ML081630307

Surry Power, Units 1 and 2 - Proposed License Amendment Request Revision of Technical Specification 3.12

ML081630307
Person / Time
Site:	Surry
Issue date:	06/09/2008
From:	Bischof G T Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
08-0310
Download: ML081630307 (39)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 9.2008 10CFR50.90U.S.NuclearRegulatoryCommission A TIN:DocumentControlDeskWashington,D.C.20555 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATIONUNITS1AND2 PROPOSED LICENSE AMENDMENT REQUEST REVISION OF TECHNICAL SPECIFICATION 3.12SerialNo.08-0310 SPS/L1C-CGL RODocketNos.50-280 50-281LicenseNos.DPR-32 DPR-37Pursuantto10CFR50.90,VirginiaElectricandPowerCompany(Dominion)requestsamendments,intheformofchangestotheTechnicalSpecifications(TS)toFacilityOperatingLicenseNumbersDPR-32andDPR-37forSurryPowerStationUnits1and2,respectively.TheproposedchangerevisesactionstatementsinTS3.12forinsertionlimitandshutdownmarginrequirements,revisestheapplicabilityfortheoperabilityoftheRodPositionIndicationandBankDemandPositionIndicationSystems,revises/addsactionstatementsforrodpositionindication,andaddsactionstatementsforgroupstepdemandcounters.TheserevisionsenhancethecompletenessoftheSurryTSandareconsistentwithNUREG-1431, StandardTechnicalSpecifications,WestinghousePlants,Revision3.0.ThreeadditionalminorchangesareproposedtomakeaterminologycorrectionandtoaddresstwominorTSdiscrepanciesintroducedbypreviouslicenseamendments.ArelatedTS3.12BasischangereflectingtheproposedTS3.12revisionsisincludedfortheNRC'sinformation.AdiscussionoftheproposedchangeisprovidedinAttachment1.Themarked-upandtypedproposedTSpagesareprovidedinAttachments2and3,respectively.Wehaveevaluatedtheproposedamendmentandhavedeterminedthatitdoesnotinvolveasignificanthazardsconsiderationasdefinedin10CFR50.92.ThebasisforourdeterminationisincludedinAttachment1.Wehavealsodeterminedthatoperationwiththeproposedchangewillnotresultinanysignificantincreaseintheamountofeffluentsthatmaybereleasedoffsiteandnosignificantincreaseinindividualorcumulativeoccupationalradiationexposure.Therefore,theproposedamendmentiseligibleforcategoricalexclusionfromanenvironmentalassessmentassetforthin10CFR51.22(c)(9).Pursuantto10CFR51.22(b),noenvironmentalimpactstatementorenvironmentalassessmentisneededinconnectionwiththeapprovaloftheproposedchange.TheproposedTSchangehasbeenreviewedandapprovedbytheFacilitySafetyReviewCommittee.

VICIOL.IML

.-.,NIIC: e_.n....of WI........,-e_lllan.......,SerialNo.08-0310DocketNos.50-280/281Page2of3 ApprovalofthisproposedTSchangeisrequestedbyJune30,2009.Dominionrequestsa50-day implementationperiodfollowingNRCapprovaloftherequested license amendments.Ifyouhaveanyquestionsorrequireadditionalinformation,pleasecontactMr.GaryD.Millerat(804)273-2771.

Sincerely, Vice President-Nuclear Engineering Attachments1.DiscussionofChange2.ProposedTechnicalSpecificationsPages(Mark-Up)3.ProposedTechnicalSpecificationsPages(Typed)

Commitmentsmadeinthisletter:None COMMONWEALTH OF VIRGINIA))COUNTYOFHENRICO)Theforegoing documentwasacknowledgedbeforeme,inandfortheCountyand Commonwealthaforesaid,todaybyGerald T.Bischof,whoisVice President-NuclearEngineering,ofVirginiaElectricandPowerCompany.Hehasaffirmedbeforemethatheisdulyauthorizedtoexecuteandfiletheforegoing document in behalfofthatCompany,andthatthestatementsinthe documentaretruetothebestofhisknowledgeandbelief.

Acknowledgedbeforemethis q 7!'dayof 9LtA<...c-

,2008.My Commission Expires:31,;{%.&*L.:JIuaNotaryPublic cc:U.S.NuclearRegulatoryCommissionRegionIISamNunnAtlantaFederalCenter61ForsythStreet,SWSuite23T85Atlanta,Georgia30303 NRC SeniorResidentInspectorSurryPowerStationStateHealth Commissioner Virginia DepartmentofHealthJamesMadisonBuilding-i h Floor 109 Governor StreetRoom730Richmond,Virginia23219Mr.S.P.LingamNRCProject Manager-SurryandNorthAnnaU.S.NuclearRegulatoryCommissionOneWhiteFlintNorth11555RockvillePikeMailStop8G9ARockville,Maryland20852SerialNo.08-0310DocketNos.50-280/281Page3of3 ATTACHMENT 1 DISCUSSION OF CHANGE VirginiaElectricand Power Company (Dominion)

Surry PowerStationUnits1and2 Serial No.08-0310 DocketNos.50-280/281 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 Attachment DISCUSSIONOFCHANGE 1.

SUMMARY

DESCRIPTIONVirginiaElectricandPowerCompany(Dominion)proposesachangetotheSurryPowerStationUnits1and2TechnicalSpecifications(TS)pursuantto10CFR50.90.TheproposedchangerevisesactionstatementsinTS3.12forinsertionlimitandshutdownmarginrequirements,revisestheapplicabilityfortheoperabilityoftheRodPositionIndicationandBankDemandPositionIndicationSystems,revises/addsactionstatementsforrodpositionindication,andaddsactionstatementsforgroupstepdemandcounters.TheserevisionsareconsistentwithNUREG-1431, StandardTechnicalSpecifications,WestinghousePlants,Revision3.0(Reference1).ThreeadditionalminorchangesareproposedtomakeaterminologycorrectionandtoaddresstwominorTSdiscrepanciesintroducedbypreviouslicenseamendments.ArelatedTS3.12BasischangereflectingtheproposedTS3.12revisionsisincludedfortheNRC'sinformation.TheproposedTSchangehasbeenreviewed,andithasbeendeterminedthatnosignificanthazardsconsiderationexistsasdefinedin10CFR50.92.Inaddition,ithasbeendeterminedthatthechangequalifiesforcategoricalexclusionfromanenvironmentalassessmentassetforthin10CFR51.22(c)(9);therefore,noenvironmentalimpactstatementorenvironmentalassessmentisneededinconnectionwiththeapprovaloftheproposedTSchange.

2.DETAILED DESCRIPTION

2.1 Proposed

ChangeThefollowingspecificchangestotheSurryUnits1and2TSareproposed:*TS3.12.AControlBankInsertionLimits-ReviseTS3.12.A.1requirementsandactionstatementsfortheshutdownbanks.-ReviseTS3.12.A.2requirementsandactionstatementsforthecontrolbanks.*TS3.12.BPowerDistributionLimits-ReviseTS3.12.B.6.ctodeletethe U+"associatedwithareferenceto10%QUADRANTPOWERTILT.

Page1of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 Attachment*TS3.12.CControlRodAssemblies-ReviseTS3.12.C.3.b.1)(b)toreplacethereferencetoFigure3.12-1Aand Figure 3.12-1BwithareferencetotheCOREOPERATINGLIMITSREPORT.*TS3.12.ERodPositionIndicationSystem-RevisethetitleofTS3.12.Efrom"RodPositionIndicationSystem"to"RodPositionIndicationSystemandBankDemandPositionIndicationSystem."-RevisetheapplicabilityofTS3.12.

