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{{#Wiki_filter:1~hrCATEGORYj.REGULATCINFORMATIONDISTRIBUTIONSTEM(RIDE)ACCESSIONNBR:9611150063DOC.DATE:96/11/07NOTARIZED:NOFACIL:50-315Donald.C.CookNuclearPowerPlant,Unit1,indianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.EAmericanElectricPowerCo.,Inc.RECIP.NAMERECIPIENTAFFILIATIONDocument.ControlBranch(DocumentControlDesk)DOCKET0500031505000316
{{#Wiki_filter:1~hrCATEGORYj.REGULATCINFORMATION DISTRIBUTIONSTEM (RIDE)ACCESSION NBR:9611150063 DOC.DATE:
96/11/07NOTARIZED:
NOFACIL:50-315 Donald.C.CookNuclearPowerPlant,Unit1,indianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E AmericanElectricPowerCo.,Inc.RECIP.NAME RECIPIENT AFFILIATION Document.ControlBranch(Document ControlDesk)DOCKET0500031505000316


==SUBJECT:==
==SUBJECT:==
ForwardsRAIrerequestsforrelieftoCodeCasesN-521,N-491,N-5096N-524.rDISTRIBUTIONCODE:A047DCOPIESRECEIVED'LTRLENCLSIZE:IITITLE:ORSubmittal:lnservice/Testing/RelieffromASMCode-GL-9-04NOTES:TERECIPIENTIDCODE/NAMEPD3-3LAHICKMANFJINTERNAL:AEOD/SPD/RABNRR/DE/EMEBOGC/HDS2RES/DSIR/EIBCOPIESLTTRENCL1111-11111011RECIPIENTIDCODE/NAMEPD3-3PDECENTER1NUDOCS-ATRACTRES/DET/EMMEBCOPIESLTTRENCL111111110EXTERNAL:LITCOANDERSONNRCPDR11NOAC1111D0ENNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 AmericanElectricP~erNuclearGeneration+p500CircleDriveBuchanan,MI491071395November7,1996DocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:ANMICINtFI.KCfRICPOWMAEP:NRC:0969AADonaldC.CookNuclearPlantUnits1and2THIRD10-YEARINTBRVALINSERVICEINSPECTIONPROGRAMANDASSOCIATEDREQUESTSFORRELIEF(TACNOS.M94871ANDM94872)REQUESTFORADDITIONALINFORMATIONReferencesLetterAEP:NRC:0969AW,E.E.Fitzpatri,cktoU.S.NRC,"DonaldC.CookNuclearPlantUnits1and2,THIRD10-YEARINTERVALINSERVICBINSPECTIONPROGRAMANDASSOCIATEDREQUESTSFORRELIEF(TACNOS.M94871ANDM94872),REQUESTFORADDITIONALINFORMATION"dated,September10,1996.2.Letter,C.A.CarpentertoE.E.Fitzpatrick,"D.C.COOK,UNITS1AND2,REQUESTINGAPPROVALOFCODECASEN-498-1ASANALTERNATIVETOTHBREQUIREDHYDROSTATICPRESSURETEST(TACNOS.M91783ANDM91784)",datedJuly5,1995.Thethird10-yearinserviceinspectionplanforCookNuclearPlantutilizescodecasesthathavenotbeenincorporatedintoRegulatoryGuide1.147.Becauseofthis,NRCapprovaloftheuseofthesecodecasesasalternativestotheASMESectionXIrequirementsisrequired,TheparticularcodecasesforwhichapprovalisrequiredwereidentifiedinourSeptember10,1996,letter(reference1).TheattachmentstothisletterprovidereliefrequeststhatwouldallowCookNuclearPlanttouseCodeCasesN-521,N-491-1,N-509,andN-524asalternativestotherequirementsofthe1989editionofASMECodeSectionXI.PleasenotethatalthoughCodeCaseN-498-1wasidentifiedinreference1,thisletterdoesnotcontainareliefrequestforuseofthiscodecasebecausewepreviouslyobtainedapprovalforitsuse(reference2).ApprovaloftheserequestsisrequiredbyJuly1,1997.E.E.FitzpatrickVicePresidentAttachmentsh9'6ii150063961107~i.PDR).ADOCK050003i5:6'~POREli U.S.NuclearRegulatoryCommissionPage2AEP:NRC:0969AAcc:A.A.BlindA.B.BeachMDEQ-DW&RPDNRCResidentInspectorJ.R.Padgett Attachment1toAEP:NRC:0969AABACKGROUNDINPORMATIONANDJUSTIFICATIONTOUSECODECASEN-521ASANALTERNATIVEPORTHEEXAMINATIONOPNOZZLETOVESSELANDSAFEENDWELDSANDINSIDERADIUSSECTIONSPORTHECOOKNUCLEARPLANTUNITS1and2THIRD10"YEARINTERVAL  
ForwardsRAIrerequestsforrelieftoCodeCasesN-521,N-491,N-509 6N-524.rDISTRIBUTION CODE:A047DCOPIESRECEIVED'LTR LENCLSIZE:IITITLE:ORSubmittal:
lnservice/Testing/Relief fromASMCode-GL-9-04NOTES:TERECIPIENT IDCODE/NAME PD3-3LAHICKMANFJ INTERNAL:
AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS2RES/DSIR/EIB COPIESLTTRENCL1111-11111011RECIPIENT IDCODE/NAME PD3-3PDECENTER1NUDOCS-ATRACTRES/DET/EMMEB COPIESLTTRENCL111111110EXTERNAL:
LITCOANDERSONNRCPDR11NOAC1111D0ENNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 AmericanElectricP~erNuclearGeneration+p 500CircleDriveBuchanan, MI491071395 November7,1996DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
ANMICINtFI.KCfRIC POWMAEP:NRC:0969AA DonaldC.CookNuclearPlantUnits1and2THIRD10-YEARINTBRVALINSERVICE INSPECTION PROGRAMANDASSOCIATED REQUESTSFORRELIEF(TACNOS.M94871ANDM94872)REQUESTFORADDITIONAL INFORMATION References LetterAEP:NRC:0969AW, E.E.Fitzpatri,ck toU.S.NRC,"DonaldC.CookNuclearPlantUnits1and2,THIRD10-YEARINTERVALINSERVICB INSPECTION PROGRAMANDASSOCIATED REQUESTSFORRELIEF(TACNOS.M94871ANDM94872),REQUESTFORADDITIONAL INFORMATION" dated,September 10,1996.2.Letter,C.A.Carpenter toE.E.Fitzpatrick, "D.C.COOK,UNITS1AND2,REQUESTING APPROVALOFCODECASEN-498-1ASANALTERNATIVE TOTHBREQUIREDHYDROSTATIC PRESSURETEST(TACNOS.M91783ANDM91784)",
datedJuly5,1995.Thethird10-yearinservice inspection planforCookNuclearPlantutilizescodecasesthathavenotbeenincorporated intoRegulatory Guide1.147.Becauseofthis,NRCapprovaloftheuseofthesecodecasesasalternatives totheASMESectionXIrequirements isrequired, Theparticular codecasesforwhichapprovalisrequiredwereidentified inourSeptember 10,1996,letter(reference 1).Theattachments tothisletterprovidereliefrequeststhatwouldallowCookNuclearPlanttouseCodeCasesN-521,N-491-1,N-509,andN-524asalternatives totherequirements ofthe1989editionofASMECodeSectionXI.PleasenotethatalthoughCodeCaseN-498-1wasidentified inreference 1,thisletterdoesnotcontainareliefrequestforuseofthiscodecasebecausewepreviously obtainedapprovalforitsuse(reference 2).ApprovaloftheserequestsisrequiredbyJuly1,1997.E.E.Fitzpatrick VicePresident Attachments h9'6ii150063 961107~i.PDR).ADOCK050003i5:
6'~POREli U.S.NuclearRegulatory Commission Page2AEP:NRC:0969AA cc:A.A.BlindA.B.BeachMDEQ-DW&RPDNRCResidentInspector J.R.Padgett Attachment 1toAEP:NRC:0969AA BACKGROUND INPORMATION ANDJUSTIFICATION TOUSECODECASEN-521ASANALTERNATIVE PORTHEEXAMINATION OPNOZZLETOVESSELANDSAFEENDWELDSANDINSIDERADIUSSECTIONSPORTHECOOKNUCLEARPLANTUNITS1and2THIRD10"YEARINTERVAL  


