ML17265A765
| ML17265A765 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/08/1999 |
| From: | MECREDY R C ROCHESTER GAS & ELECTRIC CORP. |
| To: | VISSING G S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9910210041 | |
| Download: ML17265A765 (55) | |
Text
CATEGORY14'PREGULA'IHRY INFORMATION DXSTRIBUTIO YSTEM(RIDS)ACCESSION NBR:9910210041 DOC.DATE:
99/10/08NOTARIZED:
NODOCKETFACXL:%0-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244ASH.NAMEAUTHORAFFILIATION
'MECRhD'Y,R.C.
Rochester Gas6ElectricCorp.WECXP.NAME RECIPIENT AFFILIATION VISSXNG,G.S.
SUBJECT:
Forwardsfifteenreliefrequeststhatwillbeutilizedfor.GinnaNPPfourthintervalISIprogramthatwillstartonJan1,2000.Attachment 1includessummaries 6detaileddescription ofeachreliefrequest.ADISTRIBUTION CODE:A047DCOPIESRECEIVED:LTR lENCL$SIZE:5~TTITLE:ORSubmittal:
Inservice/Testing/Relief fromASMECodeENOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
050002446RECIPIENT IDCODE/NAME LITTLE,SINTERNAL:~EXLE=CENXER, 03.~OGC/RPRES/DET/MEB COPIESLTTRENCL11111011RECIPIENT IDCODE/NAME VXSSXNG,G NUDOCS-ABSTRACT RES/DET/ERAB COPIESLTTRENCL111111EXTERNAL:
LITCOANDERSONNRCPDR1111NOAC11D'ENOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTETHTOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROF.COPIESREQUIRED:
LTTR10ENCL' AHDASubsiChory ofRGSEnergyGroup,Inc.ROCHESTER GASANDELECTRICCORPORATION
~89EASTAVENUE,ROCHESTER, N.Y.W6d9400l~7I65rf6-2700 wwwrge.cornRO8ERTC.MECREDYVicepresident NvdeerOperohons October8,1999U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate IWashington, D.C.20555
Subject:
GinnaNuclearPowerPlantInservice Inspection ASMESectionXIRequiredExaminations, ReliefRequestsR.E.GinnaNuclearPowerPlantDocketNo.50-244
DearMr.Vissing:
Thepurposeofthisletteristosubmitfifteen(15)ReliefRequeststhatwillbeutilizedforourFourthIntervalISIProgramthatwillstartonJanuary1,2000.EnclosedasAttachment 1isasummaryofourReliefRequestsaswellasadetaileddescription ofeachindividual reliefrequest.Table1identifies eachreliefrequest,thesubjectofeachrelief,andidentifies thereference paragraph of10CFR50.55adealingwiththetypeofreliefthatisbeingrequested.
Thefirst13individual reliefrequestscontained withinthebodyofAttachment 1arevirtually identical tothoseapprovedforuseduringourThirdIntervalProgram(minordifferences areexplained inTable1ofAttachment 1).Acrossreference totheThirdIntervalReliefRequestisidentified onthetopofeachcurrentproposed'eliefrequestforyourconvenience.
ReliefRequests14and15areidentical toReliefRequests42and43,recentlysubmitted forourThirdIntervalISIprogram.ItshouldbenotedthatourFourthIntervalISIProgramhasbeendeveloped toASMESectionXI,1995Edition,1996Addenda,asdescribed inourAugust26,1999submittal ofproposedReliefRequest35.RG&Ewillalsoimplement theEPRIPerformance Demonstration Initiative (PDI)toimplement mandatory AppendixVIII,consistent with10CFR50.55a(b)(2)(xv) ofthefinal10CFR50.55aRuleeffective November22,1999.Furthermore, forASMESectionXIrepairsandreplacements, ASMESectionIIICode,1995Edition,1996Addendashallbeusedasapplicable.
Finally,wewillbemaintaining thecurrentrequirements forIWEandIWL,whichwillbeASMESectionXI,1992Edition,1992Addenda.Thisistheexistingcodeofrecordper10CFR50.55a.Verylyyours,99i02i004i 99i008lPDRADOCK05000244I 8PDR'I~iRobertC.MecredyPDtI7 Attachment xc:Mr.GuyS.Vissing(MailStop8C2)ProjectDirectorate IDivisionofLicensing ProjectManagement OfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555RegionalAdministrator, RegionIU.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector
/r~s/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page1of48TABLE1SUMMARYOFRELIEFREQUESTSRELIEF10CFRREQUESTRELIEFNUMBERREFERENCE 50.55a(a)(3)(ii)50.55a(a)(3)(ii)RELIEFREUESTSUBJECTDeferRPVExaminations toEndofInterval.
VisualInternalExamination ofClass1valves50.55a(g)(5)(iii)
CategoryB-J.CastStainless BaseMetalUltrasonic Examination.
50.55a(a)(3)(ii)Regenerative HeatExchanger (RHE),Class1Examinations, (Note:Thereference toItemNumberB3.160perthe3IntervalReliefRequestNumber18-1hasbeenmovedtoReliefRequest6below.)50.55a(a)(3)(ii)
Alloy690WeldMaterial, Fabrication ofNewSteamGenerators.
50.55a(g)(5)(iii)
Regenerative HeatExchanger (RHE),InnerRadiusExaminations.
50.55a(g)(5)(iii)
Component SupportIntegralAttachment Examination Limitations.
50.55a(g)(5)(iii)
SurfaceExamination limitations associated withweldexaminations ofidentified Class1safeendnozzlesassociated withtheReactorPressureVessel.(Note:ReflectsSurfaceExamination percentage actuallyachievedduringthe1999OutageExamination,)
1050.55a(a)(3)(ii)50.55a(a)(3)(ii)VisualExamination ofmetalcontainment seals&gaskets.Successive Examinations torepairedareas.991021004>
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page2of48TABLE1SUMMARYOF<RELIEFREQUE<STS RELIEF10CFRREQUESTRELIEFNUMBERREFERENCE RELIEFREUESTSUBJECT50.55a(a)(3)(ii)
Bolttorqueortensiontestforboltedconnections.
1250.55a(a)(3)(i)
VT-2VisualExamination following repair,replacement, ormodification.
1350.55a(a)(3)(ii)
Minimumillumination andmaximumdirectexamination distanceofClassCCcomponents.
1450.55a(g)(5)(iii)
ReactorPressureVessel(RPV)WeldExamination Limitations.
1550.55a(g)(5)(iii)
ResidualHeatRemoval(RHR)HeatExchanger OutletNozzleWeldExamination Limitation.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page3of48RELIEFREQUESTNO.1(Waspreviously approvedasReliefRequestNo.1forThirdInterval)
DEFERRPVEXAMINATIONS TOENDOFINTERVALI.Sstem/ComonentforWhichReliefisRuested:Reliefisrequested fortheReactorPressureVessel(RPV)Shell-to-Flange andHead-to-FlangeWelds.IICodeReuirementASMESectionXI,1995Edition1996Addenda,CategoryB-A,ItemNumbersB1.30andB1.40.III.CodeRuirementfromWhichReliefisRuested:TableIWB-2500-1, Examination CategoryB-A,ItemNumberB1.30,requiresthattheRPVShell-to-Flange weldbeexaminedduringthefirstandthirdperiodsinconjunction withthenozzleexaminations, withatleast50percentexaminedduringthefirstperiodandtheremainder bytheendofthethirdperiod.TherequiredShell-to-Flange examination isimpractical ifperformed duringtheperiodsspecified asitcanonlybeaccomplished fromtheflangesurface.Whenperforming thisweldexamination fromtheVesselinsidesurface,qualified UTtechniques canbeutilizedtoperformamorereliableexamination withgreaterexamination coverageasdemonstrated duringour199910-YearVesselexamination.
TableIWB-2500-1, Examination CategoryB-A,ItemNumberB1.40,requiresthattheRPVHead-to-Flange weldbeexaminedfromtheflangefaceonlyduringthefirstandsecondperiods,providedthatthesesameportionsateexaminedfromtheheadduringthethirdperiod.IV.BasisforRelief:TheReactorPressureVesselisamajorsourceofradiation exposureaccumulated duringanormalrefueling outageInservice inspection.
Byperforming theaboveCategoryandItemexaminations attheendoftheintervaltherewillbenosacrifice inthequantitynorqualityofexaminations but,therewillbeasubstantial reduction inradiation exposure.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page4of48RELIEFREQUESTNO.1(Con't)V.Alternate Examinations:
R.E.GinnaNuclearPowerPlantproposesthattheexaminations identified abovebeperformed fromboththeflangesurfaceandthevesselwallatorneartheendofinterval.
