ML082320016

Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency Using the Consolidated Line Item Improvement Process

ML082320016
Person / Time
Site:	Nine Mile Point
Issue date:	08/18/2008
From:	Belcher S Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML082320016 (14)

Text

Sam L.Belcher PlantGeneralManager 0.:***\Constellation.....e Nine Mile Point Nuclear StationU.S.NuclearRegulatoryCommission Washington

,DC20555-0001 P.O.Box 63 Lycoming, New York 13093 315.349.5205 315.349.1321 Fax August 18,2008 ATTENTION:

SUBJECT:

DocumentControlDeskNineMilePointNuclearStation Unit No.1;DocketNo.50-220RenewedFacilityOperatingLicenseNo.DPR-63ApplicationforTechnical SpecificationChangeRegardingRevision ofControlRodNotchSurveillanceTestFrequencyUsingtheConsolidatedLineItemImprovement Process Inaccordancewiththeprovisions of10CFR50.90,NineMilePointNuclearStation

,LLC(NMPNS)issubmittingarequestforanamendmenttotheTechnicalSpecifications(TS)forNineMilePointUnit1 (NMP1).TheproposedamendmentwouldrevisetheTSsurveillancerequirement(SR)frequencyinTS3/4.1.1,"ControlRodSystem."Attachment1providesadescription oftheproposedchange,therequested confirmation of applicability,andplant-specificverifications.Attachment2providestheexistingTSpagemarked-uptoshowtheproposedchange.AssociatedTSBaseschangesaremarked-upinAttachment3.TheTSBaseschangesareprovidedforinformationonlyandwillbe processedinaccordancewiththeNMP1TS6.5.6,"TechnicalSpecifications(TS)BasesControl Program."Attachment4providesasummary of theregulatorycommitmentsmadeinthissubmittal.NMPNSrequestsapproval oftheproposedLicenseAmendmentbyFebruary16,2009,withtheamendmentbeingimplementationwithin60days of approval oftheamendment.

Inaccordancewith10CFR50.91,NMPNShasprovidedacopy ofthislicenseamendmentrequest

, withattachments,totheappropriatestaterepresentative.

DocumentControlDeskAugust18,2008Page2Shouldyouhaveanyquestionsregardingtheinformationinthissubmittal,pleasecontactT.F.Syrell,LicensingDirector,at(315)349-5219.Verytrulyyours,STATEOF NEW YORK TO WIT: COUNTY OF OSWEGO I , Sam L.Belcher,beingdulysworn,statethatIamPlantGeneralManager,andthatIamduly authorizedtoexecuteandfilethisrequeston behalf ofNineMilePoint NuclearStation,LLC.Tothebest of myknowledgeandbelief,thestatementscontainedinthisdocumentaretrueandcorrect.Totheextentthatthesestatementsarenotbasedonmy personalknowledge,theyarebasedupon information provided byotherNineMilePointemployeesand/orconsultants.SuchinformationhasbeenreviewedinaccordancewithcompanypracticeandIbelieveittobereliable.Subscribedandswornbeforeme,aNotaryPublicinandfortheState ofNewYorkandCounty ofOswego,this 181L day of2008.WITNESSmyHandandNotarialSeal:

My Commission Expires:--=-'---1' 1,a{a"-""o"--'--'o=---

__ SLB/GB/Notaryuic TGMYALaoNEI 1 NoWyStated

.

• My CommIsSion Expires.Attachments:1

.DescriptionandAssessment 2.ProposedTechnicalSpecificationsChanges(Marked-UpPage) 3.ProposedTechnicalSpecificationsBasesChanges(Marked-UpPage) 4.Summary of Regulatory CommitmentsMadeinthisSubmittal DocumentControlDesk August 18,2008Page3cc:S.J.Collins,NRCRegionalAdministrator,RegionIR.V.Guzman,Jr.,NRCProject ManagerE.C.Knutson

,SeniorNRC Residen t InspectorJ.P.Spath, NYSERDA ATTACHMENT 1 DESCRIPTION AND ASSESSMENTTABLEOF CONTENTS

