feedwater(N04)andoneControlRodDrive Return (N10)nozzle assemblies,onlytwentyeight(28)totalnozzle assembliesareincludedinthescopeofthisrequest.Theexcludednozzle assembliesarelistedinTables1and2and identifiedasN/Aandwillcontinuetomeetthe requirementsofASMESectionXI,by performing 100%ofthesenozzleassembliesduringthe4th Interval.ASMECodeCaseN-702alsoincludesaprovisionthat stipulatesthataVT-1 visual examinationmethodmaybeusedinlieuofthe volumetric examinationmethodfortheinsideradius sectionsof(ItemNo.83.100)listedinTable2,butasofnowallinsideradiussection examinationswithinthescopeofthis alternative requesthavebeen performed previouslyatGGNSusingan ultrasonic examinationmethod.WiththisoptionavailableinASMECodeCaseN-702,GGNSmayperform examinationsontheinsideradius sectionslistedinTable2underCodeCaseN-702witheithertheVT-1orthe volumetric examinationmethodforthe4th Interval.Table1: Nozzle-to-Vessel Weld Examinations Item Comp.ID Item DescriptionExamResults Number 2nd Interval (1)3rd Interval (2)83.90 N01A-KA24"RPV OutletNozzleto NRI (3)NotRequired (5)Vessel 83.90 N018-KA24"RPV OutletNozzleto NRI (3)NRI (3)Vessel 83.90 N02A-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90 N028-KA12"RCSInletNozzletoVessel NRI (3)NRI (3)83.90 N02C-KA12"RCSInletNozzletoVessel NRI (3)NRI (3)83.90 N02D-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90 N02E-KA12"RCSInletNozzletoVesselSpot Indications NRI (3)inthebasemetalrecorded.No indication ofgrowthfrom previously recorded examinations. GNRO-2017/00034Attachment1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR SO.SSa(z)(1) -Acceptable Level of Quality and Safety-Table 1: Nozzle-to-Vessel Weld Examinations Item Comp.ID Item Description Exam Results Number 2nd Interval (1)3rd Interval (2)83.90 N02F-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90 N02G-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N02H-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N02J-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N02K-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N02M-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N02N-KA12"RCSInletNozzletoVessel NRI (3)NotRequired (5)83.90N03A-KA24"MainSteamNozzletoSpotIndications NRI (3)Vesselinthebasemetalrecorded.Noindicationofgrowthfrom previously recorded examinations. 83.90 N038-KA24"MainSteamNozzleto 8ase Metal NRI (3)Vessel IndicationsExamined,butrecorded.Nonotcountedforindicationoftherequiredgrowthfrom 25%.previously recorded examinations. 83.90 N03C-KA24"MainSteamNozzleto NRI (3)NotRequired (5)Vessel 83.90 N03D-KA24"MainSteamNozzletoNozzleCladdingNotRequired (5)VesselCutBack Geometry Indication. 83.90 N04A-KA 14" FeedwaterNozzletoVessel N/A (4)N/A (4)83.90 N048-KA 14" FeedwaterNozzletoVessel N/A (4)N/A (4)83.90 N04C-KA 14" FeedwaterNozzletoVessel N/A (4)N/A (4) GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, IncGrandGulf Nuclear Station (GGNS),Unit1FourthInterval Inservice Inspection(lSI)ProgramRequestNo.GG-ISI-021 Proposed AlternativeRequestin Accordancewith10CFR 50.55a(z)(1) -AcceptableLevelof Quality and Safety-Table1: Nozzle-to-Vessel Weld Examinations Item Comp.ID Item DescriptionExamResults Number 2nd Interval (1)3rd Interval (2)B3.90 N04D-KA 14 11 FeedwaterNozzletoVessel N/A (4)N/A (4)B3.90 N04E-KA 14 11 FeedwaterNozzletoVessel N/A (4)N/A (4)B3.90 N04F-KA 14 11 FeedwaterNozzletoVessel