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{{#Wiki_filter: | {{#Wiki_filter:ACCELERATED DI.TPJBUTION DEMONSTATIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9403040281 DOC.DATE: | ||
94/02/22NOTARIZED: | |||
YESDOCKETFACIL:50-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E. | |||
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application foramendtolicenseDPR-74,revising 3/4.4.9.1 reheatup&cooldowncurvestoreflectrecentreactorvesselmatlsurveillance capsulereanalysis,per direction ofRegGuide1.99,Rev2.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | |||
GeneralDistribution NOTESRECXPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL: | |||
NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNAL: | |||
NRCPDRCOPIESLTTRENCL1122111111111011RECIPXENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPWNRR/DSSA/SRXB 08/LFJ7CB REGFXLE01NSXCCOPIESLTTRENCL11111111101111DDRDNOTETOALL"RIDS"RECIPIENTS: | |||
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: | |||
LTTR16ENCL14DD tIIkCCl nC'IindianaMichigan~PowerCompanyP.O.Box16631Columbus, OH43216AEP:NRC:0894U DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICAL SPECIFICATION AMENDMENT REQUESTTOUPDATETHEUNIT2HEATUPANDCOOLDOWNCURVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyFebruary22,1994 | |||
==DearDr.Murley:== | ==DearDr.Murley:== | ||
Thisletteranditsattachments constitute anapplication foramendment toTechnical Specification 3/4.4.9.1 forDonaldC.CookNuclearPlantUnit2.Specifically, werequestthattheplantheatupandcooldowncurvesbechangedtoreflecttherecentreactorvesselmaterialsurveillance capsulereanalyses whichwasperformed byWestinghouse ElectricCorporation perthedirection providedinRegulatory Guide(R/G)1.99,Rev.2.Thereasonsfortheproposedchangeandourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92(c), | |||
arecontained inAttachment 1tothisletter.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Theresultsofthecapsulereanalyses (WCAP-13515), | |||
performed byWestinghouse, weresubmitted inourletterdatedMarch12,1993,underAEP:NRC:0894T, ReactorVesselMaterialSurveillance Reports.Thisreportwasusedtogeneratetheheatupandcooldowncurvesfor15EFPY.Thesecurvesarebeingsubmitted inthislettertoreviseFigures3.4-2and3.4-3ofTechnical Specification 3/4.4.9.1, PressureandTemperature LimitsfortheReactorCoolantSystem.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant L-.-'P40304028i 940222PDR4DOCK05000316P Dr.T.E.Murley-2-AEP:NRC:0894U increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | |||
TherevisedheatupandcooldowncurvesinAttachment 3havebeenevaluated againstandreflectthecriteriaof10CFR50,AppendixG,Paragraph IV.A.2.TheimpactofthisT/SchangerequestonourLTOPsetpointhasbeenevaluated, andthecurrentLTOPsetpointwasnotrevisedasitisvalidupto15EFPY.Toimplement therevisedheatupandcooldownlimitsinanorderlyfashion,weareproposing toinstitute thesenewheatupandcooldownlimitsduringtherefueling window(Mode6)oftheupcomingCycle9-10refueling outage,priortotheunitreturning toMode5.Wepresently anticipate theoutagetobeginasearlyasAugust5,1994;therefore, werequestthatyourreviewofthesechangesbecompleted bySeptember 4,1994.TheproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee. | |||
Incompliance withtherequirements of10CFR50.91(b)(1), | |||
copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.PadgettoftheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached. | |||
