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{{#Wiki_filter:(ACCELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9504060176DOC.DATE:95/03/31NOTARIZED:YESDOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)
{{#Wiki_filter:(ACCELERATED RIDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9504060176 DOC.DATE:
95/03/31NOTARIZED:
YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)


==SUBJECT:==
==SUBJECT:==
ApplicationforamendstolicensesDPR-58&DPR-74.Amends.wouldmodifysurveillancerequirements,eliminatingrequirementtotestcertainsafeguardspumps.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRLENCLLSIZE:0+~TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNAL:cgXXECENTER01NRR/DRCH/HTCBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD3-1PDNMSS/DWM/LLDPNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RlDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 C~
Application foramendstolicensesDPR-58&DPR-74.Amends
indianaMichiganPowerCompanyP.O.Box16631Columbus,OH43216FINarch31,1995AEP:NRC:1211DocketNos.:50-31550-316U,S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENTTOTECHNICALSPECIFICATIONSURVEILLANCEREQUIREMENTS'EVISESAFETYRELATEDPUMPTESTINGTOELIMINATERECIRCULATIONALIGNMENTSANDBECONSISTENTWITHTHEINSERVICETESTINGPROGRAM(IST)ANDNUREG-1431.Thisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/Ss)forDonaldC.CookNuclearPlantunits1,and2~Specifically,weareproposingtomodifythesurveillancerequirementstoeliminatetherequirementtotestcertainsafeguardspumpsviatheirrecirculationflowpath.Thefollowingpumpsareaffected;thecentrifugalchargingpumps,residualheatremovalpumps,motordrivenauxiliaryfeedwaterpumps,andtheturbinedrivenauxiliaryfeedwaterpumps.Twopumps,thecontainmentspraypumpandsafetyinjectionpump,willcontinuetobetestedontheirrecirculationlinesbasedonexistingdesign.Thisproposedchangewouldalsoeliminatereferencestospecificdischargepressuresandflowsassociatedwiththesepumps.ThespecifictestparametersbeingremovedarecontrolledbytheapprovedCookNuclearPlantISTprogram.Thefollowingunit1andunit2T/Ssurveillancesareaffected:4.1.2.3.1,4.1.2.4,4.5.2f,4.6.2.1b,4.7.1.2a,and4.7.1.2b.TheexistingDonaldC.CookNuclearPlantT/Ssurveillancerequirementsassociatedwiththeabovepumpsrequiretestingofthepumpsutilizingtheirrecirculationlines.Thismethodoftestingprovideslimitedinformationonthepump/systems'bilitytoperformtheirsafetyrelatedfunctions.Therefore,achangetotheT/Ssurveillanceisbeingproposedtoallowtestingofthesepumpsusinghighercapacityflowpaths(whereapplicable).{'GG038PDR+0~7++>03ZZ950g0~~<<l<osoooz>q1IPgR  
.wouldmodifysurveillance requirements, eliminating requirement totestcertainsafeguards pumps.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR LENCLLSIZE:0+~TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
cgXXECENTER01NRR/DRCH/HTCB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:
NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNMSS/DWM/LLDP NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RlDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2083)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 C~
indianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216FINarch31,1995AEP:NRC:1211 DocketNos.:50-31550-316U,S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENT TOTECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS'EVISE SAFETYRELATEDPUMPTESTINGTOELIMINATE RECIRCULATION ALIGNMENTS ANDBECONSISTENT WITHTHEINSERVICE TESTINGPROGRAM(IST)ANDNUREG-1431.
Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantunits1,and2~Specifically, weareproposing tomodifythesurveillance requirements toeliminate therequirement totestcertainsafeguards pumpsviatheirrecirculation flowpath.
Thefollowing pumpsareaffected; thecentrifugal chargingpumps,residualheatremovalpumps,motordrivenauxiliary feedwater pumps,andtheturbinedrivenauxiliary feedwater pumps.Twopumps,thecontainment spraypumpandsafetyinjection pump,willcontinuetobetestedontheirrecirculation linesbasedonexistingdesign.Thisproposedchangewouldalsoeliminate references tospecificdischarge pressures andflowsassociated withthesepumps.Thespecifictestparameters beingremovedarecontrolled bytheapprovedCookNuclearPlantISTprogram.Thefollowing unit1andunit2T/Ssurveillances areaffected:
4.1.2.3.1, 4.1.2.4,4.5.2f,4.6.2.1b, 4.7.1.2a, and4.7.1.2b.
TheexistingDonaldC.CookNuclearPlantT/Ssurveillance requirements associated withtheabovepumpsrequiretestingofthepumpsutilizing theirrecirculation lines.Thismethodoftestingprovideslimitedinformation onthepump/systems'bility toperformtheirsafetyrelatedfunctions.
Therefore, achangetotheT/Ssurveillance isbeingproposedtoallowtestingofthesepumpsusinghighercapacityflowpaths (whereapplicable).
{'GG038PDR+0~7++>03ZZ950g0~~<<l<osoooz>q1IPgR  
'
'
U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1211Utilizingthistestmethodwouldprovideformoreaccuratedatatobetterdeterminetheactualpump/systemconditions.Inadditiontotheimprovementinthequalityofacquiredtestdata,theproposedamendmentwouldalsoaligntheaffectedCookNuclearPlantT/SswiththeMeritsProgramT/SsissuedasNUREG-1431.AnadministrativechangetoT/Ssurveillances4.5.2.d.2,4.5.2.e,4.6.2.c,4.7.1.2e,and4.7.1.2fisalsoincludedinthisamendment.Thesespecificationseachcontainedafootnoteassociatedwiththeunit2cycle9-10refuelingoutagewhichisnolongerapplicable,thusthefootnotesarebeingremoved.Attachment1providesadetaileddescriptionoftheproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Sincerely,EFE;E.FitzpatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMEehTHIS~~DAYOF1995Attachmentcc:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.PadgettNotaryPublic itt