ML17265A765

Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request

ML17265A765
Person / Time
Site:	Ginna
Issue date:	10/08/1999
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	VISSING G S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9910210041
Download: ML17265A765 (55)

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CATEGORY14'PREGULA'IHRYINFORMATIONDXSTRIBUTIOYSTEM(RIDS)ACCESSIONNBR:9910210041DOC.DATE:99/10/08NOTARIZED:NODOCKETFACXL:%0-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterG05000244ASH.NAMEAUTHORAFFILIATION'MECRhD'Y,R.C.RochesterGas6ElectricCorp.WECXP.NAMERECIPIENTAFFILIATIONVISSXNG,G.S.

SUBJECT:

Forwardsfifteenreliefrequeststhatwillbeutilizedfor.GinnaNPPfourthintervalISIprogramthatwillstartonJan1,2000.Attachment1includessummaries6detaileddescriptionofeachreliefrequest.ADISTRIBUTIONCODE:A047DCOPIESRECEIVED:LTRlENCL$SIZE:5~TTITLE:ORSubmittal:Inservice/Testing/RelieffromASMECodeENOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).050002446RECIPIENTIDCODE/NAMELITTLE,SINTERNAL:~EXLE=CENXER,03.~OGC/RPRES/DET/MEBCOPIESLTTRENCL11111011RECIPIENTIDCODE/NAMEVXSSXNG,GNUDOCS-ABSTRACTRES/DET/ERABCOPIESLTTRENCL111111EXTERNAL:LITCOANDERSONNRCPDR1111NOAC11D'ENOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTETHTOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROF.COPIESREQUIRED:LTTR10ENCL' AHDASubsiChoryofRGSEnergyGroup,Inc.ROCHESTERGASANDELECTRICCORPORATION~89EASTAVENUE,ROCHESTER,N.Y.W6d9400l~7I65rf6-2700wwwrge.cornRO8ERTC.MECREDYVicepresidentNvdeerOperohonsOctober8,1999U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:GuyS.VissingProjectDirectorateIWashington,D.C.20555

Subject:

GinnaNuclearPowerPlantInserviceInspectionASMESectionXIRequiredExaminations,ReliefRequestsR.E.GinnaNuclearPowerPlantDocketNo.50-244

DearMr.Vissing:

Thepurposeofthisletteristosubmitfifteen(15)ReliefRequeststhatwillbeutilizedforourFourthIntervalISIProgramthatwillstartonJanuary1,2000.EnclosedasAttachment1isasummaryofourReliefRequestsaswellasadetaileddescriptionofeachindividualreliefrequest.Table1identifieseachreliefrequest,thesubjectofeachrelief,andidentifiesthereferenceparagraphof10CFR50.55adealingwiththetypeofreliefthatisbeingrequested.Thefirst13individualreliefrequestscontainedwithinthebodyofAttachment1arevirtuallyidenticaltothoseapprovedforuseduringourThirdIntervalProgram(minordifferencesareexplainedinTable1ofAttachment1).AcrossreferencetotheThirdIntervalReliefRequestisidentifiedonthetopofeachcurrentproposed'eliefrequestforyourconvenience.ReliefRequests14and15areidenticaltoReliefRequests42and43,recentlysubmittedforourThirdIntervalISIprogram.ItshouldbenotedthatourFourthIntervalISIProgramhasbeendevelopedtoASMESectionXI,1995Edition,1996Addenda,asdescribedinourAugust26,1999submittalofproposedReliefRequest35.RG&EwillalsoimplementtheEPRIPerformanceDemonstrationInitiative(PDI)toimplementmandatoryAppendixVIII,consistentwith10CFR50.55a(b)(2)(xv)ofthefinal10CFR50.55aRuleeffectiveNovember22,1999.Furthermore,forASMESectionXIrepairsandreplacements,ASMESectionIIICode,1995Edition,1996Addendashallbeusedasapplicable.Finally,wewillbemaintainingthecurrentrequirementsforIWEandIWL,whichwillbeASMESectionXI,1992Edition,1992Addenda.Thisistheexistingcodeofrecordper10CFR50.55a.Verylyyours,99i02i004i99i008lPDRADOCK05000244I8PDR'I~iRobertC.MecredyPDtI7 Attachmentxc:Mr.GuyS.Vissing(MailStop8C2)ProjectDirectorateIDivisionofLicensingProjectManagementOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555RegionalAdministrator,RegionIU.S.NuclearRegulatoryCommission475AllendaleRoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector

/r~s/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page1of48TABLE1SUMMARYOFRELIEFREQUESTSRELIEF10CFRREQUESTRELIEFNUMBERREFERENCE50.55a(a)(3)(ii)50.55a(a)(3)(ii)RELIEFREUESTSUBJECTDeferRPVExaminationstoEndofInterval.VisualInternalExaminationofClass1valves50.55a(g)(5)(iii)CategoryB-J.CastStainlessBaseMetalUltrasonicExamination.50.55a(a)(3)(ii)RegenerativeHeatExchanger(RHE),Class1Examinations,(Note:ThereferencetoItemNumberB3.160perthe3IntervalReliefRequestNumber18-1hasbeenmovedtoReliefRequest6below.)50.55a(a)(3)(ii)Alloy690WeldMaterial,FabricationofNewSteamGenerators.50.55a(g)(5)(iii)RegenerativeHeatExchanger(RHE),InnerRadiusExaminations.50.55a(g)(5)(iii)ComponentSupportIntegralAttachmentExaminationLimitations.50.55a(g)(5)(iii)SurfaceExaminationlimitationsassociatedwithweldexaminationsofidentifiedClass1safeendnozzlesassociatedwiththeReactorPressureVessel.(Note:ReflectsSurfaceExaminationpercentageactuallyachievedduringthe1999OutageExamination,)1050.55a(a)(3)(ii)50.55a(a)(3)(ii)VisualExaminationofmetalcontainmentseals&gaskets.SuccessiveExaminationstorepairedareas.991021004>

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page2of48TABLE1SUMMARYOF<RELIEFREQUE<STSRELIEF10CFRREQUESTRELIEFNUMBERREFERENCERELIEFREUESTSUBJECT50.55a(a)(3)(ii)Bolttorqueortensiontestforboltedconnections.1250.55a(a)(3)(i)VT-2VisualExaminationfollowingrepair,replacement,ormodification.1350.55a(a)(3)(ii)MinimumilluminationandmaximumdirectexaminationdistanceofClassCCcomponents.1450.55a(g)(5)(iii)ReactorPressureVessel(RPV)WeldExaminationLimitations.1550.55a(g)(5)(iii)ResidualHeatRemoval(RHR)HeatExchangerOutletNozzleWeldExaminationLimitation.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page3of48RELIEFREQUESTNO.1(WaspreviouslyapprovedasReliefRequestNo.1forThirdInterval)DEFERRPVEXAMINATIONSTOENDOFINTERVALI.Sstem/ComonentforWhichReliefisRuested:ReliefisrequestedfortheReactorPressureVessel(RPV)Shell-to-FlangeandHead-to-FlangeWelds.IICodeReuirementASMESectionXI,1995Edition1996Addenda,CategoryB-A,ItemNumbersB1.30andB1.40.III.CodeRuirementfromWhichReliefisRuested:TableIWB-2500-1,ExaminationCategoryB-A,ItemNumberB1.30,requiresthattheRPVShell-to-Flangeweldbeexaminedduringthefirstandthirdperiodsinconjunctionwiththenozzleexaminations,withatleast50percentexaminedduringthefirstperiodandtheremainderbytheendofthethirdperiod.TherequiredShell-to-Flangeexaminationisimpracticalifperformedduringtheperiodsspecifiedasitcanonlybeaccomplishedfromtheflangesurface.WhenperformingthisweldexaminationfromtheVesselinsidesurface,qualifiedUTtechniquescanbeutilizedtoperformamorereliableexaminationwithgreaterexaminationcoverageasdemonstratedduringour199910-YearVesselexamination.TableIWB-2500-1,ExaminationCategoryB-A,ItemNumberB1.40,requiresthattheRPVHead-to-Flangeweldbeexaminedfromtheflangefaceonlyduringthefirstandsecondperiods,providedthatthesesameportionsateexaminedfromtheheadduringthethirdperiod.IV.BasisforRelief:TheReactorPressureVesselisamajorsourceofradiationexposureaccumulatedduringanormalrefuelingoutageInserviceinspection.ByperformingtheaboveCategoryandItemexaminationsattheendoftheintervaltherewillbenosacrificeinthequantitynorqualityofexaminationsbut,therewillbeasubstantialreductioninradiationexposure.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page4of48RELIEFREQUESTNO.1(Con't)V.AlternateExaminations:R.E.GinnaNuclearPowerPlantproposesthattheexaminationsidentifiedabovebeperformedfromboththeflangesurfaceandthevesselwallatorneartheendofinterval.VI.JustificationforGrantinofReliefDuringthefirstthreeinspectionsintervals,100percentoftheaccessiblelengthoftheRPVweldsincludingtheShell-to-Flangeweldswereexaminedatorneartheendoftheintervalwhentheentireexaminationcouldbeperformedfromboththeflangesurfaceandthevesselwall.Thisisamorepracticalapproachinthattherequiredexaminationsfrombothsurfacescanbeperformedatthesametime.Duringthefourthinterval,100percentoftheaccessiblelengthofallRPVweldsincludingtheshell-to-flangeandhead-to-flangeweldswillbeperformedatorneartheendoftheintervalwhenalltherequiredexaminationscanbeperformedatthesametime.Also,Class1Leakageexaminationsareperformedeachoutagetoensuresystem/componentintegrity.VII.ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

