CNL-14-210, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima

Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima

ML14365A046
Person / Time
Site:	Browns Ferry   (DPR-033, DPR-052, DPR-068)
Issue date:	12/22/2014
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Division of Operating Reactor Licensing
References
CNL-14-210
Download: ML14365A046 (79)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-210 December 22, 2014 10 CFR 50.4 10 CFR 50.54(f)

Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Tennessee Valley Authoritys Browns Ferry Nuclear Plant Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ML12056A046)

On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued the referenced letter to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of the referenced letter requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation that includes an interim evaluation and actions taken or planned to address the higher seismic hazard relative to the design basis, as appropriate, prior to completion of the risk evaluation.

In accordance with the referenced letter above, TVA is enclosing the Expedited Seismic Evaluation Process (ESEP) Report for Browns Ferry Nuclear Plant.

There are no new regulatory commitments resulting from this submittal. Should you have questions concerning the content of this letter, please contact Mr. Kevin Casey at (423) 751-8523.

U.S. Nuclear Regulatory Commission CNL-14-210 Page 2 December 22, 2014 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22nd day of December 2014.

.Shea President, Nuclear Licensing

Enclosure:

Expedited Seismic Evaluation Process (ESEP) Report for Browns Ferry Nuclear Plant cc (Enclosure):

NRR Director-NRC Headquarters NRO Director - NRC Headquarters NRR JLD Director-NRC Headquarters NRC Regional Administrator-Region II NRR Project Manager - Browns Ferry Nuclear Plant NRR JLD Project Manager-Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

ENCLOSURE EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR BROWNS FERRY NUCLEAR PLANT

Page1 EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR BROWNS FERRY NUCLEAR PLANT

BrownsFerryNuclearPlantESEPReport Page2 TableofContents Page LISTOFTABLES............................................................................................................................................4 LISTOFFIGURES..........................................................................................................................................5 1.0 PURPOSEANDOBJECTIVE...............................................................................................................6 2.0 BRIEF

SUMMARY

OFTHEFLEXSEISMICIMPLEMENTATIONSTRATEGIES......................................6 3.0 EQUIPMENTSELECTIONPROCESSANDESEL..................................................................................7 3.1 EquipmentSelectionProcessandESEL..............................................................................8 3.1.1 ESELDevelopment...............................................................................................9 3.1.2 PowerOperatedValves.......................................................................................9 3.1.3 PullBoxes...........................................................................................................10 3.1.4 TerminationCabinets.........................................................................................10 3.1.5 CriticalInstrumentationIndicators....................................................................10 3.1.6 Phase2and3PipingConnections.....................................................................10 3.2 JustificationforUseofEquipmentThatisNotthePrimaryMeansforFLEX Implementation................................................................................................................10 4.0 GROUNDMOTIONRESPONSESPECTRUM(GMRS)......................................................................10 4.1 PlotofGMRSSubmittedbytheLicensee.........................................................................10 4.2 ComparisontoSSE............................................................................................................12 5.0 REVIEWLEVELGROUNDMOTION(RLGM)...................................................................................13 5.1 DescriptionofRLGMSelected..........................................................................................13 5.2 MethodtoEstimateInStructureResponseSpectra(ISRS)..............................................14 6.0 SEISMICMARGINEVALUATIONAPPROACH.................................................................................14 6.1 SummaryofMethodologiesUsed....................................................................................15 6.2 HCLPFScreeningProcess..................................................................................................15 6.3 SeismicWalkdownApproach...........................................................................................16 6.3.1 WalkdownApproach..........................................................................................16 6.3.2 ApplicationofPreviousWalkdownInformation...............................................17 6.3.3 SignificantWalkdownFindings..........................................................................17 6.4 HCLPFCalculationProcess................................................................................................18 6.5 FunctionalEvaluationsofRelays......................................................................................18 6.6 TabulatedESELHCLPFValues(IncludingKeyFailureModes)..........................................18 7.0 INACCESSIBLEITEMS.....................................................................................................................19 7.1 IdentificationofESELItemInaccessibleforWalkdowns..................................................19 7.2 PlannedWalkdown/EvaluationSchedule/CloseOut....................................................19 8.0 ESEPCONCLUSIONSANDRESULTS...............................................................................................19 8.1 SupportingInformation....................................................................................................19

BrownsFerryNuclearPlantESEPReport TableofContents (continued)

Page Page3 8.2 IdentificationofPlannedModifications...........................................................................21 8.3 ModificationImplementationSchedule...........................................................................21 8.4 SummaryofRegulatoryCommitments............................................................................21

9.0 REFERENCES

..................................................................................................................................22 ATTACHMENTA-EXPEDITEDSEISMICEQIPMENTLIST(ESEL)FORBROWNSFERRYNUCLEAR PLANT.........................................................................................................................A1 ATTACHMENTB-ESEPHCLPFVALUESANDFAILUREMODESTABULATIONFORBROWNSFERRY NUCLEARPLANT.........................................................................................................B1