E.1forrodpositionindicationandgroupstepdemandcounteroperabilitytobe"frommovementofcontrolbankstoachievecriticalityandwiththeREACTORCRITICAL."TherevisedapplicabilityofTS3.12.E.1necessitatesrevisionsinTS3.12.Cforconsistency.-RevisetheexistingTS3.12.E.2.a,TS3.12.E.2.b,andTS3.12.E.3actionstatementsandaddactionsinTS3.12.E.4,aswellaspartofTS3.12.E.6,forrodpositionindicationinoperability.-AddTS3.12.E.5,aswellaspartofTS3.12.E.6,toincludeactionstatementsforgroupstepdemandcounterinoperability.*TS3.12.GShutdownMargin-AddTS3.12.Gtoincludeshutdownmarginrequirementsandactionstatement.*TS3.12Basis-RevisetheBasisforTS3.12toreflecttherevisionstoTS3.12.E.TheTS3.12BasischangeisincludedfortheNRC'sinformation.*TS4.10ReactivityAnomalies-ReviseTS4.10.AtodeletetherequirementtoreporttheevaluationofthespecifiedboronconcentrationdiscrepancytotheNuclearRegulatoryCommissionperSection6.6oftheTS.

3.TECHNICAL EVALUATIONThefollowingdiscussionprovidesjustificationfortheproposedchangesdiscussedinSection2.1above.TheproposedchangerevisesactionstatementsinTS3.12forinsertionlimitandshutdownmarginrequirements,revisestheapplicabilityfortheoperabilityoftheRodPositionIndicationandBankDemandPositionIndication Page 2of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 AttachmentSystems,revises/addsactionstatementsforrodpositionindication,andaddsactionstatementsforgroupstepdemandcounters.Thischangeisbeingmadetoenhance the completenessoftheSurryTSandtoachieveconsistencywithNUREG-1431forStandard[Improved]TechnicalSpecifications(ITS)withrespecttorequirementsandactionstatementsforinsertionlimits,shutdownmargin(SDM),rodpositionindication,andgroupstepdemandcounters.Threeadditionalminorchangesareproposedtomakea terminologycorrectionandtoaddresstwominorTS discrepancies introducedbypreviouslicenseamendments.ArelatedTS3.12BasischangereflectingtheproposedTS3.12revisionsisincludedfortheNRC'sinformation.

15 3.12.A Control Bank Insertion LimitsTheexistingrequirementsinTS3.12.A.1specifyingthattheshutdowncontrolrodassembliesshallbefullywithdrawnwheneverthereactoriscriticalareidenticaltotherequirementsintheoriginalSurryTS(Reference2).Theexistingaction statementswereaddedbyTSAmendments189/189(Reference3).ConsistentwiththeITSrequirementsinSection3.1.5ofNUREG-1431,theproposedchangeindicatesthattheshutdownbanksshallbewithintheinsertionlimitsspecifiedintheCOREOPERATINGLIMITSREPORT(COLR)andrevisestheactionstatementstobeidenticaltotheRequiredActionsinITSSection3.1.5.TheexistingrequirementsandactionstatementsinTS3.12.A.2forthecontrolbanks wheneverthereactoriscriticalwereincorporatedintotheSurryTSby Amendments189/189(Reference3).ConsistentwiththeITSrequirementsinSection3.1.6ofNUREG-1431forcontrolbankinsertionlimits,theproposedchangeindicatesthecontrolbanksshallbewithintheinsertionlimitsspecifiedintheCOLRandrevisestheactionstatementstobeidenticaltotheRequiredActionsinITSSection3.1.6.

15 3.12.B Power Distribution Limits Surry TechnicalSpecificationChange NO.6(Reference4)includedTSchangestoprovideprotectionagainsttheeffectsoffueldensification.InTS3.12.B.2.c(nownumberedTS3.12.B.6.c),theterminologyof

t10%quadrant(toaverage)powertiltwasintroduced.Theproposedchangedeletesthe u:t"associatedwiththereferenceto10%QUADRANTPOWERTILT(QPT)sinceanegativetiltcannotexist.

153.12.C Control Rod AssembliesSurryTS Amendments189/189(Reference3)previouslyrelocatedcyclespecificparameterscontainedintheTStotheCOLR.TSFigures3.12-1Aand1B,ControlBankInsertionLimitsforNormal3LoopOperation,"forUnits1and2,respectively,shouldhavebeendeletedbythisamendmentsinceControlBankInsertionLimitswererelocatedtotheCOLR.TSAmendments194/194(Reference5)deletedTSFigures3.12-1Aand1BandalsodeletedareferencetotheseFiguresin Page3of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 AttachmentTS3.12.A.2ControlBankInsertionLimits.ThereferenceinTS3.12.A.2waschangedfrom"Figures3.12-1Aand1B"tothe"COREOPERATINGLIMITSREPORT"(COLR).However,duetoanadministrativeoversight,anadditionalTSreferencetothedeletedTSFigures3.12-1Aand1BcontainedinTS3.12.C.3.b.1)(b)wasnotidentifiedandrevisedtoreferencetheCOLR.Theproposedchangecorrectsthisdiscrepancy.

TS 3.12.ERodPosition Indication SystemControlandshutdownrodpositionaccuracyisessentialduringpoweroperation.Powerpeaking,ejectedrodworth,orshutdownmarginlimitsmaybeviolatedintheeventofadesignbasisaccidentwithcontrolorshutdownrodsoperatingoutsidetheirlimitsandbeingundetected.Therefore,theacceptancecriteriaforrodpositionindicationisthatrodpositionsmustbeknownwithsufficientaccuracytoverifythecoreisoperatingwithinthegroupsequence,overlap,designpeakinglimits,ejectedrodworthandwithminimumshutdownmargin.Therodpositionsmustalsobeknowntoverifythealignmentlimitsarepreserved.Theaxialpositionofshutdownrodsandcontrolrodsaredeterminedbytwoseparateandindependentsystems:theBankDemandPositionIndicationSystem(commonlycalledthegroupstepdemandcounters)andtheRodPositionIndicationSystem.ThesetwosystemsprovidethecontrolroomoperatorswithredundantrodpositionindicationtoensurecompliancewiththerequirementsofTS3.12.E,aswellastoensurethattheunitisoperatingwithintheboundsoftheaccidentanalysisassumptions.TheBankDemandPositionIndicationSystemcountsthepulsesfromtheRodControlSystemthatmovetherods.Thereisonegroupstepdemandcounterforeachgroupofrods.Individualrodsinagroupallreceivethesamesignaltomoveandshould,therefore,allbeatthesamepositionindicatedbythegroupstepdemandcounterforthatgroup.TheBankDemandPositionIndicationSystemisconsideredhighly precise (+/-2steps).TheRodPositionIndicationSystemprovidesanaccurateindicationofactualrodposition,butatalowerprecisionthanthegroupstepdemandcounters.Thissystemisbasedoninductiveanalogsignalsfromaseriesofcoilsspacedalongahollowtube.TheRodPositionIndicationSystemiscapableofmonitoringrodpositionwithinatleast

+/-12stepsduringsteadystatetemperatureconditionsandwithin

+/-24stepsduringtransienttemperatureconditions.Below50%RATEDPOWER,awidertoleranceonindicatedrodpositionforamaximumofonehourinevery24hoursispermittedtoallowthesystemtoreachthermalequilibrium.Thisthermalsoaktimeisavailablebothforacontinuousonehourperiodorseveraldiscreteintervalsaslongasthetotaltimedoesnotexceed1hourinany24hourperiodandtheindicatedrodpositiondoesnotexceed24stepsfromthegroupstepdemandcounterposition.TheproposedchangerevisesthecurrentTS3.12titleof"RodPositionIndicationSystem"to"RodPositionIndicationSystemandBankDemandPositionIndication Page 4of10 SerialNo.08-0310 DocketNos.50-280/281RevisionofTS3.12 AttachmentSystem"forcompleteness.ThistitlechangeisconsistentwiththestatementofITSLCO3.1.7inNUREG-1431.ThecurrentrodpositionindicationandgroupstepdemandcounteroperabilityrequirementscontainedinTS 3.12.E.1wereincorporatedintotheSurryTSinAmendments131/131(Reference6).TheproposedchangerevisestheapplicabilityoftheTS3.12.E.1operabilityrequirementstobe"frommovementofcontrolbankstoachievecriticalityandwiththeREACTORCRITICAL,"consistentwiththeapplicabilityofModes1and2inITSSection3.1.7ofNUREG-1431.Therequirementsonrodpositionindicationandthegroupstepdemandcountersareonlyapplicableatthesetimes,becausethesearetheonlyconditionsinwhichtherodscanaffectcorepowerdistributionandinwhichtherodsarereliedupontoproviderequiredshutdownmargin.Intheshutdownconditions,theoperabilityoftheshutdownbanksandcontrolbankshasthepotentialtoaffecttherequiredshutdownmargin,butthiseffectcanbecompensatedforbyanincreaseintheboronconcentrationoftheReactorCoolantSystem.TSAmendments78/79(Reference7)revisedtheTStolimitcontrolrodmisalignmenttonomorethan

