ML17263A523

Revised ISI Program for 1990-1999 Interval.

ML17263A523
Person / Time
Site:	Ginna
Issue date:	12/31/1993
From:	ROCHESTER GAS & ELECTRIC CORP.
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ML17263A522	List: ML17263A521 ML17263A523
References
PROC-931231, NUDOCS 9401250044
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QUALITYASSURANCE MANUALGINNASTATIONAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALDATEPAGE12/31/931of5TABLEOFCONTENTSSection1.0Inservice Inspection Program:1.01~11.21~31.41.51.61.71.81.91.102.02.12.22.32.42.52.63.03.13.23.33.43.54.04.14.24.3444.55.05.15.25.35.45.5Introduction GeneralApplicable Documents Inspection Intervals Classification ofComponents Responsibility RecordsExamination MethodsandRequirements RepairRequirements Replacement Requirements SystemPressureTestingClass1ProgramPlanBasisforPreparation Components SubjecttoExamination ExtentandFrequency ofExaminations Exemption CriteriaExamination ofReactorCoolantPumpFlywheels Inservice Inspection ProgramPlanClass2ProgramPlanBasisforPreparation Components SubjecttoExamination ExtentandFrequency ofExaminations Exemption CriteriaInservice Inspection ProgramPlanClass3ProgramPlanBasisforPreparation Components SubjecttoExamination ExtentandFrequency ofExaminations Exemption CriteriaInservice Inspection ProgramPlanClass1,2&3Component SupportsBasisforPreparation Components SubjecttoExamination ExtentandFrequency ofExaminations Exemption CriteriaInservice Inspection ProgramPlan9401250044 940111.PDRADOCK05000244.

8'DR QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALDATEPAGE12/31/932of5Section2.0ReliefRequests:

1.0 Introduction

1.1GeneralSection3.0P&IDBoundaryDrawings:

1.0GeneralP&IDBoundaryDrawingsSection4.0Section5.0CodeTables:1.0GeneralTable1,Class1Table2,Class2Table3,Class3Table4,Class1,2,&3IWFComponent SupportsLineList:1.0GeneralLineListSection6.0Allocation Tables:1.0GeneralASMECodeRequirements Class1Class2Class3Class1,2,&3SupportsAugmented ReactorCoolantPumpFlywheelProgramReactorVesselAugmented Program,CategoryB-AHighEnergyProgramSnubberProgramSeismicSupportProgram QUALITYASSURANCE MANUALGINNASTATIONAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALDATEPAGE12/31/933of5Section7.0UTCalibration Blocks:1.0GeneralUTCalibration BlocksSection8.0HighEnergyProgram:1.02.03.04.05.06.07.08.09.0GeneralExamination Requirements Examination MethodsFrequency ofExamination Examination Evaluation Repair&TestingRequirements Replacement

&TestingRequirements Scheduling Reports&RecordsTable1-HighEnergyWelds&Component SupportIdentification.

Section9.0SnubberProgram:1.02.03.04.05.06.07.08.0GeneralExamination, Testing&Monitoring Requirements Examination

&TestingMethodsExamination

&TestingFrequency Examination, Testing&Monitoring Evaluation Repair,Replacement

&Modification Requirements Scheduling Reports&RecordsSection10.0SeismicSupportProgram:1.02.03.04.05.06.07.07.08.0GeneralExamination Requirements Examination MethodsFrequency ofExamination Examination Evaluation Repair&TestingRequirements Replacement

&TestingRequirements Scheduling Reports&Records QUALITYASSURANCE MANUALGINNASTATIONAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALDATEPAGE12/31/934ot5Section11.0Additional Programs:

1.02.03.04.05.05.75.8GeneralSteamGenerator TubeInspection Program2.1General2.2Examination Requirements 2.3Examination Methods2.4Frequency ofExamination 2.5Examination Evaluation 2.6Repair,Replacement

&TestingRequirements 2.7Scheduling 2.8Reports&RecordsReactorCoolantPumpFlywheelProgram3.1General3.2Examination Requirements 3.3Examination Methods3.4Frequency ofExamination 3.5Examination Evaluation 3.6Repair,Replacement

&TestingRequirements 3.7Scheduling 3.8Reports&RecordsClass1BoltingProgram(IEB82-02)4.1General4.2Examination Requirements 4.3Examination Methods4.4Frequency ofExamination 4.5Examination Evaluation 4.6Repair,Replacement

&TestingRequirements 4.7Scheduling 4.8Reports&RecordsReactorVesselAugmented Program,CategoryB-A5.1General'.2 Examination Requirements 5.3Examination Methods5.4Frequency ofExamination 5.5Examination Evaluation 5.6Repair,Replacement

&TestingRequirements Scheduling Reports&Records QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALDATEPAGE12/31/935of5SUPPLEMENT 1TOAPPENDIXB"Inservice Inspection ProgramPlan"(Separate Documentcontrolled byMaterials Engineering 6Inspection Services.)

SUPPLEMENT 2TOAPPENDIXB"TheRepair,Replacement andModification Program" QUALITYASSURANCE MANUALGINNASTATIONSection1EFFECTIVE DATE:PAGE1of34December31,1993ROCHESTER GAS8EELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALPREPAREDBY:p+Dtg~(q3QUALITYASSURANCE REVIEW:APPROVEBY:

1.0INTRODUCTION

General1.1.11.1.21~1~3ThisAppendix"B"totheQualityAssurance Manualoutlinesthethirdintervalinservice inspection examination (ISI)requirements forClass1,Class2,andClass3systems,andcomponents forRochester Gas&ElectricCorporation's (RG&E)R.E.GinnaNuclearPowerPlant(GinnaStation).

Thethirdinspection intervalbeginsonJanuary1,1990,aspermitted byParagraph IWA-2400ofASMECodeSectionXI,thesecondintervalconcluded December31,1989.Thisprogramisbasedontherequirements ofthe1986EditionoftheAmericanSocietyforMechanical Engineers (ASME)BoilerandPressureVesselCode,SectionXI,"Inservice Inspection ofNuclearPowerPlantComponents" asadoptedbytheCodeoftheFederalRegulations, 10CFRPart50,(FederalRegister53FR16051)

May5,1988.Thisprogramexcludes'he controlsoftheEnforcement Authority, andN-Stamp,inadditiontoIWEofASMESectionXI,sinceitisnotendorsedby'theRegulation.

Inservice Testingofpumps(IWP)andvalves(IWV)isperformed inaccordance withAppendixCoftheGinnaStationQualityAssurance Manual.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE INSPECTION PROGRAMFORTHE1990-1999 XNTERVALREV.3PAGE2of34Section11.2Applicable Documents RG&Ehasadoptedthefollowing documents asthebasisforthethirdinspection intervalandiscommitted tosatisfying theirrequirements.

Specificexceptions totherequirements ofASMESectionXIareidentified andlocatedinthe"ReliefRequests",

Section2.0ofthisdocument.

Thisprogramwasdeveloped inaccordance withthesedocuments:

1~2.11.2.1.11'.2ASMEBoilerandPressureVesselCodeSectionXI,"RulesforInservice Inspection ofNuclearPowerPlantComponents,"

1986Edition,noAddenda.ASMEBoiler&PressureVesselCode,SectionXI,1986Edition,noAddenda,AppendixIV.U.S.NuclearRegulatory Commission (USNRC)Regulatory Guides:a~b.1.14,Rev.1,"ReactorCoolantPumpFlywheelIntegrity" 1.147,LatestRevision, "Xnservice Inspection CodeCaseAcceptability

-ASMESectionXI,Divisionl"c~1.150,Rev.1,"Ultrasonic TestingofReactorVesselWeldsDuringPreservice andXnservice Examinations" d.1.83,Rev.1,"Inservice Inspection ofPressurized WaterReactorSteamGenerator Tubes"e.1.26,Rev.3"QualityGroupClassifications andStandards forWater,Steam,andRadioactive WasteContaining Components ofNuclearPowerPlants.1.29,Rev.3,"SeismicDesignClassification".

g1.121,Rev.0,"BasesforPluggingDegratedPWRSteamGenerator Tubes".

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE3of34h.1.65,Rev..0,"Materials andInspections forReactorVesselClosureStuds".1.2.3ASMECodeCasesInaccordance with10CFR50.55a, Footnote6,ASMESectionXICodeCasesreferenced inRegulatory Guide1.147,"Xnservice Inspection CodeCaseAcceptability-ASMESectionXX,Division1,"maybeincorporated intotheGinnaStationISIProgram.ThoseCodeCasesincludedinRegulatory Guide1.147thatwillbeimplemented atGinnaStationareidentified inthissection.EachCodeCaseisprecededbyinformation ontheapplicable component/area, ASMErequirements, andhowtheCodeCasewillbeimplemented.

Paragraph 1.2.3.1liststhosebeentechnically reviewedandwithoutconditions bytheNRC1.147andwillbeimplemented yearInspection Interval.

codecasesthathaveendorsed, withorinRegulatory Guideduringthe3rdten1.2.3.1Useofanysubsequent NRCendorsedcodecasesthatareidentified inrevisions totheRegulatory'uide 1.147maybeincorporated intheprogramandusedduringthe3rdtenyearInspection Interval.

USNRCRegulatory Guide1.147-ApprovedASMESectionXICodeCasesCodeCaseNo.Sect.XIReferences ComonentAreaN307-1IWB-2500-1 StudsandBoltswithHeaterHolesN-416IWA-4400AnyrepairedorreplacedClass2pipingcomponent thatcannotbeisolatedbyvalvesorrequiressecuringsafety/reliefvalves.N-401IWA-2233EddyCurrentExaminations QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE4of34N-402IWA-2233EddyCurrentCalibration StandardMaterialN-427*N-437N-446CodeCasesIWA-5260IWA-2300CodeCasesinInspection PlansUseofdigitalreadoutanddigitalmeasurement devicesforperforming PressureTests.Recertification ofVisualExamination Personnel.

N-460N-481N-491IWA-2000/3000 B-L-1,ItemB12.10IWF-1000/2000/3000 Alternative examination coverageforClass1andClass2welds.Alternative examination requirements forCastAustenitic PumpCasings.Alternative rulesforexamination ofClass1,2,3,andMCComponent SupportsofLightWaterCooledPowerPlants.N-498IWX-5000Alternative rulesfor10-yearHydrostatic PressureTestingforClass1and2systems.1.2.4*AsamendedbyUSNRCRegulatory Guide1.147,April,1992.R.E.GinnaUpdatedFinalSafetyAnalysisReport(UFSAR):Section5.4-ForClass1Section6.6-ForClass2and3 1AII'I QUALITYASSURANCE MANUALGXNNASTATXONTITLE:APPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVXCE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE5of341.2.5LetterdatedMarch23,1981,fromDarrellG.Eisenhut,

Director, DivisionofLicensing, USNRC,regarding Technical Specification Revisions forSnubberSurveillance 1.2.5.1FirstAddendatoASME/ANSI OM-1987,Part4Published in1988.1.2.61.2.71.2.8USASB31.1.0-1967, "PowerPiping"forHighEnergySystemsR.E.Ginna,Technical Specification 4.2."Inservice Inspection".

R.E.GinnaTechnical Specification 3.13and4.14"Snubbers".

1.2.9LetterdatedFebruary16,1989,toMr.CarlStahle,USNRC,PWRProjectDirectorate No.1,regarding proposedchangestoSnubberTechnical Specification R.E.GinnaNuclearPowerPlant,DocketNo.50-244.1.2.101.2.111.2.121.2.131'1.3.1Rochester GasandElectricCorporation Mechanical Engineering Specification, ME-256,Titled-"SnubberInspection andTestProgram".

ElectricPowerResearchInstitute PWRSteamGenerator Inspection Guidelines, Rev.2.CodeoftheFederalRegulations, 10CFRPart50.USNRC,NRCRegionIInspection Report50-244/90-12,Section3.4regarding repairprogram"ServiceInduced"and"CodeRejectable" repairs.Inspection Intervals Theinservice inspection intervals forClass1components startedonJanuary1,1970,withthesecondintervalstartingonJanuary1,1980.Thethirdinspection intervalshallstartonJanuary1,1990.

QUALITYASSURANCE MANUALGXNNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE XNSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE6ot34Section11.3.21.3'ForClass2andClass3,thefirstinspection intervalstartedonMay1,1973;thesecondonJanuary1,1980;andthethirdonJanuary1,1990.Thethirdinspection intervalforClass1,2and3isscheduled toendDecember31,1999.However,thisdateissubjecttochangeasallowedbyIWA-2400,whichstatesthateachinspection intervalmaybedecreased orextended(butnotcumulatively) byasmuchasoneyear.IfR.E.GinnaNuclearPowerPlantisoutofservicecontinuously for6monthsormore,theinspection intervalandassociated periodduringwhichtheoutageoccurredmaybeextendedforaperiodoftimeequivalent totheoutage.1.3.4A10-yearexamination ProgramPlan(Supplement 1toAppendixB),willdescribethedistribution ofexaminations forClass1,Class2,andClass3components inaccordance withInspection ProgramB,theIWB-2400, IWC-2400, IWD-2400andIWF-2400ofSectionXI,"RulesforInservice Inspection ofNuclearPowerPlantComponents",

1986Edition,noAddenda.1.4Classification ofComponents TheProgramPlancomponents andpipinghavebeenclassified byRG&Eforpurposesofinservice inspection basedonSectionXI,ArticleIWA-1320, anddefinitions contained in10CFR50.2.

l.5Responsibility Asspecified inParagraph IWA-l400ofASMESectionXI,RG&Ebearstheoverallresponsibility forimplementation ofanXSXprogram.Administrative Procedures, NDEProcedures, ISXPlansandSchedules are'inplacetocontrolandimplement theseInservice Xnspection requirements.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE7of341.6RecordsExamination recordsanddocumentation ofresultsprovidethebasisforevaluation andfacilitate comparison withpreviousresultsandsubsequent inspections.

Inaccordance withSectionXI,IWA-6000, theserecordswillbemaintained fortheplantlife.1.6.1AnInservice Inspection Reportshallbegenerated todocumentapplicable Inservice Xnspection andassociated Repair,Replacement andModification activities.

ASMENXS-1andNIS-2Formsshallbegenerated andincludedwithintheXnservice Inspection Report.f1.7Examination MethodsandRequirements Examination methodswhichwillbeusedtosatisfyCodeexamination requirements havebeenlistedfornonexempt Class1,Class2,andClass3components, asapplicable.

Providedinthefollowing isabriefexplanation oftheexamination methodswhichwillbeperformed tosatisfytheCoderequirements.

Personnel performing nondestructive examinations willbequalified inaccordance withwrittenprocedures preparedasrequiredbyParagraph IWA'-2300 ofSectionXI.Methodsofexamination arealsodescribed intheapplicable sectionsofthisInservice Inspection Program.1.7.1VisualExamination MethodVisualexaminations (VT)willbeperformed inaccordance withIWA-2210ofASMESectionXI.IWA-2210definesthethreetypesofVTexaminations asfollows:

IU)lIlt1' QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE8of~34Section11.7.1.1VT-1examinations areconducted todetermine thecondition ofthepart,component orsurfaceexamined.

Theexamination shalldetermine conditions suchascracks,wear,corrosion, erosion,orphysicaldamageonthesurfacesofthepartorcomponents.

Thistypeofexamination maybeperformed bydirectorremotemethodsasdefinedinIWA-2211.

1.7.1.2VT-2examinations're conducted todetectleakage(orabnormalleakage)frompressure-retaining components duringsystempressureorfunctional testsasdefinedinIWA-2212.

1.7.1.3VT-3examinations areconducted todetermine generalmechanical andstructural conditions ofcomponents andtheirsupportssucha'sthepresenceoflooseparts,debris,orabnormalcorrosion

products, wear,erosion,corrosion, andthelossofintegrity atboltedorweldedconnections.

VT-3Examinations arealsoconducted todetermine conditions relatedtooperability ofmechanical andhydraulic

snubbers, andspringdevices.1.7.2SurfaceExamination Method1.7.2.1Asurfaceexamination isperformed todetectthepresenceofdiscontinuities opentothesurfaceofamaterial.

Techniques forsurfaceexamination includeeithermagneticparticle(MT)orliquidpenetrant (PT)methods.Surfaceexaminations willbeconducted asdefinedinIWA-2220.

1.7.3Volumetric Examination Method1.7.3.1Avolumetric examination isperformed todetectthepresenceofdiscontinuities inthevolumeofamaterial.

Suchvolumetric examinations includeradiographic (RT),ultrasonic (UT),andeddycurrent(ET).Volumetric examinations willbeconducted asdefinedinIWA-2230.

1.7.3.2Radiography maybeperformed byutilizing eitherx-rayorgammaraytechniques.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE9of341.7.3.3TheUTexaminations maybeperformed byutilizing eithermanualormechanized UT(MechUT)techniques inaccordance withAppendixIofSectionXIandRegulatory Guide1.150,~Rev.1'fortheReactorVesselExamination only.1.7.3.4TheETMethodwillbeutilizedintheexamination ofheatexchanger tubinginaccordance withAppendixIVofASMESectionXIandUSNRCRegulatory Guide1.83.1.7.4Alternative Examination Methods1.7.4.1Alternative examination methodsmaybeperformed tothosedescribed in1.7.1,1.7.2and1.7.3asallowedinIWA-2240.

Thesemayincludesuchthingsasnewlydeveloped techniques, providedthatthesealternative methodsareshownbypractical demonstration tobeequivalent orsuperiortothoseofthespecificmethodtothesatisfaction oftheLevelIIINDEExaminer&Authorized NuclearInservice Inspector (ANII).1.7.4.2l.7.5Examinations thatdetectflawswhichrequireevaluation maybesupplemented byotherexamination methodsandtechniques todetermine thecharacter oftheflaw.Evaluation ofExamination ResultsandSuccessive Inspections l.7.5.1Theevaluation ofnondestructive examination resultsshallbeinaccordance withArticleIWA-3000ofSectionXI.Allreportable indications willbesubjecttocomparison withpreviousdatatoaidincharacterization anddetermination oforigin.Class1andClass3components containing relevantserviceinducedconditions willbeconsidered acceptable forcontinued serviceproviding ananalytical evaluation performed demonstrates thecomponent's acceptability andissubsequently examinedinaccordance withtherequirements ofIWB-3132.4, IWB-3142.4 andIWB-3144(b).

Acceptance byRepairorReplacement canalsobeperformed.

Successive inspections forClass1relevantserviceinducedconditions shallcomplywiththe

QUALITYASSURANCE MANUALGINNASTATXONTITLE:APPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE10of34Section1requirements ofIWB-2420(b) and(c).ForClass3relevant, serviceinducedconditions, successive inspections shallcomplywiththerequirements ofIWC-2420(b) and(c).Class2components containing relevantserviceinducedconditions willbeconsidered acceptable forcontinued serviceproviding anevaluation performed demonstrates thecomponent's acceptability andissubsequently examinedinaccordance withtherequirements ofIWC-3122.4, IWC-3132.3 andXWC-3134(b).

Acceptance byRepairorReplacement canalsobeperformed.

ForClass2relevantserviceinducedconditions, successive inspections shallcomplywiththerequirements ofXWC-2420(b) and(c).Period1andutothe'9'4Outae'86CodeClass1,Class2,andClass3Supportscontaining relevantserviceinducedconditions willbeconsidered acceptable forcontinued serviceproviding'n evaluation ortestisperformed thatdemonstrates thecomponent's acceptability.

Acceptance byRepairorReplacement canalsobeperformed.

Successive inspections onsupportscontaining relevantserviceinducedconditions shallcomplywiththerequirements ofIWF-2420(b) and(c).Periods2Startin'94Outaeand3:Class1,Class2,andClass3Supportswhosevisualexamination doesnotrevealconditions asdescribed intheacceptance standards

(-3400ofCodeCaseN-491),shallbeacceptable forservice.Visualexaminations whichdetectrelevantserviceinducedconditions asdescribed intheacceptance standards shallbeunacceptable forserviceunlessacceptedorcorrected byoneofthefollowing methods;-Corrective measures(adjustment,

'repair,orreplacement),

andsubsequent reexamination including therequirements of-2220(b)(Note:Successive examination requirements of-2420mustbeappliedtosupportscontaining relevantserviceinducedconditions inwhichcorrective measureswereutilizedforacceptance.)

'IffiIII QUALITYASSURANCE MANUALGINNASTATIONTITLEIAPPENDIXBR.E.GXNNANUCLEARPOWERPLANTXNSERVICE INSPECTION PROGRAMFORTHE1990-1999 XNTERVALREV.Section13PAGE11of34-Evaluation

'rTesttotheextentnecessary tosubstantiate itsintegrity foritsintendedservice(Note:Visualexaminations thatdetectsurfaceflawsthatexceed-3400criteriashallbesupplemented byeithersurfaceorvolumetric examinations)

.Note1:Flawsorrelevantconditions inwhichanalytical evaluations arebeingperformed todetermine acceptance, maybeconsidered acceptable forcontinued serviceduringthisevaluation process.1.7.6Additional Examinations 1.7.6.1Inservice examinations performe'd thatrevealedserviceinducedflawsthatexceedstheacceptance standards shallhaveadditional examinations performed.

1.7.6.2Additional examinations shallbeperformed totheextentrequiredbyIWB-2430wheneveraserviceinducedrejectable flawisidentified duringtheperformance ofISIexaminations inaccordance withtherequirements specified withinIWBandIWD.1.7.6.31.7.6.4Additional examinations shallbeperformed totheextent.requiredbyIWC-2430wheneveraserviceinducedrejectable flawisidentified duringtheperformance ofISIexaminations inaccordance withtherequirements specified withinIWC.Additional examinations shallbeperformed, startingthe'94outage,totheextentrequiredby-2430(CodeCaseN-491)wheneveraserviceinducedrejectable flawisidentified duringtheperformance ofISXexaminations inaccordance withtherequirements specified withinCodeCaseN-491andXWF.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:,APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE12of'34Section11.8RepairRequirements Repairsshallbeperformed totherequirements specified withinSupplement 2toAppendixB,TheRepair,Replacement

&Modification (RR&M)Program.ThisRR&MProgramshallapplytoASMEClass1,2&3pressureboundarypiping,components

&supports.

1.8.1Performance ofRepairRepairsonASMEClass1,2or3components shallbeperformed inaccordance withtherequirements ofIWA/B/C/D/F-4000 ofASMESectionXI,1986EditionorlaterEdition/Addenda thatisapprovedvialOCFR50.55a.

Alternatively, repairs'maybeperformed eithertotherequirements oftheoriginalConstruction Code,whichth'ecomponent orsystemwasfabricated to,ortolaterapprovededitionsoftheConstruction Code,orlaterapprovededitionsofASMESectionIIIalongwithanyCodeCasesapprovedviaRegulatory Guide1.147.1.8.2Examination/Test forRepairs1.8.2.1Applicable examination requirements oftheConstruction Codeshallbemet.Iftherepairisperformed onanexistingweldthatrequiresthecompleteremovaloftheoriginalweldmetalwithinthatjointbeforerewelding, thefollowing additional NDErequirements arerequired:

(a)Pressureretaining components greaterthan2inchesindiametershallrequirebothsurface,and1004volumetric examinations tobeperformed onthenewweld.Or(b)Pressureretaining components 2inchesorlessindiametershallrequireasurfaceexamination tobeperformed onthenewweld.Examinations andtestingofsnubbersandsupportsthathavebeenrepairedshallbeperformed inaccordance with5.0belowandSection9ofthisprogram.

1111IIIfII QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE13of341.8.2.2Theexamination shallincludetheoriginalexamination methodthatdetectedtheflaw,ifapplicable.

1.8.2.3'pplicable examination requirements ofASMEsectionXI,1986EditionshallalsobemettoserveasanewPSIbaselineforfutureISIexaminations, unlesstheexamination performed underparagraph 1.8.2.1wasconducted underconditions andwithequipment andtechniques equivalent tothoserequiredbySectionXI.1.8.2.4Ahydrostatic testshallbeperformed inaccordance withASMESectionXI,1986Edition,unlessspecifically exemptedbySectionXIArticleIWA-4400, ortheAlternate RulesofIncorporated CodeCasesorReliefRequests, asapplicable..

1.8.3SurfaceflawsinClass1,2,or3,bolts,studs,nutsandligaments mayberemovedbymechanical meansprovidedtheremovalofthatflawdoesnotalterthebasicconfiguration oftheitem.Bolts,studs,andnutsthathaveflawsthatcannotberemovedbymechanical meansshallbereplacedorreportedforevaluation asindicated bySectionXI,ArticleIWA-3100.

1.9Replacement Requirements Replacement requirements, whichincludesmodifications, areapplicable toASMEClass1,2and3pressureretaining components andpipingsystemsandtheirsupports, unlessspecifically exemptedbyASMESectionXI,1986Edition,ArticleIWA-7400.

1.9.1Replacement Performance Replacements shallmeettherequirements ofASMESectionXI,1986EditionoralaterEdition/Addenda approvedvia10CFR50.55a.

Inaddition, replacement itemsshallmeet.therequirements oftheoriginalConstruction Codetowhichtheoriginalpartwasconstructed.

TheR.E.GinnaNuclearPowerPlantReplacement ProgramisdefinedwithinSupplement 2toAppendixB.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE14of34Section11.9.1.1A"LikeforLike"replacement isanitemthatmeetstheoriginalrequirements ofthedesignandprocurement documents fortheitembeingreplacedanddoesnotrequirereconciliation, reanalysis orchangestotheitem'sdesignandtechnical requirements.

1.9.1.2Anapprovedequivalent isareplacement thatwillresultinadesignortechnical changetotheoriginalrequirements basedonreconciliation, re-analysis and/ortestingperParagraph 1.9.2.1.1.9.21.9.2.1Alternatively itemsusedforreplacement maymeetallorportionsoftherequirements lateradditions oftheConstruction CodeorSectionIII,whentheconstruction codewasnotSectionIII.Inordertousethisalternate

approach, thefollowing additional requirements apply.Reconcile therequirements affecting thedesign,fabrication andexamination ofthereplacement withtheDesignAnalysisorDesignCriteriaorothermethodsofanalysisthatdemonstrates theitemissatisfactory forthespecified designandoperating conditions.

1.9.2.2Mechanical interfaces, fitsandtolerances thatprovidesatisfactory performance arecompatible withthesystemandcomponent requirements.

1.9.2.3Materials usedarecompatible withinstallation andsystemrequirements.

1.9.2.4Ifareplacement isbecauseofafailureoftheitembeingreplaced, adesignevaluation oranalysisshallconsiderthecauseofthefailureanditsimpactonothersimilaritems,andthenecessary actionsto'etakentoprecluderecurrence.

1.9.2.51.9.2.6Whenweldingistobeperformed aspartofthereplacement, therulesofSectionIXshallbefollowedtosatisfytherequirements ofIWA-7320andIWF-7000.

CItemsidentified inIWA'-7400 willbeexemptfromtherequirements ofthereplacement program.

PIfH QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE15of341.9.3Examination/Test 1.9.3.1Thereplacement itemshallbeexaminedandpressuretestedinaccordance withtheConstruction CodeorlaterCodeprovideditmeetstherequirements of1.9.1above.1.9.3.2Snubbersshallbeexaminedandtestedinaccordance withSection9ofthisprogram.Wheretheattachment ofthenon-pressure-retaining itemisweldedtoa'ressure

boundary, theweldshallbeexaminedinaccordance withtherequirements of1.8.2.1.9.3.3Applicable examination requirements ofASMESectionXI,1986Edition,shallalsobemettoserveasanewPSIbaselineforfutureISIexaminations, unlesstheexamination performed under1.9.3.1wasconducted underconditions andwithequipment.and techniques equivalent tothoserequiredbyASMESectionXI.1.9.3.4Replacements installed bymechanical methodsshallbepressuretestedatnominaloperating

pressure, orforClass1systems,thepressureassociated with100%ratedreactorpower.1.9.4ReportsandRecordsReportsandrecordstotheextentrequiredbytheconstruction codeandIWA-7520, asapplicable forthereplacement, shallbecompleted forallreplacements.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE16of341.101.10.1l.10.1.1SystemPressureTestingGeneralRequirements Pressuretestingshallbeconducted onallClass1,2,and3pressureretaining components inaccordance withtherequirements ofSectionXIArticlesIWA-5000, IWB-5000, IWC-5000, IWD-5000; andSectionXITableIWB-2500-1

-Examination Cat.egory B-P,TableIWC-2500-1

-Examination CategoryC-H,andTableIWD-2500-1

-Examination CategoryD-A,D-BandD-C.Inaddition, "HighEnergy"MainSteamandFeedwater Pipingshallalsobepressuretestedonthesenon-class systemsinaccordance withtherulesofIWC-5000.

1.10.1.2Pressuretestsareconducted fromnormaloperating

pressure, toapressureupto254overdesignpressure.

Thedegreeofpressurization andthetestboundarydependsuponthetypeofpressuretestbeingperformed.

Avisualexamination (VT-2method)isperformed inconcertwiththepressuretestonpressureretaining components undertestpressure.

Specificexceptions fromachieving SectionXIrequirements aredetailedintheReliefRequestSectionofthisdocument.

1.10.2TypeofPressureTestsThevarioustypesofpressuretestswhicharerequiredduringtheinspection int:erval aredescribed inthefollowing:

1.10.2.1LEAKAGEPRESSURETESTThistest,isperformed subsequent torefueling outages.Theboundarysubjecttotestpressurization andtheassociated VT-2examination duringaleakagepressuretestwillextendtothepressureretaining components withinthesystemboundarycontaining pressurized reactorcoolantundertheplantmodeofnormalreactorst;artup.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E..GINNA NUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE17of341.10.2.2FUNCTIONAL PRESSURETESTThistestisperformed onceeachinspection period.Theboundarysubject,totestpressurizat'.ion andtheassociated VT-2examination duringasystemfunctional

-pressuret.estwillincludeonlythosepressureretaining components withinthesystemboundarypressurized underthetestmoderequiredduringtheperformance oraperiodicsystem/component surveillance test.1.10.2.3INSERVICE PRESSURETESTThistestisperformed onceeachinspection period.Theboundarysubjecttoatest.pressurization andtheassociated VT-'examination duringasysteminservice pressuretestwillincludeonlythosepressureretaining component'.s underoperating pressureduringnormalsystemservice.1.10.2.4HYDROSTATIC PRESSURETESTThistest:isperformed onceeachinspection interval.

Theboundarysubjecttotestpressurization andtheassociated VT-2examination duringasystemhydrostat:ic pressuretestincludesallClass1,2,and3components andpiping.1.10.2.5PNEUMATIC PRESSURETESTThistestislimitedtoClass2and3systems.Theboundarylimitssubjecttotestpressurization andtheassociat;ed VT-2examination duringasystempneumatic pressuretestarethesameasahydrostatic pressuretest.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVXCE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSection1PAGE18of341.10.2.6REPAIR/REPLACEMENT PRESSURETESTSTheboundarysubjecttotestpressurization andtheassociated'VT-2 examination islimitedtotheportionrepairedorreplaced, withintheClass1,2or3boundary.

Thespecifictypeofpressuretestiseitherahydrostatic, pneumatic oratestatoperating pressuresuchastheLeakage,Xnservice orFunctional.

Thespecifictypeoftesttobeperformed andtheexemptions whichapplytorepair/replacement pressuretestingaredescribed inSupplement 2toAppendixB,theRepair,Replacement 6Modification Program.CodeCaseN-498doesnotapplytoRepairs,Replacements orModifications.

1.10.31.10.3.1Examination Requirements Duringtheconductofpressuretests,certified VT-2examination personnel, usingRGGEapprovedNDEVT-2examination procedure andtheassociated recording form,willexaminetheportionsofpipingunderpressurization.

Theexamination andtestboundaries aredepictedoncontrolled color-coded PAID's.Insomecases,thetestboundaryextendsbeyondtheexamination boundaryduetovalvelocationand/orcheckvalveflowdirection.

Ingeneral,personnel willexamineforevidenceofleakage,inoperative leakagecollection systemsandevidenceofcorrosion.

1.10.41.10.4.1TestRequirements GENERALThecontained fluidinthesystemorfluidaddedtothesystemshallserveasthepressurizing ortestmedium.Insteamsystemseitherwaterorairmaybeused..Whereairisused,thetestprocedures shallpermitthedetection andlocationofthroughwallleakagesincomponents ofthesystemtested.Thetemperature ofthetestmediumwillbethatoftheavailable sourceunlessotherwise specified bytheimplementing testprocedure/document.

Thetestmediumwillbeofaqualitywhichisequaltoorbetterthanthesystemoperating medium.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE19of34Section11.10.4.1.1 Duringconductofhydrostatic tests,allentrained airwillbeventedfromthesystemexceptinthefollowing cases:a~b.c~d.Atmospheric StorageTanks0-15psiStorageTanksClass1systemswhereamixtureofsteam,waterandnoncondensible gasesarepresentinaproportion typicalofnormalstartupconditions.

NormalSteamSystems1.10.4.1.2 ForLeakage,Functional, Inservice andHydrostatic tests,thelevelofsyst:empressureandtemperature indicated orrecordedbynormaloperating systeminstrumentation, oralternatively bytestinstrumentation isacceptabl'e.