BrownsFerryNuclearPlantESEPReport Page4 List of Tables Page TABLE41:GMRSFORBROWNSFERRYNUCLEARPLANT.......................................................................11 TABLE42:SSEFORBROWNSFERRYNUCLEARPLANT............................................................................12 TABLE51:2XSSEFORBROWNSFERRYNUCLEARPLANT.......................................................................14 TABLEA1:EXPEDITEDSEISMICEQUIPMENTLIST(ESEL)FORBROWNSFERRYNUCLEARPLANT.........A2 TABLEB1:ESEPHCLPFVALUESANDFAILUREMODESFORBROWNSFERRYNUCLEARPLANT............B2

BrownsFerryNuclearPlantESEPReport Page5 List of Figures Page FIGURE41:GMRSATCONTROLPOINTFORBROWNSFERRYNUCLEARPLANT....................................12 FIGURE42:GMRSTOSSECOMPARISONFORBROWNSFERRYNUCLEARPLANT.................................13 FIGURE51:2XSSEFORBROWNSFERRYNUCLEARPLANT.....................................................................14 FIGURE61:COMPARISONOFBROWNSFERRYNUCLEARPLANTRLGMANDIPEEERLE.......................15

BrownsFerryNuclearPlantESEPReport Page6 1.0 PURPOSEANDOBJECTIVE FollowingtheaccidentattheFukushimaDaiichinuclearpowerplantresultingfromtheMarch11, 2011,GreatTohokuEarthquakeandsubsequenttsunami,theNuclearRegulatoryCommission(NRC) establishedaNearTermTaskForce(NTTF)toconductasystematicreviewofNRCprocessesand regulationsandtodetermineiftheagencyshouldmakeadditionalimprovementstoitsregulatory system.TheNTTFdevelopedasetofrecommendationsintendedtoclarifyandstrengthenthe regulatoryframeworkforprotectionagainstnaturalphenomena.Subsequently,theNRCissueda 50.54(f)letteronMarch12,2012[1],requestinginformationtoassurethattheserecommendations areaddressedbyallU.S.nuclearpowerplants.The50.54(f)letterrequeststhatlicenseesandholders ofconstructionpermitsunder10CFRPart50reevaluatetheseismichazardsattheirsitesagainst presentdayNRCrequirementsandguidance.Dependingonthecomparisonbetweenthereevaluated seismichazardandthecurrentdesignbasis,furtherriskassessmentmayberequired.Assessment approachesacceptabletothestaffincludeaseismicprobabilisticriskassessment(SPRA),oraseismic marginassessment(SMA).Basedupontheassessmentresults,theNRCstaffwilldeterminewhether additionalregulatoryactionsarenecessary.

ThisreportdescribestheExpeditedSeismicEvaluationProcess(ESEP)undertakenforTennesseeValley Authority(TVA)BrownsFerryNuclearPlantUnits1,2,and3.TheintentoftheESEPistoperforman interimactioninresponsetotheNRCs50.54(f)lettertodemonstrateseismicmarginthroughareview ofasubsetoftheplantequipmentthatcanbereliedupontoprotectthereactorcorefollowing beyonddesignbasisseismicevents.

TheESEPisimplementedusingthemethodologiesintheNRCendorsedguidanceinElectricPower ResearchInstitute(EPRI)3002000704,SeismicEvaluationGuidance:AugmentedApproachforthe ResolutionofFukushimaNearTermTaskForceRecommendation2.1:Seismic[2].

TheobjectiveofthisreportistoprovidesummaryinformationdescribingtheESEPevaluationsand results.ThelevelofdetailprovidedinthereportisintendedtoenabletheNRCtounderstandthe inputsused,theevaluationsperformed,andthedecisionsmadeasaresultoftheinterimevaluations.

2.0 BRIEF

SUMMARY

OFTHEFLEXSEISMICIMPLEMENTATIONSTRATEGIES TheBrownsFerryNuclearPlantFLEXstrategiesforReactorCoreCoolingandHeatRemoval,Reactor InventoryControl,andContainmentFunctionaresummarizedbelow.Thissummaryisderivedfrom theBrownsFerryNuclearPlantOverallIntegratedPlan(OIP)inResponsetotheMarch12,2012, CommissionOrderEA12049submittedinFebruary2013[3]andisconsistentwiththethirdsixmonth statusreportissuedtotheNRCinAugust2014[4].

TheOIPprovidesanindepthsequenceofeventsthatdescribestheresponseoftheplanttothe ExtendedLossofallACPower(ELAP)andlossofUltimateHeatSink(UHS)andtheoperatoractionsto betaken.Themajormilestonesoftheresponsearedescribedforeachphaseoftheresponsetothe BeyondDesignBasisExternalEvent(BDBEE).

CoreCoolingandHeatRemoval DuringPhase1(approximatelythefirsteight(8)hours)reactorcorecoolingwillbemaintainedby usingtheReactorCoreIsolationCooling(RCIC)systemalignedtotakesuctionfromthetorus.Pressure controlwillbemaintainedbyutilizingtheSafetyReliefValves(SRVs).AcontrolledReactorPressure Vessel(RPV)depressurizationwillbeginapproximatelythirty(30)minutesafterreactorshutdown

BrownsFerryNuclearPlantESEPReport Page7 usingtheRCICsystemandmanuallycyclingtheSRVstoreducetheRPVtoapressureof150psig.The RPVwillbemaintainedbetween150psigand200psiguntilthebeginningofPhase2.