N/A (4)N/A (4)B3.90 N05A-KA 12 11CoreSprayNozzleto Geometric NRI (3)Vessel I ndicationduetoCoreSpray Bracket Pad Buildup and Nozzle CladdingStripBacking. No indication ofgrowthfrom previously recorded examinations. B3.90 N05B-KA 12 11CoreSprayNozzleto GeometricNotRequired (5)Vessel I ndicationduetoCoreSpray Bracket PadBuildupand Nozzle CladdingStripBacking. No indication ofgrowthfrom previously recorded examinations. B3.90 N06A-KA 12 11RHR/LPCIInletNozzleto NRI (3)NRI (3)Vessel B3.90 N06B-KA 12 11RHR/LPCIInletNozzleto NRI (3)NotRequired (5)Vessel B3.90 N06C-KA 12 11RHR/LPCIInletNozzleto NRI (3)NotRequired (5)Vessel B3.90 N07-KA 15.5 11RCICTopHeadSpray NRI (3)NRI (3)InletNozzle GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of Quality and Safety-Table 1: Nozzle-to-Vessel Weld Examinations Item Comp.ID Item Description Exam Results Number 2nd Interval (1)3rd Interval (2)83.90 N08-KA15.5"RCICTopHeadSpray NRI (3)NRI (3)SpareInletNozzle 83.90 N09A-KA4"JetPump Instrument Nozzle Inner DiameterNotRequired (5)toVessel(ID)cladding cut-backandnozzle bore geometry indications. 83.90 N098-KA4"JetPump Instrument Nozzle One Laminar NRI (3)toVessel reflectorinthebasemetal recorded.10claddingcut-backandnozzle bore geometry indications recorded.83.90 N10-KA4"CRDReturnNozzletoVessel N/A (4)N/A (4)83.90 N16-KA8"Vibration Instrument Nozzle NRI (3)NRI (3)toVessel Notes: (1)Examinations were performedon100%ofthese Nozzle-to-VesselWeldsforthe2nd Interval.(2)Examinations were performedonaminimumof 25%ofthese Nozzle-to-VesselWeldsbysystemandnominalpipesizeforthe3rd Interval.(3)NoRecordableIndications.(4)Not Applicabletothisrequest,ASMECodeCaseN-702 excludestheFeedwater(N04)andControlRodDriveReturn(N10)nozzle assemblies. Therefore,thesearenotwithinthescopeofthisrequestandwill continuetomeetthe requirementsofASMESectionXICode Table IW8-2500-1 by performing 100%examinationofthesenozzle assembliesduringthe4thInterval.(1)Notrequiredtobeselectedfor examinationtomeetthe 25%sampleperCodeCaseN-702. Table 2: Nozzle Inside Radius Section Examinations GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFRSO.SSa(z)(l) -Acceptable Level of auality and Safety-Item Comp.ID Item Description Exam Results Number 2nd Interval (1)3rd Interval (2)83.100 N01A-KA24"RPV OutletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N018-KA24"RPV OutletNozzleInside NRINRI (3)Radius 83.100 N02A-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N028-KA12"RCSInletNozzleInside NRI (3)NRI (3)Radius 83.100 N02C-KA12"RCSInletNozzleInside NRI (3)NRI (3)Radius 83.100 N02D-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02E-KA12"RCSInletNozzleInside NRI (3)NRI (3)Radius 83.100 N02F-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02G-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02H-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02J-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02K-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02M-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N02N-KA12"RCSInletNozzleInside NRI (3)NotRequired (5)Radius 83.100 N03A-KA24"MainSteamNozzleInside NRI (3)NRI (3)Radius 83.100 N038-KA24"MainSteamNozzleInside NRI (3)NRI (3)RadiusExamined,butnotcountedfor GNRO-2017/00034Attachment1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR SO.SSa(z)(1) -Acceptable Level of Quality and Safety-Table 