1.0DESCRIPTION

2.0ASSESSMENT2.1Applicability ofPublishedSafetyEvaluation2.2OptionalChangesandVariations3.0REGULATORYANALYSIS3.1NoSignificantHazardsConsiderationDetermination3.2VerificationandCommitments4.0ENVIRONMENTALEVALUATIONNineMilePoint NuclearStation,LLCAugust18,2008 ATTACHMENT1DESCRIPTIONANDASSESSMENT

1.0DESCRIPTION

TheproposedamendmentwouldreviseNineMilePointUnit1(NMP1)TechnicalSpecifications(TS)Section3/4.1.1

,"ControlRodSystem"toincreasethesurveillancerequirement(SR)frequencyassociatedwithcontrolrodexercising.Currently,SR4.1.1a.(2)requireseachpartiallyorfullywithdrawncontrolrodtobeexercisedatleastonceeachweek(7days).TheproposedchangewouldrevisetherequiredSRfrequencyfromonceeachweektoonceevery31days.ThischangeisconsistentwithNuclearRegulatory Commission (NRC)approvedIndustry/TechnicalSpecificationTaskForce(TSTF)StandardTechnicalSpecification(STS)changeTSTF-475,Revision1,andNUREG-1433,"StandardTechnicalSpecificationsGeneralElectricPlants, BWR/4,"Revision3.1.

The Federal RegisterNoticepublishedonNovember13,2007announcedtheavailability ofthisTSimprovementthroughtheconsolidatedlineitemimprovementprocess(CLIIP).2.0ASSESSMENT2.1ApplicabilityofPublishedSafetyEvaluationNineMilePointNuclearStation,LLC(NMPNS)hasreviewedthesafetyevaluationdatedNovember13,2007aspart oftheCLIIP.Thisreviewincludedareview oftheNRC staffsevaluation,aswellasthesupportinginformationprovidedtosupportTSTF-475,Revision1.NMPNShasconcludedthatthe justificationspresentedintheTSTFproposalandthesafety evaluationpreparedbytheNRC staff areapplicabletoNMPIand justifythisamendmentfortheincorporation ofthechangestothe NMPI TS.2.2OptionalChangesandVariationsTheNMPIisacustomTechnicalSpecificationsplantand,therefore,theapplicableTSandassociatedBasessectionsarenotformattedinaccordancewithNUREG-1433forBWR/4plants.Thishasresultedinminorvariationstothe NMPI adoption ofTSTF-475thataregrammaticalandadministrativeinnatureanddonotalterorchangethetechnicalintent ofthechangesproposedforcontrolrodoperabilitysurveillancefrequencyrequirementsforSR4.1.1a.(2).Additionally,therevisednotchtestingfrequencyaddressedinTSTF-475,Revision1isspecifictofullywithdrawncontrolrods,sincepartiallywithdrawncontrolrodsalreadyhavea31daytestfrequencyascontainedinStandardTechnicalSpecifications(NUREG-1433,Revision3.1).Currently,NMPITSSR4.1.1a.(2)requirespartiallywithdrawncontrolrodstobeexercisedatleastonceeachweek.TheproposedNMPIamendmentaddresseschangestoinclude"withdrawncontrolrods"(inclusive offullyandpartiallywithdrawn).ThechangeisbaseduponSTSandTSTF-475

,Revision1.Thepurpose oftheweeklysurveillancefornotchtestingpartiallywithdrawncontrolrodsisthesameasforfullywithdrawncontrolrods

,thatis,toconfirmcontrolrodinsertioncapability.Baseduponindustryoperatingexperience,asdiscussedinthesafetyevaluationforTSTF-475,Revision1,astuckcontrolrodisanextremelyrareevent.Also,asdiscussedinthesafetyevaluation,theproposedchangefromaweeklytoamonthlytestfrequencyhasbeendeterminedtobeacceptablebasedondemonstratedhistoricalreliability oftheControlRodDriveSystemandthatmonthlytestingwillstillprovidealarge number ofteststoprovideconfidencethatanyproblemswiththesystemwouldbeidentified.Theindustryoperatingexperienceisinclusive ofnotchtesting ofbothpartiallyandfullywithdrawncontrol rods.10f2 ATTACHMENT 1 DESCRIPTION AND ASSESSMENT In support ofthistestfrequencychange,aneditorialchangewasalsoincludedinSR 4.1.Ia.(2)todetailtheconditionsrequiredtoperformtheSR,asprovidedbytheNRCModelSafetyEvaluationfor 475 ,RevisionI.Specifically,theminimumpowerlevelconditions(powerlevelgreaterthanthelowpowersetpoint oftheRodWorthMinimizer)andminimumcontrolrodwithdrawallimits(atleastonenotch)havebeenincludedintheSR.