Attachment-1toAEP:NRC:0969AAPage1System/ComponentforwhichreliefisrequestedNozzletovesselwelds,nozzleinsideradiussections,and'nozzletosafeendweldsforCookNuclearPlant,units1and2.lZ.CodeRequirementsExaminationcategoriesB-DandB-F,itemsB3.90andB3.100ofASMESectionXIcode,1989editionwithnoaddenda,require100~volumetricexaminationperIWA-2500-7ofatleast25~butnotmorethan50%ofreactorvesselnozzletovesselweldsandnozzleinsideradiussectionsbytheendofthefirstperiod.ExaminationcategoryB-F,item5.10requires100%surfaceandvolumetricexaminationperfigureIWB-2500-8ofdissimilarmetalnozzletosafeendweldsthatmaybeexaminedcoincidentwiththevesselnozzleexaminations.ZZI.BasisforcodereliefTheASMESectionXIcoderequirementsfortheexaminationofreactorpressurevesselnozzletovesselwelds,thenozzleinsideradiussections,andnozzletosafeendweldsstipulateadistributionoftheseexaminationsinatleasttwoofthethreeperiods.Thesamesequenceestablishedinthefirst10-yearintervalmustbeusedforsuccessive10-yearintervals.Theimplementationofthesecoderequirementswouldresultinanadditionalset-upoftheautomatedultrasonic(UT)equipmentusedtoexaminethenozzletovesselwelds,insideradiussections,andnozzletosafeendwelds.Additionally,personnelradiationexposurewouldincreaseduetotheadditionalset-upofautomatedUTequipmentandsupporthoursneededtoperformthisexamination.Thispositionisfurthersupportedbythefollowing.CodeCaseN-521issuedbytheASMESectionXIorganizationprovidesanacceptablealternativetothecodemethodfortheexaminationofthenozzletovesselandsafeendwelds,andinsideradiussections.ThiscodereliefwasapprovedforusefortheV.C.SummerNuclearPlant,forthesecond10-yearinterval(reference1).AlternativeMethodAsanalternativetotherequirementsofthe1989editionoftheASMESectionXIcode,itisproposedtoperformallthenozzletovessel,nozzletosafeendwelds,andinsideradiussectionexaminationsinthethirdperiodofthethirdinterval.V.JustificationforgrantingcodereliefCodeCaseN-521imposesthefollowingconditionsthatmustbemetpriortoitsuse:
Attachment-1toAEP:NRC:0969AA Page1System/Component forwhichreliefisrequested Nozzletovesselwelds,nozzleinsideradiussections, and'nozzletosafeendweldsforCookNuclearPlant,units1and2.lZ.CodeRequirements Examination categories B-DandB-F,itemsB3.90andB3.100ofASMESectionXIcode,1989editionwithnoaddenda,require100~volumetric examination perIWA-2500-7 ofatleast25~butnotmorethan50%ofreactorvesselnozzletovesselweldsandnozzleinsideradiussectionsbytheendofthefirstperiod.Examination categoryB-F,item5.10requires100%surfaceandvolumetric examination perfigureIWB-2500-8 ofdissimilar metalnozzletosafeendweldsthatmaybeexaminedcoincident withthevesselnozzleexaminations.
Attachment1toAEP:NRC:0969AAPage2noinservicerepairsorreplacementsbyweldinghavebeenperformedonthenozzletovesselandsafeendwelds,orinsideradiussection;thenozzletovesselandsafeendweldsandtheinsideradiussectionexaminationvolumeshallnotcontainflawsthatrequiresuccessiveexaminationsinaccordancewithZWA-2420(b);andtheunitisnotinthefirst10-yearinterval.CookNuclearPlanthasnotperformedinservicerepairsorreplacementsonthenozzletovesselandsafeendwelds,andinsideradiussections.Flawshavenotbeenidentifiedintheexaminationvolumethatrequiresuccessiveexaminationsandbothunits1and2areinthethird10-yearinterval;therefore,applicabilityofthiscodecasehasbeenmet.Thedeferralofallexaminationstothethirdperiodofthethird10-yearintervalwillresultinreducedset-uphoursandpersonnelradiationexposurehoursduetoconsolidationofmanpowerefforts(set-upandsupport)tothethirdperiodofthethird10-yearinterval.Theexaminationofnozzletovesselweldsfromtheshellsidewasperformedforunits1and2inthethirdperiodofthesecond10-yearintervalduringthe1995and1996refuelingoutages.Examinationofnozzletovesselweldsfromtheboreinsidediameter(fourforunit1andtwoforunit2)wereperformedinthefirstperiodtomeetcoderequ'rements.Thesecond10-yearintervalexaminationoftheinsideradiussectionsandnozzletosafeendweldswasperformedinaccordancewithtableZWA-2500-1ofthecode(atleast25%butnotmorethan50%inthefirstperiodandthebalanceof100%inthethirdperiod).Fouroftheeightinsideradiussectionsandnozzletosafeendweldswereperformedinthethirdperiod(1995)ofthesecond10-yearintervalforunit1.Sixofeightinsideradiussectionsandnozzletosafeendweld'orunit2wereexaminedin1996.Becauseweperformedamajorityoftheexaminationsinthethirdperiodofthesecond10-yearinterval,andtherewerenoflawsdetectedinanyoftheexaminationsconductedinthefirstorsecondintervals,itisreasonabletoconcludethatthedefermentofalltheexaminationstothethirdperiodofthethird10-yearintervalwillnotcompromisethesafetyofplantpersonnelorequipment.ThealternatetestusingCodeCaseN-521eliminatesthehardshipofperformingtwoautomatedexaminationsperinspectionintervalwhileprovidinganacceptablelevelofqualityandsafetyforCookNuclearPlant.VZ.ReferenceLetter,F.J.HebdontoG.J.Taylor,"EvaluationofReliefRequestsforRR-07andIWA-5242(a),VirgilC.SummerNuclearStation(TACNos.M94363andM94364),"datedApril11,1996.
ZZI.BasisforcodereliefTheASMESectionXIcoderequirements fortheexamination ofreactorpressurevesselnozzletovesselwelds,thenozzleinsideradiussections, andnozzletosafeendweldsstipulate adistribution oftheseexaminations inatleasttwoofthethreeperiods.Thesamesequenceestablished inthefirst10-yearintervalmustbeusedforsuccessive 10-yearintervals.