ATTACHMENT1TOAEP:NRC:1211DESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICALSPECIFICATIONS 1I Attachment1toAEP:NRC:1211Page1DESCRIPTIONOFCHANGESTheproposedamendmenttotechnicalspecifications(T/Ss)surveillances;4.1.2.3.1,4.1.2.4,4.5,2.d.2,4.5.2.e,4.5.2f,4.6.2.lb,4.6.2.c,4.7.1.2a,4.7.1.2b,4.7.1.2e,and4.7.1.2fmakethefollowingspecificchangestoCookNuclearPlantUnits1and2T/Ss:S4123Changessurveillance4.1.2.3.1(page3/4l-ll)from:"TheaboverequiredchargingpumpshallbedemonstratedOPERABLEbyverifying,thatonrecirculationflow,thepumpdevelopsadischargepressureofgreaterthanorequalto2390psigwhentestedpursuanttoSpecification4.0.5."To:"TheaboverequiredchargingpumpshallbedemonstratedOPERABLEbyverifyingthatthepump'sdevelopedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedheadwhentestedpursuanttoSpecification4.0.5."Changessurveillance4.1.2.4(page3/41-12)from:"AtleasttwochargingpumpsshallbedemonstratedOPERABLEbyverifying,thatonrecirculationflow,thepumpdevelopsadischargepressureofgreaterthanorequalto2405psigwhentestedpursuanttoSpecification4.0.5."To:"AtleasttwochargingpumpsshallbedemonstratedOPERABLEbyverifyingthatthepump'sdevelopedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedheadwhentestedpursuanttoSpecification4.0.5."Changessurveillance4.5.2f(page3/45-5)from:"ByverifyingthateachofthefollowingpumpsdevelopstheindicateddischargepressureonrecirculationflowwhentestedpursuanttoSpecification4.0.5.1.Centrifugalchargingpumpgreaterthanorequalto2405psig 4
U.S.NuclearRegulatory Commission Page2AEP:NRC:1211 Utilizing thistestmethodwouldprovideformoreaccuratedatatobetterdetermine theactualpump/system conditions.
Attachment1toAEP:NRC:1211Page22.Safetyinjectionpumpgreaterthanorequalto1409psig3.Residualheatremovalpumpgreaterthanorequalto190psig"To:"Byverifyingthateachofthefollowingpump'sdevelopedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedheadwhentestedpursuanttoSpecification4.0.5.1.Centrifugalchargingpumps2.Safetyinjectionpumps3.Residualheatremovalpumps"Changessurveillance4.6.2.1b(page3/46-10)from:"Byverifying,thatonrecirculationflow,eachpumpdevelopsadischargepressureofgreaterthanorequalto255psigataflowofgreaterthanorequalto700gpm,whentestedpursuanttoSpecification4.0.5."To:"Byverifyingthateachcontainmentspraypump'sdevelopedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedhead."Changessurveillance4.7.1,2a(page3/47-6)from:"Verifyingthateachmotordrivenpumpdevelopsanequivalentdischargepressureofgreaterthanorequalto1375psig(1240psigforUnit2)at60Fonrecirculationflow.TQ:"Verifyingthateachmotordrivenauxiliaryfeedwaterpump'sdevelopedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedhead."  
Inadditiontotheimprovement inthequalityofacquiredtestdata,theproposedamendment wouldalsoaligntheaffectedCookNuclearPlantT/SswiththeMeritsProgramT/SsissuedasNUREG-1431.
Anadministrative changetoT/Ssurveillances 4.5.2.d.2, 4.5.2.e,4.6.2.c,4.7.1.2e, and4.7.1.2fisalsoincludedinthisamendment.
Thesespecifications eachcontained afootnoteassociated withtheunit2cycle9-10refueling outagewhichisnolongerapplicable, thusthefootnotes arebeingremoved.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Sincerely, EFE;E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMEehTHIS~~DAYOF1995Attachment cc:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.PadgettNotaryPublic itt ATTACHMENT 1TOAEP:NRC:1211 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS 1I Attachment 1toAEP:NRC:1211 Page1DESCRIPTION OFCHANGESTheproposedamendment totechnical specifications (T/Ss)surveillances; 4.1.2.3.1, 4.1.2.4,4.5,2.d.2, 4.5.2.e,4.5.2f,4.6.2.lb, 4.6.2.c,4.7.1.2a, 4.7.1.2b, 4.7.1.2e, and4.7.1.2fmakethefollowing specificchangestoCookNuclearPlantUnits1and2T/Ss:S4123Changessurveillance 4.1.2.3.1 (page3/4l-ll)from:"Theaboverequiredchargingpumpshallbedemonstrated OPERABLEbyverifying, thatonrecirculation flow,thepumpdevelopsadischarge pressureofgreaterthanorequalto2390psigwhentestedpursuanttoSpecification 4.0.5."To:"Theaboverequiredchargingpumpshallbedemonstrated OPERABLEbyverifying thatthepump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5."Changessurveillance 4.1.2.4(page3/41-12)from:"Atleasttwochargingpumpsshallbedemonstrated OPERABLEbyverifying, thatonrecirculation flow,thepumpdevelopsadischarge pressureofgreaterthanorequalto2405psigwhentestedpursuanttoSpecification 4.0.5."To:"Atleasttwochargingpumpsshallbedemonstrated OPERABLEbyverifying thatthepump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5."Changessurveillance 4.5.2f(page3/45-5)from:"Byverifying thateachofthefollowing pumpsdevelopstheindicated discharge pressureonrecirculation flowwhentestedpursuanttoSpecification 4.0.5.1.Centrifugal chargingpumpgreaterthanorequalto2405psig 4
Attachment 1toAEP:NRC:1211 Page22.Safetyinjection pumpgreaterthanorequalto1409psig3.Residualheatremovalpumpgreaterthanorequalto190psig"To:"Byverifying thateachofthefollowing pump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5.1.Centrifugal chargingpumps2.Safetyinjection pumps3.Residualheatremovalpumps"Changessurveillance 4.6.2.1b(page3/46-10)from:"Byverifying, thatonrecirculation flow,eachpumpdevelopsadischarge pressureofgreaterthanorequalto255psigataflowofgreaterthanorequalto700gpm,whentestedpursuanttoSpecification 4.0.5."To:"Byverifying thateachcontainment spraypump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped head."Changessurveillance 4.7.1,2a(page3/47-6)from:"Verifying thateachmotordrivenpumpdevelopsanequivalent discharge pressureofgreaterthanorequalto1375psig(1240psigforUnit2)at60Fonrecirculation flow.TQ:"Verifying thateachmotordrivenauxiliary feedwater pump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped head."  