VI.Justification forGrantinofReliefDuringthefirstthreeinspections intervals, 100percentoftheaccessible lengthoftheRPVweldsincluding theShell-to-Flange weldswereexaminedatorneartheendoftheintervalwhentheentireexamination couldbeperformed fromboththeflangesurfaceandthevesselwall.Thisisamorepractical approachinthattherequiredexaminations frombothsurfacescanbeperformed atthesametime.Duringthefourthinterval, 100percentoftheaccessible lengthofallRPVweldsincluding theshell-to-flange andhead-to-flange weldswillbeperformed atorneartheendoftheintervalwhenalltherequiredexaminations canbeperformed atthesametime.Also,Class1Leakageexaminations areperformed eachoutagetoensuresystem/component integrity.
VII.Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
I'>vs/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision'0 Page5of48RELIEFREQUESTNO.2VISUALINTERNALEXAMINATION OFCLASS1VALVES(Waspreviously approvedasReliefRequestNo.5forThirdInterval)
Sstem/ComonentsforWhichReliefisReuested:Class1valvesrequiring valvebodyinternalVTexamination.
10101010101010106666ValveNo.842A842B867A867B700701720721853A853B852A852B~F1~/TgeDarling/Check Darling/Check Darling/Check Darling/Check Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Check Velan/Check Velan/Gate Velan/Gate LineNo.IOA-SI2-1502-A 10A-SI2-2501-B IOA-SI2-2501-A IOA-SI2-2501-B IOA-RC02501-A IOA-RCO-2501-A IOA-RCO-2501-B 10A-RCO-2501-B 6A-RC-2501-A 6A-RC-2501-B 6A-RC-2501-A 6A-RC-2501-B CodeReuirements:
ASMESectionXI,1995Edition1996Addenda,CategoryB-M-2,ItemNumberB12.50.CodeReuirementfromWhichReliefisRuestedTableIWB-2500-1, Examination CategoryB-M-2ItemB12.50,requiresaninternalVT-3examination onatleastonevalvewithineachgroupofvalvesthatareofthesamesize,constructional design(suchasglobe,gateorcheckvalves)andmanufacturing method,thatperformsimilarfunctions inthesystem.Thisreliefrequestisbasedonthefollowing points:Tocompletethesubjectexamination, unnecessary expenditures ofman-hours andmanremarerequiredwithessentially nocompensating increaseinplantsafety,and2.Thestructural integrity affordedbyvalvecasingmaterialutilizedwillnotsignificantly degradeoverthelifetimeofthevalve.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page6of48III(Con't)RELIEFREQUESTNO.2(Con't)BasedondatacompiledfromaplantsimilarinageanddesigntoGinnaStation,itisexpectedthatapproximately 100man-hours and5-manremexposurewouldberequiredtodisassemble, inspect,andreassemble thesevalves.Performing thisvisualexamination undersuchadverseconditions, highdosesrate(30-40R/hr),andpoor+as-castsurfaceconditions, realistically provideslittleadditional information astothevalve'scasingintegrity.
Thevalves'aterial, ahigh-strength caststainless steel(ASTMA351-CF8),
iswidelyusedinthenuclearindustryandhasperformed extremely well.Thepresenceofsomedeltaferrite(typically 5%ormore)substantially increases resistance tointergranular stresscorrosion cracking.
Thedeltaferritealsohelpsthematerialtoresistpittingandcorrosion inchloridecontaining environments.
BasisforRelief:RG&Efeelsthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatthepublic'shealthandsafetywillnotbeadversely affectedbynotperforming avisualexamination ofthevalveinternalpressureboundarysurfaces.
Additionally, thisvisualexamination addslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonnel tounnecessary radiation exposure.
Therefore, arequestforrelieffromthisrequirement issought.AVT-3examination shallbeperformed onceononevalvewithinthevalvegroupduringtheIntervalifdisassembled formaintenance.
V.ProosedAlternative Examinations:
AsstatedaboveRGAEdoesnotbelievethatthevisualexamination requiredeachten-yearintervaliswarranted.
However,asstandardmaintenance practicedictates, whenthesevalvesaredisassembled formaintenance
- purposes, avisualexamination oftheinternals andinternalpressureboundarysurfaceswillbeperformed, totheextentpractical.
VI.Justification forGrantinofRelief:RGB'eelsthatadequatesafetymarginsareinherentinthebasicvalvedesignandthatthepublic'shealthandsafetywillnotbeadversely affectedbynotperforming avisualexamination ofthevalveinternalpressureboundarysurfaces.
Additionally, thisvisualexamination addslittleornovaluetotheoverallsafetyoftheplantandsubjectsplantpersonnel tounnecessary radiation exposure.
Also,Class1Leakageexaminations areperformed eachoutagetoensuresystem/component integrity.
iIANbFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page7of48RELIEFREQUESTNO.2(Con't)Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page8of48RELIEFRE<QUESTNO.3(Waspreviously approvedasReliefRequestno.17forThirdInterval)
CATEGORYB-J,CASTSTAINLE<SS BASEMETALULTRASONIC EXAMINATION ComonentsforWhichReliefisReuested:Class1,CategoryB-JItemB9.11,ReactorCoolantCastPumpTerminalEndtoCastElbowCircumferential WeldsWeldIDPL-FW-XIII PL-FW-XVElbow-to-Pump Elbow-to-Pump
~%Coverae45%50%CodeReuirements:
ASMESectionXI,1995Edition,1996Addenda,CategoryB-J,ItemNumberB9.11.CodeReuirements fromWhichReliefisReuestedCategoryB-JwithinTableIWB-2500-1, specifies volumetric examination requirements thataretobeperformed onweldsatTerminalEnds,aswellasothercircumferential weldsassociated inthesystem.2.CodeCaseN-460specifies thatareduction inexamination coverageonanyClass1orClass2weldmaybeacceptedprovidedthereduction incoverageforthatweldislessthan10%.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page9of48RELIEFREQUE~STNO.3(Con't)BasisforRelief:Supplement 4(b)(4)ofAppendixIIIidentifies ultrasonic scanningrequirements onAustenitic andDissimilar MetalWelds.Thisparagraph furtheridentifies thatCastitemssuchasfittings, valvebodies,andpumpcasingsmayprecludemeaningful examinations becauseofgeometryandattenuation variables.
AtR.E.GinnaNuclearPowerPlant,theReactorCoolantPump,Westinghouse Model93,iscaststainless (A-351GrCF8M).Theassociated fittings(elbows)arealsocaststainless (ASTMA-351GrCF8M)andcontainslongitudinal seamwelds.TheReactorCoolantInlet/Outlet WroughtSafeEnd/PipetoElbowcircumferential weldsconsistoffittings(elbows)thatarecaststainless (ASTMA-351GrCF8M).Whenemploying optimized ultrasonic technique onthesecast/wrought welds,thetechniques maydetectlargeflaws(25%orgreaterthroughwall).Therefore, thesensitivity islessthanthatrequiredbytheCode.CastStainless basemetalandassociated weldscontainlargegrainstructures, attenuation variables impacttheperformance ofultrasonic examinations.
Experience hasshownthatthesematerials arenotalwaysamenabletoultrasonic examination anddoesnotproducereliableandmeaningful results.Currently, theindustry's Performance Demonstration Initiative (PDI)isnotaddressing Cast"Stainless Ultrasonic Examinations.
Duetothehighlyattenuative characteristics oftheaustenitic grainstructure, ultrasonic examination coveragetotheextentthatisspecified withinCodeCaseN-460maynotalwaysbeachievable.
Radiography, ifapplied,isnotexpectedtoprovideanymeaningful increaseinbenefitbeyondthealternative presented duetothehighlevelsofbackground radiation emittingfromtheseareas,significantly decreasing thesignal(imagetonoiseratio)oftheradiograph.
,/AVkFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page10of48RELIEFREQUESTNO.3(Con't)Alternate Examinations:
None.Applicable Code-required volumetric examination (UT)willbecompleted tothemaximumextentpractical (abesteffortexamination ofthecaststainless weldsbasedonstate-of-the-art techniques andassociated achievable examination coverage).
Wewillcontinuetoevaluatenewemerginginspection technology astheybecomeavailable.
TheCoderequiredsurfaceexaminations andsystemleakagetestswillbeperformed.
Justification forGrantinofRelief:Volumetric examination oncastAustenitic andDissimilar Metalweldsmayprecludemeaningful examinations becauseofgeometryandattenuation variables.
Duetothehighlyattenuative characteristics oftheAustenitic grainstructure, ultrasonic examination coveragetotheextentthatisspecified withinCodeCaseN-460maynotalwaysbeachievable.
Radiography, ifapplied,isnotexpectedtoprovideanymeaningful increaseinbenefitduetothehighlevelsofbackground radiation emittingfromtheseareas.Volumetric examination ofthecaststainless weldsbasedonstate-of-the-art techniques andassociated achievable examination coverageshallbeperformed.
Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
IAVOFOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page11of¹8RELIEFREQUESTNO.4(Waspreviously approvedasReliefRequestno.18-1forThirdInterval)
REGENERATIVE HEATEXCHANGER (RHE),CLASS1EXAMINATIONS Sstem/ComonentforWhichReliefisReuested:ChemicalandVolumeControlSystem;Regenerative HeatExchanger (RHE),Class1portion.CodeReuirements:
ASMESectionXI,1995Edition,1996Addenda,CategoryB-B,ItemNumbersB2.60,B2.80,andCategoryB-D,ItemNumbersB3.150CodeReuirements fromWhichReliefisReuested:Inaccordance withTableIWB-2500-1, thefollowing Categories andItemNumbersrequirevolumetric examination.
CategoOItemNumberB-BB-BB-DB2.60B2.80B3.150Tubesheet-to-Head WeldsTubesheet-to-Shell WeldsNozzle-to-Vessel WeldsBasis:TheRegenerative HeatExchanger (RHE)consistsofthree(3)shellandtubeheatexchangers connected inseries.TheRHEisdesignedtorecoverheatfromthereactorcoolantsystemletdownstreamduringnormaloperation.
Theletdownstreamflowsthroughtheshellsideoftheheatexchanger.
TheshellsideoftheRHEisClass1whilethetubesideisClass2.TheRegenerative HeatExchanger providesthemajorsinglesourceofradiation exposureaccumulated duringanormalrefueling outageInservice inspection.
Byperforming theaboveCategoryandItemnumberexaminations ononeofthethreeheatexchangers seeingthemostextremeconditions willprovidearepresentative sample,whilelimitingpersonnel radiation exposure.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page12of48IV(Con't)RELIEFREQUESTNO.4(Con't)FortheaboveCategories
&ItemNumbers,thebottomheatexchanger shouldbetheoneheatexchanger selectedsinceitoperatesatthehighesttemperature ofalltheunitsandistherefore themosthighlystressed.
Typicaloperating temperatures forletdownflowisaround544Deg.F.andbetween300-350Deg.F.outofthetopshell.Bylimitingtheexaminations tooneheatexchanger willsignificantly reduceradiation exposuretopersonnel.
TheexposuresavingstoISIrelatedpersonnel perinspection intervalwouldbe19.6Man-RemWholeBodyand68.0Man-RemExtremities throughthereduction of10examinations.
V.Alternate Examinations:
Rochester Gas&Electric(RG&E)proposestoutilizethe"multiple stream"conceptwhenperforming avolumetric examination ofaccessible portionsofNozzle-to-VesselWeldsandNozzleInsideRadiusWeldsequivalent tooneofthethreeidentical sectionsontheClass1Regenerative HeatExchanger.
Examinations shallbeperformed onthelowersection.Theassociated examinations shallbeperformed onceduringtheinterval.
Inaddition, RG&EproposestoperformaVT-2visualexamination ontheentireRegenerative HeatExchanger duringsystemleakagetests.VI.Justification forGrantinRelief:TheRHEconsistofthree(3)shellandtubeheatexchangers connected inseries.Thebottomheatexchanger operatesatahighertemperature ofalltheunitsandisthemosthighlystressed.
Bylimitingtheexaminations tooneheatexchanger willsignificantly reduceradiation exposuretopersonnel.
VII.Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page13of48RELIEFREQUESTNO.5(Waspreviously approvedasReliefRequestNo.27forThirdInterval)
ALLOY690WELDMATERIAL, FABRICATION OFNEWSTEAMGENERATORS Sstem/ComonentsforWhichReliefisReuested:Fortheincorporation ofCodeCases2142and2143intotheASMESectionXIProgram.TheseCasesallowtheuseofAlloy690weldmaterial, CodeReuirements:
ASMESectionXI,1995Editionwith1996Addenda,IWA-4224Requirements.
ASMEReuirements fromwhichReliefisReuested:Reliefisrequested fromtherequirements specified inIWA-4224ofthe1995Edition,with1996AddendaoftheASMESectionXICode.IWA-4224.3 UseofaDifferent Material(a)Useofmaterials ofaspecification, grade,type,class,oralloy,andheat-treated condition, otherthanthatoriginally specified, shallbeevaluated forsuitability forthespecified designandoperating conditions inaccordance withIWA-4311.
(b)Materialexamination andtestingrequirements shallbereconciled totheConstruction Coderequirements ofthecomponent.
BasisforRelief:TheuseofAlloy690typeweldfillermaterialisrequiredforthereplacement steamgenerators.
Thesematerials havebeenapprovedbyASMEthroughCodeCases2142and2143andaredesignated asUNSN06052andUNSW86152,respectively, andclassified themasF-No.43forweldprocedure andperformance qualification purposesinaccordance withASMESectionXI.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page14of48RELIEFREQUESTNO.5(Con't)IV(Con't)UNSW86152istheshieldedmetalarcweldingelectrode forAlloy690andUNSN06052isthebarefillermetal.Bothmaterials havebeenshowninnumerousEPRIstudiestohaveimprovedcorrosion resistance forAlloy690weldments ascomparedtothecurrently usedNi-Cr-Fe(N06082 andW86182)materials.
Thenewweldmaterials arethepreferred choiceforweldingapplications involving Alloy690inacorrosion environment andtheyprovideanacceptable levelofqualityandsafetybecauseoftheirsuperiorcorrosion resistant properties.
V.Alternate Examinations:
Incorporate ASME,Boiler8cPressureVesselCodeCase2142,"F-Number GroupingforNi-Cr-Fe, Classification UNSN06052FillerMetal",andCase2143,"F-Number GroupingforNi-Cr-Fe, Classification UNSW86152WeldingElectrode".
Justification forGrantinofRelief:BothUNSW86152andUNSN06052materials havebeenshowninnumerousEPRIstudiestohaveimprovedcorrosion resistance forAlloy690weldments ascomparedtothecurrently usedNi-Cr-Fe(N06082andN86182)materials.
Thenewweldmaterials arethepreferred choiceforweldingapplications involving Alloy690thatwasutilizedinFabricating thenewSteamGenerators.
VH.Imlementation Schedule:
Utilization ofthesematerials maybeusedduringtheFourthIntervalifandwhenneeded.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page15of48RELIEFREQUESTNO.6(Waspreviously approvedasReliefRequestno.32forThirdInterval)
REGENERATIVE HEATEXCHANGER (RHE),INNERRADIUSEXAMINATIONS Sstem/ComonentsforWhichReliefisRuested:ChemicalandVolumeControlSystem;Regenerative HeatExchanger (RHE),Class1InnerRadiusExaminations; RHE-NlRHE-N5CodeReuirements:
ASMESectionXI,1995Editionwith1996Addenda,CategoryB-D,ItemNumberB3.160.CodeReuirements fromWhichReliefisRuested:Inaccordance withTableIWB-2500-1, Examination CategoryB-D,ItemNumberB3.160.BasisforRelief:TheRegenerative HeatExchanger (RHE)consistsofthree(3)shellandtubeheatexchangers connected inseries.TheRHEisdesignedtorecoverheatfromthereactorcoolantsystemletdownstreamduringnormaloperation.
Theletdownstreamflowsthroughtheshellsideoftheheatexchanger.
TheshellsideoftheRHEisClass1whilethetubesideisClass2.TheRHEprovidesthemajorsinglesourceofradiation exposureaccumulated duringanormalrefueling outageInservice inspection.
InnerRadiusexaminations werescheduled tobeperformed ontheClass1sideofthebottomheatexchanger thatexperience themostextremeconditions asspecified withinReliefRequest¹4.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page16of48RELIEFREQUESTNO.6(Con't)IV(Con't)TheRHEinnerradiusexaminations weretobeperformed onsmallheavywallnozzlesthatareconnected to2"piping.Anin-depthinvestigation wasinitiated byRGBtodetermine thefeasibility ofperforming anacceptable Codeexamination.
Theinitialinvestigation reviewedthenozzletype,weldplacement andactualODweldprofilesaswellasultrasonic measurements toverifyIDconfiguration.
Toassistintheevaluation ofperforming anacceptable Codeultrasonic innerradiusexamination, ComputerModelingandmockupsofthenozzletovesselconfiguration wereinitiated.
Computermodelingwasperformed bySouthwest ResearchInstitute, AEATechnology, andEPRI.Computermodelingperformed bythevariousorganizations comparedfavorably.
Thecomputermodelinginitiative indicated severaldifferent transducers wouldberequiredtobeusedandtheinnerradiusexamination resultswouldbequestionable atbestduetothesizeandconfiguration ofthenozzles.Themodelingalsoindicated beamspreadandmodeconversion atthenotchesandneighboring surfaceswouldseriously reducethesignaltonoiseratios,causingconfusing spurioussignals.Baseduponthecomputermodelingresults,EPRINDECenterpersonnel wereutilizedtoperformactualhandsoninnerradiusexamination evaluation onthemockups.Anareawasselectedontwomockupsofthenozzle,suitabletransducers andwedgeswereselectedtoperformtheexamination.