I'>vs/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision'0Page5of48RELIEFREQUESTNO.2VISUALINTERNALEXAMINATIONOFCLASS1VALVES(WaspreviouslyapprovedasReliefRequestNo.5forThirdInterval)Sstem/ComonentsforWhichReliefisReuested:Class1valvesrequiringvalvebodyinternalVTexamination.10101010101010106666ValveNo.842A842B867A867B700701720721853A853B852A852B~F1~/TgeDarling/CheckDarling/CheckDarling/CheckDarling/CheckVelan/GateVelan/GateVelan/GateVelan/GateVelan/CheckVelan/CheckVelan/GateVelan/GateLineNo.IOA-SI2-1502-A10A-SI2-2501-BIOA-SI2-2501-AIOA-SI2-2501-BIOA-RC02501-AIOA-RCO-2501-AIOA-RCO-2501-B10A-RCO-2501-B6A-RC-2501-A6A-RC-2501-B6A-RC-2501-A6A-RC-2501-BCodeReuirements:ASMESectionXI,1995Edition1996Addenda,CategoryB-M-2,ItemNumberB12.50.CodeReuirementfromWhichReliefisRuestedTableIWB-2500-1,ExaminationCategoryB-M-2ItemB12.50,requiresaninternalVT-3examinationonatleastonevalvewithineachgroupofvalvesthatareofthesamesize,constructionaldesign(suchasglobe,gateorcheckvalves)andmanufacturingmethod,thatperformsimilarfunctionsinthesystem.Thisreliefrequestisbasedonthefollowingpoints:Tocompletethesubjectexamination,unnecessaryexpendituresofman-hoursandmanremarerequiredwithessentiallynocompensatingincreaseinplantsafety,and2.Thestructuralintegrityaffordedbyvalvecasingmaterialutilizedwillnotsignificantlydegradeoverthelifetimeofthevalve.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page6of48III(Con't)RELIEFREQUESTNO.2(Con't)BasedondatacompiledfromaplantsimilarinageanddesigntoGinnaStation,itisexpectedthatapproximately100man-hoursand5-manremexposurewouldberequiredtodisassemble,inspect,andreassemblethesevalves.Performingthisvisualexaminationundersuchadverseconditions,highdosesrate(30-40R/hr),andpoor+as-castsurfaceconditions,realisticallyprovideslittleadditionalinformationastothevalve'scasingintegrity.Thevalves'aterial,ahigh-strengthcaststainlesssteel(ASTMA351-CF8),iswidelyusedinthenuclearindustryandhasperformedextremelywell.Thepresenceofsomedeltaferrite(typically5%ormore)substantiallyincreasesresistancetointergranularstresscorrosioncracking.Thedeltaferritealsohelpsthematerialtoresistpittingandcorrosioninchloridecontainingenvironments.BasisforRelief:RG&Efeelsthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatthepublic'shealthandsafetywillnotbeadverselyaffectedbynotperformingavisualexaminationofthevalveinternalpressureboundarysurfaces.Additionally,thisvisualexaminationaddslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonneltounnecessaryradiationexposure.Therefore,arequestforrelieffromthisrequirementissought.AVT-3examinationshallbeperformedonceononevalvewithinthevalvegroupduringtheIntervalifdisassembledformaintenance.V.ProosedAlternativeExaminations:AsstatedaboveRGAEdoesnotbelievethatthevisualexaminationrequiredeachten-yearintervaliswarranted.However,asstandardmaintenancepracticedictates,whenthesevalvesaredisassembledformaintenancepurposes,avisualexaminationoftheinternalsandinternalpressureboundarysurfaceswillbeperformed,totheextentpractical.VI.JustificationforGrantinofRelief:RGB'eelsthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatthepublic'shealthandsafetywillnotbeadverselyaffectedbynotperformingavisualexaminationofthevalveinternalpressureboundarysurfaces.Additionally,thisvisualexaminationaddslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonneltounnecessaryradiationexposure.Also,Class1Leakageexaminationsareperformedeachoutagetoensuresystem/componentintegrity.

iIANbFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page7of48RELIEFREQUESTNO.2(Con't)ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page8of48RELIEFRE<QUESTNO.3(WaspreviouslyapprovedasReliefRequestno.17forThirdInterval)CATEGORYB-J,CASTSTAINLE<SSBASEMETALULTRASONICEXAMINATIONComonentsforWhichReliefisReuested:Class1,CategoryB-JItemB9.11,ReactorCoolantCastPumpTerminalEndtoCastElbowCircumferentialWeldsWeldIDPL-FW-XIIIPL-FW-XVElbow-to-PumpElbow-to-Pump~%Coverae45%50%CodeReuirements:ASMESectionXI,1995Edition,1996Addenda,CategoryB-J,ItemNumberB9.11.CodeReuirementsfromWhichReliefisReuestedCategoryB-JwithinTableIWB-2500-1,specifiesvolumetricexaminationrequirementsthataretobeperformedonweldsatTerminalEnds,aswellasothercircumferentialweldsassociatedinthesystem.2.CodeCaseN-460specifiesthatareductioninexaminationcoverageonanyClass1orClass2weldmaybeacceptedprovidedthereductionincoverageforthatweldislessthan10%.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page9of48RELIEFREQUE~STNO.3(Con't)BasisforRelief:Supplement4(b)(4)ofAppendixIIIidentifiesultrasonicscanningrequirementsonAusteniticandDissimilarMetalWelds.ThisparagraphfurtheridentifiesthatCastitemssuchasfittings,valvebodies,andpumpcasingsmayprecludemeaningfulexaminationsbecauseofgeometryandattenuationvariables.AtR.E.GinnaNuclearPowerPlant,theReactorCoolantPump,WestinghouseModel93,iscaststainless(A-351GrCF8M).Theassociatedfittings(elbows)arealsocaststainless(ASTMA-351GrCF8M)andcontainslongitudinalseamwelds.TheReactorCoolantInlet/OutletWroughtSafeEnd/PipetoElbowcircumferentialweldsconsistoffittings(elbows)thatarecaststainless(ASTMA-351GrCF8M).Whenemployingoptimizedultrasonictechniqueonthesecast/wroughtwelds,thetechniquesmaydetectlargeflaws(25%orgreaterthroughwall).Therefore,thesensitivityislessthanthatrequiredbytheCode.CastStainlessbasemetalandassociatedweldscontainlargegrainstructures,attenuationvariablesimpacttheperformanceofultrasonicexaminations.Experiencehasshownthatthesematerialsarenotalwaysamenabletoultrasonicexaminationanddoesnotproducereliableandmeaningfulresults.Currently,theindustry'sPerformanceDemonstrationInitiative(PDI)isnotaddressingCast"StainlessUltrasonicExaminations.Duetothehighlyattenuativecharacteristicsoftheausteniticgrainstructure,ultrasonicexaminationcoveragetotheextentthatisspecifiedwithinCodeCaseN-460maynotalwaysbeachievable.Radiography,ifapplied,isnotexpectedtoprovideanymeaningfulincreaseinbenefitbeyondthealternativepresentedduetothehighlevelsofbackgroundradiationemittingfromtheseareas,significantlydecreasingthesignal(imagetonoiseratio)oftheradiograph.

,/AVkFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page10of48RELIEFREQUESTNO.3(Con't)AlternateExaminations:None.ApplicableCode-requiredvolumetricexamination(UT)willbecompletedtothemaximumextentpractical(abesteffortexaminationofthecaststainlessweldsbasedonstate-of-the-arttechniquesandassociatedachievableexaminationcoverage).Wewillcontinuetoevaluatenewemerginginspectiontechnologyastheybecomeavailable.TheCoderequiredsurfaceexaminationsandsystemleakagetestswillbeperformed.JustificationforGrantinofRelief:VolumetricexaminationoncastAusteniticandDissimilarMetalweldsmayprecludemeaningfulexaminationsbecauseofgeometryandattenuationvariables.DuetothehighlyattenuativecharacteristicsoftheAusteniticgrainstructure,ultrasonicexaminationcoveragetotheextentthatisspecifiedwithinCodeCaseN-460maynotalwaysbeachievable.Radiography,ifapplied,isnotexpectedtoprovideanymeaningfulincreaseinbenefitduetothehighlevelsofbackgroundradiationemittingfromtheseareas.Volumetricexaminationofthecaststainlessweldsbasedonstate-of-the-arttechniquesandassociatedachievableexaminationcoverageshallbeperformed.ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

IAVOFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page11of¹8RELIEFREQUESTNO.4(WaspreviouslyapprovedasReliefRequestno.18-1forThirdInterval)REGENERATIVEHEATEXCHANGER(RHE),CLASS1EXAMINATIONSSstem/ComonentforWhichReliefisReuested:ChemicalandVolumeControlSystem;RegenerativeHeatExchanger(RHE),Class1portion.CodeReuirements:ASMESectionXI,1995Edition,1996Addenda,CategoryB-B,ItemNumbersB2.60,B2.80,andCategoryB-D,ItemNumbersB3.150CodeReuirementsfromWhichReliefisReuested:InaccordancewithTableIWB-2500-1,thefollowingCategoriesandItemNumbersrequirevolumetricexamination.CategoOItemNumberB-BB-BB-DB2.60B2.80B3.150Tubesheet-to-HeadWeldsTubesheet-to-ShellWeldsNozzle-to-VesselWeldsBasis:TheRegenerativeHeatExchanger(RHE)consistsofthree(3)shellandtubeheatexchangersconnectedinseries.TheRHEisdesignedtorecoverheatfromthereactorcoolantsystemletdownstreamduringnormaloperation.Theletdownstreamflowsthroughtheshellsideoftheheatexchanger.TheshellsideoftheRHEisClass1whilethetubesideisClass2.TheRegenerativeHeatExchangerprovidesthemajorsinglesourceofradiationexposureaccumulatedduringanormalrefuelingoutageInserviceinspection.ByperformingtheaboveCategoryandItemnumberexaminationsononeofthethreeheatexchangersseeingthemostextremeconditionswillprovidearepresentativesample,whilelimitingpersonnelradiationexposure.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page12of48IV(Con't)RELIEFREQUESTNO.4(Con't)FortheaboveCategories&ItemNumbers,thebottomheatexchangershouldbetheoneheatexchangerselectedsinceitoperatesatthehighesttemperatureofalltheunitsandisthereforethemosthighlystressed.Typicaloperatingtemperaturesforletdownflowisaround544Deg.F.andbetween300-350Deg.F.outofthetopshell.Bylimitingtheexaminationstooneheatexchangerwillsignificantlyreduceradiationexposuretopersonnel.TheexposuresavingstoISIrelatedpersonnelperinspectionintervalwouldbe19.6Man-RemWholeBodyand68.0Man-RemExtremitiesthroughthereductionof10examinations.V.AlternateExaminations:RochesterGas&Electric(RG&E)proposestoutilizethe"multiplestream"conceptwhenperformingavolumetricexaminationofaccessibleportionsofNozzle-to-VesselWeldsandNozzleInsideRadiusWeldsequivalenttooneofthethreeidenticalsectionsontheClass1RegenerativeHeatExchanger.Examinationsshallbeperformedonthelowersection.Theassociatedexaminationsshallbeperformedonceduringtheinterval.Inaddition,RG&EproposestoperformaVT-2visualexaminationontheentireRegenerativeHeatExchangerduringsystemleakagetests.VI.JustificationforGrantinRelief:TheRHEconsistofthree(3)shellandtubeheatexchangersconnectedinseries.Thebottomheatexchangeroperatesatahighertemperatureofalltheunitsandisthemosthighlystressed.Bylimitingtheexaminationstooneheatexchangerwillsignificantlyreduceradiationexposuretopersonnel.VII.ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page13of48RELIEFREQUESTNO.5(WaspreviouslyapprovedasReliefRequestNo.27forThirdInterval)ALLOY690WELDMATERIAL,FABRICATIONOFNEWSTEAMGENERATORSSstem/ComonentsforWhichReliefisReuested:FortheincorporationofCodeCases2142and2143intotheASMESectionXIProgram.TheseCasesallowtheuseofAlloy690weldmaterial,CodeReuirements:ASMESectionXI,1995Editionwith1996Addenda,IWA-4224Requirements.ASMEReuirementsfromwhichReliefisReuested:ReliefisrequestedfromtherequirementsspecifiedinIWA-4224ofthe1995Edition,with1996AddendaoftheASMESectionXICode.IWA-4224.3UseofaDifferentMaterial(a)Useofmaterialsofaspecification,grade,type,class,oralloy,andheat-treatedcondition,otherthanthatoriginallyspecified,shallbeevaluatedforsuitabilityforthespecifieddesignandoperatingconditionsinaccordancewithIWA-4311.(b)MaterialexaminationandtestingrequirementsshallbereconciledtotheConstructionCoderequirementsofthecomponent.BasisforRelief:TheuseofAlloy690typeweldfillermaterialisrequiredforthereplacementsteamgenerators.ThesematerialshavebeenapprovedbyASMEthroughCodeCases2142and2143andaredesignatedasUNSN06052andUNSW86152,respectively,andclassifiedthemasF-No.43forweldprocedureandperformancequalificationpurposesinaccordancewithASMESectionXI.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page14of48RELIEFREQUESTNO.5(Con't)IV(Con't)UNSW86152istheshieldedmetalarcweldingelectrodeforAlloy690andUNSN06052isthebarefillermetal.BothmaterialshavebeenshowninnumerousEPRIstudiestohaveimprovedcorrosionresistanceforAlloy690weldmentsascomparedtothecurrentlyusedNi-Cr-Fe(N06082andW86182)materials.ThenewweldmaterialsarethepreferredchoiceforweldingapplicationsinvolvingAlloy690inacorrosionenvironmentandtheyprovideanacceptablelevelofqualityandsafetybecauseoftheirsuperiorcorrosionresistantproperties.V.AlternateExaminations:IncorporateASME,Boiler8cPressureVesselCodeCase2142,"F-NumberGroupingforNi-Cr-Fe,ClassificationUNSN06052FillerMetal",andCase2143,"F-NumberGroupingforNi-Cr-Fe,ClassificationUNSW86152WeldingElectrode".JustificationforGrantinofRelief:BothUNSW86152andUNSN06052materialshavebeenshowninnumerousEPRIstudiestohaveimprovedcorrosionresistanceforAlloy690weldmentsascomparedtothecurrentlyusedNi-Cr-Fe(N06082andN86182)materials.ThenewweldmaterialsarethepreferredchoiceforweldingapplicationsinvolvingAlloy690thatwasutilizedinFabricatingthenewSteamGenerators.VH.ImlementationSchedule:UtilizationofthesematerialsmaybeusedduringtheFourthIntervalifandwhenneeded.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page15of48RELIEFREQUESTNO.6(WaspreviouslyapprovedasReliefRequestno.32forThirdInterval)REGENERATIVEHEATEXCHANGER(RHE),INNERRADIUSEXAMINATIONSSstem/ComonentsforWhichReliefisRuested:ChemicalandVolumeControlSystem;RegenerativeHeatExchanger(RHE),Class1InnerRadiusExaminations;RHE-NlRHE-N5CodeReuirements:ASMESectionXI,1995Editionwith1996Addenda,CategoryB-D,ItemNumberB3.160.CodeReuirementsfromWhichReliefisRuested:InaccordancewithTableIWB-2500-1,ExaminationCategoryB-D,ItemNumberB3.160.BasisforRelief:TheRegenerativeHeatExchanger(RHE)consistsofthree(3)shellandtubeheatexchangersconnectedinseries.TheRHEisdesignedtorecoverheatfromthereactorcoolantsystemletdownstreamduringnormaloperation.Theletdownstreamflowsthroughtheshellsideoftheheatexchanger.TheshellsideoftheRHEisClass1whilethetubesideisClass2.TheRHEprovidesthemajorsinglesourceofradiationexposureaccumulatedduringanormalrefuelingoutageInserviceinspection.InnerRadiusexaminationswerescheduledtobeperformedontheClass1sideofthebottomheatexchangerthatexperiencethemostextremeconditionsasspecifiedwithinReliefRequest¹4.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page16of48RELIEFREQUESTNO.6(Con't)IV(Con't)TheRHEinnerradiusexaminationsweretobeperformedonsmallheavywallnozzlesthatareconnectedto2"piping.Anin-depthinvestigationwasinitiatedbyRGBtodeterminethefeasibilityofperforminganacceptableCodeexamination.Theinitialinvestigationreviewedthenozzletype,weldplacementandactualODweldprofilesaswellasultrasonicmeasurementstoverifyIDconfiguration.ToassistintheevaluationofperforminganacceptableCodeultrasonicinnerradiusexamination,ComputerModelingandmockupsofthenozzletovesselconfigurationwereinitiated.ComputermodelingwasperformedbySouthwestResearchInstitute,AEATechnology,andEPRI.Computermodelingperformedbythevariousorganizationscomparedfavorably.Thecomputermodelinginitiativeindicatedseveraldifferenttransducerswouldberequiredtobeusedandtheinnerradiusexaminationresultswouldbequestionableatbestduetothesizeandconfigurationofthenozzles.Themodelingalsoindicatedbeamspreadandmodeconversionatthenotchesandneighboringsurfaceswouldseriouslyreducethesignaltonoiseratios,causingconfusingspurioussignals.Baseduponthecomputermodelingresults,EPRINDECenterpersonnelwereutilizedtoperformactualhandsoninnerradiusexaminationevaluationonthemockups.Anareawasselectedontwomockupsofthenozzle,suitabletransducersandwedgeswereselectedtoperformtheexamination.Theinspectionwastobeperformedfromthebossregionofthenozzlebecauseinspectionfromtheshellsurfaceprovedtobegreatlyaffectedbyattenuationandscatteringfromthenozzle-to-shellweldmaterial.Avarietyofinspectionfrequencieswereattemptedofwhichnoneprovidedwhatwouldbeconsideredsuccessfulforthedetectionofthenotchesonthesenozzles.Itshouldbenotedthatthetransducerpositionfordetectingtheselectednotchwasnearlyoptimum.Sincetheattemptsmadewereunsuccessfulitwasdecidedtoincreasethedepthofthenotchfrom10%to30%.Thisincreaseofthenotchisgreaterthancodeallowable.Attemptsweremadeonthegreaternotchdepthbutdetectionwasnotachievable.V.AlternateExaminations:None,RG&Ewillcontinuetoevaluatenewemerginginspectiontechnologyastheybecomeavailable.TheCoderequiredleakagetestswithassociatedVT-2examinationsshallbeperformed.