Attachment2toAEP:NRC:0969AABACKGROUNDINFORMATIONANDJUSTIFICATIONTOUSECODECASEN-491-1ASANALTERNATIVEFORTHEZNSPECTZONOFCLASS1,2,3,ANDMCCOMPONENTSUPPORTSFORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL Attachment2toAEP:NRC:0969AAPage1System/Componentforwhich,reliefisrequestedClass1,2,3,andMCcomponentsupports.CodeRequirementsTableIWF-2500-1,examinationcategoryF-A,itemsF1.10throughF1.70ofthe1989editionofASMESectionXIcode,requiresvisualandVT-3examinationofclass1,2,and3'upportsinaccordancewiththescheduleestablishedforcomponentsunderIWB,IWC,IWDandIWE.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexaminationofcomponentsupportsbebasedonafrequencyinaccordancewiththeIWB,IWC,IWD,andIWEcomponentsforeachinterval.Theproposedal"ernativemethodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-491-1providesaselectioncriteriabasedonapplyingareasonablepercentageofexaminationsforeachclassofcomponentsupports.Significantpersonnelradiationexposureandcontaminationsavingsarepredictedtoresultfromtheimplementationoftheserequirementscomparedwiththerequirementsstatedinthe1989editionoftheASMESectionXIcode.IV.CodeCaseN-491-1wasapprovedbytheASMESectionXIorganizationinApril1993,andprovidesanacceptablealternativetothecodemethodfortheexaminationofcomponentsupports.AlternativeMethodV.Asanalternativetotherequirementsofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexaminationofcomponentsupportsinaccordancewiththerequirementsestablishedinASMEapprovedCodeCaseN-491-1.JustificationforgrantingcodereliefTheASMESectionXIcodeorganizationhasapprovedtheuseofCodeCaseN-491-1asanacceptablealternative'othecoderequirementsfortheexaminationofcomponentsupports.Pipingsystemsareexaminedfrequentlyduringplantwalkdownswiththyunitsoperatingorduringplannedorunplannedoutages.Ifthefailureordegradationofasupportisobservedduringthesewalkdowns,whethertheyareformalvisual/VT-3examinationsorinformalobservations,promptactionistakenincludingtheevaluation,repair,and/orreplacementof"supports.Theuseoftheproposedalternativefortheinspectionandexaminationofcomponentsupportswillresultinsignificantlaboranddosesavingswhileprovidinganacceptablelevelofqualityandsafety.
Theimplementation ofthesecoderequirements wouldresultinanadditional set-upoftheautomated ultrasonic (UT)equipment usedtoexaminethenozzletovesselwelds,insideradiussections, andnozzletosafeendwelds.Additionally, personnel radiation exposurewouldincreaseduetotheadditional set-upofautomated UTequipment andsupporthoursneededtoperformthisexamination.
Attachment3toAEPsNRCs0969AABACKGROUNDINFORMATIONANDJUSTZPICATIONTOUSECODECASEN-509ASALTERNATIVERULESPORTHESELECTZONANDINSPECTIONOPCLASS1,2,and3INTEGRALLYWELDEDATTACHMENTSPORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL r
Thispositionisfurthersupported bythefollowing.
Attachment3toAEP:NRC:0969AAPage1System/ComponentforwhichreliefisrequestedClass1,2,and3integrallyweldedattachments.CodeRequirementsTableIWB-2500-1,examinationcategoriesB-HandB-K-1;tableIWC-2500-1,examinationcategoryC-C;andtableIWD-2500-1,examination'ategoriesD-A,D-B,andD-Cofthe1989editionofASMESectionXIcoderequiresurfaceorvolumetricexaminationforweldedattachmentsofvessels,piping,pumps,andvalves.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexaminationofintegrallyweldedattachmentstobebasedontherequirementsindicatedintablesIWB-2500-1throughIWD-2500-1.Frequencyandextentofexaminationareinaccordancewiththesetablesandtheinspectionprogramchosenbytheowner.TheproposedalternativemethodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-509providesselectioncriteriabasedonidentifieddeformationofthecomponentsupportmembersfoundintheplanteitherduringoperation,refueling,maintenance,examination,inserviceinspection,ortesting.ThecriteriastatedinCodeCaseN-509aremorereasonablethantherandomexaminationofallweldedattachmentsinthattheyfocustheexaminationandtheevaluationonthosecomponentsupportsandweldedattachmentsthataresusceptibletoearlyfailure.Significantpersonnelradiationexposureandcontaminationsavingsarepredictedtoresultfromtheimplementationoftheserequirements.CodeCaseN-509wasapprovedinNovember1992bytheASMESectionXIorganizationandprovidesanacceptablealternativetothecodemethodfortheexaminationofweldedattachmentsforvessels,piping,pumps,andvalves.IV.'lternativeMethodAsanalternativetotherequirementsofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexaminationofweldedattachmentsforvessels,piping,pumps,andvalvesinaccordancewithCodeCaseN-509.V.JustificationforgrantingcodereliefTheASMESectionXIcodeorganizationhasapprovedtheuseofCodeCaseN-509asanacceptablealternative,tothecoderequirementsfortheexaminationofweldedattachmentsforvessels,piping,pumps,andvalves.Componentsupportsareexaminedfrequentlyduringplantwalkdowns,bothwiththeunitsoperatingorduringplannedorunplannedoutages.Ifafailureordeformationofacomponentsupportisobservedduringthesewalkdowns,asurfaceexaminationoftheappropriateboundaryofthewelded Attachment3toAEP:NRC:0969AAPage2attachmentshallbeperformedinaccordancewithCodeCaseN-509.Thisexaminationstrategyismorereasonablethanthecodemethodofrandomexaminationofweldedattachmentsduetoitsfocusonhigherstressedcomponentsupportsthatwouldbemoresusceptibletofailureintheattachmentweld.Theuseoftheproposedalternativefortheinspectionandexaminationofweldedattachmentswillresultinsignificantlaboranddosesavingswhileprovidinganacceptablelevelofqualityandsafety.
CodeCaseN-521issuedbytheASMESectionXIorganization providesanacceptable alternative tothecodemethodfortheexamination ofthenozzletovesselandsafeendwelds,andinsideradiussections.
Attachment4toAEP:NRC:0969AABACKGROUNDINFORMATIONANDKJSTIFICATZONFORTHEUSEOFCODECASEN-524ASANALTERNATIVEFORTHEEXAMZHATIONREQUIREMENTSFORLONGITUDINALWELDSZNCLASS1AND2PIPINGFORCOOKNUCLEARPLANTUNITS1AND2THIRD10-YEARINTERVAL Attachment4toAEP:NRC:0969AAPage1IZ.System/ComponentforwhichreliefisrequestedClass1and2longitudinalweldsinpiping.CodeRequirementsTableIWB-2500-1,examinationcategoryB-J,itemsB9.12andB9.22,andtableIWC-2500-1,examinationcategoriesC-F-1andC-F-2ofASMESectionXIcode,1989editionwithnoaddenda,requirevolumetricand/orsurfaceexaminationfromtheintersectionoflongitudinalandcircumferentialweldsforadistanceofonepipediameterinlengthbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthepipewallthicknessforclass2welds.IIZ.BasisforcodereliefZV.The1989editionofASMESectionXIcoderequirestheexaminationoflongitudinalclass1and2pipingweldsbeinaccordancewiththerequirementsoftablesIWB-2500-1andIWC-2500-1.Thelengthofweldexaminedshallbeonepipediameterbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthewallthicknessforclass2welds.Class1and2longitudinalpipingweldsdoexistin~ariousCookNuclearPlantsystems.CodeCaseN-524providesanacceptablealternativethatexaminestheintersectionalareaofcircumferentialandlongitudinalwelds,whichistheareamostpronetofailure.ThispositionisfurthersupportedbytheapprovalofCodeCaseN-524bytheASMESectionXIorganizationasanacceptablealternativetothecodeexaminationofclass1and2longitudinalpipingwelds.AlternativeMethodV.Asanalternativetotherequirementsofthe1989editionoftheASMESectionXIcode,itisproposedtoexamineclass1and2longitudinalpipingweldsinaccordancewiththerequirementsstatedinASMECodeCaseN-524.JustificationforgrantingcodereliefCodeCaseN-524wasapprovedbytheASMESectionXIcodeorganizationfortheexaminationofclass1and2longitudinalpipeweldsasanalternatemethodtothecodeexamination.Thiscodecaseacceptsthecodeexaminationofthecircumferentialweldvolumeassufficientindeterminingtheintegrityoftheintersectionofcircumferentialandlongitudinalwelds.Theintersectionofthelongitudinalandcircumferentialweldsisexpectedtopossessthehighestresidualstressesofthecollectiveweldduetothemanufacturingprocessandtherefore,athoroughcodeexaminationofthecircumferentialweldvolumewouldbeadequateindeterminingtheintegrityofthisarea.Additionally,therehavebeennoreportedfailuresintheindustry,wherethefailurewasinitiatedoutsidetheintersectionareathatwouldbeexaminedduringtheultrasonictestingofthecircumferentialweld.
ThiscodereliefwasapprovedforusefortheV.C.SummerNuclearPlant,forthesecond10-yearinterval(reference 1).Alternative MethodAsanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformallthenozzletovessel,nozzletosafeendwelds,andinsideradiussectionexaminations inthethirdperiodofthethirdinterval.
Attachment4toAEP:NRC:0969AAPage2Theimplementationofthiscodecasewillsignificantlyreducelaborandradiationexposureduetodecreasedscaffoldinginstallationandinsulationremovalforvisualaccesstothelongitudinalwelds,.Theuseofthiscodecaseprovidesanacceptablealternativetothecurrentcodemethodofexaminingclass1and2longitudinalpipingweldswhileprovidinganacceptablelevelofqualityandsafety.
V.Justification forgrantingcodereliefCodeCaseN-521imposesthefollowing conditions thatmustbemetpriortoitsuse:
Attachment 1toAEP:NRC:0969AA Page2noinservice repairsorreplacements byweldinghavebeenperformed onthenozzletovesselandsafeendwelds,orinsideradiussection;thenozzletovesselandsafeendweldsandtheinsideradiussectionexamination volumeshallnotcontainflawsthatrequiresuccessive examinations inaccordance withZWA-2420(b);
andtheunitisnotinthefirst10-yearinterval.
CookNuclearPlanthasnotperformed inservice repairsorreplacements onthenozzletovesselandsafeendwelds,andinsideradiussections.
Flawshavenotbeenidentified intheexamination volumethatrequiresuccessive examinations andbothunits1and2areinthethird10-yearinterval; therefore, applicability ofthiscodecasehasbeenmet.Thedeferralofallexaminations tothethirdperiodofthethird10-yearintervalwillresultinreducedset-uphoursandpersonnel radiation exposurehoursduetoconsolidation ofmanpowerefforts(set-upandsupport)tothethirdperiodofthethird10-yearinterval.
Theexamination ofnozzletovesselweldsfromtheshellsidewasperformed forunits1and2inthethirdperiodofthesecond10-yearintervalduringthe1995and1996refueling outages.Examination ofnozzletovesselweldsfromtheboreinsidediameter(fourforunit1andtwoforunit2)wereperformed inthefirstperiodtomeetcoderequ'rements.
Thesecond10-yearintervalexamination oftheinsideradiussectionsandnozzletosafeendweldswasperformed inaccordance withtableZWA-2500-1 ofthecode(atleast25%butnotmorethan50%inthefirstperiodandthebalanceof100%inthethirdperiod).Fouroftheeightinsideradiussectionsandnozzletosafeendweldswereperformed inthethirdperiod(1995)ofthesecond10-yearintervalforunit1.Sixofeightinsideradiussectionsandnozzletosafeendweld'orunit2wereexaminedin1996.Becauseweperformed amajorityoftheexaminations inthethirdperiodofthesecond10-yearinterval, andtherewerenoflawsdetectedinanyoftheexaminations conducted inthefirstorsecondintervals, itisreasonable toconcludethatthedeferment ofalltheexaminations tothethirdperiodofthethird10-yearintervalwillnotcompromise thesafetyofplantpersonnel orequipment.
Thealternate testusingCodeCaseN-521eliminates thehardshipofperforming twoautomated examinations perinspection intervalwhileproviding anacceptable levelofqualityandsafetyforCookNuclearPlant.VZ.Reference Letter,F.J.HebdontoG.J.Taylor,"Evaluation ofReliefRequestsforRR-07andIWA-5242(a),
VirgilC.SummerNuclearStation(TACNos.M94363andM94364),"
datedApril11,1996.
Attachment 2toAEP:NRC:0969AA BACKGROUND INFORMATION ANDJUSTIFICATION TOUSECODECASEN-491-1ASANALTERNATIVE FORTHEZNSPECTZON OFCLASS1,2,3,ANDMCCOMPONENT SUPPORTSFORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL Attachment 2toAEP:NRC:0969AA Page1System/Component forwhich,reliefisrequested Class1,2,3,andMCcomponent supports.
CodeRequirements TableIWF-2500-1, examination categoryF-A,itemsF1.10throughF1.70ofthe1989editionofASMESectionXIcode,requiresvisualandVT-3examination ofclass1,2,and3'upports inaccordance withthescheduleestablished forcomponents underIWB,IWC,IWDandIWE.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexamination ofcomponent supportsbebasedonafrequency inaccordance withtheIWB,IWC,IWD,andIWEcomponents foreachinterval.
Theproposedal"ernative methodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-491-1providesaselection criteriabasedonapplyingareasonable percentage ofexaminations foreachclassofcomponent supports.
Significant personnel radiation exposureandcontamination savingsarepredicted toresultfromtheimplementation oftheserequirements comparedwiththerequirements statedinthe1989editionoftheASMESectionXIcode.IV.CodeCaseN-491-1wasapprovedbytheASMESectionXIorganization inApril1993,andprovidesanacceptable alternative tothecodemethodfortheexamination ofcomponent supports.
Alternative MethodV.Asanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexamination ofcomponent supportsinaccordance withtherequirements established inASMEapprovedCodeCaseN-491-1.Justification forgrantingcodereliefTheASMESectionXIcodeorganization hasapprovedtheuseofCodeCaseN-491-1asanacceptable alternative'o thecoderequirements fortheexamination ofcomponent supports.
Pipingsystemsareexaminedfrequently duringplantwalkdowns withthyunitsoperating orduringplannedorunplanned outages.Ifthefailureordegradation ofasupportisobservedduringthesewalkdowns, whethertheyareformalvisual/VT-3 examinations orinformalobservations, promptactionistakenincluding theevaluation, repair,and/orreplacement of"supports.