DuringPhase1,fireprotectionpersonnelaredispatchedtodeploytheportableFLEXpumpingsystems andcommencelayinghoseasrequiredfortransitiontoPhase2.

Atapproximatelyeight(8)hoursintotheevent(beginningofPhase2),theoperatorswilllowerRPV pressurebyusingSRVstoreducepressure,allowingfortransitionfromRCICtoinjectingriverwater utilizingtheportableFLEXpumpingsystemstakingadvantageoftheResidualHeatRemoval(RHR) servicewater/RHRcrosstie.

ContainmentIntegrity DuringPhase1,containmentintegrityismaintainedbycontrollingreactorparameterstonotchallenge containmentlimitswithinthefirsteight(8)hoursoftheevent.

DuringPhase2containmentcoolingisaccomplishedbycontainmentventing,utilizingtheexisting hardenedwetwellventsystem,astheprimarystrategyforcontainmentcooling.Thiswillutilizeanew severeaccidentcapableventingsystem,asdescribedinNRCOrderEA13109[5].Containmentspray canstillbeaccomplishedwithportableFLEXpumpingsystemsutilizingtheservicewatertoRHRcross tiefeaturetoaugmentcontainmentventing.

SupportSystems The250VDCsystem,suppliedbybatteriesinPhase1andbatteriesandbatterychargersinPhases2 and3,supportstheoperationoftheRCICsystemAutomaticDepressurizationSystem (ADS)valves Phase1InstrumentationandControl(I&C)components,aswellasthecontrolpowerforthe480VAC shutdownboardsassociatedwiththeESELloadsinPhases2and3.

Batteryboards1,2,and3supplyloadsinallthreeunits,soallthreebatteryboards,theirassociated 250VDCbatteriesandbatterychargers,andall250VDCReactorMotorOperatedValve(RMOV) boardshavebeenaddedtotheESEL.AlsoontheESELare250VDCpanelsSBA,SBB,SBC,SBD,and SBEBandtheirassociatedbatteriesandbatterychargers.

Twoportable480VFLEXGeneratorswillbeavailable.Asinglegeneratorhasthecapacitytosupplyall safetyrelated250VDCbatterychargersviaaloadcontrolcenter.ThesewillbeavailablebeforePhase 2.A480VFLEXgeneratorcanbeconnectedtoadistributionpanelandprovidepowerforthe250VDC UnitBatteryCharger#1,250VDCUnitBatteryCharger#2A,and250VDCUnitBatteryCharger#3.

Twoportable1.1MWe,4kvFLEXSupportGeneratorswillbedeployedandconnectedtothe4.6KV shutdownboardstopowerMOVswiththeabilitytosupplyadditionalloadssuch:

120VACinstrumentation Ventilation Pumpmotors Figures1a,1b,and2aof[4]providetheFLEXflowpathsforBFN.

3.0 EQUIPMENTSELECTIONPROCESSANDESEL TheselectionofequipmentfortheExpeditedSeismicEquipmentList(ESEL)followedtheguidelinesof EPRI3002000704[2].TheESELforBrownsFerryNuclearPlantUnits1,2,and3ispresentedin AttachmentA.InformationpresentedinAttachmentAisdrawnfromReference[6].

BrownsFerryNuclearPlantESEPReport Page8 3.1 EquipmentSelectionProcessandESEL TheselectionofequipmenttobeincludedontheESELwasbasedoninstalledplantequipment creditedintheFLEXstrategiesduringPhase1,2and3mitigationofaBDBEE,asoutlinedintheBrowns FerryNuclearPlantOIPinResponsetotheMarch12,2012,CommissionOrderEA12049[3]andis consistentwiththethirdsixmonthstatusreportissuedtotheNRCinAugust2014[4].TheOIP providestheBrownsFerryNuclearPlantFLEXmitigationstrategyandservesasthebasisforequipment selectedfortheESEP.

ThescopeofinstalledplantequipmentincludesequipmentrelieduponfortheFLEXstrategiesto sustainthecriticalfunctionsofcorecoolingandcontainmentintegrityconsistentwiththeBrowns FerryNuclearPlantOIP.FLEXrecoveryactionsareexcludedfromtheESEPscopeperEPRI3002000704

[2].TheoveralllistofplannedFLEXmodificationsandthescopeforconsiderationhereinislimitedto thoserequiredtosupportcorecooling,reactorcoolantinventoryandsubcriticality,andcontainment integrityfunctions.PortableandprestagedFLEXequipment(notpermanentlyinstalled)areexcluded fromtheESELperEPRI3002000704.

TheESELcomponentselectionfollowedtheEPRIguidanceoutlinedinSection3.2ofEPRI3002000704.