I8Nk//FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page17of48RELIEFREQUESTNO.6(Con't)VI.JustificationforGrantinofRelief:IthasbeenproventhatanacceptableCodeexaminationoftheRHEnozzleinnerradiusregionisnotpossibleutilizingcurrenttechnology.Itdemonstratesthatsignalsfromdifferentdepthnotcheslocatedinthemostoptimumpositionofthemock-upcouldnotbedifferentiatedfromnoiseandgeometricreflectorswithouttheaidoffingerdampingontheIDsurface.Theevaluationshavealsoshownthatthelimitationinthebossarea,inthe0and180degreeposition,alongwiththetransitiontotheseareas,limitsthesizeoftransducersthatcanbeemployedandwherethetransducerscanbeplaced.VII.ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

References:

EPRIReportTitle"EvaluationofUltrasonicExaminationTechnologyforInspectionofRegenerativeHeatExchangerNozzlesattheRochesterGas&Electric,GinnaNuclearPlant"Dated17April1996byDouglasE.MacDonaldandE.KimKietzman.AEAReactorServicesReportTitle"ReportontheMathematicalModelingofTwoNozzleSpecimensforRochesterGasEcElectricCorporation"Dated16November1992byP.D.BirchallandL.N.J.Poulter.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page18of48RELIEFREQUESTNO.7(WaspreviouslyapprovedasReliefRequestNo.34forThirdInterval)COMPONENTSUPPORTINTEGRALATTACHMENTEXAMINATIONLIMITATIONSSstem/ComonentsforwhichReliefisReuested:ThisReliefRequestisrequestedforthree(3)supports.InspectionsofthesesupportsisaddressedbyClass2,CategoryC-C,ItemNumberC3.20,IdentifiedComponentSupportIntegralAttachmentsSurfaceExaminations.~BtlCoverageObtained~S<temMSU-33MSU-34Penetration14050%50%82%Mainsteam(MS)Mainsteam(MS)ResidualHeatRemoval(RHR)II.CodeReuirement:ASMESectionXICode,1995Edition,1996Addenda,requiresessentially100%oftheweldlengthtoobtaincodecoverage.ASMESectionXICodeCaseN-460statesthatiftheentireexaminationvolumeorareacannotbeexaminedduetointerferencebyanothercomponentorpartgeometry,areductionincoverageisacceptableprovidedthatthecoverage(thelackof)islessthan10%.III.CodeReuirementfromwhichReliefisReuested:Reliefisrequestedfromexamining100%ofthelengthforthese3supports.Examining100%oftheweldlengthwouldbeimpractical,becausethesupportwouldhavetoberedesignedorreplacedtoenableinspection.Theamountofcoverageisestimatedat50%forMSU-33,50%forMSU-34,and82%forPenetration140.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page19of48RELIEFREQUESTNO.7(Con't)IV.BasisforRelief:Reliefisrequestedpursuanttotheprovisionsof10CFR50.55a(g)(5)(iii),therequiredexaminationcoveragefortheidentifieditemsareimpracticalandwouldrequireredesigntoallowexaminationortobereplacedtoenableinspection.R.E.GinnaNuclearPowerPlantwasdesignedandconstructedtotheB31.1,1955editionconstructioncode.Thiscodedidnotcontainrequirementstoensurethatitemsbeaccessibleforfutureexaminations.TheabovenotedintegralattachmentsassociatedwiththecomponentsupportsorpenetrationanchorsupportswereinstalledutilizingthisconstructioncodewhichdidnotprovideforaccessibilityforfutureISINDE.Duetothelimiteddesignaccessibility,ISIexaminationscannotbeperformedontheinaccessiblewelds.ThetwoMainSteamsupports(MSU-33andMSU-34)aresimilarindesigninthathaveacomplexgussetassemblythatisweldedtotheprocesspiping(integralattachment)andweldedtothebaseplate,whichissecuredtotheconcretefloor.Duetothesmallsizeofgussets,accessislimitedforboththesurfaceexaminationandsurfacepreparationoftheintegralattachmentweldslocatedundertheprocesspiping,Theachievableaccesspercentagehasbeenidentifiedabovewithinthisreliefrequest.Theidentifiedcomponentsupports(includingtheintegralattachments)areperiodicallyvisuallyexamined(VT-3).ASMESectionXIperiodicleakageexaminationsareperformedaswellasOperatorwalkdownsasspecifiedbyPlantOperatingProcedures.Theseoperatorwalkdowns,periodicsystemleakageexaminationsandcomponentsupportvisualexaminationsprovideadditionalassurancesinmaintainingplantsafety.V.AlternateExaminations:R.E.GinnaNuclearPowerPlantproposesthatthesurfaceexaminationcoverageidentifiedabovebeacceptableinmeetingCodeRequirementsandisnotconduciveinobtainingtherequirementsspecifiedwithinCodeCaseN-460.

FOURTHINTERVALISIRELIE<FREQUESTSATTACHMENT1Revision0Page20of48RELIEFREQUESTNO.7(Con't)VI.JustificationfortheGrantinofRelief:R.E.GinnaNuclearPowerPlantwasdesignedandconstructedtotheB31.1,1955editionconstructioncode.ThiscodedidnotcontainrequirementstoensurethatitemsbemadeaccessibleforfutureNDEexaminations.Duetotheoriginallimiteddesignaccessibility,ISIexaminationcoveragecannotbeobtainedtotheextentrequiredbythecurrentASMECode.ASMESectionXIleakageexaminationsareperformedaswellasOperatorwalkdownsasspecifiedbyPlantOperatingProcedures.Theseoperatorwalkdowns,periodicsystemleakageexaminationsandcomponentsupportvisualexaminationsprovideadditionalassurancesinmaintainingplantsafety.TheidentifiedexaminationcoveragefortheseitemsshouldbeacceptableinfulfillingASMESectionXIcoveragerequirements.VII.ImlementationSchedule:ImplementationshallbeperformedfortheFourthInterval.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page21of48RELIEFREQUE~STNO.8(WaspreviouslyapprovedasReliefRequestNo.36forThirdInterval)REACTORPRESSUREVESSELNOZZLE-to-SAFEENDBUTTWELDSURFACEEXAMINATIONLIMITATIONSSstem/ComonentsforwhichReliefisReuested:ThisReliefRequestisrequestedforsix(6)ReactorPressureVesselNozzle-to-SafeEndButtWelds.InspectionoftheseweldsisaddressedunderClass1,CategoryB-F,ItemNumberB5.10,Nozzle-to-SafeEndWeldSurfaceExaminationsasidentifiedbelow.WeldID¹ISISumma¹CoveraeObtainedPIFW-IIPL-FW-VPIFW-IVPL-FW-VIIAC-1003-1AC-1002-100210000240000270000300000330000360062%75%68.5%72%0%(*)0%(*)Note:(*)=weldsembeddedinconcrete.CodeReuirement:ASMESectionXICode,1995Edition,1996Addenda,CategoryB-F,ItemNumberB5.10,volumetricandsurfaceexaminationsshallbeperformedwithessentially100%oftheweldlengthtoobtaincodecoverage.ASMESectionXICodeCaseN-460statesthatiftheentireexaminationvolumeorareacannotbeexaminedduetointerferencebyanothercomponentorpartgeometry,areductionincoverageisacceptableprovidedthatthe(lackof)coverageislessthan10%.PreviousCodesutilizeddidnotincludethis90%coveragerequirementandexaminationswereperformedtotheextentobtainable.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page22of48RELIEFREQUESTNO.8(Cont'd)III.CodeReuirementfromwhichReliefisReuested:Reliefisrequestedfromthesurfaceexaminationrequirementsforthesix(6)identifiedwelds.SurfaceExaminationofthefirstfour(4)weldsislimitedduetoOriginalConstructionCodeinterferencesofthefloorandwallinthe"Sandbox"wheretheseweldsarelocated.The"Sandboxes"wouldhavetoberedesignedtoenabletheweldstobesurfaceexaminedtoobtainCoderequiredcoverage.(VolumetricexaminationoftheseweldsisperformedfromtheinsideoftheVesselandisnotapartofthisReliefRequest.)SurfaceExaminationofthelasttwoweldsisimpractical.TheconcretesurroundingtheReactorPressureVesselhasembeddedthesewelds.TheconcretewallaroundtheReactorPressureVesselwouldhavetoberedesignedorreplacedtoenablethetwo(2)weldstobeinspectedwithasurfaceexamination.(VolumetricexaminationoftheseweldsisperformedfromtheinsideoftheVesselandisnotapartofthisReliefRequest.)IV.BasisforRelief:Reliefisrequestedpursuanttotheprovisionsof10CFR50.55a(g)(5)(iii),therequiredexaminationcoveragefortheidentifiedweldsisimpracticalandwouldrequireredesignorreplacementtoobtainCoderequiredsurfaceexaminationcoverage.R.E.GinnaNuclearPowerPlantwasdesignedandconstructedtotheB31.1,1955editionConstructionCode.Thiscodedidnotcontainrequirementstoensurethatitemsbeaccessibleforfutureexaminations.Theabovenotedpipingweldswereinstalledutilizingthisconstructioncode,whichdidnotprovideforaccessibilityforfutureISINDE.Duetothelimiteddesignaccessibility,ISIsurfaceexaminationcoverageisbelowCodepercentagerequirementsasidentifiedwithinthisReliefRequest.Thefirstfour(4)weldsofthisReliefRequestarelocatedina"Sandbox"configuration.Withinthe"Sandbox",theweldsareagainstthefloorandonewall.Theangledwallisjoinedtothefloorandisagainsttheweld.ThesurfaceexaminationoftheseweldsislimitedduetoOriginalConstructionCodeinterferencesofthefloorandwallofthe"Sandbox".The"Sandboxes"wouldhavetoberedesignedtoenabletheweldstobeinspectedtoobtainCoderequiredcoverageforthesurfaceexaminations.Thelasttwo(2)weldsofthisReliefRequestareembeddedinconcrete.ThisconcretestructureisthewallthatsurroundstheReactorPressureVessel~