Theuseoftheproposedalternative fortheinspection andexamination ofcomponent supportswillresultinsignificant laboranddosesavingswhileproviding anacceptable levelofqualityandsafety.
Attachment 3toAEPsNRCs0969AA BACKGROUND INFORMATION ANDJUSTZPICATION TOUSECODECASEN-509ASALTERNATIVE RULESPORTHESELECTZON ANDINSPECTION OPCLASS1,2,and3INTEGRALLY WELDEDATTACHMENTS PORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL r
Attachment 3toAEP:NRC:0969AA Page1System/Component forwhichreliefisrequested Class1,2,and3integrally weldedattachments.
CodeRequirements TableIWB-2500-1, examination categories B-HandB-K-1;tableIWC-2500-1, examination categoryC-C;andtableIWD-2500-1, examination'ategories D-A,D-B,andD-Cofthe1989editionofASMESectionXIcoderequiresurfaceorvolumetric examination forweldedattachments ofvessels,piping,pumps,andvalves.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexamination ofintegrally weldedattachments tobebasedontherequirements indicated intablesIWB-2500-1 throughIWD-2500-1.Frequency andextentofexamination areinaccordance withthesetablesandtheinspection programchosenbytheowner.Theproposedalternative methodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-509providesselection criteriabasedonidentified deformation ofthecomponent supportmembersfoundintheplanteitherduringoperation, refueling, maintenance, examination, inservice inspection, ortesting.ThecriteriastatedinCodeCaseN-509aremorereasonable thantherandomexamination ofallweldedattachments inthattheyfocustheexamination andtheevaluation onthosecomponent supportsandweldedattachments thataresusceptible toearlyfailure.Significant personnel radiation exposureandcontamination savingsarepredicted toresultfromtheimplementation oftheserequirements.
CodeCaseN-509wasapprovedinNovember1992bytheASMESectionXIorganization andprovidesanacceptable alternative tothecodemethodfortheexamination ofweldedattachments forvessels,piping,pumps,andvalves.IV.'lternative MethodAsanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexamination ofweldedattachments forvessels,piping,pumps,andvalvesinaccordance withCodeCaseN-509.V.Justification forgrantingcodereliefTheASMESectionXIcodeorganization hasapprovedtheuseofCodeCaseN-509asanacceptable alternative,to thecoderequirements fortheexamination ofweldedattachments forvessels,piping,pumps,andvalves.Component supportsareexaminedfrequently duringplantwalkdowns, bothwiththeunitsoperating orduringplannedorunplanned outages.Ifafailureordeformation ofacomponent supportisobservedduringthesewalkdowns, asurfaceexamination oftheappropriate boundaryofthewelded Attachment 3toAEP:NRC:0969AA Page2attachment shallbeperformed inaccordance withCodeCaseN-509.Thisexamination strategyismorereasonable thanthecodemethodofrandomexamination ofweldedattachments duetoitsfocusonhigherstressedcomponent supportsthatwouldbemoresusceptible tofailureintheattachment weld.Theuseoftheproposedalternative fortheinspection andexamination ofweldedattachments willresultinsignificant laboranddosesavingswhileproviding anacceptable levelofqualityandsafety.
Attachment 4toAEP:NRC:0969AA BACKGROUND INFORMATION ANDKJSTIFICATZON FORTHEUSEOFCODECASEN-524ASANALTERNATIVE FORTHEEXAMZHATION REQUIREMENTS FORLONGITUDINAL WELDSZNCLASS1AND2PIPINGFORCOOKNUCLEARPLANTUNITS1AND2THIRD10-YEARINTERVAL Attachment 4toAEP:NRC:0969AA Page1IZ.System/Component forwhichreliefisrequested Class1and2longitudinal weldsinpiping.CodeRequirements TableIWB-2500-1, examination categoryB-J,itemsB9.12andB9.22,andtableIWC-2500-1, examination categories C-F-1andC-F-2ofASMESectionXIcode,1989editionwithnoaddenda,requirevolumetric and/orsurfaceexamination fromtheintersection oflongitudinal andcircumferential weldsforadistanceofonepipediameterinlengthbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthepipewallthickness forclass2welds.IIZ.BasisforcodereliefZV.The1989editionofASMESectionXIcoderequirestheexamination oflongitudinal class1and2pipingweldsbeinaccordance withtherequirements oftablesIWB-2500-1 andIWC-2500-1.
Thelengthofweldexaminedshallbeonepipediameterbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthewallthickness forclass2welds.Class1and2longitudinal pipingweldsdoexistin~ariousCookNuclearPlantsystems.CodeCaseN-524providesanacceptable alternative thatexaminestheintersectional areaofcircumferential andlongitudinal welds,whichistheareamostpronetofailure.Thispositionisfurthersupported bytheapprovalofCodeCaseN-524bytheASMESectionXIorganization asanacceptable alternative tothecodeexamination ofclass1and2longitudinal pipingwelds.Alternative MethodV.Asanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoexamineclass1and2longitudinal pipingweldsinaccordance withtherequirements statedinASMECodeCaseN-524.Justification forgrantingcodereliefCodeCaseN-524wasapprovedbytheASMESectionXIcodeorganization fortheexamination ofclass1and2longitudinal pipeweldsasanalternate methodtothecodeexamination.
Thiscodecaseacceptsthecodeexamination ofthecircumferential weldvolumeassufficient indetermining theintegrity oftheintersection ofcircumferential andlongitudinal welds.Theintersection ofthelongitudinal andcircumferential weldsisexpectedtopossessthehighestresidualstressesofthecollective weldduetothemanufacturing processandtherefore, athoroughcodeexamination ofthecircumferential weldvolumewouldbeadequateindetermining theintegrity ofthisarea.Additionally, therehavebeennoreportedfailuresintheindustry, wherethefailurewasinitiated outsidetheintersection areathatwouldbeexaminedduringtheultrasonic testingofthecircumferential weld.
Attachment 4toAEP:NRC:0969AA Page2Theimplementation ofthiscodecasewillsignificantly reducelaborandradiation exposureduetodecreased scaffolding installation andinsulation removalforvisualaccesstothelongitudinal welds,.Theuseofthiscodecaseprovidesanacceptable alternative tothecurrentcodemethodofexamining class1and2longitudinal pipingweldswhileproviding anacceptable levelofqualityandsafety.
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Revision as of 07:51, 29 June 2018

