ML17261B124
| ML17261B124 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/30/1990 |
| From: | BROWN B W, MUDLIN J D EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML17261B121 | List: |
| References | |
| CON-FIN-D-6022 EGG-MS-8923, NUDOCS 9008080272 | |
| Download: ML17261B124 (73) | |
Text
Attachment 2EGG-MS-8923 TECHNICAL EVALUATION REPORTONTHETHIRD10-YEARINTERVALINSERVICE INSPECTION PROGRAMPLAN:ROCHESTER GASANDELECTRICCORPORATION, R.E.GINNANUCLEARPOWERSTATION,DOCKETNUMBER50-244B.W.BrownJ.D.MudlinPublished April1990IdahoNationalEngineering Laboratory EG&GIda'ho,Inc.IdahoFalls,Idaho83415Preparedfor:U.S.NuclearRegulatory Commission Washington, D.C.20555underDOEContractNo.DE-AC07-76ID01570 FINNo.D6022(Project5)9008080272 9PDRADOCK90080605000244PDC ABSTRACTThisreportpresentstheresultsoftheevaluation oftheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection (ISI)ProgramPlan,submitted July21,1989,including therequestsforrelieffromtheAmericanSocietyofMechanical Engineers (ASHE)BoilerandPressureVesselCodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical.
TheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlanisevaluated inSection2ofthisreport.TheISIProgramPlanisevaluated for(a)compliance withthe"appropriate edition/addenda ofSectionXI,(b)acceptability ofexamination sample,(c)correctness oftheapplication ofsystemorcomponent examination exclusion
- criteria, and(d)compliance withISI-related commitments identified duringpreviousNuclearRegulatory Commission (NRC)reviews.Therequestsforreliefareevaluated inSection3ofthisreport.Thisworkwasfundedunder:U.S.NuclearRegulatory Commission FINNo.06022,Project5Operating Reactor,Licensing IssuesProgram,ReviewofISIforASHECodeClass1,2,and3Components SUMMARYTheLicensee, Rochester GasandElectricCorporation, haspreparedtheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection (ISI)ProgramPlantomeettherequirements ofthe1986EditionoftheASMECodeSectionXI.Thethird10-yearintervalbeganJanuary1,1990andendsDecember31,1999.Theinformation intheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlan,submitted July21,1989,wasreviewed.
IncludedinthereviewweretherequestsforrelieffromtheASMECodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical.
Asaresultofthisreview,arequestforadditional information (RAI)wasprepareddescribing theinformation and/orclarification requiredfromtheLicenseeinordertocompletethereview.TheLicenseeprovidedadditional information inthesubmittal datedJanuary16,1990.BasedonthereviewoftheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlan,theLicensee's responsetotheNuclearRegulatory Commission's RAI,andtherecommendations forgrantingrelieffromtheISIexamination requirements thathavebeendetermined tobeimpractical, itisconcluded thattheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlan,withtheexception oFRequestforReliefNos.10and13,isacceptable andincompliance with10CFR50.55a(g)(4).
111 I~,CONTENTSABSTRACT~~~~11SUMMARY~~~~~~oillINTRODUCTION~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~~~~~~~~~~~12.EVALUATION OFINSERVICE INSPECTION PROGRAMPLAN...................
32.1Documents Evaluated
...........................................
32.2Compliance withCodeRequirements
..........
2.2.1Compliance withApplicable CodeEditions2.2,2Acceptability oftheExamination Sample...332.2.3Exclusion Criteria.~~~~~~~~~~~~~~~~~~~~2.2.4Augmented Examination Commitments
..........................
42..3Conclusions
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3.EVALUATION OFRELIEFREQUESTS...................................
~.53.1Class1Components
.............................................
.53.1.1ReactorPressureVessel3.1.1.1RequestforReliefNo.1,Examination CategoryB-A,ItemBl.30,DeferralofRPVShell-to-Flange WeldExaminations
..........'...............................
~.53.1.1.2RequestforReliefNo.2,Examination CategoryB-D,ItemsB3.90andB3.100,ReactorPressureVesselNozzle-to-Vessel WeldsandNozzleInsideRadiusSections,..............
~~~~~~~~.83.1.23.1.33.1.4Pressurizer (Noreliefrequests)
HeatExchangers andSteamGenerators (Norelief'requests)
P'pingPressureBoundary...................................
113.1.4.1RequestforReliefNo.16(Part1of2),Examination CategoryB-K-I,ItemB10.10,Class1PipingIntegrally WeldedAttachments
......'....................
ll 3.1.5PumpPressureBoundary123.1.5.1RequestforReliefNo.4,Examination CategoryB-L-1andB-L-2,ItemsB12.10andB12.20,Class1PumpCasingWeldsandPumpCasings.............
123.1.6ValvePressureBoundary..153.1.6.1RequestforReliefNo.5,Examination CategoryB-H-2,ItemB12.50,Class1ValveBodyInternalSurfaces......................................
153.1.7General(Noreliefrequests) 3.2Class2Components
...........
3.2.1PressureVessels(Noreliefrequests) 3.2.2Piping....~~~~~~~~~~~~~~~~~~~~18183.2.2.1RequestforReliefNo.15,Examination CategoryC-F-1andC-F-2,ItemsC5.10andC5.50,Class2PipingWelds...............
...............
183.2.2.2RequestforReliefNo.16(Part2of2),Examination CategoryC-C,ItemC3.20,Class2PipingIntegrally WeldedAttachments
.3.2.3Pumps(Noreliefrequests) 3.2.4Valves(Noreliefrequests) 3'.5General(Noreliefrequests) 3.3Class3Components (Noreliefrequests) 183'PressureTests..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~\193.4.1Class1SystemPressureTests(Noreliefrequests) 3.4.2Class2SystemPressureTests..............................
193.4.2.1RequestforReliefNo.7,SystemHydrostatic TestofThreeChargingPumpsandDischarge PipingtoDischarge Isolation ValvesintheChemistry andVolumeControlSystem...............'.
..............
193.4.2.2RequestforReliefNo.8,SystemHydrostatic TestofReactorCoolantSystemOverpressure Protection NitrogenAccumulator SystemValvesPCV430andPCV431C~~~~~~~~~~o'~~~~~~~~~~~20 3.4.2.3RequestforReliefNo.9,SystemHydrostatic TestoftheSecondary SideoftheSteamGenerator andAssociated HainSteamPiping.....223.4.2.4RequestforReliefNo.13,SystemHydrostatic TestofNon-ISIClassified Systems............
.......253.4.3Class3SystemPressureTests.283.4.3.1RequestforReliefNo.6,SystemHydrostatic TestoftheRadioactive WasteHoldupTank...................
283.4.3.2RequestforReliefNo.10,SystemHydrostatic TestoftheStandbyAuxiliary Feedwater PumpRecirculation Line....................
283.4.3.3RequestforReliefNo.11,SystemHydrostatic TestoftheBoricAcidFilterandAssociated PipingintheChemicalandVolumeControlSystem.3.4.3.4RequestforReliefNo.12,SystemHydrostatic TestofPortionsoftheEmergency DieselGeneration 30System0~~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~~~303.4.3.5RequestforReliefNo.14,SystemHydrostatic TestofAllPressureRetaining Components WithintheClass3PortionoftheServiceWaterSystem............
323.4.4General(Noreliefrequests) 3.5General~~~~~~~~~~~~~~~~~343.5.1Ultrasonic Examination Techniques (Noreliefrequests) 3.5.2ExemptedComponents (Noreliefrequests) 3.5.3Other.~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~353.5.3.1RequestforReliefNo.3,UseofanAuthorized Inspection AgencytoProvideInspection Services.......'5~CONCLUSION~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t,~~~~~~~~~~~3845.REFERENCES
......................
~~~~~~~~~~~~~~~~~~~~~~~~~40
.r.*L~+pipII" TECHNICAL EVALUATION REPORTONTHETHIRD10-YEARINTERVALINSERVICE INSPECTION PROGRAMPLAN:ROCHESTER GASANDELECTRICCORPORATION, R.E.GINNANUCLEARPOWERSTATION,DOCKETNUMBER50-2441.INTRODUCTION Throughout theservicelifeofawater-cooled nuclearpowerfacility, 10CFR50.55a(g)(4)
(Reference 1)requiresthatcomponents (including supports) thatareclassified asAmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCodeClass1,Class2,andClass3meettherequirements, exceptthedesignandaccessprovisions andthepreservice examination requirements, setforthintheASMECodeSectionXI,"RulesforInservice Inspection ofNuclearPowerStationComponents,"
(Reference 2)totheextentpractical withinthelimitations ofdesign,geometry, andmaterials ofconstruction ofthecomponents..