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page23of48IV(Con't)RELIEFREQUESTNO.8(Cont<d)ASMESectionXIClass1systemleakageexaminationsareperformed.Theseleakageexaminationsdemonstratepressureboundaryintegrityandprovideadditionalassurancesinmaintainingplantsafety.V.AlternateExaminations:R.E.GinnaNuclearPowerPlantproposesthatthesurfaceexaminationcoverageidentifiedforthefirstfour(4)weldsabovebeacceptableinfulfillingtheCoderequiredexaminationcoverage.Theactualphysicalconfigurationofthe"Sandboxes"isnotconduciveinobtainingtherequirementsspecifiedwithinCodeCaseN-460foracceptablecoverage.VolumetricexaminationoftheseweldsisperformedfromtheinsideoftheVessel,andwillbeperformedduringthe2009outage.Forthelasttwo(2)welds,theCodesurfaceexaminationrequirementsareimpracticalandcannotbeexaminedduetothembeingembeddedinconcrete.VolumetricexaminationoftheseweldsisperformedfromtheinsideoftheVessel,andwillbeperformedduringthe2009Outage.VI.JustificationfortheGrantinofRelief:R,E.GinnaNuclearPowerPlantwasdesignedandconstructedtotheB31.1,1955editionConstructionCode.ThiscodedidnotcontainrequirementstoensurethatitemsbemadeaccessibleforfutureNDEexaminations.Duetotheoriginallimiteddesignaccessibilityorlackofdesignaccessibility,ISIsurfaceexaminationcoveragecannotbeobtainedtotheextentrequiredbytheASMECode.ASMESectionXIClass1systemleakageexaminationsareperformed.Theseleakageexaminationsdemonstratepressureboundaryintegrityandprovideadditionalassurancesinmaintainingplantsafety.TheidentifiedexaminationcoveragefortheseitemsshouldbeacceptableinfulfillingASMESectionXIcoveragerequirements.

g/svo//FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page24of48RELIEFREQUE<STNO.8(Cont'd)VII.ImlementationSchedule:ThesurfaceexaminationswillbeperformedduringtheendoftheFourthIntervalonthefirstfour(4)accessiblewelds.Forthetwo(2)weldsembeddedinconcrete,surfaceexaminationscannotbeperformed.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page25of48RELIEFREQUESTNO.9(WasReliefRequestNo,37forThirdInterval)CONTAINMENTINSPECTIONSEALSANDGASKETSSstem/ComonentsforwhichReliefisReuested:SealsandgasketsofClassMCpressureretainingcomponentsandmetalliclinersofClassCCcomponents,ExaminationCategoryE-D,ItemNumbersE5.10andE5.20ofIWE-2500,TableIWE-2500-1,ASMESectionXI,1992Edition,1992Addenda.Severalhundredsealsandgasketsareaffectedbythisreliefrequest.II.CodeReuirement:ASMESectionXICode,1992Edition,1992Addenda,IWE-2500,TableIWE-2500-1,CategoryE-D,ItemNumbersE5.10andE5.20requiressealsandgasketsonairlocks,hatches,andotherdevicestobevisuallyexamined,VT-3,onceeachintervaltoassurecontainmentleak-tightintegrity.III.CodeReuirementfromwhichReliefisReuested:ReliefisrequestedfromperformingtheCode-requiredvisualexamination,VT-3,ontheaboveidentifiedmetalcontainmentsealsandgaskets,IV.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperformingcontainmentexaminations.Thepenetrationsdiscussedbelowcontainsealsandgaskets.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page26of48RELIEFREQUESTNO.9(Cont'd)ElectricalPenetrationsElectricalpenetrationsuseaheaderplateattachedtoacontainmentpenetrationnozzleflangewithredundant0-ringsbetweentheheaderplateandflangeface.Modulesthroughwhichelectricalconductorspassareinstalledintheheaderplate.Onetype,manufacturedbyAmphenol,usessealsandgasketstoassureleaktightintegrity.Asecondtype,manufacturedbyConax,usesasetofcompressionfittings.ReplacementmodulesfortheAmphenolpenetrationsuseacombinationof0-ringsandcompressionfittings.Eachpenetrationispressurizedwithdrynitrogentomaintainandmonitorintegrityandtopreventtheintrusionofmoistureintothepenetration.Thesesealsandgasketscannotbeinspectedwithoutdisassemblyofthepenetrationtogainaccesstothesealsandgaskets.ContainmentPersonnelandEquipmentHatchesThePersonnelandEquipmentHatchesutilizeaninnerandouterdoorwithgasketsurfacestoensurealeaktightintegrity.Thesehatchesalsocontainothergasketsandsealssuchasthehandwheelshaftseals,electricalpenetrations,blankflanges,andequalizingpressureconnectionswhichrequiredisassemblytogainaccesstothegasketsandseals.Sealandgasketjointsreceivea10CFR50AppendixJtest.Asnotedin10CFR50AppendixJ,thepurposeofTypeBtestsistomeasureleakageofcontainmentorpenetrationswhosedesignincorporatesresilientseals,gaskets,sealantcompounds,andelectricalpenetrationsfittedwithflexiblemetalsealassemblies.Examinationofsealsandgasketsrequirethejoints,whichareprovenadequatethroughAppendixJtesting,bedisassembled.Forelectricalpenetrations,thiswouldinvolveapre-maintenanceAppendixJtest,de-terminationofcablesatelectricalpenetrationsifenoughcableslackisnotavailable,disassemblyofthejoint,removalandexaminationofthesealsandgaskets,reassemblyofthejoint,re-terminationofthecablesifnecessary,postmaintenancetestingofthecables,andapostmaintenanceAppendixJtestofthepenetration.TheworkrequiredfortheContainmentHatcheswouldbesimilarexceptforthede-termination,re-termination,andtestingofcables.Thisimposestheriskthatequipmentcouldbedamaged.The1992Edition,1993Addenda,ofSectionXIrecognizesthatdisassemblyofjointstoperformtheseexaminationsisnotwarranted.Note1inExaminationCategoryE-Dwasmodifiedinthe1995EditionofSectionXItostatethatsealorgasketconnectionsneednotbedisassembledsolelyforperformanceofexaminations.However,withoutdisassembly,mostofthesurfaceofthesealsandgasketswouldbeinaccessible.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page27of48IV(Con't)RELIEFREQUESTNO.9(Cont'd)Forthosepenetrationsthatareroutinelydisassembled,aTypeBtestisrequireduponfinalassemblyandpriortostart-up.SincetheTypeBtestwillassuretheleaktightintegrityofprimarycontainment,theperformanceofthevisualexaminationwouldnotprovideanincreaseinthelevelofsafetyorquality.SealsandgasketsarenotpartofthecontainmentpressureboundaryundercurrentCoderules(NE-1220(b)).Theairlocksandhatchescontainingthesematerialsaretestedinaccordancewith10CFR50,AppendixJ.IfincreasedleakageisidentifiedduringtheseAppendixJtests,thecauseofleakagewouldbeinvestigated.Ifincreasedleakagewereduetodegradationofthesealorgasketmaterial,correctivemeasureswouldbeappliedandthecomponentretested.RepairorreplacementofsealsandgasketsisnotsubjecttoCode(1992Edition,1992Addenda)rulesinaccordancewithParagraphIWA-4111(b)(5)ofASMESectionXI.ThevisualexaminationofsealsandgasketsinaccordancewithIWE-2500,TableIWE-2500-1isaburdenwithoutanycompensatingincreaseinthelevelofsafetyorquality.Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(ii).Compliancewiththeoriginalrequirementsofthissectionwouldresultinhardshiporunusualdifficultywithoutacompensatingincreaseinthelevelofqualityandsafety.Testingthesealandgasketjointsinaccordancewith10CFR50,AppendixJwillprovideadequateassuranceoftheleak-tightintegrityofthesealsandgaskets.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page28of48RELIEFREQUESTNO.9(Cont'd)AlternateExaminations:Theleaktestingofsealandgasketjointswillbeinaccordancewith10CFR50,AppendixJ.Noadditionalalternativeexaminationstothevisualexamination,VT-3,ofthesealsandgasketswillbeperformed.JustificationfortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-1submittedbyDavis-BesseasoneoftheEPRI"ContainmentInspectionProgramGuide"PilotPlantReliefRequests.ThisReliefRequestwillminimizeGinnaoperatingandmaintenancecostwithoutdecreasingthelevelofqualityandsafety.ImlementationSchedule:ReliefisrequestedforthefirstinspectionintervalfortheIWEContainmentInspectionProgram(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspectionsoftheGinnaInserviceInspectionProgram.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page29of48RELIEFREQUESTNO.10(WasReliefRequestNo.38forThirdInterval)CONTAINMENTINSPECTIONSUCCESSIVEEXAMINATIONSAFTERREPAIRSstem/ComonentsforwhichReliefisReuested:AllClassMC,ParagraphsIWE-2420(b)andIWE-2420(c)successiveexaminationrequirementsforcomponentsfoundacceptableforcontinuedservice.CodeReuirement:ParagraphsIWE-2420(b)andIWE-2420(c)ofthe1992Edition,1992AddendaofASMESectionXIrequiresthatwhencomponentexaminationresultsrequireevaluationofflaws,evaluationofareasofdegradation,orrepairsinaccordancewithArticleIWE-3000,andthecomponentisfoundtobeacceptableforcontinuedservice,theareascontainingsuchflaws,degradation,orrepairsshallbereexaminedduringthenextinspectionperiodlistedinthescheduleoftheinspectionprogramofParagraphIWE-2411orParagraphIWE-2412,inaccordancewithTableIWE-2500-1,ExaminationCategoryE-C.CodeReuirementfromwhichReliefisReuested:ReliefisrequestedfromtherequirementsofASMESectionXICode,1992Edition,1992Addenda,ParagraphsIWE-2420(b)andIWE-2420(c)toperformsuccessiveexaminationonrepairs.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperformingcontainmentexaminations.ThepurposeofarepairistorestorethecomponenttoanacceptableconditionforcontinuedserviceinaccordancewiththeacceptancestandardsofArticleIWE-3000.ParagraphIWA-4150requirestheownertoconductanevaluationofthesuitabilityoftherepairincludingconsiderationofthecauseoffailure.