2: Nozzle Inside Radius Section Examinations Item Comp.ID Item Description Exam Results Number 2nd Interval (1)3rd Interval (2)therequired 25%.83.100 N03C-KA 24 11MainSteamNozzleInside NRI (3)NotRequired (5)Radius 83.100 N03D-KA 24 11MainSteamNozzleInside NRI (3)NotRequired (5)Radius 83.100 N04A-KA 14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100 N048-KA 14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100N04C-KA14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100N04D-KA14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100N04E-KA14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100N04F-KA14 11 FeedwaterNozzleInside N/A (4)N/A (4)Radius 83.100N05A-KA12 11CoreSprayNozzleInside Geometric NRI (3)Radius reflectors recorded.83.100 N058-KA 12 11CoreSprayNozzleInside NRI (3)NotRequired (5)Radius 83.100N06A-KA12 11RHR/LPCIInletNozzle NRI (3)NRI (3)InsideRadius 83.100 N068-KA 12 11RHR/LPCIInletNozzle NRI (3)NotRequired (5)InsideRadius 83.100 N06C-KA 12 11RHR/LPCIInletNozzle NRI (3)NotRequired (5)InsideRadius 83.100N07-KA15.5 11RCICTopHeadSpray NRI (3)NRI (3)InletNozzleInsideRadius 83.100 N08-KA 15.5 11RCICTopHeadSpray NRI (3)NRI (3) GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (151)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of Quality and Safety-Table 2: Nozzle Inside Radius Section Examinations Item Comp.ID Item Description Exam Results Number 2nd Interval (1)3rd Interval (2)Spare Inlet Nozzle Inside Radius 83.100 N09A-KA 4" Jet Pump Instrument Nozzle NRI (3)Not Required (5)I nside Radius 83.100 N098-KA 4" Jet Pump Instrument Nozzle NRI (3)NRI (3)Inside Radius 83.100 N10-KA 4" CRD Return Nozzle Inside N/A (4)N/A (4)Radius 83.100 N16-KA 8" Vibration Instrument Nozzle NRI (3)NRI (3)I nside Radius Notes: (1)Examinations were performedon100%of these Nozzle Inside Radius Sectionsforthe 2nd Interval.(2)Examinations were performedona minimum of 25%of these Nozzle Inside Radius Sections by system and nominal pipe size forthe3rd Interval.(3)No Recordable Indications. (4)Not Applicable to this request, ASME Code Case N-702 excludes the Feed water (N04)and Control Rod Drive Return(N10)nozzle assemblies. Therefore, thesearenot within the scope of this request and will continue to meet the requirements of ASME Section XI by performing 100%examination of these nozzle assemblies duringthe4th Interval.(5)Not requiredtobe selected for examination to meet the 25%sample per Code Case N-702. GNRO-2017/00034Attachment1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of Quality and Safety-Table 3: Nozzle Assemblies to be Examined for the 4th Interval Group Description of Nozzle Assemblies Quantity Minimum Examination N0124"RecirculationOutlet 2 1 N0212"RecirculationInlet 12 3 N0324"MainSteamLine4 4 1 N0512"CoreSpray 2 1 N06 12" RHR/LPCllnlet 3 1N0715.5"RCICTopHeadSprayInletNozzle 1 1 N0815.5"RCICTopHeadSprayInletSpareNozzle 1 1 N094"JetPumpInstrumentation 2 1 N168"VibrationInstrumentation 1 1Note:ASMECodeCaseN-702excludestheFeedwater(N04)andControlRodDriveReturn(N10)nozzleassemblies.Therefore,thesearenotlistedherebecausetheyarenotwithinthescopeofthisrequest.ThesenozzleassemblieswillcontinuetomeettherequirementsofASMESectionXICodeTableIWB-2500-1,byperforming100 %examinationofthesenozzleassembliesduringthe4thInterval. 