.:!:12stepsindicatedposition.TheseamendmentsincludedactionsinTS3.12.E.2andTS3.12.E.3fundamentallythesameasthecurrentactions;subsequentTSrevisionsincludedterminologychanges(e.g.,RCCvs.controlrodassemblyandcoreinstrumentationvs.moveableincoredetectors).TheproposedchangerevisestheexistingTS3.12.E.2.a,TS3.12.E.2.b,andTS3.12.E.3actionstatementsandaddsactionsinTS3.12.E.4,aswellaspartofTS3.12.E.6,forrodpositionindicationinoperability.Inaddition,theproposedchangeaddsTS3.12.E.5,aswellaspartofTS3.12.E.6,toincludeactionstatementsforgroupstepdemandcounterinoperability.TheserevisionsareconsistentwiththeRequiredActionsinITSSection3.1.7ofNUREG-1431.Thevariousactionstatementtimerequirementsarebasedonoperatingexperienceandreflectthesignificanceofthecircumstanceswithrespecttoverificationofrodpositionandpotentialrodmisalignment.ReductionofRATEDPOWERtolessthanorequalto50%putsthecoreintoaconditionwhererodpositionisnotsignificantlyaffectingcorepeakingfactors.Therefore,duringoperation below 50%ofRATEDPOWER,nospecialmonitoringisrequired.Intheshutdownconditions,theoperabilityoftheshutdownbanksandcontrolbankshasthepotentialtoaffecttherequiredshutdownmargin,butthiseffectcanbecompensatedforbyanincreaseintheboronconcentrationoftheReactorCoolantSystem.ArelatedTS3.12BasischangereflectingtheproposedTS3.12revisionsisincludedfortheNRC'sinformation.TS3.12.G Shutdown MarginNewrequirementsarebeingaddedtospecifythat,wheneverthereactorissubcritical,theshutdownmarginrequirementsintheCOLRshallbesatisfiedandtorequirethat,iftheshutdownmarginisnotwithinthespecifiedlimits,initiateborationwithin Page 5of10 SerialNo.08-0310 DocketNos.50-280/281 RevisionofTS3.12 Attachment15minutestorestoretheshutdownmargintowithinthespecifiedlimits.TheserequirementsareconsistentwiththeITSrequirementsinSection 3.1.1ofNUREG1431.

TS 4.10 Reactivity AnomaliesTheexistingrequirementsinTS 4.1 O.AregardingmonthlycomparisonofactualversuspredictedboronconcentrationandreportingoftheevaluationofthespecifieddiscrepancyperSection6.6oftheTSarethesameastherequirementsintheoriginalSurryTS(Reference2)withrevisionofAtomicEnergyCommissiontoNuclearRegulatoryCommission.TheoriginalSurryTS6.6.B.1requiredAbnormalOccurrenceReports,oneofwhichdefined(atthattime)inTS 1.0.1.5wasuncontrolledorunanticipatedchangeinreactivity.SurryTSAmendments 104/104(Reference10)includedrevisionstothenotificationrequirementsintheTStobeconsistentwith10CFR50.72and10CFR50.73.Theserevisionsincluded1)replacementoftheTS 1.0.1definitionforAbnormalOccurrencewiththefollowingdefinitionofaReportableEvent(nownumberedasTS1.0.H):"AreportableeventshallbeanyofthoseconditionsspecifiedinSection50.73of10CFRPart50."and2)deletionoftheTS6.6.BrequirementsforNon-RoutineReports,includingTS6.6.B.1forAbnormalOccurrenceReports.WhenTSAmendments 104/104wereimplementeddeletingtheTS6.6.Brequirements,theTS4.1 O.AreferencetoreportingperSpecification6.6shouldhavealsobeendeleted.Theproposedchangedeletesthephrase"andreportedtotheNuclearRegulatoryCommissionperSection6.6oftheSpecifications"inTS4.10.A.ThisdeletionisconsistentwithITSSection5.6ReportingRequirements,whichdoesnotincludereportingofanydiscrepancybetweentheactualversuspredictedboron concentration.

4.REGULATORY EVALUATION

4.1 Applicable

Regulatory Requirements/CriteriaSection182aoftheAtomicEnergyActrequiresapplicantsfornuclearpowerplantoperatinglicensestodevelopTS,whichareincludedasapartoftheoperatinglicense(OL).10CFR50.36,Technicalspecifications,setsforththecontentoftheTS.ThisregulationrequirestheTStoincludeitemsinspecificcategoriesincluding,(1)safetylimits,limitingsafetysystemsettings,andlimitingcontrolsettings,(2)limitingconditionsforoperation(LCOs),(3)surveillancerequirements,(4)designfeatures,andadministrativecontrols.1 OCFR50.36doesnotspecifytheparticularspecificationstobeincludedaspartofaplant'sOL.ByletterdatedMay9,1988,(Reference8)theNRCdescribedresultsofanNRCstaffreviewtodeterminewhichLCOsshouldbeincludedintheTS.Thisultimatelyresultedinfourcriteriabeingdeveloped,asdescribedinthe"FinalPolicyStatementonTechnicalSpecificationsImprovementsforNuclearPowerReactors,"(Reference9),whichwerelatercodifiedin10CFR50.36(c)(2)(ii).

Page6of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 AttachmentCriterion2of 10CFR50.36(c)(2)(ii)requiresthataTSLCOmustbe established for" aprocessvariable,designfeature,oroperatingrestrictionthatisaninitialconditionofadesignbasis accident or transientanalysisthat eitherassumesthefailureoforpresentsachallengetotheintegrityofafissionproductbarrier." SDM satisfiesCriterion2of10CFR50.36(c)(2)(ii).Eventhoughitisnot directlyobservedfromthecontrolroom,SDMisconsideredaninitialconditionprocessvariablebecauseitis periodicallymonitoredtoensurethattheunitisoperatingwithintheboundsof accidentanalysisassumptions.Insertionlimits,therodpositionindicatorchannels,andthegroupstepdemand counterchannelssatisfyCriterion2of10CFR50.36(c)(2)(ii).

4.2 DeterminationofNo

Significant Hazards ConsiderationVirginiaElectricandPowerCompany(Dominion)proposesachangetotheSurryPowerStationUnits1and2TechnicalSpecifications(TS) pursuantto10CFR50.90.TheproposedchangerevisesactionstatementsinTS3.12forinsertionlimitandshutdownmargin(SDM)requirements,revisesthe applicabilityforthe operabilityoftheRodPositionIndicationandBankDemandPositionIndicationSystems, revises/adds action statementsforrodpositionindication,andaddsaction statementsforgroupstepdemandcounters.Thischangeisproposedtoenhancethe completenessoftheSurryTSandtoachieve consistencywithNUREG-1431, StandardTechnicalSpecifications, WestinghousePlants,Revision3.0(Reference1),withrespecttothe requirements and action statementsforinsertionlimits,SDM,rodpositionindication,andgroupstepdemandcounters.Threeadditionalminorchangesareproposedtomakea terminologycorrectionandtoaddresstwominorTS discrepanciesintroducedbypreviouslicense amendments.