Forhydrostatic tests,theinstrument requirements ofIWA-5260andapplicable CodeCaseN-437mustbemet.1.10.4.2LEAKAGEPRESSURETESTREQUIREMENTS Thesystemleakagepressuretestshallbeconducted atapressurenotlessthannominaloperating pressureassociated with100%RatedReactorPower.Thepressureandtemperature willbeattainedatarateinaccordance withtheheat-uplimitations specified intheGinnaTechnical Specifications forthecomponent/piping systembeingtested.1.10.4.3FUNCTIONAL PRESSURETESTREQUIREMENTS Thesystemfunctional pressuretestisnormallyperformed duringperformance oraPeriodicSurveillance Test.Thetestisusedtoestablish thetestconditions associated withnormalsystemoperating pressureandtemperature forperformance ofthesystemfunctional pressuretest.1.10.4.4INSERVICE PRESSURETESTREQUIREMENTS Theoperating pressureandtemperature duringnormalsystemoperation isusedduringperformance ofthistest.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE20of34l.l0.4.51.10.4.5.1 HYDROSTATIC PRESSURETESTREQUIREMENTS General1.10.4.5.2 CodeCaseN-498stipulations maybeemployedonClass1and2RequiredSystemsinlieuofthe10yearHydrostatic Test.Hydrostatic testpressurerequirements varyamongeachoftheclassifications.

Theminimumtestpressurewillbemaintained fortheentiredurationofthetest,withtheexception oftestsperformed attemperatures greaterthan200'F,wheretheexamination phasemaybeperformed atalowerpressurecorresponding to200'F.Thetestpressureshallnotexceedthemaximumallowable testpressureofanycomponent.

withinthetestboundary.

Thehydrostatic testpressure, including statichead,willnotexceed106%ofthespecified testpressureforthesystemanywherewithinthetestboundary.

1.10.4.5.2.1 Incaseswherethehighestandlowestelevations "cannotbeisolated, andthetestpressureincluding statichead,wouldexceed106:ofthespecified testpressureatthelowestpoint,thetestpressurewillbereduced.1.10.4.5.2.2 Incaseswherethehighandlowelevations resultinunreasonably smalldifferences betweenthetest,pressure including statichead,and106~ofthespecified testpressure, thetestpressurewillbereducedtoaccommodate theprecision ofthetestinstrument.

1.10.4.5.2.3 Thetestpressure, asidentified insections1.10.4.5.2.1 and1.10.4.5.2.2, willbeadjustedsuchthat,thetestpressure, including statichead,doesnotexceed106%ofthespecified testpressureatthelowestpoint.Theresulting pressureatthehighestpointwillbeconsidered acceptable.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE21of34Section11.10.4.5.3Thehydrostatic testboundarywillendatthetransition betweensystempipingandinstrumentation tubingshownonP&IDdrawings.

Whenthistransition doesnotoccuratanisolation valve,theboundarywillbeextendedtothefirstisolation valveafterthetransition.

1.10.4.6Thefollowing sectionslistthehydrostatic testpressurerequirements whichwillbemetforeachCodeclassification:

1.10.4.6.1

,Class1'hesystemhydrostatic pressuretestisconducted atthepressurecalculated fromthefollowing tablebasedonthetesttemperature:

TestTemeratureDe.F.TestPressure100orless200300400500orgreater1.10P1.08P1.06P1.04P1.02P1.10.4.6.2 "P"isthenominaloperating pressurecorresponding withl00%ratedreactorpower.Linearinterpolation willbeusedatintermediate testtemperatures.

Technical Specification heat-up/cool-down limitswillbeobserved.

Class2,3,andHighEnergy:a~Thetestpressurewillbeatleast1.10timesthesystempressureforsystemswithadesigntemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithadesigntemperature above200'F.Thesystempressurewillbethelowestpressuresettingamong'the numberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurewillbesubstituted forthesyst:empressure.

II QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE22of34b.Inthecaseofatmospheric storagetanks,thenominalhydrostatic pressuredeveloped withthetankfilledtoitsdesigncapacitywillbeacceptable asthetestpressure.

c~For0to15psistoragetanks,thetestpressurewillbe1.1timesthedesignpressureofvapororgasspaceaboveliquidlevelforwhichoverpressure protection isprovidedbythereliefvalves.Ifreliefvalvesarenotinstalled, thetestpressurewillbeequalto1.1timesthenormaloperating pressure.

d.Forthepurposeofthetest,open-ended portionsofasuctionordrainlinefromastoragetankextending tothef'irstshutoffvalveareconsidered asanextension ofthestoragetank.e.Foropenendedportionsofdischarge linesbeyondthelastshutoffvalveinnonclosed systems,atestthatdemonstrates unimpaired flowwillbeperformed inlieuofasystemhydrostatic pressuretest.Unimpaired flowforClass2isdefinedasan"openflowpath"andforClass3as"adequate flowduringsystemoperation".

1.10.51.10.5.11.10.5.2TestImplementation Allpressuretestingisimplemented usingboth.theVT.-2examination procedure andthespecifictestprocedure forthetypeoftestandportionofsystembeingtested.Applicable RequiredSystemPressureTestBoundaries shallbeconfirmed priortoexamination performance.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE23of34Section11.10.6Scheduling Whenusingtheinspection plan,itshouldbenotedthatduringaperiodorrefueling outageinwhichahydrostatic testisperformed onasystemorportion(s) ofasystem,theleakagetest(Functional orInservice) requiredforthatperiodonthesamesystemorportionofthesystem,maybedeletedfromthatperiodoroutage.Thehydrostatic testwillsatisfytherequirements

,forthatleakagetest.2.02.1CLASS1PROGRAMPLANBasisforPreparation 2.1.1Preparation oftheClass1ISIprogramplanwasbasedontherequirements ofArticlesIWB-l000andIWB-2000ofSectionXI.Thesearticlesproviderulesandguidelines forexemptions,

.inspection schedules, andexamination requirements forClass1pressureretaining components andtheirintegralattachments.

2.1.2Asallowedby10CFR50.55a (b)(2)(ii),

theextentandfrequency requirements forClass1CategoryB-Jweldexaminations maybebasedonthe1974EditionofASMESectionXIwithAddendathroughSummer,1975.ThisearlierCodedoesnot.haveanycriteriaestablished fortheselection ofspecificweldstobeexamined, andtherefore, stresslevelcriteria, andterminalendcriteriaisnotrequiredfortheselection process.Insteadofutilizing theearlierCoderulesforCategoryB-Jwelds(whichhasnoselection guidance),

the1986Coderuleswillbeutilizedtotheextent,practical.

Inlieuofthestresslevelselection criteriaTableIWB-2500-1, Notel(b),allaccessible terminalend,welds(including terminalendstovesselperNotel(a)ofTableIWB-2500-1) shallbeselected.

RefertoCodeTable1inSection4forselection criteria.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE24of34Section12.2Components SubjecttoExamination 2.2.1Basedontherequirements ofSectionXI,Class1nonexempt pressure-retaining components andtheirintegralattachments willbesubjecttoexamination duringthethirdinspection interval.

2.32.3.12.4ExtentandFrequency ofExaminations Class1components, aslistedinSection4,Table1shallbeexaminedtotheextentandfrequency requiredinTableIWB-2500-1 andFiguresIWB2500throughIWB2500-20ofSectionXI.Exemption Criteria2.4.1Inaccordance withIWB-1220, certainClass1components areexemptfromexamination.

Thefollowing criteriawereappliedtoexemptcomponents fromsurfaceandvolumetric examinations inaccordance withSectionXIExemtionCriteriaCodeReference Pipingof1inchnominalpipeIWB-1220(b)

(1)size(NPS)andsmaller,exceptforsteamgenerator tubingComponents andtheirconnections IWB-1220(b)

(2)inpipingof1inchNPSandsmaller2.5Examination ofReactorCoolantPumpFlywheels TheReactorCoolantPumpFlywheels shallbeexaminedasspecified inSection11ofthisprogram.Theseexaminations shallbescheduled intheClass1sectionoftheISIprogramplan.2.6Znservice Inspection ProgramPlan(Supplement 1toAppendixB)Thisplanprovidestheexamination requirements forClass1components perthe1986EditionofSectionXI.Theserequirements shallbesatisfied duringthethirdinspection interval.

Theplanalsoshowstheresultsofexaminations performed intheprevioustwointervals.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE25of34Section1Adetaileddescription ofthecontentsoftheClass1Examination Plancanbefoundinthe"Introduction".

Thisimmediately precedesthetablesandtheisometric andcomponent

drawings, intheplan.Fromthisplan,anexamination scheduleisextracted forimplementation oftheexaminations foreachoutageofthethirdinterval.

3.03.13.1.1CLASS2PROGRAMPLANBasisforPreparation Preparation oftheClass2ISIprogramplanisbasedontherequirements ofArticlesIWC-1000andIWC-2000ofSectionXI.Thesearticlesproviderulesandguidelines forexemptions, inspection

schedule, andexamination requirements forClass2pressureretaining components andtheirintegralattachments.

3.2Components SubjecttoExamination 3.2.1Basedontherequirements ofSectionXI,Class2,nonexempt pressure-retaining components andtheirintegralattachments willbesubjecttoexamination duringthethirdinspection interval.

3.3ExtentandFrequency ofExaminations 3.3.1Class2components, aslistedinSection4,Table2,shallbeexaminedtotheextentandfrequency requiredinTableIWC2500-1andFiguresIWC2500-1throughIWC2500-13ofSectionXI.3.4Exemption CriteriaIWC-1220ofSectionXIprovidestheexemption criteriaforClass2components.

Thefollowing criteriawereusedtoexemptClass2components fromsurfaceandvolumetric examinations inaccordance withIWC-1220.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAM-FORTHE1990-1999 INTERVALREV.Section13PAGE26of343.4.1Thefollowing components (orpartsofcomponents) ofResidualHeatRemoval(RHR),Emergency CoreCooling(ECC),andContainment HeatRemoval(CHR),systems(orportionsofsystems)areexemptfromthevolumetric andsurfaceexamination requirements ofIWC-2500:

(a)vessels,piping,pumps,valvesandothercomponents 4inchesNPSandsmallerinallsystemsexceptinhighpressuresafety'injection systemsofpressurized waterreactorplants;(b)vessels,piping,pumps,valves,andothercomponents l-l/2inchesNPSandsmallerinhighpressuresafetyinjection systemsofpressurized waterreactorplants;(c)component connections 4inchesNPSandsmaller(including nozzles,socketfittings, andotherconnections) invessels,piping,pumps,valves,andothercomponents ofanysizeinallsystemsexceptinhighpressuresafetyinjection systemsofpressurized waterreactorplants;(d)component connections 1-1/2inchesNPSandsmaller(including nozzles,socketfittingsandotherconnections) invessels,piping,pumps,valvesandothercomponents ofanysizeinhighpressuresafetyinjection systemsofpressurized waterreactorplants;(e)vessels,piping,pumps,valves,othercomponents, andcomponent connections ofanysizeinstatically pressurized, passive(i.e.,nopumps)safetyinjection systemsofpressurized waterreactorplants;and(f)pipingandothercomponents ofanysizebeyondthelastshutoffvalveinopen-endedportionsofsystemsthatdonotcontainwaterduringnormalplantoperating conditions.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE27of34Section13.4.2Thefollowing components (orpartsofcomponents) ofsystems(orportionsofsystems)otherthanRHR,ECCandCHRsystemsareexemptfromthevolumetric andsurfaceexamination requirement's ofIWC-2500:

(a)vessels,piping,pumps,valvesandothercomponents 4inchesNPSandsmaller;(b)component connections 4inchesNPSsmaller(including nozzles,socketandotherconnections) invessels,pumps,valvesandothercomponents size;andfittingspiping,ofany(c)vessels,piping,pumps,valves,othercomponents andcomponent connections ofany.sizeinsystemsorportionsofsystemsthatoperate(whenthesystemfunctionisrequired) atapressureequaltoorlessthan275psigandatatemperature equaltoorlessthan200'F;and3.4.3(d)pipingandothercomponents ofanysizebeyondthelastshutoffvalveinopenendedportionsofsystemsthatdonotcontainwaterduringnormalplantoperating conditions.

Inadditiontotheexemptions ofIWC-1220, non-pipingcomponent sizeexemptions shallbeasfollows:Nonpiping components havingacumulative inletandacumulative outletnominalcrosssectionarea,neitherofwhichexceedsthenominalcrosssectionareaoftheapplicable exemption size,shallbeexemptedfromthesurface,volumetric, andvisualVT-1andVT-3examination requirements ofIWC-2500.

Theapplicable exemption sizeshallbe4"NPSforallsystemsexcepttheClass2HighPressureSafetyInjection System,whichshallbe11/2"NPS.Thispositionisbasedontheinterpretation oftheclarification madebyfootnote1ofIWC-1220ofthe1989AddendatoASMESectionXI.Forthepurposeofapplyingthiscriteria, itisassumedthattheintention oftheCodeisnottoaccumulate thecross-section areasofpipingfromdifferent fluidsystemsenteringagivencomponent (e.g.,heatexchanger shell&

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE28of34Section1tubesides),northenon-process piping(e.g.,vents,drainsandinstrumentation).

3.5Inservice Inspection ProgramPlan(Supplement 1toAppendixB)Thisplanprovidestheexamination requirements forClass2components perASMESectionXI,1986Edition,noAddenda.Theserequirements shallbesatisfied duringthethirdinspection interval.

Theplanalsoshowstheresultsofexaminations performed duringtheprevioustwointervals.

Adetaileddescription ofthecontentsoftheClass2Examination Plancanbefoundinthe"Introduction".

Thisimmediately precedesthetablesandtheisometric andcomponents drawingsintheplan.Fromtheplananexamination scheduleisextracted forimplementation oftheexaminations foreachoutageofthethirdinterval.

4.04.1CLASS3PROGRAMBasisforPreparation 4.1.1Preparation oftheClass3ISIprogramwasbasedontherequirements ofArticlesIWD-1000andIWD-2000ofSectionXI.Thesearticlesproviderulesandguidelines forexemptions, inspection schedules, andexamination requirements forClass3pressureretaining components andtheirintegralattachments.

~~

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE29of344.2Components SubjecttoExamination 4.2.1Basedontherequirements ofSectionXI,Class3nonexempt pressure-ret:aining components integralattachments willbesubjecttoexamination during:thethirdinspection interval:,

4.2.1.1OtherClass3systemsarenotsubjecttotheexamination orSystemPressureTestingrequirements ofASMESectionXIbecausetheydonotmeetthesystemfunctionrequirements ofExamination Categories D-A,D-BandD-C,where:D-ASystemsinsupportofReactorShutdownFunctionD-BSystemsinsupportofEmergency'ore Cooling,Containment HeatRemoval,Atmosphere Clean-upandReactorResidualHeat,Removal.D-CSystemsinsupportofResidualHeatRemovalFromSpentFuelStoragePool.4.3ExtentandFrequency ofExaminations 4.3.1Class3components, aslistedinTable3shallbeexaminedtotheextentandfrequency requiredinTableIWD2500-1andFigureIWD2500-1ofSectionXI.4.3.2Integrally weldedattachments shallbeexamined, utilizing theVT-3method,onceduringtheIntervalonallClass3Component Supports.

Theassociated Class3Categories havebeengroupedsincethemethodsofexamination andtheirRequirements areidentical.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE30of34Section14'Exemption Criteria4.4.1Inaccordance withIWD-l220, certainClass3components areexemptfromexamination.

Thefollowing exemption criteriawasappliedtoClass3systemsasspecified inIWD-l220:

ExemtionCriteriaSectionXIReference Integralattachments ofsupportsandrestraints tocomponents that,are4inchesNPSandsmallerwithinthesystemboundaries ofExamination Categories D-A,D-B,andD-Cshallbeexempt.fromtheVT-3examination, exceptforAuxiliary Feedwater.

Exemption fortheAuxiliary Feedwater Systemis1inchandless.IWD-l220.1 Integralattachments ofsupportsandrestraints tocomponents exceeding 4"nominalpipesizemaybeexemptedfromthevisualexamination VT-3ofTableIWD-2500-1 provided:

IWD-1220.2 (a)thecomponents arelocatedinsystems(orportionsofsystems)whosefunctionisnotrec{uired insupportofreactorresidualheatremoval,containment heatremoval,andemergency corecooling;and(b)Thecomponents operateatapressureof275psigorlessandat,atemperature or200degreesForless.

QUALITYASSURANCE MANUALGINNASTATIONAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.Section13PAGE31of"344.4.2Inadditiontotheexemptions ofIWD-1220, non-pipingcomponent sizeexemptions shallbeasfollows:Nonpiping components havingacumulative inletandacumulative outletnominalcrosssectionarea,neitherofwhichexceedsthenominalcrosssectionareaoftheapplicable exemption size,shallbeexemptedfromthesurface,volumetric, andvisualVT-1andVT-3examination requirements ofIWD-2500.

Theapplicable exemption sizeshallbe4"NPSforallsystemsexcepttheClass3Auxiliary Feedwater System,whichshallbe1"NPS.Thispositionisbasedontheinterpretation oftheclarification madebyfootnote1ofIWD-1220ofthe1989AddendatoASMESectionXI.Forthepurposeofapplyingthiscriteria, itisassumedthattheintention oftheCodeisnottoaccumulate thecross-section areasofpipingfromdifferent fluidsystemsenteringagivencomponent (e.g.,heatexchanger shell&tubesides),northenon-process piping(e.g.,vents,drainsandinstrumentation).

4.5Inservice Inspection ProgramPlan(Supplement 1toAppendixB)Thisplanprovidestheexamination requirements forClass3IWDcomponents perthe1986EditionofSectionXI.Theserequirements shallbesatisfied duringthethirdinspection interval.

Theplanalsoshowstheresultsofexaminations performed duringtheprevioustwointervals.

Adetaileddescription ofthecontentsoftheClass3Examination Plancanbefoundinthe"Introduction".

Thisimmediately precedesthetablesandtheisometric andcomponent drawingsintheplan.Fromtheplananexamination scheduleisextracted forimplementation oftheexaminations foreachoutageofthethirdinterval.

tll

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSection1PAGE32ot345.05.1CLASS1qCLASS2~ANDCLASS3COMPONENT SUPPORTSBasisforPreparation Thefollowing paragraphs (5.1through5.4)describetheInservice Inspection ProgramforClass1,2,and3component supportsfortheFirstandSecondPeriods,uptoandincluding thefirstoutage('93).Theremainder oftheSecondandThirdPeriodsshallbeinaccordance withCodeCaseN-491(forIWF-1000,

-2000and-3000)andIWFofthe'86SectionXICode.5.1.1Preparation ofthecomponent supportISIProgramwasbasedontherequirements ofArticlesIWF-1000andIWF-2000ofSectionXI.'hesearticlesproviderulesandguidelines forexemptions, inspection schedules, andexamination requirements forClass1,Class2,andClass3component supports.

Inservice testrequirements andVT-3inspection requirements forsnubbersshallbeconducted inaccordance withSection9ofthisprogramwhichimplements therequirements ofArticleIWF-2000.

5.2Component SupportsSubjecttoExamination 5.2.1Basedontherequirements ofSectionXI,nonexempt component supportsfortheClass1,Class2andClass3systemsidentified inparagraphs 2.2,3.2and4.2ofthissectionshallbesubjecttoexamination duringthethirdinspection interval.

Thecomponent supportsrequiring examination shallbeasfollows:5.2.l.lPlateandShell-Type SupportsSupportswhicharefabricated fromplateandshellelements, suchasvesselskirtsandsaddles,andarenormallysubjected toabiaxialstress.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSection13PAGE33of345.2.1.2Linear-Type SupportsSupportsactingunderessentially asinglecomponent ordirectstress.Suchelementsmayalsobesubjected toshearstress.Examplesofsuchstructural elementsare:tensionandcompression struts;beamsandcolumnssubjected to,bending;trusses;frames;arches;rings;andc'ables.5.2.1.3Component StandardSupportsAsupportassemblyconsisting ofoneormoregenerally mass-produced unitsusuallyreferredtoascatalogitems.ExamplesofsuchitemsareshowninFigureIWF-1210-1 ofSectionXI.5.35.3.1ExtentandFrequency ofExamination Component supportsselectedforexamination shallbethosecomponents requiredtobeexaminedundertherequirements of2.3,3.3and4.3,IWF-2500.

Theinservice test,requirements ofArticleIWF-5000shallbesatisfied bytherequirements ofSection9ofthisprogram.5.3.1.1Class3component supportscontaining integrally weldedattachments shallbeexamined, utilizing theVT-3method,onceduringtheInterval.

Theassociated IWFcategories havebeengroupedsincethemethodsofexamination andassociated Requirements areidentical.

5.3.25.3.3Inaddition, snubbersshallbefunctionally testedatthefrequency requiredbySection9ofthisprogram.Onpipingsystemswhereapipingseismicanalysisboundaryisbeyondthesafetyclassboundary, thecomponent supportswithintheportionbetweenthosetwoboundaries shallbeexamined.

Theextentoftheseexaminations shallbeconsistent withtheexamination requirements ofthatsafetyclasssystem.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALREV.3PAGE34of34Section15.3.45.45.4.15.4.2HighEnergyPipingComponent SupportsshallbeexaminedtoIWC-2500CategoryC-CandtoIWF-2500inanAugmented Program.Exemptions ASMESectionXI,1986Edition,noAddenda,doesnotcontaindefinedexemption criteriaforcomponent supports.

Exemption criteriaspecified inIWB,IWCandIWDhavebeenused.5.5Inservice Inspection ProgramPlan(Supplement 1toAppendixB)Thisplanidentifies andincorporates theappropriate component supportsintotheClass1,2,and3sectionsoftheexamination plan.Theserequirements shallbesatisfied duringthethirdinspection interval.

Theplanalsoshowstheresultsofexaminations performed intheprevioustwointervals.

QUALITYASSURANCE MANUALGINNASTATIONSection2EFFECTIVE DATE:PAGE1of39December31,1993ROCHESTER GAS&ELECTRICCORPORATION SIGNATURE DATETITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREQUESTSPREPAREDBYQUALITYASSURANCE APPROVEDGY1.0Introduction:

General:Inaccordance with10CFR50.55a(g)

(5)(iv),Rochester Gas&Electrichasrequested relieffromthoseASMESectionXIrequirements thathavebeendetermined impractical forcertainareas.Thissectionidentifies eachactiveandownerwithdrawn ReliefRequestsubmitted totheNuclearRegulatory Commission fortheirconsideration andacceptance.

Table1providesinformation inasummaryformatforbothactiveandwithdrawn reliefrequestsapplicable toR.E.GinnaNuclearPowerPlant.Following Table1,detailedReliefRequestsarelisted.Theseprovideinformation onthecomponent forwhichreliefisrequested, ASMErequirements, proposedalternate method,andotherpertinent information, asneeded.Existingactivereliefrequestscanbewithdrawn bytheowneratanytime.Additional reliefrequestswillbesubmitted totheNuclearRegulatory Commission, asappropriate.

c QUALITYASSURANCE MANUALGINNASTATIONTITLEIAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE2of39Section2TABLEISUMMARYOPRHJFPRRebelRequestNumberSectionXIRefesence IWB.2500.1 Cat.B.AComponent RPVShcUtoBangeWeMASMERequiscment forWhichReliefisRequested Volumetric Examination duringtwodUferentpcAodsReasonforReliefRequestToperformaUexaminations assoriatcd withtheSheU.toBangeduringthesamepcskxLProposedAkemateExamination PerformaUexaminations associated withtheSheUaoRangeatorneartheendoftheinterval.

IWB.2500.1 Cat.B-DRPVNozxlcto-Vcsscl WeMsVolumetric Examinadon duringtwodifferent pcAods.ToperformaUexaminations assocktcd withtheNosxk.to.

VesselwcMsduringthesamepcsloLPerformaUcxaminatkins associated withtheNoxxkto.Vessel weMsatorneartheendofthelntervaLIWA.1400Inspection huthorixed Inspection Agency.Useof'huthorixed Agency'cw YorkStatehasnotendorsedASMECodesanddoesnothaveanAuthorixcd Inspection Agency.UseR.E.CinnaQualityAssurance Pmgram.4(')IWB.2500ICat.B.LIB-L2ReactorCoolantPumpCaseWeMsandIntervals.

Volumetric Examinatkn ofeaseweMsandvisualofintemab.PumpmateriaiandconBgumtion.

Hydsostatie test,surfaceandvisualexamsofoutsidesurfaces.

IWB-2500ICat.BM.2ChssIValvesCreatcrthanNPS4.VisualExamination ofvalwintemds.Excessive radiation exposuseandhistorical reliability ofvalves.ExaminevalveIntcmakwhendisassembled formaintcnanee.

IWD2500-1Cat.D.BIWC5222(a)Rsdioanive WasteHoMupTank,ChargingPumpsVisualBueucadon athydsostade prcssure.

VisualExamination at3420psigHydrostatic Pressure.

TankwUIberenderedinoperatiw duringtests.Pumpshavemaximumpressurelimitonthescab.Performvisualexamination eachperiodatnoAnalopcradngprcssure.

PerformHydroTestandvisualat2400psig.IWC5222(a)ValvesPCV430andPCV431C.VisualExasninadon atHydrostatic Pressure.

Valvediaphragms cannotwithstand TestPrcssure.

Hydrostatic TesttoFkxConnection operatediaphragm pcrvalvetestrequirements andpcrfonnInsesvice visualexamination onceperperiod.10(')IWC5222(a)IWD-5223(a)

IWD.5223(a)

Secondary Sideofsteamgenerator andassoriatcd mainsteampiping.StandbyAuxiliary PumpRceiscuLUnefromAOV9710A,AOV9710Bandthekassoei.atcddownstream Roworifices.

BoricAcidFilterandassoriatcd pipingbetweenValves347,348Aand349A.VisualExamination atHydrostatic Pressure.

VisualExamination atllydsostatie Pressure.

VisualExaminatkn atHydrostatic Pressure.

RCBEadoptedpressuredifferential limitadon of800psigtopreventprimarysidetubesheetchddingscpamtiolL PressureRedunknBowOriTicerequiresremovalandbiank4sff.

SystempipingdocsnotprovMelsolatkntocondcmate supplyrank.SigniTicant tankreduction wouMbcrequiredforremovalandiscomidered impractkai.

TestPrcssurerequiredwillexceedlimitsforsafeworkingpressureonBoricAcidFil(crHousingFhngeCmkets.Hydrostatk Testat1.10timesinsteadof1.25Psvsettingandperformvisualcxammatfoiu PerformInservice VisualExamination onceperperiosLPerformInservice VisualExamination onceperperiod.(v)~WillIDRAWN QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE3of39Section2TAB!XISUMMARYOFRFJJFPRURISReliefRequestNumberSectfonXIReference ASMERequirement forWhichRriiefkRequested ReasonlorReliefRequestProposedAlternate Examination 12.1IWD-5223(a) hirStanforDieselGenerator htciuding ReceiverTanksandPiping.VisualExaminatkn atHydrostatic Pressure.

AirStartPressureTestwouMfcqiilfctclndnatlon pfioftofcacMngengineskidtoprecludeaktoairstanmotors,kavtngportionofpfpinguntestable.

PerformInseivkeExamination onceperperiodandonceeachquarteraprcssuredecaytestperformed oiiairrcccivcl; IWD-5223(a)

IWD.5223(a)

FuelOilTransferPumpsandassoriated plpuigtotert(dr(all atOilStorageTankJacketCoolingWaterSystemandassociated pipingtoterminals atWaterExpansknTanks.VisualExaminarion atHydrostatic Pressure.

VisualExamination atHydrostatic Prcssure.

RequireshohtknofDieselOilStorageandDryTankwherenomeansofkola(ionkprovidedatTransferpumpdischarge pipingwithtanksventedtoatmosphere.

CoolingWaterExpansion Tankventedtoaunosphcre requiring isoktknwithvastpipingInvolvedwillbeunabletoprcssurixc PerformsystemFunctional Tesringwithassockted VisualExamination onceperperiod.PerformSystemFunctional Testingwithassociated VkualExamination oncepcfpcfiud.13(111)TableIVC2500I,CategoryCHCkss2PipingPen((rath(3 containment vesselwithbalanceofpipingsystemoutskleSectionXIscope.UnderRevision.

15(')IWC.2500Cat.CF-I&CF-2l(emsC5.10andC5.50resp.Ckss3PonionoftheservkewatersystemQass2PipingWeMsc3/8'ondnal wallthkknemforpiping>NPSC.VisualExamination atHydrostatic Pressure..

PipingWeMsc3/8'ominal wallthickness dono(requiresurfaceandvolumetric examinanons.

Ilydrostatic Tesungisimpra(tical duetosystemdesignthatisopenwnded andempkyingbutterily valvesthatwcfcnotdcsigncdtoprovideakaktightboundary.

Atamhdmumterminalconnection weMsofidcntilied exemptedweMspcrItemsC5.10andC5.50ofTabkIWC2500shouMbeexaminetk PerformInservice VisualExamination onceperperiod.SurfaceandVolumetric Examinations ontcmunalconnection weMSofMen(ipcdexemptedweMSshallbeperformed totherequirements ofIWC.25001.IWB-2500Cat.8K.lItemB10.10andIWC.2500,Cat.CC,l(emC3.20QassI&2!ntcgral Attachment onpipingspeciTically supportAttachments.

Volumetric orsurfaceexamination onQassIIntegralAttachments isrequiredonBaseAttachment

>5/8.Qass2requiresasUrfaccexamination onBaseAttachments

>3/0'.IntegtulAttachments onCkssI&2supponattachments shoUMhaveasUffaccexamination toinsuresafetyandsystemintegrity.

OnCkssI&2Integralhnachmcnts, asurfaceexamination shallbeperformed onsupponattachments toIWBandIWC-2500requirements.

I9IVC2500CategoryCB,ItemsCol&C2.22Pulsation

Dampener, NosskWeM&InsideRadius.Applicable Surfaceand/orVolumetric Examinations.

Physicalconfiguration notconducive forfullExamination coverage.

PerformSurfaceand/orVolumetric Examination toMaximumextentpractkaL(')"(1~1)~

'4N'I1 QUALITYASSURANCE, MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTXNSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISXRELIEFREUESTSREV.Section23PAGE4of39ReliefRequestNumberSectionXIReference Component TABIX1SUMMARYOPRHIKFmSlSASMERequirement forWhichReliefisRequested ReasonforReliefRequestProposedAlternate Examination 23(~)IWAA400Chss3Valves:V~VMIIVMI3V~V~VA738V.4739VA760llydrostatie TestingofCodeImpraetieality Rephcement Activities.

ASMESectionIIINDEwithPTofRootPass.PerformaVT.2leakTest.ThisReliefisaone-time'se only.24(~)IWA-4400Class3VrdvcstVMI3V.4027V4020V~Ifydrostatic TestingofCodeImpractkality Replacement Activities.

ASMESectionIIINDEwithPTofRootPass.PcrfonnaVT2leakTest.ThisReliefisaone-timeusconly.(~)~ONETIMEUSEONLY.

tAI QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSSection2PAGE5of39RELIEFREQUESTNO.1DEFERRPVEXAMINATIONS TOENDOFINTERVALComponents forWhichReliefisRequested:

Thecomponent forwhichreliefisrequested istheReactorPressureVessel(RPV)Shell-to-Flange Weld.ASMERequirement fromWhichReliefisRequested:

TableIWB-2500-1, Examination CategoryB-A,requiresthattheRPVShell-to-Flange weldbeexaminedduringthefirstandthirdperiodsinconjunction withthenozzleexaminations, withatleast50percentexaminedduringthefirstperiodandtheremainder bytheendofthethirdperiod.TherequiredShell-to-Flange examination isimpractical ifperformed duringtheperiodsspecified asitcanonlybeaccomplished fromtheflangesurface.III.ProposedAlternate Method:Duringthefirsttwoinspection intervals, 100percentoftheaccessible lengthoftheRPVweldsincluding theShell-to-Flange weldwereexaminedatorneartheendoftheintervalwhentheentireexamination couldbeperformed fromboththeflangesurfaceandthevesselwall.Thisisamorepractical approachinthattherequiredexaminations frombothsurfacescanbeperformed atthesametime.Duringthethirdinterval, 100percentoftheaccessible lengthofallRPVweldsincluding theshell-to-flange weldwillbeperformed atorneartheendoftheintervalwhenalltherequiredexaminations canbeperformed atthesametime.

I QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE6of39RELIEFREQUESTNO.2DEFERRPVNOZZLEEXAMINATIONS TOENDOFINTERVALComponents forWhichReliefis'equested:

Thecomponents forwhichreliefisrequested aretheRPVNozzle-to-Vessel weldsandNozzleInsideRadiusSections.

ASMERequirements forWhichReliefisRequested:

TableIWB-2500-1, Examination CategoryB-D,ItemB3.90,Nozzle-to-Vessel weldsallowspartialdeferral.

"Ifexaminations areconducted frominsidethecomponent andthenozzleweldisexaminedbystraight.

beamultrasonic methodfromthenozzlebore,theremaining examinations requiredtobeconducted fromtheshellinsidediametermaybeperformed atorneartheendofeachinterval."