Attachment1toAEP:NRC:1211Page3TS4.712bChangessurveillance4.7.1.2b(page3/47-6)from:"Verifyingthattheturbinedrivenpumpdevelopsanequivalentdischargepressureofgreaterthanorequalto1285psig(1180psigforUnit2)at60'Fandataflowofgreaterthanorequalto700gpmwhenthesecondarysteamsupplypressureisgreaterthan310psig.TheprovisionsofSpecification4'.4arenotapplicableforentryintoMODE3.To.'Verifyingthattheturbinedrivenauxiliaryfeedwaterpump'developedheadatthetestflowpointisgreaterthanorequaltotherequireddevelopedheadwhenthesecondarysteamsupplypressureisgreaterthan310psig.TheprovisionsofSpecification4.0.4arenotapplicableforentryintoMODE3."4.52.d.2452e462c47.12eand4.7.12fDeletethe"daggers"andassociatedfootnotereferencetoTechnicalSpecification4.0.8.ThisreferencewasspecificallyassociatedwithasurveillanceextensionapprovedduringUnit2cycle9-10.Itisnolongerapplicable.II.JUSTIFICATIONFORCHANGESTheproposedtechnicalspecificationchangeeliminatesthesurveillancerequirementtotesttheUnit1andUnit2centrifugalcharging,safetyinjection,residualheatremoval,containmentspray,motordrivenauxiliaryfeedwaterandsteamdrivenauxiliaryfeedwaterpumpsontheirrecirculationlines.Itshouldbenotedthatthecontainmentspraypumpsandsafetyinjectionpumpswillcontinuetobetestedontheirrecirculationflowpathsasaresultofexistingsystemdesign.Thisproposedchangewouldalsoremovethereferencestospecificdischargepressuresandflowsassociatedwiththesepumps.ThischangeisconsistentwiththeassumptionsandguidanceprovidedinNUREG-1431,"StandardTechnicalSpecifications,WestinghousePlants,"whichstates:"Thepurposeforconductingperiodictestingofthepumpslistedaboveistodetectgrossdegradationcausedbyimpellerstructuraldamageorotherhydrauliccomponentproblems.ThistestingisrequiredbySectionXIoftheAmericanSocietyofMechanicalEngineers(ASME)Code.Thetestingdescribedabovemaybeaccomplishedbymeasuringthepumpdevelopedheadatonlyonepointofthepumpperformancecurve.Thisverifiesboththatthemeasured Attachment1toAEP:NRC:1211Page4performanceiswithinanacceptabletoleranceoftheoriginalpumpbaselineperformanceandthattheperformanceatthetestflowisgreaterthanorequaltotheperformanceassumedintheplantsafetyanalysis.SurveillancerequirementsarespecifiedintheInserviceTesting(IST)ProgramwhichencompassesSectionXIoftheASMECode."Thepurposeoftheproposedchangeistoeliminatetherecirculationflowpathrequirementfortestingtheabovepumpsand,whereapplicable,allowtestingofthepumpsutilizingahighcapacityflowpath.Surveillancetestsonpumprecirculationlinesprovidelimitedinformationonthepump/system'sabilitytoperformitssafetyfunction.Thetestperformedonrecirculationoffersonedatapointatminimalflowandhighestpossiblehead,equivalentinmostcasestothepump'sshutoffhead.Suchlowflowoperationcouldproduceunstablehydraulicforceswhichmayresultininaccurateperformancedataandmayalsobedetrimentaltothepump.Pumpperformancetestdatashouldbeobtainedatflowratesascloseaspossibletothepump'sbestefficiencypoint.Atsuchflowrates,'ydraulicforcesarerelativelystableandmoreaccuratedatais.,assured.Furthermore,whilesomepumpdegradationcanbeobservedatbothlowerandhigherflowrates,systemdegradation(e.g.,pipeblockage)canbeobservedonlyatthehigherflowrates,Ingeneral,pump/systemdegradationisfarmoreapparentathigherflowrates.-Testingonhighercapacityflowpathsinsteadofthepump'srecirculationlineis,therefore,preferableinordertoobtainmoreaccuratedata,betterdeterminepump/systemconditions,andminimizelowflowpumpoperation.InadditiontoitsconsistencywithNUREG-1431,theabovediscussionisconsistentwithissuesaddressedinNUREG/CP-0123,"ProceedingsoftheSecondNRC/ASMESymposiumonPumpandValveTesting,"inparticularwithpapersentitled,"PumpTestingintheNuclearIndustry:TheComprehensiveTestandOtherConsiderations(page133),""TestQuality(page159),"and"OperatingPumpsonMinimum.Flow(page557)."TheT/Srequirementlimitingthesurveillancetesttoonlytherecirculationlinealsoplacesunduedemandsonthepump,system,andoperatorsforcertainpumps,likethecentrifugalchargingpumps.Technicalspecificationtestingofthesepumpsontheirrecirculationlinesrequirethepumpstobesecuredfromoperation,thesystemrealigned,andthepumpsrestartedtosupportarecirculationalignment.Byallowingforahighercapacityflowpath,systemrealignmentbecomesunnecessaryandnormaloperationalflowpathsneednotbedisturbed.Operatorflexibilitytotestthepumpsonahighercapacityflowpath,wherepossible,willaidinminimizingrequiredsystemmanipulationsaswellasmaximizingcomponentavailability.