Thissectionoftheregulations alsorequiresthatinservice examinations ofcomponents andsystempressuretestsconducted duringsuccessive 120-month inspection intervals shallcomplywiththerequirements inthelatesteditionandaddendaoftheCodeincorporated byreference in10CFR50.55a(b) onthedate12monthspriortothestartofthe120-month inspection
- interval, subjecttothelimitations andmodifications listedtherein.Thecomponents (including supports) maymeetrequirements setforthinsubsequent editionsandaddendaofthisCodewhichareincorporated byreference in10CFR50.55a(b) subjecttothelimitations andmodifications listedtherein.TheLicensee, Rochester GasandElectricCorporation, haspreparedtheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection (ISI)ProgramPlantomeettherequirements ofthe1986EditionoftheASMECodeSectionXI.Thethird10-yearintervalbeganJanuary1;1990andendsDecember31,1999.Asrequiredby10CFR50.55a(g)(5),
ifthelicenseedetermines thatcertainCodeexamination requirements areimpractical andrequestsrelieffromthem,thelicenseeshallsubmitinformation andjustifications totheNuclearRegulatory Commission (NRC)tosupportthatdetermination.
'Pursuant to10CFR50.55a(g)(6),
theNRCwillevaluatethelicensee's determinations under10CFR50.55a(g)(5) thatCoderequirements areimpractical.
TheNRCmaygrantreliefandmayimposealternative requirements thataredetermined tobeauthorized bylaw,willnotendangerlifeorpropertyorthecommondefenseandsecurity, andareotherwise inthepublicinterest, givingdueconsideration totheburdenuponthe6'licenseethatcouldresultiftherequirements wereimposedonthefacility.
Theinformation intheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlan(Reference 3),submitted July21,1989,wasreviewed, including therequestsforrelieffromtheASHECodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical.
ReviewoftheISIProgramPlanwasperformed usingtheStandardReviewPlansofNUREG-0800 (Reference 4),Section5.2.4,"ReactorCoolantBoundaryInservice Inspections andTesting,"
andSection6.6,"Inservice Inspection ofClass2and3Components."
InaletterdatedNovember16,1989(Reference 5),theNRCrequested additional information requiredinordertocompletethereviewoftheISIProgramPlan.Additional information wasprovidedbytheLicenseeinasubmittal datedJanuary16,1990(Reference 6).TheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlanisevaluated inSection2ofthisreport.TheISIProgramPlanisevaluated for(a)compliance withtheappropriate edition/addenda ofSectionXI,(b)acceptability ofexamination sample,(c)correctness oftheapplication ofsystemorcomponent examination exclusion
- criteria, and(d)compliance withISI-related commitments identified duringpreviousNRCreviews.Therequestsforreliefareevaluated inSection3ofthisreport.Unlessotherwise stated,references totheCoderefertotheASHECode,SectionXI,1986Edition.Specificinservice test(IST)programsforpumpsandvalvesarebeingevaluated inotherreports.
02.EVALUATION OFINSERVICE INSPECTION PROGRAMPLANThisevaluation consisted ofareviewoftheapplicable programdocuments todetermine whetherornottheyareincompliance withtheCoderequirements andanylicenseconditions pertinent toISIactivities.
Thissectiondescribes thesubmittals reviewedandtheresultsofthereview.2.1Oocuments Evaluated Reviewhasbeencompleted onthefollowing information providedbytheLicensee:
(a)R.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection ProgramPlan;and(b)Letter,datedJanuary16,1990,containing theLicensee's responsetotheNRCrequestforadditional information.
2.2Compliance withCodeReuirements 2.2.1ComliancewithAlicableCodeEditionsTheInservice Inspection ProgramPlayshallbebasedontheCodeeditionsdefinedin10CFR50.55a(g)(4) and10CFR50.55a(b).
BasedonthestartingdateofJanuary1,1990,fortheR.E.GinnaNuclearPowerStation,theCodeapplicable tothethird10-yearintervalISIprogramplanisthe1986Edition.AsstatedinSection1ofthisreport,theLicenseehaswrittentheR.E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlantomeettherequirements ofthe,1986EditionoftheASHECode.I2.2.2AccetabilitoftheExamination SamleInservice volumetric, surface,andvisualexaminations shallbeperformed onASHECodeClass1,2,and3components andtheirsupportsusingsamplingschedules described inSectionXIoftheASMECodeand 0A10CFR50.55a(b).
Samplesizeandweldselection havebeenimplemented inaccordance withtheCodeandappeartobecorrect.2.2.3Exclusion CriteriaThecriteriausedtoexcludecomponents fromexamination shallbeconsistent withParagraphs IWB-1220, IWC-1220, IWC-1230, IWO-1220',
and10CFR50.55a(b).
Theexclusion criteriahavebeenappliedbytheLicenseeinaccordance withtheCodeasdiscussed intheISIProgramPlanandappeartobecorrect.2.2.4AumentedExamination Commitments Inadditiontotherequirements specified inSectionXIoftheASMECode,theLicenseehascommitted toperformaugmented examinations inaccordance withNRCRegulatory Guide1.14,"ReactorCoolantPumpFlywheelIntegrity,"
Revision1,(Reference 7)andNRCRegulatory Gu'ide1.150,"Ultrasonic TestingofReactorVesselWeldsOuringPreservice andInservice Examinations,"
Revision1(Reference 8).Also,circumferential buttweldsinhighenergypipingoutsideofcontainment whereafailurewouldresultinunacceptable consequences willreceiveradiographic orultrasonic volumetric examinations andmagneticparticlesurfaceexaminations.
'2.3Conclusions Basedonreviewofthedocuments listedabove,itisconcluded thattheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection ProgramPlanisacceptable andincompliance with10CFR50.55a(g)(4).
3.EVALUATION OFRELIEFREQUESTSRequestsforrelieffromtheASHECoderequirements thattheLicenseehasdetermined tobeimpractical forthethird10-yearinspection intervalareevaluated inthefollowing sections.
3.1Class1Comonents3.1.1ReactorPressureVessel3.1.1.1ReuestforReliefNo.1Examination CateorB-AItemBl.30.DeferralofRPVShell-to-Flan eWeldExaminations CodeReuirement:
SectionXI,TableIWB-2500-1, Examination CategoryB-A,Item81.30requiresa100%volumetric examination oftheReactorPressureVesselshell-to-flange weldasdefinedbyFigureIWB-2500-4.
Note5statesthat,ifpartialexaminations areconducted fromtheflangeface,theremaining volumetric examinations requiredtobeconducted fromthevesselwallmaybeperformed atorneartheendofeachinspection interval.
Note6statesthattheexamination ofshell-to-flange weldsmaybeperformed duringthefirstand'hirdinspection periodsinconjunction withthenozzleexamination ofExamination CategoryB-D.Atleast50%ofshell-to-flange weldsshallbeexaminedbytheendofthefirstinspection periodandtheremainder bytheendofthethirdinspection period.Licensee's CodeReliefReuest:Reliefisrequested todeferthevolumetric examination oftheReactorPressureVessel(RPV)shell-toflangeweldtotheendoftheinspection interval.
Licensee's ProosedAlternative Examination:
TheLicenseestatesthat,duringthethirdinterval, 100%oftheaccessible lengthofallRPVwelds,including theshell-to-flange weld,willbeperformed atorneartheendoftheintervalwhenalltherequiredexaminations canbeperformed atthesame.time.
Licensee's BasisforReuestinRelief:TheLicenseestatesthattherequiredshell-to-flange examination isimpractical ifperformed duringtheperiodsspecified asitcanbeaccomplished onlyfromtheflangesurface.Duringthefirsttwoinspection intervals, 100%oftheaccessible lengthoftheRPVwelds,including theshell-to-flange weld,wasexaminedatorneartheendoftheintervalwhentheentireexamination couldbeperformed fromboththeflangesurfaceandthevesselwall.Thisisamorepractical approachinthattherequiredexaminations frombothsurfacescanbeperformed atthesametime.TheLicensee's January16,1990submittal statedthatRochester GasandElectricreceivedreliefforR.E.Ginnaforthesecondinterval(1979-1989) allowingdeferralofallvesselmechanized examinations including categoryB-Atotheendofthesecondinterval.
Fullexamination oftheRPVshell-to-flange weld(Category B-A)wasperformed fromtheflangesurfaceandfromthevesselshellduringtheendofintervalMarch-April 1989refueling outage.Theexamination wasperformed inaccordance withthe1974Edition,Summer1975AddendaoftheASMECode.Indications wererecordedandanalyzedduringtheseriesofexaminations performed atthe1989outage.Comparisons oftheirsizetothesameindications recordedduringthepreservice examination andthe1979endofthefirstintervalinservice examination ledtonoindications ofgrowthofdefects.Theindications weresizedutilizing, bothconventional beamspreadtechniques andspecially developed focusedbeamsizingtechniques.
Noevidenceofgrowthwasdetectedbyutilizing theseexamination techniques.
Theseexaminations werewitnessed bytheNRCandtheirconsultants duringthe1989outage.
tIf't)9
~0Theresultsofthe1989examinations withcomparative sizingcalculations
.andfracturemechanics evaluation weresubmitted totheNRConHay4,1989.ThedataprovidedwereacceptedbytheNRConJune5,1989withnorequirements foraugmented examinations.
TheLicenseehas,therefore, scheduled thenextseriesofCategoryB-ARPVexaminations forthe1999timeframe(endofthis10-yearinterval).