Examination CategoryB-D,Item3.100NozzleInsideRadiusSections, doesnotallowdeferraltotheendoftheinterval, andrequires(footnote 2)25percentto50percentofthenozzlestobeexaminedduringthefirstperiod,withtheremainder tobeexaminedattheendoftheinterval.

Examinations fromthenozzleboreandnozzleinsideradiusexaminations canonlybeperformed ontwo(outlets) ofthesixmajornozzleswithoutremovalofthecorebarrel.Themechanized examination ofthetwoaccessible nozzleandinsideradiussectionsisquiteexpensive, andthenozzle-to-vessel examination isonlyapartialexamination fromthenozzlebore.Fromatechnical positionconsidering theprogresswhichisbeingmadeinultrasonic examination equipment andtechniques andforthecorrelation ofdataobtainedfromtheborewiththatobtained, fromtheshell,itishighlydesirable toperformbothexaminations atthesametime.III.ProposedAlternate Method:Rochester Gas&Electric(RG&E)proposestoperformbothnozzle-to-vessel examinations (fromthenozzleboreandfromtheshellinsidediameter) atorneartheendoftheinterval.

Thenozzleinsideradiusexaminations willalsobeperformed atthistime.Thismorepractical approachwillallowalltherequiredexaminations tobeperformed atthesametimeonallthenozzlesandnozzleinsideradii.

ItII'tI QUALITYASSURANCE

'ANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE'990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE7of39WITHDRAWN RELIEFREQUESTNO~3UUSEOFAUTHORIZED INSPECTION AGENCYExamination Requirement forWhichReliefisRequested:

TheASMEBoilerandPressureVesselCode,SectionXI,1986Edition,IWA-1400(f),

requiresanarrangement withanAuthorized Inspection Agencytoprovideinspection services.

Inaddition, theCoderequiresthatcertainadministrative functions beperformed bythe"Enforcement Authority" and"Authorized NuclearInservice Inspector".

ProposedAlternative:

GinnaStationislocatedinthestateofNewYork.ThisstatehasnotendorsedASMECodesandtherefore doesnotprovideadministrative organization andcontrolssuchas"Enforcement Authority",

"Authorized NuclearInservice Inspector" and"Reporting Systems".

However,GinnaStation's QualityAssurance Programdoesprovideequivalent administrative control.Therefore, RG&ErequeststhatGinna'sStationQualityAssurance ProgrambeusedinlieuofCodeadministrative functions.

Rochester Gas&Electric's programfortheinservice inspection, governedbytheR.E.GinnaStationQualityAssurance Manual,containstherequirements andresponsibilities forimplementation oftheprogramandprocedures.

Theprocedures havebeenpreparedandapprovedbytheresponsible organizations withinRochester Gas&Electric(e.g.,GinnaStation,Engineering, Materials Engineering andInspection

Services, ElectricMeterandLaboratory andPurchasing).

Approvedprocedures willbeimplemented tocontrolthestandards forexamination evaluation.

Theseprocedures includetheidentifications oftheorganization performing theinspection, description ofthemethodofinspection tobeused,acceptance andrejection

criteria, andrequirements forproviding evidenceofcompletion andcertification oftheinspection activity.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREQUESTSREV.Section23PAGE8of39WITHDRAWN RELIEFREQUESTNO.3(Con't)Inaddition, procedures aredeveloped byGinnaStationtoprescribe thedisposition ofnonconformances.

Theprocedures implemented fortherepairs,theretestprocedures andthetestresultswillbereviewedbythePlantOperating ReviewCommittee.

Themembersofthiscommittee includetechnically qualified staffpersonnel.

Examination techniques havebeenestablished inaccordance withwrittenrequirements andincorporated intowrittenprocedures.

qualifications fornondestructive testpersonnel areincompliance withRegulatory Guide1.58,"Qualification ofNuclearPowerPlantInspection, Examination andTestingPersonnel."

Recordsandreportsoftheinservice inspection willbedeveloped andmaintained byRochester GasandElectricandincludesuchitemsasexamination plansandschedules, examination ofresultsandcorrective actions.Thefunctions oftheauthorized nuclearinservice inspector, namelytheirreviewandverification ofinservice examinations, personnel qualification andequipment certification duringtheannualoutagesatGinnaStationwillbeperformed bypersonnel oftheHartfordSteamBoilerInspection andInsurance Company.Thequalifications oftheinspectors, inspections specialists andinspection agencyareincompliance withtheCode.

IttIIt QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE9of39WITHDRAWN RELIEFREQUESTNO.4RCPCASINGWELDSVOLUMETRIC ANDINTERNALEXAMINATION Components forWhichReliefisRequested:

Eachofthe27.5inchdiameterrecirculation loopsatR.E.GinnahasaClass1ReactorCoolantPump.Thefunctionofthesetwopumpsistoprovideforcedcirculation throughtheRPVcoreduringnormalreactoroperation.

CodeRequirement forWhichReliefisRequested:

TableIWB-2500-1, Examination Categories B-L-landB-L-2requirevolumetric examination ofcasingweldsandvisualexamination ofinternalpressureboundarysurfacesofonepumpcaseineachofthepumpgroupsperforming similarsystemfunctions eachinspection interval.

Theseexaminations areimpractical forthereactorcoolantpumpsatGinnaStationandreliefis,therefore, requested.

A.Supporting Information Thetworeactorcoolantpumps(RCP)forR.E.GinnaareWestinghouse Model93pumps.Eachpumpcasingisfabricated byweldingfourstainless steel(SA351CF8)castingstogether.

Thus,thereare3circumferential pressure-retaining weldsthataretobevolumetrically inspected inaccordance withCategoryB-L-l.2.Theunsuitability ofultrasonic examination wasdemonstrated duringthe"A"reactorcoolantpumpexamination in1980.Anattemptwasmadetodetermine thewallthicknesses usingultrasonic examination,'he casingweldsmustbeinspected usingtheminiature linearaccelerator (MINAC).3.Radiographic examination usingtheMINACwasperformed ontheR.E.Ginna"A!'CPduringtheSpring1981refueling outage.Inaddition, thesametypeofexamination hasbeenperformed atseveralothersites.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE10of39WITHDRAWN RELIEFREQUESTNO.4(Con't)Thisexamination wasperformed byplacingtheMINACinsidethepumpcasingandplacingthefilmontheoutsideofthepump.Toperformtheexamination, thepumpwascompletely disassembled.

Disassembly tothisextentisfarbeyondanydisassembly expectedforthisexamination.

Also,insulation onthecasingexteriorwasremovedforfilmplacement.

Additionally, thepumpbowlmustbedryforinstallation oftheMINAC.Therefore, allfuelassemblies wereremovedfromthereactorvesselandthevesselwaterlevelloweredtobelowthenozzles.Completedisassembly ofthepumpwasalsorequiredtoconducttheVT-lexamination inaccordance withCategoryB-L-2.4~NoproblemshavebeenfoundwiththeweldsatR.E.Ginnaorothersites.Additionally, noproblemshavebeenfoundduringtheCategoryB-L-2visualexamination.

Thevisualexamination wasconducted at,R.E.Ginnaby"usingthevideocameraontheMINAC.Thewholebodyexposuretopersonnel duringtheSpring1981directlyattributable totheRCP"A"examinations 93,067millirem.

Thisdoesnotincludethedosereceivedduringthecompletecoreunloadtogettheplantincondition fortheRCPdisassembly.,

5.Thenuclearindustryhasbeensuccessfully applyingleak-before-break conceptstoprimaryloopandClass1auxiliary pipingsystemsofcommercial nuclearpowerplants.Currently, theanalysessupporting suchconceptscomesunderthereviewoftheNuclearRegulatory Commission byGeneralDesignCriteria-4 (GDC-4).

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE11of39Section2RELIEFREQUESTNO.4(Con't)Thereareeightdifferent modelsofRCP'sinWestinghouse-type PWRs.Model93methodology usedintheanalysesisconsistent withthatrecommended inNUREG1061,Vol.3andGDC-4.AfiniteelementstressanalysismodelfortheModel93pumpwasdeveloped.

TheRCPcasingsarecaststainless steel.Thechemistries ofeachheatofmaterialusedinthe=pumpswereusedtodetermine thefracturetoughness.

Thephenomenon ofthermalagingwasaddressed.

Theprogramsuccessfully demonstrates thatleak-before-break analysesareapplicable toallprimarypumpcasingsofallWestinghouse designPWRsforwhichthescreening loadsarereasonably applicable andthefracturetoughness areknown.6.Webelievethatperforming avolumetric examination oftheGinnaStationUnit1RCPcasingweldsandavisualexamination oftheinteriorpressureretaining surfaceofonepumpduringthethirdlO-yearinspection perioddoes.notprovideanincreaseinsafetyandexpectedradiation exposure.

Thefollowing itemshavebeenconsidered:

a~b.Visualexamination (VT-2)oftheexteriorofallpumpsduringthehydrostatic pressuretestrequiredbyTableIWB2500-1CategoryB-P.PerformaVisualexamination (VT-l)oftheexternalsurfaces'of theweldsofonepumpcasing.coPerformavisualexamination (VT-3)oftheinternalsurfaceseachtimepumpdisassembly isrequiredformaintenance.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE12of39WITHDRAWN d.RELIEFREQUESTNO.4(Con't)Performanevaluation todemonstrate thesafetyandserviceability ofthepumpcasing.Theevaluation willinclude:Establishing materialproperties including fracturetoughness values.(ii)Performing astressanalysisofthestructure.

(iii)(iv)(v)Reviewing oftheoperating historyofthestructure.

Selection oflocations forpostulating flaws.Determination ofaflawsizeresulting inthedetectable leakrate(vi)(vii)Establishing thestability oftheselectedflaw.Demonstration thatapostulated through-wall flawwhichyieldsdetectable leakageremainsstableforalldesignloadings, withamarginof2onflawsize.NOTE:Inmakingthisassessment, thermalagingembrittlement andanyotherprocesses whichmaydegradetheproperties ofthepumpcasingduringservicewillbeconsidered.

jVP QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE13of39Section2RELIEFREQUESTNO.5VISUALINTERNALEXAMINATION OFCLASS1VALVESComponents forWhichReliefisRequested:

Class1valvesrequiring valvebodyinternalVTexamination.

Size~Xn.1010101010101010ValveNo.842A842B867A867B700701720721853A853B852A852BMFGTeDarling/Check Darling/Check Darling/Check Darling/Check Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Check Velan/CheckVelan/Gate Velan/Gate LineNo.10A-SI2-1502-A 10A-SI2-2501-B 10A-SI2-2501-A 10A-SI2-2501-B 10A-RC02501-A 10A-RCO-2501-A 10A-RCO-2501-B 10A-RCO-2501-B 6A-RC-2501-A 6A-RC-2501-B 6A-RC-2501-A 6A-RC-2501-B II.ASMERequirement, forWhichReliefisRequested TableIWB-2500-1, Examination CategoryB-M-2,requiresaninternalVT-3examination onatleastonevalvewithineachgroupofvalvesthat.areofthesamesize,constructional design(suchasglobe,gateorcheckvalves)andmanufacturing method,thatperformsimilarfunctions inthesystem.Thisreliefrequestisbasedonthefollowing points:tocompletethesubjectexamination, unnecessary expenditures ofman-hours andmanremarerequiredwithessentially nocompensating increaseinplantsafety,and QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE14of39RELIEFREQUESTNO.5(Con't)2.thestructural integrity affordedbyvalvecasingmaterialutilizedwillnotsignificantly degradeoverthelifetimeofthevalve.BasedondatacompiledfromaplantsimilarinageanddesigntoGinnaStation,itisexpectedthatapproximately 100manhoursand5manremexposurewouldberequiredtodisassemble, inspect,andreassemble thesevales.Performing thisvisualexamination undersuchadverseconditions, highdosesrate(30-40R/hr),andpooras-castsurfaceconditions, realistically provideslittleadditional information astothevalve'scasingintegrity.

Thevalvesmaterial, ahigh-strength caststainless steel(ASTMA35l-CF8),

iswidelyusedinthenuclearindustryandhasperformed extremely well.Thepresenceofsomedeltaferrite(typically 54ormore)substantially increases resistance tointergranular stresscorrosion cracking.

Thedeltaferritealsohelpsthematerialtoresistpittingcorrosion inchloridecontaining environments.

RG&Efeelsthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatthepublic'shealthandsafetywillnotbeadversely affectedbynotperforming avisualexamination ofthevalveinternalpressureboundarysurfaces.

Additionally, thisvisualexamination addslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonnel tounnecessary radiation exposure.

Therefore, arequestforrelieffromthisrequirement issought.III.ProposedAlternative Method:A'sstatedabove,RG&Edoesnotbelievethatthevisualexamination requiredeachten-yearintervaliswarranted.

However,asstandardmaintenance practicedictates, whenthesevalvesaredisassembled formaintenance

purposes, avisualexamination oftheinternals andinternalpressureboundarysurfaceswillbeperformed, totheextentpractical.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREOUESTSREV.Section23PAGE15of39WITHDRAWN RELIEFREQUESTNO.6HYDROSTATIC TESTINGOFRADIOACTIVE WASTEHOLDUPTANKComponent forWhichReliefisRequested:

Theradioactive wastehold-uptankinthewastedisposalsystemprovidesameansofstoringcontaminated waterthathasbeenusedintheoperation ofthenuclearpowerplant.Thewastedisposalsystemandwastehold-uptankmayberequiredtofunctioninallmodesofreactoroperation including coldshutdownandrefueling.

II.ASMERequirement forWhichReliefisRequested:

TableIWD2500-1,Examination CategoryD-B,ItemNo.D2.10,requiresVT-2examination ofthewastehold-uptankathydrostatic testinglevels(atleast1.10systempressure) duringeachintervalaswellasVT-2examinations atnominaloperating pressureduringeachperiod.Thedesignofthewastedisposalsystemissuchthatcontaminated waterisstoredinthewasteholduptankuntilsuchtimeasthelevelofcontamination isbelowthelimitsfordischarge.

Atthistimetheholduptanksmaybeunavailable forusebyemptyingthestoredliquid.Severalimportant systemswithinthechemicalvolumeandcontrolsystemdrainintothewastedisposalsystemhold-uptanks.Thesearethevolumeandcontroltankdrains,reactorcoolantletdownsystem,reactorcoolantdraintankdischarge, andthedemineralizer systemdrains.Ifthetankwastobehydrostatically testedbyfillingitwithwaterandpressurizing to1.10systempressure, thehold-uptankwouldberendereduseless.Theplantwouldthenbepotentially putintoanunsafecondition foranyabnormalplantfunctionandifstartupoccurredwithoutaholduptankbeingavailable.

fC QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE16of39Section2WITHDRAWN RELIEFREQUESTNO.6(Con't)Sincethishold-uptankconstantly storesliquid,anydegradation ofthetankmaterialwouldshowuppriortoitbecomingaproblem.RGGEbelievesthathydrostatically testingtherad-waste hold-uptankputsGinna'splantinanunsafecondition andtherefore arequestforrelieffromthisrequirement issought.III.ProposedAlternative Method:AVisualVT-2examination shallbeperformed onceeveryperiodwiththesystematnormaloperating pressuretoverifycontinued structural integrity.

'\

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFOR,THE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE17of39Section2RELIEFREQUESTN0.7REDUCEDHYDROSTATIC PRESSURETESTINGOFCHARGINGPUMPSDISCHARGE PIPINGComponents forwhichReliefisRequested:

CVCS,ThreeChargingPumpsandDischarge PipingtoDischarge Isolation Valves.ASMERequirements forwhichReliefisRequested:

IWC-5222(a)

SystemHydrostatic Test;Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200F(93C)orless,andatleast1.25timesthesystempressurePsvforsystemswithDesignTemperature above200F(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Thiscorresponds toatestpressureof3420psig.Thechargingpumpshaveaminimumhydrostatic testpressurelimitation onthesealsof2400psig,asspecified bythepumpmanufacturer.

Asaresult,thepumpsandassociated discharge pipingtothefirstisolation valvescannotbetestedtotherequiredCodeTestPressure.

III.,Proposed Alternate Method:Duringthehydrostatic testandassociated VT-2examination, thechargingpumpsandassociated discharge pipingtothefirstisolation valveswillbetestedatapressureof2400psig.

QUALITYASSURANCE MANUALGXNNASTATXONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE18of39RELIEFREQUESTNO.8ALTERNATIVE TESTINGOFRCSOVERPRESSURE PROTECTIONS NITROGENACCUMULATOR SYSTEMOFVALVESPCV430&PCV431CX.Components forWhichReliefisRequested:

RCSOverpressure Protection NitrogenAccumulator SystemValvesPCV430andPCV431CIX.ASMERequirements forWhichReliefisRequested:

IWC-5222(a)

SystemHydrostatic Test;Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200'F(93C)orless,andatleast1.25timesthesystempressurePsvforsystemswithDesignTemperature above200F(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Thiscorresponds toatestpressureof137.5psig.Thediaphragms intheoperators ofthesubjectvalvesareonlydesignedtowithstand amaximumpressureof105psig,andtherefore cannotbetestedtotherequiredCodetestpressure.

lXIX.ProposedAlternate Method:TheRCSoverpressure nitrogenaccumulator syst:emwillbetestedtotheCoderequirements uptotheflexconnection tothevalveoperator.

Operability ofthediaphragm andoperatorisverifiedbyvalvetestingrequirements.

Inaddition, aninservice pressuretestatoperating pressurewillbeperformed onceeachinspection periodonthepiping,including thediaphragm.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE19of39RELIEFREQUESTNO~9REDUCEDHYDROSTATIC TESTOFTHESTEAMGENERATOR SECONDARY SIDEComponents forWhichReliefisRequested:

MainSteamSecondary SideofSteamGenerator andDownstream PipingtoClassBoundary.

ASMERequirement fromWhichReliefisRequested:

IWC-5222(a)

SystemHydrostatic Test;Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200'F(93C)orless,andatleast1.25timesthesystempressurePsvforsystemswithDesignTemperature above200oF(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Sincethedesigntemperature oftheMainSteamsystemisgreaterthan200F,thetestpressureisrequiredtobe1.25timesPsv,or1356psig.Apressuredifferential limitation of800psigbetweentheprimaryandsecondary sideoftheSteamGenerator hasbeenadopted.Thiswasestablished earlyinplantlifeduetotheexperiences ofsomeplantswithprimarysidetubesheetcladdingseparation.

Tomaintainthis800psigdifferential, andtherequiredpressureonthesecondary side,theprimarysystemmustbeheateduptoaminimumof160'Fwhichwouldresultinaproblemwithheatbalanceandapotential operational problemduringimplementation ofthetestprocedure.

Theadministrative controlsnecessary toassureaproperandsafetestandthecomplexity requiredforthetestprocedure resultinasituation thatshouldbeminimized.

InadditiontotheSectionXIvolumetric andsurfacesexamination requirements, thepipingispartoftheaugmented inspection programsinceitfallswithinthehighenergybreakcriteria.'

QUALITYASSURANCE MANUALGXNNASTATIONTITLEAPPENDIXBR.E.GXNNANUCLEARPOWERPLANTXNSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALXSIRELIEFREUESTSREV.Section23PAGE20of39RELIEFREQUESTNO.9(con't)Aletterwassubmitted toDennisL.Ziemann.ChiefOperating ReactorBranch¹2,USNRC,Dated:November8,1979,requesting relief.

Subject:

SystemPressureTestRestriction forSteamGenerator andassociated Feedwater andMainSteampiping,R.E.GinnaNuclearPowerPlant¹1,DocketNo.50-244.III.ProposedAlternate Method:Testthesecondary sideoftheSteamGenerator andassociated MainSteampipingatapressureof1194psig,whichcorresponds to1.10timesthePsvsetting.Thesecomponents areinsidecontainment andanysignificant leakagewouldbedetectedbyvariousleakagemonitoring systemsduringplantoperation.

IIII QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E-GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE21of39Section2WITHDRAWN RELIEFREQUESTNO.10ALTERNATIVE HYDROSTATIC TESTINGOFSTANDBYAUXILIARY PUMPRECIRCULATION LINEI.Component forWhichReliefisRequested:

Feedwater, StandbyAuxiliary Pumprecirculation linebetweenAOV9710A,AOV9710Bandtheirassociated downstream floworifices.

I.ASMERequirement fromWhichReliefisRequested:

IWD-5223(a)

SystemHydrostatic Test;Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200F(93C)orless,andatleast1.25timesthesyst:empressurePsvforsystemswithDesignTemperature above200F(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted "forPsv.Inordertohydrotest thispipingtoSectionXIrequirements, thepressurereducingfloworificesdownstream ofAOV9710A&Bwouldrequireremovalandblankflangesinstalled.

Systempipingdoesnotprovideanisolation valvebetweentheorificesandtheCondensate SupplyTank.Asignificant reduction intanklevelwouldberequiredtofacilitate orificeremoval,whichisconsidered tobeimpractical.

II.ProposedAlternate Method:TheClass3portionofthispipingshallbeVT-2examinedatoperational discharge pressureduringfunctional testingwhichisperformed onceeachperiod.

va QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE22of39Section2RELIEFREQUESTNO.11ALTERNATIVE HYDROSTATIC TESTINGOFBORICACIDFILTER&ASSOCIATED PIPINGI.Component forWhichReliefisRequested:

CVCS,BoricAcidFilter(CSFLBA)andallpipingbetweenvalves347,348Aand349A.ASMERequirement fromWhichReliefisRequested:

IWD-5223(a)SystemHydrostatic Test:Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200'F(93C)orless,andatleast1.25timesthesystempressurePsvforsystemswithDesignTemperature above200'F(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted forPsv.Thehydrostatic testpressurenecessary tosatisfySectionXIrequirements willexceedthelimitsforthesafeworkingpressureontheBoricAcidFilterhousingflangegaskets.ProposedAlternate Method:TheBoricAcidFilterandassociated pipingshallbeVT-2examined, atfulloperational pressureduringinservice testingwhichshallbeperformed onceeachperiod.

1 QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE23of39Section2RELZEFREQUESTNO12ALTERNATIVE HYDROSTATIC TESTINGOFTHEEMERGENCY DIESELGENERATOR COMPONENTS

&ASSOCIATED PIPINGI.Component forWhichReliefisRequested; Emergency DieselGeneration:

2.3.StartingAirincluding receivertanksandassociated piping.FuelOilTransferpumps,suctionanddischarge including miscellaneous linesterminating atoilstoragetanks.JacketCoolingWatersystemincluding miscellaneous lineterminating atcoolingwaterexpansion tanks.II.ASMERequirement fromWhichReliefisRequested:

IWD-5223(a)

SystemHydrostatic Test;,The systemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200'F(93C)orless,andatleast1.25timesthesyst:empressurePsvforsystemswithDesignTemperature above200F(93C).ThesystempressurePsvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)not.providedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted forPsv.Onlyportionsofthepipingassociated withthecomponents

'identified abovearecapableofbeingpressuretested.TheAirStartSystempressuretestwouldrequiretermination priortoreachingtheengineskidtoprecludeadministrating airto'theAirStartMotors.ThiswouldleavethatportionofpipingbetweentheAirStartMotorstothefirstisolation, priortoreachingtheengineskid,untestable.

(rIE' QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE24of39RELIEFREQUESTNO.12(Con't)TheDieselFuelOilTransfersystemwouldrequireflangeconnection disassembly andtheinstallation ofblindflangestoisolatetheDieselOilStorageTank,whichisventedtoatmosphere, andtheDayTankwherenomeansisprovidedtoisolatethetransferpumpdischarge pipingatapointclosetothedaytank.Additionally, theoverflowpipingfromthedaytanktothestoragetank,whichisidentified asClass3,hasnoisolation valvesinstalled andisventedtotheatmosphere.

TheJacketCoolingWaterSystemwouldrequireisolating theCoolingWaterExpansion Tank,duetoventstotheatmosphere, whichwouldincludemostofthepipingsubjecttopressuretesting.Duetotheamountofpipingwithintheclassboundarywhichisunabletobepressurized, testinginaccordance withSectionXIrequirements wouldnotprovesystemintegrity overandabovetheexistingSurveillance Inservice andFunctional Testing.ProposedAlternate Method:Inservice Testingshallbeperformed ontheAirStartSystematleastonceeachperiodinaccordance withtherequirements ofSectionXI.Additionally, onceeachquarterapressure'decaytestshallbeperformed ontheairreceivertoverifycheckvalveoperability inthereversedirection fortheairreceiverinletcheck.SystemFunctional Testingshallbeperformed atleastonceeachperiodontheDieselFuelOilTransferandJacketCoolingWaterSystemsinaccordance withtherequirements ofSectionXI.Inadditiontothetestingdiscussed above,Technical Specifications 6.4.1requiressurveillance testingtobeperformed onamonthlybasis.Suchas,verifying operability ofthefueloiltransferpumpsandverifying thatthedieselstartsfromnormalstandbyconditions.

11 QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNA'NUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREOUESTSREV.3PAGE25of39Section2RELIEFREQUESTNO.13IALTERNATIVE PRESSURETESTINGOFCONTAINMENT PENETRATION PIPINGUnderRevision.

I' QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE XNSPECTXON PROGRAMFORTHE1990-1999 XNTERVALISIRELIEFREUESTSREV.3PAGE26of39Section2RELIEFREQUESTNO14ALTERNATIVE HYDROSTATIC TESTINGOFTHECLASS3SERVICEWATERSYSTEMComponent forWhich,ReliefisRequested:

ServiceWater,Allpressureretaining components withintheClass3portionoftheServiceWaterSystem.ASMERequirement forWhichReliefisRequested:

IWD-5223(a)

SystemHydrostatic Test;Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressurePsvforsystemswithDesignTemperature of200F(93C)orless,andatleast1.25timesthesystempressurePsvforsystemswithDesignTemperature above200F(93C).Thesystempressure.

Psvshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted forPsv.Rochester GasandElectricbelievesthatthehydrostatic testrequirement fortheservicewatersystemisimpractical duetosystemdesignwhichdictatestheuseofanopen-ended test.Theportionofthesystemdownstream oftheheatexchanger isalsoopen-ended andcannotbehydrostatically tested.Theremaining sectionofthesystemisonlyisolatable bymeansofbutterfly valveswhichwerenotdesignedtoprovidealeak-tight boundary.

Withthesystemassuchitwouldbeimpractical toexpecttheleakagesotherthanatthevalvescouldbedetected.

Theamplemarginincoolingcapacityinherently providedbysystemdesigndoesnotdictatetheneedforanessentially leak-tight, boundary.

Sincethesystemisinconstantoperation, itsintegrity iscontinually monitored.

Thoroughinspection ofthesystemeachperiodatthefulloperating pressureisadequatetodetectanygrossfailuresinthesystemwithoutdegrading systemsafetyoravailability.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE27of39Section2RELIEFREQUESTNO.14(Con't)III.ProposedAlternate Method:Pressureretaining components withintheoperational boundarywillreceiveaninservice testatoperating pressureandanassociated VT-2examination eachperiodduringtheinterval.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTXNSERVICE XNSPECTION PROGRAMFORTHE1990-1999 XNTERVALISIRELIEFREUESTSREV.3PAGE28of39Section2WITHDRAWN RELIEFREQUESTNO.15CLASS2PIPING<3/8",AUGMENTED EXAMINATION Component forWhichReliefisRequested:

Class2,IWC2500-1TableExamination CategoryC-F-landC-F-2,ItemsC5.l0andC5.50.ASMERequirements forWhichReliefisRequested:

CategoryC-F-landC-F-2(ItemsC5.10andC5.50,respectively) forpipingwelds>3/8inchesnominalwallthickness forpiping>NPS4,asurfaceandvolumetric examination isrequiredon100%ofeachweldrequiring examination ateachinspection interval.

III.ProposedAlternate Method:Rochester GasandElectricbelievesasaminimumthattheterminalconnection weldsofidentified exemptedwelds(<3/8"nominalwall)shouldbeexaminedtotherequirements of,XWC2500-1Table,CategoryC-F-landC-F-2,XtemsC5.10andC5.50respectively.

Theseexaminations areidentified intheClass2Allocation TablesasAugmented Examinations andalsoareincludedunderthecategoryC-F-landC-F-2.IntheProgramPlanTables(Supplement 1toAppendixB).Theseareidentified asC-F-lorC-F-2followedby"---".Thesecomponents arealsonotedintheinstruction field.1 4N QUALITYASSURANCE MANUALGXNNASTATIONTITLEAPPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVICE XNSPECTXON PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE29of39Section2WITHDRAWN RELIEFREQUESTNO16CLASS1&2INTEGRALATTACHMENTS'UGMENTED EXAMINATIONS Components forWhichReliefisRequested:

Class1andClass2IntegralAttachments onPipingspecifically toSupportAttachments.

ASMERequirements forWhichReliefisRequested:

ForClass1,IntegralAttachments onpipingasindicated inIWB-2500-1, CategoryB-K-l,ItemB10.10,requiresvolumetric orsurfaceexamination beperformed onBaseAttachment Thickness

>5/8".ForClass2,IntegralAttachments onpipingasindicated=in IWC-2500-1, CategoryC-C,XtemC3.20,requiresasurfaceexamination beperformed onBaseAttachments

>3/4".Ithasbeenfeltthatsupportattachments tothepressureboundarysuchasgussetsandstanchions shouldhaveasurfaceexamination performed toinsurethesafetyandintegrity oftheClass1andClass2Systems.III.ProposedAlternate Method:Surfaceexaminations shallbeperformed onIntegralAttachments onpipingspecifically supportattachments onceperintervalinaccordance withIWB-2500-1 andIWC-2500-1, B-K-landC-C,respectively.

,gLfl QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREOUESTSREV.3PAGE30of39Section2RELIEFREQUESTNO.19PULSATION DAMPENER'LTERNATIVE EXAMINATIONS FORNOZZLEWELDS&INSIDERADIUS'Components forWhichReliefisRequested:

ChargingSystem,Class2PulseDampenernozzleinsideradiusandnozzleweldsexamination volumesperCategoryC-B,ItemsC2.21andC2.22.ASMERequirements forWhichReliefisRequested:

WithinTableIWC-2500-1, CategoryC-Bprovidesexamination requirements forClass2pressureretaining nozzleweldsinvessels.ThePulseDampenercontainsthree(3)nozzles,inline,locatedat.thebottomoftheunit.Thesenozzlesrequirebothsurfaceandvolumetric examinations asspecified byItemC2.21fornozzle-to-shell welds.Thesamethree(3)nozzlesalsorequirevolumetric examination asidentified byItemC2.22forthenozzleinsideradiussections.

ASMESectionXIrequires"essentially 100>oftheweldlength"asspecified withintheNoteswithintheIWC-2500-1 tables.ASMESectionXICode.CaseN-460statesthatiftheentireexamination volumeorareacannotbeexaminedduetointerference byanothercomponent orpartgeometry, areduction incoverageisacceptable providedthatthecoverageislessthan10>.R.E.GinnaNuclearPowerPlantwasconstructed toB31.1,1955edition.Thiscodedidnotcontainrequirements toensurethatitemsbeaccessible forfutureexaminations.

ThePulseDampenerwasconstructed andinstalled intheearly1970's,theconstruction codeutilizeddidnotprovideprovisions foraccessibility forISINDE.ThePulseDampenercontainsthree(3)nozzlesthatrequireexamination underASMESectionXI,1986Edition,noaddendaperCategoryC-B.Thesenozzlesareidentified asCF-N1,CF-N2andCF-N3.Thethree(3)Nozzle-to-Shell weldsrequirebothsurfaceandvolumetric examinations asspecified byItemC2.21.Thesamenozzlesarealsoexaminedvolumetrically fortheNozzleInsideRadiusSectionperItemC2.22.ThedesignofthePulseDampenerisnotconducive forexamination ofthenozzlesasidentified withintheaboveitemnumbers.Theoutboard 1ig1NI~~-HIIIIl1II QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE XNSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE31of39Section2RELIEFREQUESTNO.19(Con't)nozzleisidentified asCF-N1.Betweenthisnozzleandthemiddlenozzle(identified asCF-N2)isasupportthatcoverstheedgeofonenozzleweldheataffectedzone.Fromthemiddlenozzletothethirdnozzle(identified asCF-N3)isaspaceofonly7/8"fromtheedgeofonenozzleweldheataffectedzonetotheedgeoftheothernozzleheataffectedzone.Duetotheidentified interferences ofthenozzlesandvesselsupport,theassociated volumetric andsurfacevolumecoverageacceptance criteriaisbelowthestatedvaluewithinCodeCaseN-460.Thefollowing tablesummarizes thecoverageobtainedusingtheindicated examination methods.NozzleWeldNDEMethodofCoveraeCF-N1PTUT66465%CF-N2'TUT66465~oCF-N3PTUT>90~o80<SinceASMESectionXICoderequiresexamination ofthiscomponent andsinceitistheonlyoneofitstype,styleandfunction; theaboveidentified surfaceandvolumecoverageshouldbeacceptable inmeetingcoderequirements.

XI.ProposedAlternate Method:Rochester GasandElectric(RG&E)proposesthattheNDEsurfaceandvolumecoverageidentified withinthetableabovebeacceptable infulfilling thecoderequiredexaminations.