Attachment 1toAEP:NRC:1211 Page3TS4.712bChangessurveillance 4.7.1.2b(page3/47-6)from:"Verifying thattheturbinedrivenpumpdevelopsanequivalent discharge pressureofgreaterthanorequalto1285psig(1180psigforUnit2)at60'Fandataflowofgreaterthanorequalto700gpmwhenthesecondary steamsupplypressureisgreaterthan310psig.Theprovisions ofSpecification 4'.4arenotapplicable forentryintoMODE3.To.'Verifyingthattheturbinedrivenauxiliary feedwaterpump'developed headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhenthesecondary steamsupplypressureisgreaterthan310psig.Theprovisions ofSpecification
tl~~l' Attachment1toAEP:NRC:1211Page5TheproposedT/Salsoeliminatesspecificflowandpressuresetpointsthatcorrelatewithtestingthecentrifugalcharging,safetyinjection,residualheatremoval,containmentspray,andmotordrivenandturbinedrivenauxiliaryfeedwaterpumpsontheirrecirculationlines.ThespecificflowsandpressuresthatdemonstratethecapabilityofthepumptoperformitsintendedsafetyfunctionareidentifiedintheCookNuclearPlantISTprogram.Theminimumperformancevalues,modeledintheaccidentanalysisoridentifiedastheminimumsystemrequirement,areusedintheISTprogramasthelowestacceptablevaluesforcontinuedoperation.Afinalbenefitofchangingthetestingrequirementsofthecentrifugalcharging,safetyinjection,residualheatremoval,containmentspray,andmotordrivenandturbinedrivenauxiliaryfeedwaterpumpsisthatitwillassureuniformtestrequirementsforT/Spumpswithsimilartestingrequirements.Currently,essentialservicewaterandcomponentcoolingwaterpumpsarerequiredtobetestedinaccordancewiththeISTprogram.SpecificflowandpressurerequirementsaredefinedbytheISTprogramandnottheT/Ssurveillance.Insummary,theproposedchangewillassuretheacquisitionofaccuratedata,betterdeterminepump/systemconditions,andminimizelowflowpumpoperation.Additionally,thechangewillprovidesurveillanceguidanceconsistentwithNUREG-1431,NUREG/CP-0123,andexistingservicewatercomponentT/SscurrentlyresidentinCookNuclearPlantT/Ss.III.10CFR5092CRITERIPer10CFR50.92,aproposedchangedoesnotinvolveasignificanthazardsconsiderationifthechangedoesnot:l.involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety.CriterionThepurposeforconductingperiodictestingofthepumpsidentifiedinthisproposedamendmentistodetectgrossdegradationasrequiredbySectionXIoftheASMECode.TheCookNuclearPlantISTprogram,whichencompassesSectionXIoftheASMECode,isthebasisfortheexistingaswellastheproposedT/Ss.Testingthepumpsutilizingahighcapacity Attachment1toAEP:NRC:1211Page6flowpathinsteadofarecirculationflowpath(whereapplicable)willhavenoimpactontheabilityofthepumptoperformitsintendedfunction.Infact,itisexpectedthatthehighcapacityflowpathwillprovideamoreaccurateassessmentofthepump/systems'onditionsandabilitytomeettheirsafetyfunction.Theremovalofspecifictestparameters,infavorofreferencingtheCookNuclearPlantISTProgram,willnotimpacttheabilityofthepumpstoperformtheirsafetyrelatedfunction.ISTProgramparametersensurethatthepumpsundertestprovidethesupportassumedintheplant'ssafetyanalyses.Therefore,basedontheseconsiderations,itisconcludedthattheproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Crterion2Theproposedchangewillprecludetheneedtorealignselectedpumpstotheirrecirculationflowpathsfortestingpurposes(whereapplicable).Eliminatingtheneedforalignmenttotherecirculationflowpathaidsinmaximizingthepump'savailabilitytoperformitssafetyfunction.Asstatedpreviously,theremovalofthespecifictestparameters,infavorofreferencingtheCookNuclearPlantISTProgramwillnotimpacttheabilityofthepumpstoperformtheirintendedsafetyfunction.Thus,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Criterion3Asstatedpreviously,testingoftheselectedpumpsutilizingahighcapacityflowpathwillprovidegreaterassuranceofpumpcapabilityandmaximizepumpavailability.Additionally,removingspecifictestparametersinfavorofreferencingtheCookNuclearPlantISTProgramwillhavenoimpactontheabilityofthepumpstoperformtheirintendedsafetyfunction.Therefore,webelievethatthemarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Basedontheseconsiderations,itisconcludedthatthechangesdonotinvolveasignificantreductioninamarginofsafety.
 