1. Thescopeofcomponentsislimitedtothatrequiredtoaccomplishthecorecoolingand containmentsafetyfunctionsidentifiedinTable32ofEPRI3002000704.The instrumentationmonitoringrequirementsforcorecooling/containmentsafetyfunctions arelimitedtothoseoutlinedintheEPRI3002000704guidance,andareasubsetofthose outlinedintheBrownsFerryNuclearPlantOIP.

2. Thescopeofcomponentsislimitedtoinstalledplantequipment,andFLEXconnections necessarytoimplementtheBrownsFerryNuclearPlantOIPasdescribedinSection2.

3. ThescopeofcomponentsassumesthecreditedFLEXconnectionmodificationsare implemented,andarelimitedtothoserequiredtosupportasingleFLEXsuccesspath(i.e.,

eitherPrimaryorBackup/Alternate).

4. ThePrimaryFLEXsuccesspathistobespecified.SelectionoftheBackup/Alternate FLEXsuccesspathmustbejustified.

5. Phase3copingstrategiesareincludedintheESEPscope,whereasrecoverystrategiesare excluded.

6. Structures,systems,andcomponentsexcludedpertheEPRI3002000704guidanceare:

Structures(e.g.containment,reactorbuilding,controlbuilding,auxiliarybuilding,etc.)

Piping,cabling,conduit,HVAC,andtheirsupports Manualvalvesandrupturedisks PoweroperatedvalvesnotrequiredtochangestateaspartoftheFLEXmitigation strategies Nuclearsteamsupplysystemcomponents(e.g.RPVandinternals,reactorcoolant pumpsandseals,etc.)

7. Forcasesinwhichneitherdivisionwasspecifiedasaprimaryorbackupstrategy,thenonly onedivisioncomponent(generallyDivisionI)isincludedintheESEL

BrownsFerryNuclearPlantESEPReport Page9 3.1.1 ESELDevelopment TheESELwasdevelopedbyreviewingtheBrownsFerryNuclearPlantOIP[3][4]todeterminethe majorequipmentinvolvedintheFLEXstrategies.Furtherreviewsofplantdrawings(e.g.,Pipingand InstrumentationDiagrams(P&IDs)andElectricalOneLineDiagrams)wereperformedtoidentifythe boundariesoftheflowpathstobeusedintheFLEXstrategiesandtoidentifyspecificcomponentsin theflowpathsneededtosupportimplementationoftheFLEXstrategies.Boundarieswereestablished atanelectricalormechanicalisolationdevice(e.g.,isolationamplifier,valve,etc.)inbranch circuits/branchlinesoffthedefinedstrategyelectricalorfluidflowpath.P&IDsweretheprimary referencedocumentsusedtoidentifymechanicalcomponentsandinstrumentation.Theflowpaths usedforFLEXstrategieswereselectedandspecificcomponentswereidentifiedusingdetailed equipmentandinstrumentdrawings,pipingisometrics,electricalschematicsandonelinedrawings, systemdescriptions,designbasisdocuments,etc.,asnecessary.Hostcomponentswereidentifiedfor subassemblies.

Cabinetsandequipmentcontrolscontainingrelays,contactors,switches,potentiometers,circuit breakersandotherelectricalandinstrumentationthatcouldbeaffectedbyhighfrequencyearthquake motionsandthatimpacttheoperationofequipmentintheESELarerequiredtobeontheESEL.These cabinetsandcomponentswereidentifiedintheESEL.FortheESEL,therelaysidentifiedwereinthe RCICandAutomaticDepressurizationSystem(ADS),andmalfunctionoftheserelaysduringaseismic eventcouldleadtothefailureofthereactorcorecoolingsafetyfunction.

ForPhase1,RCICisthepreferredpathforinventorycontrolandcorecooling.Therefore,theRCIC systemwasusedasthebasisforthePhase1ESEL.ForPhase2andPhase3,inventorycontroland corecoolingismaintainedbyportableFLEXpumpsinjectingtotheRHRservicewaterandtotheRHR systemviatheRHRservicewatertoRHRcrosstie.Relaysthatcouldmalfunctionduringaseismic eventandpreventsuccessfulRCICoperationwereincludedintheESEL.

ForeachparametermonitoredduringtheFLEXimplementation,asingleindicationwasselectedfor inclusionintheESEL.Foreachparameterindication,thecomponentsalongtheflowpathfrom measurementtoindicationwereincluded,sinceanyfailurealongthepathwouldleadtofailureofthat indication.Componentssuchasflowelementswereconsideredaspartofthepipingandwerenot includedintheESEL.

3.1.2 PowerOperatedValves Page33ofEPRI3002000704[2]notesthatpoweroperatedvalvesnotrequiredtochangestateas partoftheFLEXmitigationstrategiesareexcludedfromtheESEL.Page32alsonotesthatfunctional failuremodesofelectricalandmechanicalportionsoftheinstalledPhase1equipmentshouldbe considered(e.g.RCIC).Toaddressthisconcern,thefollowingguidanceisappliedintheBrownsFerry NuclearPlantESELforfunctionalfailuremodesassociatedwithpoweroperatedvalves:

PoweroperatedvalvesthatremainenergizedduringtheELAPevents(suchasDCpowered valves),wereincludedontheESEL.