Sincerely, E.EDFitztrickVicePresident cadAttachments cc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector | |||
-BridgmanJ.R.Padgett STATEOFOHIO)COUNTYOFFRANKLIN) | |||
E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification Amendment'equest toUpdatetheUnit2HeatupandCooldownCurves,andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~~dayof,19NOTARPUBLICRITAD.HILLNOTARYPUBLIC.STATEOfOHIO Attachment 1toAEP:NRC:0894U 10CFR50.92 DETERMINATION FORPROPOSEDCHANGESTOTHEDONALDCCOOKNUCLEARPLANTUNIT2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:0894U Page11.0SECTIONSCHANGEDUnit2Technical Specification (T/S)3.4.9.1Figure3.4-2,ReactorCoolantSystemHeatupLimitations, andFigure3.4-3,ReactorCoolantSystemCooldownLimitations arebeingchanged.Also,thebasesforTechnical Specification 3/4.4.9arebeingupdatedtoreflecttheanalysesperformed byWestinghouse, andtheextendedtimeframeof15EFPY.2.0EXTENTOFCHANGESWeareproposing tochangetheheatupandcooldowncurvesshowninFigures3.4-2,and3.4-3,aswellasthebasesforthosespecifications, toreflectanextendedtimeframeof15EFPY.3'CHANGESREUESTEDTheT/SchangesfoundinAttachments 2and3arebasedonimplementation ofR/G1.'99,Revision2.Thefollowing Unit2T/Spagesareimpactedbythischange:Page3/44-25Page3/44-26PageB3/44-6PageB3/44-104.0DISCUSSION Paes344-25and344-26Figures3.4-2and3.4-3aretheheatupandcooldown(P-T)limitcurvesforUnit2.Thesecomposite curvesreflecttheadjustedreference temperature ofthemostlimitingmaterialattheendof15EFPY,andarebasedonthefollowing considerations. | |||
Intermediate shellplate, C5556-2,isthelimitingmaterialasdetermined byposition1ofR/G1.99,Revision2,withaCuandNicontentof0.15%and0.57%,respectively. | |||
2~Thefluencevaluescontained inTable6-14ofWestinghouse WCAP-13515, "Analysis ofCapsuleUfromIndianaMichiganPowerCompany,CookNuclearPlantUnit2ReactorVesselRadiation Surveillance Program", | |||
datedFebruary1993.Thisreportwassubmitted asanattachment toletterAEP:NRC:0894T, datedMarch12,1993. | |||
Attachment 1toAEP:NRC:0894U Page2PaesB344-6andB344-10ThePressure-Temperature basesareproposedtobemodifiedtoreflecttheUnit2CapsuleUAnalysis, aspresented inWestinghouse WCAP-13515. | |||
==5.0 NOSIGNIFICANT== | |||
HAZARDSDETERMINATION Wehaveevaluated theproposedT/Ss,andhavedetermined thatitshouldnotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c). | |||
Operation oftheCookNuclearPlantinaccordance withtheproposedamendment willnot:(1)Involveasinificantincreaseintherobabilit orconseencesofanaccidentreviouslevaluated. | |||
TheproposedchangestotheP-TcurvesarebeingupdatedasaresultoftheUnit2CapsuleUanalysis, WCAP-13515. | |||
Theanalysiswasrequiredpertheremovalscheduleestablished inTable4.4-5oftheCookNuclearPlantTechnical Specifications. | |||
Theanalysiswasperformed basedonguidancefromR/G1.99,Revision2.Thechangeonlyinvolvesarevisedtimeframeformaterialqualification from12EFPYto15EFPYassupported bytheaforementioned Westinghouse analysis. | |||
Therefore, weconcludethatthechangeswillnotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated | |||
: accident, norwillthechangesinvolveasignificant reduction inamarginofsafety.(2)Createtheossibilit ofanewordifferent kindofaccidentfromanreviouslanalzed.Theproposedchangesdonotinvolveanyphysicalmodifications totheplant.Therefore, thechangesshouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously analyzedorevaluated. | |||
Attachment 1toAEP:NRC:0894U Page3(3)Involveasinificantreduction inamarinofsafetSeetheresponseto(1)above.6.0PENDINGTSsPROPOSALS IMPACTING THISSUBMITTAL Therearecurrently nootherT/Ssproposals underreviewthatwouldimpactthissubmittal. | |||
