ML17335A263: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REGULAYINFORMATIONDISTRIBUTIO,SYSTEM(RIDS)ACCESSIONNBR:9810130323DOC.DATE:98/10/08NOTARIZED:YESDOCKETFACIL:$0-'315DopaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315;.,y30-".16DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONPOWERS,R.P.IndianaMichiganPowerCo.(formerlyIndiana8MichiganEleRECXP.NAMERECIPIENTAFFILIATIONRecordsManagementBranch(DocumentControlDesk)
{{#Wiki_filter:REGULAYINFORMATION DISTRIBUTIO, SYSTEM(RIDS)ACCESSION NBR:9810130323 DOC.DATE:
98/10/08NOTARIZED:
YESDOCKETFACIL:$0-'315DopaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315;.,y30-".16 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION POWERS,R.P.
IndianaMichiganPowerCo.(formerly Indiana8MichiganEleRECXP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)


==SUBJECT:==
==SUBJECT:==
Applica'tionforamendstolicensesDPR-585DPR-74,revisingTSContainmentSysBases3/4.6,.1.4reinternalpressure&,3/4.6.1.5reairtemp.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:CE6RECIPIENTIDCODE/NAMEPD3-3LASTANG,J'NTERNAXLECERMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTCOPIESLTTRENCL111111111111RECIPIENTIDCODE/NAMEPD3-3PDNRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS3COPIESLTTRENCL11111111100EXTERNAL:NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 L4I IndianaMichiganPowerCompany500CircleDriveBuchanan,Ml491071373October8,1998DocketNos.:50-31550-316AEP:NRC:131710CFR50.92U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskMailStop0-Pl-17Washington,D.C.20555-0001Gentlemen:DonaldC.CookNuclearPlantUnits1and2TECHNICALSPECIFICATIONAMENDMENT-CONTAINMENTSYSTEMSBASES3/4.6.1.4INTERNALPRESSUREand3/4.6.1.5AIRTEMPERATUREThisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/Ss)basesforCookNuclearPlantunits1and2.ThisamendmentproposestochangeContainmentSystemsT/Sbases3/4.6.1.4,InternalPressure,and3/4.6.1.5,AirTemperature.BackgroundinformationrelevanttotheT/Sandouranalysesconcerningsignificanthazardsconsiderationsiscontainedinattachment1tothisletter.Attachment2containscurrentT/Spagesmarkeduptoshowwherethebaseschangeswillbemade.Attachment3containsthenewproposedT/Sbasespages.Theproposedchangehasbeenreviewedbytheplantnuclearsafetyreviewcommitteeandthenuclearsafetyanddesignreviewcommittee.WerequestthattheapprovedT/Samendmentbeeffectivethirtydaysfromissuance.Inaccordancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtheMichiganDepartmentofPublicHealth.y0oiTHISDAYOFSWORNTOASUBSCRDBEFOREME.~,f.~r1998",R.P.PowersVicePresident~e%J1Jg/jmcAttachments9810130323'7810089PDRADQCK05000315PPDRQNotaryublicVhlERIELBUNNEU.MycommissionExpiresI~Public,BeiienCounly,NVy~  
Applica'tion foramendstolicensesDPR-585DPR-74,revising TSContainment SysBases3/4.6,.1.4 reinternalpressure&,3/4.6.1.5 reairtemp.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution NOTES:CE6RECIPIENT IDCODE/NAME PD3-3LASTANG,J'NTERNAXLECERMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT COPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESLTTRENCL11111111100EXTERNAL:
NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 L4I IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071373 October8,1998DocketNos.:50-31550-316AEP:NRC:1317 10CFR50.92U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskMailStop0-Pl-17Washington, D.C.20555-0001 Gentlemen:
DonaldC.CookNuclearPlantUnits1and2TECHNICAL SPECIFICATION AMENDMENT
-CONTAINMENT SYSTEMSBASES3/4.6.1.4 INTERNALPRESSUREand3/4.6.1.5 AIRTEMPERATURE Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)basesforCookNuclearPlantunits1and2.Thisamendment proposestochangeContainment SystemsT/Sbases3/4.6.1.4, InternalPressure, and3/4.6.1.5, AirTemperature.
 