/r~o/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page30of48IV(Con't)RELIEFREQUESTNO.10(Cont'd)Iftherepairhasrestoredthecomponenttoanacceptablecondition,itisoverlyconservativetorequiresuccessiveexaminations.OtherparagraphsoftheASMECoderecognizethisrequirementasoverlyconservative.Iftherepairwasnotsuitable,thentherepairdoesnotmeetcoderequirementsandthecomponentisnotacceptableforcontinuedservice.NeitherParagraphIWB-2420(b),ParagraphIWC-2420(b),norParagraphIWD-2420(b)requiresarepairtobesubjecttosuccessiveexaminationrequirements.Furthermore,iftherepairareaissubjecttoaccelerateddegradation,itwouldstillrequireaugmentedexaminationinaccordancewithTableIWE-2500-1,ExaminationCategoryE-C.ThesuccessiveexaminationofrepairsinaccordancewithParagraphsIWE-2420(b)andIWE-2420(c)constitutesaburdenwithoutacompensatingincreaseinqualityorsafety.Intheirresolutiontopubliccomment03.3,theNRCstatedwithinSECY96-080datedApril17,1996:"ThepurposeofIWE-2420(b)istomanagecomponentsfoundtobeacceptableforcontinuedservice(meaningnorepairorreplacementatthistime)asanExaminationCategoryE-Ccomponent.Ifthecomponenthadbeenrepairedorreplaced,thenthemorefrequentexaminationwouldnotbeneeded."Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(ii).Compliancewiththeoriginalrequirementsofthissectionwouldresultinhardshiporunusualdifficultywithoutacompensatingincreaseinthelevelofqualityandsafety.Therequirementtoperformsuccessiveexaminationsfollowingrepairshasbeenremovedinthe1997AddendaofASMESectionXI.ThisaddendahasbeenapprovedbytheASMEMainCommitteeandhasbeenpublished.V.AlternateExaminations:SuccessiveexaminationsinaccordancewithParagraphsIWE-2420(b)andIWE-2420(c)arenotrequiredforrepairsmadeinaccordancewithArticleIWA-4000.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page31of48RELIEFREQUE~STNO.10(Cont'd)JustificationfortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-6submittedbyDavis-BesseasoneoftheEPRI"ContainmentInspectionProgramGuide"PilotPlantReliefRequests.ThisReliefRequestwillminimizeGinnaoperatingandmaintenancecostwithoutdecreasingthelevelofqualityandsafety.ImlementationSchedule:ReliefisrequestedforthefirstinspectionintervalfortheIWEContainmentInspectionProgram(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspectionsoftheGinnaInserviceInspectionProgram.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page32of48RELIEFREQUESTNO.11(WasReliefRequestNo.39forThirdInterval)CONTAINMENTINSPECTIONBOLTTORQUEORTENSIONTESTINGSstem/ComonentsforwhichReliefisReuested:ClassMCpressureretainingbolting.CodeReuirement:ASMESectionXI,1992Editionwiththe1992Addenda,TableIWE-2500-1,ExaminationCategoryE-G,PressureRetainingBolting,ItemE8.20.Bolttorqueortensiontestingisrequiredonboltedconnectionsthathavenotbeendisassembledandreassembledduringtheinspectioninterval.CodeReuirementfromwhichReliefisReuested:ReliefisrequestedfromASMESectionXI1992Editionwiththe1992AddendaTableIWE-2500-1ExaminationCategoryE-G,PressureRetainingBolting,ItemE8.20.Bolttorqueortensiontestingisrequiredonboltedconnectionsthathavenotbeendisassembledandreassembledduringtheinspectioninterval.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperformingcontainmentexaminations.Bolttorqueortensiontestingisrequiredonboltedconnectionsthathavenotbeendisassembledandreassembledduringtheinspectioninterval.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page33of48RELIEFREQUE<STNO.11(Cont'd)IV(Con't)Determinationofthetorqueortensionvaluewouldrequirethattheboltingbeun-torquedandthenre-torquedorre-tensioned.TheperformanceoftheTypeBtestitselfprovesthatthebolttorqueortensionremainsadequatetoprovidealeakratethatiswithinacceptablelimits.Thetorqueortensionvalueofboltingonlybecomesanissueiftheleakrateisexcessive.Onceaboltistorquedortensioned,itisnotsubjecttodynamicloadingthatcouldcauseittoexperiencesignificantchange.VerificationoftorqueortensionvaluesonboltedjointsthatareprovenadequatethroughAppendixJtestingandvisualinspectionisadequatetodemonstratethatdesignfunctionismet.TorqueortensiontestingisnotrequiredonanyotherASMESectionXI;Class1,2,or3boltedconnectionsortheirsupportsaspartoftheInserviceinspectionprogram.Also,allpenetrationsatR.E.GinnaNuclearPowerPlantareseatedwithpressure(notunseated).Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(ii).Compliancewiththeoriginalrequirementsofthissectionwouldresultinhardshiporunusualdifficultywithoutacompensatingincreaseinthelevelofqualityandsafety.AlternateExaminations:ThefollowingexaminationsandtestsrequiredbySubsectionIWEensurethestructuralintegrityandtheleak-tightnessofClassMCpressureretainingbolting,and,therefore,noadditionalalternativeexaminationsareproposed:

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page34of48RELIEFREQUESTNO.11(Cont'd)(1)ExposedsurfacesofboltedconnectionsshallbevisuallyexaminedinaccordancewithrequirementsofTableIWE-2500-1,ExaminationCategoryE-G,PressureRetainingBolting,ItemNo.E8.10,and(2)BoltedconnectionsshallmeetthepressuretestrequirementsofTableIWE-2500-1,ExaminationCategoryE-P,AllPressureRetainingComponents,ItemE9.40,and(3)Ageneralvisualexaminationoftheentirecontainmentonceeachinspectionperiodshallbeconductedinaccordancewith10CFR50.55a(b)(2)(x)(E).JustificationfortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-7submittedbyDavis-BesseasoneoftheEPRI"ContainmentInspectionProgramGuide"PilotPlantReliefRequests.ThisReliefRequestwillminimizeGinnaoperatingandmaintenancecostwithoutdecreasingthelevelofqualityandsafety.ImlementationSchedule:ReliefisrequestedforthefirstinspectionintervalfortheIWEContainmentInspectionProgram(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspectionsoftheGinnaInserviceInspectionProgram.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page35of48RELIEFREQUESTNO.12(WasReliefRequestNo.40forThirdInterval)CONTAINMENTINSPECTIONVT-2AFTERREPAIR,REPLACEMENTORMODIFICATIONSstem/ComonentsforwhichReliefisReuested:Allcomponentssubjecttotherulesandrequirementsforrepair,replacementormodificationofClassMC,IWE-5000systempressuretestingvisualexaminationinaccordancewiththe1992Edition,1992AddendaofASMESectionXI.CodeReuirement:ParagraphIWE-5240ofthe1992Edition,1992AddendaofASMESectionXIrequiresthattherequirementsofParagraphIWA-5240forvisualexamination,VT-2,areapplicablefollowingrepair,replacementormodification.CodeReuirementfromwhichReliefisReuested:ReliefisrequestedfromperformingtheVT-2visualexaminationinconnectionwithsystempressuretestingfollowingrepair,replacementormodificationunderArticleIWE-5000.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperformingcontainmentexaminations.ParagraphIWE-5210statesthatexceptasnotedwithinParagraphIWE-5240,therequirementsofArticleIWA-5000arenotapplicabletoClassMCorClassCCcomponents,