Examination CategoryB-AinTableIWB-2500ItemnumberB1.30alreadyallowsexamination deferralasindicated infootnote5ofthenotes.Byfollowing the1986Codecriteria, theCodewouldrequireavessel-to-flange examination fromtheflangesealsurfaceduringthefirstperiodofthethirdinterval.
Sinceallreactorvesselexaminations, including thevessel-to-flange weldfromtheflangesurfaceandwall,wereaccomplished in1989,theprescribed B-A,B1.30,Codecriteriawouldallowanother10yearsbeforethereexamination.
Sincetheexamination oftheRPVvessel-to-flange weldwasaccomplished completely in1989,theLicenseeproposestoreexamine theweldattheendofthethirdinterval.
TheLicenseealsobelievesthattheresultsobtainedfromanexamination performed duringthefirstperiodofthethirdintervalwouldnotprovidethebestdatatoensureadditional safetyandsystemreliability.
Also,performing thistypeofexamination ataconstantfrequency ratherthanayearortwofollowing amajorexamination ofthatsamecomponent willproducemoremeaningful results.Evaluation:
Paragraph IWB-2420(a),
"Successive Inspections,"
statesthatthesequenceofcomponent examinations established duringthefirstinspection intervalshallberepeatedduringeachsuccessive inspection
- interval, totheextentpractical.
Sincetheexaminations wereperformed duringthethirdperiodofthesecondintervalwith'NRCapproval, theintentoftheCodewillbemetbyexamining theseweldsduringthethirdperiodofthethirdinterval.
lItO'III
==
Conclusions:==
intentoftheTherefore, itrequested.
Basedontheabove,itisconcluded thattheCodewillbemetbythealternative
- schedule, isrecommended thatreliefbegrantedas3.1.1.2ReuestforReliefNo.2Examination Cateor8-DItems83.90andB3.100ReactorPressureVesselNozzle-to-Vessel WeldsandNozzleInsideRadiusSectionsCodeReuirement:
SectionXI,TableIWB-2500-1, Examination CategoryB-D,ItemB3.90requiresa100%volumetric examination oftheRPVnozzle-to-vessel weldsasdefinedbyFigureIWB-2500-7.
Inspections maybepartially deferredunderthefollowing conditions:
Ifexaminations areconducted frominsidethecomponent andthenozzleweldisexaminedbystraightbeamultrasonic methodfromthenozzlebore,theremaining examinations requiredtobeconducted fromtheshellinsidediametermaybeperformed atorneartheendofeachinspection interval.
Examination CategoryB-D,ItemB3.100requiresa100%volumetric examination of.theRPVnozzleinsideradiussectionsasdefinedbyFigureIWB-2500-7.
Atleast25%butnotmorethan50%(credited) ofthenozzlesshallbeexaminedbytheendofthefirstinspection periodandtheremainder bytheendoftheinspection interval.
Licensee's CodeReliefReuest:Reliefisrequested todeferthevolumetric examinations oftheRPVnozzle-to-vessel weldsandnozzleinsideradiussectionstotheendoftheinspection interval.
Licensee's ProosedAlternative Examination:
TheLicenseeproposestoperformbothnozzle-to-vessel examinations (fromthenozzleboreandfromtheshellinsidediameter) atornear I
theendoftheinterval.
Thenozzleinsideradiusexaminations willalsobeperformed atthistime.Thismorepractical approachwillallowalltherequiredexaminations tobeperformed atthesametimeonallthenozzlesandnozzleinsideradii.Licensee's BasisforReuestinRelief:TheLicenseestatesthatexaminations fromthenozzleboreandnozzleinsideradiusexaminations canbeperformed ononlytwo(outlets) ofthesixmajornozzleswithoutremovalofthecorebarrel.Themechanized examination ofthetwoaccessible nozzleandinsideradiussectionsisexpensive, andthenozzle-to-vessel examination isonlyapartialexamination fromthenozzlebore.Fromatechnical positionconsidering theprogresswhichisbeingmadeinultrasonic examination equipment andtechniques andforthecorrelation ofdataobtainedfromtheborewiththatobtainedfromtheshell,itishighlydesirable toperformbothexaminations atthesametime.TheLicensee's January16,1990submittal statedthatRochester GasandElectricreceivedreliefforR.E.Ginnaforthesecondinterval(1979-1989) allowingdeferralofallvesselmechanized examinations including categoryB-Dtotheendofthesecondinterval.
Fullexaminations oftheRPVnozzle-to-vessel welds(Category B-D)wereperformed fromthenozzleboresduringtheendofintervalMarch-April 1989refueling outage.AllRPVnozzleinsideradiussectionexaminations werealsoperformed atthistime.Allexaminations wereperformed inaccordance withthe1974Edition,Summer1975AddendaoftheASMECode.Indications wererecordedandanalyzedduringtheseriesofexaminations performed atthe1989outage.Comparisons oftheirsizetothesameindications recordedduringthepreservice examination andthe1979endofthefirstintervalinservice examination ledtonoindications ofgrowthofdefects.Theindications weresizedutilizing both
~I~~fg' conventional beamspreadtechniques andspecially developed focusedbeamsizingtechniques.
Noevidenceofgrowthwasdetectedbyutilizing theseexamination techniques.
Theseexaminations werewitnessed bytheNRCandtheirconsultants duringthe1989outage.Resultsofthe1989examinations withcomparative sizingcalculations andfracturemechanics evaluation weresubmitted totheNRConMay,4,1989.ThedataprovidedwereacceptedbytheNRConJune5,'1989withnorequirements foraugmented examinations.
TheLicenseehas,therefore, scheduled thenextseriesofCategoryB-DRPVexaminations forthe1999timeframe(endofthis10-yearinterval).
TheCategoryB-Dweldsandinsideradiussectionsforallvesselsotherthanthereactorvesselhavebeenscheduled forexamination duringthethreeperiodsofthethirdinterval.
Byfollowing the1986Codecriteria, theCodewouldrequireanozzleexamination fromtheboreduringthefirstperiodofthethirdinterval.
Sinceallreactorvesselexaminations, including nozzle-to-shell fromboththeboreandshellandnozzleinsideradiussections, wereaccomplished in1989,theprescribed B-D,B3.90andB3.100Codecriteriawouldallowanother10yearsbeforethereexamination.
Sincetheexaminations wereaccomplished completely in1989,theLicenseeproposestoreexamine themattheendofthethirdinterval.
TheLicenseealsobelievesthatthe,resultsobtainedfromanexamination performed duringthefirstperiodofthethirdintervalwouldnotprovidethebestdatatoensureadditional safetyandsystemreliability.
Also,performing thistypeofexamination ataconstantfrequency ratherthanayearortwofollowing amajorexamination ofthatsamecomponent willproducemoremeaningful results.Evaluation:
Paragraph IWB-2420(a),
"Successive Inspections,"
statesthatthesequenceofcomponent examinations established duringthefirstinspection intervalshallberepeatedduring10 eachsuccessive inspection
- interval, totheextentpractical.
Sincetheexaminations wereperformed duringthethirdperiodofthesecondintervalwithNRCapproval, theintentoftheCodewillbemetbyexamining theseweldsduringthethirdperiodofthethirdinterval.
==
Conclusions:==
Basedontheabove,itisconcluded thattheintentoftheCodewillbemetbythealternative schedule.
Therefore, itisrecommended thatreliefbegrantedasrequested.
3.1.2Pressurizer (Noreliefrequests) 3.1.3HeatExchanersandSteamGenerators (Noreliefrequests) 3.1.4PiinPressureBoundar3.1.4.1ReuestforReliefNo.16Part1of2Examination CateorB-K-IItemB10.10Class1PiinInterailWeldedAttachments NOTE:RequestforRelief.No.16waswithdrawn bytheLicenseeintheJanuary16,1990submittal, whichstatesthefollowing:
"ReliefRequestNumber16isnotrequiredbytheCode.Theassociated programplantableswillbecorrected andupdatedtoassureaccurateaccounting.
Thisactivitywillbeperformed toreflectthe'non-requirement'ode statussincetheassociated thicknesses are<5/8"forclass1and<3/4"forclass2.ReliefRequestNumber16isnotrequiredandwillbedeleted."
11
3.1.5PumPressureBoundar3.1.5.1ReuestforReliefNo.4Examination CateorB-L-1andB-L-2ItemsB12.10and812.20Class1PumCasinWeldsandPum~CssinsCodeReuirement:
SectionXI,TableIWB-2500-1, Examination CategoryB-L-1,ItemB12.10requiresa100%volumetric examination ofClass1pumpcasingweldsasdefinedbyFigureIWB-2500-16.
Examination CategoryB-L-2,ItemB12.20requiresa100%visual(VT-3)examination oftheinternalsurfacesofClass1pumpcasings.Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required volumetric andvisual(VT-3)examinations ofthereactorcoolantpumpcasingweldsandinternal,
- surfaces, respectively.
Licensee's ProosedAlternative Examination:
Avisualexamination (VT-1)oftheexternalsurfacesoftheweldsofonepumpcasingwillbeperformed.