In accordancewiththecriteriasetforthin10CFR50.92,DominionhasevaluatedtheproposedTSchangeanddeterminedthatthechangedoesnot represent a significant hazards consideration.Thefollowingisprovidedinsupportofthisconclusion:1.Doesthechangeinvolvea significantincreaseinthe probability or consequencesofanaccidentpreviouslyevaluated?Response:No.Theproposedchangeisbeingmadetoenhancethe completenessoftheSurryTSandtoachieveconsistencywithNUREG-1431withrespectto requirementsandactionstatementsforinsertionlimits,SDM,rodpositionindication,andgroupstepdemandcounters.Theproposedchangedoesnotaddormodifyanyplantsystems,structuresor components(SSCs).Thus,theproposedchangedoesnotaffectinitiatorsofanalyzedevents or assumed mitigation of accident or transientevents.Therefore,thischangedoesnot Page7of10 SerialNo.08-0310 DocketNos.50-280/281 Revision ofTS3.12 Attachmentinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.2.Doesthechangecreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated?Response:No.Theproposedchangedoesnotinvolveaphysicalalterationoftheplant(nonewordifferenttypeofequipmentwillbeinstalled).AlthoughtheproposedchangerevisestheapplicabilityoftheoperabilityrequirementsfortheRodPositionIndicationandBankDemandPositionIndicationSystems,itdoesnotinvolveachangeinmethodsgoverningplantstartup,operation,orshutdown.Theproposedchangedoesnotadverselyaffectaccidentinitiatorsorprecursors,nordoesitalterthedesignassumptions,conditions,orconfigurationofthefacility.TheproposedchangedoesnotalterorpreventtheabilityofSSCstoperformtheirintendedfunctiontomitigatetheconsequencesofaninitiatingeventwithintheassumedacceptancelimits.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.3.Doesthischangeinvolveasignificantreductioninamarginofsafety?Response:No.Theproposedchangedoesnotresultinplantoperationinaconfigurationoutsidetheanalysesordesignbasis,nordoesitaltertheconditionorperformanceofequipmentorsystemsusedinaccidentmitigationorassumedinanyaccidentanalysis.Therefore,theproposedTSchangedoesnotinvolveasignificantreductioninamarginofsafety.Basedontheabove,Dominionconcludesthattheproposedchangepresentsnosignificanthazardsconsiderationunderthestandardssetforthin10CFR50.92(c),and,accordingly,afindingof"nosignificanthazardsconsideration"isjustified.

4.3 ConclusionBasedontheconsiderationsdiscussedabove,(1)thereisreasonableassurancethatthehealthandsafetyofthepublicwillnotbeendangeredbyimplementationoftheproposedTSchange,(2)suchactivitieswillbeconductedincompliancewiththeCommission'sregulations,and (3)theissuanceoftheamendmentwillnotbeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic.

Page 8of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS3.12 Attachment 5.ENVIRONMENTAL CONSIDERATIONTheproposedamendmentmeetstheeligibilitycriterionforcategoricalexclusionsetforthin1 OCFR51.22(c)(10)asfollows:(i)Theproposedchangeinvolvesnosignificanthazardsconsideration.AsdescribedinSection4.2above,theproposedchangeinvolvesnosignificanthazardsconsideration.(ii)Thereisnosignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsite.Theproposedchangedoesnotinvolvetheinstallationofanynewequipmentorthemodificationofanyequipmentthatmayaffectthetypesoramountsofeffluentsthatmaybereleasedoffsite.Therefore,thereisnosignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsite.(iii)Thereisnosignificantincreaseinindividualorcumulativeoccupationradiation exposure.Theproposedchangedoesnotinvolvephysicalplantchangesorintroduceanynewmodesofplantoperation.Therefore,thereisnosignificantincreaseinindividualorcumulativeoccupationalradiationexposure.Basedontheabove,Dominionconcludesthat,pursuantto10CFR51.22(b),noenvironmentalimpactstatementorenvironmentalassessmentneedbepreparedinconnectionwiththeproposedamendment.

Page 9of10 SerialNo.08-0310DocketNos.50-280/281RevisionofTS 3.12 Attachment 6.REFERENCES 1.NUREG-1431,StandardTechnicalSpecifications,WestinghousePlants, Volume 1,Rev.3.0,datedJune2004.

2.Original Surry Technical Specifications,datedMarch17,1972.

3.Letter from USNRCtoW.L.Stewart, Virginia Electric and Power Company, datedMarch2,1994,"

Subject:

SurryUnits1and2-Issuance of AmendmentsRe:Core OperatingLimitsReport(TACNos.

M87004 and M87005)." 4.Letter from USNRC to Stanley Ragone, Virginia Electric and Power Company, datedMarch30,1973-Tech Spec Change NO.6.5.Letter from USNRCtoJ.P.O'Hanlon, Virginia Electric and Power Company, dated November15,1994,"

Subject:

SurryUnits1and2-Issuance of AmendmentsRe:Core OperatingLimitsReport(COLR)(TACNos.

M89910 and M89911)." 6.Letter from USNRCtoW.R.Cartwright, Virginia Electric and Power Company, dated August2,1989,"

Subject:

SurryUnits1and2-Issuance of Amendments Re: IndividualRodPosition IndicatingSystem(TACNos.

69106 and 69107)." 7.Letter from USNRC to R.H.Leasburg, Virginia Electric and Power Company, dated June17,1982-AmendmentNos.78and79.

8.Thomas E.Murley,Director,Officeof Nuclear Reactor Regulation, US Nuclear Regulatory Commission, letter to WalterS.Wilgus, Chairman, The B&W OwnersGroup,"NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups'Applicationofthe Commission'sInterimPolicy Statement Criteria to Standard Technical Specifications,"datedMay9,1988.9.US Nuclear Regulatory Commission,"FinalPolicy Statement on Technical Specifications Improvements for Nuclear Power Reactors"(FinalPolicy Statement),58FR39132,datedJuly22,1993.

10.Letter from USNRCtoW.L.Stewart, Virginia Electric and Power Company, dated December11,1985-AmendmentNos.104and104.Page10of10 SerialNo.08-0310DocketNos.50-280and281 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGES (MARK-UP)VirginiaElectricand Power Company (Dominion)SurryPowerStationUnits1and2 TS3.12-1-u159....3.12CONTROLROD ASSEMBLIESANDPOWERDISTRIBUTIONLIMITS AppficabilityAppliestotheoperationofthecontrolrodassembliesand power distribution limits.QbjectjveToensurecoresubcriticality after areactortrip, alimitonpotentialreactivityinsertionsfromhypothetical controlrodassemblyejection,andanacceptable corepowerdistributionduringpoweroperation.

Specjfication A.Control Bank Insertion Umits 1.INSER-rA3.TheControlBankInsertionUmitsshownintheCOREOPERATING LIMITSREPORTmayberevisedonthe basis of physicscalculationsandphysicsdataobtainedduringunit startup andsubsequentoperation,inaccordancewiththefollowing:AmendmentNos. and 194 INSERTA(inTS3.12.A.1onpageTS3.12-1):bankshallbewithintheinsertionlimitsspecifiedintheCORE OPERATING LIMITSREPORT.Withoneormoreshutdownbanksnotwithinlimits:a.Within1hour,verifyshutdownmarginiswithinthelimitsspecifiedintheCORE OPERATINGLIMITSREPORTorinitiateborationtorestoreshutdownmargintowithinlimitandb.Within2hours,restoreshutdownbankstowithinlimits.Iftheabove requirementsarenotmet,beinHOT SHUTDOWNwithin6hours.

INSERTB(inTS3.12.A.2onpageTS3.12-1):withintheinsertionlimitsspecifiedintheCORE OPERATINGLIMITSREPORT.Withcontrolbankinsertionlimitsnotmet:a.Within1hour,verifyshutdownmarginiswithinthelimitsspecifiedintheCORE OPERATINGLIMITSREPORTorinitiateborationtorestore shutdownmargintowithinlimitandb.Within2hours,restorecontrolbankstowithinlimits.Iftheabove requirementsarenotmet,beinHOT SHUTDOWNwithin6hours.

TS3.12-7..(36*07=965.The allowable QUADRANT POWER TILT is 2.0%andisonly applicable while operatingatTHERMAL POWER>50%.6.If, exceptforoperationat THERMAL POWER50%orforphysicsandcontrol rod assemblysurveillancetesting,the QUADRANT POWER TILT exceeds 2%, then: a.Within2hours, eitherthehot channel factors shall be determinedandthe powerleveladjustedtomeettherequirementof Specification 3.12.B.l, orb.ThepowerlevelshallbereducedfromRATED POWER2%foreachpercent of QUADRANTPOWERTILT.Thehighneutronfluxtrip setpoint shall besimilarlyreducedwithinthefollowing4hours.

d+ele, e,c.Ifthe QUADRANTPOWERTILT exceeds e;0%.thepowerlevelshallbereducedfromRATEDPOWER 2%foreachpercent of QUADRANT POWER TILT within thenext30minutes.Thehigh neutronfluxtrip setpointshallbesimilarlyreducedwithinthefollowing4hours.