3.0 REGULATORY ANALYSIS3.1No Significant Hazards Consideration DeterminationNineMilePointNuclearStation(NMPNS)hasreviewedtheproposednosignificanthazardsconsiderationdetermination(NSHCD)publishedinthe Federal Registeraspart oftheconsolidatedlineitemimprovementprocess(CLIIP).NMPNShasconcludedthattheproposedNSHCDpresentedinthe Federal RegisternoticeisapplicabletoNineMilePointUnit1 (NMPI)andisherebyincorporatedbyreferencetosatisfytherequirements of10CFR50.91(a).Theproposedchangewouldalsorevisethesurveillancerequirement(SR)frequencyforexercisingpartiallywithdrawncontrolrodsfromweeklytomonthly.NMPNShasreviewedtheNSHCDpublishedinthe Federal RegisteraspartoftheCLIIPandconcludeditadequatelydescribeschangingthenotchtestingrequirementfromweeklytomonthlyforallcontrolrods(partiallyorfullywithdrawn).

3.2 Verification and CommitmentsAsdiscussedinthenotice ofavailabilitypublished inthe Federal Regist eronNovember13,2007forthisTSimprovement,NMPNShasverifiedtheapplicability ofTSTF-475to NMPI,andcommitstoestablishingTechnicalSpecificationBasesfortheTSasproposedinTSTF-475

,Revision1asdescribedinthislicenseamendmentrequest.ThischangeisbasedonTSTFchangetravelerTSTF-475(Revision1)thatproposesrevisionstotheSTSbyrevisingthefrequency ofSR3/4.1.1,notchtesting ofawithdrawncontrolrod,from"7daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM"to"31daysafterthecontrolrodiswithdrawnandTHERMALPOWERisgreaterthantheLPSP ofRWM." 4.0 ENVIRONMENTAL EVALUATIONNMPNShasreviewedtheenvironmentalevaluationincludedinthemodelsafetyevaluationdatedNovember13,2007aspart oftheCLIIP.NMPNShasconcludedthatthe staffsfindingspresentedinthatevaluationareapplicableto NMPIandtheevaluationisherebyincorporatedbyreferenceforthis application.

20f2 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES(MARKED-UPPAGE)TSPage30 Nine Mile Point Nuclear Station, LLC August18,2008 or LIMITING CONDITION FOR OPERATION secondary containment penetration flowpathnot isolated.(e)If Specification 3.1.1a(1)(a) is not met whileinthe refueling condition, then: Immediatelysuspendcore alterations, except for fuel assembly removal, and Immediately initiate action to fully insert all insertable controlrodsincorecells containingoneormorefuel assemblies.

(2)Reactivitymargin-stuck control rods Control rods which cannot be moved with controlroddrive pressureshallbe considered inoperable.

Inoperable controlrodsshallbe valved out ofservice,insuch positions that Specification 3.1.1a(1)(a)ismet.Innocaseshallthe number of non-fully inserted rods valved out of service be greaterthansix during power operation.

If this specification is not met, the reactorshallbeplacedinthe cold shutdown condition.Ifa partially or fully withdrawn control rod drive cannot be moved withdriveorscram pressure the reactorshallbe broughttoa shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless investigation demonstrates that the cause of the failure is notduetoafailed control rod drive mechanism collet housing.SURVEILLANCE REQUIREMENT y5fJ (AMENDMENT NO.-'t-42-,-+ae-)

30 INSERT: Each withdrawncontrolrodshallbe exercisedata frequencyof31daysafterthecontrolrodhasbeen withdrawnandpowerlevelis greaterthanthelowpowersetpointoftheRWM.Inserteach withdrawncontrolrodatleastonenotch.