PoweroperatedvalvesnotrequiredtochangestateaspartoftheFLEXmitigationstrategies werenotincludedontheESEL.TheseismiceventalsocausestheELAPevent;therefore,the valvesareincapableofspuriousoperationastheywouldbedeenergized.

PoweroperatedvalvesnotrequiredtochangestateaspartoftheFLEXmitigationstrategies duringPhase1,andarereenergizedandoperatedduringsubsequentPhase2and3

BrownsFerryNuclearPlantESEPReport Page10 strategies,werenotevaluatedforspuriousvalveoperationastheseismiceventthatcaused theELAPhaspassedbeforethevalvesarerepowered.

3.1.3 PullBoxes PullboxesweredeemedunnecessarytobeaddedtotheESELsasthesecomponentsprovide completelypassivelocationsforpullingorinstallingcables.Nobreaksorconnectionsinthecabling wereincludedinpullboxes.Pullboxeswereconsideredpartofconduitandcabling,whichwere excludedinaccordancewithEPRI3002000704[2].

3.1.4 TerminationCabinets Terminationcabinets,includingcabinetsnecessaryforFLEXPhase2andPhase3connections,provide consolidatedlocationsforpermanentlyconnectingmultiplecables.Theterminationcabinetsandthe internalconnectionsprovideacompletelypassivefunction;however,thecabinetsareincludedinthe ESELtoensureindustryknowledgeonpanel/anchoragefailurevulnerabilitiesisaddressed.

3.1.5 CriticalInstrumentationIndicators Criticalindicatorsandrecordersaretypicallyphysicallylocatedonpanels/cabinetsandareincludedas separatecomponents;however,seismicevaluationoftheinstrumentindicationmaybeincludedinthe panel/cabinetseismicevaluation(ruleofthebox).

3.1.6 Phase2and3PipingConnections Item2inSection3.1abovenotesthatthescopeofequipmentintheESELincludesFLEX connectionsnecessarytoimplementtheBrownsFerryNuclearPlantOIP[3]asdescribedinSection2.

Item3inSection3.1alsonotesthatThescopeofcomponentsassumesthecreditedFLEXconnection modificationsareimplemented,andarelimitedtothoserequiredtosupportasingleFLEXsuccesspath (i.e.,eitherPrimaryorBackup/Alternate).

Item6inSection3.1abovegoesontoexplainthatPiping,cabling,conduit,HVAC,andtheirsupports areexcludedfromtheESELscopeinaccordancewithEPRI3002000704[2].

Therefore,pipingandpipesupportsassociatedwithFLEXPhase2andPhase3connectionsare excludedfromthescopeoftheESEPevaluation.However,anyactivevalvesinFLEXPhase2andPhase 3connectionflowpathareincludedintheESEL.

3.2 JustificationforUseofEquipmentThatisNotthePrimaryMeansforFLEXImplementation TheBrownsFerryNuclearPlantESELisbasedontheprimarymeansofimplementingtheFLEX strategy.Therefore,noadditionaljustificationisrequired.

4.0 GROUNDMOTIONRESPONSESPECTRUM(GMRS) 4.1 PlotofGMRSSubmittedbytheLicensee TheDesignBasisEarthquake(DBE)controlpointelevationisdefinedatthebaseoftheReactor Building,whichcorrespondstoadepthof52ft.(El.519)andisthedeepeststructurefoundation elevationcontrolpoint.HereafterDBEisreferredtoasSafeShutdownEarthquake(SSE).Table41 showstheGMRSaccelerationsforarangeoffrequencies.TheGMRSatthecontrolpointelevationis showninFigure41[7].

BrownsFerryNuclearPlantESEPReport Page11 Table41: GMRSforBrownsFerryNuclearPlant Frequency (Hz)

GMRS (g) 100 2.71E01 90 2.74E01 80 2.79E01 70 2.93E01 60 3.28E01 50 4.04E01 40 4.90E01 35 5.20E01 30 5.57E01 25 5.80E01 20 5.68E01 15 5.27E01 12.5 4.99E01 10 4.73E01 9

4.56E01 8

4.25E01 7

4.05E01 6

3.96E01 5

3.52E01 4

3.19E01 3.5 3.02E01 3

2.80E01 2.5 2.47E01 2

2.31E01 1.5 1.98E01 1.25 1.77E01 1

1.46E01 0.9 1.37E01 0.8 1.30E01 0.7 1.21E01 0.6 1.08E01 0.5 9.54E02 0.4 7.63E02 0.35 6.68E02 0.3 5.72E02 0.25 4.77E02 0.2 3.82E02 0.15 2.86E02 0.125 2.39E02 0.1 1.91E02

BrownsFerryNuclearPlantESEPReport Page12

Figure41:GMRSatControlPointforBrownsFerryNuclearPlant 4.2 ComparisontoSSE TheSSEwasdevelopedconsistentwith10CFRPart100,AppendixAthroughanevaluationofthe maximumearthquakepotentialfortheregionsurroundingthesite.Consideringthehistoricseismicity ofthesiteregion,BrownsFerryNuclearPlantwasdesignedusingaconservativeassumptionthata seismiceventatanunstatedlocationcouldcausearesponsewithanintensityVIIontheModified MercalliIntensityScaleof1931attheplantsite.