7.If, except foroperationatTHERMAL POWER50%orforphysicsandcontrolrod assembly surveillance testing, after a further period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the QUADRANTPOWERTILTin Specification 3.12.B.5aboveisnot corrected tolessthan2%:

a.[f the design hot channelfactorsfor RATED POWERarenot exceeded, anevaluationastothecauseofthediscrepancyshallbemadeandaspecialreportissuedtotheNuclearRegulatory Commission.b.Ifthe designhotchannelfactorsforRATEDPOWER are exceededandthe power is greaterthan10%Ithenthe high neutron flux, Overpower f.Tand OvertemperatureTtripsetpointsshallbereduced1

%foreachpercentthehot channel factor exceedstheRATED POWER design valueswithinthenext4hours,andtheNuclearRegulatory Commissionshallbenotified.AmendmentNos.

t18-a:ud 210-TS3.12-8..Q2 B4 94 c.Ifthehot channelfactorsarenot determined,thenthe OverpowerTand Overtemperature trip setpointsshallbe reducedbythe equivalent of 2%powerforevery1%

QUADRANT POWERTILTwithinthenext4hours,and the Nuclear Regulatory Commissionshallbenotified.

C.Control Rod Assemblies1.Tobe considered OPERABLEduringstartupand POWER OPERATION each control rod assembly shall:a.Thecontrolrod assembly is restored to OPERABLEstatus,as defined in Specification 3.12.C.Iand2,orb.the shutdown margin requirement of Specification 3.I2.A.3.c is satisfied.

POWER OPERATIONmaythen continue provided that::2)Aav8 itspssitiQR Sdfla9lil sf YilrifyiRgfB8YilfBBHt H}38H1)betrippable, andI)be trippable,11.s+crs2)aligned within+/-24steps ofitsgroupstep demand position)tJm;iu8 the otbep!1h,e power and"TAljrHl:al pilri8S, as defined in Section 3.I2.E.!.b,or+/-12 steps3)haveadroptime oflessthanorequalto2.4secondsto dashpot entry.3.Startup and POWER OPERATION may continuewithone control rod assembly inoperable providedthatwithinonehoureither:2.Tobe considered OPERABLE during shutdownmodes,each control rod assembly shall: 2)haveadroptime oflessthanorequalto2.4secondsto dashpot entry.1)either: Amendment Nos. aRQ (b)(a)theshutdownmargin requirementofSpecification3.12.A.3.cisdetermlned-to bemetwithinonehourandat leastonceper12hoursthereafter.TS3.12-9powershallbereducedtolessthan75%ofRATEDPOWERwithinone(1)hour,and thel;HighNeutronFluxtrip setpointshaltbereducedtolessthan-orequalto85%of o RATEoO POWERfwithinthenextfour(4)hours, ortheremainderofthecontrol rodassembliesin the;groupwiththeinoperablecontrolrodassemblyoarealignedtowithin12stepsoftheinoperablerodwithinone(1) hour whilemaintainingthecontrolrod assembly sequence and.insertionJ Spe.cf-Aed

t"\

0";theTHERMAL

<E--c.oR E:POWERlevelshallbe restrictedpursuantto OPER.()t.TltJ q Specification3.12.Aduringsubsequentoperation.

LIM I,S RepoRT;2)" 3)4)thehotchannelfactorsareshowntobewithinthedesignlimitsof Specification3.12.8.1within72hours.Further,itshallbedemonstratedthatthevalueofFxy(Z)usedinthe Constant.Axial Offset Controlanalysisisstillvalid.areevaluationofeach accident analysisofTable 3.12-1isperformedwithin5 days..Thisreevaluationshallconfirmthatthepreviousanalyzedresultsoftheseaccidentsremainvalidforthe duration of operationunderthese conditions.

Amendment Nos.0-l86 and 186 TS 3.12-11 Above 50%power.theRodPosition Indication System shali be OPERABLE andcapableof determiningthecontrolrod assembly positions to within+/-12 steps at their respective groupstepdemandcounter indications.Frommovementofcontrolbankstoachieve.

criticalityupto 50%power.theRod Position Indication System shall bef OPERABLE and capable of determining the control rod assemblypositionsto withi!1+/-24 steps of their respective group step demand counter indications for a maximum of one houroutof twenty-four.andto within+/-12 steps otherwise.

the eRe t-1euF Seaft" f)e.Fiea.Ul9 elsmaRs GOYRters be OPERABLE 8"d capable aI,determining tt:le grel:JJ3 elsmeRe to withi"+/-2 stOJ3&:=-a.E.92 94-94-.Rod PpsitiqoIndicationSystem'Pas;(kI')5'1 s+eNn-E-.___-----_1.positionindicationshalf be providedasfollows:Fro tY)move.Me.u...+

of C8Y\tro I bt4t'=:s+n t:UN1 wtu.-.REACTO R C£I neAt-, b.t=Y-oW)rno"\}eMW of c...L..-CDt'l+ro(baA\.ks+0 eanpa e ofa.ch iore: ex i ficoJJry determiningthegroup demand positionstowithin+/-2steps.l.UA.t-t LV i th.:e:'ettpesiti:

te 09AtfOlj; Cf-\i1 tAL,.4 4-'----_-----'

..on(,.tr_(f("

.2.If 0 position indicator isa..f:or epef8tion 8ee\'eeftheposition of!the control rod assembly shallindirectly usingfthemovableincore detectorsatleastonce per 8hoursand immediately

..any motionofthe control$'rodassemblyexceeding 24 steps.-&f.Pi\teN" naA1"e,.('i'.l t<f::---4r.-<;$educe power tolessthan50%ofRATED POWER withinhours.Duringoperationsbelow50%ofRATEDPOWER.

notspecialmonitoringisrequired.AmendmentNos.186126

/NSER.-r c, F.ONB Parameters TS 3.12-12-00 eS*S5<E-1.Thefollowing DNBrelatedparametersshallbemaintainedwithintheirlimitsduringPOWEROPERATION:*ReactorCoolantSystemTavg577.0°F*PressurizerPressure2205psig*ReactorCoolantSystemTotalFlowRate273,000gpma.TheReactorCoolantSystemTavgand Pressurizer Pressureshallbeverifiedtobewithintheirlimitsatleastonceevery12 hours.b.The Reactor Coolant System Total FlowRateshallbedeterminedtobewithinitslimitbymeasurementatleastonceperrefuelingcycle.

2.3.WhenanyoftheparametersinSpecification3.12.F.1hasbeen determinedtoexceeditslimit, eitherrestorethe parameter towithinitslimitwithin2hoursorreduceTHERMALPOWERtolessthan5%ofRATEDPOWERwithinthenext4hours.ThelimitforPressurizerPressureinSpecification3.12.F.1isnotapplicableduringeitheraTHERMALPOWERramp increase inexcessof5%ofRATEDPOWERperminuteora THERMALPOWERstepincreaseinexcessof10%ofRATEDPOWER.AmendmentNos.203 8:Ad 208 t INSERTC(onpageTS3.12-12):3.Ifmorethanonerodposition indicatorpergroupisinoperable,placethecontrolrods undermanualcontrolimmediately, monitorandrecordRCST avgonceperhour,verifythepositionofthecontrolrod assemblies indirectlyusingthe movable incore detectorsatleastonceper8hours,andrestore inoperable position indicators to OPERABLEstatussuchthatamaximumofoneposition indicatorpergroupis inoperablewithin24hours.4.Ifoneormorerodswith inoperablepositionindicatorshavebeenmovedin excessof24stepsinonedirectionsincethelast determinationoftherod'sposition,verifythepositionofthecontrolrod assemblies indirectlyusingthe movable incore detectorswithin4hoursorreducepowertolessthan50%ofRATED POWER within8hours.5.Ifonegroupstepdemand counterperbankformorethanoneormorebanksis inoperable,verifythatallrodpositionindicatorsfortheaffectedbank(s)are OPERABLEonceper8hoursandverifythatthemost withdrawnrodandtheleast withdrawnrodoftheaffectedbank(s)arelessthanorequalto12stepsapartonceper8hours.