Theactualphysicalconfiguration ofthecomponent beingexaminedisnotconducive inobtaining therequirements specified withinCodeCaseN-460.Inaddition, RG&EproposestoperformaVT-2visualexamination ontheentirePulseDampenerduringaleakagetestandhydrostatic pressuretestinaccordance withIWA-5000andTableIWC-2500-1, asapplicable.

Ihll~'

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE32of39Section2ONE-TIMEUSEONLYRELIEFREQUESTNO~23ALTERNATIVE CLASS3HYDROSTATIC TESTINGFORCODEREPLACEMENTS Components forWhichReliefisRequested:

A.ServiceWaterSystem,RulesforHydrostatic TestingofRepairs,Replacements orModifications topressureretaining Class3components.

Installation ofisolation valvesa~b.C.d.e.f.gV-4611V-4613V-4626V-4669V-4738V-4739V-4760B.TurbineDrivenAuxiliary Feedwater System,RulesforHydrostatic TestingofRepairs,Replacements orModifications topressureretaining Class3components.

Installation ofvalveV-4023II.ASMERequirements forWhichReliefisRequested:

Hydrostatic testingofRepairs,Replacements orModifications onClass3systemsisrequiredbyIWA-4400whichspecifies thathydrostatic testingshallbeperformed toIWD-5223(a).

Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressureP,forsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureP,forsystemswithDesignTemperature above200'F.ThesystempressureP,shallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted forP,.

LI4 QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTXON PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE33of39Section2ONE-TIMEUSEONLYRELIEFREQUESTNO.23(Con't)IXI.Basis:Thefirstactivitytobeperformed isthereplacement ofseven(7)valvesintheClass3ServiceWaterSystem.Thesecondactivityisthereplacement ofacheckvalveintheClass3TurbineDrivenAuxiliary Feedwater System.ServiceWaterSstem:Seven(7)valveswithintheservicewatersystemarecurrently beingreplaced:

valvenumbers4611,4613,4626,4669,4738,4739,and4760.Thereplacement ofthevalvesisbeingperformed tothe1986editionofASMEB&PVCode,SectionIII.Anevaluation toestablish theworkareatestboundaries forthevalvereplacements wasperformed asdiscussed below(refertodrawings33013-1250 sheets1-3):V-4626Thereplacement valveisagatevalve.Boththeupstreamanddownstream isolations wouldrequiretheuseofbutterfly typeisolation valves,thusmakinganelevated(hydrostatic) pressuretestimpractical.

(seeReliefRequestg14)V-4611/V-4669/V-4738/V-4739/V-4760/V-4613:Thefirstfivereplacement valvesaregatevalvesandserveasloopcross-connects.

V-4613isabutterfly typedesignandservesasaloopisolation valve.Inordertoisolatetheselectedareasforreplacement, freezesealswouldberequiredtomaintainsomesystemssuppliedbytheServiceWaterSystemoperational.

Theuseoffreezesealsasisolation boundaries isnotfeasible.

Inordertoestablish testboundaries, completeservicewaterloopswouldberequiredtobeisolated, thuscreatinganoperational hardshipresulting inareduction inplantsafetyduetorendering certaincriticaloperational andsafetyrelatedequipment unavailable.

'tIl1 QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE34of39Section2ONE-TIMEUSEONLYRELIEFREQUESTNO.23(Con't)TurbineDrivenAuxiliarFeedwater Sstem:Theworkactivitybeingperformed isthereplacement ofcheckvalve4023intherecirculation testline.TheCodeusedforthisworkisthe1989editionofANSIB31.1.Oncethevalveisinstalled, thepipesectioncannotbeisolatedtoperformtheelevated(hydrostatic) pressuretest.Referring todrawing33013-1237, boundaries fortheworkareawouldbethepumpsuctionvalves(V-4024&4098),thepumpdischarge valve(V-3996)anddownstream flowcontrolvalveV-4291.BothV-3996andV-4291arenotdesignedforisolation applications, andwouldrequiretheinstallation oftestblocks.Installation oftheseblockswasfoundtobeimpractical.

Partoftheworkareawouldincorporate pipinghavingadesignpressureof150psi,witharequiredtestpressureof2304psi,therefore, anunacceptable condition wouldexist.Installation ofatestblockatthedischarge ofthepumpwasreviewedandfoundtobeimpractical becausedisassembly ofthepumpwouldberequired.

IV.ProposedAlternate Method:Alternative PressureTestRequirements forWeldedRepairsorInstallation ofReplacement ItemsbyWelding:Class3:UsingANSIB31.1andASMEB&PVCodeCaseN-416asabasisforrelief,Rochester Gas&Electricconsiders thefollowing alternative requirements tobeacceptable:

NDEshallbeperformed inaccordance withthemethodsandacceptance criteriaofSubsection NDofthe1986EditionofSectionIII.Additional NDEalsoisperformed bydyepenetrant testingoftherootpassweldfortheservicewatervalves.ForV-4023,asurfaceexamination willbeperformed.

QUALITYASSURANCE MANUALGINNASTATION1lTITLBAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE35of39ONE-TIMEUSEONLYRELIEFREQUESTNO.23(Con't)2.Priorto,orimmediately uponreturntoservice,aVT-2visualexamination shallbeperformed inconjunction withaninservice orfunctional leakagetest,usingthe1986EditionofSectionXI,inaccordance withIWA-5000, atnominaloperating pressureandtemperature.

Thiscoderequiredtestpressureandthenominalsystempressureatwhichaleaktestwillbeperformed asproposedareshowninthetablebelow:SWSValvesCodeRequiredTestPressureTestPressuretobePerformedf'~

V-4611V-4613V-4626V-4669V-4738V-4739V-4760165psig165psig165psig165psig165psig165psig165psig75psig(Nom.)75psig(Nom.)75psig(Nom.)75psig(Nom.)75psig(Nom.)75psig(Nom.)75psig(Nom.)Testpressurereflectssystemoperating pressureofnominal75psig.Thetestpressure(andnominaloperating pressure) isconsidered adequatetodetectpotential leakageafterperforming thereplacement.

IIEl QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE36of39ONE-TIMEUSEONLYRELIEFREQUESTNO.23(Con't)AFWValveV-4023CodeRequiredTestPressure2304psigTestPressuretobePerformed 1100psig(Nom.)(2)Testpressurereflectssystemoperating pressureofnominal1100psig.3.UseofthisReliefRequestwillbedocumented ontheNIS-2FormfortheReplacement.

N QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE INSPECTXON PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.Section23PAGE370(39ONE-TIMEUSEONLYRELIEFREQUESTNO24ALTERNATIVE CLASS3HYDROSTATIC TESTINGFORCODEREPLACEMENTS Components forWhichReliefisRequested:

ServiceWaterSystem,RulesforHydrostatic TestingofRepairs,Replacements orModifications topressureretaining Class3components.

Installation ofisolation valvesa~b.c~d.V-4663V-4013V-4027V-4028ASMERequirements forWhichReliefisRequested:

Hydrostatic testingofRepairs,Replacements orModifications onClass3systemsisrequiredbyIWA-4400whichspecifies thathydrostatic testingshallbeperformed toXWD-5223(a).

Thesystemhydrostatic testpressureshallbeatleast1.10timesthesystempressureP,forsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesyst:empressureP,forsystemswithDesignTemperature above200'F.ThesystempressureP,shallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressurePdshallbesubstituted forPy.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSREV.3PAGE38of39Section2ONE-TIMEUSEONLYRELIEFREQUESTNO.24(Con't)III.Basis:Thisrequestforreliefisfora"one-time" useforthereplacement offour(4)Class3servicewatervalves.Thefourvalvesbeingreplacedarevalvenumbers4663,4013,4027,and4028.Thereplacement represents apreviously unscheduled activityattributable todefectsencountered duringarefurbishment program.Thereplacement ofthevalvesisbeingperformed tothe1986editionofASMEB&PVCode,SectionIII.Anevaluation toestablish theworkareatestboundaries forthevalvereplacements wasperformed asdiscussed below(refertodrawings33013-1250 sheet3forV-4663and33013-1237 forV-4013,V-4027,andV-4028)Allreplacement valvesaregatevalves.Isolation boundaries forthevalveswouldrequiretheuseofbutterfly valves,makinganelevated(hydrostatic) pressuretestimpractical.

(seeReliefRequestg14)IV.ProposedAlternate Method:Alternative PressureTestRequirements forWeldedRepairsorInstallation ofReplacement ItemsbyWelding:Class3:UsingANSIB31.1andASMEB&PVCodeCaseN-416asabasisforrelief,Rochester Gas&Electricconsiders thefollowing alternative requirements tobeacceptable:

NDEshallbeperformed inaccordance withthemethodsandacceptance criteriaofSubsection NDofthe1986EditionofSectionIII.Additional NDEalsoisperformed bydyepenetrant testingoftherootpassweld.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALISIRELIEFREUESTSSection23PAGE39ot39ONE-TIMEUSEONLYRELIEFREQUESTNO.24(Con't)2.Priorto,orimmediately uponreturntoservice,aVT-2visualexamination shallbeperformed inconjunction withaninservice orfunctional leakagetest,usingthe1986EditionofSectionXI,inaccordance withIWA-5000, atnominaloperating pressureandtemperature.

Thiscoderequiredtestpressureandthenominalsystempressureatwhichaleaktestwillbeperformed asproposedareshowninthetablebelow:SWSValvesV-4663V-4013V-4027V-4028CodeRequiredTestPressure165psig165psig165psig165psigTestPressuretobePerformed 75psig(Nom.)75psig(Nom.)75psig(Nom.)75psig(Nom.)Testpressurereflectssystemoperating pressureofnominal75psig.Thetestpressure(andnominaloperating pressure) isconsidered adequatetodetectpotential leakageafterperforming thereplacement.

3.UseofthisReliefRequestwillbedocumented ontheNIS-2FormfortheReplacement.

QUALITYASSURANCE MANUALGINNASTATIONSection3EFFECTIVE DATE:PAGE1of3December31,1993ROCHESTER GAS5ELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALP&IDBOUNDARYDRAWINGSPREPAREDBY:QUALITYASSURANCE APPROVEDY:l~Caha1~"1f3I8-z89g-.y31.0General:TheP&IDdrawingsincludedwithinthissectionidentifydrawingscontaining linesclassified asASMEClass1,2,3andHighEnergypressureboundary.

Auniquelineidentifier hasbeenestablished foreachclass-lineandhighenergypressureboundaryline.Thelineidentifier wasusedinthepreparation ofthe"Line,List"toidentifythepressureboundaryaswellasdocumentthelineontheapplicable P&IDdrawing.TherulesofASMESectionXIwereappliedtobothclassandhighenergypressureboundaries asspecified byIWB/C/D/F-1200.

Thecolorcodedlinesappearing ontheapplicable drawingsidentifythoselinesrequiring Inservice Inspection andarenotexemptunderASMESectionXIforvolumetric, surfaceand/orvisualexaminations.

Leakageexamination boundaries andaccompanying visualexaminations forleakageisnotaddressed onthesedrawings.

Pressureboundaries thatarenotcolorcodedreflectlinesthatareexemptfromvolumetric, surfaceand/orvisualexaminations.

Thefollowing colorcodeswereappliedtoClass1,2,3,andHighEnergypressureboundaries; Class1Class2&HighEnergyClass3BlueRedGreen QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALP&IDBOUNDARYDRAWINGSREV.Section32PAGE2of3Thefollowing listidentifies theP&IDdrawingsthatcontainASMEClass1,2,3,orHighEnergypressureboundaries.

DrawinNumberRevision123112eet121eet1eet233013-1231 33013-1232 33013-1236 Sheet33013-1236 Sheet33013-1237 33013-1238 33013-1239 Sheet,33013-1239 Sheet33013-1245 33013-1246 Sheet33013-1246 Sheet33013-1247 33013-1248 33013-1250 Sheet33013-1250 Sheet33013-1250 Sheet33013-1258 33013-1260, 33013-1261 33013-1262 Sheet33013-1262 Sheet(*)33013-1263 33013-1264 33013-1265 Sheet33013-1265 Sheet33013-1266 33013-1270 Sheet33013-1272 Sheet33013-1272 Sheet(*)33013-1275 Sh33013-1275 Sheet33013-1277 Sheet(*)33013-1278 Sh(*)33013-1278 Sh33013-1279 33013-1863 33013-1865 33013-1866 33013-1870 Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.2298627911918762017131491415211057146516565226899118138

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALP&IDBOUNDARYDRAWINGSREV.Section32PAGE3of3DrawinNumber33013-1882 33013-1886 Sheet233013-1887

(*)33013-1893 33013-1908 Sheet333013-1915 33013-1991

(*)33013-2278 33013-2279 Sheet1RevisionRev.9Rev.5Rev.5Rev.10Rev.3Rev.9Rev.8Rev.0Rev.0Note:(*)=Identifies P&IDscontaining ASMEClasspipingNPS1"andbelow.Theseidentified drawingsarenotincludedwithinthissection.

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LfaCfkfetW>>tk~NLŽRr~--~~~~IIN~WI~~loof~NNIII~l',~~t~IIlklI~AOO"IiI<<QJwjIfly~eweAt~wNt~w~ws~A>0)WNNIONWkt~I~>w~0M~)N0>i~f733!~0iIIIlLO>~<<",!Ž~l.!'wICC~ll~ewI~~actIIWIN~Nf0>sINN>>NNlttlWt>Nt~OWW~NIIWWiL)30'SO\I~INkt9:yg'W1~0.II~NI~)SCOwt~'>t-llewoj~l~l,IWMNMt~LOLOOIOOOIODCN>1>O~luAOCDCNWN~~MIN~I>>L>>tI~~ICtolwiCVI III2IICIJ~R~I8cl)011I)2CellINI<<N>>W,NHIWONH~Ne-ewINWHNt~LIelnI.let~NHN~Ndt~eeeowIH~Ikl~~-I~HHI,4-..~ttteIllg!Hfonln).IItIA~I.H6)e~i>>I~HI~tlHINH.HNQ~8L..~&'-)HNII~IIF>>-~~P<<wyHe~k~Y.-"t~e<ekl~CHICL':~IekkNH,~HwttetHN~IIAHIII'ItIl~IN)II~~NHWt.till.~NI~I,Lklh.rA-I,Lklhr8L)1Il".)III-HIHN~HINilHtHN~.I,,Lkl)r'tttAILi.'lie~----~2;Ilrr~Inkl)-I~enen!g,,A"n<<:l)nr--),II:L)lw~w~III~enI;:)Irk)wasIl.ltrrIW<<JAN+H'~1,)N'HWe~g--IH~~IIPL'ILL~I~W~tt~wewIt~tk~Q~tkOwl~~H~I~WWW-I",,i~I)INI~N.L)w~INtH~HeNlNlttwtKH~~~wINI~IAN~NtAtINNI;t!I--.ptHHN~~~~INHN~H~~1~~~wten~~~IANlk<<I0ekho~tntHl~~W~AQg)~QiI.Tc~LNIwep,H11Ie.'r1~~~HI~~IWI~~NLLIIirtO}POS>>NOOIININtlnwCC~~IC~etnCH~~2545o78IIII)210 IO12N-~I~r.I>>~~I>>~N~~IHWWW~P>>~NW>>NItNI~I~I-N>>.~IIHOt>>t~INN\~HIHIW~WH>>~NHN~elI~~lotl~>>I>>.~NM~~NNtW11>>>>l~NH~n~>>NItt>>NINHj>>IW~NN~HI>>INIOOINt~HN~11~<<>>I>>INN~W>>tt>>I1f+~~IWHII+<< ~I~>>I<<~~NIN>>~t~~H>>WOO~~~~ISaNIN~NWWWNININWW~>>NIHHMII~MANONlt~HOO11I~Hl.CTiiI~~t-O~1~IIH~lltN~NII~N~W~~HI>>~~~N~Irt<<M~NWt<<t~It~NNI~NWMHl~WWN<<tHNNNM~NOO1I~IW1-11>>t~t~IN~11M~M>>MWHN<<~HINtl>>~WIHH~I11MN~IIO1~H~I>>PftttttN~IM~IIWIIN~WtN~H~Hl~~ttIIIIt>>tO~llHI'N~~1>>l~~1~IllfOINirlLM~1>>~HII<<l~>>IHtltifill.'"i~~IHIHNHIII>>W~H~Itt>>lIIW~N~~HIOHOI>>IWffNtl>>HIIH~IYItHl~N~Hl~~~NNI~I<<NOWHI~,Ir>>IWLINIINN~II QUALITYASSURANCE MANUALGINNASTATIONSection4PAGE1of27EFFECTIVE DATE:December31,1993ROCHESTER GAS8ELECTRICCORPORATION SIGNATURE DATETITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALCODETABLESPREPAREDBY:QUAUTYASSURANCE REVIEW:APPROVEDY:a.-)-f3f84+31.0GeneralThefollowing CodeTablesweredeveloped toaddressapplicable ASMESectionXIRequirements specifically toR.E.GinnaNuclearPowerPlant.TheFormatofeachTableisidentical andadefinition appearsbeforethestartofeachtext.ASMESectionXICode,1986Edition,noAddenda,and10CFR50specifythatthisprogramconformstoArticlesIWB,C,DandFofASMESectionXI,ifnotalteredbyaReliefRequestand/orCodeCase.Thefollowing listidentified theCodeTableapplicability. CodeTableComonentJurisdiction Class1Class2Class3Class1,2and3IWFComponent Supports ItemNtxExanunation CategoryTheASMESecuonXIitemNo.andCategoryofthecomponent arelistedhthesecolumrn.Components andPartsTobeExanunedEachtypeofexamination areaislistedhthiscolumn.Examhation MethodsThcNDEmethodrequiredtosatisfyCoderequirements islistedinthiscolumn.Examination Requirements forThirdInspecthn intervalThiscolumnprovidesinformation regarding thcnumberand/orpercentofexaminations requiredtobeperformed fortheinspecdon htervaiExamhation Technique/Exanunation AreaCommentsThiscolumnprovides&formation speciTictoexamination techniques, examination areas,orcomments. 0td0H0toXHWOn~~0tglHUtfy~~oxIWO~LOQEgf~tf)H0R'dWXg04QQH'zCdOXXUPH0Mfll00 ItemNtx'nCategoryBl.)0B-ABl.l)Bl.)2REACTORPRESSUREVESSELComponents andPartsTobeExaminedCucumferentia) andLongitudinal ShellWeMsExanunation MethodsVoluinetrie Exartdnation Rcqudrcments forThhdInspection Interval)00)bofonecucumfcrcrzia) weMtobeexauuncdattructural discontinuhy hthebchlh>>region.Theducecubercircumfercntia) wzldsshallbeperiormed asaAugmented ProgramasspeeiT>>dby10CFRPart50.Examinations maybeperformed atorneartheendoftheInspccrion IntetvaLExaudnarion Tcchn'quelgxauunation AreaCommcrasExamination ofcucumferenria) sheUweMswillbeperformed whhUTtechniques. Thereareno)onghudina) weMsatR.E.Ginna.Qg>10RCMPSCCAPPgHM4KOH0Im81.20BAB1.2]B).228130B.AB).COB.AB).50B-ABI.S)B3.00BDB3100BDSC.)0B-EBI.)IBc.)2Sc.)3Circumfcreruial audMerMiona) HeadWeMsShell.to.Flange WeMVolumctrk Head-to-F)ange WeMVolumetric andSurfaceRepairWeldsNozzk-to.Vessel WeMsandVolumetric hozzkIruideRadiusSectionPania)Penetmtion WcMs:Visual(VT-2)VesselNmzksConsolRodDriveNmzksInsuumentation Nmzles)00bboftheweMtobeexamineLAtleast509boftheweMshallbeexaminedfromtheRangefacebytheendofthefustInspection periodandtheremtdnder bytheendofthethirdInspecuon period.100)boftheweMtobeexamineL)009bofnmzks.Atleast25)bbutnotmorethan50)bofthenmzksshallbeexaminedbythecndofthefiatperiodandtheremainder bytheendofd>>IntctvaLAtkast25)bofeachgroupofweMsofcomparabk sizeandfunctiontobeexandneLTherearenomeridional orcircumferenria) headweMsatILE.Gutna.ThesheU.to.lhnge weMwillbecxanunedfromthevesselsealsurfaceandfromthevesselwallinsidesurfacewhhUT.NOTE:ReliefRequestu1.Thehead.to.Range weMwillbeexaminedwithUTandsurfaceexamination techniques whentheheadisremoved.NorepairweldsatR.E.Ginna.'Ihenmxle-to-vessel weMsandnozzkiiuideradiussecrionswillbeexaminedwithUT.Examination wiBbeperfosnef duringthesystemhydrostatic testorahernariively toCodeCa>>N-49TLVTexaminations willbeperiormcd Maccordance withIWA-52Cth 0MWOo~~0tg)Ha~><OMIbf)O+bf)Z+)f)H0MHgR'Ef0RwagH0'JyLB5.10S.FS520B.FBS30B6.10SZ.)IVessure-Retaining Dissimilar MetalbveMsVolumetric 8SurfacePressure-Rctahung Dissin8ar Metal)VeMsC)osurcHeadNuts>2SurfaceinchesinDiameterAllNozzle.to safeendbuttweMsNPS4orlarger.)00)bofnutstobeexanuneLExamhtation maybeperfosncd atorneartheendoftheinspection intcrvaLEaunsmaybeperformed cou>>ident whhthevesselnozzleexamsrequire)byCategoryB.D.Nodissimilar metalweldsonRPVatILE.Gin@aNutswillbeexaminedwhhMTwhenrenovcdforrefueling. MfD0b0 Table1NSERVVICE INSPECTION PROGRAMC1ASS1(Gout'd)itemNo.Examinarion CategoryComponents andPartsTobe~Examination MethodsExamination Requirements forThirdInspection intervalExamfnatNn Technique/Examfnathn AreaCommentsREACTORPRESSUREVESSELcont'dBrx20BGIQosureHeadStuds,InPlace,>2IncheslnDiameterVolumetrk 1009bolstudstobeexamined. Xuamfnadon maybeperformed atorneartheendoltheinspecrion intervaLQosurestudexamfnarions maybeperformed 'inpince.'xaminations shouMbeschedukdwhenstudsareremovedtoreduceradiation exposureandaBow0>>mostthomughexaminarion. CodeCaseNS07-Ishallapply.86.50BZ.IB7.10BG.2B7~B4.2QosureHeadStuds,WhenRemoved,>2InchesinDiameterVolumetrk andSurfaceThreadsinFhmge>2InchesInDiameterVolumetri Prcssure-Retaining Bohings2InchesinDiameterCRDHousingsBohs,Studs,andNutsVisual(VT.I)Pressure. Retaining QosureVisual(VT.I)WashersandBufhings>2InchesinDhmetcr10016ofstudstobexanunc<<LXammiai'on maybeperformed atorneartheendoltheInspccrion imervaL10016ofthreakdholestobecxanun<<LExanunation maybeperformed atorneartheendoftheinspection intervaLAUwashcrsandbushingstobeexamineduponstudrcmovaLExamfnatkn maybeperformed atornearthecndoftheInspection intcnraLABbohs,studs,andnutstobeexanun<<L'ThestudswillbeexaminedwithUTandMT.CodeCaseNS0r/Ishallapply.Nopressure-retaining bohing<2'ndiameteronRPVatLE.Gfnna.Pressure-retaining CRDhousingbohngwBIbeexanuncdwhendisassembl<<L H~0U)~NQWOWtf)HRc(7tf)C('Ef>O(f)OWI+IeWa+tf)OIgrrH+tf)HOe()7~HgoBRIOB.HB13.10B-N.IIntegralAttachments lorRPVVesselImeriorN/AVisual(VTS)Accessible areastobeexaminedduringeachInspection periorLNoIntegrally weldedattachments onRPVatILE.GfnnathatmeetthereqIremcntsofCategoryBH.B13.50B.N2interiorAttachments WithinBemineRegionVisual(VT.I)Accessl>>k attachment weldstobeexamin<<LExandnations maybecompktcdatorneartheendoltheinspectkn IntesvaLB13.60B.N.2B13.70BNBBIO.10InteriorAttachments BeyondBehlineRegionVisual(VT-3)CweSupport Structure Visual(VTS)ConuolRodDriveHousingVolmnetric orWcMsSurfaceAcccssRrk attachment weMstobeexamln<<LExaminations maybecompleted atorneartheendoftheInspecrion intervaLWithcore.support strttureremoved,allaceessibk surfacestobeexamin<<LExamfnacions maybecompktedatorneartheendoftheinspection IntetvaLWcMsinIOIboftheperipheral CRDhousingstobecxamin<<L~nsmaybeperformed atornearthecndoftheInspection huesvaLTheCRDhousLngweMswillbeexaminedwithPT.(I)(D0I"0 ItemNo.Examinarion Category8IS.IOB.PREACIORPRESSUREVESSEL<<ont'dComponents andPartsTobeExaminedExaminenonMethodsAllPressure.Retaining Vhual(VT2)Boundaries forVesselComponents INSERVKXINSPKCIION PROGRAMCIASS1COMPONKNIS (Cont'd)Examinarion Rolulrements forThirdInspecth>n IntervalAUcomponents tobeexaminedduringsystemleakagetest.Examfnarions tobeperformed inaccordance withIWB.5221priortoplantstartupaftereachrefueling outage.Examinarion Technictur/Examfnarion AreaCommentsVTtxaminarions willbeperformed inaccordance withIWA.524kQgk)0RC(/)QZCCVWWgH(I)Ot3H0B15.11B-PABPressure-Retaining Boundaries forVesselComponents Visual(VT.2)Allcomponents tobeexanunedduringsystemhydrostatic testorahernatiwly toCodeCaseNIPS.Examinarions tobeperformed lnsccordanm whhitVB.5221/5222 atorneard>>endoftheInspection IntervaLVTexanunations willbeperiormed Inaccordance wnhIWA-524L0(/)WOO~~0')H~u)Z~ov)Itf)O())tf)<+'Lf)H(/)HgQCrE)OXXU0H0g04QrI(/)80r0 TsbkIINSERVKXINSPECIION PROGRAMCXASSICOMFONENIS (Gxa'd)ItemNcxPRESSURIZER 82.108882.1182.12Components andPansTobeExamhedCircumferential andlongitudinal SheU.to-Head WeMsExamination hlethodsVolumetric Exatnination Rcqmremeats forThirdInspection intervalTheupperandbwerhead-tosheU weMstobeexamfnccL Onefootofonehngitudhal weMintetsccring eachhead-to-sheU weMtobeexamhcd.Examinarion Technique/Examhation AreaCommentsExamination willbeperfoccacd withUTtechniques. (I)RKOH082.208882.21822283.1108DEh)208-DBS.C0B.FCircumfccearial andMeriTioaai HeadWeMsVolumetric Nmzkco.Vessel WeMsN/ANmzkInsideRadiusSecrionsVolumetric Nozzle-toSafe EndDissimilar MetalWeldsseInchesNPSSurfacesndVolumetric HeaterPenetration WeMsVisual(VT.2)Iheremenopessurixer headweMsatLE.Ghna.AUhsMeradiussecrionstobeexamhed.Atleast2596lmcnotmorethanStylkofthenozzksshallbeexaminedbytheeadofchefustperiodandthercmahdcrbythecndoftheinspection iatccvaLAUpressurizer heaterpenetration weklsshaUbeexaminedduchgsystemhydrostatic testorahernatively toCodeCaseN~98insecordancewithIW8.5222atorneartheendoftheinspection imecvaLAUbuttweMstobeexamhed.Nonozxk-to.vessel welds.NouksarehtegraUycastintotheheadofpressurizer atLE.Girma.Exandnations willbeperformed whhUTtechniques. VTexamhation willbeperformed inaccordance withIWA.5240. Examinations willbeperiormcd withPTandUTtechniques. 00)i2"HEr)Oo~~U0c()HO(/)Id+c()O+c()Z+QHR'E)tdXg04QQHC'I)OEr)Ez)UigicHXIDL'dt)30'Ef85.508-FNoxxk-toSafe EadDissiaular MetalWeMs<4InchesNPSN/ANonmzle-to-safe end~imUarmetalweMsonpressurixer atLE.Gina'5.60 B.FNoule.toSafe EndSocketWeMsN/ANodissimilar metalsocketweMsonpressurixer stiLE.Ginna.Bck6084.186.70Bc%80PressureRetahiagBohhg>2IncheshDiameterBohr,Scuds,andNutsVisual(VT.I)s2InchesiaDhmeterAUbohr,scuds,andnutstobeexamhed.Nobohingoapressurixer >2iacheshdiameterstR.E.Ghna.Bohingexamharioas maybeperformed hplaceuadercensionorwhendisassembkd orremoved.V08820B-HIntegraUy WeldedAttachments Pessurixcr supportsMrtnotrequiredforexamharioa for3rdand4thhcervakbyCode.O 4C' Tabk1INSERVICK INSPECIION PROCRAMCIASSIOOMPONENIS (Cont'd)hemNtxExanunation CategoryPRESSURIZER Cont'dBI520B-PComponents andPansTobeExaminedPressure.Retaining Boundaries forVesselComponents Examlnarion MethodsVisual(VI'2)Examinarion Requirements forThhdInspeerion IntervalAllpressurixer components tobeexaminedduringsystemkahagetest.Examination tobeperformed inaccordance withIWB.5221priortophntstattupaftereachrefueling outageExamination Tcehnhlue/Examination AreaCommentsVTexamination willbeperformed inaccordance withIWB-5240. cMOH0B1521B-PPressure.Retaining Oundaries forVesselComponents Visual(VT-2)Allpressurizer components tobeexaminedduringsystemhydrostatic testorahetnativciy toCodeCaseNAPLExanunation tobeper-formedInaccordance withIWB-5221/5222 atorneartheendoftheInspecrion huervaLVTexaminarion willbeperformed inaccordance withIWA.5240. HOMEr)OOH~U0tf)HOMI+If)O+tOHR'EfAR'T)(r()OtdxaPHXIX()())0'dM(i)00 IranExamination NfxCategorySITA%IGENERATORS 82308.882318282Components andPartsTobeExaminedCireumferenrial sndMeridfonal WeMsintheIffwerHeadExaminarion MethodsNNSERVICK NSPECIION PROGRAM(2ASSI(2)MPONENIS (Co%'d)Examhation Requirements forIhffdfnspecdon IntavafExsfnhation Technique/Exanination AreaCommentsTherearcnosteamgenerator kfwerheadcircumferenthl ormeridional weMs.MCCOYOH082.S08883.130B.DBXICOB.D85.70B.FTubesheec to.HeadWeMVolumetric NmzkInsideRadiusSectionsVolumetri NPS4orLargerNmzle.to. SafeEndDiafmilar MetalWchhSurfaceandVolumetric lessthanNFL,Nmzk.to.SafeEndDissimBar MetalWeMsNmxle.toVesselWeMsN/AThttubahccc.tDhcad wcMwillbccfulffuncd. 'Theexanhation willbelimitedtooneofthetwostcamgcfltrators AllnmzkinsideradiussenionswBIbesmfninccL Atkast2596hznocmorethanSty)hofthenozzksshallbetxanuncdbythetndofthefirsthspection periodandcheremainder bytheendoftheinspenionmtavalAllnozzlesafe~dissimihr metalweMsshallbeexamined. Examination willbeperformed withUTtechniques. Therearenosteamgenerator nmzle-to-vessel weMs.Nozzksaftintegrally castintoheads.Examinations willbeperformed withUTccehniques. 'Iherearenosteamgenerator nmzle.to.vessel webb.Exanunafonswillbeperformed withPTandUTteehniqua atRE.Ginns.Therearenosteamgenerator wehhofthistype.H0(I)gH(z)OO~~Ucf)HO(I)I+cf)O>cf)HXIvmQH4I)C'I)OWQ2e(zfU~HXIX'I)(II086.90lhG.I86.10086.110NmxlecoSafe EndDissimilar MetalWCMsPrcssure-Rctsuung Bohng>2InchesinDhmecerNobokhgonsteangenerators >2IncheshdiameteracRE.GinnLTherearenosteamgenemcorwehhofttustype.8730BG2BI5308-PIntegmByWeMedAttachments Pressure.Retahing Bomxhries N/AVisual(VT-2)Bohr,Studs,andNutsVisusl(VTI)s2InchesinDiameterAllboks,scuds,sndnutswillbeexanined. Iheexamination willbelimitedtooneofthetwosttafngcntfstofs. ABnesmgenerator components cobeeaunfnedduringsystemleakagetest.Exanhations cobepaformtdinccordanmwhhIWB-5221priortophntstanupafttreachrefuelhgoutage.Examinations msybeperformed inphctundertensionorwhenrcmovcd.Ihertarenostcamgenerator imegraBywehkdattachments. IW8.250013.VTexsmlnarions willbeperformed haccordance withIWA-524th (/)(t)00 ItemExandnation No.Categon/STEAMGENERATORS Cont'dSISSIB-PBI6.20B4)Components andPansTobeExaminedExamination MethodsPressure. Retaining Boundaries Visual(VT.2)SteamGenemtorTubingVolumetric TaMeIINSERVKXINSPECIION PROGRAMCLASSICDMPONENIS (Gun'd)'Requirements forlMrdinspection IntervalAllsteamgenerator components tobeexaminedduringsystemhydrostatic testorahernatively toCodeCaseN~PILExanunarions totgeperformed inaccordance whhIWB.5221/5222 atorneartheendoftheinspection intervaLThetubinginthehockgside,U.bendportion,andoptionally coMkgsidewillbeexanuned. Examination Technique/Examination AreaCommentsVTexaininanons willbeperformed inaccordance withIWA4240.Examination requirements, exandnation method,andtheextentandfrequency ofexaminarion shallbeinaccordance withplantTcchnical SpeciYications. H'xf40(/)XErfgHtdOo0tf)H>OfJ)Itf)O>tf)Z+tf)H0(HgR'(fQ0QaEfCEfOX~H0Qg>10RR(/)gZCC~~JYgH(I)CKOH0(f)000 Ia ItemNo.Examination Category82508.882518252HEATEXCHANGERS Components andPansTobeExaminedHeadWeMsExamination MethodsTaMeINSERVVICE INSPECIION PROGRAMaASSICOMPONENTS (Cont'd)Examination Requirements forThirdInspection InterualExamination Technique/Examination AreaCommentsNotneridional orcircumfcrenriai healweMsinbeatexchanger atILE.GinnaQg>10RCMP'CC~VPgHMCKO082.6088Tubcshect-to.Head WeldsVolumeuie Eachtubesheet-to.head weMwillbecxanulRdExamination wiBbeperformed withUTteclmiques. 82.70B.B82JSB-B83.1508-D83.160B.D85100B.F8511085.12086.120BG.I8&.13086.1COLonghudinal WeldsTubesheet.to&hell WeMsVo!umetrie Nmzle-to-Vessel WcMsandNozzkInsideRadiusSectionVolumetri Pressure-Retaining Dissimihr MetalWcMsBohs,Studs,andNtxss2InchesMDiameterPrcssure-Retaining BohingN/A)2InchesinDiameterEachtubeshect.to.shell weMwillbecxanuncd. Allnmzle.to-sheB andnmzleinsMeradiussectionswillbecxaminctL Atleast2596butnotmorethan50%ofthenozzlesshallbeexaminedbytheendofthefirstinspecuon periodandtheremainder bytheendoftheInterrakTherearenoRHElongitudinal weMsatILE.Ginna.Examination willbeperformed withUTtecluuquea, Examination willbeperformed withUTtechmques. Noheatexchanger dissimilar weMsatR.E.GfnnLNoheatexchanger bolringatR.E.GlnnaNoheatexchanger bohingatILE.Ginna.0MXHWOO0~OMI+If)O())tf)<+M)Hg0CQQHR'E)C'E)OXVRXO~HXIX'd())0b7Integrally WeMedAnnehmentsIntegrally weMedauachments notrequiredforexamination for3rdand4thIntcnrais bycode.815C0B.P815AIB.PPressure.Retaining Boundaries Pressure-Retainfng Oundsries Visual(VT-2)Visual(VT.2)AllRHEcomponents wiilbeexaminedduringsystemkakagetest.Examinarions tobeperformed inaccordance withIW8.5221priortophntstartupaftereachrefueling outage.AllRHEcomponents w81beexaminedduringsystemhyhostatk testorahernatively toCodeCaseNA98.Exandnations tobeper-formedinaccordance withIW8.5221/5222 atorneartheendoftheinspection InterrakVTexaminarions willbeperformed inaceordanee withIWA.5240VTexaminations willbeperformed Maccordance withIWA524k(D00 II itemNo.PIPING85.130B.F85.140LFComponents sndPansTobeExaminedDissimQar MetalWekhs4InchesNPSDhsimibrMetalWeMs<4inchesNPSExarrdnation MethodsVolumetric andSurfaceN/ATable1INSERVKXINSPECllON PROGRAMCIASS1COMPONENIS (Cont'd)Exarrdnation Requirements forT)drdInspection intervalAllbuttweldstobeexamined. Examination Technique/Exsndnatbn AreaCommentsThewekhwillbeexaminedwithUTandPT.Nodbsimitsr metalweMs<4inchesNPSatLE.GtnnaQg>I0RRf/)gMCCOYQQgHMOH085150B.F86.150BGI86.16086.)7089.10W89.1189.12WDissinular MetalSoc'ketWeMsPressure.Retsinhrg Boking>2InchesinDiameterPressure-Rettdning Bokings2InchesinDiameterCucumferential PipeWekhs4InchesNPSLongitudinal PipeWeldss4InchesNPSN/AVolumetric andSurfaceVolumetric andSurhce259kof0>>requiredcircumferential buttweldstobeexamined. SeeNoteIatendofTabkIforsekctioncriteria. Longitudinal weMsthatadjoinschedukdeircumferemisl wekbaretobeexamined. Onepipediameterncxtoexceed12inchesofeachbngitudinsl weMkngthrcquireLNodissimilar metalsocketwekhatILE.Ghana.Nopressure. retaining bohing>2incheshtdiameteratLE.Ginna.Noprcssure.retaining bohing<<2h>>hesonpipingatLE.Girma.ThepipingwekbwillbeexaminedwhhUTandPT.ThepipingwekhwillbeexanunedwithUTsndPT.0f/)gHXOO0I~)t)HOf/)+ItaI'Ejtt)OEtttt)ZL)t)HQHR'dOErjErjO~H'Tjtd0m89.21Circumferential WeMsSurface<4InchesNPS25%ofthercquircdcircumferential buttweMstobeexamhteLSeeNoteIatendofTableIforsekctioncriteriL'thepipingwekhwillbeexaminedwhhPT.g0Longitudinal PipeVVeMs<4InchesNPSNopressure.retaining bnghudktst pipewelds<4h>>hesNPSatILE.Ginna.8920W898)8932W8940WBranchPipeConnection Weldsa4InchesNPSBranchPipeConnection WeMs<4InchesNPSSocket)VeMsVolumetric andSurfaceSurface2544oftherequiredbranchconnection jointstobeexamined. SeeNote)atendofTableIforsekctioncriteriL25%oftherequiredbranchconnection jointstobeexamineLSeeNoteIatendofTable)forsekctioneriterim25)kof6erequiredsoc'kctwebbtobeexandneLSeehoreIatendofTabkIforselenioneritcria. lhebranchconnection wekbwillbeexaminedwithUTandPT.Thebranchconnection weMswillbeexamh>>dwithPT.ThesocketweMswittbeexaminedwhhPT.00Bttk)0B.KIIntegrally WeMcdAttachments Integrally weMcdattachments rxxrequiredforexamination for3rdand4thintervabbycode. F~~II.~-.~ ItemNtxPIPINCCont'dBI%50B.PGomponents andPartsTobeExaminedABPressureRetaining Visual(VT-2)Boundaries forPipingComponents Table1NSERVKXINSPKCIION PROGRAM(XASS1COMPONENIS (Cora'd)Examinarion Requirements forThirdInspecrion intervalAllcomponents tobeexaminedduringsystemleakagetest.Examfnarion tobeperformed inaccordance withIWB.5221priortoplantstanupaltereachfefuelfng outage.Examination Technique/Examination AreaCommentsVTexamination wiBbeperformed inaccordance whhIWA.5241Qg>10OH0B15.5)B-PAllPressureRetaining Boundaries forPipingComponents Visual(VT-2)Allcomponents tobeexaminedduringsystemhydrostaric testoralternatively toCodeCaseN498.Examination tobeperformed inaccordance withIWB.5221/5222 atorneartheendoftheInspection IntetvahVTexamination willbeperformed inaccordance withIWA.5240. 0MgHWO0NOHa~<+OMI~tOOLQQ>NOHMHgRdg0CQe'Q(OXXU~H'0(2)0'E)M(t)0I0