TheSSEisdefinedintermsofaPeakGroundAcceleration(PGA)andadesignresponsespectrum.

ConsideringasiteintensityofVII,aPGAof0.20gwasestimated.Table42showsthespectral accelerationvaluesasafunctionoffrequencyforthe5%dampedhorizontalSSE[7].

Table42: SSEforBrownsFerryNuclearPlant Frequency (Hz)

SpectralAcceleration (g) 100 0.2 25 0.2 10 0.22 5

0.3 2.5 0.28 1

0.16 0.5 0.12

BrownsFerryNuclearPlantESEPReport Page13

Figure42: GMRStoSSEComparisonforBrownsFerryNuclearPlant TheSSEenvelopstheGMRSforlowerfrequencyrangeupto3Hz.TheGMRSexceedstheSSEbeyond thatpoint.AstheGMRSexceedstheSSEinthe1to10Hzrange,theplantdoesnotscreenoutofthe ESEPaccordingtoSection2.2ofEPRI3002000704[2].Thetwospecialscreeningconsiderationsas describedinSection2.2.1ofEPRI3002000704,namelya)LowSeismicHazardSiteandb)NarrowBand Exceedancesinthe1to10HzrangedonotapplyforBrownsFerryNuclearPlantandhenceHigh ConfidenceofaLowProbabilityofFailure(HCLPF)evaluationsarerequired.

5.0 REVIEWLEVELGROUNDMOTION(RLGM) 5.1 DescriptionofRLGMSelected Section4ofReference[2]presentstwoapproachesfordevelopingtheReviewLevelGroundMotion (RLGM)tobeusedintheESEP:

1. TheRLGMmaybederivedbylinearlyscalingtheSSEbythemaximumratiooftheGMRS/SSE betweenthe1and10Hzrange(nottoexceed2xSSE).InstructureRLGMseismicmotions wouldbederivedusingexistingSSEbasedinstructureresponsespectra(ISRS)withthesame scalefactor.

2. Alternately,licenseeswhohavedevelopedappropriatestructural/soilstructureinteraction (SSI)modelscapableofcalculatingISRSbasedonsiteGMRS/uniformhazardresponse spectrum(UHRS)inputmayopttousetheseISRSinlieuofscaledSSEISRS.

BasedonareviewoftabulateddatainTables41andtheSSEvaluesofTable42,intherange between1and10HzthemaximumratioofGMRStotheSSEiscalculatedtobe:

SFmax=SAGMRS(10HZ)/SASSE10Hz)=0.473g/0.22g=2.15 Sincethecomputedscalefactorisgreaterthan2.0,theRLGMwouldbesetalevelof2xSSE.Thisis showninTable51andFigure51.

BrownsFerryNuclearPlantESEPReport Page14 Table51:2xSSEforBrownsFerryNuclearPlant Frequency (Hz)

SpectralAcceleration (g) 100 0.4 25 0.4 10 0.44 5

0.6 2.5 0.56 1.0 0.32 0.5 0.24

Figure51:2xSSEforBrownsFerryNuclearPlant 5.2 MethodtoEstimateInStructureResponseSpectra(ISRS)

TheRLGMISRSforBrownsFerryNuclearPlantaregeneratedbyscalingthedesignbasisSSEupto0.3g RLEasdeterminedintheSeismicIPEEE.AdditionalinformationisprovidedinSection6.1.

6.0 SEISMICMARGINEVALUATIONAPPROACH ItisnecessarytodemonstratethatESELitemshavesufficientseismiccapacitytomeetorexceedthe demandcharacterizedbytheRLGM.TheseismiccapacityischaracterizedasthePGAforwhichthere isaHCLPF.ThePGAisassociatedwithaspecificspectralshape,inthiscasethe5%dampedRLGM spectralshape.TheHCLPFcapacitymustbeequaltoorgreaterthantheRLGMPGA.Thecriteriafor seismiccapacitydeterminationaregiveninSection5ofEPRI3002000704[2].

TherearetwobasicapproachesfordevelopingHCLPFcapacities:

BrownsFerryNuclearPlantESEPReport Page15

1.

Deterministicapproachusingtheconservativedeterministicfailuremargin(CDFM) methodologyofEPRINP6041SL,AMethodologyforAssessmentofNuclearPower PlantSeismicMargin(Revision1)[8].

2.

ProbabilisticapproachusingthefragilityanalysismethodologyofEPRITR103959, MethodologyforDevelopingSeismicFragilities[9].