Theinspection wastobeperformed fromthebossregionofthenozzlebecauseinspection fromtheshellsurfaceprovedtobegreatlyaffectedbyattenuation andscattering fromthenozzle-to-shell weldmaterial.
Avarietyofinspection frequencies wereattempted ofwhichnoneprovidedwhatwouldbeconsidered successful forthedetection ofthenotchesonthesenozzles.Itshouldbenotedthatthetransducer positionfordetecting theselectednotchwasnearlyoptimum.Sincetheattemptsmadewereunsuccessful itwasdecidedtoincreasethedepthofthenotchfrom10%to30%.Thisincreaseofthenotchisgreaterthancodeallowable.
Attemptsweremadeonthegreaternotchdepthbutdetection wasnotachievable.
V.Alternate Examinations:
None,RG&Ewillcontinuetoevaluatenewemerginginspection technology astheybecomeavailable.
TheCoderequiredleakagetestswithassociated VT-2examinations shallbeperformed.
I8Nk//FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page17of48RELIEFREQUESTNO.6(Con't)VI.Justification forGrantinofRelief:Ithasbeenproventhatanacceptable Codeexamination oftheRHEnozzleinnerradiusregionisnotpossibleutilizing currenttechnology.
Itdemonstrates thatsignalsfromdifferent depthnotcheslocatedinthemostoptimumpositionofthemock-upcouldnotbedifferentiated fromnoiseandgeometric reflectors withouttheaidoffingerdampingontheIDsurface.Theevaluations havealsoshownthatthelimitation inthebossarea,inthe0and180degreeposition, alongwiththetransition totheseareas,limitsthesizeoftransducers thatcanbeemployedandwherethetransducers canbeplaced.VII.Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
References:
EPRIReportTitle"Evaluation ofUltrasonic Examination Technology forInspection ofRegenerative HeatExchanger NozzlesattheRochester Gas&Electric, GinnaNuclearPlant"Dated17April1996byDouglasE.MacDonald andE.KimKietzman.
AEAReactorServicesReportTitle"ReportontheMathematical ModelingofTwoNozzleSpecimens forRochester GasEcElectricCorporation" Dated16November1992byP.D.BirchallandL.N.J.Poulter.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page18of48RELIEFREQUESTNO.7(Waspreviously approvedasReliefRequestNo.34forThirdInterval)
COMPONENT SUPPORTINTEGRALATTACHMENT EXAMINATION LIMITATIONS Sstem/ComonentsforwhichReliefisReuested:ThisReliefRequestisrequested forthree(3)supports.
Inspections ofthesesupportsisaddressed byClass2,CategoryC-C,ItemNumberC3.20,Identified Component SupportIntegralAttachments SurfaceExaminations.
~BtlCoverageObtained~S<temMSU-33MSU-34Penetration 14050%50%82%Mainsteam (MS)Mainsteam (MS)ResidualHeatRemoval(RHR)II.CodeReuirement:
ASMESectionXICode,1995Edition,1996Addenda,requiresessentially 100%oftheweldlengthtoobtaincodecoverage.
ASMESectionXICodeCaseN-460statesthatiftheentireexamination volumeorareacannotbeexaminedduetointerference byanothercomponent orpartgeometry, areduction incoverageisacceptable providedthatthecoverage(thelackof)islessthan10%.III.CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromexamining 100%ofthelengthforthese3supports.
Examining 100%oftheweldlengthwouldbeimpractical, becausethesupportwouldhavetoberedesigned orreplacedtoenableinspection.
Theamountofcoverageisestimated at50%forMSU-33,50%forMSU-34,and82%forPenetration 140.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page19of48RELIEFREQUESTNO.7(Con't)IV.BasisforRelief:Reliefisrequested pursuanttotheprovisions of10CFR50.55a(g)(5)(iii),
therequiredexamination coveragefortheidentified itemsareimpractical andwouldrequireredesigntoallowexamination ortobereplacedtoenableinspection.
R.E.GinnaNuclearPowerPlantwasdesignedandconstructed totheB31.1,1955editionconstruction code.Thiscodedidnotcontainrequirements toensurethatitemsbeaccessible forfutureexaminations.
Theabovenotedintegralattachments associated withthecomponent supportsorpenetration anchorsupportswereinstalled utilizing thisconstruction codewhichdidnotprovideforaccessibility forfutureISINDE.Duetothelimiteddesignaccessibility, ISIexaminations cannotbeperformed ontheinaccessible welds.ThetwoMainSteamsupports(MSU-33andMSU-34)aresimilarindesigninthathaveacomplexgussetassemblythatisweldedtotheprocesspiping(integral attachment) andweldedtothebaseplate,whichissecuredtotheconcretefloor.Duetothesmallsizeofgussets,accessislimitedforboththesurfaceexamination andsurfacepreparation oftheintegralattachment weldslocatedundertheprocesspiping,Theachievable accesspercentage hasbeenidentified abovewithinthisreliefrequest.Theidentified component supports(including theintegralattachments) areperiodically visuallyexamined(VT-3).ASMESectionXIperiodicleakageexaminations areperformed aswellasOperatorwalkdowns asspecified byPlantOperating Procedures.
Theseoperatorwalkdowns, periodicsystemleakageexaminations andcomponent supportvisualexaminations provideadditional assurances inmaintaining plantsafety.V.Alternate Examinations:
R.E.GinnaNuclearPowerPlantproposesthatthesurfaceexamination coverageidentified abovebeacceptable inmeetingCodeRequirements andisnotconducive inobtaining therequirements specified withinCodeCaseN-460.
FOURTHINTERVALISIRELIE<FREQUESTSATTACHMENT 1Revision0Page20of48RELIEFREQUESTNO.7(Con't)VI.Justification fortheGrantinofRelief:R.E.GinnaNuclearPowerPlantwasdesignedandconstructed totheB31.1,1955editionconstruction code.Thiscodedidnotcontainrequirements toensurethatitemsbemadeaccessible forfutureNDEexaminations.
Duetotheoriginallimiteddesignaccessibility, ISIexamination coveragecannotbeobtainedtotheextentrequiredbythecurrentASMECode.ASMESectionXIleakageexaminations areperformed aswellasOperatorwalkdowns asspecified byPlantOperating Procedures.
Theseoperatorwalkdowns, periodicsystemleakageexaminations andcomponent supportvisualexaminations provideadditional assurances inmaintaining plantsafety.Theidentified examination coveragefortheseitemsshouldbeacceptable infulfilling ASMESectionXIcoveragerequirements.
VII.Imlementation Schedule:
Implementation shallbeperformed fortheFourthInterval.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page21of48RELIEFREQUE~STNO.8(Waspreviously approvedasReliefRequestNo.36forThirdInterval)
REACTORPRESSUREVESSELNOZZLE-to-SAFE ENDBUTTWELDSURFACEEXAMINATION LIMITATIONS Sstem/ComonentsforwhichReliefisReuested:ThisReliefRequestisrequested forsix(6)ReactorPressureVesselNozzle-to-Safe EndButtWelds.Inspection oftheseweldsisaddressed underClass1,CategoryB-F,ItemNumberB5.10,Nozzle-to-Safe EndWeldSurfaceExaminations asidentified below.WeldID¹ISISumma¹CoveraeObtainedPIFW-IIPL-FW-VPIFW-IVPL-FW-VII AC-1003-1 AC-1002-1 00210000240000270000300000330000360062%75%68.5%72%0%(*)0%(*)Note:(*)=weldsembeddedinconcrete.
CodeReuirement:
ASMESectionXICode,1995Edition,1996Addenda,CategoryB-F,ItemNumberB5.10,volumetric andsurfaceexaminations shallbeperformed withessentially 100%oftheweldlengthtoobtaincodecoverage.
ASMESectionXICodeCaseN-460statesthatiftheentireexamination volumeorareacannotbeexaminedduetointerference byanothercomponent orpartgeometry, areduction incoverageisacceptable providedthatthe(lackof)coverageislessthan10%.PreviousCodesutilizeddidnotincludethis90%coveragerequirement andexaminations wereperformed totheextentobtainable.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page22of48RELIEFREQUESTNO.8(Cont'd)III.CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromthesurfaceexamination requirements forthesix(6)identified welds.SurfaceExamination ofthefirstfour(4)weldsislimitedduetoOriginalConstruction Codeinterferences ofthefloorandwallinthe"Sandbox" wheretheseweldsarelocated.The"Sandboxes" wouldhavetoberedesigned toenabletheweldstobesurfaceexaminedtoobtainCoderequiredcoverage.
(Volumetric examination oftheseweldsisperformed fromtheinsideoftheVesselandisnotapartofthisReliefRequest.)
SurfaceExamination ofthelasttwoweldsisimpractical.