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page36of48IV(Con't)RELIEFREQUESTNO.12(Cont'd)ParagraphIWE-5240statesthattherequirementsofParagraphIWA-5240(correctedfromIWA-5246toIWA-5240inthe1993Addenda)forvisualexaminationsareapplicable.ParagraphIWA-5240identifiesa"VT-2"visualexamination.VT-2examinationsareconductedtodetectevidenceofleakagefrompressure-retainingcomponents,withorwithoutleakagecollectionsystems,asrequiredduringtheconductofasystempressuretest.Inaddition,personnelperformingVT-2examinationsarerequiredtobequalifiedinaccordancewithSubarticleIWA-2300ofASMESectionXI.Forrepairs,replacementsormodificationsthatareperformedunderASMESectionXICode,applicableConstructionCode(orInstallationCode)non-destructiveexaminations(NDE)areperformedandmustmeettheacceptancecriteriaoftheConstruction/InstallationCode.InadditiontotheConstructionCodeNDE,applicableASMESectionXINDEpre-serviceNDEarealsoperformed.TheseConstructionCodeandSectionXIpre-serviceNDErequirementsprovideadditionalassurancesthattherepairs,replacementsormodificationsaresoundandleak-tight.TableIWE-2500-1,ExaminationCategoryE-P,identifiestheexaminationmethodof10CFR50,AppendixJanddoesnotspecificallyidentifyaVT-2visualexamination.10CFR50,AppendixJprovidesrequirementsfortestingaswellasacceptableleakagecriteria.ThesetestsareperformedbyAppendixJ"Test"personnelandutilizecalibratedequipmenttodetermineacceptability.Additionally,10CFR50.55a(b)(2)(x)(E)requiresageneralvisualexaminationofthecontainmenteachperiodthatwouldidentifyanystructuraldegradationthatmaycontributetoleakage.A"VT-2"visualexaminationwillnotprovideadditionalassuranceofsafetybeyondthatofcurrentAppendixJpractices.Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(i).Theproposedalternative(pressuretestinginaccordancewith10CFR50,AppendixJ)willprovideanacceptablelevelofqualityandsafety.ThereferencetoparagraphIWA-5240hasbeenremovedinthe1997AddendaofASMESectionXI.ThisaddendahasbeenapprovedbytheASMEMainCommitteeandshouldbepublishedin1998.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page37of48RELIEFREQUESTNO.12(Cont'd)AlternateExaminations:Testingshallbeconductedinaccordancewith10CFR50,AppendixJ,inlieuofParagraphIWE-5240ofASMESectionXI,aswellasperforminganIWEdetailedvisualexamination(VT-1)oftherequiredorreplacedarea.JustificationfortheGrantinofRelief:Forrepairs,replacementsormodificationsthatareperformedunderASMESectionXICode,applicableConstructionCode(orInstallationCode)non-destructiveexaminations(NDE)areperformedandmustmeettheacceptancecriteriaoftheConstruction/InstallationCode.InadditiontotheConstructionCodeNDE,applicableASMESectionXINDEpre-serviceNDEarealsoperformed.TheseConstructionCodeandSectionXIpre-serviceNDErequirementsprovideadditionalassurancesthattherepairs,replacementsormodificationsaresoundandleak-tight.ThisReliefRequestwillminimizeGinnaoperatingandmaintenancecostwithoutdecreasingthelevelofqualityandsafety.ImlementationSchedule:ReliefisrequestedforthefirstinspectionintervalfortheIWEContainmentInspectionProgram(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspectionsoftheGinnaInserviceInspectionProgram.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page38of48RELIEFREQUESTNO.13(WasReliefRequestNo.41forThirdInterval)CONTAINMENTINSPECTIONREMOTEVTOFCLASSCCSstem/ComonentsforwhichReliefisReuested:AllcomponentssubjecttotherulesandrequirementsforInserviceInspectionofClassCCConcreteComponents,ExaminationCategoryL-A,Concrete,ItemL.1.11asapplicabletoIWL-2310,VisualExaminationandPersonnelQualificationandIWA-2210,VisualExaminations.CodeReuirement:ASMESectionXI,1992Edition,1992Addenda,IWL-2310,VisualExaminationandPersonnelQualificationandIWA-2210,VisualExaminationsrequiresspecificminimumilluminationandmaximumdirectexaminationdistanceforallconcretesurfaces.CodeReuirementfromwhichReliefisReuested:ReliefisrequestedfromParagraphIWA-2210,VisualExaminationRequirementsforminimumilluminationandmaximumdirectexaminationdistanceofClassCCcomponentsunderParagraphIWI2310.