ItemNo.ExaminadonCategoryComponents andPartsTobeExaminedExamination MethodsTable1INSERVICE INSPECllON PROGRAMCIASS1COMPONENIS (Cont'd)Examinadon Requirements forThirdInspection IntervalExamination Technique/Examination AreaCommentsQg>10RR(/)P'cCCQOPUMPS86.180BG.IBohrandStuds,>2InchesVolumeukinDiameterAllbohsandstudstobeexanunedforhemsassociated withonecomponent Inamuhicomponent group.ThebohingwtlIbeexaminedwhhUT.CodeCaseN.307.1shallapply.TheboltingmaybeexaminedInpkceundertensionorwhendisassembled orremovetL86.190B4.18620084.187XOBG.28IIL208-KI812.10B.LI812.208-L2815.60B.PFlangeSurfaceforBolting>>2IncheshDiameterWhenConnection kDisassembled Nuts,Bushings, andWashers>2InchesinDiameterPrcssure-Retammg Bohmgs2lachesinDiameterIntegmlly WeMedAttachments PumpCasingWeMsInternalSurfacesofPumpCasingsPressure.Retaining Boundaries forPumpComponents Visual(VT.I)Visual(VT-I)Visual(VT.I)Visual(VM)Visual(VT.2)Examination inc!udesIinchanntdarsurfaceofIkngearoundeachstudhoksurfacewhendisassembled. AUnuts,bushings, andwasherstobeexanuncdwhendisassembkd ononecomponent inamuhicomponentgroup.ReactorcoolantpumpeasingweMsononepumptobeexamineLOnereactorcoolantpumptobeexanunedwhendisassembfoL Allcomponents tobeexaminedduringsystemkahsgetest.Examfnatson tobcperformed trtaccordance withIWB$221priortopkntstartupaftereachrefueling outage.VTexamination willbeperformed whenUsassembletL VTexamination willbeperformed whendhassembkd. Nopressure. retaining bohfng<2InchesindiameteronpumpsatILE.Gfnna.Integrally weldedattachments notrequiredforexamination for3rdand4thintervals bycode.Examination performed inaccordance withCodeCaseN.481.PumpcasingInternalsurfacewillbeexaminedwithvkualtechniques whendisasscmbktL VTexanunations willbeperformed inaccordance withIWA.5240. 0(/lXOo~~3tf)H0(I)I+tf)O+'LOH(/)H~I-3'E)(T)Xg0CQQC'EfO(x)XUPHMCl081%618-PRG1.14FlywheelPressure. Retaining Boundaries forPumpComponents PumpFIywheekVisual(VT2)SurfaceandVolumetric AUcomponents tobeexaminedduringsystemhydrostatk testorahcmatively toCodeCaseN.498.Examination tobeperformed Inaccordance withIW8.5221/5222 atorneartheendoftheinspection intervaLEachreactorcookntpumpIlywheeltobeexaminedperRcg.Guide1.14.HighmessareastobeexaminedeachperiodwithfuUexamination attheendofintcrvaLVTexaminations willbeperformed inaccordance withIWA524thExaminations willbeperformed withMTandUTtechniques onthe2activecomponents asaminimumonanAugmented Program.(/)(D0I00

INSHMCEINSPECllON PROGRAMCIASSICOMPONENIS (Cont'd)ItemExaminarion No.CategoryComponents andPansTobeExanunedExamination Retiuirements forThirdInspecrion IntervalExaminarion Tcchnhiue/Examfnarion AreaCommentsOVALVES86.210BGI8&.22086230Bohing>2InchesinN/ADiameterNovalvebohfng>2inchesindhtmeteratLE.Ginna87.70BG.2Bohings2InchesInDiameterVisual(VT-I)Allbohs,studs,andnutstobeexaminedonIcomponent pergroup.Thebohingmaybeexaminedinplaceundertensionorwhendlsassembkd orremoveL810308KI812308-MI812.40B-hlI8IL508M.2815.708P815.718PIntegrally WeMcdAttachments Pressure. Retaining WeMsinValveBodies<4InchesNPSPressure-Retaining WeldsinValveBodiesa4InchesNPSInternalSurfacesofValveBodiesonValves>4InchesNPSAllPrcssure. Retaining Boundaries forValveComponents AllPressureRetaining Boundsries forValveComponents Vo!muetricVisual(VT4)Visual(Vl'-2)Visual(VT-2)AilweMsononevalveIneachgroupofvalvesthatlsofthesamensttucrion andsfmBsrfunctiontobecxaminohOnevalveiueachgmupofvalvesthatisofthesomeconstruction andsimBsrfunctiontobecxaminctL Allcomponents tobeexaminedduringsystemkahsgetest.Examination tobeperformed inaccordance withIWB5221priortoplantstsrtupaftereachrefueling outage.Allcomponents tobeexaminedduringsystemhydroststk t<<storahctnatfvely toCodeCaseNA98.Examination tobeperformed inaccordance whhIW8.5221/5222 atorneartheendoftheinspection IntervalIntegrally weMcdattachments notrequfmlforexamination for3rdand4thintcrvahbyaxle.Nopressureretaining weMsInvalvebodies<4inchesNPSatILE.Ginns.ValveweMswillbeexanunedwithUT.InternalsurfacesofvalvebodiestobeexaminedwithVT.3.VTexaminations willbeperformed inaccordance withIWB-5240. VTexaminations willbeperformed inaccordance withIWA.5240. 0(I)gHXOo~~OeH>tf)Z+o(f)I+tOO()7tf)ZR'E)go4Ac'QHOXead(gi0'T)(I)900O TableIAsaUowedbyIOCFR50.55(a)(b)(2)(ii), ASMESectionXI1974Editionwithaddendathrough1975kpermitted forCategoryBJweMsekctionanddoesnotutilizestresskvelcrfteriiu CategoryBJweMsekcdonshallbeperformed toASM'ection XI,1986Edition,noaMcndaandshallnccutilizestresslevelcriteria. Exanunations selectedshallbedistributed insuchamamurtoinclude:(a)Allacoessibk TerminalEndsineachpipeorbranchrunconnected tovessek.(b)Allaeeessibk TerminalEndsandjointsineachpipeorbranchrunconnected toothercomponents suchaspumps,branchesandanchors.(e)Alldissbnilar metalwelds.Q)%10QRMQSCCAWWgHM'gK00Nixer(d)AddiYional pipingweMs(structural discontinuity weMs)sothattheuxalnumberofcircumferential buttweMs(orbranchconnection orsocketweMs)sckctcdI'orexainination equals25%ofthecfrcumferentksI burtweMs(orbranch<<onncction orsocketweMs)intheReactorCoolantpipingsystem.ThistotaldoesmxincludeweMsexcludedbyIWB-1220. TheseaddiYional weMsmaybekcatedInoneMopandshallbesekctedamongtheQassIsyrtems,prorated, tothedegreepiactkaLTerminalEnd(TE)WeMsaredefinedastheexuemiYies ofpipingrunsthatconnecttoructures, components, orpipeanchors,eachofwhichactsasarigidrestmintorpmvMesatleasttwodegreesofrestraint topipingthermalexpansion. Thkdefinition (ref.IWA.9000) isinterpreted toincludethefolhwingt (a)Chcumferential weMswhfun3pipediameters ofthecenterUne ofrigidpipeanchorsoranchorsatpenetmtions oftheprknaryreactorconta'uunent. (b)Pipingconnection weMsinwhkhthemainprocesspipingisatkast3timeskrgerthantheBranchRun.(c)Pipingconnections torigMlymountedeomponentr, suchasvessels,pumps,cet.Thefolkwingweldtypesareidentified inSupplementItoAppendixB,theProgramPlan.'E.ATerminalEndataPipingAnchor'E-BTerminalEndataBranchConnection 'E.PTerminalEndataPumpConnection 'E.VTerminalEndataVesselConnection

• SDStructural Discontinuity

'PPipetoPipeBurtWeld'EAMLongitudinal SeamWeMNote:WhenmorethanoneweMtypekapplicable, themorerestrictive (i.c.'IE)isutilized. TerminalEndsatcomponent orbranchconnections areconsidered tobethepipingweMconnection tothesafewn4nozzk,reducer,weMokLsockoletorfiange.2.Structural Discontinuity (SD)WeMsincludescircumferentksl weMjointsatpipe-to.nozzk, pipe-to.valve, pipe.topumporpipe.tofirting.Fitting.to.Firting connections andallsocket.wcMcd connections shaBbeconsidered Structural Discontinuities. 0MgHEzj0n~~U0tf)H~If)QOMI'Tj+If)O(EItf)~+If)HtdR(jQC'EjOLxj0RwavbsH'd(EI0'Tj=Im(2)Examination islimitedtothoseintegrally weldedartachmems thatmeetthefolkrwing conditions: (a)theattachment kontheoutsidesurfaceofthepressure.retaining component; (b)theattaclunent providescomponent supportasdefinedinNF-1110;(e)theattachment basematerialdesignthkkncssk5/8inchorgreater,and0(d)theartaclunent weMjoinstheartachment eitherdirectlytothesurfaceofthecomponent ortoanMtegrally cartorforgedattachment tothecomponent. Examinafons includetheweMcdattachments ofpipingrequiredtobeexanunedbyExanunation Category8JandtheweMedattachments toassociated pumpsandvalvesintegraltosuchpiping. 1 Itemho.Exandnatlon Category'IheASMESectionXIItemÃtxandCategoryofthecomponent arelistedinthesecolumns.Components andpartsTobeExandnedEachtypeofexarrunatfon areaislistedInthiscolumn.Examhtation MethodsTheNDEmethodrequiredtosatisfyCoderequirements islistedhthiscolumn.Table2Examination Requirements forThirdItnpection IntervalThiscolunmprovidesInformation regarding thenumberand/orpercentofexamfrmtions requiredtobeperformed fortheinspection intervaLExamination Technique/Exanunation /treaCommentsThiscohunnprovidesInformation speeiTictoexanunation techniques, exandnatfon areas,orcomments. Qg>I0RAM'CCLOH040MWO~LOHOMI'd+tOO>tOZ+tOHMH~QH'R'TfC'0OXDRxa~HXIXMN0'Ef

ItemNtxPRESSUREVESSELSC1.10G*Components andPatsTobeExaminedSheBCircumferenthl tveMsExamhethn MethabVolumetric TaMe2INSERVICE INSPBCIION PROGRAMCRASS2COMPONENIS Examination Rcquiremerrts forTturdinspection interval100%ofeachweMtobeexamhted(appliesonlytowekhatgrossstructural discontintuties). FormukiplevessehofsinulardesignsILcandsetvioe,examinations maybelimitedtoonevesseLExamhetion Techtuque/Examination AreaCommentsThewekbwillbeexaminedwhhUT.Qg>10R2e(/)~R((Ot3H0CIMCAC)30GACL10CBCh1IC220GBC2.21C2.22GBHealCircumferential WeklsVolumetric NouksinVessehxl/2-N/AInchNonunalThickness NouletoSheB(orHeal)WeldNozzksWithotaReinforcing PLsteinYeech>I/2.lochNomirelThkknessNoule.to.SheB(orHead)WeMSurfaceandVolumetric NazeInsideRadiusSectionVolumetric Tubesheet.toSheB WeMVolumeuie 100%ofeachhead-toaheB weMtobecxamineLformukiplevcssebofsimBardesignsizeandservice,xaninations maybelimitedtoonevesseL100%ofeachweMtobecxaminecL Formukfpkvcssehofsiuuhrdesignsheandservke,eanhations neybeBmitedtoonevesseLABnoukstobeseketedatterndnalendsofpipingrunssekctedforexamination underCategories CF.landC.F-2.100%ofeachweMtobeexatrdnccL ManwaysandlendhokscxcludeLFormuhplevessehofsimihrdesign,she,andservke,examinations maybelimitedtoonevesseL100%ofeachareatobexataunetL Manwaysandhandholesarecxduded.FormuMplevesselsofsimilardesign,she,andservice,examinations neybelimitedtoonevesseLTheweldswiBbeexanuncdwithUT.NoCodercquircdNouksMVcssehaI/2.loch NominalThickness Nozzk-toSheB (orHead)WeMatLE.GinnLlheweMswillbeexaminedwithUTandMTorPTasappbcabk. ThenouleinsideraliussectionwillbeexaminedwithUT.H0(/)XErfgHXOOH~U0QHO(I)ItOO(2')ZLkf)H1-3'E)g04Ae'QzOXXU'PH'ElN0'E)C230GBC291GBNoukswithReinforcing PhtcinVcsseh>I/2inchNominalThkkncssRehtforcing PhteWekhSurheeSurfacetoNazetkVesselABnonksatterminalendsofpipingruns.Forrntdtiple vessebofsimBardesign,size,andservice,cxanhetions maybelimedtoonevesseLSeeC291,C232,C283Thereinforcing plateweMswiBbecxandnedwhhPTorMTasapplieab'k. (I)(B000 i Tabb2INSERVKXINSPECIION PROGRAMCLASS2COMPONEÃIS (Conc'd)ItemNtxExamination CategoryComponents andPansTobeExaminedExaminarion MetbxhExamination Reciuirements for'thirdInspection Intetva)Examination Technhiue/ExaminatIon AreaCommentsPRESSUREVESSEISCont'dCL32GBNozzle.ToSheB (orHead)N/AWeMsWhenInsideofVesselisAccessible ABnozzksatterminalendsofpipingruns.FormuhipkvessebofsimBardesign,sbe,andsavice,xamlnations maybelimbedtoonevesseLTheInsideofvesselisnotaccessible, perfornung CL33Instead.0C233CBC3.10GCCC.IOGDCy.IOGHCy20GHNozzk-ToShcB (orHead)Visual(Vl'2)WcldsIVhenInsideofVesselisInaeeessibk Integrally WeldedAt.tachments Prcssure. RaainingRobingN/A>2InchesinDiameterPressure.Recaining Compo-Visual(VT.2)PressureRetaining CompoVisual(VT2)nentsABnozzksatterminalerxisofpiphtgfur@.FormuhiplevcssebofsimBardesign,size,andservke,examinations cnaybelirnitcdtoonevesseLI0095oleachweMtobeexamineLAnachmencs whosebasematerhlis3/4InchorgreatercobesekaeLWheremultlpkvessehareprovidedwithanumberofsimilarattachments, theanachments maybediscributed amongthevesseh.Formuhiplevessehofsfnulardesignandsavice,examinations maybeBmhcdtoonevesseLABpressure-rccaining boundaries forvessebcobeexaminedduringsystempressuretest.Examinarions tobeperformed inaeeordance whhIWG522lforeachinspeaion pericxLABpressure. retaining boundaries forvessehtobeexaminedduringsystemhydroscack testorahernarively toCodeCaseNAPB.Examinations tobeperformed inaccordance withIWC.522I/5222atorneartheendoteachinspeaion intavalorduringsameinspection periodsofeachhtetvalVTexamfnarions willbeperformed Inaccordance whhIWB-524LB>>reluhcdcomponent tobeexaminedduringsystemleakagetest.TheweMedattachments willbeexaminedwithMTorPTasapplicable. Nopressure.rccaining vesselbohing>2InchesindiameteratILE.Cinna.VTexaminations wiBbeperformed inaccordance whhIWA5240.VTexaminations wiBbeperformed inaccordance withIWA.52C0. H0(/)XkEr)0cf)K(=)M)<o(/)I~I~cf)O~tOQ~tDH("I-Ig0QHCdAXErfU~H0'dm 'h itenNo.PIPINGC3.20CCComponents andPatsTobeExaminedlntegraBy WeMcdAuachmeas Table2NSERVVICE DISPECIION PROGRAM42/ASS2COMPONENIS (Cont'd)'Requirements forThirdInspection IntervalIOOIIofeachweMtobeexaminers Attachments whosebasematerblb3/4bchorgreatertobeselected. Selection Bmftcdtothosecomponems selectedunderExanunatbn Categories GF.IandGF.2.Examination Techruque/Examfnatbn AreaConunents 'IhewekbwiBbeexaminedwithMTorPTasapplicable. Qg>10CCMgCCCCPSYCHMRKOH0C4.20GDC5.10CF-IC5.11C5.12GF.IC5.20GFIC52IPressureRetaining Boking>2InchesinDiameterPipbgWeMsMAustenitic Stainless SteelorHigh-ABoypiphtga3/B.inch hommalWaBTIuckness forPiping>4NPS,Circumferential PipingWekbinAusteniYie Stainless SteelorHigh-AlbyPipinga3/8lochNominalWaBThickness forPiping>4NPS,Lon.gitudinal PipingWeMsinAustenftie Stainless SteelorHigh.AlbyPipingal/S.loch NominalWallThickness forPipinga2NPSands4NPS,Circumferential SurfaceandVolumetric SurfaceandVolumetric Noprcssure. retaining baking>2InchesindiameeratR.E.Ginna.Nobngkudfnal weMsoftlushennumberatR.E.Ging.IBIDofeachcircumfcrcntbl weMrcquiYing examination. SeeNoteIatendofTable2forselection criterh.'IheweMswillbeexaminedwithUTandPT.1009kofeachcueumferential weklrequiting TheweldswillbeexaminedwhhUTandPT.emnfnatbn. SeeNoteIatendofTable2forsebctioncrftcriL0MgHXOOH~U0u)HOMI+kf3O+tOHMHgR'EfN0CQQHCIEfOWraaQHdf330WLC522GF.IC520CF-IC5.40OF-IC5.41PipingWeMsinAusterdYic caaudessSteelorHigh.AlbyPipingal/5-Inch NominalWaBThickness forPipinga2NPSands4NPS,Iongkudinal SocketWeMsinAusteniYie StalnbssSteelorHigh-AlbyPipingPipeBranchConnections hAustenftb Stairdcss SteelorHigh-Alby Pipinga2NPS,Circumferential IOOIkoleachweldrequiring examination. SeeNoteIatendofTable2forsebctioncrucrh.100%ofeachcircumferential weMrequiYing examinatbn. SeeNoteIatendofTable2forselection criteri.Nobngitudinal weMsofthisitennumberatR.E.Ging.Theweldswillbe<<xaninedwithPT.0M800 g'PN itemNtxExamhation CategoryPIPINGcont'dCS.c2GF.IComponentsandPansTobeExamhedPipeBranchConnections hAustcniYie Stainless SteelorHigh-Alby Ptpmgs2NPS,lnnghudhal Examhation MethodsN/ATsbk2CHSERVICE INSPECllON PROCRAMflASS2COMPONENIS (Coca'd)Examhation Requirements forTtdrdInspection IntervalExamination Technique/Examination AreaCommentsNobnghudhal weldsofthisitemnmnberatiLE.Girma.Ag>IOH0Cx50GF-2CSSIC552C5.60CF.2CSAiIC5.62C5.70GF-2Cx80GF-2CRSIPipingWefdshCarbonorInw.AlbySteels3/8.InchNominalIVaBTldckness forPiping>4NPS,Circumferential andLongitudhal PipingWewsinGutenorInw.ABoySteel>I/5-InchNominalWalllhickncsu forPipings2NPSandirCNPS,Cfrcumfcrenriai andLongitudinal SocketWelChhCmbonorLow&bySteelPipeBranchConnections inCarbonorlnw.AlbySteels2NPS,Circumferential SurfaceandVolumetric N/ASurface100%ofeachciicumferenrial and2.5cofeachbnghudhaI weMrequhingcxanunatbn. SceNote2atendofTabk2forsekccioncriteria. Inaddition, 10Nliofthemahsteamandmainfecdwater wcldsbestedoutsidecontainmcnc andtraveling safetyareasshallbeexaminedperTechnhdSpcriTicacions. 100%ofeacheireumferential weMrequiiriing exsnunation. SeeNoce2atendofTable2Iorsekeuoncriteria. liewewswiBbeexamhedwhhUTandMT.Nocarbonorbabysteelnonexempt wewsinthhcategoryatILE.Ginns.Nocarbonorbwatbysteelnonexempt weldshthkcategoryatR.E.Cinns.TheweldsvriBbeexaminedwithMT.H0f/)ixiHEx)0cf)HUtf)~~ov)I+)wcf)O(2')<(/)~gQHRE)OXDRwaQH'E)fy)0ImC5$2GF.IPipeBranchConnections IllCsfboiiofLDW.ABoySteels2NPS,Inngitudhal Nobngitudhal weldsofthbitemnumberatILE.CinnLg0C720GHPressureReuuningCompoVisual(VT.2)Pressure.Retaining Compo.Visual(Vl'-2)Allpressure.retahhg boundaries forpipingcobeexandnedduringsystemprcssuretest.Examination tobeperformed inaccordance whhIVc&5221foreachhspcction pcrkxLABpressure.retching boundaries forpipingtobecxandnedduringsystemhydrostatic testorakcrnarivcfy coCodeCaseNA98.Examha.tiontobeperformed inaccordance wkhIN'O522I/5222 atornearthecndofeachhspeetion Intervalorduringsamehspection periodsofeachhtcrvaLVTexamhatbns mllbeperiormed inaceordancc withIWA.5240. VTexmninstions wBIbeperformed inaccordance withRVA.5240. 0(I)(B00 ItemNo.PUMPSCgaGCComponents andPartsTobeExaminedintegral/ WehkdAt.N/hcachmcncs Tabk2!NSEINICE INSPECIION PROGRAMt2ASS2COMPONDPIS (Cosa'd)Exanutioa Rccluftements forThirdInspccrion IntervalExination Tcchahlue/Examinarion AreaCnuaents10096ofeachwehftobe~hnachmems whosebasemateriaiis3/4inchorgreatertobesekctohSekctionlimitedtothosecomponents sekctcdunderExamination CategoryGG.NopumpsmeetthiscriteriaatR.E.Glans.Qg>10RR(I)QECCLQ~)H(/)CKOC430GDPressure. Retaining Bohing>2InchesInDiameterN/ANoprcssure. retaining pumpbohing>2InchesindiameteratLE.Ginna.C6.10CGCPA'NPressure. Reta'uung WeldsinPumpCasingsN/APressure. Retaining Compo.ncntsVisual(Vl'-2)PressureRetaining CompoVimal(VT-2)nentshllpressure-training boundaries forpumpstobeexaminedduringpressuretest.Exanunationtobepcriormcd inaccordance withIWC-5221foreachInspecrioa periohAllpressureretainiag boundaries forpumpscobeexanunedduringsystemhydrosratk testoralternatively toCodeCaseNAPILExamination tobeperformed inaccordance withIVTS221/5222 atorneartheendofeachInspccrion huesvaIorduringsamein.spccrionperiodsofeachintcrvahNopressure-retaining pumpweMsatLyGinnaVTexanunations willbepcriormcd haccordance withIWA.5240. VTexaminatkns willbeperformed inaccordance withIWAS240.0(/)gHtdOO~~U0cf)H0O)Igtf)O~tOQ~cg)H0QHXU~H'T)())0XIdn0 ItemNo.Examinarion CategoryVALVESC3AOGCComponents andPartsTobeExaminedIntegral/ WchkdAt.SurfacetathmentsTabk2NSSERVIcX INSPECIION PROGRAMCLASS2COMPONENIS (Cont'd)Examhation Requirements forlhhdinspection htenral100%ofeachweMtobeexamh<<LAuachments whosebasematerialis3/ihchofgreatertobesekcted.Sckcthnlimbedtothosecomponents seketedunderExandnatkn CategoryGG.Examhation Technique/Examination AreaCommentsTheweldswBIbeexaminedwithMTorPTasapplicable. ZC(C'0CIAOGDCy.70GHCTAOGHPressure-Rctahing Bolting>2InchesinNuneterPressure.Retahing WcMshVahreBodiesPressureRetaining Compo.ncntsVisual(VT.2)Prcssure-Retaining Compo.Visual(VT.2)Allpressure.retahhg boundaries forvalvestobeexaminedduringsystemprcssuretest.Examination tobeperformed haccordance whhIWG5221foreachinspectbnpcriocLAIIpressure.retatnmg boundaries forvalvestobeexaminedduringsystemhydrostatic testorahematively toCodeCaseNA9KExamina.thntobeperformed inaccordance whhIIVG5221/5222 atorneartheendofeachinspectionimervalorduringsamehspretionperiodofeachint<<vaLNopressure-retainhg bohing>2hcheshdiameteratLE.Ghna.Nopressure. retaining wcidshvalvebodiesatLE.Ginna.VTexaminations willbeperformed inaccordance withIWA.524LVTexaminations willbeperform<<l inaccordance withIWA5240.H00)gH(x)0o~~+QHUtf)~<o(f)I'dgtf)OLOQ~tOH(/)H~0QHaC'E)OXwa~H0Z

TaMe2(I)TheweMssekctcdforexamination shallInclude7.5%,butnixkssthan28weMs,ofallausteniuc tainlesssteelorhighutBoy weMsnot<<xemptcdbyIWG1220.(SomeweMsnocexemptedbyttusCasearenotrequiredtobenondesuuctively examinedperExamination CategoryGF.I.Thesewelds,however,shallbeincludedlnthetotalweMcounttowhichthe7.5qbsamplingrateisapplied.) Thecxanunatlons shaBbedistriliuted asfoUows:O(a)theexanunations shallbedhtributed amongtheQass2systemsprorated, tothedegreepracticable, onthenumberofnonexempt austeniYie stainksssteelorhigh.alba weMsineachsystem(Le.,ifasystemcontains30qbofthenonexempt weMs,then30%ofthenondtcructive examhtations requhedbyExamination CategoryGF.IshouMbeperformed onthatsystem);(b)withinasystem,theexaminations shallbedistributed amongtcrtrdnai ends[seehote(3))andstructural discontinuiYies [seeNoce(4))prorated, tothedegreepracticable, onthenumberofnonexempt ternunalendsandstructmul disconthtuhies inthatsystem;and(2)(3)(c)whhhteachsystem,examhtations shallbedistnl>utcd bctwcenhneskcsproratedtothedegreepracticable. TheweMssekctedforexambation shallhclude7.5%,butnotlessthan28weMs,ofallcarbonorbw~weMsnotexempccdbyIWC1220.(SomeweMsnotcxemptcdbytidsCasearenocreqtdrcdtobenondestructively examine!perExamhtation CategoryGF.2.TheseweMs,however,shallbeIncludedlnthetoadweMcomutowhichthe7.596samplingrateisapplied.) Theexaminations shallbedistributed asfolbwst(a)theexaminations shaBbedimibutcd amongtheCLsss2systemsprorate,tothedegreepracticable, onthenumberofnonexempt ear[enorhiwaBoyweMsineachsystem(Le.,ifasystemconttdns30%ofthenonexempt weMs,then30%ofthenondestructive examinations requiredbyExanunation CategoryGF-2shouMbeperformed onthatsystem);(b)withinasystem,theexambtations (hallbedistnliuted amongterminalends[seeNote(3))andstructural discontinuitks (seeNcce(<))prorated, tothedegreepracticable, onthenumberofnonexempt ternunalendsandstructural discontinuhks inthatsystem;and(e)withineachsystem,exandnadons shallbedistributed betweenlinesizesproratedtothedegreepractkabk. (d)OnlythoseweMsshowingreportable preservice transverse indkations needtobeexaminedfortransverse rellectois. TerminalEnds(TE)aredefinedMTableINotes,notenumberl.Structural DiseontkuiYies (SD)aredefinedinTableINoccs,notenumber2.ThefoBowfngwcMtypesareidentified MSupplement ItoAppendixB,theProgramPLtn.'EATerminalEndataPipingAnchor'KBTerminalEndataBranchConnection

• TE.PTemunalEndataPumpConnection

~TE.VTemunalEndataVesselConnection ~SDSuuctural Discontinuhy PPPipetoPipeButtWeM'EAldLongitudinal SeamWeMNote:WhenmorethanoneweMrypekapp!ieable,themorerestrktive (i.e.TE)isutilized. H0(f)gH[x[Oo~~cf)Ha~<+O[f)['d+cf)Otdtf)~R0g0QHIc([O[x)XU~H'dN0L0r.00 tvgWI ItemNo.TheASVESectionXIRemNo.andCateEoryofthecomponent arelistedinthesecolumns.Components andPansTobeExaminedEachtypeofexamination areaislistedintidecolumn.TheNDEmethodrequiredtosatisfyCoderequirements islistedinthiscolumn.SNSERVICE INSPECTION PROGRAMCXXK(IJISSExamination Requirements forThirdInspection ImetvafThiscolumnprovidesInformation regarding thenumberandforpercentofexaminations requiredtobeperformed fortheInspection IntervahExamination Technique/Examfnadon AreaCommemsTldscolumnprovidesInformation spcciTictoexamination techniques, examination areas,orcouuucnts. RCCV~~gHV)NK0H00MXHWOoOH~tErHOMI~tdyOtEst3>u)H~HeQHIOWErfUdfXI0d0Ct0 ~It Tabk3itemNtxExamlnarion CategoryCLASS3COMPONENTS Components andPansTobeExaminedExanunation MethodsExamination Requirements forThirdInspcctlotllluelvalExamination Tcchrdqaelgxamlnarion AreaCommentsRCC~Ob3Dl.10DAD2.10D-8D3.10DCD120IMthroaghDIMD2.20D3thoughD2X4D3.20DCthroughD3.60IntegralAttachments ofSupponsandRestraints, Hydraulic

Snubbers, Spring,ConsamtLoad,andShockAbsorbers Visual(VTQ)prcssure.Retaining CompoVisual(VT2)Allcomponents tobeexamineddaringsystempressureorsystemhydrostatic testasdefinedbyIWD-2500ITableDescriptions.