Alternatively,reducepowertolessthan50%ofRATED POWER within8hours.6.Ifthe requirements of Specifications3.12.E.2,3.12.E.3,3.12.E.4,or 3.12.E.5arenotsatisfied,thentheunitshallbeplacedinHOT SHUTDOWNwithin6hours.

INSERTD(onpageTS3.12-12):

G.Shutdown Margin 1.Wheneverthereactorissubcritical,theshutdownmarginshallbewithinthelimits specifiedintheCORE OPERATINGLIMITSREPORT.Ifthe shutdown rnarqinisnotwithinlimits,within15minutes,initiateborationtorestore shutdownmargintowithinlimits.

TS 3.12-13 62-84=94 The reactivity control conceptassumedfor operationisthat reactivity changes accompanying changes in reactorpowerarecompensated bycontrolrod assembly monon.Reactivitychangesassociatedwithxenon,samarium,fueldepletion.andlargechangesin reactorcoolanttemperature(operatingtemperaturetoCOLOSHUTDOWN are compensatedforby changesinthesolubleboronconcentration.DuringPOWER OPERATION,theshutdowncontrolrodassembliesarefullywithdrawnandcontrolof powerisbythecontrolbanks.AreactortripoccurringduringPOWEROPERATION willplacethe reactorintoHOTSHUTDOWN.Thecontrolrod assembly insertion limits provide for achievingHOTSHUTOOWNby reactortripatanytime,assumingthehighestworthcontrolrodassembly r.emainsfullywithdrawn.withsufficientmargins tomeetthe assumptionsusedintheaccidentanalysis.Inaddition,theyprovidealimitonthemaximuminserted Controlrodassemblyworthintheunlikelyeventofa hypotheticalfassemblyejectionandprovideforacceptablenuclearpeakingfactors.Thelimitmaybe determinedonthebasisofunitstartupandoperatingdatatoprovideamorerealisticlimitwhichwill allowformoreflexibilityinunitoperationandstillassurecompliance with the shutdown requirement.

The maximumshutdownmarginrequirementoccursatendofcorelifeandisbasedonthevalueusedin the analysesofthehypotheticalsteambreakaccident.The contrail rod assemblyinsertionlimitsarebasedonendofcorelifeconditions.Themarginfortheentirecyclelengthisestablishedat1.77%reactivity.Otheraccident analyses withtheexceptionoftheChemicalandVolumeControlSystem malfunction; analysesarebasedon1

%reactivityshutdownmargin.Relative positions of controllbanksaredeterminedbyaspecifiedcontrolbankoverlap.Thisoverlapisbasedon theconsiderationofaxialpowershapecontrol.Thespecifiedcontrolrodassemblyinsertion lim.itshavebeenestablishedtolimitthepotentialejectedcontrolrodassemblyworth i1ordertoaccountfortheeffectsoffueldensification.Thevariouscontrolrod assemblies((shutdown banks,controlbanksA,B,C,andD)areeachtobemovedasabank;that is, with each assemblyinthe bankwithinonestep (518ofthebankposition.IMSERT EAmendmentNos.

186 Ilnd*1-86 TS 3.12-14 The specified Control rod assemblydroptimeis consistent with safetyanalysesthathavebeenperformed.

An inoperable controlrodassemblyimposesadditionaldemandsontheoperators.

The permissible numberofinoperablecontrolrod asSemblies is limitedtooneinorderto

--limit the magnitudeofthe operatingburden,butsuchafailurewouldnot prevent droppingoftheOPERABLEcontrolrodassembliesuponreactortrip.AmendmentNos. afld 199 INSERTE(onpagesTS3.12-13andTS3.12-14):Theaxialpositionofshutdownrodsandcontrolrodsare determinedbytwo separate and independentsystems:theBankDemandPositionIndicationSystem (commonlycalledthegroupstepdemandcounters)andtheRodPositionIndicationSystem.TheBankDemandPositionIndicationSystemcountsthepulsesfromtheRodControlSystemthatmovetherods.Thereisonegroupstepdemand counterforeachgroupof rods.Individualrodsinagroupallreceivethesamesignaltomoveandshould, therefore,allbeatthesamepositionindicatedbythegroupstepdemand counter forthatgroup.TheBankDemandPositionIndicationSystemis considered highly precise (+/-2steps).TheRodPositionIndicationSystemprovidesanaccurateindicationofactualrodposition,butatalowerprecisionthanthegroupstepdemandcounters.Thissystemisbasedon inductiveanalogsignalsfromaseriesofcoilsspacedalonga hollow tube.TheRodPositionIndicationSystemiscapableofmonitoringrodpositionwithinatleast

.+/-.12stepsduringsteadystate temperatureconditionsand within.+/-.24stepsduring transient temperatureconditions.Below50%RATEDPOWER,a wider tolerance onindicatedrodpositionforamaximumofonehourinevery24hoursis permittedtoallowthesystemtoreachthermalequilibrium.Thisthermalsoaktimeis availablebothfora continuousonehourperiodorseveral discreteintervalsaslongasthetotaltimedoesnotexceed1 hourinany24hourperiodandtheindicatedrodpositiondoesnotexceed24stepsfromthegroupstepdemand counter position.The requirementsontherodpositionindicatorsandthegroupstepdemand countersareonly applicablefromthe movementofcontrolbankstoachieve criticalityandwith the REACTOR CRITICAL,becausethesearetheonly conditionsinwhichtherodscanaffectcore power distributionandinwhichtherodsarereliedupontoproviderequired shutdownmargin.Thevariousaction statement time requirementsarebasedon operating experienceandreflectthe significanceofthe circumstances with respect to verificationofrodpositionandpotentialrod misalignment.ReductionofRATED POWERtolessthanorequalto50%putsthecoreintoaconditionwhererodpositionis not significantlyaffectingcorepeakingfactors.Therefore,during operationbelow50%ofRATEDPOWER,nospecialmonitoringisrequired.Intheshutdown conditions, the operabilityoftheshutdownbanksandcontrolbankshasthepotentialtoaffectthe required shutdownmargin,butthiseffectcanbe compensatedforbyan increaseinthe boron concentrationofthe ReactorCoolantSystem.

TS 4.1()"1-93=12-93..4.10 REACTIVITY ANOMAliES Agpljgtbi'ilY Applies to potential reactivity anomalies.

Objectjye To require evaluation of applicable reactivity anomalies within the reactor.SPecification A.B.Foflowing a normalization of the computed boron concentrationasa funetton of bumup, the actual boron concentrationofthe coolant shall be compared monthly with the predicted value.If the difference between the observed and predicted steady-state concentrations reaches the equivalentofone percent in reactivity, an evaluationastothe cause of the discrepanCyshallbe made.sAQ r-epertee to the Nuclear Regulatory-<>Ommission SeetisA lUi of SpecificatioR$t The provisions of tSpecification 4.0.4 are not applicable.

.}During periods of POWER OPERATION at greater than 10%of RATED}POWER, the hot channel factors identified in Section3.12shall be:p determined during each effectivefullpower month of operation usingdatafrom limited core maps.If these factors exceed theirlimits,an evaluationastothe causeofthe anomaly shafl be made.The provisions}

of Specification 4.0.4 are not applicable...Amendment NQs.175 and 114 Serial No.08-0310 Docket Nos.50-280 and 281 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONSPAGES(TYPED)VirginiaElectricandPower Company (Dominion)

Surry PowerStationUnits1and2 TS3.12-1 3.12 CONTROLRODASSEMBLIESANDPOWER DISTRIBUTION LIMITS ApplicabilityAppliestotheoperationofthecontrolrodassembliesandpowerdistributionlimits.

Objective To ensure core subcriticalityaftera reactortrip,alimiton potential reactivity insertions from hypothetical control rod assembly ejection, and an acceptable core powerdistributionduringpoweroperation.