Avisualexamination (VT-3)oftheinternalsurfaceswillbeperformed eachtimeapumpisdisassembled.
Avisualexamination (VT-2)oftheexteriorofallpumpswillbeperformed duringthehydrostatic pressuretestrequiredbyTableIWB-2500-1,'Category B-P.Also,anevaluation willbeperformed todemonstrate thesafetyandserviceability ofthepumpcasing.Inmakingthisassessment, thermalagingembrittlement andanyotherprocesses thatmaydegradetheproperties ofthepumpcasingduringservicewillbeconsidered.
Licensee's BasisforReuestinRelief:Thetworeactor'oolantpumpsforR.E.GinnaareWestinghouse Model93pumps.Eachpumpcasingisfabricated byweldingfourstainless steel(SA351CFS)castingstogether.
Thus,therearethree12 circumferential pressureretaining weldsrequiring volumetric inspection inaccordance withCategoryB-L-l.TheLicenseestatesthattheunsuitability ofultrasonic examination wasdemonstrated duringthe"A"reactorcoolantpumpexamination in1980whenanattemptwasmadetodetermine thewallthicknesses usingultrasonic examination techniques.
Atthattime,itwasdetermined thatthecasingweldsmustbeinspected usingtheminiature linearaccelerator (HINAC).Radiographic examination usingtheHINACwasperformed ontheR.E.Ginna"A"reactorcoolantpumpduringtheSpring1981refueling outage.Thisexamination wasperformed byplacingtheHINACinsidethepumpcasingandplacingthefilmontheoutsideofthepump.Toperformtheexamination, thepumpwascompletely disassembled.
Also,theinsulation onthecasingexteriorwasremovedtopermitfilmplacement.
Additionally, thepumpbowlmustbedryforinstallation oftheHINAC.Therefore, allfuelassemblies wereremovedfromthereactorvesselandthevesselwaterlevelloweredtobelowthenozzles.Completedisassembly ofthepumpwasalsorequiredtoconducttheVT-1examination inaccordance with-'Category B-L-2.NoproblemshavebeenfoundwiththeweldsatR.E.Ginnaorothersites.Additionally, noproblemshavebeenfoundduringtheCategoryB-L-2visualexamination.
Visualexamination wasconducted atR.E.GinnabyusingthevideocameraontheMINAC.Thewholebodyexposuretopersonnel duringthespring1981refueling outagedirectlyattributable tothereactorcoolantpump"A"examinations is93,067millirem.
Thisdoesnotincludethedosereceivedduringthecompletecoreunloadtogettheplantincondition forthereactorcoolantpump'isassembly.
13 Thenuclearindustryhasbeensuccessfully applyingleak-before-break conceptstoprimaryloopandClass1auxiliary pipingsystemsofcommercial nuclearpowerpl,ants.Currently, theanalysessupporting suchconceptscomeunderthereviewoftheNRCbyGeneralDesignCriteria-4 (GOC-4).Eightdifferent modelsofreactorcoolantpumpsareusedinWestinghouse PWRs.Model93methodology usedintheanalysesisconsistent withthatrecommended inNUREG-1061, Vol.3andGDC-4.AfiniteelementstressanalysismodelfortheModel93pumpwasdeveloped.
Thereactorcoolantpumpcasingsarecaststainless steel.Thechemistries ofeachheatofmaterialusedinthepumpswereusedtodetermine thefracturetoughness.
Thephenomenon ofthermalagingwasaddressed.
Theprogramsuccessfully demonstrates thatleak-before-break analysesareapplicable toallprimarypumpcasingsofallWestinghouse designPWRsforwhichthescreening loadsarereasonably applicable andthefracturetoughness isknown.Evaluation:
Thevolumetric examination isimpractical toperformtotheextentrequiredbytheCodebecauseradiographic techniques forthesubjectpumpcasingweldsrequirecompletedisassembly ofthepumps,andultrasonic examinations arelimitedbythecoarsegrainstructure inherentinthickstainless steelcastings.
Thevisualexamination isperformed todetermine whetherunanticipated severedegradation ofthecasingisoccurring duetophenomena suchaserosion,corrosion, orcracking.
However,previousexperience duringexamination ofsimilarpumpsatother'plantshasnotshownanysignificant degradation ofpumpcasings.14 0"IIQF~t Thedisassembly ofthepumpsforthesolepurposeofinspection isamajoreffortand,inadditiontothepossibility ofdamagetothepumps,couldresultinpersonnel receiving excessive radiation exposure.
However,ifthepumpsaredisassembled formaintenance, theCode-required volumetric andvisualexaminations shouldbeperformed.
==
Conclusions:==
Basedontheaboveevaluation, itisconcluded thattheCoderequirement isimpractical.
Therefore, itisrecommended thatreliefbegrantedprovidedthat(a)visualexamination (VT-3)oftheinternalsurfacesofthepumpsisperformed wheneverthepumpsaredisassembled, (b)volumetric examination ofthepumpcasingweldsisperformed whenevertheweldsareexposedduetodisassembly ofthepump,(c)asurfaceexamination ofthepumpcasingweldsisperformed ifthepumpsarenotdisassembled, and(d)ifthepumpshavenotbeendisassembled, thisfactshouldbereportedbytheLicenseeintheISISummaryReportattheendoftheinterval.
3.1.6ValvePressureBoundar3.1.6.1RevestforReliefNo.5.Examination Cateor8-M-2ItemB12.50Class1ValveBodInternalSurfacesCodeReuirement:
SectionXI,TableIWB-2500-1, Examination CategoryB-M-2,Item812,50requires-a100%visual(VT-3)examination ofClass1valvebodyinternalsurfaces.
Examinations arelimitedtoatleastonevalve,withineachgroupofvalvesthatareofthesamesize,constructional design,andmanufacturing method,andthatperformsimilarfunctions inthesystem.Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required visual(VT-3)examination ofthevalvebodyinternalsurfacesofonevalveineachofthefollowing fourgroupsofClass1valves:15 Size~In.1010101010101010ValveNumber842A842B867A867B700701720721853A853B852A8528MfTeDarling/Check Darling/Check Darling/Check Darling/Check Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Check Velan/Check LineNumber10-SI2-2501-A 10A-SI2-2501-810-SI2-2501-B 10A-SI2-2501-B10A-RCO-2501-A 10A-AC7-2501-A 10A-AC7-2501-B 10A-AC7-2501-B 6A-RC-2501-A 6A-RC-2501-B 6A-RC-2501-A 6A-RC-2501-B Licensee's ProosedAlternative Examination:
TheLicenseestatesthat,asstandardmaintenance practicedictates, whenthesevalvesaredisassembled formaintenance
- purposes, avisualexamination oftheinternals andinternalpressureboundarysurfaceswillbeperformed totheextentpractical.
Licensee's BasisforReuestinaRelief:TheLicenseestatesthat,tocompletethesubjectexamination, unnecessary expenditures ofman-hours andmanremarerequiredwithessentially nocompensating increaseinplantsafety.Also,thestructural integrity affordedbyvalvecasingmaterialusedwillnotsignificantly degradeoverthelifetimeofthevalve.BasedondatacompiledfromaplantsimilarinageanddesigntoGinnaStation,itisexpectedthatapproximately 100manhoursand5manremexposurewouldberequiredtodisassemble, inspect,andreassemble thesevalv'es.Performing thisvisualexamination undersuchadverseconditions, highdoserates(30to40R/hr),andpooras-castsurfaceconditions, realistically provideslittleadditional information astothevalve'scasingintegrity.
Thevalvematerial, ahigh-strength caststainless steel(ASTt1A351-CF8),
iswidelyusedinthenuclearindustryandhas16
~~1~t performed extremely well.Thepresenceofsomedeltaferrite(typically 5%ormore)substantially increases resistance tointergranular stresscorrosion cracking.
Thedeltaferritealsohelpsthematerialtoresistpittingcorrosion inchloridecontaining environments.
TheLicenseefurtherstatesthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatpublichealthandsafetywillnotbeadversely affectedbynotperforming avisualexamination ofthevalveinternalpressureboundarysurfaces.
Additionally, thisvisualexamination addslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonnel tounnecessary radiation exposure.
Evaluation:
Thevisualexamination isperformed todetermine whetherunanticipated severedegradation ofthevalvebodyisoccurring duetophenomena suchaserosion,corrosion, orcracking.
However,previousexperience duringexamination ofsimilarvalvesatotherplantshasnotshownanysignificant degradation ofvalvebodies.Disassembly ofthevalvesforthesolepurposeofinspection isamajoreffortand,inadditiontothepossibility ofdamagetothevalves,couldresultinpersonnel receiving excessive radiation exposure.
However,ifthevalvesaredisassembled formaintenance, theinternalsurfacesshouldbeexamined.
==
Conclusions:==
Hasedontheaboveevaluation, itisconcluded thattheCoderequirement isimpractical.