5.Basis for UseCurrently,ASMECodeCaseN-702islistedinNRCRegulatoryGuide1.147,Revision17,(Reference5)asconditionallyacceptableforuse.Theconditionreadsasfollows: "The technical basis supporting the implementation ofthisCodeCaseis addressedbyBWRVIP-108:BWRVesselandInternalsProject,"TechnicalBasisfortheReduction of Inspection RequirementsfortheBoiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii,"EPRITechnicalReport1003557, October 2002 (ML-023330203) and BWRVIP-241:BWRVessel andInternalsProject,"ProbabilisticFractureMechanicsEvaluationfortheBoilingWater ReactorNozzle-to-VesselShellWeldsandNozzle Blend Radii,"EPRITechnical Report 1021005, October 2010(ML11119A041).The applicabilityofCodeCaseN-702 mustbeshownby demonstratingthatthecriteriainSection5.0 of NRC Safety Evaluation regarding BWRVIP-108 dated December 18, 2007 (ML073600374)orSection5.0 of NRC Safety Evaluation regarding BWRVIP-241 1 dated Apri/19, 2013(ML13071A240)aremet.Theevaluation 1GGNSmeetsthe demonstrationcriteriainSection5.0oftheNRCSafety EvaluationofBWRVIP-108anddoesnotneedtouse BWRVIP-241. GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of auality and Safety-demonstrating the applicabilitv oftheCodeCase shall be reviewed and approvedbvtheNRC priortothe applicationoftheCode Case."GGNShaschosentousethecriteriainSection5.0oftheBWRVIP-108asallowedabovefor demonstrating the applicabilityofASMECodeCaseN-702withthe background provided below.ElectricPowerResearch Institute (EPRI)Technical Report 1003557,BWRVessel andInternalsProject(BWRVIP),TechnicalBasisforthe Reduction of Inspection RequirementsfortheBoilingWater Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, (Reference6)providesthebasisforASMECodeCaseN-702.The evaluationfoundthatthefailure probabilityduetoaLow Temperature Overpressureeventatthenozzleblendradiusregionand nozzle-to-vesselshellweldisverylow(i.e.,<1X10-6for40years)withorwithoutlSIandthis evaluationisonly applicabletotheinitial40yearsofoperationforGGNS.Thereportconcludesthat inspection of 25%ofeachnozzletypeis technically justified. BWRVIP-108 was originally submittedtotheNRCforreviewand approval via BWRVIPletter2002-323on November 25,2002 (Reference 7), supplemented by Tennessee Valley Authority(TVA)letterdatedNovember 15,2004 (Reference8),and BWRVIPlettersdatedJuly 25,2006, and September13,2007(References9and 10).On December19,2007,theNRCissueda Safety EvaluationReport(SER)approvingtheuseofBWRVIP-108(Reference11).Section5.0oftheSERstatesthateachlicenseeshould,withintherequestforalternative, demonstratetheplantmeetsthe specified criteriaandthe demonstration is contained in Attachment 1.6.ConclusionThisproposed alternativetouseASMECodeCaseN-702inlieuoftheASMECode,SectionXIrequirementsprovidesan acceptablelevelof quality and safety in accordancewith10CFR 50.55a(z)(1)forallapplicable RPV nozzle-to-vesselweldsandnozzleinsideradius sections excludingtheN04andN10nozzleslistedinTables1and2,andforthosenozzle assembliestobe examined and scheduledinTable3.7.Duration of Proposed Alternative Upon authorizationbyNRC,thisrequestforan alternativetouseASMECodeCaseN-702willbe implementedduringthe4th 10-yearlSIInterval beginning on December1,2017andendingon November 1,2024,which correspondstothe40yearsofinitial operationthattheBWRVIP-108(Ref.6)evaluationisapplicabletoforGGNS. 