Theconcretesurrounding theReactorPressureVesselhasembeddedthesewelds.TheconcretewallaroundtheReactorPressureVesselwouldhavetoberedesigned orreplacedtoenablethetwo(2)weldstobeinspected withasurfaceexamination.
(Volumetric examination oftheseweldsisperformed fromtheinsideoftheVesselandisnotapartofthisReliefRequest.)
IV.BasisforRelief:Reliefisrequested pursuanttotheprovisions of10CFR50.55a(g)(5)(iii),
therequiredexamination coveragefortheidentified weldsisimpractical andwouldrequireredesignorreplacement toobtainCoderequiredsurfaceexamination coverage.
R.E.GinnaNuclearPowerPlantwasdesignedandconstructed totheB31.1,1955editionConstruction Code.Thiscodedidnotcontainrequirements toensurethatitemsbeaccessible forfutureexaminations.
Theabovenotedpipingweldswereinstalled utilizing thisconstruction code,whichdidnotprovideforaccessibility forfutureISINDE.Duetothelimiteddesignaccessibility, ISIsurfaceexamination coverageisbelowCodepercentage requirements asidentified withinthisReliefRequest.Thefirstfour(4)weldsofthisReliefRequestarelocatedina"Sandbox" configuration.
Withinthe"Sandbox",
theweldsareagainstthefloorandonewall.Theangledwallisjoinedtothefloorandisagainsttheweld.Thesurfaceexamination oftheseweldsislimitedduetoOriginalConstruction Codeinterferences ofthefloorandwallofthe"Sandbox".
The"Sandboxes" wouldhavetoberedesigned toenabletheweldstobeinspected toobtainCoderequiredcoverageforthesurfaceexaminations.
Thelasttwo(2)weldsofthisReliefRequestareembeddedinconcrete.
Thisconcretestructure isthewallthatsurrounds theReactorPressureVessel~
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page23of48IV(Con't)RELIEFREQUESTNO.8(Cont<d)ASMESectionXIClass1systemleakageexaminations areperformed.
Theseleakageexaminations demonstrate pressureboundaryintegrity andprovideadditional assurances inmaintaining plantsafety.V.Alternate Examinations:
R.E.GinnaNuclearPowerPlantproposesthatthesurfaceexamination coverageidentified forthefirstfour(4)weldsabovebeacceptable infulfilling theCoderequiredexamination coverage.
Theactualphysicalconfiguration ofthe"Sandboxes" isnotconducive inobtaining therequirements specified withinCodeCaseN-460foracceptable coverage.
Volumetric examination oftheseweldsisperformed fromtheinsideoftheVessel,andwillbeperformed duringthe2009outage.Forthelasttwo(2)welds,theCodesurfaceexamination requirements areimpractical andcannotbeexaminedduetothembeingembeddedinconcrete.
Volumetric examination oftheseweldsisperformed fromtheinsideoftheVessel,andwillbeperformed duringthe2009Outage.VI.Justification fortheGrantinofRelief:R,E.GinnaNuclearPowerPlantwasdesignedandconstructed totheB31.1,1955editionConstruction Code.Thiscodedidnotcontainrequirements toensurethatitemsbemadeaccessible forfutureNDEexaminations.
Duetotheoriginallimiteddesignaccessibility orlackofdesignaccessibility, ISIsurfaceexamination coveragecannotbeobtainedtotheextentrequiredbytheASMECode.ASMESectionXIClass1systemleakageexaminations areperformed.
Theseleakageexaminations demonstrate pressureboundaryintegrity andprovideadditional assurances inmaintaining plantsafety.Theidentified examination coveragefortheseitemsshouldbeacceptable infulfilling ASMESectionXIcoveragerequirements.
g/svo//FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page24of48RELIEFREQUE<STNO.8(Cont'd)VII.Imlementation Schedule:
Thesurfaceexaminations willbeperformed duringtheendoftheFourthIntervalonthefirstfour(4)accessible welds.Forthetwo(2)weldsembeddedinconcrete, surfaceexaminations cannotbeperformed.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page25of48RELIEFREQUESTNO.9(WasReliefRequestNo,37forThirdInterval)
CONTAINMENT INSPECTION SEALSANDGASKETSSstem/ComonentsforwhichReliefisReuested:SealsandgasketsofClassMCpressureretaining components andmetalliclinersofClassCCcomponents, Examination CategoryE-D,ItemNumbersE5.10andE5.20ofIWE-2500, TableIWE-2500-1, ASMESectionXI,1992Edition,1992Addenda.Severalhundredsealsandgasketsareaffectedbythisreliefrequest.II.CodeReuirement:
ASMESectionXICode,1992Edition,1992Addenda,IWE-2500, TableIWE-2500-1, CategoryE-D,ItemNumbersE5.10andE5.20requiressealsandgasketsonairlocks, hatches,andotherdevicestobevisuallyexamined, VT-3,onceeachintervaltoassurecontainment leak-tight integrity.
III.CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromperforming theCode-required visualexamination, VT-3,ontheaboveidentified metalcontainment sealsandgaskets,IV.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
Thepenetrations discussed belowcontainsealsandgaskets.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page26of48RELIEFREQUESTNO.9(Cont'd)Electrical Penetrations Electrical penetrations useaheaderplateattachedtoacontainment penetration nozzleflangewithredundant 0-ringsbetweentheheaderplateandflangeface.Modulesthroughwhichelectrical conductors passareinstalled intheheaderplate.Onetype,manufactured byAmphenol, usessealsandgasketstoassureleaktightintegrity.
Asecondtype,manufactured byConax,usesasetofcompression fittings.
Replacement modulesfortheAmphenolpenetrations useacombination of0-ringsandcompression fittings.
Eachpenetration ispressurized withdrynitrogentomaintainandmonitorintegrity andtopreventtheintrusion ofmoistureintothepenetration.
Thesesealsandgasketscannotbeinspected withoutdisassembly ofthepenetration togainaccesstothesealsandgaskets.Containment Personnel andEquipment HatchesThePersonnel andEquipment Hatchesutilizeaninnerandouterdoorwithgasketsurfacestoensurealeaktightintegrity.
Thesehatchesalsocontainothergasketsandsealssuchasthehandwheel shaftseals,electrical penetrations, blankflanges,andequalizing pressureconnections whichrequiredisassembly togainaccesstothegasketsandseals.Sealandgasketjointsreceivea10CFR50AppendixJtest.Asnotedin10CFR50AppendixJ,thepurposeofTypeBtestsistomeasureleakageofcontainment orpenetrations whosedesignincorporates resilient seals,gaskets,sealantcompounds, andelectrical penetrations fittedwithflexiblemetalsealassemblies.
Examination ofsealsandgasketsrequirethejoints,whichareprovenadequatethroughAppendixJtesting,bedisassembled.
Forelectrical penetrations, thiswouldinvolveapre-maintenance AppendixJtest,de-termination ofcablesatelectrical penetrations ifenoughcableslackisnotavailable, disassembly ofthejoint,removalandexamination ofthesealsandgaskets,reassembly ofthejoint,re-termination ofthecablesifnecessary, postmaintenance testingofthecables,andapostmaintenance AppendixJtestofthepenetration.
TheworkrequiredfortheContainment Hatcheswouldbesimilarexceptforthede-termination, re-termination, andtestingofcables.Thisimposestheriskthatequipment couldbedamaged.The1992Edition,1993Addenda,ofSectionXIrecognizes thatdisassembly ofjointstoperformtheseexaminations isnotwarranted.
Note1inExamination CategoryE-Dwasmodifiedinthe1995EditionofSectionXItostatethatsealorgasketconnections neednotbedisassembled solelyforperformance ofexaminations.
However,withoutdisassembly, mostofthesurfaceofthesealsandgasketswouldbeinaccessible.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page27of48IV(Con't)RELIEFREQUESTNO.9(Cont'd)Forthosepenetrations thatareroutinely disassembled, aTypeBtestisrequireduponfinalassemblyandpriortostart-up.
SincetheTypeBtestwillassuretheleaktightintegrity ofprimarycontainment, theperformance ofthevisualexamination wouldnotprovideanincreaseinthelevelofsafetyorquality.Sealsandgasketsarenotpartofthecontainment pressureboundaryundercurrentCoderules(NE-1220(b)).Theairlocksandhatchescontaining thesematerials aretestedinaccordance with10CFR50,AppendixJ.Ifincreased leakageisidentified duringtheseAppendixJtests,thecauseofleakagewouldbeinvestigated.
Ifincreased leakagewereduetodegradation ofthesealorgasketmaterial, corrective measureswouldbeappliedandthecomponent retested.
Repairorreplacement ofsealsandgasketsisnotsubjecttoCode(1992Edition,1992Addenda)rulesinaccordance withParagraph IWA-4111(b)(5) ofASMESectionXI.Thevisualexamination ofsealsandgasketsinaccordance withIWE-2500, TableIWE-2500-1isaburdenwithoutanycompensating increaseinthelevelofsafetyorquality.Reliefisrequested inaccordance with10CFR50.55a(a)(3)(ii).