===Background===
information relevanttotheT/Sandouranalysesconcerning significant hazardsconsiderations iscontained inattachment 1tothisletter.Attachment 2containscurrentT/Spagesmarkeduptoshowwherethebaseschangeswillbemade.Attachment 3containsthenewproposedT/Sbasespages.Theproposedchangehasbeenreviewedbytheplantnuclearsafetyreviewcommittee andthenuclearsafetyanddesignreviewcommittee.
WerequestthattheapprovedT/Samendment beeffective thirtydaysfromissuance.
Inaccordance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.y0oiTHISDAYOFSWORNTOASUBSCRDBEFOREME.~,f.~r1998",R.P.PowersVicePresident
~e%J1Jg/jmcAttachments 9810130323
'7810089PDRADQCK05000315PPDRQNotaryublicVhlERIELBUNNEU.Mycommission ExpiresI~Public,BeiienCounly,NVy~  
~v~ge+JVVL*gl  
~v~ge+JVVL*gl  
~U.STNuclearRegulatoryCommissionPage2AEP:NRC:1317c:J.A.AbramsonJ.L.Caldwell,w/attachmentsMDEQBDW&RPDNRCResidentInspector,w/attachmentsJ.R.Sampson,w/attachments  
~U.STNuclearRegulatory Commission Page2AEP:NRC:1317 c:J.A.AbramsonJ.L.Caldwell, w/attachments MDEQBDW&RPDNRCResidentInspector, w/attachments J.R.Sampson,w/attachments  
~U.S.NuclearRegulatoryCommissionPage3AEP:NRC:1317bc:T.P.Beilman-w/attachmentsE.R.Eckstein/D.R.Hafer/K.R.BakerJ.J.EutoFOLIO-w/attachmentsB.J.HickleG.HonmaJ.B.Kingseed/G.P.Arent/M.J.GumnsJ.F.Stang,Jr.,NRC-Washington,DC,w/attachments ATTACHMENT1TOAEP:NRC:1317SUPPORTINGANALYSESFORTECHNICALSPECIFICATIONAMENDMENT-CONTAINMENTSYSTEMSBASES3/4.6.1.4INTERNALPRESSUREand3/4.6.1.5AIRTEMPERATURE
~U.S.NuclearRegulatory Commission Page3AEP:NRC:1317 bc:T.P.Beilman-w/attachments E.R.Eckstein/D.
R.Hafer/K.R.BakerJ.J.EutoFOLIO-w/attachments B.J.HickleG.HonmaJ.B.Kingseed/G.
P.Arent/M.J.GumnsJ.F.Stang,Jr.,NRC-Washington, DC,w/attachments ATTACHMENT 1TOAEP:NRC:1317 SUPPORTING ANALYSESFORTECHNICAL SPECIFICATION AMENDMENT
-CONTAINMENT SYSTEMSBASES3/4.6.1.4 INTERNALPRESSUREand3/4.6.1.5 AIRTEMPERATURE