Examfnarion tobeperformed inaeeordanee INq)-5221 foreachinspection periodandperformed onceeachintervalinaccordance whhIWD.5223. AIIrequiredanachments tobeexamineddaringeachinspection IntervalasdefinedbyIIVD.2500 ITabkDeseriptions. Formultiplecomponents inasystemofsin8ardesign,fusion,andservice,theintegralattachment ofonlyoneofthemuhpkcomponents shallbeexamined. 1hektegralanachments selectedshallcorrespond tothosesupportcomponents selectedforcxandnarion inactor.dancewithIIVF-2510(b). VTexandnations willbeperformed inaceordanee withIWA.5240. H0(I)gHWOOH~0HUt()~>o(f)I'E)+tg)O~'))-3Lt()HdQHC'0OX0Rwa0rmQ0 IIII'~N~hV<<->~~llr1~~ itemÃo.Examinsuon CategoryTheARVESectionXIItemNo.andCategoryofthecomponent arehstedinthesecolmnns.Components andPartsTobeExaminedEachtypeofexamination areaishstcdinthiscolmnn.TheIIDEmethodrequiredtosatisfyCodererfufrements islistedintldscolumn.~nRepurements forThhdInspection intervalThiscolumnprovidesInformation regarding thenumberand/orpercentofxaminadons roiuiredtobeperformed fortheInspection IntervahExandnation Technhiuef Examination AreaCrnmerusThiscolumnprovidesInformation spceiTictoexamination tcchnhiues, cxaminauon ~ofcommentnQgPNRRMQECCLAH0H0CQgHWOoOHU'LOHOMIdId'+LOQ>tg)HMH~XI0CQQR'dCMOtrfeUEf%0dMID0I0 BNSERVICE INSPECI)N PROGRAMC1JISSI,CJASS2,AND(1ASS3COMPONENT SUPPORTSitemNtxComponents andPartsTobeExaminedExamination Requirements forThirdInspection IntervalCIASSIAND3IWFCOMPONENIS SUPPORTSFROM1990TO1993OUTAGEUSINGIWF1986CodePIATEANDSHEILTYPESUPPORUNEARTYPESUPPORTSANDCOMPONENT STANDARDSUPPORTSxamlnadon Tcchrdqtu JXamfnatmn AreaConunents Qg>10RR(I)0R(((I)O0F1.10F.AthoughFI.40F2.)0F-BthoughF2.40F3.10F<throughFATSOMechanical Connections toPressure-Rcaunfng Compo-nentsandBuiMingStructure; WeMConner.tionstoBuiMingStructure; WeMandMechanical Connccdons atInterme.rUateJointslnMuftf-connectcd IntegralandNonintegral Supports; andComponent Dlspktcement SettingsofGuidesandStops,Misalignment ofSupports, AssemblyolSu.pportItems;SpringTypeSupports; ComtantLoadTypeSuppotts; ShockAbsorbers; Hydraulic Type5nubbersVisual(VT4)Component supportstobeselectedforexamlnadon arethesupportsofthenonexempc (2assI,2,and3components scheduedtobexaamfnerL Examination boudarlesestablished iusecordamwkhIWF-130th Examinations maybeperformed duringnormalsystemoperation orplantout.agesFuncuonal testingofsnubbertypesupportcomponents shaBbeperformed inaccordance withTeciudcal Specifications andlnaccordance withrequirements ofthisprogram.ItemNo.Components 8PartstobeExaminedExamination MethodExamination Requirement fortheThirdintervalExamination Techniqucrgxamfnation AreaCommentsCLASSI.2.AND3IWFCOMPONENT SUPPORTSFROM1994TO1999,USINGCODECASEN491ANDIWF1986CODEH0(I)LHXOO~~a0tf)HO(I)Itf)O>tf)~g0QH('dOXwa~H'EfW0'dFI.10F-AClassIpipingsupportsVisual(VT3)25%ofClassIsuppottsFunctional testingofsnubberrypesupportcomponents shallbeperformed inaccordance withTechnical Spccilkations andinaccordance withrequirements ofthisprogram.F120F.AClass2pipingsupportsVisual(VTB)1546ofClass2supportsF120F-AClass3pipingsupportsVisual(VT3)I0%ofaass3supportsFI40FAChssI,2,53supportsVisual(VT4)10ryrtrexceptformultipleotherthanpipingsupportscomponents. (DnV0 QUALITYASSURANCE MANUALGINNASTATIONISection5EFFECTIVE DATE:REV.'AGE31of96December31,1993ROCHESTER GAS&ELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWER'PLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVAL~LINELISTPREPAREDBYQUAUTYASSURANCE REVIEW:APPROVEBY:(Z-Z-)1.0GeneralThefollowing linelistwasdeveloped utilizing ASMESectionXIRulesandCriteriatoidentifyallClass1,2&3exemptandnon-exempt items.Thislistfurtheridentifies non-exemptpipinglinesandcomponents,,type ofnondestructive examination requirements aswellasproviding alinedescription. Visualexamination forleakage(VT-2)boundaries arenotaddressed inthisSection,butshallbeadministratively confirmed bytheresponsible Rochester Gas&Electricorganization beforeimplementation. ThelinelistisgroupedbyP&IDDrawingNumber,Class,System,andComponent Type.Thisinformation appearsoneachpageoftheLineListontheupperlefthandcorner.TheComponent Typedescription definestheinformation aseithercomponents orpiping.Ontheindividual pages,uniquelinenumberswereidentified thatcorrespond toadescription ofaparticular segment.Otherrelativeinformation listedwithineachpageofthelinelistincludesISIFigureNumbers,materialtype,pipesize,wallthickness, applicable codeexemption basis,typicalexamination (NDE)methods,applicable operating pressureandtemperature, aswellascomponent insulation information. Therevisionstatusof"R"shallindicatethatachangehasoccurredanywherehorizontally forthelinenumberinquestion. ARevisionStatusof"A"indicates anewentrywasmade.Avisualrepresentation ofthelinenumbercanbeseenonthecorresponding P&IDcontained withinSection3.Lines1"andunderarenotshown.However,theyareidentified inthelinelistdatabase. RE.CINNANUCLEARPOWERPIANTInservke~nBoanderyLIneLbtThhdIaspecaoa IntervalP&IDNor33013-1231 Chssr2System:MAINSIEAMCompTypmCOMPONENIS RG&EIIneNo.EMSOIAEMSOIB151Size~Fi.MstrL~la.B-lBlOANOAXXIOAR0.000SUR/VOL715505-SIErWCENERATOR* SUR/VOL715505~STEMGENERATOR KThknsExemption NDE~la.BssaMethodPo~Ternln?LbedeserirernsrhsRevisedR1I/91RII/91OH0H0MXHWO+LI?HVHLIyggOMIHeOMLI)HtdyQ0H2g tC LE.GINNANUCLEARPOWERPIANTInservise Exanrination BsnnnhnYUneUstThiniIspectionIntervalPAIDNot330131231(2asst2S)sterntMAINSTEAMCompT)TresPIPINCH0RCAElineNo.CEbertlineNo.ISISizeThhns~F1.MrnrI~in.~In.NDEMethortPo~TernIntlinedeseri'ernarhr30A-M$600-IA30B.M$600-1B6AMSGR'.IA6h-M$600IB6B-M$600.IA6B-MSSS.I B6GM$600.1A6OM$600-IB6D.M$600-1A6D.M$600IB6LM$600IA6LM$600IB6EM$6N.IA6F.M$600-1B6G-~IA6G.M$600.IB3A.M$6N.IA3A-M$80IB2A.M$60alh2A.MS600-1B ISA-M$600.1h1$A-M$600.1BISB.M$60alb1$B-M$600.1BISCM$600-IhMS-100MS-200MS.100MS300M$300MS120MS300MS300MS300MS300M$300MS300MS300MS300M$300M$300MS300MS.1000SMS-1001MS1000SMS-1001MS.1000SM$1001MS-1000SMS1001MS1000SM$1001MS-1000SMS-1001MS.1000SMS-1001MS.1000SKS.1001MS-1000SM$1001MS-1000SMS1001MS-1000B333B-9AB.IOB-9hB-IOB.9hB10B-9hB.IOB-9hB.IO*B.9AB.IOB-9AB-IOB9AB10B.9AB10B-9B.IOB-9hB3BBA115A11$A106A106A106h106h106hl06h106hl06h106A106A106A106A106A106A106A106A106A106A10630AOMSO30Aml~6Ama4326AO0.4326Ama4326.000.432MO0.4326.0004326Am0432MOa432MOa432MO0.4326Am04326AO0.432M0a4326'4323'3003'3002AXtOANO2Ama000IM0.145IM0.1451$00.147180OAXN1500.000IWC.1222(A) IViZ1222(A)IWC.1222(A) IS&1222(A) IWC.1222(A) IWC1222(A)IWC1222(A)IWC1222(A)IWC1222(A)SUR/VOLSUR/VOLBUR/VOLSUR/VOLSVR/VOLSUR/VOLSVR/VOLSUR/VOLSUR/VOLSUR/VOLSVR/VOLSVR/VOLSUR/VOLSUR/VOLBUR/VOLSUR/VOI71550571550571550571550571550571550571550571550$715505715505715505715505715505715505715505715505715505715$0$715505Y715$05Y715$05Y5/GIA10VALVE3517.5/GIBTOVALVE3516.30'SPIPETOVALVE3505A.30'SPIPE10VALVE3504A.3(PMSPIPE10VALVE3411.30'SPIPE10VALVE3410.3(7MSPIPETOVALVE3509.30'SPIPETOVALVE3508.3(7MSPIPE10VALVE3511.30'SPIPETOVALVE3510.30'SPIPETOVALVE3513.30'SPIPE10VALVE3512.30'SPIPETOVALVE3515.30'SPIPE10VALVE3514.30'SPIPE106X2REDUCKL30'SPIPE106X2REDUCEII30MSPIPE10VALVE3615(3517BYPASS).30'SPIPETOVALVE3614(3516BYPASS).6G-M$600.1ATOVALVE3521.6G-MLSIBTOVALVE3520.30'SPIPE10VALVE34556A.MSCi00 IBTOVALVE3504C.6A.MS600Ih10VALVE3505C.30'SPIPETOVALVE3$0a30'SPIPETOVALVE3503.R11/91RII/91RII/91R11/91RII/9IR11/91Rll/91R11/91R11/91R11/91h11/91A11/91R11/91R06/93R06/93H0(/)XHtd0+QHHIOgO(/lH'N0g'LOH0Hg50e"QOX0(/l(()0Ft00 lfII'lItI~ lLE.GINNANUCLEARPOWERPIANTlaserioeExamhstha BoundaryuneurtTldrdIaspecdoa IntervalRGREuNGBbertIIneNo.PdrIDNo:33013123IChss:3System:MAINSlEAMCompType:COMPONENIS ISISize~FI.Metrl.~h.TwasRremptioa NDE~in.BasisMetlrodPo~TernIn?unedeseri'ennsrlrs NIAOAROAXONOIWA;VTDTURBINEDMVENAFWPUMPTURBINE.RobedAIUPIOH0gH0MXHXO+LOHrHtOg0U)(HIDE%0~eHoH2g5%gHMID0Pe00 R.E.GINNANUCLEARPOWERPIANTnsservire Examinadon BoundaryUneUstThirdInspeenon IntervalPSIDNot33013-1231 Chtss.:3System.sMAINSTEAMCompType:PIPINGROSEUneNo.GUbertUneho.SWRIUneNo.ISISize~Fi.MatrL~in.NDEMethodPoT~emIn?Unedeseri'/remarks 30A.M$600I30B.M$6fOI8A-MV-150 I6A-M$600I6B.M$6M-I6GMS600I4A-MV.150-1 3A.M$600I3B-M$600.13CM$60alISA.M$6NII8B-MS600.1 ISGM$600IISD.MSCi00-1 MS.120MS.120MS.120MS-120M$120B.9Ahll5810hl15N/hG32A106G32A106G32h106N/AG32h106B.9hAl15810A115G32A106G32h106B-9AhlI5B.IOA115Ba003aoo&00&00&006lO4AO&00&00&00MO180150MOIWD.1220.1 IWD-1220.1 IWD-1220.1 IWD1220.1IWD-1220.1 IWD1220.1IWD1220.1IWD.1220.1 l~NOIWA,1~NOIWAOAKONOIWAOA32OA32F32a000IL216(L216tL216ale0.1450.145IL145715505Y715505Y1085508Y1085508Y1085508Y1085508715505715505lOSS5081085508715505715505VALVE3517'IOREDUCERATVALVE3519.VALVE3516TOREDUCERATVALVE351LAFWPUMPTURBINEEXHTOATMOS.3505ATO3505K35IMATO3504IL6A8:6BIO3A.AUXFWPUMPTURBINEQUENCHTANKTOBA.6CTOAUXFWPUMPTUBELIKEVALVE3615TO30A.MSCi00.1. VALVE3614'IO30B-M$600.1.3505CTO6A350K'IO6K30A.M$600ITOVALVE8527.308M$6MITOVALVES52LA06/93h06/93A11/91RII/91AII/9IR11/91A06/93A06/93RII/91RII/91A06/93AOdr/930VlgHWOt0+LDHHID~OV)WLu)nvXHtotggtDH0HQQOgH0

ILE.GINNANUCLEARPOWERPLANTIaservkeExautlnathn BoundaryUneUstThirdInspecUon IntervalPAIDNo..:33013.1231 I2asstHE.2System.tMAINSTEAMCompType:HFPIPINGtAPP.BRUBEuNSWRIUneNo.ISI~Fi.MatrLPo~Terntn?UnedeseriremaAsOH030A.M$600.1A30B.M$600IB6AM$600lh6A.M$600IB6B.M$600.IA6B-M$600IB6CM$600IA6GM$600IB6D-M$600.IA6D.MS@00IB6E.M$400-1A6E-M$600-IB6FM$600IA6EM$600IB6GM$600IA6G-M$600.1BMS100MS200MS100M$300MS300MS.200MS300M$300MS300MS300M$300M$300MS300MS300MS1000SMS1001MS.1000SMS1001MS.1000SMS1001MS.1000SMS.1001MS.1000SMS-1001MS-1000SMS1001~MS.1000SMS.IOUISMS.1001HE.Ih115HE.2AAIISHE-IAA106HE.2hl06HE-IAA106HE.2hl06HFIhh106HE.2A106HE.IAA106HE2A106HE.IAA106HE.2A106HE.IAh105HE.2AI06HE-IAA106HE.2A1063MO1350BMO13506.00OA326.00OA326.00OA32ASOA32AS0.432600OA326AOOA32600sL4326ASOA32600OA32600tL4326AOOA326'A32650OA32SUR/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUB/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUR/VOLSUB/VOLSUR/VOL7155057155057155057155057155057155057155057IS5057155057155057155057155057155057155057155057155055/GlbTOVALVE3517.5/GIBTOVALVE3516.30'SPIPETOVALVE3505A.30'SPIPE'IOVALVE35IMA.3IPMSPIPETOVALVE3411.30'SPIPETOVALVE3410.RPMSPIPETOVALVE3509.3tyMSPIPE'10VALVE350IL30'SPIPETOVALVE3511.30'SPIPE10VALVE351(L30'SPIPE10VALVE3513.30'SPIPETOVALVE3512.30'SPIPE10VALVE3515.30'SPIPETOVALVE3514SsyMSPIPE10VALVE3521.30'SPIPETOVALVE3520.R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93H0UIgHtd0+'4HOT/IHIEIgto0+u)H()H4OWR5gHM800 Rt'ItjWt ILE.GINNANUCLEARPOWERPIANTInrertdee Ezamhathn BoundaryLheIlrt'IIdrdhpectionIntervalPAIDNa.t33013.1231 ChartHE3S7rtemtMALISTEAMCompType:HE-PIPING: APP-BOH0RUTElheNo.30A-MS600 I30B-MS600.1 0BbertUneNo.ISI~Pi.MatrLHE.IAAIISHE-2A1153IL00I~30.00I~SUR/VOLSUR/VOL715505Y715505YVALVE3517TOREDUCERATVALVE3519.VALVE3516TOREDUCERATVALVE351LSizeThlarrExemption NDE~h.~h.BariaMetlrodPo~TernIn?Lhedereri'ernaritr RcvbedA06/93A06/93H0MgHWO+tOHHH3gOEIIHIE?O+II)HtOQ0HgOXxagH0

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LFGINNANUCLEARPOWERPIANTInservloe Eaunlnndoa ~IIneLhtlldrdInspeedoa laterralRGBEUneNo.CBbertSWRIUneNo.IIneNo.PSFOIAPSFOIBPMDNo..r330131238CLsss:3System.:STANDBYAUXIIJARY FEEDWATER ComplYPe:COMPONENIS ISIShe~Fi.MatrL~is.N/hN/AlMtnsExemptioa NDE~in.BashMetirodPo~TernIInlUnedeseri'/remsrlts OAXONOIWAVT4STANDBYAFWPUMPC.IXOOONOIWAVT4STANDBYAFWPUMPD.RevtedAII/91A11/PlOCdH04H~OM~gQsosHQCdOCHLI3<5<+OthOCd~HgRaHIOASWIOHoweHgO4A'tfMtDn0 IIE'lPltII'J4llIlI1IIIIItIIEl ILE.GINNANUQZARPOWERHANTInservkeExamlnadon BoundaryUneUstTidtdInspecdon Interval9&IDNo:33013.1238 Qass.:3System:STANDBYAUOUARYFEEDWATER Gnnp~tPIPINGH0RG&ElineNo.4ACD.152S 4A.FW8.1525-A 4A.FWB152SBdfKD.I52S3A-FWB902S-A3A.FWB902S.BBOFWB-9025 MAFW8902SISB.FW8.9025 GBbettSWRIUneNo.UneNo.151~Fi.MartiC2&hA106G28A106G28h106C28AA106C.22A106C22A106G23A106G22A106G22AA1064AO0200NOSURPORTS4AO03004AO03004AO0300NOSUPPOR'IS 3AO03003.0003003.000200IM02001500200NDEMethodPo~TernIn7Linedeserl'emartts9707hTO4A.FW81525-*9629hTOSIBYAUXFWPUMPCSUCIION.9629BTOSIBYAUXFWPUMPDSUCIION.9707BTOeh-FW81525.ILSTBYAUXFWPUMPCDISCHARGE TO970th.STBYAUXFWPUMPDDISCHARGE 'IO97041L3A.FW8-902S-A TO3A.FW8-902$ K3A.FW&d02S.A TOLFWOL3A.FW8-9025-B TOLFW07.R06/93RII/91RII/91R06/93RII/9IR11/91R11/91R11/91R11/91H0F/IgHXO+tOHHUIgOMtOOHtOgIOHoHgR'dgH It'tIIt1rIIj1JlFa'II,'IIIIKII' ILE.CINNANUCLEARPOWERPIANTIsetxtlte Examlnathn BotmdstyLineUstIh(n(Inspect&a IntervalP&IDNot3301312391 aasst3System.:DIESELCENERATORS CompIYpmCOMPONENIS RC&EUneNo.SWRIlineNo.ISISiseIhkns~FI.MatrL~In.NDEMethylPo~TernIntUnecieserinlremarhs 0H0ESWOSAESW09AFDGOIFDG02FDG03FOAMFDGOSFDC06FDC07KDGOIAPDCOIAPDG02APDG04APDGOSAPDG06APDC07APDGOBSDGOIATDGOIAIDC02ATDG03AIDG03BTDGOehC37NlhN/hN/AN/ANlhNlhNlhNlhN/ANlhN/AN/AN/AN/AN/hN/AN/ANlhN/AN/AN/AN/AOASOAXSOAOOASOOASOAXSOASOAXOOASOAXO0.00OASO0.00OAXO0.00OAXS0.00OAXO0.00OAXSOAOOASO0.00OAXSOASOAXOOASOAXOOASOAXSOASOAXSOAOOAXOOAOOAXSOAO0.0000.00OAXOOAO0.000OAOOASOOASOAXOIWD.122IL IIWD.122shl IWD1220.1IWD1220.1IWD1220.1IWD.1220.1 IWD-1220.1 IWD1220.1NOIWANOIWAIWD-1220.1 IWD-1220.1 IWD1220.1IWD1220.1 IWD.1220.1 IWD.1220.1 NOIWAIWD-1220.1 IWD.1220.1 IWD.1220.1 IWD.1220.1 IWD-122thl DIESELGENhJACKETWATERHEATEXCHGLDIESELGENALUBEOILCOOLELDIESELCENhPRMARYBL'KLDIESELGENAPRIMARYFIL'KLDIESELGENASECONDARY BLTELDIESELGENASECONDARY FILTELDIESELGENALUBEOILBLIELDIESELCENAINTAKEFILIELDIESELGENAINTAKEBLIELDIESELCENERAIOR

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R.E.CINNANUCLEARPOWERPIANTInservlte Examlnathn BonnrhryLheUrtTMnIInspection IntervalPMDNot330131239-2aass..:3System:DIESELGENERATORS CompType:PIPINGOH0ROSEUneNo.GBbertLheNo.ISIShe~Fi.MstrL~h.NDEMethodPoT~emIn?Lhedeseri'/remarks 20A.DCISHB203-DG-150eB SADG-BSBDC-BSC.DG-B3A.FO-1506B 3B.FO1506B2A.FO1506B2ASA.150' 2SFO.150632GFO.1506B 2D.FO150431$A.FO1506B1$ASA.I~B1$A3W.125IB1$B-IO1506B1$CFO.1504BISD.FO1506B125A.PO-1506B N/hA53G4)A53G36G36G36N/AA53N/AA53N/hA53N/hA53N/AA53N/AA53N/AA53N/AA53N/AA53N/AA53N/AA53N/AA53N/AN/A2IL0020ASSAICSANSAN3'.002AS2'AX?2AO2.001$01.501$01$01$0IM02500250OAXSOAXSOAXO0416OA3S0.1450.1450.1450.1450.1450.1330.1330.133(11330.1330.1330.133NOSUPPORTSNOSUPPORTSNOSUPPORTSIWD.1220.1 IWD.1220.1 IWD1220.1IWD1220.1IWD.1220.1 IWD1220.1IWD1220.1IWD1220.1IWD1220.1IWD-1220.1 IWD1220.1IWD1220.1IWD1220.1IWD.1220.1 VT3VT3VT3VT3VT3AIRINTAKEDGILAIREXHAUSTDGIILJW-HX-BTOJWPUMPSUCT.JWPUMPBDISCHG'IODG-LDG-BREIURNUNETOJW-HX-LDIESELOILSIORAGETANKTO5956,2'ED.2DTOOILTRANSFERPUMP.1$ATODIESELOILSTORAGETANKLAIRRECEIVERS BlRB2TO5906AStS,5975OILTRANSFERPUMPTO5966S5976.1$A'IO5967Bt5960.3ATO3ILDAYTANKBTO5960B,2A,2ATODGBAIRSTARTINGMOTOR.5900BTOCOOUNCWATEREXPANSION TANK.I~TOIA.5914TO5910Ik3A.5966TOI*1$3TODAYTANKLR06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93HCIUlXHXO+'LOHHexoMtOOHIDE'LJ3HpHggHImVl80b400 Pf4 KE.GINNANUCLEARPOWERPLANTInserviee Examinatbn BonndatyUneUstThitdSspeetion ImetvalP&IDNot33013.1245 CLsss.t2SystemtAtMUARYCOOLANTCXW CompTYpe:COMPONENTS Otd0RG&EUneNo.PACOIAPACOIB12471247ISISize~FI.MatrL~in.410350410350THISCOMPACCOUNTED FORON33013-1247. h11/91THISPUMPACCOUNTED FORON33013.1247. h11/91T?dtnsExempdonNDE~in.BasisMethodPo~TernInIUnedeserln/remarks RevisedOMQHWO+IOHH~gOMw,~tDOHIDEIOHpHgOW0MtD0fpr.00

• 11llIID ILE.GINNANUQZARPOWERPLANTInsessloe Exnmlnnaoa OanddttyUneUstlMtdInspeedoa Itnesval9&IDNot33013-1245 Qnss.t3System:AUXIUARYCOOIANTZCW CompTypesCOMPONKNIS H0RGREUneNo.EAC01EACOIAEACOIBEAC02AEAC02BKAC04AEAC04BEACOSAKAQ5BEACOSCEACOSAFAC06BESS04AKSS04BKSS04CESS040PAC02APAC023TACOIGRhettSWRIUNllNLSI~FI.MsttLN/hCAI~1B.109$-109N/AN/AN/hN/AN/hN/AN/hN/AN/AN/AN/AIWD1220.1IWD.1220.1 IWD-122aIIWD1220.1IWD1220.1IWD122alIWD.1220.1 IWD.1220.1 IWD.1220.1 IWD1220.1IWD.1220.1 NOIWANOIWA080OAXOIWD.I~IOAOCACAOOAOOAXOOAX)0AXOaooolxoaoo0AxoOAOOANOOANOAXOOASOAXOaooaoooOANOAXOOAOOAXOOAOOAXOaooaooo0.00OAXO0.00OANO0.00OAXO0.00OAmoaooolxoNDEMethodVTQVTDN/hN/A<275<200<275<200<<275<<200<275<200<275<200<275<200<275<200<275<200<275<200<275<200FAIIZDFUELRADMOhlit)RHEATKXCHGILCOMPONENT COOUNCWATERHEATKXCHGR*COMPONENT COOUNCWATERHEATEXCHGRLRHRHXAACCOUNlTD IQRON33013-1247.