Therefore, itisrecommended thatreliefbegrantedprovidedthat(a)visual(VT-3)examination oftheinternalsurfacesofthevalvesisperformed whenevertheinternalsurfacesaremadeaccessible duetodisassembly and(b)ifthevalveshavenotbeendisassembled, thisfactshouldbereportedbytheLicenseeintheISISummaryReportattheendoftheinterval.
17 lJf*P 3:1.7General(Noreliefrequests) 3.2Class2Comonents3.2.1PressureVessels(Noreliefrequests) 3.2.2~Piin3.2.2.1ReuestforReliefNo.15Examination CateorC-F-1andC-F-2ItemsC5.10andC5.50Class2PiinWeldsNOTE:RequestforReliefNo.15waswithdrawn bytheLicenseeintheJanuary16,1990submittal, whichstatesthefollowing:
"RequestforReliefNumber15isnotrequiredbytheCode.IntheClass2allocations tables,theweldsconcerning thisreliefareincludedinthetablesandintheprogramplantables.Sincethereliefrequestisnotrequiredtomeetthecode,thisreliefrequestwillbedeleted.Changestotheallocation tablesandintheprogramplantableswillbemadetoinsurecorrectaccountability."
3.2.2.2ReuestforReliefNo.16Part2of2Examination CateorC-CItemC3.20Class2PiinInterailWeldedAttachments NOTE:RequestforReliefNo.16waswithdrawn bytheLicenseeintheJanuary16,1990submittal, whichstatesthefollowing:
"ReliefRequestNumber16isnotrequiredbytheCode.Theassociated programplantableswillbecorrected andupdatedtoassureaccurateaccounting.
Thisactivitywillbeperformed toreflectthe"non-requirement" codestatussincetheassociated thicknesses are<5/8"forclass1and<3/4"forclass2.ReliefRequestNumber16isnotrequiredandwillbedeleted."
3.2.3~Pums(Noreliefrequests) 18 Iplvgt'kt
3.2.4Valves(Noreliefrequests) 3.2.5General(Noreliefrequests) 3.3Class3Comonents(Noreliefrequests) 3.4PressureTests3.4.1Class1SstemPressureTests(Noreliefrequests) 3.4.2Class2SstemPressureTests3.4.2.1ReuestforReliefNo.7SstemHdrostatic TestofThreeCharinPumsandDischarePiintoDischareIsolation ValvesintheChemistrandVolumeControlSstemCodeReuirement:
SectionXI,Par'agraph IWC-5222(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofChargingPumps1,2,and3andassociated discharge pipingtodischarge isolation valvesintheChemistry andVolumeControlSystemattherequiredpressureof3420psig.Licensee's ProosedAlternative Examination:
TheLicenseestatesthat,duringthehydrostatic testandassociated VT-219 fl,llcN visualexamination, thechargingpumpsandassociated discharge pipingtothefirstisolation valveswillbetestedatapressureof2400psig.Licensee's BasisforReuestinRelief:TheLicenseestatesthatthechargingpumpshaveahydrostatic testpressurelimitation onthesealsof2400psig,asspecified bythepumpmanufacturer.
Asaresult,thepumpsandassociated discharge pipingtothefirstisolation valvescannotbetestedtotherequiredCodetestpressure.
Evaluation:
Thepumpdesigndoesnotpermithydrostatic testingoftheCVCchargingpumpsandassociated discharge pipingtothefirstisolation valvesattheCode-required testpressurewithoutoverpressurizing thepumpseals.Therefore, theCode-required hydrostatic testpressureisimpractical toattain.TheLicensee's proposedalternative testatthereducedpressureof2400psigwillprovidereasonable assurance ofthecontinued inservice structural integrity.
==
Conclusions:==
Basedontheabove,itisconcluded thattheCode-required hydrostatic testisimpractical toperform.Therefore, itisrecommended thatreliefbegrantedasrequested.
3.4.2.2ReuestforReliefNo.8SstemHdrostatic TestofReactorCoolantSstemOverressureProtection NitroenAccumulator SstemValvesPCV430andPCV431CCodeReuirement:
SectionXI,Paragraph IWC-5222(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumber20 I'iO eofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafety'orreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofthereactorcoolantsystem(RCS)overpressure protection nitrogenaccumulator systemvalvesPCV430andPCV431Cattherequiredtestpressureof137.5psig.Licensee's ProosedAlternative Examination:
TheLicenseestatesthattheRCSoverpressure nitrogenaccumulator systemwillbetestedpertheCoderequirements uptotheflexconnection tothevalveoperator.
Inaddition, aninservice pressuretestatoperating pressurewillbeperformed onceeachinspection periodonthepiping,including thediaphragm.
Licensee's BasisforReouestin Relief:TheLicenseestatesthatthediaphragms inthesubjectvalveoperators areonlydesignedtowithstand amaximumpressureof105psigand,therefore, cannotbetestedtotherequiredCodetestpressure.
Evaluation:
Thesystem'sdesigndoesnotpermithydrostatic testingoftheRCSoverpressure protection nitrogenaccumulator systemvalvesPCV430andPCV431CattheCode-required testpressurewithoutoverpressurizing thediaphragms intheoperators ofthesevalves.Therefore; theCode-required hydrostatic testisimpractical toperform.Theinservice pressuretest,whichincludesthediaphragms, willprovide,reasonable assurance ofthecontinued inservice structural integrity.
21
==
Conclusions:==
Basedontheabove,Code-required hydrostatic testisTherefore, itisrecommended thatrequested.
itisconcluded thattheimpractical toperform.reliefbegrantedas3.4.2.3ReuestforReliefNo.9SstemHdrostatic TestoftheSecondarSideoftheSteamGenerator andAssociated MainSteam~Pl1IICodeReuirement:
SectionXI,Paragraph IWC-5222(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofthesecondary sideoftheSteamGenerator andassociated MainSteampipingattherequiredpressureof1356psig.Licensee's ProosedAlternative Examination:
TheLicenseestatesthatthesecondary sideoftheSteamGenerator andassociated HainSteampipingwillbetestedatapressureof1194psig,whichcorresponds to1.10timesthesystempressure.
Licensee's BasisforReuestinRelief:TheLicenseestatesthatapressuredifferential limitation of800psigbetweentheprimaryandsecondary sideoftheSteamGenerator hasbeenadopted.Thiswasestablished earlyinplantlifeduetothe22
~~
experiences ofsomeplantswithprimarysidetubesheet claddingseparation.
Tomaintainthis800psigdifferential andtherequiredpressureonthesecondary side,theprimarysystemmustbeheatedtoaminimumof160'Fwhichwouldresultinaproblemwithheatbalanceandapotential operational problemduringimplementation ofthetestprocedure.
Theadministrative controlsnecessary toensureaproperandsafetestandthecomplexity requiredforthetestprocedure resultinasituation thatshouldbeminimized.
InadditiontotheSectionXIvolumetric andsurfaceexamination requirements, thepipingispartoftheaugmented inspection programsinceitfallswithinthehighenergybreakcriteria.
TheLicensee's January16,1990submittal statesthefollowing:
"The800psidifferential pressurelimitation wasestablished earlyintheplantlifeofR.E.Ginna.Thislimitation wasinitiated afterseveralWestinghouse SteamGenerators withexplosively weldedtubesheet claddingexperienced primarysidetubesheet claddingseparation.
Thehydrostatic testcausestheSteamGenerator tubesheet todeflectduetoreverseloading(inthedirection oppositetonormaloperation).
Thepressurelimitation of800psiisanattempttolimittubesheet deflection andthepotential forcladdingfailure.Tomaintainan800psidifferential pressureacrossthetubesheet whileperforming aCodeacceptable hydrostatic testof1356psi(1.25x1085psi),therequiredprimarysystempressurewouldbe556psi(1356psi-800psi).During,theperiodoftimethatahydrostatic testandassociated examination wouldbeperformed, theplantisoperating withtheLowTemperature Overpressure Protection System(LTOP)setpointsineffect.TheLTOPsetpointsareusedtolimitprimarysystempressureto400psiorless.Inordertopressurize theprimarysystemto556psi(avaluegreaterthan400psi)theLTOPsetpointsmustbechangedtohighervaluesandadditionally thesteamgenerators arerequiredtobefunctional duetoprimarysystempressure.
Whenthesteamgenerators arefunctional, 23 IP'ggap safetyvalisesandlevelinstrumentation arealsorequiredtobefunctional.
Safetyvalvescannotbefunctional duringahydrostatic testduetogaggingrequirements andlevelinstrumentation cannotbefunctional sincethesteamgenerators arewatersolidandtherefore levelreadingswouldbeoffscale.LTOPsetpointsarechangedwhentheprimarysystemtemperature reaches350degreeF,thusthereisthepotential ofaTechnical Specification violation iftheprimarysystemispressurized to556psi.Technical Specification 3.1.1.2limitsthetubesheet differential temperature to100degreeFwhilethepotential foradifferential temperature of290degreeF(350deg.F-60deg.F)exists.Inordertoalleviate theseproblems, theSteamGenerator anddownstream piping,totheclassboundary, willbepressurized to1194psi(1.Ix1085psi)insteadof1356psi(1.25x1085psi).Thisactionwillminimizethepotential fortubesheet problemswhilefulfilling theintentofahydrostatic testtoinsuretheintegrity ofthepressureboundary.