Attachment1toAEP:NRC:1317Page1~BackroundTechnicalSpecifications3/4.6.1.4,InternalPressure,and3/4.6.1.5,AirTemperature,involveacontainmentpressureandtemperatureparameter(0.3psigand60'Frespectively)thatmustbemonitoredandcontrolledduringreactoroperation.ThesetwoparametersarelimitedbytheT/Stoensurethevalidityofinitialconditionassumptionsusedinthecalculationforpeakcontainmentpressurefollowingalossofcoolantaccident(LOCA).Thiscalculationwasthebasisfora12psigdesignpressurefortheCookNuclearPlantcontainments.Thebasesdescriptionof.thesetwooperatinglimitsunnecessarilyreferencesthecurrentcalculatedvalue(11.49psig)ofthepeakcontainmentpressurefollowingaLOCA.Becauseaspecificnumberisprovided,changestotheplantorrefinementsinanalysisthatresultinachangetothemaximumcalculatedpeakcontainmentpressurealsorequirechangestothesetwobasessections.Thelastsuchchangewasmadeinamendments214and199,forunits1and2respectively,asaresultofrefinedanalysisperformedfor'theunit130%steamgeneratortubepluggingamendment.Inclusioninthebasesofthecurrentspecificcalculatedvalueof11.49psigforpeakcontainmentpressureisnotnecessaryforanunderstandingandappreciationofthetwooperatinglimitscontrolledbyT/Ss3.6'.4and3.6.1.5.Further,the12psigcontainmentdesignpressurelimitisalreadyincludedinbothbasessections.Therefore,thisamendmentrequestisproposingtomodifyT/Sbases3/4.6.1~4and3/4.6.1.5bydeletingreferencetothespecificnumericalvalueof11.49psigcurrentlycalculatedforthepeakcontainmentpressurefollowingaLOCA.DescritionofAmendmentReuestInT/Sbases3/4.6.1.4InternalPressure,deletethesecondparagraphstating,"ThemaximumpeakpressureresultingfromaLOCAeventiscalculatedtobe11.49psig,whichincludes0.3psigforinitialpositivecontainmentpressure."Addanewsecondparagraphstating,"ThecalculationformaximumpeakcontainmentpressurefollowingaLOCAassumesaninitialcontainmentpressureofpositive0.3psiganddemonstratesthatthe12psigcontainmentdesignpressurewillnotbeexceeded."InthesecondparagraphofT/Sbases3/4.6.1.5,deletethesecondsentence,"Thelowertemperaturelimitof60'Fwilllimitthepeakpressureto11.49psigwhichislessthanthecontainmentdesignpressureof12psig.",andreplaceitwith,"Thelowertemperaturelimitof60'Fwilllimi.tthecalculatedpeakcontainmentpressuretolessthanthecontainmentdesignpressureof12psig."
Attachment 1toAEP:NRC:1317 Page1~BackroundTechnical Specifications 3/4.6.1.4, InternalPressure, and3/4.6.1.5, AirTemperature, involveacontainment pressureandtemperature parameter (0.3psigand60'Frespectively) thatmustbemonitored andcontrolled duringreactoroperation.
Attachment1toAEP:NRC:1317Page2JustificationforAmendmentThepurposeoftechnicalspecifications3.6.1.4and3.6.1.5istomaintainthevalidityofcontainmentoperatingassumptionsmadeindesigningtheCookNuclearPlantcontainmentforapeakpressureof12psig.Thebasesforthesespecificationsareadequatelydescribedwithoutincludinginthediscussionaspecificnumericalvalueforthecurrentcalculatedpeakcontainmentpressure.Themaximumpeakcontainmentpressurecalculationandthecurrentnumericalvalueof11.49psigareproperlydescribedinChapter14oftheCookUFSAR.Theprovisionsof10CFR50.59Chanestestsandexeriments,therefore,appropriatelycontrolchangesormodificationshavinganimpactonthecalculationornumericalresult.DeletingthecurrentanalysisvaluefromtheT/SswillavoidthenecessityofchangingtheT/Sswhenever,plantmodificationsorrefinedanalysistechniquesresultinchangestothenumericalvalueforthepeakcalculatedcontainmentpressurefollowingaLOCA.BasisforNoSinificantHazardsDeterminationInaccordancewith10CFR50.92,thisproposedamendmentdoesnotinvolveasignificanthazardsconsiderationifitdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalyticaltechniqueorchangetoanyoperatinglimit.oftheT/Ss.Thereforetheprobabilityorconsequencesofaccidentspreviouslyevaluatedcouldnotbeimpacted.(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalyticaltechniqueorchangetoanyoperatinglimitoftheT/Ss.Thereforethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluatedcouldnotbeinvolved.(3)involveasignificantreductioninamarginofsafety.ThechangestoT/Sbases3/4.6.1.4and3/4.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalyticaltechniqueorchangetoanyoperatinglimitoftheT/Ss.Thereforethechangecannotinvolveareductioninamarginofsafety.}}