Jjl ATTACHMENT2TOAEP:NRC:1211EXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOREFLECTPROPOSEDCHANGES
==4.0. 4arenotapplicable==
forentryintoMODE3."4.52.d.2452e462c47.12eand4.7.12fDeletethe"daggers" andassociated footnotereference toTechnical Specification 4.0.8.Thisreference wasspecifically associated withasurveillance extension approvedduringUnit2cycle9-10.Itisnolongerapplicable.
II.JUSTIFICATION FORCHANGESTheproposedtechnical specification changeeliminates thesurveillance requirement totesttheUnit1andUnit2centrifugal
: charging, safetyinjection, residualheatremoval,containment spray,motordrivenauxiliary feedwater andsteamdrivenauxiliary feedwater pumpsontheirrecirculation lines.Itshouldbenotedthatthecontainment spraypumpsandsafetyinjection pumpswillcontinuetobetestedontheirrecirculation flowpaths asaresultofexistingsystemdesign.Thisproposedchangewouldalsoremovethereferences tospecificdischarge pressures andflowsassociated withthesepumps.Thischangeisconsistent withtheassumptions andguidanceprovidedinNUREG-1431,"Standard Technical Specifications, Westinghouse Plants,"whichstates:"Thepurposeforconducting periodictestingofthepumpslistedaboveistodetectgrossdegradation causedbyimpellerstructural damageorotherhydraulic component problems.
ThistestingisrequiredbySectionXIoftheAmericanSocietyofMechanical Engineers (ASME)Code.Thetestingdescribed abovemaybeaccomplished bymeasuring thepumpdeveloped headatonlyonepointofthepumpperformance curve.Thisverifiesboththatthemeasured Attachment 1toAEP:NRC:1211 Page4performance iswithinanacceptable tolerance oftheoriginalpumpbaselineperformance andthattheperformance atthetestflowisgreaterthanorequaltotheperformance assumedintheplantsafetyanalysis.
Surveillance requirements arespecified intheInservice Testing(IST)Programwhichencompasses SectionXIoftheASMECode."Thepurposeoftheproposedchangeistoeliminate therecirculation flowpathrequirement fortestingtheabovepumpsand,whereapplicable, allowtestingofthepumpsutilizing ahighcapacityflowpath.
Surveillance testsonpumprecirculation linesprovidelimitedinformation onthepump/system's abilitytoperformitssafetyfunction.
Thetestperformed onrecirculation offersonedatapointatminimalflowandhighestpossiblehead,equivalent inmostcasestothepump'sshutoffhead.Suchlowflowoperation couldproduceunstablehydraulic forceswhichmayresultininaccurate performance dataandmayalsobedetrimental tothepump.Pumpperformance testdatashouldbeobtainedatflowrates ascloseaspossibletothepump'sbestefficiency point.Atsuchflowrates,
'ydraulic forcesarerelatively stableandmoreaccuratedatais.,assured.
Furthermore, whilesomepumpdegradation canbeobservedatbothlowerandhigherflowrates, systemdegradation (e.g.,pipeblockage) canbeobservedonlyatthehigherflowrates, Ingeneral,pump/system degradation isfarmoreapparentathigherflowrates.
-Testingonhighercapacityflowpaths insteadofthepump'srecirculation lineis,therefore, preferable inordertoobtainmoreaccuratedata,betterdetermine pump/system conditions, andminimizelowflowpumpoperation.
Inadditiontoitsconsistency withNUREG-1431, theabovediscussion isconsistent withissuesaddressed inNUREG/CP-0123, "Proceedings oftheSecondNRC/ASMESymposium onPumpandValveTesting,"
inparticular withpapersentitled, "PumpTestingintheNuclearIndustry:
TheComprehensive TestandOtherConsiderations (page133),""TestQuality(page159),"and"Operating PumpsonMinimum.Flow(page557)."TheT/Srequirement limitingthesurveillance testtoonlytherecirculation linealsoplacesunduedemandsonthepump,system,andoperators forcertainpumps,likethecentrifugal chargingpumps.Technical specification testingofthesepumpsontheirrecirculation linesrequirethepumpstobesecuredfromoperation, thesystemrealigned, andthepumpsrestarted tosupportarecirculation alignment.
Byallowingforahighercapacityflowpath, systemrealignment becomesunnecessary andnormaloperational flowpaths neednotbedisturbed.
Operatorflexibility totestthepumpsonahighercapacityflowpath, wherepossible, willaidinminimizing requiredsystemmanipulations aswellasmaximizing component availability.
tl~~l' Attachment 1toAEP:NRC:1211 Page5TheproposedT/Salsoeliminates specificflowandpressuresetpoints thatcorrelate withtestingthecentrifugal
: charging, safetyinjection, residualheatremoval,containment spray,andmotordrivenandturbinedrivenauxiliary feedwater pumpsontheirrecirculation lines.Thespecificflowsandpressures thatdemonstrate thecapability ofthepumptoperformitsintendedsafetyfunctionareidentified intheCookNuclearPlantISTprogram.Theminimumperformance values,modeledintheaccidentanalysisoridentified astheminimumsystemrequirement, areusedintheISTprogramasthelowestacceptable valuesforcontinued operation.
Afinalbenefitofchangingthetestingrequirements ofthecentrifugal
: charging, safetyinjection, residualheatremoval,containment spray,andmotordrivenandturbinedrivenauxiliary feedwater pumpsisthatitwillassureuniformtestrequirements forT/Spumpswithsimilartestingrequirements.
Currently, essential servicewaterandcomponent coolingwaterpumpsarerequiredtobetestedinaccordance withtheISTprogram.Specificflowandpressurerequirements aredefinedbytheISTprogramandnottheT/Ssurveillance.
Insummary,theproposedchangewillassuretheacquisition ofaccuratedata,betterdetermine pump/system conditions, andminimizelowflowpumpoperation.
Additionally, thechangewillprovidesurveillance guidanceconsistent withNUREG-1431, NUREG/CP-0123, andexistingservicewatercomponent T/Sscurrently residentinCookNuclearPlantT/Ss.III.10CFR5092CRITERIPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:l.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.Criterion Thepurposeforconducting periodictestingofthepumpsidentified inthisproposedamendment istodetectgrossdegradation asrequiredbySectionXIoftheASMECode.TheCookNuclearPlantISTprogram,whichencompasses SectionXIoftheASMECode,isthebasisfortheexistingaswellastheproposedT/Ss.Testingthepumpsutilizing ahighcapacity Attachment 1toAEP:NRC:1211 Page6flowpathinsteadofarecirculation flowpath(whereapplicable) willhavenoimpactontheabilityofthepumptoperformitsintendedfunction.
Infact,itisexpectedthatthehighcapacityflowpathwillprovideamoreaccurateassessment ofthepump/systems'onditions andabilitytomeettheirsafetyfunction.
Theremovalofspecifictestparameters, infavorofreferencing theCookNuclearPlantISTProgram,willnotimpacttheabilityofthepumpstoperformtheirsafetyrelatedfunction.
ISTProgramparameters ensurethatthepumpsundertestprovidethesupportassumedintheplant'ssafetyanalyses.
Therefore, basedontheseconsiderations, itisconcluded thattheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Crterion2Theproposedchangewillprecludetheneedtorealignselectedpumpstotheirrecirculation flowpaths fortestingpurposes(whereapplicable).
Eliminating theneedforalignment totherecirculation flowpathaidsinmaximizing thepump'savailability toperformitssafetyfunction.
Asstatedpreviously, theremovalofthespecifictestparameters, infavorofreferencing theCookNuclearPlantISTProgramwillnotimpacttheabilityofthepumpstoperformtheirintendedsafetyfunction.
Thus,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Criterion 3Asstatedpreviously, testingoftheselectedpumpsutilizing ahighcapacityflowpathwillprovidegreaterassurance ofpumpcapability andmaximizepumpavailability.
Additionally, removingspecifictestparameters infavorofreferencing theCookNuclearPlantISTProgramwillhavenoimpactontheabilityofthepumpstoperformtheirintendedsafetyfunction.
Therefore, webelievethatthemarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety.
Jjl ATTACHMENT 2TOAEP:NRC:1211 EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES
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Revision as of 07:03, 29 June 2018

Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Modify Surveillance Requirements,Eliminating Requirement to Test Certain Safeguards Pumps
ML17332A714
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 03/31/1995
From: FITZPATRICK E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A715 List:
References
AEP:NRC:1211, NUDOCS 9504060176
Download: ML17332A714 (20)
v • d • e


Text

(ACCELERATED RIDSPROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9504060176 DOC.DATE:

95/03/31NOTARIZED:

YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.

IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)

SUBJECT:

Application foramendstolicensesDPR-58&DPR-74.Amends

.wouldmodifysurveillance requirements, eliminating requirement totestcertainsafeguards pumps.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR LENCLLSIZE:0+~TITLE:ORSubmittal:

GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:

cgXXECENTER01NRR/DRCH/HTCB NRR/DSSA/SRXB OGC/HDS2EXTERNAL:

NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNMSS/DWM/LLDP NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1122111111NOTETOALL"RlDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2083)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR13ENCL12 C~

indianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216FINarch31,1995AEP:NRC:1211 DocketNos.:50-31550-316U,S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:

DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENT TOTECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS'EVISE SAFETYRELATEDPUMPTESTINGTOELIMINATE RECIRCULATION ALIGNMENTS ANDBECONSISTENT WITHTHEINSERVICE TESTINGPROGRAM(IST)ANDNUREG-1431.

Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantunits1,and2~Specifically, weareproposing tomodifythesurveillance requirements toeliminate therequirement totestcertainsafeguards pumpsviatheirrecirculation flowpath.

Thefollowing pumpsareaffected; thecentrifugal chargingpumps,residualheatremovalpumps,motordrivenauxiliary feedwater pumps,andtheturbinedrivenauxiliary feedwater pumps.Twopumps,thecontainment spraypumpandsafetyinjection pump,willcontinuetobetestedontheirrecirculation linesbasedonexistingdesign.Thisproposedchangewouldalsoeliminate references tospecificdischarge pressures andflowsassociated withthesepumps.Thespecifictestparameters beingremovedarecontrolled bytheapprovedCookNuclearPlantISTprogram.Thefollowing unit1andunit2T/Ssurveillances areaffected:

4.1.2.3.1, 4.1.2.4,4.5.2f,4.6.2.1b, 4.7.1.2a, and4.7.1.2b.

TheexistingDonaldC.CookNuclearPlantT/Ssurveillance requirements associated withtheabovepumpsrequiretestingofthepumpsutilizing theirrecirculation lines.Thismethodoftestingprovideslimitedinformation onthepump/systems'bility toperformtheirsafetyrelatedfunctions.

Therefore, achangetotheT/Ssurveillance isbeingproposedtoallowtestingofthesepumpsusinghighercapacityflowpaths (whereapplicable).

{'GG038PDR+0~7++>03ZZ950g0~~<<l<osoooz>q1IPgR

'

U.S.NuclearRegulatory Commission Page2AEP:NRC:1211 Utilizing thistestmethodwouldprovideformoreaccuratedatatobetterdetermine theactualpump/system conditions.

Inadditiontotheimprovement inthequalityofacquiredtestdata,theproposedamendment wouldalsoaligntheaffectedCookNuclearPlantT/SswiththeMeritsProgramT/SsissuedasNUREG-1431.

Anadministrative changetoT/Ssurveillances 4.5.2.d.2, 4.5.2.e,4.6.2.c,4.7.1.2e, and4.7.1.2fisalsoincludedinthisamendment.

Thesespecifications eachcontained afootnoteassociated withtheunit2cycle9-10refueling outagewhichisnolongerapplicable, thusthefootnotes arebeingremoved.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.