Inadditiontotheabovetest,systempressuretestswillbeperformed eachperiodatsystemoperating pressureandtemperature toassuresystemintegrity.
Thesteamgenerator andassociated systemsarealsosubjected tovolumetric andsurface(SectionXI)examinations.
TheFeedwater andHainSteampipingisalsoincludedinanaugmented inservice inspection programtoprovideadditional assurances ofthesystemintegrity."
Evaluation:
Thesystem'sdesigndoesnotpermitpressurizing thesecondary sideoftheSteamGenerator andassociated HainSteampipingtotheCode-required testpressurewithoutthepotential ofcladdingfailureduetoreverseloading.Therefore, theCode-required hydrostatic testisimpractical toperform.Pressurizing thecomponents tothealternative testpressures willprovidereasonable assurance ofthecontinued inservice structural integrity.
==
Conclusions:==
Basedontheabove,itisconcluded thattheCode-required hydrostatic testofthesecondary sideoftheSteamGenerator andassociated HainSteampipingis24 impractical.
Therefore, itisrecommended thatreliefbegrantedasrequested.
3.4.2.4ReuestforReliefNo.'13SstemHdrostatic TestofNon-ISIClassified SstemsCodeReuirement:
SectionXI,Paragraph IWC-5222(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofthenon-ISIclassified systems,whichdonotcarryradioactive gasesorfluids,thatcontainlinespenetrating primarycontainment.
Reliefisrequested'for thefollowing lines:Penetration 120121121124124132202202203DescritionNitrogenFilltoSafetyInjection Accumulators; I-SI-903NitrogenSupplytoPressurizer ReliefTank;3/4-RC-151 ReactorNakeupWatertoPressurizer ReliefTank;2-RC-151PostAccidentTestPointContainment Atmosphere PostAccidentTestPointContainment Recirculating FilterandCoolingUnitCDischarge Containment Depressurization andMini-Purge ExhaustHydrogenSupplytoRecombiner 8HainBurnerHydrogenSupplytoRecombiner 8PilotBurnerPostAccidentTestPointContainment Atmosphere 25 (continued)
Penetration 203210301303304304305305305305305307309310310313317324332332332DescritionPostAccidentTestPointContainment Recirculation FilterandCoolingUnit'DDischarge Recombiner OxygenMakeuptoContainment HeatingSteamSupplytoContainment; 2-HS-150-4 HeatingSteamCondensate ReturnfromContainment HydrogenSupplytoRecombiner AMainBurnerHydrogenSupplytoRecombiner APilotBurnerPostAccidentTestPointContainment Atmosphere PostAccidentTestPointContainment Recirculating FilterandCoolingUnitADischarge PostAccidentTestPointContainment Recirculating FilterandCoolingUnitBDischarge Containment AirSampleInletContainment AirSampleOutletFireServiceWaterContainment Mini-Purge SupplyInstrument AirSupplytoContainment; 2-IA-125-8 ServiceAirSupplytoContainment Containment LeakrateTestConnection Depressurization Containment LeakrateTestConnection Supply;6-AT-150-4 Demineralized WaterHydrogenMonitorAInletHydrogenMonitor8InletHydrogenMonitorOutletLicensee's ProosedAlternative Examination:
TheLicenseeproposestotesttheselinesinaccordance with10CFR50AppendixJ,"ReactorCont'ainment LeakageTestingforWaterCooledPowerReactor,"
commensurate withthesafetyfunctionthelineperformsinaccordance withTechnical Specification, Surveillance requirements.
Additionally, atleastonceeachperiod,exposedportionsofthelinespenetrating primarycontainment willbeexaminedduringnormalsystemoperation, Licensee's BasisforReuestinRelief:TheLicenseestatesthatthesafetyfunctionoftheselinesistobecomepartofthecontainment isolation systemduringperiodswhencontainment isolation isrequired.
Therefore, thepressuretestingrequirements shouldbebasedonthecontainment systemdesignnottheassociated processsystemdesignrequirements.
26 lIIAl)>>
TheLicensee's January16,1990submittal statesthefollowing:
"DuetothevintageoftheR.E.GinnaPlant,thepipingwithinthesepenetration boundaries wasnotconstructed toClass2requirements, Regulatory Guide1.26doesnotrequirethesepenetrations tobeclassified as(jualityGroupBorClass2.However,Rochester GasandElectrichasoptionally classified theselinesClass2.Foroptionally classified piping,IWA-1320(e) allowstheOwnertheoptiontoapplytheSectionXIrules.Inthecaseoftheselines,Rochester Gas&Electrichasconcluded thatAppendixJtestingandaVT-2examination onceperperiodduringnormalsystemoperation willprovidetestingcommensurate withthesafetyfunction.
Inaddition, theselinesarenowsubjecttoASHESectionXIrulesforRepairsandReplacements."
Evaluation:
Althoughtheselineswerenotconstructed toClass2requirements, theLicenseehasnotshownthatthesystem'ssafetycriteriapermittheselinestobenonnuclear safetyclass.Therefore, paragraph IWA-1320(e) maynotbeapplicable.
Inaddition, AppendixJaddresses thestructural integrity oftheprimarycontainment, notthestructural integrity oftheCodeClass2processpipingforwhichreliefisbeingrequested.
Therequestforreliefdoesnotcontaininformation aboutthepressures involved.
TheproposedAppendixJtestpressuremaybemuchlowerthantheCode-required testpressure, inwhichcasetheinservice structural integrity wouldnotbeidentified.
Also,theproposedAppendixJtestdoesnotidentifythelocationofaleakifpresent.IConclusions:
Basedontheaboveevaluation, itisconcluded thattheLicenseehasnotjustified thedetermination ofimpracticality.
Therefore, itisrecommended thatreliefbedenied.27 0Ilt'~I~)
e3.4.3Class3SstemPressureTests3.4.3.1ReuestforReliefNo.6.SstemHdrostatic TestoftheRadioactive WasteHolduTankNOTE:RequestforReliefNo.6waswithdrawn bytheLicenseeintheJanuary16,1990submittal, whichstatesthefollowing:
"ThisrequestisspecifictotheCodehydrostatic testrequirements concerning thewastehold-uptank.Liquidwastefromvariouslocations intheplantincluding thereactorcoolantdraintank,chemicaldraintank,intermediate andauxiliary buildingsumps,floor,laundryandshowerdrainsaredivertedtothewastehold-uptank.Duringcoldshutdownandrefueling outages,thelevelinthistankvariesdepending ontheactivities performed duringanoutage.IfrequiredtoperformtheCodeexamination whenthetankisfull,thereisapossibility ofahazardous situation occurring.
Liquidwastecouldbedivertedtothewastehold-uptankwhileperforming therequiredCodestaticheadexamination.
Thisactioncouldresultinaliquidradioactive wastespillatoneofvariouslocations.
Itwastheintentofthisreliefrequesttopreventahazardous eventfromoccurring.
Uponreviewofyourinquiry,wehaveconcluded thatitispossibletoperformtherequiredexamination onthiscomponent.
Itwillrequiregreatercoordination withOperations andplantoutageactivities thanisnormallyexpected, butitcanbeperformed.
Therefore, ReliefRequestNumber6isnolongerrequired."
3.4.3.2RevestforReliefNo.10SstemHdrostatic TestoftheStandbAuxiliarFeedwater PumRecirculation LineCodeReuirement:
SectionXI,Paragraph IWD-5223(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems28 (orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic, testoftheStandbyAuxiliary Feedwater Pumprecirculation linebetweenvalvesAOV9710AandAOV97108andtheirassociated downstream floworifices.
Licensee's ProosedAlternative Examination:
TheLicenseestatesthattheClass3portionofthispipingshallbeVT-2examinedatoperational discharge pressureonceeachperiodduringfunctional testing.Licensee's BasisforReuestinRelief:TheLicenseestatesthat,inordertohydrostatically testthispipingtoSectionXIrequirements, thepressurereducingfloworificesdownstream ofvalveAOV9710AandBwouldrequireremovalandblankflangesinstalled.
Systempipingdoesnotprovideanisolation valvebetweentheorificesandtheCondensate SupplyTank.Asignificant reduction intanklevelwouldberequiredtofacilitate orificeremoval,whichisconsidered tobeimpractical.
Evaluation:
TheLicenseehasnotprovidedadequateinformation tojustifythedetermination ofimpracticality.
Information thatshouldbeaddressed includes(a)whytheLicenseeconsiders itimpractical tolowertheCondensate SupplyTankleveland(b)whetherornottheuseoffreezeplugshasbeenconsidered and,ifso,whyitwouldbeimpractical tousethem.Conclusions:
Basedontheabove,itisconcluded thattheLicenseehasnotdemonstrated thattheCode-required hydrostatic testisimpractical.