Thesetwoparameters arelimitedbytheT/Stoensurethevalidityofinitialcondition assumptions usedinthecalculation forpeakcontainment pressurefollowing alossofcoolantaccident(LOCA).
Thiscalculation wasthebasisfora12psigdesignpressurefortheCookNuclearPlantcontainments.
Thebasesdescription of.thesetwooperating limitsunnecessarily references thecurrentcalculated value(11.49psig)ofthepeakcontainment pressurefollowing aLOCA.Becauseaspecificnumberisprovided, changestotheplantorrefinements inanalysisthatresultinachangetothemaximumcalculated peakcontainment pressurealsorequirechangestothesetwobasessections.
Thelastsuchchangewasmadeinamendments 214and199,forunits1and2respectively, asaresultofrefinedanalysisperformed for'theunit130%steamgenerator tubepluggingamendment.
Inclusion inthebasesofthecurrentspecificcalculated valueof11.49psigforpeakcontainment pressureisnotnecessary foranunderstanding andappreciation ofthetwooperating limitscontrolled byT/Ss3.6'.4and3.6.1.5.Further,the12psigcontainment designpressurelimitisalreadyincludedinbothbasessections.
Therefore, thisamendment requestisproposing tomodifyT/Sbases3/4.6.1~4and3/4.6.1.5 bydeletingreference tothespecificnumerical valueof11.49psigcurrently calculated forthepeakcontainment pressurefollowing aLOCA.DescritionofAmendment ReuestInT/Sbases3/4.6.1.4 InternalPressure, deletethesecondparagraph stating,"Themaximumpeakpressureresulting fromaLOCAeventiscalculated tobe11.49psig,whichincludes0.3psigforinitialpositivecontainment pressure."
Addanewsecondparagraph stating,"Thecalculation formaximumpeakcontainment pressurefollowing aLOCAassumesaninitialcontainment pressureofpositive0.3psiganddemonstrates thatthe12psigcontainment designpressurewillnotbeexceeded."
Inthesecondparagraph ofT/Sbases3/4.6.1.5, deletethesecondsentence, "Thelowertemperature limitof60'Fwilllimitthepeakpressureto11.49psigwhichislessthanthecontainment designpressureof12psig.",andreplaceitwith,"Thelowertemperature limitof60'Fwilllimi.tthecalculated peakcontainment pressuretolessthanthecontainment designpressureof12psig."
Attachment 1toAEP:NRC:1317 Page2Justification forAmendment Thepurposeoftechnical specifications 3.6.1.4and3.6.1.5istomaintainthevalidityofcontainment operating assumptions madeindesigning theCookNuclearPlantcontainment forapeakpressureof12psig.Thebasesforthesespecifications areadequately described withoutincluding inthediscussion aspecificnumerical valueforthecurrentcalculated peakcontainment pressure.
Themaximumpeakcontainment pressurecalculation andthecurrentnumerical valueof11.49psigareproperlydescribed inChapter14oftheCookUFSAR.Theprovisions of10CFR50.59Chanestestsandexeriments, therefore, appropriately controlchangesormodifications havinganimpactonthecalculation ornumerical result.DeletingthecurrentanalysisvaluefromtheT/Sswillavoidthenecessity ofchangingtheT/Sswhenever, plantmodifications orrefinedanalysistechniques resultinchangestothenumerical valueforthepeakcalculated containment pressurefollowing aLOCA.BasisforNoSinificantHazardsDetermination Inaccordance with10CFR50.92,thisproposedamendment doesnotinvolveasignificant hazardsconsideration ifitdoesnot:(1)involve asignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limit.oftheT/Ss.Therefore theprobability orconsequences ofaccidents previously evaluated couldnotbeimpacted.
(2)create thepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limitoftheT/Ss.Therefore thepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated couldnotbeinvolved.
(3)involve asignificant reduction inamarginofsafety.ThechangestoT/Sbases3/4.6.1.4 and3/4.6.1.5 donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limitoftheT/Ss.Therefore thechangecannotinvolveareduction inamarginofsafety.}}