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS BASES CHANGES (MARKED-UP PAGE)TSBasesPage38NineMile Point Nuclear Station, LLC August18,2008

,..BASESFOR 3.1.1 AND 4.1.1 CONTROL ROD SYSTEM The allowableinoperablerod patterns willbedeterminedusing informationobtainedinthe startup test program supplemented by calculations.

During initial startup, the reactivity conditionofthe as-built core will be determined.

Also, sub-critical patterns of widely separated withdrawn control rods willbeobservedinthe controlrodsequencesbeingused.The observations, together with calculated strengthsofthe strongest controlrodsin these patterns willcompriseasetof allowable separations of malfunctioningrods.Duringthefuel cycle, similar observations madeduringanycold shutdowncanbeused toupdateand/orincreasethe allowable patterns..Alsoifdamge within,thecorolroddrivemeanismandinp icular, cracks'drive intern housings, canno beruledouthenagenericprlem affecting a nnotberuled ut.Circumfe ntial cracksresungfromsessassisted inter anular corrosionaveoccurredine collethousiofdrivesateveralSWRs.

Thitypeofcracngcould occur in numberofdriveandifthe crack propagatedunseveranceofhe collet housing ccurred,scmcouldbeprevtedinthe affecterods.Limitingeperiodofop ation with a tentially severed IIetousingandrequirig increased survei ance after detecngone stuck r (j willassureatthe reactor willotbe operated witharge numberofro withfailedcolle housings.*FSAR b.Control Rod Withdrawal (1)Control rod dropout accidents as discussed in Appendix E*canleadto significantcoredamage.

If coupling integrity is maintained, the possibilityofarod dropout accident is eliminated.

The overtravel position feature provides a positive checkasonlyuncoupled drives mayreachthis position.Neutron instrumentationresponsetorod movement provides an indirect verification thattherodiscoupledtoitsdrive.

Detailsofthe controlroddrivecouplingaregivenin Section IV.B.6.1-.AMENDMENT 38 INSERT: Control rod insertion capability is demonstrated by inserting each partiallyorfully withdrawn controlrodat least one notch and observingthatthecontrolrodmoves.The control rod may then be returnedtoits original position.This ensuresthatthe controlrodisnot stuckandisfree to insertonascramsignal.This surveillanceisnot required when thermal powerisless than or equaltothe low power set point (LPSP)oftheRWM,since notch insertion maynotbe compatible with the requirements oftheRWM.The31day surveillance test frequencytakesinto account operating experience related to changesinCRD performance.

This surveillance requirementallows31daysafter withdrawal of the control rod concurrent with thermal power greater thantheLPSP of the RWM to perform the surveillance.

The requirement to exercise controlrodsatleastonceper24 hoursinthe event power operation is continuing withtwoormore control rods which are valved out of serviceoronefullyor partially withdrawn control rod whichcannotbe moved, provides a reasonabletimeto test the controlrodsand provide assurance of the reliability of the remaining control rods.

ATTACHMENT 4

SUMMARY

OF REGULATORY COMMITMENTSMADEIN THIS SUBMITTALNineMile Point Nuclear Station, LLC August18,2008 ATTACHMENT 4

SUMMARY

OF REGULATORY COMMITMENTS MADE IN THIS SUBMITTALLISTOF REGULATORY COMMITMENTSThefollowingtableidentifiesthoseactionscommittedtobyNMPNSinthisdocument.Anyotherstatementsinthissubmittalareprovidedforinformationpurposesandarenotconsideredtoberegulatorycommitments.PleasedirectquestionsregardingthesecommitmentstoT.F.Syrell,LicensingDirector,at(315)349-5219.

REGULATORY COMMITMENT DUE DATE/EVENTNMPNSwillestablishtheTechnicalSpecificationsBasesforThiscommitmentwill beTS3/4.1.1consistentwiththoseshowninTSTF-475

, Revisionimplementedwithin

,60daysfrom 1,"ControlRodNotchTestingFrequencyandSRMInsertthedate oftheapproval of theControlRodAction "asdescribed inthelicenseamendmentproposedamendment.

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