Compliance withtheoriginalrequirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityandsafety.Testingthesealandgasketjointsinaccordance with10CFR50,AppendixJwillprovideadequateassurance oftheleak-tight integrity ofthesealsandgaskets.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page28of48RELIEFREQUESTNO.9(Cont'd)Alternate Examinations:
Theleaktestingofsealandgasketjointswillbeinaccordance with10CFR50,AppendixJ.Noadditional alternative examinations tothevisualexamination, VT-3,ofthesealsandgasketswillbeperformed.
Justification fortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-1submitted byDavis-Besse asoneoftheEPRI"Containment Inspection ProgramGuide"PilotPlantReliefRequests.
ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.Imlementation Schedule:
Reliefisrequested forthefirstinspection intervalfortheIWEContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page29of48RELIEFREQUESTNO.10(WasReliefRequestNo.38forThirdInterval)
CONTAINMENT INSPECTION SUCCESSIVE EXAMINATIONS AFTERREPAIRSstem/ComonentsforwhichReliefisReuested:AllClassMC,Paragraphs IWE-2420(b)andIWE-2420(c) successive examination requirements forcomponents foundacceptable forcontinued service.CodeReuirement:
Paragraphs IWE-2420(b)andIWE-2420(c) ofthe1992Edition,1992AddendaofASMESectionXIrequiresthatwhencomponent examination resultsrequireevaluation offlaws,evaluation ofareasofdegradation, orrepairsinaccordance withArticleIWE-3000, andthecomponent isfoundtobeacceptable forcontinued service,theareascontaining suchflaws,degradation, orrepairsshallbereexamined duringthenextinspection periodlistedinthescheduleoftheinspection programofParagraph IWE-2411orParagraph IWE-2412, inaccordance withTableIWE-2500-1, Examination CategoryE-C.CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromtherequirements ofASMESectionXICode,1992Edition,1992Addenda,Paragraphs IWE-2420(b)andIWE-2420(c) toperformsuccessive examination onrepairs.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
Thepurposeofarepairistorestorethecomponent toanacceptable condition forcontinued serviceinaccordance withtheacceptance standards ofArticleIWE-3000.
Paragraph IWA-4150requirestheownertoconductanevaluation ofthesuitability oftherepairincluding consideration ofthecauseoffailure.
/r~o/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page30of48IV(Con't)RELIEFREQUESTNO.10(Cont'd)Iftherepairhasrestoredthecomponent toanacceptable condition, itisoverlyconservative torequiresuccessive examinations.
Otherparagraphs oftheASMECoderecognize thisrequirement asoverlyconservative.
Iftherepairwasnotsuitable, thentherepairdoesnotmeetcoderequirements andthecomponent isnotacceptable forcontinued service.NeitherParagraph IWB-2420(b),Paragraph IWC-2420(b),
norParagraph IWD-2420(b)requiresarepairtobesubjecttosuccessive examination requirements.
Furthermore, iftherepairareaissubjecttoaccelerated degradation, itwouldstillrequireaugmented examination inaccordance withTableIWE-2500-1, Examination CategoryE-C.Thesuccessive examination ofrepairsinaccordance withParagraphs IWE-2420(b)andIWE-2420(c) constitutes aburdenwithoutacompensating increaseinqualityorsafety.Intheirresolution topubliccomment03.3,theNRCstatedwithinSECY96-080datedApril17,1996:"ThepurposeofIWE-2420(b)istomanagecomponents foundtobeacceptable forcontinued service(meaningnorepairorreplacement atthistime)asanExamination CategoryE-Ccomponent.
Ifthecomponent hadbeenrepairedorreplaced, thenthemorefrequentexamination wouldnotbeneeded."Reliefisrequested inaccordance with10CFR50.55a(a)(3)
(ii).Compliance withtheoriginalrequirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityandsafety.Therequirement toperformsuccessive examinations following repairshasbeenremovedinthe1997AddendaofASMESectionXI.ThisaddendahasbeenapprovedbytheASMEMainCommittee andhasbeenpublished.
V.Alternate Examinations:
Successive examinations inaccordance withParagraphs IWE-2420(b)andIWE-2420(c)arenotrequiredforrepairsmadeinaccordance withArticleIWA-4000.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page31of48RELIEFREQUE~STNO.10(Cont'd)Justification fortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-6submitted byDavis-Besse asoneoftheEPRI"Containment Inspection ProgramGuide"PilotPlantReliefRequests.
ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.Imlementation Schedule:
Reliefisrequested forthefirstinspection intervalfortheIWEContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page32of48RELIEFREQUESTNO.11(WasReliefRequestNo.39forThirdInterval)
CONTAINMENT INSPECTION BOLTTORQUEORTENSIONTESTINGSstem/ComonentsforwhichReliefisReuested:ClassMCpressureretaining bolting.CodeReuirement:
ASMESectionXI,1992Editionwiththe1992Addenda,TableIWE-2500-1, Examination CategoryE-G,PressureRetaining Bolting,ItemE8.20.Bolttorqueortensiontestingisrequiredonboltedconnections thathavenotbeendisassembled andreassembled duringtheinspection interval.
CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromASMESectionXI1992Editionwiththe1992AddendaTableIWE-2500-1 Examination CategoryE-G,PressureRetaining Bolting,ItemE8.20.Bolttorqueortensiontestingisrequiredonboltedconnections thathavenotbeendisassembled andreassembled duringtheinspection interval.
BasisforRelief:10CFR50.55a wasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
Bolttorqueortensiontestingisrequiredonboltedconnections thathavenotbeendisassembled andreassembled duringtheinspection interval.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page33of48RELIEFREQUE<STNO.11(Cont'd)IV(Con't)Determination ofthetorqueortensionvaluewouldrequirethattheboltingbeun-torqued andthenre-torqued orre-tensioned.
Theperformance oftheTypeBtestitselfprovesthatthebolttorqueortensionremainsadequatetoprovidealeakratethatiswithinacceptable limits.Thetorqueortensionvalueofboltingonlybecomesanissueiftheleakrateisexcessive.
Onceaboltistorquedortensioned, itisnotsubjecttodynamicloadingthatcouldcauseittoexperience significant change.Verification oftorqueortensionvaluesonboltedjointsthatareprovenadequatethroughAppendixJtestingandvisualinspection isadequatetodemonstrate thatdesignfunctionismet.TorqueortensiontestingisnotrequiredonanyotherASMESectionXI;Class1,2,or3boltedconnections ortheirsupportsaspartoftheInservice inspection program.Also,allpenetrations atR.E.GinnaNuclearPowerPlantareseatedwithpressure(notunseated).
Reliefisrequested inaccordance with10CFR50.55a(a)(3)
(ii).Compliance withtheoriginalrequirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityandsafety.Alternate Examinations:
Thefollowing examinations andtestsrequiredbySubsection IWEensurethestructural integrity andtheleak-tightness ofClassMCpressureretaining bolting,and,therefore, noadditional alternative examinations areproposed:
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page34of48RELIEFREQUESTNO.11(Cont'd)(1)Exposedsurfacesofboltedconnections shallbevisuallyexaminedinaccordance withrequirements ofTableIWE-2500-1, Examination CategoryE-G,PressureRetaining Bolting,ItemNo.E8.10,and(2)Boltedconnections shallmeetthepressuretestrequirements ofTableIWE-2500-1, Examination CategoryE-P,AllPressureRetaining Components, ItemE9.40,and(3)Ageneralvisualexamination oftheentirecontainment onceeachinspection periodshallbeconducted inaccordance with10CFR50.55a(b)(2)(x)(E).
Justification fortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestE-7submitted byDavis-Besse asoneoftheEPRI"Containment Inspection ProgramGuide"PilotPlantReliefRequests.
ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.Imlementation Schedule:
Reliefisrequested forthefirstinspection intervalfortheIWEContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page35of48RELIEFREQUESTNO.12(WasReliefRequestNo.40forThirdInterval)
CONTAINMENT INSPECTION VT-2AFTERREPAIR,REPLACEMENT ORMODIFICATION Sstem/ComonentsforwhichReliefisReuested:Allcomponents subjecttotherulesandrequirements forrepair,replacement ormodification ofClassMC,IWE-5000systempressuretestingvisualexamination inaccordance withthe1992Edition,1992AddendaofASMESectionXI.CodeReuirement:
Paragraph IWE-5240ofthe1992Edition,1992AddendaofASMESectionXIrequiresthattherequirements ofParagraph IWA-5240forvisualexamination, VT-2,areapplicable following repair,replacement ormodification.
CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromperforming theVT-2visualexamination inconnection withsystempressuretestingfollowing repair,replacement ormodification underArticleIWE-5000.
BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
Paragraph IWE-5210statesthatexceptasnotedwithinParagraph IWE-5240, therequirements ofArticleIWA-5000arenotapplicable toClassMCorClassCCcomponents,
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page36of48IV(Con't)RELIEFREQUESTNO.12(Cont'd)Paragraph IWE-5240statesthattherequirements ofParagraph IWA-5240(corrected fromIWA-5246toIWA-5240inthe1993Addenda)forvisualexaminations areapplicable.
Paragraph IWA-5240identifies a"VT-2"visualexamination.
VT-2examinations areconducted todetectevidenceofleakagefrompressure-retaining components, withorwithoutleakagecollection systems,asrequiredduringtheconductofasystempressuretest.Inaddition, personnel performing VT-2examinations arerequiredtobequalified inaccordance withSubarticle IWA-2300ofASMESectionXI.Forrepairs,replacements ormodifications thatareperformed underASMESectionXICode,applicable Construction Code(orInstallation Code)non-destructive examinations (NDE)areperformed andmustmeettheacceptance criteriaoftheConstruction
/Installation Code.InadditiontotheConstruction CodeNDE,applicable ASMESectionXINDEpre-service NDEarealsoperformed.
TheseConstruction CodeandSectionXIpre-service NDErequirements provideadditional assurances thattherepairs,replacements ormodifications aresoundandleak-tight.
TableIWE-2500-1, Examination CategoryE-P,identifies theexamination methodof10CFR50,AppendixJanddoesnotspecifically identifyaVT-2visualexamination.
10CFR50,AppendixJprovidesrequirements fortestingaswellasacceptable leakagecriteria.
Thesetestsareperformed byAppendixJ"Test"personnel andutilizecalibrated equipment todetermine acceptability.
Additionally, 10CFR50.55a(b)(2)(x)(E) requiresageneralvisualexamination ofthecontainment eachperiodthatwouldidentifyanystructural degradation thatmaycontribute toleakage.A"VT-2"visualexamination willnotprovideadditional assurance ofsafetybeyondthatofcurrentAppendixJpractices.
Reliefisrequested inaccordance with10CFR50.55a(a)(3)(i).
Theproposedalternative (pressure testinginaccordance with10CFR50,AppendixJ)willprovideanacceptable levelofqualityandsafety.Thereference toparagraph IWA-5240hasbeenremovedinthe1997AddendaofASMESectionXI.ThisaddendahasbeenapprovedbytheASMEMainCommittee andshouldbepublished in1998.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page37of48RELIEFREQUESTNO.12(Cont'd)Alternate Examinations:
Testingshallbeconducted inaccordance with10CFR50,AppendixJ,inlieuofParagraph IWE-5240ofASMESectionXI,aswellasperforming anIWEdetailedvisualexamination (VT-1)oftherequiredorreplacedarea.Justification fortheGrantinofRelief:Forrepairs,replacements ormodifications thatareperformed underASMESectionXICode,applicable Construction Code(orInstallation Code)non-destructive examinations (NDE)areperformed andmustmeettheacceptance criteriaoftheConstruction
/Installation Code.InadditiontotheConstruction CodeNDE,applicable ASMESectionXINDEpre-service NDEarealsoperformed.
TheseConstruction CodeandSectionXIpre-service NDErequirements provideadditional assurances thattherepairs,replacements ormodifications aresoundandleak-tight.
ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.Imlementation Schedule:
Reliefisrequested forthefirstinspection intervalfortheIWEContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page38of48RELIEFREQUESTNO.13(WasReliefRequestNo.41forThirdInterval)
CONTAINMENT INSPECTION REMOTEVTOFCLASSCCSstem/ComonentsforwhichReliefisReuested:Allcomponents subjecttotherulesandrequirements forInservice Inspection ofClassCCConcreteComponents, Examination CategoryL-A,Concrete, ItemL.1.11asapplicable toIWL-2310, VisualExamination andPersonnel Qualification andIWA-2210, VisualExaminations.
CodeReuirement:
ASMESectionXI,1992Edition,1992Addenda,IWL-2310, VisualExamination andPersonnel Qualification andIWA-2210, VisualExaminations requiresspecificminimumillumination andmaximumdirectexamination distanceforallconcretesurfaces.
CodeReuirementfromwhichReliefisReuested:Reliefisrequested fromParagraph IWA-2210, VisualExamination Requirements forminimumillumination andmaximumdirectexamination distanceofClassCCcomponents underParagraph IWI2310.
FOURTHINTERVALISIRELIEFREQUE<STS ATTACHMENT 1Revision0Page39of48RELIEFREQUESTNO.13(Cont'd)BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
Inadditiontotherequirements ofSubsection IWL,theRulemaking alsoimposestherequirements ofSubsection IWAofthe1992Edition,1992Addendum, ofASMESectionXIforminimumillumination andmaximumdirectexamination distanceofClassCCcomponents, specifically fortheexamination ofconcreteunderParagraph IWL-2510.
Whenremotelyperforming thevisualexaminations requiredbySubsection IWLParagraph IWL-2510,themaximumdirectexamination distancespecified inTableIWA-2210-1 maybeextended, andtheminimumillumination requirements specified inTableIWA-2210-1 maybedecreased.
IWA-2210allowsforremoteexamination aslongastheremoteexamination procedure isdemonstrated toresolvetheselectedtestchartcharacters.
TheRegistered Professional Engineer(RPE)willidentifyminimumsizeofindications ofinterest.
Forremotevisualexamination, theprocedure andequipment tobeusedwillbedemonstrated capableofresolving theseminimumindications tothesatisfaction oftheRPEandtheAuthorized NuclearInsurance Inspector (ANII),asallowedinIWA-2240, "Alternative Examinations."
Therecordofdemonstration willbeavailable toRegulatory Authorities.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page40of48IV(Con't)RELIEFREQUE~STNO.13(Cont'd)Accessibility tohigherportionsofthedomeandthecontainment buildingitselfmakeitahardshiptoobtainthemaximumdirectexamination distanceandminimumillumination requirements.
Theinstallation ofextensive temporary scaffoldsystemsoraclimbingscaffoldsystemtoaccesstheseportionsofthecontainment wouldbenecessary.
Thesescaffolds wouldprovidelimitedaccessduetocontainment geometryrestrictions aswellasstructural andequipment interferences.
Theinstallation andremovalofthesescaffolds wouldincreasebothworkerradiation exposureandpersonnel safetyinordertomeetParagraph IWA-2210requirements.
TheNRCstaffreceivedsevencommentsthatwereconsolidated intoPublicComment¹2.3inPartIIIofAttachment 6AtoSECY-96-080.
TheStaffresponsetotheseconcernsisasfollows:"Comments receivedfromASMEmembersonthecontainment committees indicatethatthenewer,morestringent requirements ofIWA-2210werenotintendedtobeusedfortheexamination ofcontainments andwereinadvertently includedinSubsection IWL.TheNRCagreesthatremoteexaminations aretheonlypractical methodforinspecting muchofthecontainment surfacearea.50.55a(b)
(2)(x)(B)hasbeenaddedtothefinalrulewhichcontainsalternative lightingandresolution requirements whichmaybeusedinlieuoftherequirements contained inIWA-2210-1."
However,asspecified within10CFR50.55a(b)(2)(x)(B) ofthefinalrule,thisalternative appliesonlytoSubsection IWE,andnottoSubsection IWL.Reliefisrequested inaccordance with10CFR50.55a(a)(3)(ii).Compliance withtheoriginalrequirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityandsafety.V.Alternate Examinations:
Whenperforming remotelythevisualexaminations requiredbySubsection IWL,Paragraph IWL-2510, themaximumdirectexamination distancespecified inTableIWA-2210-1 maybeextended, andtheminimumillumination requirements specified inTableIWA-2210-1 maybedecreased providedthattheconditions orindications forwhichthevisualexamination isperformed canbedetectedatthechosendistanceandillumination.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page41of48RELIEFREQUESTNO.13(Cont'd)Justification fortheGrantinofRelief:ThisReliefRequestissimilartoReliefRequestL-1submitted byCalvertCliffsasoneoftheEPRI"Containment Inspection ProgramGuide"PilotPlantReliefRequests.
ReliefRequestL-1(forCalvertCliffs)wassubsequently approvedbytheNRC.RefertoaletterfromtheNRC(S.Bajwa)toBaltimore GasandElectric(C.Cruse),datedNovember16,1998(DocketNo.50-317/318).
ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.Imlementation Schedule:
Reliefisrequested forthefirstinspection intervalfortheIWLContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revtsion0Page42of48RELIEFREQUESTNO.14(WasReliefRequestNo.42forThirdInterval)
REACTORPRESSUREVESSEL(RPV)WELDEXAMINATION LIMITATIONS Sstem/ComonentsforwhichReliefisReuested:ThisReliefRequestpertainstoeight(8)ReactorPressureVesselweldsorInnerRadiusVolumetric examinations.