Revision as of 07:09, 29 June 2018

Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp
ML17335A263
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/08/1998
From: POWERS R P
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17335A264 List:
References
AEP:NRC:1317, NUDOCS 9810130323
Download: ML17335A263 (10)
v • d • e


Text

REGULAYINFORMATION DISTRIBUTIO, SYSTEM(RIDS)ACCESSION NBR:9810130323 DOC.DATE:

98/10/08NOTARIZED:

YESDOCKETFACIL:$0-'315DopaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315;.,y30-".16 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION POWERS,R.P.

IndianaMichiganPowerCo.(formerly Indiana8MichiganEleRECXP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)

SUBJECT:

Applica'tion foramendstolicensesDPR-585DPR-74,revising TSContainment SysBases3/4.6,.1.4 reinternalpressure&,3/4.6.1.5 reairtemp.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:CE6RECIPIENT IDCODE/NAME PD3-3LASTANG,J'NTERNAXLECERMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT COPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-3PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESLTTRENCL11111111100EXTERNAL:

NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:

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

LTTR13ENCL12 L4I IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071373 October8,1998DocketNos.:50-31550-316AEP:NRC:1317 10CFR50.92U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskMailStop0-Pl-17Washington, D.C.20555-0001 Gentlemen:

DonaldC.CookNuclearPlantUnits1and2TECHNICAL SPECIFICATION AMENDMENT

-CONTAINMENT SYSTEMSBASES3/4.6.1.4 INTERNALPRESSUREand3/4.6.1.5 AIRTEMPERATURE Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)basesforCookNuclearPlantunits1and2.Thisamendment proposestochangeContainment SystemsT/Sbases3/4.6.1.4, InternalPressure, and3/4.6.1.5, AirTemperature.

Background

information relevanttotheT/Sandouranalysesconcerning significant hazardsconsiderations iscontained inattachment 1tothisletter.Attachment 2containscurrentT/Spagesmarkeduptoshowwherethebaseschangeswillbemade.Attachment 3containsthenewproposedT/Sbasespages.Theproposedchangehasbeenreviewedbytheplantnuclearsafetyreviewcommittee andthenuclearsafetyanddesignreviewcommittee.

WerequestthattheapprovedT/Samendment beeffective thirtydaysfromissuance.

Inaccordance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.y0oiTHISDAYOFSWORNTOASUBSCRDBEFOREME.~,f.~r1998",R.P.PowersVicePresident

~e%J1Jg/jmcAttachments 9810130323

'7810089PDRADQCK05000315PPDRQNotaryublicVhlERIELBUNNEU.Mycommission ExpiresI~Public,BeiienCounly,NVy~

~v~ge+JVVL*gl

~U.STNuclearRegulatory Commission Page2AEP:NRC:1317 c:J.A.AbramsonJ.L.Caldwell, w/attachments MDEQBDW&RPDNRCResidentInspector, w/attachments J.R.Sampson,w/attachments

~U.S.NuclearRegulatory Commission Page3AEP:NRC:1317 bc:T.P.Beilman-w/attachments E.R.Eckstein/D.

R.Hafer/K.R.BakerJ.J.EutoFOLIO-w/attachments B.J.HickleG.HonmaJ.B.Kingseed/G.

P.Arent/M.J.GumnsJ.F.Stang,Jr.,NRC-Washington, DC,w/attachments ATTACHMENT 1TOAEP:NRC:1317 SUPPORTING ANALYSESFORTECHNICAL SPECIFICATION AMENDMENT

-CONTAINMENT SYSTEMSBASES3/4.6.1.4 INTERNALPRESSUREand3/4.6.1.5 AIRTEMPERATURE

Attachment 1toAEP:NRC:1317 Page1~BackroundTechnical Specifications 3/4.6.1.4, InternalPressure, and3/4.6.1.5, AirTemperature, involveacontainment pressureandtemperature parameter (0.3psigand60'Frespectively) thatmustbemonitored andcontrolled duringreactoroperation.

Thesetwoparameters arelimitedbytheT/Stoensurethevalidityofinitialcondition assumptions usedinthecalculation forpeakcontainment pressurefollowing alossofcoolantaccident(LOCA).