Forwards RAI Re Requests for Relief from Code Cases N-521, N-491,N-509 & N-524
ML17333A636
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 11/07/1996
From: FITZPATRICK E
AMERICAN ELECTRIC POWER CO., INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0969AA, AEP:NRC:969AA, TAC-M94871, TAC-M94872, NUDOCS 9611150063
Download: ML17333A636 (17)
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Text

1~hrCATEGORYj.REGULATCINFORMATION DISTRIBUTIONSTEM (RIDE)ACCESSION NBR:9611150063 DOC.DATE:

96/11/07NOTARIZED:

NOFACIL:50-315 Donald.C.CookNuclearPowerPlant,Unit1,indianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E AmericanElectricPowerCo.,Inc.RECIP.NAME RECIPIENT AFFILIATION Document.ControlBranch(Document ControlDesk)DOCKET0500031505000316

SUBJECT:

ForwardsRAIrerequestsforrelieftoCodeCasesN-521,N-491,N-509 6N-524.rDISTRIBUTION CODE:A047DCOPIESRECEIVED'LTR LENCLSIZE:IITITLE:ORSubmittal:

lnservice/Testing/Relief fromASMCode-GL-9-04NOTES:TERECIPIENT IDCODE/NAME PD3-3LAHICKMANFJ INTERNAL:

AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS2RES/DSIR/EIB COPIESLTTRENCL1111-11111011RECIPIENT IDCODE/NAME PD3-3PDECENTER1NUDOCS-ATRACTRES/DET/EMMEB COPIESLTTRENCL111111110EXTERNAL:

LITCOANDERSONNRCPDR11NOAC1111D0ENNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:

LTTR13ENCL12 AmericanElectricP~erNuclearGeneration+p 500CircleDriveBuchanan, MI491071395 November7,1996DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:

ANMICINtFI.KCfRIC POWMAEP:NRC:0969AA DonaldC.CookNuclearPlantUnits1and2THIRD10-YEARINTBRVALINSERVICE INSPECTION PROGRAMANDASSOCIATED REQUESTSFORRELIEF(TACNOS.M94871ANDM94872)REQUESTFORADDITIONAL INFORMATION References LetterAEP:NRC:0969AW, E.E.Fitzpatri,ck toU.S.NRC,"DonaldC.CookNuclearPlantUnits1and2,THIRD10-YEARINTERVALINSERVICB INSPECTION PROGRAMANDASSOCIATED REQUESTSFORRELIEF(TACNOS.M94871ANDM94872),REQUESTFORADDITIONAL INFORMATION" dated,September 10,1996.2.Letter,C.A.Carpenter toE.E.Fitzpatrick, "D.C.COOK,UNITS1AND2,REQUESTING APPROVALOFCODECASEN-498-1ASANALTERNATIVE TOTHBREQUIREDHYDROSTATIC PRESSURETEST(TACNOS.M91783ANDM91784)",

datedJuly5,1995.Thethird10-yearinservice inspection planforCookNuclearPlantutilizescodecasesthathavenotbeenincorporated intoRegulatory Guide1.147.Becauseofthis,NRCapprovaloftheuseofthesecodecasesasalternatives totheASMESectionXIrequirements isrequired, Theparticular codecasesforwhichapprovalisrequiredwereidentified inourSeptember 10,1996,letter(reference 1).Theattachments tothisletterprovidereliefrequeststhatwouldallowCookNuclearPlanttouseCodeCasesN-521,N-491-1,N-509,andN-524asalternatives totherequirements ofthe1989editionofASMECodeSectionXI.PleasenotethatalthoughCodeCaseN-498-1wasidentified inreference 1,thisletterdoesnotcontainareliefrequestforuseofthiscodecasebecausewepreviously obtainedapprovalforitsuse(reference 2).ApprovaloftheserequestsisrequiredbyJuly1,1997.E.E.Fitzpatrick VicePresident Attachments h9'6ii150063 961107~i.PDR).ADOCK050003i5:

6'~POREli U.S.NuclearRegulatory Commission Page2AEP:NRC:0969AA cc:A.A.BlindA.B.BeachMDEQ-DW&RPDNRCResidentInspector J.R.Padgett Attachment 1toAEP:NRC:0969AA BACKGROUND INPORMATION ANDJUSTIFICATION TOUSECODECASEN-521ASANALTERNATIVE PORTHEEXAMINATION OPNOZZLETOVESSELANDSAFEENDWELDSANDINSIDERADIUSSECTIONSPORTHECOOKNUCLEARPLANTUNITS1and2THIRD10"YEARINTERVAL

Attachment-1toAEP:NRC:0969AA Page1System/Component forwhichreliefisrequested Nozzletovesselwelds,nozzleinsideradiussections, and'nozzletosafeendweldsforCookNuclearPlant,units1and2.lZ.CodeRequirements Examination categories B-DandB-F,itemsB3.90andB3.100ofASMESectionXIcode,1989editionwithnoaddenda,require100~volumetric examination perIWA-2500-7 ofatleast25~butnotmorethan50%ofreactorvesselnozzletovesselweldsandnozzleinsideradiussectionsbytheendofthefirstperiod.Examination categoryB-F,item5.10requires100%surfaceandvolumetric examination perfigureIWB-2500-8 ofdissimilar metalnozzletosafeendweldsthatmaybeexaminedcoincident withthevesselnozzleexaminations.