6.1 SummaryofMethodologiesUsed BrownsFerryNuclearPlantperformedaSMAforUnits2and3in1996andUnit1in2004.TheSMAis documentedinReferences[10]and[11]andconsistedofscreeningwalkdownsandHCLPFanchorage calculations.ThescreeningwalkdownsusedthescreeningtablesfromChapter2ofEPRINP6041SL

[8].ThewalkdownswereconductedbyengineerstrainedinEPRINP6041SL(theengineersattended theEPRISMAAddOncourseinadditiontotheSQUGWalkdownScreeningandSeismicEvaluation TrainingCourse),andweredocumentedonScreeningEvaluationWorkSheets(SEWS)fromEPRINP 6041SL.AnchoragecapacitycalculationsusedtheCDFMcriteriafromEPRINP6041SL.Seismic demandwastheIndividualPlantExaminationofExternalEvents(IPEEE)ReviewLevelEarthquake(RLE) forSMA(meanNUREG/CR0098[12]groundresponsespectrumanchoredto0.3gPGA).

Figure61showsthemeanNUREG/CR0098groundresponsespectrumusedastheIPEEERLEforthe SMA,comparedtotheESEPRLGMresponsespectrum.ThefigureshowsthatIPEEERLEenvelopesthe ESEPRLGMatallfrequenciesbetween1and10Hz.

Figure61:ComparisonofBrownsFerryNuclearPlantRLGMandIPEEERLE 6.2 HCLPFScreeningProcess TheSMAwasbasedontheIPEEERLE,whichwasanchoredto0.3gpeakgroundacceleration.Browns FerryNuclearPlantUnits2and3identifiedaminimumHCLPFof0.26gandUnit1identifieda minimumHCLPFofatleast0.3g.Thelimitingconfigurationswerereevaluated[13]anddeterminedto alsohaveaHCLPFcapacityofatleast0.3g.Notethesecomponentshavebeenreplaced.TheRLEis greaterthantheRLGMatfrequenciesbetween1Hzto10Hz.Therefore,anycomponentswhoseSMA basedHCLPFcapacityexceedstheRLEcanbescreenedoutfromHCLPFcalculations.Thescreening tablesinEPRINP6041SL[8]arebasedongroundpeakspectralaccelerationsof0.8gand1.2g.These

BrownsFerryNuclearPlantESEPReport Page16 bothexceedtheRLGMpeakspectralacceleration.Theanchoragecapacitycalculationswerebasedon SSEfloorresponsespectrascaledtotheRLE.Equipmentforwhichthescreeningcaveatsweremetand forwhichtheanchoragecapacityexceededtheRLEseismicdemandcanbescreenedoutfromESEP seismiccapacitydeterminationbecausetheHCLPFcapacityexceedstheRLGM.

TheBrownsFerryNuclearPlantUnits1,2and3ESELcontainsatotalof549items.Ofthese,135are valves,bothpoweroperatedandrelief.InaccordancewithTable24ofEPRINP6041SL[8]active valvesmaybeassignedafunctionalcapacityof0.8gpeakspectralaccelerationwithoutanyreview otherthanlookingforvalveswithlargeextendedoperatorsonsmalldiameterpiping,andanchorageis notafailuremode.Therefore,valvesontheESELmaybescreenedoutfromESEPseismiccapacity determination,subjecttothecaveatregardinglargeextendedoperatorsonsmalldiameterpiping.

ThenonvalvecomponentsintheESELaregenerallyscreenedbasedontheSMAresults.IftheSMA showedthatthecomponentmettheEPRINP6041SLscreeningcaveatsandtheCDFMcapacity exceededtheRLEdemand,thecomponentcanbescreenedoutfromtheESEPcapacitydetermination.

6.3 SeismicWalkdownApproach 6.3.1 WalkdownApproach WalkdownswereperformedinaccordancewiththecriteriaprovidedinSection5ofEPRI3002000704

[2],whichreferstoEPRINP6041SL[8]fortheSeismicMarginAssessmentprocess.Pages226 through230ofEPRINP6041SLdescribetheseismicwalkdowncriteria,includingthefollowingkey criteria.

TheSRT[SeismicReviewTeam]shouldwalkby100%ofallcomponentswhicharereasonably accessibleandinnonradioactiveorlowradioactiveenvironments.Seismiccapability assessmentofcomponentswhichareinaccessible,inhighradioactiveenvironments,orpossibly withincontaminatedcontainment,willhavetorelymoreonalternatemeanssuchas photographicinspection,morerelianceonseismicreanalysis,andpossibly,smallerinspection teamsandmorehurriedinspections.A100%walkbydoesnotmeancompleteinspectionof eachcomponent,nordoesitmeanrequiringanelectricianorothertechniciantodeenergize andopencabinetsorpanelsfordetailedinspectionofallcomponents.Thiswalkdownisnot intendedtobeaQAorQCrevieworareviewoftheadequacyofthecomponentattheSSElevel.

IftheSRThasareasonablebasisforassumingthatthegroupofcomponentsaresimilarandare similarlyanchored,thenitisonlynecessarytoinspectonecomponentoutofthisgroup.The similaritybasisshouldbedevelopedbeforethewalkdownduringtheseismiccapability preparatorywork(Step3)byreferencetodrawings,calculationsorspecifications.Theone componentoreachtypewhichisselectedshouldbethoroughlyinspectedwhichprobablydoes meandeenergizingandopeningcabinetsorpanelsforthisverylimitedsample.Generally,a sparerepresentativecomponentcanbefoundsoastoenabletheinspectiontobeperformed whiletheplantisinoperation.Atleastfortheonecomponentofeachtypewhichisselected, anchorageshouldbethoroughlyinspected.