8.PrecedentsTheNRCStaffhas authorized similarrequestsbasedonmeetingthe demonstrationcriteriaofBWRVIP-108asrequiredfortheuseofCodeCaseN-702 includingthelast authorized request GG-ISI-013tousethisCodeCaseatGGNSforthe3rd 10-yearlSIInterval,whichis Reference4,andthe precedentslistedbelow: GNRO-2017/00034 Attachment 1 Entergy Nuclear Operations, Inc Grand Gulf Nuclear Station (GGNS), Unit 1 Fourth Interval Inservice Inspection (lSI)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordance with10CFR50.55a(z)(1) -Acceptable Level of auality and Safety-*RiverBendStation,DocketNo.50-458,"RiverBendStation,Unit1-RBS-ISI-015ProposedAlternativeTo10CFR50.55a Examination RequirementsForReactor PressureVesselWeldInspections,NRCSER(TACNo. ME2817)", August 2,2010 (ADAMS Accession No.ML0101440097)*Cooper NuclearStation,DocketNo.50-298,"Cooper Nuclear Station-RequestForReliefNo.Ri-04forTheFourth10-Year Inservice InspectionIntervalRegarding InspectionofReactorVesselNozzle-VesselShell Welds,NRCSER(TACNo.ME3319)", October 8,2010(ADAMSAccessionNo. ML100470703)*PilgrimNuclearPowerStation,DocketNo.50-293,"Relief Request PRR-20, Alternative Examination Requirements for Nozzle-To-ShellandInnerRadiiWeldsUsingASMECodeCaseN-702 and BWRVIP-108, NRC'-SER(TACNo.ME3290)", August 25,2010 (ADAMS Accession No.ML102290163) 9.References1.ASMESectionXI,2007Editionthroughthe2008 Addenda2.ASMEBoilerandPressureVesselCode,CodeCaseN-702,"Alternative RequirementsforBoilingWaterReactor(BWR)NozzleInnerRadiusand Nozzle-to-ShellWelds,SectionXI,Division1," February20,20043.Requestfor Alternative GG-ISI-013, Proposed Alternativeto10CFR50,55aExamination RequirementsforReactorPressureVesselWeld Inspections,DocketNo.50-416,LicenseNo,NPF-29,Dated:April6,2011,(ADAMS AccessionNo.ML110960459)4.GrandGulf NuclearStation,Unit1-ReliefRequest GG-ISI-013BasedOnCodeCaseN-702,NRCSER(TACNo.ME5990),Dated: November 4,2011, (ADAMS AccessionNo.ML112710328)5.NRC RegulatoryGuide1.147,Revision17, Inservice InspectionCodeCase Acceptability, ASMESectionXI,Division1,Dated: August2014,(ADAMS AccessionNo.ML13339A689)6.EPRI TechnicalReport1003557, BWRVIP-108: BWR Vessel and Internals Project, TechnicalBasisfor the Reduction of Inspection Requirementsforthe Boiling Water Reactor Nozzle-to-VesselShellWelds and Nozzle Bend Radii, Dated: October 20027.Letterfromthe BWRVIPtotheNRC(2002-323), ProjectNo.704-BWRVIP-108: BWR Vessel and Internals Project, TechnicalBasisforthe Reduction of Inspection Requirementsforthe Boiling Water GNRO-2017/00034Attachment1 Entergy Nuclear Operations, IncGrandGulf Nuclear Station (GGNS),Unit1FourthInterval Inservice Inspection (151)Program RequestNo.GG-ISI-021 Proposed Alternative Request in Accordancewith10CFR SO.SSa(z)(1) -AcceptableLevelof Quality and Safety-Reactor Nozzle-to-Vessel Shell Welds and Nozzle Bend Radii, Dated: November25,2002,(ADAMSAccessionNo. ML023330203)8.LetterfromTVAtotheNRC, Browns Ferry Nuclear Plant (BFN)-Units 2 and 3 American Society of Mechanical Engineers (ASME)Section XI, Inservice Inspection (151)Program-Requests for Relief15/-22, and 3-/5/-18 for Examination of Reactor PressureVessel(RPV) Nozzle-to-VesselShellWelds and Nozzle Inner Radius Sections-ResponsetoNRCrequestforAdditionalInformation(RAI),(TACNos.MC0167andMC0168),Dated: November15,2004,(ADAMSAccessionNo.ML043380321)9.LetterfromtheBWRVIPtotheNRC(2006-349), Project 704-BWRVIP ResponsetoNRC Request for Additional Information on BWRVIP-108,Dated:July 