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{{#Wiki_filter:1~hrCATEGORYj. | {{#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- | 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: | 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. | |||
e'd}} | e'd}} | ||
Revision as of 06:51, 29 June 2018
| ML17333A636 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| 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) | |
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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