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

copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Sincerely, EFE;E.Fitzpatrick VicePresident SWORNTOANDSUBSCRIBED BEFOREMEehTHIS~~DAYOF1995Attachment cc:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector

-BridgmanJ.R.PadgettNotaryPublic itt ATTACHMENT 1TOAEP:NRC:1211 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS 1I Attachment 1toAEP:NRC:1211 Page1DESCRIPTION OFCHANGESTheproposedamendment totechnical specifications (T/Ss)surveillances; 4.1.2.3.1, 4.1.2.4,4.5,2.d.2, 4.5.2.e,4.5.2f,4.6.2.lb, 4.6.2.c,4.7.1.2a, 4.7.1.2b, 4.7.1.2e, and4.7.1.2fmakethefollowing specificchangestoCookNuclearPlantUnits1and2T/Ss:S4123Changessurveillance 4.1.2.3.1 (page3/4l-ll)from:"Theaboverequiredchargingpumpshallbedemonstrated OPERABLEbyverifying, thatonrecirculation flow,thepumpdevelopsadischarge pressureofgreaterthanorequalto2390psigwhentestedpursuanttoSpecification 4.0.5."To:"Theaboverequiredchargingpumpshallbedemonstrated OPERABLEbyverifying thatthepump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5."Changessurveillance 4.1.2.4(page3/41-12)from:"Atleasttwochargingpumpsshallbedemonstrated OPERABLEbyverifying, thatonrecirculation flow,thepumpdevelopsadischarge pressureofgreaterthanorequalto2405psigwhentestedpursuanttoSpecification 4.0.5."To:"Atleasttwochargingpumpsshallbedemonstrated OPERABLEbyverifying thatthepump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5."Changessurveillance 4.5.2f(page3/45-5)from:"Byverifying thateachofthefollowing pumpsdevelopstheindicated discharge pressureonrecirculation flowwhentestedpursuanttoSpecification 4.0.5.1.Centrifugal chargingpumpgreaterthanorequalto2405psig 4

Attachment 1toAEP:NRC:1211 Page22.Safetyinjection pumpgreaterthanorequalto1409psig3.Residualheatremovalpumpgreaterthanorequalto190psig"To:"Byverifying thateachofthefollowing pump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhentestedpursuanttoSpecification 4.0.5.1.Centrifugal chargingpumps2.Safetyinjection pumps3.Residualheatremovalpumps"Changessurveillance 4.6.2.1b(page3/46-10)from:"Byverifying, thatonrecirculation flow,eachpumpdevelopsadischarge pressureofgreaterthanorequalto255psigataflowofgreaterthanorequalto700gpm,whentestedpursuanttoSpecification 4.0.5."To:"Byverifying thateachcontainment spraypump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped head."Changessurveillance 4.7.1,2a(page3/47-6)from:"Verifying thateachmotordrivenpumpdevelopsanequivalent discharge pressureofgreaterthanorequalto1375psig(1240psigforUnit2)at60Fonrecirculation flow.TQ:"Verifying thateachmotordrivenauxiliary feedwater pump'sdeveloped headatthetestflowpointisgreaterthanorequaltotherequireddeveloped head."

Attachment 1toAEP:NRC:1211 Page3TS4.712bChangessurveillance 4.7.1.2b(page3/47-6)from:"Verifying thattheturbinedrivenpumpdevelopsanequivalent discharge pressureofgreaterthanorequalto1285psig(1180psigforUnit2)at60'Fandataflowofgreaterthanorequalto700gpmwhenthesecondary steamsupplypressureisgreaterthan310psig.Theprovisions ofSpecification 4'.4arenotapplicable forentryintoMODE3.To.'Verifyingthattheturbinedrivenauxiliary feedwaterpump'developed headatthetestflowpointisgreaterthanorequaltotherequireddeveloped headwhenthesecondary steamsupplypressureisgreaterthan310psig.Theprovisions ofSpecification

4.0. 4arenotapplicable

forentryintoMODE3."4.52.d.2452e462c47.12eand4.7.12fDeletethe"daggers" andassociated footnotereference toTechnical Specification 4.0.8.Thisreference wasspecifically associated withasurveillance extension approvedduringUnit2cycle9-10.Itisnolongerapplicable.

II.JUSTIFICATION FORCHANGESTheproposedtechnical specification changeeliminates thesurveillance requirement totesttheUnit1andUnit2centrifugal

charging, safetyinjection, residualheatremoval,containment spray,motordrivenauxiliary feedwater andsteamdrivenauxiliary feedwater pumpsontheirrecirculation lines.Itshouldbenotedthatthecontainment spraypumpsandsafetyinjection pumpswillcontinuetobetestedontheirrecirculation flowpaths asaresultofexistingsystemdesign.Thisproposedchangewouldalsoremovethereferences tospecificdischarge pressures andflowsassociated withthesepumps.Thischangeisconsistent withtheassumptions andguidanceprovidedinNUREG-1431,"Standard Technical Specifications, Westinghouse Plants,"whichstates:"Thepurposeforconducting periodictestingofthepumpslistedaboveistodetectgrossdegradation causedbyimpellerstructural damageorotherhydraulic component problems.

ThistestingisrequiredbySectionXIoftheAmericanSocietyofMechanical Engineers (ASME)Code.Thetestingdescribed abovemaybeaccomplished bymeasuring thepumpdeveloped headatonlyonepointofthepumpperformance curve.Thisverifiesboththatthemeasured Attachment 1toAEP:NRC:1211 Page4performance iswithinanacceptable tolerance oftheoriginalpumpbaselineperformance andthattheperformance atthetestflowisgreaterthanorequaltotheperformance assumedintheplantsafetyanalysis.

Surveillance requirements arespecified intheInservice Testing(IST)Programwhichencompasses SectionXIoftheASMECode."Thepurposeoftheproposedchangeistoeliminate therecirculation flowpathrequirement fortestingtheabovepumpsand,whereapplicable, allowtestingofthepumpsutilizing ahighcapacityflowpath.

Surveillance testsonpumprecirculation linesprovidelimitedinformation onthepump/system's abilitytoperformitssafetyfunction.

Thetestperformed onrecirculation offersonedatapointatminimalflowandhighestpossiblehead,equivalent inmostcasestothepump'sshutoffhead.Suchlowflowoperation couldproduceunstablehydraulic forceswhichmayresultininaccurate performance dataandmayalsobedetrimental tothepump.Pumpperformance testdatashouldbeobtainedatflowrates ascloseaspossibletothepump'sbestefficiency point.Atsuchflowrates,

'ydraulic forcesarerelatively stableandmoreaccuratedatais.,assured.