Therefore, itisrecommended thatreliefbedenied.29 3.4.3.3ReuestforReliefNo.11SstemHdrostatic TestoftheBoricAcidFilterandAssociated PiinintheChemicalandVolumeControlSstemNOTE:RequestforReliefNo.11waswithdrawn bytheLicenseeintheJanuary16,1990submittal, whichstatesthefollowing:
"Theflangegasketwas'reviewed withnewtechnical information thateliminated concernsoverthesafeworkingpressureoftheBoricAcidFilterhousingflangegasket.Uponreviewofyourinquiry,ithasbeenconcluded thattheHydrostatic testispossibleandwillbeincorporated intotheplan.Therefore, ReliefRequestNumber11isnolongerrequired."
3.4.3.4ReuestforReliefNo.12SstemHdrostatic TestofPortionsoftheEmerencDieselGeneration SstemCodeReuirement:
SectionXI,Paragraph IWD-5223(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licen'see's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofthefollowing portionsoftheEmergency DieselGeneration System:(a)StartingAir,including receivertanksandassociated piping,30 0\(Wl (b)FuelOilTransferpumps,suctionanddischarge lines,including miscellaneous linesterminating atoilstoragetanks,and(c)JacketCoolingWatersystem,including miscellaneous linesterminating atthecoolingwaterexpansion tanks.Licensee's ProosedAlternative Examination:
TheLicenseestatesthatinservice testingshallbeperformed ontheAirStartSystematleastonceeachperiodinaccordance withtherequirements ofSectionXI.Additionally, onceeachquarter,apressuredecaytestshallbeperformed ontheairreceivertoverifycheckvalveoperability inthereversedirection fortheairreceiverinletcheck.Systemfunctional testingshallbeperformed atleastonceeachperiodontheDieselFuelOilTransferandJacketCoolingWaterSystemsinaccordance withtherequirements ofSectionXI.Inadditiontothetestingdiscussed above,Technical Specification 6.4.1requiressurveillance testingtobeperformed onamonthlybasis,suchasverifying operability ofthefueloiltransferpumpsandthatthedieselstartsfromnormalstandbyconditions.
Licensee's BasisforReuestinRelief:TheLicenseestatesthatonlyportionsofthepipingassociated withthecomponents identified abovearecapableofbeingpressuretested.TheAirStartSystempressuretestwouldrequiretermination priortoreachingthee6gineskidtoprecludeadministrating airtotheAirStartMotors.ThiswouldleavethatportionofpipingbetweentheAirStartMotorstothefirstisolation, priortoreachingtheengineskid,untestable.
31 e1I TheDieselFuelOilTransfersystemwouldrequireflangeconnection disassembly andtheinstallation ofblindflangestoisolatetheDieselOilStorageTank,whichisventedtoatmosphere, andtheDayTankwherenomeansisprovidedtoisolatethetransferpumpdischarge pipingatapointclosetothedaytank.Additionally, theoverflowpipingfromthedaytanktothestoragetank,whichisidentified asClass3,hasnoisolation valvesinstalled andisventedtotheatmosphere.
Ouetoventstotheatmosphere, theJacketCoolingWaterSystemwouldrequireisolating theCoolingWaterExpansion Tank,including mostofthepipingsubjecttopressuretesting.DuetotheamountofpipingwithintheClassboundarywhichisunabletobepressurized, testinginaccordance withSectionXIrequirements wouldnotprovesystemintegrity overandabovetheexistingsurveillance Inservice andFunctional Testing.Evaluation:
Thesystem'sdesigndoesnotpermitpressurizing alloftheseClass3linestotheCode-required testpressure.
Therefore, theCode-required hydrostatic testpressurefortheunisolatable portionsofthispipingisimpractical toattain.Theproposedalternative testingwillprovidereasonable assurance ofthecontinued inservice structural integrity.
==
Conclusions:==
Basedontheabove,itisconcluded thattheCode-required hydrostatic testisimpractical.
Therefore, itisrecommended thatreliefbegrantedasrequested.
i3.4.3.5ReuestforReliefNo.14SstemHdrostatic TestofAllPressureRetaininComonentsWithintheClass3PortionoftheServiceWaterSstemCodeReuirement:
SectionXI,Paragraph IWD-5223(a) requiresthatthesystemhydrostatic testpressurebeatleast1.10timesthesystempressureforsystemswithDesignTemperature 32 of200'Forless,andatleast1.25timesthesystempressureforsystemswithDesignTemperature above200'F.Thesystempressureshallbethelowestpressuresettingamongthenumberofsafetyorreliefvalvesprovidedforoverpressure protection withintheboundaryofthesystemtobetested.Forsystems(orportionsofsystems)notprovidedwithsafetyorreliefvalves,thesystemdesignpressureshallbesubstituted forthesystempressure.
Licensee's CodeReliefReuest:Reliefisrequested fromperforming theCode-required hydrostatic testofallpressureretaining components withintheClass3portionoftheServiceWaterSystem.Licensee's ProosedAlternative Examination:
TheLicenseestatesthatpressureretaining components withintheoperational boundarywillreceiveaninservice testatoperating pressureandanassociated VT-2visualexamination eachperiodduringtheinterval.
Licensee's BasisforReuestinRelief:TheLicenseestatesthatthehydrostatic testrequirement fortheServiceWatersystemisimpractical duetosystemdesignwhichdictatestheuseofanopen-ended test.Theportionofthesystemdownstream oftheheatexchanger isalsoopen-ended andcannotbehydrostatically tested.Theremaining sectionofthesystemisonlyisolatable bymeansofbutterfly valveswhichwerenotdesignedtoprovidealeaktightboundary.
Withthesystemassuch,itwouldbeimpractical toexpectthattheleakages, otherthanatthevalves,couldbedetected.
Theamplemarginincoolingcapacityinherently providedbysystemdesigndoesnotdictatetheneedforanessentially leaktightboundary.
Sincethesystemisinconstantoperation, itsintegrity, iscontinually monitored.
Thoroughinspection ofthesystemeachperiodatthefulloperating pressureisadequate33 C\<Pl4 todetectanygrossfailuresinthesystemwithoutdegrading systemsafetyoravailability.
Evaluation:
TheCode-required hydrostatic pressuretestofisolatedportionsofClass3pipingassociated withtheServiceWaterSystemisimpractical toperformbecausethebutterfly valvesofthissystemareunabletosustainthepressurerequiredforthehydrostatic test.Withregardtotheopen-ended portionsoftheselines,paragraph IWD-5223(d) ofSectionXIshouldapply.Paragraph IWD-5223(d) statesthat,foropen-ended portionsofdischarge linesbeyondthelastshutoffvalveinnonclosed systems(e.g.,servicewatersystems),
confirmation ofadequateflowduringsystemoperation shallbeacceptable inlieuofsystemhydrostatic test.The.inservice testandtheconfirmation ofadequateflowduringsystemoperation willprovidereasonable assurance ofthecontinued inservice structural integrity.
==
Conclusions:==
Basedontheabove,itisconcluded thattherequiredhydrostatic testoftheseportionsofpipingisimpractical toperform.Therefore, itisrecommended thatreliefbegrantedasrequested.
3.4.4General(Noreliefrequests) 3.5General3.5.1Ultrasonic Examination Techniues(Noreliefrequests) 3.5.2ExemtedComonents(Noreliefrequests) 34 I~~3.5.3Other3.5.3.1ReuestforReliefNo.3UseofanAuthorized InsectionAenctoProvideInsectionServices'odeReuirement:
SectionXI,Paragraph IWA-1400(f) requiresanarrangement withanAuthorized Inspection Agencytoprovideinspection services.
Inaddition, theCoderequiresthatcertainadministrative functions beperformed bythe"Enforcement Authority" and"Authorized NuclearInservice Inspector."
Licensee's CodeReliefRevest:Reliefisrequested fromusingan"Authorized Inspection Agency"forISI.Licensee's ProosedAlternative Examination:
Recordsandreportsoftheinservice inspection willbedeveloped andmaintained byRochester GasandElectricandincludesuchitemsasexamination plansandschedules, examination results,andcorrective actions.Thefunctions oftheauthorized nuclearinservice inspector, namelytheirreviewandverification ofinservice examinations, personnel qualification, andequipment certification duringtheannualoutagesatGinnaNuclearPowerStationwillbeperformed bypersonnel oftheHartfordSteamBoilerInspection andInsurance Company.Thequalifications oftheinspectors, inspections specialists, andinspection agencyareincompliance withtheCode.Licensee's BasisforReuestinRelief:GinnaNuclearPowerStationislocatedintheStateofNewYork.TheLicenseestatesthatthisstatehasnotendorsedASHECodesand,therefore, doesnotprovideadministrative organization andcontrolssuchas"Enforcement Authority,"
"Authorized Nuclear35 rI4"J
~~Inservice Inspector,"
and"Reporting Systems."
However,GinnaStation's gualityAssurance Programdoesprovideequivalent administrative control.Therefore, theLicenseerequeststhatGinna'sStationgualityAssurance ProgrambeusedinlieuofCodeadministrative functions.