Thiscalculation wasthebasisfora12psigdesignpressurefortheCookNuclearPlantcontainments.

Thebasesdescription of.thesetwooperating limitsunnecessarily references thecurrentcalculated value(11.49psig)ofthepeakcontainment pressurefollowing aLOCA.Becauseaspecificnumberisprovided, changestotheplantorrefinements inanalysisthatresultinachangetothemaximumcalculated peakcontainment pressurealsorequirechangestothesetwobasessections.

Thelastsuchchangewasmadeinamendments 214and199,forunits1and2respectively, asaresultofrefinedanalysisperformed for'theunit130%steamgenerator tubepluggingamendment.

Inclusion inthebasesofthecurrentspecificcalculated valueof11.49psigforpeakcontainment pressureisnotnecessary foranunderstanding andappreciation ofthetwooperating limitscontrolled byT/Ss3.6'.4and3.6.1.5.Further,the12psigcontainment designpressurelimitisalreadyincludedinbothbasessections.

Therefore, thisamendment requestisproposing tomodifyT/Sbases3/4.6.1~4and3/4.6.1.5 bydeletingreference tothespecificnumerical valueof11.49psigcurrently calculated forthepeakcontainment pressurefollowing aLOCA.DescritionofAmendment ReuestInT/Sbases3/4.6.1.4 InternalPressure, deletethesecondparagraph stating,"Themaximumpeakpressureresulting fromaLOCAeventiscalculated tobe11.49psig,whichincludes0.3psigforinitialpositivecontainment pressure."

Addanewsecondparagraph stating,"Thecalculation formaximumpeakcontainment pressurefollowing aLOCAassumesaninitialcontainment pressureofpositive0.3psiganddemonstrates thatthe12psigcontainment designpressurewillnotbeexceeded."

Inthesecondparagraph ofT/Sbases3/4.6.1.5, deletethesecondsentence, "Thelowertemperature limitof60'Fwilllimitthepeakpressureto11.49psigwhichislessthanthecontainment designpressureof12psig.",andreplaceitwith,"Thelowertemperature limitof60'Fwilllimi.tthecalculated peakcontainment pressuretolessthanthecontainment designpressureof12psig."

Attachment 1toAEP:NRC:1317 Page2Justification forAmendment Thepurposeoftechnical specifications 3.6.1.4and3.6.1.5istomaintainthevalidityofcontainment operating assumptions madeindesigning theCookNuclearPlantcontainment forapeakpressureof12psig.Thebasesforthesespecifications areadequately described withoutincluding inthediscussion aspecificnumerical valueforthecurrentcalculated peakcontainment pressure.

Themaximumpeakcontainment pressurecalculation andthecurrentnumerical valueof11.49psigareproperlydescribed inChapter14oftheCookUFSAR.Theprovisions of10CFR50.59Chanestestsandexeriments, therefore, appropriately controlchangesormodifications havinganimpactonthecalculation ornumerical result.DeletingthecurrentanalysisvaluefromtheT/Sswillavoidthenecessity ofchangingtheT/Sswhenever, plantmodifications orrefinedanalysistechniques resultinchangestothenumerical valueforthepeakcalculated containment pressurefollowing aLOCA.BasisforNoSinificantHazardsDetermination Inaccordance with10CFR50.92,thisproposedamendment doesnotinvolveasignificant hazardsconsideration ifitdoesnot:(1)involve asignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limit.oftheT/Ss.Therefore theprobability orconsequences ofaccidents previously evaluated couldnotbeimpacted.

(2)create thepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

ThechangestoT/Sbases3.6.1.4and3.6.1.5donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limitoftheT/Ss.Therefore thepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated couldnotbeinvolved.

(3)involve asignificant reduction inamarginofsafety.ThechangestoT/Sbases3/4.6.1.4 and3/4.6.1.5 donotinvolveaphysicalchangetotheplant,changeinanalytical technique orchangetoanyoperating limitoftheT/Ss.Therefore thechangecannotinvolveareduction inamarginofsafety.

Retrieved from "https://kanterella.com/w/index.php?title=ML17335A263&oldid=735155"