Volumetric examination limitations oftheseeightweldsareidentified inAttachment Number1.CodeReuirement:
Whenperforming Volumetric examinations, ASMESectionXICode,1995Edition,1996Addenda,requiresessentially 100%oftheweldlengthorareatoobtaincoverage.
ASMESectionXICodeCaseN-460statesthatiftheentireexamination volumeorareacannotbeexaminedduetointerference byanothercomponent orpartgeometry, areduction incoverageisacceptable providedthatthecoverage(thelackof)islessthan10%.ReuirementfromwhichReliefisReuested:Reliefisrequested fromexamining 100%oftheweldlengthorareasfortheseeight(8)identified items.Examining 100%oftheweldlengthorareaswouldbeimpractical duetooriginaldesigninterference.
Attachment Number1identifies volumetric examination achievable coverageandassociated limitations.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page43of48RELIEFREQUE~STNO.14(Cont'd)BasisforRelief:Reliefisrequested pursuanttotheprovisions of10CFR50.55a(g)(5)(iii),
therequiredexamination coveragefortheidentified itemsareimpractical andwouldrequireredesigntoallowexamination ortobereplacedtoenableinspection.
TheReactorPressureVessel(RPV)wasdesignedandconstructed toASMESectionIII,1965Edition.Thiscodedidnotcontainrequirements toensurethatitemsbeaccessible forfutureexaminations.
Theeight(8)itemsidentified withinAttachment Number1wasinstalled utilizing thisconstruction codewhichdidnotprovideforaccessibility forfutureISINDE:TheClass1ReactorPressureVesselispartoftheASMESectionXIVT-2LeakageExamination boundary.
Class1LeakageExaminations areperformed eachrefueling outageasrequiredbytheCodetoinsurepressureboundaryintegrity.
InadditiontotheASMESectionXIleakageexaminations, Operatorwalkdowns asspecified byPlantOperating Procedures arealsoperformed.
Thecombination ofoperatorwalkdowns andtheClass1leakageexamination thatisperformed eachrefueling outageprovideadditional assurances inmaintaining plantsafety.Alternate Examinations:
R.E.GinnaNuclearPowerPlantproposesthatthevolumetric examination coverageidentified withinAttachment Number1beacceptable infulfilling requiredCodevolumetric examination coverage.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page44of48RELIEFREQUESTNO.14(Cont'd)Justification fortheGrantinofRelief:TheReactorPressureVesselwasdesignedandconstructed toASMESectionIH,1965Editionconstruction code.Thiscodedidnotcontainrequirements toensurethatitemsbemadeaccessible forfutureNDEexaminations.
Duetotheoriginallimiteddesignaccessibility, examination coveragecannotbeobtainedtotheextentrequiredbytheASMESectionXICode.ASMESectionXIClass1leakageexaminations areperformed eachoutageaswellasOperatorwalkdowns asspecified byPlantOperating Procedures.
Theseoperatorwalkdowns andsystemleakageexaminations provideadditional assurances inmaintaining plantsafety.Theidentified volumetric examination coveragefortheseitemsshouldbeacceptable infulfilling coveragerequirements.
Previousexaminations wereperformed ontheseitemsinconformance totheCoderequirements ineffectforRG&Eatthosetimes.Imlementation Schedule:
Implementation shallbeperformed attheendoftheFourthInterval.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page45of48RELIEFREQUESTNO.14(Cont'd)Attachment Number1CategoryItemSum.Weld<<umberNumberNumberIDDere!iiuu/R<<iremeuiLimitations B-AB1.30000501RPV-AVesseltoFlangeCirc.Weld54%000502SectionXICodeRequired000503Keyways&Irradiation SlotsB-AB1.11000300RPV-DLowerShelltoRingForging81%Circ.Weld.SectionXICodeRequiredGuideLugs&IncoresB-DB-DB-DB3.90001900N1AB3.90002500N1BB3.100002300N2A-IRSNozzleVesselWD028D-30M.
55%'ozzle BossSectionXICodeRequired70%NozzleVesselWD208D-30M.
55%'ozzle BossSectionXICodeRequired70%NozzleInsideRadiusSection.90%InnerRadiusSectionXICodeRequiredB-DB-DB-DB3.100B3.90B3.90002900N2B-IRS003100AC-1003003400AC-1002NozzleInsideRadiusSection.90%SectionXICodeRequiredNozzleVesselWD108D-30M.
55%'ection XICodeRequired72%NozzleVesselWD288D-30M.
55%'ection XICodeRequired72%InnerRadiusNozzleBossNozzleBossVolumetric WeldExamination 2Volumetric NearSurfaceExamination FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page46of48RequestforReliefNo.15(WasReliefRequestNo.43forThirdInterval)
ResidualHeatRemoval(RHR)HeatExchanger OutletNozzleWeldsExamination Limitations I.Sstem/ComonentsforWhichReliefisRuested:ThisReliefRequestpertainstotwo(2)ResidualHeatRemoval(RHR)HeatExchanger OutletNozzletoShellWelds,ASMEClass2,CategoryC-B,ItemC2.32.Thereisonenozzleofthistypeassociated witheachofthetwoidentical RHRHeatExchangers.
TheCoderequiresthattheexamination beperformed whenthecomponent isopened.BothHeatExchangers wereopenedandVolumetrically examined.
Limitedcoverageisidentified below.Summaru¹WeldIDExamCoveraeLimitations 169253ONSRHE-1B 79%duetointernalweldedseparation plate169053ONSRHE-1A 79%duetointernalweldedseparation plateII.ASMESectionXICodeReuirement:
ASMESectionXICode,1995Edition,1996Addenda,requiresessentially 100%oftheweldlengthorareatoobtaincoverage.
ASMESectionXICodeCaseN-460statesthatiftheentireexamination volumeorareacannotbeexaminedduetointerference byanothercomponent orpartgeometry, areduction incoverageisacceptable providedthatthecoverage(thelackof)islessthan10%.
/sea/FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page47of48RequestforReliefNo.15(Cont'd)III.RuirementfromWhichReliefisReuested:Reliefisrequested fromexamining 100%oftheweldlengthorareasforthesetwo(2)"identified items.Examining 100%oftheweldlengthorareaswouldbeimpractical duetooriginaldesigninterference.
IV.BasisforRelief:Reliefisrequested pursuanttotheprovisions of10CFR50.55a(g)(5)(iii),
therequiredexamination coveragefortheidentified itemsareimpractical andwouldrequireredesigntoallowexamination ortobereplacedtoenableinspection.
Thetwoidentical ResidualHeatRemoval(RHR)HeatExchangers wasdesignedandconstructed toASMESectionVIII,1965Edition.Thiscodedidnotcontainrequirements toensurethatitemsbeaccessible forfutureexaminations.
Thetwo(2)ASMEClass2itemsidentified abovewereinstalled utilizing thisconstruction codewhichdidnotprovideforaccessibility forfutureISINDE.TheISIASMESectionXIvolumetric requirement isidentified withinTableIWC-2500-1, CategoryC-B,ItemNumberC2.32.TheResidualHeatRemoval(RHR)HeatExchangers ispartoftheASMESectionXIVT-2LeakageExamination boundary.
LeakageExaminations areperformed eachperiodasrequiredbyCategoryC-B,ItemNumberC2.33oftheCodetoinsurepressureboundaryintegrity.
InadditiontotheASMESectionXIleakageexaminations, Operatorwalkdowns asspecified byPlantOperating Procedures arealsoperformed.
Thecombination ofoperatorwalkdowns andperiodleakageexaminations thatareperformed provideadditional assurances inmaintaining plantsafety.V.Alternate Examinations:
R.E.GinnaNuclearPowerPlantproposesthatthevolumetric examination coverageidentified aboveshallbeacceptable infulfilling therequiredvolumetric examination coverage.
FOURTHINTERVALISIRELIEFREQUESTSATTACHMENT 1Revision0Page48of48RequestforReliefNo.15(Cont'd)VI.Justification fortheGrantinofRelief:TheResidualHeatRemoval(RHR)HeatExchangers weredesignedandconstructed toASMESectionVIII,1965Editionconstruction code.Thiscodedidnotcontainrequirements toensurethatitemsbemadeaccessible forfutureNDEexaminations.
Duetotheoriginallimiteddesignaccessibility, examination coveragecannotbeobtainedtotheextentrequiredbythecurrentASMECode.ASMESectionXIperiodicleakageexaminations areperformed aswellasOperatorwalkdowns asspecified byPlantOperating Procedures.
Theseoperatorwalkdowns andperiodicsystemleakageexaminations provideadditional assurances inmaintaining plantsafety.Theidentified volumetric examination coveragefortheseitemsshouldbeacceptable infulfilling coveragerequirements.
VII.Imlementation Schedule:
Theseexaminations willbeperformed inaccordance withTableIWC-2500-1 fortheFourthInterval.
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