FOURTHINTERVALISIRELIEFREQUE<STSATTACHMENT1Revision0Page39of48RELIEFREQUESTNO.13(Cont'd)BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperformingcontainmentexaminations.InadditiontotherequirementsofSubsectionIWL,theRulemakingalsoimposestherequirementsofSubsectionIWAofthe1992Edition,1992Addendum,ofASMESectionXIforminimumilluminationandmaximumdirectexaminationdistanceofClassCCcomponents,specificallyfortheexaminationofconcreteunderParagraphIWL-2510.WhenremotelyperformingthevisualexaminationsrequiredbySubsectionIWLParagraphIWL-2510,themaximumdirectexaminationdistancespecifiedinTableIWA-2210-1maybeextended,andtheminimumilluminationrequirementsspecifiedinTableIWA-2210-1maybedecreased.IWA-2210allowsforremoteexaminationaslongastheremoteexaminationprocedureisdemonstratedtoresolvetheselectedtestchartcharacters.TheRegisteredProfessionalEngineer(RPE)willidentifyminimumsizeofindicationsofinterest.Forremotevisualexamination,theprocedureandequipmenttobeusedwillbedemonstratedcapableofresolvingtheseminimumindicationstothesatisfactionoftheRPEandtheAuthorizedNuclearInsuranceInspector(ANII),asallowedinIWA-2240,"AlternativeExaminations."TherecordofdemonstrationwillbeavailabletoRegulatoryAuthorities.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page40of48IV(Con't)RELIEFREQUE~STNO.13(Cont'd)Accessibilitytohigherportionsofthedomeandthecontainmentbuildingitselfmakeitahardshiptoobtainthemaximumdirectexaminationdistanceandminimumilluminationrequirements.Theinstallationofextensivetemporaryscaffoldsystemsoraclimbingscaffoldsystemtoaccesstheseportionsofthecontainmentwouldbenecessary.Thesescaffoldswouldprovidelimitedaccessduetocontainmentgeometryrestrictionsaswellasstructuralandequipmentinterferences.TheinstallationandremovalofthesescaffoldswouldincreasebothworkerradiationexposureandpersonnelsafetyinordertomeetParagraphIWA-2210requirements.TheNRCstaffreceivedsevencommentsthatwereconsolidatedintoPublicComment¹2.3inPartIIIofAttachment6AtoSECY-96-080.TheStaffresponsetotheseconcernsisasfollows:"CommentsreceivedfromASMEmembersonthecontainmentcommitteesindicatethatthenewer,morestringentrequirementsofIWA-2210werenotintendedtobeusedfortheexaminationofcontainmentsandwereinadvertentlyincludedinSubsectionIWL.TheNRCagreesthatremoteexaminationsaretheonlypracticalmethodforinspectingmuchofthecontainmentsurfacearea.50.55a(b)(2)(x)(B)hasbeenaddedtothefinalrulewhichcontainsalternativelightingandresolutionrequirementswhichmaybeusedinlieuoftherequirementscontainedinIWA-2210-1."However,asspecifiedwithin10CFR50.55a(b)(2)(x)(B)ofthefinalrule,thisalternativeappliesonlytoSubsectionIWE,andnottoSubsectionIWL.Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(ii).Compliancewiththeoriginalrequirementsofthissectionwouldresultinhardshiporunusualdifficultywithoutacompensatingincreaseinthelevelofqualityandsafety.V.AlternateExaminations:WhenperformingremotelythevisualexaminationsrequiredbySubsectionIWL,ParagraphIWL-2510,themaximumdirectexaminationdistancespecifiedinTableIWA-2210-1maybeextended,andtheminimumilluminationrequirementsspecifiedinTableIWA-2210-1maybedecreasedprovidedthattheconditionsorindicationsforwhichthevisualexaminationisperformedcanbedetectedatthechosendistanceandillumination.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page41of48RELIEFREQUESTNO.13(Cont'd)JustificationfortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestL-1submittedbyCalvertCliffsasoneoftheEPRI"ContainmentInspectionProgramGuide"PilotPlantReliefRequests.ReliefRequestL-1(forCalvertCliffs)wassubsequentlyapprovedbytheNRC.RefertoaletterfromtheNRC(S.Bajwa)toBaltimoreGasandElectric(C.Cruse),datedNovember16,1998(DocketNo.50-317/318).ThisReliefRequestwillminimizeGinnaoperatingandmaintenancecostwithoutdecreasingthelevelofqualityandsafety.ImlementationSchedule:ReliefisrequestedforthefirstinspectionintervalfortheIWLContainmentInspectionProgram(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspectionsoftheGinnaInserviceInspectionProgram.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revtsion0Page42of48RELIEFREQUESTNO.14(WasReliefRequestNo.42forThirdInterval)REACTORPRESSUREVESSEL(RPV)WELDEXAMINATIONLIMITATIONSSstem/ComonentsforwhichReliefisReuested:ThisReliefRequestpertainstoeight(8)ReactorPressureVesselweldsorInnerRadiusVolumetricexaminations.VolumetricexaminationlimitationsoftheseeightweldsareidentifiedinAttachmentNumber1.CodeReuirement:WhenperformingVolumetricexaminations,ASMESectionXICode,1995Edition,1996Addenda,requiresessentially100%oftheweldlengthorareatoobtaincoverage.ASMESectionXICodeCaseN-460statesthatiftheentireexaminationvolumeorareacannotbeexaminedduetointerferencebyanothercomponentorpartgeometry,areductionincoverageisacceptableprovidedthatthecoverage(thelackof)islessthan10%.ReuirementfromwhichReliefisReuested:Reliefisrequestedfromexamining100%oftheweldlengthorareasfortheseeight(8)identifieditems.Examining100%oftheweldlengthorareaswouldbeimpracticalduetooriginaldesigninterference.AttachmentNumber1identifiesvolumetricexaminationachievablecoverageandassociatedlimitations.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page43of48RELIEFREQUE~STNO.14(Cont'd)BasisforRelief:Reliefisrequestedpursuanttotheprovisionsof10CFR50.55a(g)(5)(iii),therequiredexaminationcoveragefortheidentifieditemsareimpracticalandwouldrequireredesigntoallowexaminationortobereplacedtoenableinspection.TheReactorPressureVessel(RPV)wasdesignedandconstructedtoASMESectionIII,1965Edition.Thiscodedidnotcontainrequirementstoensurethatitemsbeaccessibleforfutureexaminations.Theeight(8)itemsidentifiedwithinAttachmentNumber1wasinstalledutilizingthisconstructioncodewhichdidnotprovideforaccessibilityforfutureISINDE:TheClass1ReactorPressureVesselispartoftheASMESectionXIVT-2LeakageExaminationboundary.Class1LeakageExaminationsareperformedeachrefuelingoutageasrequiredbytheCodetoinsurepressureboundaryintegrity.InadditiontotheASMESectionXIleakageexaminations,OperatorwalkdownsasspecifiedbyPlantOperatingProceduresarealsoperformed.ThecombinationofoperatorwalkdownsandtheClass1leakageexaminationthatisperformedeachrefuelingoutageprovideadditionalassurancesinmaintainingplantsafety.AlternateExaminations:R.E.GinnaNuclearPowerPlantproposesthatthevolumetricexaminationcoverageidentifiedwithinAttachmentNumber1beacceptableinfulfillingrequiredCodevolumetricexaminationcoverage.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page44of48RELIEFREQUESTNO.14(Cont'd)JustificationfortheGrantinofRelief:TheReactorPressureVesselwasdesignedandconstructedtoASMESectionIH,1965Editionconstructioncode.ThiscodedidnotcontainrequirementstoensurethatitemsbemadeaccessibleforfutureNDEexaminations.Duetotheoriginallimiteddesignaccessibility,examinationcoveragecannotbeobtainedtotheextentrequiredbytheASMESectionXICode.ASMESectionXIClass1leakageexaminationsareperformedeachoutageaswellasOperatorwalkdownsasspecifiedbyPlantOperatingProcedures.Theseoperatorwalkdownsandsystemleakageexaminationsprovideadditionalassurancesinmaintainingplantsafety.Theidentifiedvolumetricexaminationcoveragefortheseitemsshouldbeacceptableinfulfillingcoveragerequirements.PreviousexaminationswereperformedontheseitemsinconformancetotheCoderequirementsineffectforRG&Eatthosetimes.ImlementationSchedule:ImplementationshallbeperformedattheendoftheFourthInterval.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page45of48RELIEFREQUESTNO.14(Cont'd)AttachmentNumber1CategoryItemSum.Weld<<umberNumberNumberIDDere!iiuu/R<<iremeuiLimitationsB-AB1.30000501RPV-AVesseltoFlangeCirc.Weld54%000502SectionXICodeRequired000503Keyways&IrradiationSlotsB-AB1.11000300RPV-DLowerShelltoRingForging81%Circ.Weld.SectionXICodeRequiredGuideLugs&IncoresB-DB-DB-DB3.90001900N1AB3.90002500N1BB3.100002300N2A-IRSNozzleVesselWD028D-30M.55%'ozzleBossSectionXICodeRequired70%NozzleVesselWD208D-30M.55%'ozzleBossSectionXICodeRequired70%NozzleInsideRadiusSection.90%InnerRadiusSectionXICodeRequiredB-DB-DB-DB3.100B3.90B3.90002900N2B-IRS003100AC-1003003400AC-1002NozzleInsideRadiusSection.90%SectionXICodeRequiredNozzleVesselWD108D-30M.55%'ectionXICodeRequired72%NozzleVesselWD288D-30M.55%'ectionXICodeRequired72%InnerRadiusNozzleBossNozzleBossVolumetricWeldExamination2VolumetricNearSurfaceExamination FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page46of48RequestforReliefNo.15(WasReliefRequestNo.43forThirdInterval)ResidualHeatRemoval(RHR)HeatExchangerOutletNozzleWeldsExaminationLimitationsI.Sstem/ComonentsforWhichReliefisRuested:ThisReliefRequestpertainstotwo(2)ResidualHeatRemoval(RHR)HeatExchangerOutletNozzletoShellWelds,ASMEClass2,CategoryC-B,ItemC2.32.ThereisonenozzleofthistypeassociatedwitheachofthetwoidenticalRHRHeatExchangers.TheCoderequiresthattheexaminationbeperformedwhenthecomponentisopened.BothHeatExchangerswereopenedandVolumetricallyexamined.Limitedcoverageisidentifiedbelow.Summaru¹WeldIDExamCoveraeLimitations169253ONSRHE-1B79%duetointernalweldedseparationplate169053ONSRHE-1A79%duetointernalweldedseparationplateII.ASMESectionXICodeReuirement:ASMESectionXICode,1995Edition,1996Addenda,requiresessentially100%oftheweldlengthorareatoobtaincoverage.ASMESectionXICodeCaseN-460statesthatiftheentireexaminationvolumeorareacannotbeexaminedduetointerferencebyanothercomponentorpartgeometry,areductionincoverageisacceptableprovidedthatthecoverage(thelackof)islessthan10%.

/sea/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page47of48RequestforReliefNo.15(Cont'd)III.RuirementfromWhichReliefisReuested:Reliefisrequestedfromexamining100%oftheweldlengthorareasforthesetwo(2)"identifieditems.Examining100%oftheweldlengthorareaswouldbeimpracticalduetooriginaldesigninterference.IV.BasisforRelief:Reliefisrequestedpursuanttotheprovisionsof10CFR50.55a(g)(5)(iii),therequiredexaminationcoveragefortheidentifieditemsareimpracticalandwouldrequireredesigntoallowexaminationortobereplacedtoenableinspection.ThetwoidenticalResidualHeatRemoval(RHR)HeatExchangerswasdesignedandconstructedtoASMESectionVIII,1965Edition.Thiscodedidnotcontainrequirementstoensurethatitemsbeaccessibleforfutureexaminations.Thetwo(2)ASMEClass2itemsidentifiedabovewereinstalledutilizingthisconstructioncodewhichdidnotprovideforaccessibilityforfutureISINDE.TheISIASMESectionXIvolumetricrequirementisidentifiedwithinTableIWC-2500-1,CategoryC-B,ItemNumberC2.32.TheResidualHeatRemoval(RHR)HeatExchangersispartoftheASMESectionXIVT-2LeakageExaminationboundary.LeakageExaminationsareperformedeachperiodasrequiredbyCategoryC-B,ItemNumberC2.33oftheCodetoinsurepressureboundaryintegrity.InadditiontotheASMESectionXIleakageexaminations,OperatorwalkdownsasspecifiedbyPlantOperatingProceduresarealsoperformed.Thecombinationofoperatorwalkdownsandperiodleakageexaminationsthatareperformedprovideadditionalassurancesinmaintainingplantsafety.V.AlternateExaminations:R.E.GinnaNuclearPowerPlantproposesthatthevolumetricexaminationcoverageidentifiedaboveshallbeacceptableinfulfillingtherequiredvolumetricexaminationcoverage.

FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT1Revision0Page48of48RequestforReliefNo.15(Cont'd)VI.JustificationfortheGrantinofRelief:TheResidualHeatRemoval(RHR)HeatExchangersweredesignedandconstructedtoASMESectionVIII,1965Editionconstructioncode.ThiscodedidnotcontainrequirementstoensurethatitemsbemadeaccessibleforfutureNDEexaminations.Duetotheoriginallimiteddesignaccessibility,examinationcoveragecannotbeobtainedtotheextentrequiredbythecurrentASMECode.ASMESectionXIperiodicleakageexaminationsareperformedaswellasOperatorwalkdownsasspecifiedbyPlantOperatingProcedures.Theseoperatorwalkdownsandperiodicsystemleakageexaminationsprovideadditionalassurancesinmaintainingplantsafety.Theidentifiedvolumetricexaminationcoveragefortheseitemsshouldbeacceptableinfulfillingcoveragerequirements.VII.ImlementationSchedule:TheseexaminationswillbeperformedinaccordancewithTableIWC-2500-1fortheFourthInterval.

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