RHR.HX.BACCOUNTED FOROV33013-1247. S/GBLOWDOWNSAMPIZHEATEXCHGRA.5/GSLOWDOWNSAMPIZHEATEXCHGRLPRESSURIZER LIQUIDSPACESAMPLEHE.RCIZCPBHOTLECSAMPLEHEATEXCHGR.PRESSURIZER STKALISPACEShldplEHE.RHRPUMPCOOLERA.RHRPUMPCOOlERILPOSTACQDENTSAMPIZCOOLER*POSTACQDENTSAMPIZCOOLERLPOSTACQDENTSAMPLECOOLERC.POSTACQDENTSAMPLECOOLERD.COMPONENT COOUNCWAlERPUMPh.COMPONENT COOUNCWATERPUMPILCOMPONENT COOUNCWATERSURCETANK.A11/91AII/91A11/91A11/91A11/91A11/91A11/91AII/91h11/91A11/91h11/91h11/91A11/91A11/91A11/91A11/91ROl/92ROl/92A11/91QMXHXAHMlg0Mw,~I-IeIIIIHLOQHg0g0<<"QM80rtI00 t, ILE.CINNAhVCIEARPOWERPLANTInserviee Buunlnadon BoundaryUneUstThirdInspeedon IntervalPMDNo..:33013-1245 CLass:3~em.tAIDGUARYCOOIANTASW CompI7petPIPINCOb30ROBEUneNo.GEbertUneNo.SWRIUneNo.NDEMethodInlI4APCS.15214BAGS-15214GAC5.152 IOA4CS152IOBACS152IOGAC5.152 IODACSIS2IOEACS.I52IOMC$152IOG*CS-IS2IOHACS.152 101*C$.152IQMCS152IOK.AC5.152 IOLACS1528A.AC5-152 8BAC$1526A4CS.1524AAC5.152 4BAC$1524GACS.1523lWLCS-152 3BACS-1$23GACS-152 3DAC5.152 3SACS.1522A4CS.152 2B4C$1$22GAC$1522DAC$1522EACS1522FACS.IS2204CS-I522H4CS-I522I.ACS1522J4CS1522KACS15213hAC5.152LSILACS-152 I3GACS-I52CC.100CC200CG300OC100CC100CGIOOCC100CG200CG200CC200CG200CGIOOCGIOOCC240,120CG240,120 CG14IL180 CC170,180N/hN/hN/hN/AN/AN/hN/hN/AN/AN/AN/hN/hN/hN/AN/AN/AN/AN/AN/AN/hN/AN/AN/hN/hN/hN/AN/AN/AN/AN/AN/AN/AG2G4G6C2G2G2G2G4G6G6G6G6G4G2G2G6G2G4G6G4N/hG6N/AN/AG4N/AN/AG6N/AN/AN/hN/AG6G6N/hN/AN/AN/A14AS14AS14ASIOASIGASIOASIGASIGASIGASIGASIOASl(LOO10.0010.00IGAS8AS8.006AS4AS4AS4AS3AS3AS3AS3AS3AS2AS2AS2AS2.002AS2.002.002.002.002.002.00130130037503750375036503650365036503650365036503650365036503650365036503650280023703370337IL21602160216031602160.1$40.1540.1540.1$4(L1540.1540.1540.1540.1$40.1540.154O.NS0.1450.145NOSUPPORISNOSUPPORTSNOSUPPORISNOSUPPORISNOSUPPORISIWD.I22ILIIWD.122sLIIWD-1220.1 IWDI22sLIIWD.1220.1 IWD1220.1IWD1220.1IWD-I22ILIIWD1220.1IWD.1220.1IWD-122ILI IWD-1220.1 IWD.1220.1 IWD1220.1IWD1220.1IWD1220.1IWD.122Q,I IWD1220.1IWD1220.1IWD.1220.1 IWD.1220.1IWD1220.1VTQVF4VT3VT3VT3VT4VT3VM'T3VT3VT3VT3VT3VT3VT4VT3VT4VT3<150<150<150<150<150<150c150<150<150c150c150c150<150c150<<150<150c150<150<150<150<150<150<150<150<150<150<150<150<150c150c150<150<150<150<150<150<150<150<150<150<200<200<200<200<200<200<200<200<200<200<200<200<200<200<<200<<200<200-<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<<200<200<200<20010X14RDCRFROMBCCPUMPTO10'DCRS.734BIO10'EDUCLNG ELLBEPORE738A.14'EEATRHRHEOUILEISIQCCPUMPS.VALVE723ATO14IEE,14AVALVE723BIO14X10'EDUCEIL N'EDUCERIQVALVE733A,CCHE*14'EDUCER TOVALVE7338,OCHEILCCHEAIOVALVE734A,14IL14BIQRHRHEIL14BIQRHRHEARHRHEBOUIIETTO14'EE.RHRHEhOUIIZTIQN'EDUCER. 14CTOCCPUMPASUCIION.14CIQCCPUMP8SUCIION.CCHEBIQ7348,14ILCCPUMPAIOVALVE723ACCPUMPBIOVALVE723IL14C'IQ4GIOCIOACAHHX.IOEIQACAPCP.CCSURGETANK'IO728,6/LDRAINFROM148IOSALIPLEHES.SAMPLEHES'IQ772D.772D'IOCCPUMPSSUCIION.CCSURGETANKIQ732.747HTO3CIOCIO707h,RHRPUMP*2AIQ7078, RHRPUMPILRHRPUMPBIQ7088,2D.RHRPUMPA1074lh,769,IOL699IQCCSURGETANK.CCSURCETANKIO731A.CCSURGETANKIO713.4CIQ823,729.740AIQIOL740BTO14GCCSURGETANKIORCVO17.3AIOVALVE747GVALVE747KIOIS,PASCOOLEILIS,PASCOOLERSIQVALVE747F.R11/91RII/91RII/91R11/91R11/91RII/91R11/91RII/91RIV91R11/91R11/91R11/91RII/91RIV91R11/91R11/91RIV91R01/92RIV91RIV91R11/91R11/91RII/91AIV91R11/91RIV91RIV91R11/91RII/91RII/91RII/91RII/91AII/91A11/91AII/91All/91A11/91AII/91H0V)XHX0+tOHHUIgOVlg'QH0Hgg0<"Q0OPd0(0IDnr.0 Cllt(W44PlN~'II'i1'Le'C),Ill4'(k~~~'~t*IAt&h'I;f' ILE.GINNANUCILARPOWERFIANTlnrervkeExamination BonndaryUneLbt'IhlrdnrpeenonIntervalPKIDNot33013.1246-I CleartIEpactAUXIUARYCOOIANT~CompTYperCOMPONLNIS O0RGStEUneNo.GBbertSWRIUneNo.UneNo.ISIShe~pi.MatrL~h.%Mt'xemption hDE~in.lhsisMethodPo~TernIn?Unedesert'ennarlsRevisedPRCOIAPRCOIBA.7h-7SUB/VOL5UR/VOL'IHISPUMPACCOUNIED fORON33013-1260. R06/93THISPUMPACCOUNIED fORON33013126aR06/93H0MgHROHIE)H~'LOQgOMIU3OMHII2g~'LDH0HgQHOX0g0CQM8nr.00

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IOA-AG60110VALVE252.10-AG60110IOB.AG601. 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THISCOMPACCOUNIKD FORON33013.1239. THISCOMPACCOUNTED MRON33013.1239. THISCOMPACCOUNTED MRON33013-1239. 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THLSCOMPACCOUNTED FORON33013-1245. STANDBYSPENTFUELPOOLHEATEXCHGR.THISCOMPACCOUNTED FORON33013-1243. 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NDEMethodSUR/VOLSUB/VOL5210Y5210Y5210Y5210Y5210Y5210Y5210Y5210YBORICAQDTANK8TO8X8X8IEE.BOAICAQDTANKh'10SXSX8IEE.BORICAQDTANKh'10LOOPSEALFLANGE.BORICAQDTANKBI0LOOPSEALFIANCE.8X8X2IEEONSASMOI8'10VALVE345.BORICAQDTANKBTOHCV105.8X8X2IEEONSSSIQOIAIOVALVE331.BORICAQDTAIrI(AI0HCV104.Po~TernIn?Unedercri'/remarks R11/91R11/91R11/91R11/91R11/91R11/91H~Q(I)~QQQQHXHRWOWHLDH$+~tOQ~C)MOtdI~HXEr(UHtO0gHtI)HOe(E)HgQ4QrE)(/)(Dn00 InrIt R.FGINNANUCLEARPOWERPIANTInservkeExamlnsthn BoundaryLIneIAstTMrdInspeedon Intessral F&IDNot33013-12701 Chss.t3System-:WASTEDISPOSAILIQUIDDRAINSComp~sCOMPONENIS RG&EGtTbertSWRIUneNo.UneNo.LineNo.151~fi.MatrLSizeTlrfsrs~In.~In.NDEMerliodPoT~emIatUnedeseri'emarksOW0fWD03FWD09PWD12TWDI0N/AN/AN/AN/A0.00OAI0.000.000OAKs0.000OAO0.000IWDl~IWDI22sk2IWD12202IWD12202<<275<<200<275<200<275<200<275<200ULTRAFILTRATION SYSTEM.WASTEBLTEILWASTEHOLDUPTANKPUMP.WASTEHOLDUPTANK.R06/93'06/93R06/93R06/93H0MLHtdO+tAIHHtEIg+ONII3OHtI3g0HgmU)tD0po00 'HIIIIIIkI,NwI RE.0NNANUQEARPOWERPIANTlaservfce 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KE.CINNANUCLEARPOWERPIANTSnsenkeExaminatron BoandayUneUstIMrdInspeedon lntavalP&IDNo.:33013.1275.2 Gast:2System.:WASIEDISPOSALCAS H2RECOMBINCompType:PIPINCAH0RG&ELbeNo.2AWDG-152N2B.WDG152NCBbatSWRIUneNo.UneNrxISI~FI.MatrLN/hN/hSizeIhknsExemp6sn~in.~ln.IWC1222(A)IWC1222(A)PoT~emIn?Unerteseri'emarltsc275c200-PEN202TORDCRBEPOREVALVEIOS4ILPENP304TOVALVE1084A.RRevtsrrI R05/P3R06/930MXHXAHIOH~tO'ggOMIHIOOLOHIOQ0HgUl90I0O

ILE.GINNANUCLEARPOWERPIANTInsaviceExnmInntion BontxhryLIneUstThhdInrpeetbn IntavnlPAIDNot33013.1275-2 Chsst3SprtantWASTEDLSPOSALGAS H2RECOMBINComp~PIPINGOH0RGBEUneNo.0BbatSWRIUneNo.UneNo.ISISIte~PI.MstrL~h.IMmsExanpnonNDE~b.BssisMettrrsIPo~TernIn?Unedesert'fremsrIrs 2CWDG-152N 2DWDG.152N N/AN/h200OAN0IWD.122QI<275<200-PEN202'IQIM25,N25A,3/O'REDCL AQSr932'1000IWD122sl1<275<200-PEN30iTOIM33,5433A,3/<'REDCL =A06/93H0MreHRO+'LOHHe@OUl>reHHEIgLI3OHQOX0g0M8nPe00 R.E.OINNANUCLEARPOWERPIANTInsersriee hmlnrnkrn BoundaryUneUstThirdSspeetion IntervalPMDNo-t33013.1277.1 Casa.:2System:STEAMGENERATOR BIOWDOWNComp~:CONPONENISH0RCMUneNo.OtTbertUneNo.SWRIUneNo.ISI~Fi.MatrlSIseThknsExampdonNDE~b.~h.BasisMethodPo~Terntntlinedeseri'/remarks RevisedEh!SOIAEM501BB-IBlSUR/VOLSVR/VOL715505715505TIVSCOMPACCOVNTED FORON33013.1231. THISCOMPACCOUNTED MRON33013.1231. R0dr/93R06/93HQMgHX0~IHtOH~tOQgOMIH~gIO0IOHoHg0UlID00 ItI' R.E.GINNANUCLEARPOWERPIANTlnservlee Examlnanon BoundaryUneUstThirdInspeenon IntervalPAIDNo,t330131277.1Class..:2System.tSTEAMGENERATOR SLOWDOWNCompT)pe:PIPINGRCAEUneNo.CBbertSWRIlineNo.UneNo.ISISite~FI.MatrL~ln.Po~TernIn?Unedeserl'/remarlts 3A.BD600. IA225D.BD600 lh225DBD600.1B 2A.M5600.1A 2A-M5600. IB28-M$600lb28MS600IB2CM5600I8SCB100SG8-200SG8-100SOB-200SC8-200'400 N/AA106N/AN/hN/AA106B31h106N/Ahl06B31A106B31A1060.000(10000.000IL218IL218IL2180218IL218IWC1222(A) lÃC1222(A)IWG1222(h) IV&1222(h) 15%.1222(A) IWG1222(A)IWO1222(A) WGI222(h)1005547Y10055471005547100554710055471005547TEE2A-M5600lh628T05701.VALVES701TOVALVE5738.VALVES702TOVALVE5737.N.NOZZIET0FIRSTTEECIRTHWFID.N.NOZZLET0FIRSTTEECIRTHWELD.S.NOZZIET0HRSTTEECIRTHWFID.S.NOZZLE10FIRSTTEEGIRTHWELD.2AM5600-IBIt28TOVALVE5702.R06/93R06/93R06/93R06/93R06/93R06/93R06/93R06/93H0(/lXHWA+NOHHIOg+O(/)~IH100'LOHClQHgNOA0O)(D00 R.E.GINNANUCLEARPOWERPIANTlnservheExaminathn BoundaryUneLhtThirdInspeenon IntervalBkIDNor33013-1279 Classr2SystemrKSTACQDENTSAMPUNG CompTypesPIPINGOHQRGBLbeNo.3hSS-151GBbertSWRIUneNo.UneNo.ISISize~Fi.MatrL~in.3AOt1000IWG1222(A)PENP107TOVALVE172LTldmsExemption NDE~in.BashMctbodPo~TernIn?UnedeserfremaritsRReehedAIVPIH~mQUl~gQWHYXOZHIE)H$4HM785VCtE?HQWeHgQ ILE.GINNANUCLEARPOWERFIANTInservtoe Examination Borrndary UneUstTInnlIspectionIntervalP&IDNo..:330131863Qasst2SystemtCONTAINMENT HVACSYSTEMSCompT)rePIPINGH0RG&EUneNoGBbertSWRIlliinneeNo.lineNo.151Slee~FI.MatrL~In.Po~TernfatLmedeseri'eaaarfsIASUCTIAB.RETIBSUCTIGRETIGSUCI'DRETIDSOCTN/hN/hN/hN/AN/AN/hN/AOi)0OAOOAROi)0OASOASaooDidOAXO(LIMOOXNOIMOOIMOOIWC1222(B)IWC1222(B)IWC1222(B)IWG1222(B)IWGI222(B)IWG1222N) IWG1222(B)60120601206012060120601206012060120VLV1559TO'h'ONTREQRCFANASYS.VLV1562IIIRUPEN305'IOCONIINMENT. VLV1556TO'IPCONTREQRCFANBSYS.VLV1574%IRUPEN124'IOCONIINMENT. VLV1571TO"VCONTREQRCFANCSYS.VLV1568%IRUPEN203IOCONIINMENT. VLV1563TO'O'ONTREQRCFANDSYS.AOI/92R06/93hOl/92h01/92A01/92A01/92hOl/92hjQOMgHWO+IDHHu)ZOMpVX'40HIDE'4HoHgH0U)(t)0I00 kIVI R.E.GDINANUCLEARPOWERPIANTInserieeKxamhsthn BoundnryLheLIstThirdlnspeethn IntervalPAIDNo:33013-1865 Chss:2System:CONTAINMENT HVACSYSTEMSCompTPpetPIPINGRGAEuneNo.0ihertIIneNo.151SheThhrsExemption NDE~pi.MerrL~in.~h.MethodPo~TernIn?Lhedesert'enartrsRevisedN/A6AOtL000INC.1222(Cj 12580~V7445OUTCONTPASTPEN309TOV7478.R06/93QMgHWO>tl)HHII3g+ONIQt3H2eIhfdOWOV)ID0I00 PV LE.GDINANUCLEARPOWERPIANTInserviee Xxaminadon BotmdaryLIneustThhdtnspeedon intervalPBIDNo-t33013-1866 Chns:2SystemtCONTAINMENT PURGEEXH5MONITComp~:PIPINGGilbertSWRILbeNo.IIneNo.ISISize~fi.MatrL~In.TIdmsExemption NDE~in.BasisMethodPo~TernIn?unedesertnrremsrts N/A36AQILGOGIWC1222(B)36'URGEEXHAUSTIHRUPEN300.0M~gQgH'g%ORI'LI2HoecoHQQRCWM8n00 III ILE.GINNANUCLEARPOWERPIANTInsavkeExnmlnsfion Oottndery LineUst11drdspeetionlntavnlBIFIDNot330131870CIosst2SystemsHVACAIDQUARY dcINIEILKBLDG.CompTTPetPIPINGH0GBbatUneNo.SWRIUneNo.ISISite~Fi.MstrL~ln.TldmsExanption NDE~in.BssisMethodPoT~emIn7Unedesefi'/rernsrks N/h6AO(1000IWC1222(C) 110VALVE7P70PASTPENP132TOVALVE7971.RevisedR06/93HQMCHX0~IHQHgOUlIpVWt170Ht17gLI7HpHgQoF30M80r.0 t'I ~ILE.GINNANUQZARPOWERPIANTInsaviceEstnminntion RonndayUneList'IIdnIinspection IntavnlP8IDNot33013-1882 Qass:2Systan:CONTAINMENT BREATHING AIRCompType:PIPINGOH0RGBUneNo.GEbatSWRIUUnneeNo.UneNo.ISISizeTIdmsExempdonNDE~PI.~~I~~~8MctbodPoT~emln7Unedeserirerrnrirs 6.AT-15046LT400NthNlh6'F000IWC1222iC)<275<200VALVE7443TIIRUPENP317IOPIANGE.AIUPI6000.000IWC.1222(C) <275<200VALVE7444THRVPENP313IOPLANGE.R06/93H~OM~gQHAHgH'g%ORHÃR5'QHoweH@O0 lf41 ILE.GINNANUCLEARPOWERPLANTlamvkeExamhucha BoundaryLIneLbtThinlnspeeaoainterredRG&ElineNo.GBbertLIneNo.P&IDNot33013-1886.2 Chess-t2System:SERVICEAIRCompType:PIPINGISISize~Pi.MntrL~in.2AS0AXOIWC.1222(A) NDEMethodPo~TernIn?UnedeseriremarksRevbedVALVE714I'IIIRUPENP310TOVALVE7226.R06r93H0'gH0MXHWO+IOHVH~gOM'LOQtlyH0g0Q0MIn00 LE.GINNANUQEARPOWERPIANTInsetvtee ExamInathn BonndaryUne11stThIrdlnspeethn IntervalP&IDNm.:33013-1887 Chss..t2SystmntINSTRUMENTAIR CONINMTBLDG Comp~PIPINGOH0RG&EUneNo.2-IA.1258 2ASDIXIEIWC1222(A)VALVE5392THRUPENP310TOVALVE5393.GBbertSWRI51SIte'IhtnsExempnonNDELbeNsxLbeNo.~FI.MatrL~h.~in.MethodPoT~emIn7Lbedeseri'emarksRevisedA11/91H~OM~NQs2sH2gWOWHII3sEs$~+otOOX>IWma'LOHoweHgOU)80Ttpo00 'v ILE.CINNANIIQZARPOWERPIANTInsaviteExamhrrrha ~UneUrtTldrdInrpecdon IntavrdPEdDNot3301319084 Chert2S)rtantPiUMARYWATERTREATMENT CompT)perPIPINCHQfRGBLheNo.3PW.125I2.PW125-12A.PW.125'I CGbatSWRIUneNo.LineNo.ISISizeTIdrno~Fi.MrrrrL~h.~h.N/AN/AN/AIVi&1222(A) IWC1222(A)IWC1222(A)NDEMethodPo~TernIn?Lhedesairemorirs3X2RDCROUTSIDETO3X2RDCRINSIDE.R06/93VALVE8418TO3X2RDCRONSIDECONTNMT.R06/933X2RDCRINSIDECONTNMTTOVALVEIM19.ROdr/93H0MgHEz)0hf>rHQH~tO'2cgOMItOOHkg~eH()h9Qg0em0)(D()-Tt00 R.E.GINNANUCLEARPOWERPIANTInsavkeExamfmnion BonndaryUneUst'Ihbdlnspeedon IntetvalPMDNot33013.1915 13asst2SystemtHEATINGSIKAId5CONDENSATK Comp~PIPING0H0RGAEUneNo.GBbettSWRIUneNo.UneNo.SizeThhtsExempdonNDE~h.~in.RaslsMethodPoT~emIn?Unedeseri'emasinPENEIRAIION 301TOVAIVE6165.RevisedhI1/910MgHXA>eHHtOg+ON'LOOHtOggtOH0HggH0

R.E.GINNANUQZARPOWERPIANTInsnvieeExaminadon BoundaryUneUstTMtdInspection IntervalRGAEUneNo.GEbertSWRILineNo.UneNo.P8IDNo..:33013-1991 Qass.t2System...: FIREPROTECllON INCONTAINMENT Cop'Iype:PipiNGISI~F1.MatrLSIseTidesExampthnNDE~in.~in.BasisMetissdPo~TeteIn?Unedesetin/retnarka 0H0'geh-FS-152 2A.F5400N/AN/Aext0OAXO2.00t1000IWC12t)2IA)IWC.1221(A) 13580-VALVE9227'IOVALVE9229INCONTAINMENT. R11/91VALVE5129ATPENP103TO5130.A11/91H0NQHRO>u)HH113g00)td)OHingLI)H<-oHQF/)8n00 Itt.t LE.GUINANUCLEARPOWERPIANTInsaeiceExeminstha BcrrrsLsryLIneUstThinlInspecdon IntaveiPMDNot33013-2279.1 CLsss.:3System:WASTEEVAPORATOR SKIDCompTypaCOMPONENTS OH0ROTELineNo.GBbatSWRIlineNo.UneNo.ISISizeThkns~Fi.MstrL~b.~b.N/AN/AN/AExempthnIWD1220.1IWD.1220.1 IWD1220.1NDEMethotlPoT~emIn?lineCesalremsrhsWASTEEVAPORATOR CONCENTRATOIL WASTEEVAPORATOR FEEDTANKPUMP.WASTEEVAPORATOR FEEDTANKR06/93R06/93R06/93H~ON~gQQgHXHR%ORWP~HMTel'C)NORI>ItaeaHLDOgH'4HOeTT2HQO00cs ,1 LE.GINNANUCIEARPOWERPIANTIneervlee Eaunlnathm ~UneIirtThlnlInrprethrn lntereaIP&lDNot33013-2279-1 Cher-:3System:WASTEEVAPORATOR SKIDCompT?perPIPING13OH0RG&ENNMA.WD9ISB-WD9MSA.WD90QbertlineNo.ISIPirl,Marrl.N/AN/hN/hIW0.000150OAXrOOAXSIWD.122aIIWD1220.1IWD1220.1~TernIn?linedererlremarks?WEFTTWDOBTO2642D,WEFTPUMP.R06/93?IhTOSWDI4,26427.7ShR06/93?WECONCENTRATOR EWD07'TO2620C,SWDI4R06/93HOMNTNHWOgLOH~LI7Q~OU?IHeOLI7HpHggH0V?O0r-00 QUALITYASSURANCE MANUALGINNASTATXONSection6EFFECTIVE DATE:PAGE1of6December31,1993ROCHESTER GAS8ELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESPREPAREDBY:QUALITYASSURANCE REVIEW:APPROVEOBY:1.0GeneralThissectionidentifies programexamination .allocations for"ASMECodeRequired" and"Augmented Required" groupsthatwillbeperformed duringthethirdintervalatR.E.GinnaNuclearPowerPlant.Thetablesidentifythetotalnumberofcomponents, therequirednumberandthedistribution oftherequirednumberwithinoneofthethreeperiods.The"ASMECodeRequired" groupaddresses theprogramrequirements withrespecttoASMESectionXI.Thisgroupisdividedintothefollowing allocations. Class1Class2Class3Class1,2,&3SupportsThe"Augmented Required" groupaddresses Rochester Gas&Electriccommitments thatwereaddedtothe.Inservice Inspection Programtoensurecompliance tothecommitments andperformance. Thisgroupisdividedintothefollowing allocations. ReactorCoolantPumpFlywheelProgramReactorVesselAugmented, Program,CategoryB-AHighEnergyProgramSnubberProgramSteamGenerator TubingProgramSeismicSupportProgramOtheradditional "Owner.Elected" examinations areperformed byRochester Gas&Electric. Theseadditional examinations arenotmandatory andaredetermined bytheownertoensureadditional safetyandreliability oftheplant.Theseadditional "OwnerElected"examinations arenotidentified withinthefollowing allocation tables. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESFIEV.Section62PAGE2of6ASMECODEREUIREDClass1CatecaCor TotalReceuired ThirdIntervalScheduled/Percent Period1Period2Period3B-AB-BB-DB-FB-G-1B-G-2B-JB-L-1B-L-2B-M-1B-M-2101230241515245195229536132218.2124(*)ifdisassembled. 2/28.5%4/57.1%5/20.8>o5/33.3~49/25.1~o 3/33.3%28/21.2~o 3/100~o0/0<o2/100<1/100+o2/57.1~o1/71.49'/45.8>o 3/53.3%49/50.2>o 3/66.6451/59.8<o 0/10040/0>o0/10043/10042/100413/100>o7/100'7/100% 3/100'3/100~o 0/10091/10040/100>o(3remaining, onlyifdisassembled, PerRRg5.)B-N-1B-N-2B-N-3IB-0B-QTotal209504791/33.3%0/0%0/040/043/27.2~o18/3041/66.640/0<o0/0>o0/0>o4/63.6<o24/701/100%2/100~o1/100~o3/10044/100418/1004 '\F1k QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESREV.Section62PAGE3of6Class2~CateorTotalRecCuired ThirdIntervalScheduled/Percent Period1Period2Period3C-AC-BC-CC-F-1C-F-2C-HTotal2230131677387721319131812453301243623/23.0%6/33.3%29/23.4<o 17/32'~o10/33.3>o 39/31.4p4/53.8~o6/66.6~o52/65.3~o 19/67.9410/66.6443/66.1%6/100~o6/100~o43/100>o17/100410/100>o42/100>oClass3CatecaCor rTotalReceuired ThirdIntervalScheduled/Percent Period1Period2Period3D-A,D-B&D-C14514138/26.9%54/65.2%49/100%D-A,D-B&D-C30Hydro/Leakage 16453/32~3+o51/64~3~o60/100<Total175305 I QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESREV.2PAGE4of6Section6Class12&3SuortsOriionalDistribution to1986CodeClass~GrouTotalReceuired ThirdIntervalScheduled/Percent Period1Period2Period3Class1Class2Class3Total159377477101314236814165119/13.4~o 55/52.1>o 93/253+o134/616+o38/26.9454/65.2>o 150/23.0% 243/59.6< 68/100<141/100~o49/100>o258/100%IncoorationofCodeCaseN-491with1986CodeRevisedDistribution ProgramReference CategoryTotalItemSuortsPeriod1Completed ReuiredCreditedPeriod2Completed /Credited Period3Scheduled Scheduled 1986CodeReq.forPeriod1and'93OutageF-A,B,CAllItems1013651150Completed (23.0%)44Completed 199253Scheduled Scheduled CodeCaseN-491forPeriod2(Starting'94Outage)andPeriod3F-AF1.10F-AF1.20F-AF1.30F-AF1.40114,358467743258504410Credit19Credit17Credit10Credit6Credit5Sched.17Credit2Sched.12Credit4Sched.0Credit3Sched.llSched.20Sched.17Sched.31Sched.Totals101318456(30.4%) 49(57.0%)79(100%)AuentedReuiredRCPFlheelProram:CatecaCor rTotalReceuired Flywheel26ThirdIntervalScheduled/Percent Period1Period2Period32/333+o2/66~6+o2/100> QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESREV.Section62PAGE5ot6ReactorVesselAuentedProramCatecaCor rTotalRecCuired CateorB-A:ThirdIntervalScheduled/Percent Period1Period2Period3B-A0/0>0/O~o3/1004HihEnerProram:CatecaCor rTotalRecCuired ThirdIntervalScheduled/Percent Period1Period2Period3HE-CB97HE-CC(*)17HE-DB18HE-LK2Total13497175417434/3549/52.9418/33.342/28.5~o30/65.9~o 3/70.6~o18/66.642/57.l~o33/100~o5/100%18/10042/100+o(*)=DenotesIntegralAttachment CodeCaseN-491Class2CriteriaNon-Class HihEnerSuortDistribution Period2Period1Completed ProgramCategoryTotalCompleted /Credited Period3Reference ItemSuortsReuiredCreditedScheduled Scheduled Requirement forPeriod1and'93Outage.N/A626220Comp.6Comp.(31.7%)18Sched.19Sched.CodeCaseN-491forPeriod2(Starting'94Outage)andPeriod3N/A(F-AF1.20)623Credit(27.3%)4Credit0Sched.(63.6%)4Sched.(100%) QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALALLOCATION TABLESREV.2PAGE6of6Section6SnubberProram:CatecaCor cTotalRecCuired SN-VT(*)1491039ThirdIntervalScheduled/Percent Period1Period2Period3443/43.04 447/86.4% 149/1004SN-FT(Total149149298118848/322~o57/704~o44/100~o(*)=Note:GenericLetter90-09willbeimplemented duringthe'94OutageoftheSecondPeriod.SeismicSuortProramOutsideASMEClassBoundarCodeCaseN-491Class2CriteriaSeismicSucrtDistribution ProgramReference CategoryItemTotalSuortsPeriod1Period2Completed CreditedPeriod3ReiredCreditedScheduled Scheduled CodeCaseN-491forPeriod2(Starting'94Outage)andPeriod3N/A(F-AF1.20)93190Comp.0Credit:9Sched.(47.3%)10Sched.(100%) QUALITYASSURANCE MANUALGINNASTATIONSection7PAGE1of3EFFECTIVE DATE:December31,1993ROCHESTER GAS8ELECTRICCORPORATION TITLEAPPENDIXBR.E.GXNNANUCLEARPOWERPLANTULTRASONXC CALIBRATXON BLOCKLXSTINGSIGNATURE PREPAREDBY:j~*QUALITYASSURANCE REVIEW:APPROVEBYDATEi2-fi31.0General:Thelistbelowidentifies Ultrasonic Calibration BlocksthatareownedbyRochester Gas&ElectricandutilizedatR.E.GinnaNuclearPowerPlant.Othercalibration blocksnotownedbyRochester Gas&Electricmaybeemployedonlyiftheymeettheapplicable requirements specified withinASMESectionXI,1986Edition,noAddenda.IDENTIFICATION NUMBER6-SS-108-.134-1A-REG 6-SS-408-.280-2-REG B-SS-108-.148-3-REG 8-SS-408-.322-4-REG B-SS-160-.906-5-REG 10-SS-108-.165-6-REG 10-SS-408-.365-7-REG 10-SS-140-1.0-8-REG '12-SS-SS-.156-9-REG 14-SS-10-.250-10-REG 14-CS-30-.375-11-REG PL-1.187-SS-12-REG PL-.30-SS-13-REG PL-3.5-CS-14-REG 9-CSCL-15-REG 7-CSCL-16-REG 5-CSCL-17-REG PL-3.0-SS-18-REG DESCRIPTION 6"D-SCHEDULE 10-SS-PIPE 6"D-SCHEDULE 40-SS-PIPE 8"D-SCHEDULE 10-SS-PIPE 8"D-SCHEDULE 40-SS-PIPE 8"D-SCHEDULE 160-SS-PIPE 10"D-SCHEDULE 10-SS-PIPE 10"D-SCHEDULE 40-SS-PIPE 10"D-SCHEDULE 140-SS-PIPE 12"D-SCHEDULE 5-SS-PIPE 14"D-SCHEDULE 10-SS-PIPE 14"D-SCHEDULE 30-CS-PIPE 1-187THICK-SS-PLATE .30THICK-SS-PLATE 3.5THICK-CS-PLATE 9"THICK-CS-CLAD-VESSEL BLOCK7"THICK-CS-CLAD-VESSEL BLOCK5"THICK-CS-CLAD-VESSEL BLOCK3"THICK-SS-PLATE MATERIALSPEC.SA312SA312SA312SA312SA312SA312SA312SA376SA312SA312SA106SA240SA240SA533SA508SA508SA508SA479 QUALITYASSURANCE MANUALGINNASTATIONTITLf:APPENDIXBR.E.GINNANUCLEARPOWERPLANTULTRASONIC CALIBRATION BLOCKLISTINGSection7PAGE2of3IDENTIFICATION NUMBER6-SS-160-.719-19-REG 4-SS-160-.531-20-REG 3-SS-160-.438-21-REG 8.5-6-8-CS-22-REG 6-1-8-CS-23-REG IR-CSCL-24-REG 6-SS-120-.562-25-REG FS/NS-CSCL-26-REG IR-CSCL-27-REG CRD-SS/IN-.656-28-REG 10-SS-140-1.0-29-REG 3.5-.625-8-CS-30-REG 5.375-3.5-8-CS-31-REG 1.187-8-7-CS-32-REG 1.187-N-7-CS-33-REG 1.125-8-12-CS-34-REG 1.125-N-12-CS-35-REG 1.250-8-7-CS-36-REG 1.250-N-7-CS-37-REG 10-SS-160-1.147-70 6-SS-X-1.1-38-REG 29-SS-X-2.5-39-REG SI/N-CSCL-40-REG 27.5-CSS-X-2.4-41-REG 29-CSCL-X-2.5-42-REG 5.437-SS-X-1.0-43-REG PL-1.5-CS-44-REG 14-CS-100-.938-45-REG DESCRIPTION 6"D-SCHEDULE 160-SS-PIPE 4"D-SCHEDULE 160-SS-PIPE 3"D-SCHEDULE 160-SS-PIPE REACTORPRESSUREVESSELNUTREACTORPRESSUREVESSELSTUDO.D.INNERRADIUSBLOCK6"D-SCHEDULE 120-SS-PIPE FLANGEANDNOZZLESHELLBLOCKNOZZLEINNERRADIUSBLOCKSS-CONTROL RODDRIVEBLOCK10"D-SCHEDULE 140-SS-PIPE REACTORCOOLANTPUMPSTUDREACTORCOOLANTPUMPNUTMATERIALSPEC.SA312SA376SA376SA320-L43SA320-L43SA533SA312SA533SA553SA182SA312ACTUALSTUDACTUALNUT1187"DIA.X7THREADS/IN-CS-STUD SA1931.187"DIA.X7THREADS/IN-CS-NUT SA1941.250"DIA.X7THREADS/IN-CS-NUT 10"D-SCHEDULE 160-SS-PIPE 6"D-1.1"WALL-SS-PIPE 29"ID-SS-PIPE SAFETYINJECTION NOZZLEBLOCK27.5"ID-CS-PIPE 29"ID-CLAD-CS-PIPE 5.437"D-1"WALL-SS-PIPE 1.5"THICK-CS-PLATE 14"D-SCHEDULE 100-CS-PIPE SA194SA312SA182SA182SA508SA351SA508SA182SA285SA1061.125"DIA.X12THREADS/IN-CS-STUD SA1931.125"DIA.X12THREADS/IN-CS-NUT SA1941.250"DIA.,X7THREADS/IN-CS-STUD SA193 II QUALITYASSURANCE MANUALGXNNASTATIONTITLE:APPENDIXBR-E-GXNNANUCLEARPOWERPLANTULTRASONIC CALIBRATION BLOCKLISTINGREV.Section71PAGE3of3IDENTIFICATION NUMBER18-CS-100-1.156-46-REG 4-SS-80-.337-47-REG 3-SS-80-.300-48-REG 4.25-R-CS-N/RB-49-REG 1.250-B-6-A490-50-REG 1.375-8-17-A490-51-REG 1.375-8-24-A490-52-REG 1.375-S-33-A490-53-REG 3-SP-14-A514-GRF-54-REG 2-IC600-80-J-NOZ-55-REG 1.875-9-8N-CS-56-REG 1.0-4-8N-CS-57-REG 1.875-S-S-CS-58-REG 2.89-1.87-8-CS-59-REG 2-CS-,40-.218-60-REG S-CS-100-.594-63-REG 15.0-SS-X-1.60-61-REG 20-CS-X-1.281-64-REG 24-CS-80-1.218-65-REG 30-CS-X-,1.250-66-REG 36-CS-X-1.47-67-REG 3.0-CS-80-.218-68-REG DESCRIPTION 18"D-SCHEDULE 100-CS-PIPE 4"D-SCHEDULE 80-SS-PIPE 3"D-SCHEDULE 80-SS-PIPE REACTORPRESSUREVESSELNUTREFERENCE BLOCKS/GSECONDARY MANWAYBOLT1.375DIA.X17"LONG-STEEL-STUD 1.375DIA.X24"LONG-STEEL-STUD 1.375DIA.X33"LONG-STEEL-STUD COLUMNPINS/G"j"NOZZLES/GANDPRESSURIZER MANWAYBOLTS/GHANDHOLDBOLTS/GPRIMARYMANWAYSTUDS/GPRIMARYMANWAYCLOSURENUT2"BLOWDOWN8"FWBLOCK15"PZRBLOCK20"FWBLOCK24"MSBLOCK30"MSBLOCK30"MSBLOCK3"BLOWDOWNMATERIALSPEC.SA106SA312SA312SA'516ASTMA490ASTMA490ASTMA490ASTMA490ASTMA514INCONEL600SA193SA193SA193SA193SA335SAW6-GRBSA182-F316 SA333-GR6SA106-GRBSA517-GR70SA517-GR70SA335-QUALITYASSURANCE MANUALGINNASTATIONSection8EFFECTIVE DATE:PAGE1of8December311993ROCHESTER GAS6ELECTRICCORPORATION SIGNATURE DATETITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMPREPAREDBY:QUALITYASSURANCE RAPPROVEDBY'z-g-)3g,MIEI.P-3-1.0General:Theaugmented inservice inspection programforHighEnergy(Class6Non-Class) Piping,outsideofcontainment, asestablished inRochester GasandElectricCorporation's Report"EffectofPostulated PipeBreaksOutsidetheContainment Building", datedOctober29,1973,providesfortheexamination ofallidentified circumferential buttweldsatdesignbreaklocations andatdiscontinuity (Consequential) locations whereafailurewouldresultinunacceptable consequences. Thisprogramalsoestablishes aNon-Class HighEnergyPipingcomponent supportexamination requirements. Therequiredexaminations areusedtodetectanychangeincondition ordevelopment ofserviceinducedflawsinadvanceofapotential failure.Surveillance ofthesecomponents bytheinspection programprovidesassurance thatthedesignbasisorconsequential MainSteamorFeedwater breakswillnotoccur.2.0Examination Requirements: 2.1Identified HighEnergyPipingcircumferential buttweldsat,designbreaklocations anddiscontinuity (consequential) locations shallbeexaminedutilizing volumetric, surfaceandvisualexamination techniques. 4tI QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E-GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMREV.3PAGE2of8Section8I2.2Identified Non-Class HighEnergyPipingcomponent supportsshallbeexaminedutilizing visualexamination techniques. Forperiods2and3,areducedselection shallbeutilizedbasedontherequirements ofCodeCaseN-491forClass2pipingsupports. Thissamplingschemerequiresa15%sampledistribution amongthesystemsandsupporttypeswithineachsystem.Allintegralattachments associated withHighEnergycomponent supportsshallreceiveasurfaceexamination, basedontheCoderequirements forClass2pipingintegrally weldedattachments. 2.3Examinations onHighEnergyPipingcircumferential buttweldsatdesignbreaklocations andconsequential breaklocations, aswellascomponent supportsandintegrally weldedattachments, areidentified withinTable1ofthissection.I2.42.4.12.4.2SystemPressureTestingandassociated visualexamination forleakage,shallbeperformed onthemainrunoftheHighEnergyPiping.The10-yearHydrostatic testingrequirements forHighEnergyPipingwasderivedfromASMESectionXICode,IWC-5000, asacontinuation oftheClass2boundary. Withtheimplementation ofCodeCaseN-498withintheISIProgram,thecodecaserequirements maybeperformed inlieuofhydrostatic testrequirements forHighEnergyPiping.Leakagetestingrequirements forHighEnergyPipingwasderivedfromASMESectionXICode,IWC-5000,asacontinuation oftheClass2boundary.