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Revision as of 08:13, 29 June 2018
| ML17331B274 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/22/1994 |
| From: | FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17331B276 | List: |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 AEP:NRC:0894U, AEP:NRC:894U, NUDOCS 9403040281 | |
| Download: ML17331B274 (12) | |
Text
ACCELERATED DI.TPJBUTION DEMONSTATIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9403040281 DOC.DATE:
94/02/22NOTARIZED:
YESDOCKETFACIL:50-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
Application foramendtolicenseDPR-74,revising 3/4.4.9.1 reheatup&cooldowncurvestoreflectrecentreactorvesselmatlsurveillance capsulereanalysis,per direction ofRegGuide1.99,Rev2.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution NOTESRECXPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNAL:
NRCPDRCOPIESLTTRENCL1122111111111011RECIPXENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPWNRR/DSSA/SRXB 08/LFJ7CB REGFXLE01NSXCCOPIESLTTRENCL11111111101111DDRDNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR16ENCL14DD tIIkCCl nC'IindianaMichigan~PowerCompanyP.O.Box16631Columbus, OH43216AEP:NRC:0894U DonaldC.CookNuclearPlantUnit2DocketNo.50-316LicenseNo.DPR-74TECHNICAL SPECIFICATION AMENDMENT REQUESTTOUPDATETHEUNIT2HEATUPANDCOOLDOWNCURVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyFebruary22,1994
DearDr.Murley:
Thisletteranditsattachments constitute anapplication foramendment toTechnical Specification 3/4.4.9.1 forDonaldC.CookNuclearPlantUnit2.Specifically, werequestthattheplantheatupandcooldowncurvesbechangedtoreflecttherecentreactorvesselmaterialsurveillance capsulereanalyses whichwasperformed byWestinghouse ElectricCorporation perthedirection providedinRegulatory Guide(R/G)1.99,Rev.2.Thereasonsfortheproposedchangeandourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92(c),
arecontained inAttachment 1tothisletter.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Theresultsofthecapsulereanalyses (WCAP-13515),
performed byWestinghouse, weresubmitted inourletterdatedMarch12,1993,underAEP:NRC:0894T, ReactorVesselMaterialSurveillance Reports.Thisreportwasusedtogeneratetheheatupandcooldowncurvesfor15EFPY.Thesecurvesarebeingsubmitted inthislettertoreviseFigures3.4-2and3.4-3ofTechnical Specification 3/4.4.9.1, PressureandTemperature LimitsfortheReactorCoolantSystem.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant L-.-'P40304028i 940222PDR4DOCK05000316P Dr.T.E.Murley-2-AEP:NRC:0894U increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TherevisedheatupandcooldowncurvesinAttachment 3havebeenevaluated againstandreflectthecriteriaof10CFR50,AppendixG,Paragraph IV.A.2.TheimpactofthisT/SchangerequestonourLTOPsetpointhasbeenevaluated, andthecurrentLTOPsetpointwasnotrevisedasitisvalidupto15EFPY.Toimplement therevisedheatupandcooldownlimitsinanorderlyfashion,weareproposing toinstitute thesenewheatupandcooldownlimitsduringtherefueling window(Mode6)oftheupcomingCycle9-10refueling outage,priortotheunitreturning toMode5.Wepresently anticipate theoutagetobeginasearlyasAugust5,1994;therefore, werequestthatyourreviewofthesechangesbecompleted bySeptember 4,1994.TheproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee.
Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.PadgettoftheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached.