ZZI.BasisforcodereliefTheASMESectionXIcoderequirements fortheexamination ofreactorpressurevesselnozzletovesselwelds,thenozzleinsideradiussections, andnozzletosafeendweldsstipulate adistribution oftheseexaminations inatleasttwoofthethreeperiods.Thesamesequenceestablished inthefirst10-yearintervalmustbeusedforsuccessive 10-yearintervals.

Theimplementation ofthesecoderequirements wouldresultinanadditional set-upoftheautomated ultrasonic (UT)equipment usedtoexaminethenozzletovesselwelds,insideradiussections, andnozzletosafeendwelds.Additionally, personnel radiation exposurewouldincreaseduetotheadditional set-upofautomated UTequipment andsupporthoursneededtoperformthisexamination.

Thispositionisfurthersupported bythefollowing.

CodeCaseN-521issuedbytheASMESectionXIorganization providesanacceptable alternative tothecodemethodfortheexamination ofthenozzletovesselandsafeendwelds,andinsideradiussections.

ThiscodereliefwasapprovedforusefortheV.C.SummerNuclearPlant,forthesecond10-yearinterval(reference 1).Alternative MethodAsanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformallthenozzletovessel,nozzletosafeendwelds,andinsideradiussectionexaminations inthethirdperiodofthethirdinterval.

V.Justification forgrantingcodereliefCodeCaseN-521imposesthefollowing conditions thatmustbemetpriortoitsuse:

Attachment 1toAEP:NRC:0969AA Page2noinservice repairsorreplacements byweldinghavebeenperformed onthenozzletovesselandsafeendwelds,orinsideradiussection;thenozzletovesselandsafeendweldsandtheinsideradiussectionexamination volumeshallnotcontainflawsthatrequiresuccessive examinations inaccordance withZWA-2420(b);

andtheunitisnotinthefirst10-yearinterval.

CookNuclearPlanthasnotperformed inservice repairsorreplacements onthenozzletovesselandsafeendwelds,andinsideradiussections.

Flawshavenotbeenidentified intheexamination volumethatrequiresuccessive examinations andbothunits1and2areinthethird10-yearinterval; therefore, applicability ofthiscodecasehasbeenmet.Thedeferralofallexaminations tothethirdperiodofthethird10-yearintervalwillresultinreducedset-uphoursandpersonnel radiation exposurehoursduetoconsolidation ofmanpowerefforts(set-upandsupport)tothethirdperiodofthethird10-yearinterval.

Theexamination ofnozzletovesselweldsfromtheshellsidewasperformed forunits1and2inthethirdperiodofthesecond10-yearintervalduringthe1995and1996refueling outages.Examination ofnozzletovesselweldsfromtheboreinsidediameter(fourforunit1andtwoforunit2)wereperformed inthefirstperiodtomeetcoderequ'rements.

Thesecond10-yearintervalexamination oftheinsideradiussectionsandnozzletosafeendweldswasperformed inaccordance withtableZWA-2500-1 ofthecode(atleast25%butnotmorethan50%inthefirstperiodandthebalanceof100%inthethirdperiod).Fouroftheeightinsideradiussectionsandnozzletosafeendweldswereperformed inthethirdperiod(1995)ofthesecond10-yearintervalforunit1.Sixofeightinsideradiussectionsandnozzletosafeendweld'orunit2wereexaminedin1996.Becauseweperformed amajorityoftheexaminations inthethirdperiodofthesecond10-yearinterval, andtherewerenoflawsdetectedinanyoftheexaminations conducted inthefirstorsecondintervals, itisreasonable toconcludethatthedeferment ofalltheexaminations tothethirdperiodofthethird10-yearintervalwillnotcompromise thesafetyofplantpersonnel orequipment.

Thealternate testusingCodeCaseN-521eliminates thehardshipofperforming twoautomated examinations perinspection intervalwhileproviding anacceptable levelofqualityandsafetyforCookNuclearPlant.VZ.Reference Letter,F.J.HebdontoG.J.Taylor,"Evaluation ofReliefRequestsforRR-07andIWA-5242(a),

VirgilC.SummerNuclearStation(TACNos.M94363andM94364),"

datedApril11,1996.

Attachment 2toAEP:NRC:0969AA BACKGROUND INFORMATION ANDJUSTIFICATION TOUSECODECASEN-491-1ASANALTERNATIVE FORTHEZNSPECTZON OFCLASS1,2,3,ANDMCCOMPONENT SUPPORTSFORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL Attachment 2toAEP:NRC:0969AA Page1System/Component forwhich,reliefisrequested Class1,2,3,andMCcomponent supports.

CodeRequirements TableIWF-2500-1, examination categoryF-A,itemsF1.10throughF1.70ofthe1989editionofASMESectionXIcode,requiresvisualandVT-3examination ofclass1,2,and3'upports inaccordance withthescheduleestablished forcomponents underIWB,IWC,IWDandIWE.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexamination ofcomponent supportsbebasedonafrequency inaccordance withtheIWB,IWC,IWD,andIWEcomponents foreachinterval.

Theproposedal"ernative methodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-491-1providesaselection criteriabasedonapplyingareasonable percentage ofexaminations foreachclassofcomponent supports.

Significant personnel radiation exposureandcontamination savingsarepredicted toresultfromtheimplementation oftheserequirements comparedwiththerequirements statedinthe1989editionoftheASMESectionXIcode.IV.CodeCaseN-491-1wasapprovedbytheASMESectionXIorganization inApril1993,andprovidesanacceptable alternative tothecodemethodfortheexamination ofcomponent supports.

Alternative MethodV.Asanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexamination ofcomponent supportsinaccordance withtherequirements established inASMEapprovedCodeCaseN-491-1.Justification forgrantingcodereliefTheASMESectionXIcodeorganization hasapprovedtheuseofCodeCaseN-491-1asanacceptable alternative'o thecoderequirements fortheexamination ofcomponent supports.

Pipingsystemsareexaminedfrequently duringplantwalkdowns withthyunitsoperating orduringplannedorunplanned outages.Ifthefailureordegradation ofasupportisobservedduringthesewalkdowns, whethertheyareformalvisual/VT-3 examinations orinformalobservations, promptactionistakenincluding theevaluation, repair,and/orreplacement of"supports.