3.0 Examination

Methods:3.1Applicable examinations shallbeperformed inaccordance with1.7.1,1.7.2,1.7.3and1.7.4ofSection1. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 XNTERVALHXGHENERGYPROGRAMREV.Section83PAGE3of84.04.1Frequency ofExamination Xdentified HighEnergyPipingcircumferential buttweldsatdesignbreaklocations shallbeexaminedonceeachperiod.Circumferential. buttweldsat.discontinuity (consequential) locations shallbeexaminedonceperinterval. 4.3SelectedNon-Class HighEnergyPipingcomponent supportsshallbeexaminedonceperinterval. Identified HighEnergyPipingXntegrally weldedattachments shallbeexaminedonceperinterval. 4~44.55.0OnthemainrunofHighEnergyPipingpressureboundary, aLeakageexamination shallbeperformed onceperperiod.InlieuofaHydrostatic TestonceperintervalonthemainrunofHighEnergyPipingpressureboundary, aLeakageexamination maybeperformed onceperintervaltoCodeCaseN-498criteria. Examination Evaluation: 5.1Thhevaluation ofexaminations oftheHigh-Energy pipingweldsoutsideofcontainment willbeinaccordance withSectionXIXWC-3130forvisualexaminations andIWC-3120forvolumetric andsurfaceexaminations. Evaluations ofradiographic resultsshallbeinaccordance withtheacceptance criteriaforradiographic examinations referenced inUSASB31.1.0-1967, "PowerPiping"and"ASMESectionXI."Ultrasonic Examinations performed inaccordance withtherequirements ofAppendixIandIIIandtheacceptance criteriainUSASB31.1.0-1967(Radiography). Visualexaminations ofidentified HighEnergyPipingSupportswillbeevaluated inaccordance withIWF-3000forPeriod1,and-3000ofCodeCaseN-491forPeriods2and3. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMREV.Section83PAGE4of'86.06.1Repair&TestingRequirements: Repairsandapplicable systempressuretestsperformed onASMEClass2and3HighEnergypressureretaining pipingandassociated component supportsandintegralattachments shallconformtotherequirements"specified withinSupplement 2toAppendixB,theRepair,Replacement andModification Program.CodeCaseN-498doesnotapplytoRepairs.7.07.18.0Replacement &TestingRequirements: Replacements, including Modifications, andapplicable systempressuretestsperformed onASMEClass2and3HighEnergypressureretaining pipingandassociated component supportsandintegralattachments shallconformtotherequirements specified withinSupplement 2toAppendixB,theRepair,Replacement andModification Program.CodeCaseN-498doesnotapplytoReplacements andModifications. Scheduling: 8.18.29.0Scheduling oftheHighEnergyProgrampipingwelds,component supportsandintegralattachments shallbeperformed andcontrolled within.Supplement 1toAppendixB,theProgramPlan.Table1identifies welds,component supportsandintegralattachments thatarewithintheHighEnergyProgram.ReportsandRecords:9.1ReportsandRecordsgenerated onHighEnergypressureretaining components, integralattachments andcomponent supportsshallconform,asapplicable, totherequirements ofSection1andSupplement 2toAppendixB,theRepair,Replacement andModification Program. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMREV.Section83PAGE5of8TABLE1HIGHENERGYPROGRAMMAINSTEAMLOOPA-WELDS:-DesinBasisBreak30A-MS-600-1A D30A-MS-600-1A F130A-MS-600-1A D136-MS-600-1 L1ConseuentialBreak30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1 30A-MS-600-1 D2EE2GG2JL30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1 D3E1FG1HKMAINSTEAMLOOPB-WELDS:DesinBasisBreak30B-MS-600-1B D30B-MS-600-1B J1ConseuentialBreak30B-MS-600-1B H136-MS-600-1 P130B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1 D1EKL1M030B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1 30B-MS-600-1 D2JLL2NP QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMREV.3PAGE6of8Section8TABLE1Cont.MAINSTEAM-TURBINEBUILDING-WELDS:DesinBasisBreak36-MS-600-1 L2ConseuentialBreak36-MS-600-1 24A-MS-600-1A 24A-MS-600-1A 24A-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A L4BClDlBCD24A-MS-600-1A 24A-MS-600-1A 24A-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A ABlDABlClFEEDWATER -TURBINEBUILDING-WELDS:DesinBasisBreak20-FW-900-1 M3ConseuentialBreak20-FW-900-1 20-FW-900-1 20-FW-900-1 20-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 JLMM2BDFH20-FW-900-1 20-FW-900-1 20-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 KlLlMlACEG IHI QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMSection8PAGE7of8TABLE1Cont.FEEDWATER LOOPA-WELDS:DesinBasisBreak20-FW-900-1 M420-FW-900-1 U2ConseuentialBreak20-FW-900-1 Ul14A-FW-900-lA AA14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A T2U7U6VAVlV2AWYZlZ314A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A T3U5VVBV2V2BXZZ2Z4FEEDWATER LOOPB-WELDS:DesinBasisBreak20-FW-900-1 Al14B-FW-900-1B NConseuentialBreak20-FW-900-1 F414B-FW-900-1B V14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1B 14B-FW-900-1B 14B-FW-900-1B F3FlGGlG4HAHlH2AzLNl0114B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1B 14B-FW-900-1B 14B-FW-900-1B F5F2G2G3HHBH2H2BKM0P fIE QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION REPORTFORTHE1990-1999 INTERVALHIGHENERGYPROGRAMREV.3PAGE8of8Section8TABLE1Cont.MAINSTEAM -COMPONENT SUPPORTS: (*)MSU-35(*)MS-34(*)MS-35(*)MS-47MS-59MS-36MS-37(*)MS-150MS-38MS-39MS-151MS-40(*)MS-41S13AS13BMS-42MS-43MS-167MS-153MS-44(*)MS-149MS-45(*)MS-46S23AS23BFEEDWATER -LOOPA-COMPONENT SUPPORTSFWU-16FWU-17(*)FWU-18FWU-19FWU-20(*)FWU-21FWU-22FWU-23FWU-24FWU-25(*)FWU-26(*)FWU-27(*)FWU-28FEEDWATER -LOOPB-COMPONENT SUPPORTSFWU-36FWU-35FWU-34FWU-32FWU-33FWU-31FWU-30(*)FWU-29FWU-40(*)FWU-39FWU-38FWU-37FEEDWATER -MAIN-COMPONENT SUPPORTSFW-37FW-38FW-39FW-40FW-41FW-42FW-43(*)FW-45FEEDWATER -RECIRCULATION LINE-COMPONENT SUPPORTS: CD-167CD-168CD-169(*)CD-170NOTE:*=IntegralAttachments QUALITYASSURANCE MANUALGXNNASTATIONSection9EFFECTIVE DATE:PAGE1of4December31,1993ROCHESTER GAS8,ELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSNUBBERPROGRAMPREPAREDBYQUALITYASSURANCE REVIEW:APPROVEDY:1.0General:1.21.2.1Theinspection andtestingofallsafetyrelatedsnubbersshallbeimplemented andperformed inaccordance withMechanical Engineering Specification ME-256,"SnubberXnspection 6TestProgram", toensuretherequiredoperability ofthesesnubbersduringaseismicorotherevent,initiating dynamicloads.Thesnubberprogram,asdefinedwithinME-256,establishes bothvisualexamination andfunctional testingrequirements. Thisprogrampertainstomechanical andhydraulic snubbers. 1.2.2Thesnubberprogramincludes: a~b.c~d.e.f.gh.VisualInspection Requirements VisualInspection FailureEvaluation VisualInspection Corrective ActionandImpactonExamination Frequency Functional TestingRequirements Functional TestSampleFunctional TestFailureAnalysisFunctional TestingCorrective ActionFunctional TestingMethodsInspection andTestingDocumentation 1.3TheSnubberProgramadherestotherequirements ofASMESectionXI,1986EditionArticleXWFandincludesguidenceprovidedbyASME/ANSI OMc-1990, Part4.1.4R.E.GinnaNuclearPowerPlantTechnical Specifications establishes aSnubberSealServiceLifeMonitoring forHydraulic Snubbersthatiscontrolled byR.E.GinnaStationProcedures. IIIIilY QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSNUBBERPROGRAMREV.Section93PAGE2of42.0Examination, TestingandMonitoring Requirements: 2.1Visual(VT-3)Examinations andFunctional (FT)Testingshallbeperformed totheextentspecified withinME-256.2.2Thesealservicelifeofhydraulic snubbersshallbemonitored andsealsreplacedasrequiredtoensurethattheservicelifeisnotexceededbetweensurveillance inspections duringaperiodwhenthesnubberisrequiredtobeoperable. Thesealreplacement shallbedocumented andretainedinaccordance withTechnical Specification.

3.0 Examination

andTestingMethods:3.1Visual(VT-3)Examinations andFunctional (FT)Testing'shall beperformed to'.,verify therequirements specified withinME-256,asaminimum.4.0Examination andTestingFrequency: 4.14.24.3Visual(VT-3)Examinations andFunctional (FT)Testingshallbeperformed atthefrequency specified withinME-256.Visual(VT-3)BaselineExaminations shallbeperformed whenevernewsnubbersareinstalled, reinstallation ofexistingorswappedsnubbersthatwerefunctionally tested,orafterrepairs,replacements ormodifications. Functional testingrequirements fornewinstallations orsparesshallbeequaltoormorestringent thanthatspecified withinME-256.5.0Examination, TestingandMonitoring Evaluation: I5.1SnubbersthatdonotappeartoconformwiththeVisual(VT-3)Examination requirements ofMechanical Engineering Specification ME-'256,shallbereportedforevaluation andappropriate corrective action.Visualexamination failureevaluation shallbeperformed whennecessary andrequiredbyME-256.Corrective actionmayincluderepair,replacemen't ormodification ofthesnubber.

QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSNUBBERPROGRAMREV.Section93PAGE3of45.2Snubbersthatdonotappeartoconformwiththevisualexamination acceptance requirements andarelaterconfirmed asfailuresandappearsinoperable maybedeclaredoperableforthepurposeofestablishing thenextvisualinspection

interval, providing that:(1)thecauseoftherejection isclearlyestablished andremediedforthatparticular snubberandforothersnubbersthatmaybegenerically susceptible; and(2)theaffectedsnubberisfunctionally testedinthe"asfound"condition anddetermined operable.

Allsnubbersfoundconnected toaninoperable commonhydraulic fluidreservoir shallbecountedasinoperable fordetermining thenextinspection interval. Snubbersthat,donotappeartoconformwiththevisualexamination acceptance requirements andarelaterconfirmed asfailuresbutdoesnotappearinoperable shallnotbedeclaredinoperable andthecauseoftherejection shallberemedied. 5.3Snubbersthatdonotmeettheoperability testingacceptance criteriainME-256shallbeevaluated todetermine thecauseofthefailureandappropriate corrective actiontaken.5.4Theservicelifeofasnubberisevaluated viamanufacturing inputandengineering information throughconsideration ofthesnubberserviceconditions andfunctional designrequirements. Theonlysnubbercomponents withservicelivesnotexpectedtoexceedplantlifearesealando-ringsfabricated fromcertainsealmaterials. Therefore, asealreplacement programisrequiredtomonitorsnubbersealando-ringservicelifeandtoassuresnubberoperability isnotdegradedduetoexceeding component servicelife. tK QUALITYASSURANCE MANUALGINNASTATXONTITLE:APPENDIXBR.E.GXNNANUCLEARPOWERPLANTINSERVICE XNSPECTION PROGRAMFORTHE1990-1999 INTERVALSNUBBERPROGRAMREV.3PAGE4of4Section96.06.1Repair,Replacement andModification Requirements: Repairs,Replacements andModifications performed onsnubbersunderthisprogramshallconform,asapplicable, totherequirements specified withinSupplement 2toAppendixB,theRepair,Replacement andModification Program.7.07.17.2Scheduling: TheVisualExaminations andFunctional Testingschedules shallbeestablished, trackedandmaintained withinSupplement 1tothisAppendix. TheXnservice Inspection ProgramPlanshallidentifyandtrackexpandedoradditional testingand/orexaminations asspecified andrequiredbyME-256.8.0ReportsandRecords:8.1ReportsandrecordsfortheVisual(VT-3)Examinations andFunctional (FT)Testingshallbemaintained onallsnubberslistedwithinME-256.8.28.3Applicable recordsandreports,asrequiredbySupplement 2forRepairs,Replacements orModifications, shallbemaintained forsnubbers. Recordsoftheservicelivesofallhydraulic andmechanical snubberslistedinthisprogram,including thedateatwhichtheservicelifecommences, andassociated installation andmaintenance recordswillbemaintained.

QUALITYASSURANCE MANUALGINNASTATIONSection10REV.PAGE1oI6EFFECTIVE DATE:December31,1993ROCHESTER GAS8ELECTRICCORPORATION SIGNATURE DATETITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMPREPAREDBYQUALITYASSURANCE REVIEW:APPROVED': I2-I-$3fr-4->31.0General:1.2Theaugmented inservice inspection programforSeismicCategoryIsupportsoutsideoftheASMEClassboundarywasdeveloped toprovidegreaterassurance thatidentified component supportswilloperatewhenandifneededduringaseismicevent.SeismicCategoryIsupportsoutsideoftheASMEClassboundaryareidentified inTable1.2.0I2ol3.0Examination Requirements: SelectedSeismicCategoryIsupportsshallbeexaminedutilizing visual(VT-3)examination techniques. Supportselection shallbebasedonCodeCaseN-491forClass2pipingsupports. Thissamplingschemerequiresa15%sampledistributed amongthesystemsandsupporttypeswithin-eachsystem.Examination Methods:3.1Thevisual(VT-3)examination shallbeperformed inaccordance withSection1.4.0Frequency ofExamination: 4.15.0Theselectedsampleshallbeexaminedatleastonceduringtheinspection interval. Examination Evaluation: 5.1Thevisual(VT-3)examination resultsshallbeevaluated inaccordance withIWF-3000forPeriod1,and-3000ofCodeCaseN-491forPeriods2and3. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMREV.Section101PAGE2of65.26.06.17.07.18.08.19.09.1Supportswhichdonotmeetthevisual(VT-3)examination requirements shallbereportedforevaluation andappropriate corrective action.Repair&TestingRequirements: Applicable repairsandtestingshallbeperformed totherequirements ofSupplement 2toAppendixB,theRepair,Replacement andModification Program.CodeCaseN-498doesnotapplytoRepairs.Replacement &Modification, andTestingRequirements: Replacements andModifications, andapplicable testingshallbeperformed totherequirements ofSupplement 2toAppendixB,theRepair,Replacement andModification Program.CodeCaseN-498doesnotapplytoReplacements andModifications. Scheduling: Scheduling ofidentified SeismicCategoryIsupportsshallbeperformed andcontrolled withinSupplement 1toAppendixB,theprogramplan.ReportsandRecords:Reportsandrecordsgenerated onidentified SeismicCategoryIsupportsshallconformtoapplicable requirements specified withinSection1andSupplement 2toAppendixB.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E-GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMSection10PAGE3of6Table1SeismicCategoryISupportsLineSegment:AFW100SupportNumberAFU-130AFU-139SupportNumberAFU-132SupportNumberAFU-137SupportNumberAFU-138LineSegment:AFW200SupportNumberAFU-88LineSegment:AFW300SupportNumberAFU-4Support,NumberAFU-5SupportNumberAFU-6SupportNumberAFU-7LineSegment:CfTC100SupportNumberCVU-84LineSegment:CVC200SupportNumberCVU-125SupportNumberCVU-126SupportNumberCVU-129SupportNumberCVU-130LineSegment:CVC700SupportNumberCVC-56SupportNumberCVC-58 QUALIT'ZASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMREV.Section101PAGE4of6Table1(Cont.)SeismicCategoryISupportsLineSegment:CVC730SupportNumberCVC-39SupportNumberCVC-40LineSegment:FW300SupportNumberFWU-40FWU-36FWU-32FWU-28SupportNumberFWU-39FWU-35FWU-31SupportNumberFWU-38FWU-34FWU-30SupportNumberFWU-37FWU-33FWU-29LineSegment:FW301SupportNumberFWU-16FWU-20FWU-24SupportNumber$'WU-17FWU-21FWU-25SupportNumberFWU-18FWU-22FWU-26SupportNumberFWU-19FWU-23FWU-27LineSegment:MS300SupportNumberMSU-35MSU-52MSU-48MSU-57SupportNumberMSU-59MSU-53MSU-49SupportNumberMSU-60MSU-54MSU-50SupportNumberMSU-51MSU-47MSU-56LineSegment:RHR300SupportNumberRHU-86SupportNumberRHR-87SupportNumberRHU-90SupportNumberRHR-91 QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMREV.Section101PAGE5of6Table1(Cont.)SeismicCategoryISupportsLineSegment:SAFW450SupportNumberAFU-169AFU-177SupportNumberAFU-170SupportNumberAFU-175SupportNumberAFU-176LineSegment:SGB-300SupportNumberBDU-21SupportNumberBDU-23LineSegment:SGB-400SupportNumberBDU-26SupportNumberBDU-27LineSegment:S2100SupportNumberSIU-8LineSegment:SI200SupportNumberSIU-55LineSegment:SW1500SupportNumberSWU-363SupportNumberSWU-364SupportNumberSWU-365SupportNumberSWU-366 II'I QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E-GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALSEISMICSUPPORTPROGRAMREV.1PAGE6of6Section10Table1(Cont.)SeismicCategoryISupportsLineSegment:SW2100SupportNumberSWU-523SWU-533SupportNumberSWU-524SWU-534SupportNumberSWU-525SupportNumberSWU-526LineSegment:SW2300SupportNumberSWU-602SWU-606SupportNumberSWU-603SWU-607SupportNumberSWU-604SupportNumberSWU-605LineSegment:SW2500SupportNumberSWU-637SWU-638SupportNumberSWU-642SupportNumberSWU-639SupportNumberSWU-640 QUALITYASSURANCE MANUALGINNASTATIONSectionllEFFECTIVE DATE:PAGE1of9December31,1993ROCHESTER GAS8ELECTRICCORPORATION TITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSSIGNATURE PREPAREDBY:$~+)gQUALITYASSURANCE REVIEW:APPROVEDY:DATEI~-I-6lZ441.0General:Thepurposeofthissectionistoprovideinformation andclarification onadditional inspection programsbeingperformed atR.E.GinnaNuclearPowerPlant.Theseinspection programsmaybedueinparttoASMESectionXIprogramrequirements ortoothercommitments madebyRochester GasandElectric. Thefollowing listidentifies additional inspection programsbeingperformed atR.E.GinnaNuclearPowerPlant:SteamGenerator TubeInspection ProgramReactorCoolantPumpFlywheelProgramClass1BoltingProgram(IEB82-02).,ReactorVesselAugmented Program,CategoryB-A2.0SteamGenerator TubeInsectionProram:2.1General:2~1.1TheSteamGenerator TubeInspection Programincorporates therequirements ofASMESectionXICode,underCategoryB-Q,ItemNumberB16.20.TheCoderequiresthatSteamGenerator tubinginU-TubeDesignbevolumetrically (EddyCurrent)examinedtotheextentandfrequency governedbytheplantTechnical Specifications. Inaccordance withthisCoderequirement andR.E.GinnaStationTechnical Specifications, eddycurrentexaminations shallbeperformed. SteamGenerator Tubingshallbeexaminedtheirfulllength,atleastonceeveryfiveyears. I' QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.Sectionll3PAGE2of92.1.2TheSteamGenerator TubeInspection Programalsoincorporates therequirements ofUSNRCRegulatory Guide1.83,Revision1,datedJuly,1975,"Inservice Inspection ofPressurized WaterReactorSteamGenerator Tubes"andtherecommendations oftheElectricPowerResearch(EPRI)PWRSteamGenerator Inspection Guidelines, Revision2.2.2Examination Requirements: 2.2.1Theprogramforeachyearofthefiveyearsshallinclude,asaminimum,thefollowing requirements: l.Arotatingrandomsamplingof20%ofalloperational tubesfortheirfulllength.2.Arotatingrandomsampleof20~ofeachtypeofsleevedinlettubefortheirfulllength,,including thesleevefromtheupperendthroughtheexpandedtransition ofthelowerend.3.Alloperational tubesthathadapreviously identified degradation ofgreaterthan20%throughwalltotheextentofpreviously identified degradation. However,ifaftertwo(2)consecutive inspections thesetubeshavenothadgreaterthan104furtherpenetration, theinspection frequency onthesetubesmaybeextendedto40months.2.2.22Othertubesmaybeaddedtotheprogrameachyearasnecessary tomeetotherconcernsandareclassified as"ownerelected". "OwnerElected"examinations arenotmandatory andmaybeperformed asdetermined bytheowner.TheGinnaSteamGenerator Reliability Committee maychangetheaforementioned plantomeetoutageschedules, providedthatthechangesmeettherequirement ofRegulatory Guide1.83andSupplement 1tothisAppendix. 2.3Examination Method:2.3.1EddyCurrent(Volumetric) Examination techniques shallbeemployedtoperformtherequiredexaminations onSteamGenerator tubes. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.Section11'PAGE3of92.42.4.12.5Frequency ofExaminations: Examinations shallbeperformed everyrefueling outagetotheextentrequiredandspecified within2.2,asaminimum.Examination Evaluation: 2.5.1EddyCurrentevaluation shallbeperformed inaccordance withR.E.GinnaStationTechnical Specifications. 2.62.6.1Repair,Replacement andTestingRequirements Repaircriteriaforsteamgenerator tubesisbasedontherequirements ofRegulatory Guide1.121,"BasesforPluggingDegradedPWRSteamGenerator Tubes".2.6.1.12.6.1.22.6.22.72.7.12.82.8.1Steamgenerator tubesthathaveimperfections greaterthan40percentthrough-wall asindicated byeddycurrent,shallberepairedbypluggingorsleeving. Steamgenerator sleevesthathaveimperfections greaterthan30percentthroughwallasindicated byeddycurrentshallberepairedbyplugging. Repairsbyweldedplugsandsleevesshallbeperformed inaccordance withSupplement 2tothisAppendix. Scheduling: EddyCurrentexamination schedules ofSteamGenerator Tubesshallbeestablished withinSupplement 1tothisAppendix. ReportsandRecords:Applicable recordsshallbemaintained asspecified withinSection1ofthisprogramandasapplicable andrequiredwithinSupplement 2tothisAppendix. QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.Section113PAGE4of92.8.2Within15daysfollowing thecompletion oftheevaluation ofeachinservice inspection ofsteamgenerator tubes,thenumberoftubesrequiredbyParagraph 2.6.1abovetobepluggedorsleevedineachsteamgenerator shallbereportedtotheUSNCRin,aSpecialReport.2.8.3Thecompleteresultsofthesteamgenerator tubeinservice inspection shallbesubmitted totheUSNRCinaSpecialReportwithin12monthsfollowing thecompletion oftheinspection. ThisSpecialReportshallinclude:(a)Numberoftubesinspected andextenttowhichinspected. (b)Locationandpercentofwall-thickness penetration. foreachindication ofanimperfection, and(c)Identification oftubespluggedorsleeved.2.8.4Ifthenumberoftubesinagenerator fallingintocategories (a)or(b)belowexceedsthecriteria, thenresultsoftheinspection shallbeconsidered aReportable Eventpursuantto10CFR50.73.Oralnotification totheNRCStaffshallbeaccomplished within48hours,butnosoonerthanthenextnormalworkingdayafterthefinalreviewoftheeddycurrentresults.Awrittenfollow-up reportshallprovideadescription ofinvestigations conducted todetermine thecauseofthetubedegradation andcorrective measurestakentoprecluderecurrence. Categories (a)and(b)are:(a)Morethan10percentofthetotaltubesinspected aredegraded(imperfections greaterthan20percentofthenominalwallthickness). However,previously degradedtubesmustexhibitat,least10percentfurtherwallpenetration tobeincludedinthiscalculation. (b)Morethan1percentofthetotaltubesinspected aredegraded(imperfections greaterthantherepairlimit). ,I QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.Section113PAGE5of93.0ReactorCoolantPumFlheelProram:3.1General:Theaugmented inservice inspection programforReactorCoolantPumpFlywheels incorporates therequirements oftheUSNRCRegulatory Guide1.14,Revision1,datedAugust1975,entitled"ReactorCoolant:PumpFlywheelIntegrity". 3.2Examination Requirements: 3.2.1Examinations shallbeperformed. onallactiveReactorCoolantPumpFlywheels andAnti-Rotation Pawls.3'Examination Method:3.31ReactorCoolantPumpFlywheels shallbeexaminedusingUltrasonic andSurfaceexamination techniques. 3.3.23.3'ReactorCoolantPumpAnti-Rotation PawlsshallbeexaminedusingSurfaceexamination techniques. Ultrasonic andSurfaceexaminations shallconformtoandbeperformed inaccordance withSection1ofthisprogram.3.4Frequency ofExaminations: 3.4.1Examinations shallbeperformed onalloperating ReactorCoolantPumpFlywheelandAnti-Rotation Pawlsonceeachperiod.3.5Examination Evaluation: 3.5.1Examination evaluations shallbeperformed inaccordance withSection1ofthisprogram.3.5.2Unacceptable examinations shallbereportedforevaluation andappropriate corrective action. QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.3PAGE6of9Section113.6Repair,Replacement andTestingRequirements 3.6.13.7RepairsandReplacements shallbeperformed inaccordance withSupplement 2tothisAppendix, asapplicable. Scheduling: 3.7.1Examination schedules shallbeestablished withinSupplement, 1tothisAppendix. 3.8ReportsandRecords:3.8.1Applicable recordsshallbemaintained asspecified inSection1ofthisprogramand'whenrequiredwithinSupplement 2tothisAppendix. 4.0Class1BoltinProramIEB82-024.1General:Thisaugmented inspection programwasestablished toaddressIEBulletin82-02,"Degradation ofThreadedFasteners intheReactorCoolantPressureBoundaryofPWRPlants"datedJune2,1982.4.2Examination Requirements: 4.2.1Examinations shallbeperformed onthreadedfasteners ofclosureconnections whenopenedforcomponent inspection ormaintenance forthefollowing, asapplicable: Steamgenerator andpressurizer manwayclosures. 2.Valvebonnetsandpumpflangeconnections installed onlineshavinganominaldiameterof6inchesorgreater.3.Controlroddrive(CDR)flangeandpressurizer heaterconnections thatdonothavesealweldstoprovideleak-tight integrity. 4LHII QUALITYASSURANCE MANUALGINNASTATIONTITLEAPPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVXCE INSPECTXON PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.3PAGE7of9Section114.3Examination Method:4.3.1Applicable threadedfasteners ofclosureconnections shallbeexaminedutilizing bothSurfaceandVisualtechniques. 4'Frequency ofExaminations: 4.4.1Applicable components containing threadedfasteners ofclosureconnections shallbeexaminedwhenopenedforcomponent inspection ormaintenance. 4.5Examination Evaluation: 4.5.1Examination evaluations shallbeperformed inaccordance withSection1ofthisprogram.4.5.2Unacceptable examinations shallbereportedforevaluation andappropriate corrective action.4.6Repair,Replacement andTestingRequirements 4.6.14.7RepairsandReplacements shallbeperformed inaccordance withSupplement 2tothisAppendix, asapplicable. Scheduling: 4.7.1Examination schedules shallbeestablished, asapplicable andrequired, withinSupplement 1"tothisAppendixortheMaintenance Inservice Inspection Program(MISIP).4.8ReportsandRecords:4.8.1Applicable recordsshallbemaintained asspecified withinSection1ofthisprogramandasapplicable whenrequiredwithinSupplement 2tothisAppendix.

QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.3PAGE8of9Section115.0ReactorVesselAuentedProramCateorB-A:-5.15.2General:rAsspecified withintheFederalRegister, 10CFRPart50,Vol.57,No.152datedAugust6,1992,aspecificaugmented examination programisrequiredforASMESectionXICategoryB-A,ShellWeldsof"Pressure Retaining WeldsinReactorVessel".Examination Requirements: 5.2.15.3Examinations shallbeperformed onallASMESectionXICategoryB-A,ItemB1.0,ShellWeldsof"Pressure Retaining WeldsinReactorVessel"thatarenotrequiredbytheCode.Examination Method:5.3.15.4Ultrasonic examinations shallconformandbeperformed inaccordance withSection1ofthisprogram.Frequency ofExaminations: 5.4.15.5Examinations shallbeperformed onceduringtheInspection Interval. Examination Evaluation: 5.5.15.5.25.6Examination Evaluations shallbeperformed inaccordance withSection1ofthisprogram.Unacceptable examinations shallbereportedforevaluation andappropriate corrective action.Repair,Replacement andTestingRequirements 5.6.1RepairsandReplacements shallbeperformed inaccordance withSupplement 2tothisAppendix, asapplicable. i<<iIIll QUALITYASSURANCE MANUALGINNASTATIONTITLE:APPENDIXBR.E.GINNANUCLEARPOWERPLANTINSERVICE INSPECTION PROGRAMFORTHE1990-1999 INTERVALADDITIONAL PROGRAMSREV.3PAGE9of9Section115.75.7.15.85.8.1Scheduling: Examination schedules shallbeestablished withinSupplement 1tothisAppendix. 1ReportsandRecords:Applicable recordsshallbemaintained asspecified withinSection1ofthisprogramandwhenrequiredwithinSupplement 2tothisAppendix.}}