Furthermore, whilesomepumpdegradation canbeobservedatbothlowerandhigherflowrates, systemdegradation (e.g.,pipeblockage) canbeobservedonlyatthehigherflowrates, Ingeneral,pump/system degradation isfarmoreapparentathigherflowrates.

-Testingonhighercapacityflowpaths insteadofthepump'srecirculation lineis,therefore, preferable inordertoobtainmoreaccuratedata,betterdetermine pump/system conditions, andminimizelowflowpumpoperation.

Inadditiontoitsconsistency withNUREG-1431, theabovediscussion isconsistent withissuesaddressed inNUREG/CP-0123, "Proceedings oftheSecondNRC/ASMESymposium onPumpandValveTesting,"

inparticular withpapersentitled, "PumpTestingintheNuclearIndustry:

TheComprehensive TestandOtherConsiderations (page133),""TestQuality(page159),"and"Operating PumpsonMinimum.Flow(page557)."TheT/Srequirement limitingthesurveillance testtoonlytherecirculation linealsoplacesunduedemandsonthepump,system,andoperators forcertainpumps,likethecentrifugal chargingpumps.Technical specification testingofthesepumpsontheirrecirculation linesrequirethepumpstobesecuredfromoperation, thesystemrealigned, andthepumpsrestarted tosupportarecirculation alignment.

Byallowingforahighercapacityflowpath, systemrealignment becomesunnecessary andnormaloperational flowpaths neednotbedisturbed.

Operatorflexibility totestthepumpsonahighercapacityflowpath, wherepossible, willaidinminimizing requiredsystemmanipulations aswellasmaximizing component availability.

tl~~l' Attachment 1toAEP:NRC:1211 Page5TheproposedT/Salsoeliminates specificflowandpressuresetpoints thatcorrelate withtestingthecentrifugal

charging, safetyinjection, residualheatremoval,containment spray,andmotordrivenandturbinedrivenauxiliary feedwater pumpsontheirrecirculation lines.Thespecificflowsandpressures thatdemonstrate thecapability ofthepumptoperformitsintendedsafetyfunctionareidentified intheCookNuclearPlantISTprogram.Theminimumperformance values,modeledintheaccidentanalysisoridentified astheminimumsystemrequirement, areusedintheISTprogramasthelowestacceptable valuesforcontinued operation.

Afinalbenefitofchangingthetestingrequirements ofthecentrifugal

charging, safetyinjection, residualheatremoval,containment spray,andmotordrivenandturbinedrivenauxiliary feedwater pumpsisthatitwillassureuniformtestrequirements forT/Spumpswithsimilartestingrequirements.

Currently, essential servicewaterandcomponent coolingwaterpumpsarerequiredtobetestedinaccordance withtheISTprogram.Specificflowandpressurerequirements aredefinedbytheISTprogramandnottheT/Ssurveillance.

Insummary,theproposedchangewillassuretheacquisition ofaccuratedata,betterdetermine pump/system conditions, andminimizelowflowpumpoperation.

Additionally, thechangewillprovidesurveillance guidanceconsistent withNUREG-1431, NUREG/CP-0123, andexistingservicewatercomponent T/Sscurrently residentinCookNuclearPlantT/Ss.III.10CFR5092CRITERIPer10CFR50.92,aproposedchangedoesnotinvolveasignificant hazardsconsideration ifthechangedoesnot:l.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.Criterion Thepurposeforconducting periodictestingofthepumpsidentified inthisproposedamendment istodetectgrossdegradation asrequiredbySectionXIoftheASMECode.TheCookNuclearPlantISTprogram,whichencompasses SectionXIoftheASMECode,isthebasisfortheexistingaswellastheproposedT/Ss.Testingthepumpsutilizing ahighcapacity Attachment 1toAEP:NRC:1211 Page6flowpathinsteadofarecirculation flowpath(whereapplicable) willhavenoimpactontheabilityofthepumptoperformitsintendedfunction.

Infact,itisexpectedthatthehighcapacityflowpathwillprovideamoreaccurateassessment ofthepump/systems'onditions andabilitytomeettheirsafetyfunction.

Theremovalofspecifictestparameters, infavorofreferencing theCookNuclearPlantISTProgram,willnotimpacttheabilityofthepumpstoperformtheirsafetyrelatedfunction.

ISTProgramparameters ensurethatthepumpsundertestprovidethesupportassumedintheplant'ssafetyanalyses.

Therefore, basedontheseconsiderations, itisconcluded thattheproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Crterion2Theproposedchangewillprecludetheneedtorealignselectedpumpstotheirrecirculation flowpaths fortestingpurposes(whereapplicable).

Eliminating theneedforalignment totherecirculation flowpathaidsinmaximizing thepump'savailability toperformitssafetyfunction.

Asstatedpreviously, theremovalofthespecifictestparameters, infavorofreferencing theCookNuclearPlantISTProgramwillnotimpacttheabilityofthepumpstoperformtheirintendedsafetyfunction.

Thus,itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Criterion 3Asstatedpreviously, testingoftheselectedpumpsutilizing ahighcapacityflowpathwillprovidegreaterassurance ofpumpcapability andmaximizepumpavailability.

Additionally, removingspecifictestparameters infavorofreferencing theCookNuclearPlantISTProgramwillhavenoimpactontheabilityofthepumpstoperformtheirintendedsafetyfunction.

Therefore, webelievethatthemarginforsafetyasdefinedin10CFR100hasnotbeenreduced.Basedontheseconsiderations, itisconcluded thatthechangesdonotinvolveasignificant reduction inamarginofsafety.

Jjl ATTACHMENT 2TOAEP:NRC:1211 EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES

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