Theuseoftheproposedalternative fortheinspection andexamination ofcomponent supportswillresultinsignificant laboranddosesavingswhileproviding anacceptable levelofqualityandsafety.

Attachment 3toAEPsNRCs0969AA BACKGROUND INFORMATION ANDJUSTZPICATION TOUSECODECASEN-509ASALTERNATIVE RULESPORTHESELECTZON ANDINSPECTION OPCLASS1,2,and3INTEGRALLY WELDEDATTACHMENTS PORCOOKNUCLEARPLANTUNITS1and2THIRD10-YEARINTERVAL r

Attachment 3toAEP:NRC:0969AA Page1System/Component forwhichreliefisrequested Class1,2,and3integrally weldedattachments.

CodeRequirements TableIWB-2500-1, examination categories B-HandB-K-1;tableIWC-2500-1, examination categoryC-C;andtableIWD-2500-1, examination'ategories D-A,D-B,andD-Cofthe1989editionofASMESectionXIcoderequiresurfaceorvolumetric examination forweldedattachments ofvessels,piping,pumps,andvalves.III.BasisforcodereliefThe1989editionoftheASMESectionXIcoderequirestheexamination ofintegrally weldedattachments tobebasedontherequirements indicated intablesIWB-2500-1 throughIWD-2500-1.Frequency andextentofexamination areinaccordance withthesetablesandtheinspection programchosenbytheowner.Theproposedalternative methodtobeusedbyCookNuclearPlantandoutlinedinASMECodeCaseN-509providesselection criteriabasedonidentified deformation ofthecomponent supportmembersfoundintheplanteitherduringoperation, refueling, maintenance, examination, inservice inspection, ortesting.ThecriteriastatedinCodeCaseN-509aremorereasonable thantherandomexamination ofallweldedattachments inthattheyfocustheexamination andtheevaluation onthosecomponent supportsandweldedattachments thataresusceptible toearlyfailure.Significant personnel radiation exposureandcontamination savingsarepredicted toresultfromtheimplementation oftheserequirements.

CodeCaseN-509wasapprovedinNovember1992bytheASMESectionXIorganization andprovidesanacceptable alternative tothecodemethodfortheexamination ofweldedattachments forvessels,piping,pumps,andvalves.IV.'lternative MethodAsanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoperformexamination ofweldedattachments forvessels,piping,pumps,andvalvesinaccordance withCodeCaseN-509.V.Justification forgrantingcodereliefTheASMESectionXIcodeorganization hasapprovedtheuseofCodeCaseN-509asanacceptable alternative,to thecoderequirements fortheexamination ofweldedattachments forvessels,piping,pumps,andvalves.Component supportsareexaminedfrequently duringplantwalkdowns, bothwiththeunitsoperating orduringplannedorunplanned outages.Ifafailureordeformation ofacomponent supportisobservedduringthesewalkdowns, asurfaceexamination oftheappropriate boundaryofthewelded Attachment 3toAEP:NRC:0969AA Page2attachment shallbeperformed inaccordance withCodeCaseN-509.Thisexamination strategyismorereasonable thanthecodemethodofrandomexamination ofweldedattachments duetoitsfocusonhigherstressedcomponent supportsthatwouldbemoresusceptible tofailureintheattachment weld.Theuseoftheproposedalternative fortheinspection andexamination ofweldedattachments willresultinsignificant laboranddosesavingswhileproviding anacceptable levelofqualityandsafety.

Attachment 4toAEP:NRC:0969AA BACKGROUND INFORMATION ANDKJSTIFICATZON FORTHEUSEOFCODECASEN-524ASANALTERNATIVE FORTHEEXAMZHATION REQUIREMENTS FORLONGITUDINAL WELDSZNCLASS1AND2PIPINGFORCOOKNUCLEARPLANTUNITS1AND2THIRD10-YEARINTERVAL Attachment 4toAEP:NRC:0969AA Page1IZ.System/Component forwhichreliefisrequested Class1and2longitudinal weldsinpiping.CodeRequirements TableIWB-2500-1, examination categoryB-J,itemsB9.12andB9.22,andtableIWC-2500-1, examination categories C-F-1andC-F-2ofASMESectionXIcode,1989editionwithnoaddenda,requirevolumetric and/orsurfaceexamination fromtheintersection oflongitudinal andcircumferential weldsforadistanceofonepipediameterinlengthbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthepipewallthickness forclass2welds.IIZ.BasisforcodereliefZV.The1989editionofASMESectionXIcoderequirestheexamination oflongitudinal class1and2pipingweldsbeinaccordance withtherequirements oftablesIWB-2500-1 andIWC-2500-1.

Thelengthofweldexaminedshallbeonepipediameterbutnogreaterthanonefootmaximumforclass1weldsandtwoandone-halftimesthewallthickness forclass2welds.Class1and2longitudinal pipingweldsdoexistin~ariousCookNuclearPlantsystems.CodeCaseN-524providesanacceptable alternative thatexaminestheintersectional areaofcircumferential andlongitudinal welds,whichistheareamostpronetofailure.Thispositionisfurthersupported bytheapprovalofCodeCaseN-524bytheASMESectionXIorganization asanacceptable alternative tothecodeexamination ofclass1and2longitudinal pipingwelds.Alternative MethodV.Asanalternative totherequirements ofthe1989editionoftheASMESectionXIcode,itisproposedtoexamineclass1and2longitudinal pipingweldsinaccordance withtherequirements statedinASMECodeCaseN-524.Justification forgrantingcodereliefCodeCaseN-524wasapprovedbytheASMESectionXIcodeorganization fortheexamination ofclass1and2longitudinal pipeweldsasanalternate methodtothecodeexamination.

Thiscodecaseacceptsthecodeexamination ofthecircumferential weldvolumeassufficient indetermining theintegrity oftheintersection ofcircumferential andlongitudinal welds.Theintersection ofthelongitudinal andcircumferential weldsisexpectedtopossessthehighestresidualstressesofthecollective weldduetothemanufacturing processandtherefore, athoroughcodeexamination ofthecircumferential weldvolumewouldbeadequateindetermining theintegrity ofthisarea.Additionally, therehavebeennoreportedfailuresintheindustry, wherethefailurewasinitiated outsidetheintersection areathatwouldbeexaminedduringtheultrasonic testingofthecircumferential weld.

Attachment 4toAEP:NRC:0969AA Page2Theimplementation ofthiscodecasewillsignificantly reducelaborandradiation exposureduetodecreased scaffolding installation andinsulation removalforvisualaccesstothelongitudinal welds,.Theuseofthiscodecaseprovidesanacceptable alternative tothecurrentcodemethodofexamining class1and2longitudinal pipingweldswhileproviding anacceptable levelofqualityandsafety.

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