Specification A.ControlBankInsertionLimits1.Wheneverthereactoriscritical,exceptforphysicstestsandcontrolrodassembly surveillance testing, each shutdown bank shall be within the insertion limits specifiedinthe CORE OPERATINGLIMITSREPORT.

With one or moreshutdownbanksnotwithinlimits:a.Within1hour,verifyshutdownmarginiswithinthelimitsspecifiedintheCOREOPERATINGLIMITSREPORTorinitiateborationtorestoreshutdownmargintowithinlimitandb.Within2hours,restoreshutdownbankstowithinlimits.

Iftheaboverequirementsarenotmet,beinHOTSHUTDOWNwithin6hours.2.Wheneverthereactoriscritical,exceptforphysicstestsandcontrolrodassembly surveillance testing,thefull length control banksshallbe within the insertionlimitsspecifiedintheCOREOPERATINGLIMITSREPORT.Withcontrolbankinsertionlimitsnotmet:a.Within1hour,verifyshutdownmarginiswithinthelimitsspecifiedintheCOREOPERATINGLIMITSREPORTorinitiateborationtorestore Amendment Nos.

TS3.12-1Ashutdownmargintowithinlimitandb.Within2hours,restorecontrolbankstowithinlimits.

Iftheaboverequirementsarenotmet,beinHOTSHUTDOWNwithin6hours.3.TheControlBankInsertionLimitsshownintheCOREOPERATINGLIMITSREPORTmaybe revisedonthebasisof physics calculations and physics data obtained during unit startup and subsequent operation, in accordancewiththe following:

Amendment Nos.

TS 3.12-7 5.TheallowableQUADRANTPOWERTILTis 2.0%andisonlyapplicablewhileoperatingatTHERMAL POWER>50%.6.If,exceptforoperationatTHERMALPOWER

<50%orforphysicsandcontrolrodassembly surveillancetesting,the QUADRANTPOWERTILT exceeds 2%, then:a.Within2hours,eitherthehotchannelfactorsshallbedeterminedandthepowerleveladjustedtomeettherequirementofSpecification 3.12.B.1, orb.ThepowerlevelshallbereducedfromRATEDPOWER 2%foreachpercent of QUADRANT POWERTILT.Thehigh neutronfluxtrip setpointshallbesimilarlyreducedwithinthefollowing4hours.

c.IftheQUADRANTPOWERTILTexceeds10%,thepowerlevelshallbereducedfromRATEDPOWER 2%foreachpercentof QUADRANT POWERTILTwithinthenext 30minutes.Thehighneutronfluxtrip setpointshallbesimilarlyreducedwithinthefollowing4hours.

7.If,exceptforoperationatTHERMALPOWER

<50%orforphysicsandcontrol rod assembly surveillance testing, after a further period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the QUADRANT POWERTILTin Specification 3.12.B.5aboveisnot corrected tolessthan 2%: a.IfthedesignhotchannelfactorsforRATEDPOWERarenotexceeded,anevaluationastothecauseofthediscrepancyshallbemadeandaspecialreportissuedtotheNuclearRegulatoryCommission.

b.IfthedesignhotchannelfactorsforRATEDPOWERareexceededandthe power is greaterthan10%,thenthehigh neutron flux, Overpower and OvertemperatureTtripsetpointsshallbereduced1

%foreachpercentthehot channel factorexceedstheRATEDPOWERdesignvalueswithinthenext4hours,andtheNuclearRegulatoryCommissionshallbenotified.

Amendment Nos.

TS3.12-8 c.Ifthehotchannelfactorsarenotdetermined,thenthe OverpowerDTand Overtemperature ilT trip setpointsshallbe reducedbythe equivalentof2%powerforevery1

%QUADRANT POWERTILTwithinthenext4hours,andtheNuclearRegulatoryCommissionshallbenotified.C.ControlRodAssemblies1.Tobeconsidered OPERABLEduringstartupand POWER OPERATION eachcontrolrodassemblyshall:1)betrippable,2)alignedwithin

+/-12stepsor+/-24stepsofitsgroupstepdemandposition,asdefinedinSection3.12.E.1.b,and3)haveadroptimeoflessthanorequalto2.4secondstodashpotentry.2.Tobe considered OPERABLEduringshutdownmodes,eachcontrolrodassembly shall:1)betrippable,and2)haveadroptimeoflessthanorequalto2.4secondstodashpotentry.3.StartupandPOWER OPERATIONmaycontinuewithonecontrolrodassembly inoperableprovidedthatwithinonehoureither:a.Thecontrolrodassemblyisrestoredto OPERABLEstatus,asdefinedin Specification 3.l2.C.land2,orb.theshutdownmargin requirement of Specification 3.12.A.3.c IS satisfied.

POWER OPERATIONmaythencontinueprovidedthat:1)either: Amendment Nos.

TS3.12-9(a)powershallbereducedtolessthan75%ofRATEDPOWERwithin one (1)hour,andtheHighNeutronFluxtripsetpointshallbereducedtolessthanorequalto85%ofRATEDPOWERwithinthenextfour(4)hours,or(b)theremainderofthecontrolrodassembliesinthegroupwiththe inoperablecontrolrod assembly are alignedtowithin12stepsofthe inoperablerodwithinone(1)hourwhile maintaining the control rod assembly sequence and insertion limits specified in the CORE OPERATINGLIMITSREPORT;the THERMALPOWERlevelshall be restricted pursuant to Specification 3.l2.A during subsequent operation.2)theshutdownmarginrequirementofSpecification 3.l2.A.3.cisdeterminedtobemetwithinonehourandatleastonceper12hoursthereafter.3)thehotchannelfactorsareshowntobewithinthedesignlimitsof Specification 3.l2.B.lwithin72hours.Further,itshallbe demonstratedthatthevalueof Fxy(Z)usedintheConstantAxialOffsetControlanalysisisstillvalid.4)areevaluationofeachaccidentanalysisofTable3.12-1isperformedwithin5days.Thisreevaluationshallconfirmthatthepreviousanalyzedresultsoftheseaccidentsremainvalidforthedurationofoperationundertheseconditions.

Amendment Nos.

TS3.12-11E.RodPositionIndicationSystemandBankDemandPositionIndicationSystem1.Frommovementofcontrolbankstoachievecriticalityandwiththe REACTORCRITICAL,rodpositionindicationshallbeprovidedasfollows:a.Above50%power,theRodPositionIndicationSystemshallbe OPERABLEandcapableofdeterminingthecontrolrodassembly positionstowithin+/-12stepsoftheirrespectivegroupstepdemandcounterindications.b.Frommovementofcontrolbankstoachievecriticalityupto50%power,the Rod Position Indication System shall be OPERABLE and capable of determiningthecontrolrod assembly positionstowithin+/-24steps of theirrespectivegroupstepdemandcounterindicationsforamaximumofonehouroutoftwenty-four,andtowithin

+/-12stepsotherwise.c.FrommovementofcontrolbankstoachievecriticalityandwiththeREACTORCRITICAL,theBankDemandPositionIndicationSystemshallbe OPERABLEandcapableofdeterminingthegroupdemandpositionstowithin

+/-2steps.2.Ifonerodpositionindicatorpergroupforoneormoregroupsisinoperable,thepositionofthecontrolrodassemblyshallbeverifiedindirectlyusingthemovableincoredetectorsatleastonceper8hoursandimmediatelyafteranymotionofthe non-indicating control rod assembly exceeding24steps.Alternatively, reduce powertolessthan50%ofRATED POWERwithin8hours.

During operationsbelow50%ofRATEDPOWER,nospecialmonitoringisrequired.

Amendment Nos.

TS3.12-12 3.Ifmorethanonerodpositionindicatorpergroupisinoperable,placethecontrolrodsundermanualcontrol immediately, monitorandrecordRCSTavgonceperhour,verifythepositionofthecontrolrodassembliesindirectlyusingthemovable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and restore inoperable position indicators to OPERABLEstatussuchthata maximumofone position indicatorpergroupisinoperablewithin24hours.

4.Ifoneormorerodswithinoperablepositionindicatorshavebeenmovedinexcessof24stepsinonedirectionsincethelastdeterminationofthe rod'sposition,verify the positionofthe control rod assemblies indirectlyusingthe movable incore detectorswithin4hoursorreduce powertolessthan50%ofRATED POWERwithin8hours.