Sincerely, E.EDFitztrickVicePresident cadAttachments cc:A.A.Blind-BridgmanG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett STATEOFOHIO)COUNTYOFFRANKLIN)
E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification Amendment'equest toUpdatetheUnit2HeatupandCooldownCurves,andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~~dayof,19NOTARPUBLICRITAD.HILLNOTARYPUBLIC.STATEOfOHIO Attachment 1toAEP:NRC:0894U 10CFR50.92 DETERMINATION FORPROPOSEDCHANGESTOTHEDONALDCCOOKNUCLEARPLANTUNIT2TECHNICAL SPECIFICATIONS Attachment 1toAEP:NRC:0894U Page11.0SECTIONSCHANGEDUnit2Technical Specification (T/S)3.4.9.1Figure3.4-2,ReactorCoolantSystemHeatupLimitations, andFigure3.4-3,ReactorCoolantSystemCooldownLimitations arebeingchanged.Also,thebasesforTechnical Specification 3/4.4.9arebeingupdatedtoreflecttheanalysesperformed byWestinghouse, andtheextendedtimeframeof15EFPY.2.0EXTENTOFCHANGESWeareproposing tochangetheheatupandcooldowncurvesshowninFigures3.4-2,and3.4-3,aswellasthebasesforthosespecifications, toreflectanextendedtimeframeof15EFPY.3'CHANGESREUESTEDTheT/SchangesfoundinAttachments 2and3arebasedonimplementation ofR/G1.'99,Revision2.Thefollowing Unit2T/Spagesareimpactedbythischange:Page3/44-25Page3/44-26PageB3/44-6PageB3/44-104.0DISCUSSION Paes344-25and344-26Figures3.4-2and3.4-3aretheheatupandcooldown(P-T)limitcurvesforUnit2.Thesecomposite curvesreflecttheadjustedreference temperature ofthemostlimitingmaterialattheendof15EFPY,andarebasedonthefollowing considerations.
Intermediate shellplate, C5556-2,isthelimitingmaterialasdetermined byposition1ofR/G1.99,Revision2,withaCuandNicontentof0.15%and0.57%,respectively.
2~Thefluencevaluescontained inTable6-14ofWestinghouse WCAP-13515, "Analysis ofCapsuleUfromIndianaMichiganPowerCompany,CookNuclearPlantUnit2ReactorVesselRadiation Surveillance Program",
datedFebruary1993.Thisreportwassubmitted asanattachment toletterAEP:NRC:0894T, datedMarch12,1993.
Attachment 1toAEP:NRC:0894U Page2PaesB344-6andB344-10ThePressure-Temperature basesareproposedtobemodifiedtoreflecttheUnit2CapsuleUAnalysis, aspresented inWestinghouse WCAP-13515.
5.0 NOSIGNIFICANT
HAZARDSDETERMINATION Wehaveevaluated theproposedT/Ss,andhavedetermined thatitshouldnotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).
Operation oftheCookNuclearPlantinaccordance withtheproposedamendment willnot:(1)Involveasinificantincreaseintherobabilit orconseencesofanaccidentreviouslevaluated.
TheproposedchangestotheP-TcurvesarebeingupdatedasaresultoftheUnit2CapsuleUanalysis, WCAP-13515.
Theanalysiswasrequiredpertheremovalscheduleestablished inTable4.4-5oftheCookNuclearPlantTechnical Specifications.
Theanalysiswasperformed basedonguidancefromR/G1.99,Revision2.Thechangeonlyinvolvesarevisedtimeframeformaterialqualification from12EFPYto15EFPYassupported bytheaforementioned Westinghouse analysis.
Therefore, weconcludethatthechangeswillnotinvolveasignificant increaseintheprobability orconsequences ofapreviously evaluated
- accident, norwillthechangesinvolveasignificant reduction inamarginofsafety.(2)Createtheossibilit ofanewordifferent kindofaccidentfromanreviouslanalzed.Theproposedchangesdonotinvolveanyphysicalmodifications totheplant.Therefore, thechangesshouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously analyzedorevaluated.
Attachment 1toAEP:NRC:0894U Page3(3)Involveasinificantreduction inamarinofsafetSeetheresponseto(1)above.6.0PENDINGTSsPROPOSALS IMPACTING THISSUBMITTAL Therearecurrently nootherT/Ssproposals underreviewthatwouldimpactthissubmittal.
li