25,2006,(ADAMSAccessionNo.ML062080159)10.LetterfromtheBWRVIPtotheNRC(2007-268), Project 704-Supplemental Analyses Supporting BWRVIP-108, Dated: September13,2007,(ADAMSAccessionNo. ML072600167)11.Letterfrom/theNRCtotheBWRVIP,SafetyEvaluationof ProprietaryEPRIReport,"BWRVesselandInternalsProject,TechnicalBasisfortheReductionofInspection RequirementsfortheBoilingWater Reactor Nozzle-to-VesselShellWeldsandNozzleInnerRadius(BWRVIP-108),"Dated:December19,2007,(ADAMSAccessionNo. ML073600374)12.GGNSCalculationMC-Q1B13-10002, Reduction of Inspection Requirements on RecirculationInletand Outlet Nozzles, Rev.o. Attachment 2 to GNRO-2017/00034 Attachment 1 to Relief GG-ISI-021, Responses to BWRVIP-108, Plant-Specific Applicability Criteria GNRO-2017/00034 Attachment 2 Attachment 1 to Relief GG-ISI-021, Responses toBWRVIP-108, Plant-Specific Applicability CriteriaSection5.0oftheNRC'sSERthat approvedtheuseof BWRVIP-108 (Reference 11)statesinpart: "LicenseeswhoplantorequestrelieffromtheASMECode,SectionXI requirementsforRPV nozzle-to-vesselshellweldsandnozzle inner radius sectionsmayreferencetheBWRVIP-108reportasthe technicalbasisfortheuseofASMECodeCase702asan alternative. However, eachlicenseeshould demonstratethe specific applicationoftheBWRVIP-108reportto theirunitsinthereliefrequestby showingthatallthe following general and nozzle-specific criteria are satisfied:" GGNS applicability was evaluated and demonstrated as documentedinGGNS CalculationMC-Q1B 13-10002, Reduction of Inspection Requirements on Recirculation Inlet and Outlet Nozzles,Rev.0 (Reference12).This demonstration is summarized below.Applicable GGNS Terms and Parameters

• Reactor PressureVessel(RPV) constantforinletnozzle, CRPV2=19,332psi*RPV constantforinletnozzle, CNozzle3=1,637 psi*RPV constant for outlet nozzle, CRPV4=16,171psi*RPV constant for outlet nozzle, CNozzle5=1,977psi*Reactor core pressure=1,056psigor1

,070.696 psia*MaximumRPVradius= 126.75 inches*RPVwall thicknessatNozzleN2,t2= 7.4479[(AvgLong+AvgTrans)/2J*RPVwall thicknessatNozzleN1,t4= 7.4948 inches[(AvgLong+AvgTrans)12J*Nozzle innerradiusfor outletnozzles,rj= 10.84375 inches*Nozzle outerradiusfor outletnozzles,r o=20.03125 inches*Nozzle innerradiusforinletnozzles,rj= 5.8125 inches*Nozzle outerradiusforinletnozzles,r o=13.125 inches GNRO-2017/00034 Attachment 2 Attachment 1 to Relief GG-ISI-021, ResponsestoBWRVIP-108, Plant-Specific Applicability Criteria General CriterionCriterion1 The maximum RPV Heat/Cooldownrateislimitedtolessthan 115°F/hour. GGNS ComplianceMaximumheatupandcooldownratesarelimitedto

5100°Fin anyone-hourperiod,in accordancewithGGNS Technical Specification Surveillance Requirement 3.4.11.1.Criteria for the Recirculation Inlet NozzlesCriterion2 GGNS Compliance (pxr)=(1056 psix126.75 in)=0.9296<LlS CRPvi2 19332(7.4479 in)Criterion3 GGNS Compliance Criteria for the Recirculation Outlet NozzlesCriterion4 GNRO-2017/00034 Attachment 2 Attachment1toRelief GG-ISI-021, ResponsestoBWRVIP-108, Plant-Specific Applicability Criteria (pxr)<1.15 CRPV4/4 GGNS Compliance (p x r)=(1056 psi x 126.75 in)=1.104<1.15 CRflV4/4 16171(7.4948)Criterion5 GGNS Compliance p x (r}+r;2)_1056psi x (20.03125)2

+(10.84375)2 =0.97698<1.15 Cllozzle5 (r o 2-r/)-1977 (20.03125)2-(10.84375)2Theresultsoftheabove equations demonstrate the applicabilityofBWRVIP-108toGGNSby showingthefivecriteria specifiedinSection5.0oftheNRCSERaremet.}}