5.Ifonegroupstepdemandcounterperbankformorethanoneormorebanksis inoperable, verifythatallrod position indicatorsforthe affected bank(s)are OPERABLEonceper8hoursandverifythatthemostwithdrawnrodandtheleastwithdrawnrodoftheaffectedbank(s)arelessthanorequalto12stepsapartonceper8hours.

Alternatively, reduce powertolessthan50%

of RATED POWERwithin8hours.

6.IftherequirementsofSpecification3.12.E.2,3.12.E.3,3.12.EA,or3.12.E.5arenotsatisfied,thentheunitshallbeplacedinHOT SHUTDOWNwithin6hours.

F.DNBParameters1.ThefollowingDNBrelatedparametersshallbemaintainedwithintheirlimitsduringPOWEROPERATION:*ReactorCoolantSystem Tavg::;577.0 oP*Pressurizer Pressure2205psig*ReactorCoolantSystemTotalPlowRate273,000gpma.TheReactorCoolantSystemTavgandPressurizerPressureshallbeverifiedto Amendment Nos.

TS 3.12-12Abewithintheirlimitsatleastonceevery12hours.b.TheReactorCoolantSystemTotalFlowRateshallbe determinedtobewithinitslimitby measurementatleastonceperrefuelingcycle.2.Whenanyoftheparametersin Specification3.12.F.1hasbeen determined to exceeditslimit, eitherrestorethe parametertowithinits limit within2hoursor reduce THERMALPOWERtolessthan5%ofRATED POWERwithinthenext4 hours.3.Thelimitfor PressurizerPressurein Specification 3.12.F.lisnot applicable duringeithera THERMALPOWERrampincreaseinexcessof5%ofRATED POWERperminuteora THERMAL POWER step increase in excessof10%of RATED POWER.G.Shutdown Margin 1.Wheneverthereactorissubcritical,theshutdownmarginshallbewithinthelimitsspecifiedintheCORE OPERATINGLIMITSREPORT.

Iftheshutdownmarginisnotwithinlimits,within15minutes,initiateborationtorestoreshutdownmargintowithinlimits.

TS3.12-13 Basis The reactivity control concept assumed for operationisthat reactivity changes accompanyingchangesin reactorpowerare compensatedbycontrolrod assembly motion.Reactivity changesassociatedwithxenon,samarium,fueldepletion,andlargechangesinreactorcoolant temperature (operating temperaturetoCOLDSHUTDOWN)are compensatedforbychangesinthesoluble boron concentration.

DuringPOWEROPERATION,the shutdown control rod assemblies are fully withdrawn and controlofpowerisbythe controlbanks.A reactor trip occurring duringPOWEROPERATIONwillplacethereactorintoHOTSHUTDOWN.Thecontrolrodassembly insertionlimitsprovideforachievingHOT SHUTDOWN by reactortripatanytime, assumingthehighestworthcontrolrodassemblyremainsfullywithdrawn,withsufficientmarginstomeet the assumptionsusedintheaccidentanalysis.Inaddition,theyprovidealimitonthe maximuminsertedcontrolrodassemblyworthintheunlikelyeventofahypotheticalassemblyejectionandprovideforacceptable nuclearpeakingfactors.Thelimitmaybedeterminedonthebasisofunitstartupandoperatingdatatoprovideamorerealisticlimitwhichwillallowformoreflexibilityinunitoperationandstillassurecompliancewiththeshutdownrequirement.Themaximumshutdownmarginrequirementoccursatendofcorelifeandisbasedonthevalueusedintheanalysesofthehypotheticalsteambreakaccident.Thecontrolrodassemblyinsertionlimitsarebasedonendofcorelifeconditions.Theshutdownmarginfortheentirecyclelengthis establishedat1.77%reactivity.Otheraccidentanalyseswiththe exceptionofthe Chemical and Volume Control System malfunction analyses are basedon1%reactivity shutdown margin.Relative positions of controlbanksare determinedbya specified control bank overlap.This overlap is basedonthe consideration ofaxialpowershape control.The specified control rodassemblyinsertionlimitshavebeenestablishedtolimitthepotentialejectedcontrolrodassemblyworthinordertoaccountfortheeffectsoffueldensification.Thevariouscontrolrodassemblies(shutdownbanks,controlbanksA,B,C,andD)areeachtobemovedasabank;thatis,witheachassemblyinthebankwithinonestep(5/8inch)ofthebankposition.

The axial position of shutdownrodsand control rods are determinedbytwo separate and independentsystems:theBankDemandPositionIndicationSystem(commonlycalledthegroupstepdemandcounters)andtheRodPositionIndicationSystem.TheBank Demand Position IndicationSystemcountsthepulsesfromtheRod Control Systemthatmovetherods.Thereisonegroupstepdemandcounterforeachgroupofrods.Individual Amendment Nos.

TS3.12-14rodsina group all receivethesame signaltomoveand should, therefore,allbeatthe same position indicatedbythegroupstepdemand counterforthatgroup.TheBankDemand PositionIndicationSystemisconsideredhighlyprecise

(+/-2steps).TheRodPositionIndicationSystemprovidesanaccurateindicationofactualrodposition,butatalowerprecisionthanthegroupstepdemandcounters.Thissystemisbasedoninductiveanalogsignalsfromaseriesofcoilsspacedalongahollowtube.TheRodPosition Indication System is capable of monitoring rod positionwithinatleast

+/-12steps during steady state temperature conditionsandwithin+/-24stepsduring transient temperature conditions.Below50%RATED POWER, a wider tolerance on indicated rod positionfora maximum of one hour in every24hoursispermittedtoallowthesystemtoreachthermalequilibrium.Thisthermalsoaktimeis availablebothfora continuousonehourperiodorseveraldiscrete intervalsaslongasthetotaltimedoesnotexceed1hourinany24hourperiodandtheindicatedrodpositiondoesnotexceed24stepsfromthegroupstepdemandcounterposition.

The requirementsontherod position indicatorsandthegroupstep demand countersareonly applicablefromthe movementofcontrolbanksto achieve criticalityandwiththe REACTOR CRITICAL, because thesearethe only conditions in which the rods can affect core power distributionandin whichtherodsarerelieduponto provide required shutdown margin.The various action statement time requirements are based on operating experience and reflect the significance of the circumstances with respect to verification of rod position and potential rod misalignment.

ReductionofRATEDPOWERtolessthanorequalto50%putsthecoreintoaconditionwhererodpositionisnotsignificantlyaffectingcorepeakingfactors.Therefore,during operation below50%RATED POWER, no special monitoring is required.Inthe shutdownconditions,theoperabilityoftheshutdownbanksandcontrolbankshasthepotentialtoaffectthe required shutdownmargin,butthis effectcanbe compensatedforbyan increaseintheboron concentrationoftheReactorCoolantSystem.

The specified control rod assemblydroptimeis consistentwithsafetyanalysesthathavebeen performed.

An inoperable control rod assembly imposes additional demands on the operators.

The permissible number of inoperablecontrolrod assembliesislimitedtoonein order to limit the magnitude of the operating burden, but such a failure would not prevent dropping of the OPERABLEcontrolrodassembliesuponreactortrip.

Amendment Nos.

TS4.10-1 4.10 REACTIVITY ANOMALIES Applicability Applies to potential reactivity anomalies.

Objective To require evaluation of applicable reactivity anomalieswithinthereactor.

Specification A.Following a normalizationofthe computed boron concentrationasa function of bumup, the actual boron concentration of the coolant shall be compared monthly with the predicted value.If the difference between the observed and predicted steady-state concentrations reaches the equivalent of one percentinreactivity,an evaluationastothe cause of the discrepancy shall be made.The provisions of Specification 4.0.4 are not applicable.

B.During periods of POWER OPERATION at greaterthan10%of RATED POWER,thehot channel factors identified in Section3.12shallbe determined during each effective full power month of operationusingdatafromlimitedcoremaps.

Ifthesefactors exceed their limits, an evaluationastothe cause of the anomaly shall be made.The provisions of Specification4.0.4arenotapplicable.

Amendment Nos.