Rochester GasandElectric's programfortheinservice inspection, governedbytheR'.E.GinnaNuclearPowerStationgualityAssurance Manual,containstherequirements andresponsibilities forimplementation oftheprogramandprocedures.
Theprocedures havebeenpreparedandapprovedbytheresponsible organizations withinRochester GasandElectric(e.g.,GinnaStation,Engineering, Materials Engineering andinspection
- Services, ElectricHeterandLaboratory andPurchasing).
Approvedprocedures willbeimplemented tocontrolthestandards forexamination evaluation.
Theseprocedures includeidentifications oftheorganization performing theinspection, description ofthemethodofinspection tobeused,acceptance andrejection
- criteria, andrequirements forproviding evidenceofcompletion andcertification oftheinspection activity.
Inaddition, procedures aredeveloped byGinnaNuclearPowerStationtoprescribe thedisposition ofnonconformances.
Theprocedures implemented fortherepairs,theretestprocedures, andthetestresultswillbereviewedbythePlantOperating ReviewCommittee.
Membersofthiscommittee includetechnically qualified staffpersonnel.
Examination techniques havebeenestablished inaccordance withwrittenrequirements andincorporated intowrittenprocedures.
gualifications fornondestructive testpersonnel areincompliance withRegulatory Guide1.58,"gualification ofNuclearPowerPlantInspection, Examination andTestingPersonnel."
36 C.I4 Evaluation:
AlthoughtheStateofNewYorkdoesnotendorsetheASHECode,and,therefore, doesnotprovideadministrative organization andcontrolssuchas"Enforcement Authority,"
Authorized NuclearInservice Inspector,"
and"Reporting Systems,"
equivalent administrative controlisprovidedbytheGinnaNuclearPowerStationgualityAssurance Program.Personnel oftheHartfordSteamBoilerInspection andInsurance Companywillperformthefunctions oftheAuthorized NuclearInservice Inspector duringtheannualoutagesatGinnaNuclearPowerStation.TheHartfordSteamBoilerInspection andInsurance Companyhasbeendesignated theAuthorized NuclearInservice Inspector byotherstatesforothernuclearreactors.
Therefore, theintentoftheCodewillbemetbyusingtheGinnaNuclearPowerStationgualityAssurance PrograminlieuoftheCodeadministrative functions.
==
Conclusions:==
Basedontheabove,itisconcluded thattheintentoftheCodewillbemet.Therefore, itisrecommended thatreliefbegrantedasrequested.
37 e-~a~44~'
tt~P~l~4.CONCLUSION Pursuantto10CFR50.55a(g)(6),
ithasbeendetermined thatcertainSectionXIrequiredinservice examinations areimpractical toperform.Inallcasesforwhichreliefisrequested, exceptRequestforReliefNo.13,theLicenseehasdemonstrated thatspecificSectionXIrequirements areimpractical.
ForRequestforReliefNos.10and13,itisconcluded that:(a)theLicenseehasnotprovidedinformation tosupportthedetermination thattheCoderequirement isimpractical and(b)requiring theLicenseetocomplywiththeCoderequirement wouldnotresultinhardship.
RequestforReliefNos.6,11,15,and16werewithdrawn bytheLicenseeanddeletedfromtheISIProgramPlan.Thistechnical evaluation hasnotidentified anypractical methodbywhichtheLicenseecanmeetallthespecificinservice inspection requirements ofSectionXIoftheASHECodefortheexistingR.E.GinnaNuclearPowerStationfacility.
Requiring compliance withalltheexactSectionXIrequiredinspections wouldrequireredesignofasignificant numberofplantsystems,sufficient replacement components tobeobtained, installation ofthenewcomponents, andabaselineexamination ofthesecomponents.
Evenaftertheredesignef,orts,completecompliance withtheSectionXIexamination requirements probablycouldnotbeachieved.
Pursuantto10CFR50.55a(g)(6),
reliefisallowedfromtheserequirements whichareimpractical toimplement ifgrantingthereliefwillnotendangerlifeorpropertyorthecommondefenseandsecurityandisotherwise inthepublicinterestgivingdueconsideration totheburdenuponthelicenseethatcouldresultiftherequirements wereimposedonthefacility.
Therefore, itisconcluded thatthepublicinterestisnotservedbyimposingcertainprovisions ofSectionXIoftheASMECodethathavebeendetermined tobeimpractical.
IThedevelopment ofneworimprovedexamination techniques shouldcontinuetobemonitored.
Asimprovements intheseareasareachieved, theLicenseeshouldincorporate thesetechniques intheISIprogramplanexamination requirements.
38
~~"5asedonreviewoftheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection ProgramPlan,theLicensee's responsetotheNRCrequestforadditional information, andtherecommendations forgrantingrelieffromtheISIexamination requirements thathavebeendetermined tobeimpractical, itisconcluded thattheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection ProgramPlan,withtheexception ofRequestforReliefNos.10and13,isacceptable andincompliance with10CFR50.55a(g)(4).
39 4y~~i 5.REFERENCES 1.CodeofFederalRegulations, Volume10,Part50.2.AmericanSocietyofMechanical Engineers BoilerandPressureVesselCode,SectionXI,Division1,1986Edition.3.R.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection ProgramPlan,datedJuly21,1989.4.NUREG-0800, StandardReviewPlans,Section5.2.4,"ReactorCoolantBoundaryInservice Inspection andTesting,"
andSection6.6,"Inservice Inspection ofClass2and3Components,"
July1981.5.Letter,datedNovember16,1989,A.R.Johnson(NRC)toR.C.Mecredy[Rochester GasandElectricCorporation (RGE)],requestforadditional information.
6.Letter,datedJanuary16,1990,R.C.Mecredy(RGE)toA.R.Johnson(NRC),responsetotheNRCrequestforadditional information.
7.NRCRegulatory Guide1.14,"ReactorCoolantPumpFlywheelIntegrity,"
Revision1,August1975.8.NRCRegulatory Guide1.150,"Ultrasonic TestingofReactorVesselWeldsDuringPreservice andInservice Examinations,"
Revision1,February1983.40 44e~l44N NPQcCAAI33S'39r~CLI~192,Cr'0I'~iQ'~Lc,,g2.TITI.EANDSUBTIT'U.S.NUCLEARREGULATORY CSIONBIBL!OGRAPHIC DATASHEETlScotntttvctytng ontnpioycrgolPPRTNI"'Aanincd oyIIIIC.Addvot.,Evoo.,Rty.,oldAdocntgtm ttvtntttti.
IItny,IEGG-HS-8923 Technical Evaluation ReportontheThird10-YearIntervalInservice Inspection ProgramPlan:Rochester GasandElectricCorporation, R.E.GinnaNuclearPowerStation,DocketNumber50-2445.AUTHORISI B.W.Brown,J.D.Hudlin3.DATEREPORTPUBLISHED AprilI1995tLFINORGRANTNUMBERFIN-D6022 (Proj.5)6.TYPEOFREPORTTechnical 7.PERIODCOVEREDttnctonrr Octal6,PERFORMING ORGANIZATION NAMEANDADDRESSlllhlnCptoyiorOiytoon.Ottcrorltrpion, ItS.itoctcgrgtrpvtctory Convnntt'oncndmgttinpcootcth'itcontrgctor protntcnottonnctmotlinpoddtycclEGLGIdaho,IncP.0.Box1625IdahoFalls,ID83415-2209 9.SPONSORING ORGANIZATION NAMEANOADDRESStttgtnC,typo~cgphotoliTcontrcctor gnoygctotgnCDitnron,Orthoorgtcp>>n.IlS.hhrcgtcrntptttgtory Commtction.
nnttmctlnpottdtctcl Haterials andChemicalEngineering BranchOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.2055510.SUPPLEMENTARY NOTES11.ABSTRACTQEOytorotoritalThisreportpresentstheresultsoftheevaluation oftheR.E.GinnaNuclearPowerStationThird10-YearIntervalInservice Inspection (ISI)ProgramPlan,submitted July21,1989,including therequestsforrelieffromtheAmericanSocietyofHechanical Engineers (ASHE)BoilerandPressureVesselCodeSectionXIrequirements whichtheLicenseehasdetermined tobeimpractical; TheR:E.GinnaNuclearPowerStationThird10-YearIntervalISIProgramPlanisevaluated inSection2ofthisreport.TheISIProgramPlanisevaluated for(a)compliance withtheappropriate edition/addenda ofSectionXI,(b)acceptability ofexamination sample,(c)correctness oftheapplication ofsystemor-component examination exclusion
- criteria, and(d)compliance withISI-related commitments identified duringpreviousNuclearRegulatory Commission (NRC)reviews.Therequestsforreliefareevaluated inSection3ofthisreport.12.KEYWORDS/OESCRIPTORS ILiawordyorpnrgtcttnawiucatttrttrgrcntrt iniocgnnptncnoon,l13.AVAILASILITY STATEMEtITUnlimited 14.$ECUIIITYCLASSIFICATION IThltpettiUnclassified IThnntporttUnclassified
'I5.NUhl6ER0FPAG6S16.PRICEFIRCFORM335I249I s~~'V