Thewalkdownprocedureshouldbeperformedinanadhocmanner.Foreachclassof componentstheSRTshouldlookcloselyatthefirstitemsandcomparethefieldconfigurations withtheconstructiondrawingsand/orspecifications.Ifaonetoonecorrespondenceisfound, thensubsequentitemsdonothavetobeinspectedinasgreatadetail.Ultimatelythe walkdownbecomesawalkbyofthecomponentclassastheSRTbecomesconfidentthatthe

BrownsFerryNuclearPlantESEPReport Page17 constructionpatternistypical.Thisprocedureforinspectionshouldberepeatedforeach componentclass;although,duringtheactualwalkdowntheSRTmaybeinspectingseveral classesofcomponentsinparallel.Ifseriousexceptionstothedrawingsorquestionable constructionpracticesarefoundthenthesystemorcomponentclassmustbeinspectedincloser detailuntilthesystematicdeficiencyisdefined.

The100%walkbyistolookforoutliers,lackofsimilarity,anchoragewhichisdifferentfrom thatshownondrawingsorprescribedincriteriaforthatcomponent,potentialSI[Seismic Interaction]problems,situationsthatareatoddswiththeteammemberspastexperience,and anyotherareasofseriousseismicconcern.Ifanysuchconcernssurface,thenthelimited samplesizeofonecomponentofeachtypeforthoroughinspectionwillhavetobeincreased.

Theincreaseinsamplesizewhichshouldbeinspectedwilldependuponthenumberofoutliers anddifferentanchorages,etc.,whichareobserved.ItisuptotheSRTtoultimatelyselectthe samplesizesincetheyaretheoneswhoareresponsiblefortheseismicadequacyofallelements whichtheyscreenfromthemarginreview.AppendixDgivesguidanceforsamplingselection.

6.3.2 ApplicationofPreviousWalkdownInformation SeveralESELitemswerepreviouslywalkeddownduringtheBrownsFerryNuclearPlantUnits1,2and 3,SeismicIPEEEprogram.Thosewalkdownresultswerereviewedandthefollowingstepsweretaken toconfirmthatthepreviouswalkdownconclusionsremainedvalid.

Awalkbywasperformedtoconfirmthattheequipmentmaterialconditionandconfigurationis consistentwiththewalkdownconclusionsandthatnonewsignificantinteractionsrelatedto blockwallsorpipingattachedtotanksexist.

IftheESELitemwasscreenedoutbasedonthepreviouswalkdown,thatscreeningevaluation wasreviewedandreconfirmedfortheESEP.

InallcasesitwasdeterminedthattheHCLPFcapacitiesestablishedfortheseitemsundertheseismic IPEEEprogramremainedvalid.Thus,allESELcomponentsthatwerepartoftheIPEEEprogramhavea HCLPFcapacityof0.3gorgreaterandarethusadequateforESEP[7].

6.3.3 SignificantWalkdownFindings ConsistentwiththeguidancefromEPRINP6041SL[8],nosignificantoutliersoranchorageconcerns wereidentifiedduringtheBrownsFerryNuclearPlantUnits1,2and3seismicwalkdowns.Basedon walkdownresults,HCLPFcapacityevaluationswererecommendedforthefollowingtwelve(12) components:

RCICTurbineDrivenPump TerryTurbineControlBox VacuumTank RCICBackUpControlPanel MainControlRoomBenchboard LPNLInstrumentRack MotorOperatedValve

BrownsFerryNuclearPlantESEPReport Page18 AirOperatedValve PipingandTubing ElectricalRaceways BlockWalls RelayEvaluations 6.4 HCLPFCalculationProcess ESELitemsnotincludedinthepreviousIPEEEevaluationsatBrownsFerryNuclearPlantwere evaluatedusingthecriteriainEPRINP6041SL[8].Thoseevaluationsincludedthefollowingsteps:

Performingseismiccapabilitywalkdownsforequipmentnotincludedinpreviousseismic walkdowns(SQUG,IPEEE,orNTTF2.3)toevaluatetheequipmentinstalledplantconditions PerformingscreeningevaluationsusingthescreeningtablesinEPRINP6041SLasdescribedin Section6.2 PerformingHCLPFcalculationsconsideringvariousfailuremodesthatincludebothstructural failuremodes(e.g.anchorage,loadpathetc.)andfunctionalfailuremodes AllHCLPFcalculationswereperformedusingtheCDFMmethodologyandaredocumentedinTVA Calculation:CDQ9992014000268BFNExpeditedSeismicEvaluationProcess(ESEP)HCLPFCapacity Calculation[13].

6.5 FunctionalEvaluationsofRelays TheESELidentifiesessentialrelaysforESEP.AlloftheserelaysareassociatedwiththeRCICsystem.

TherelaysarethesameconfigurationandtypeforBrownsFerryNuclearPlantUnits1,2,and3.Allof therelaysareinthenormallyopenstate,exceptforfour(4)thatcanbeexcludedfromthisevaluation becausechatterisacceptable.Therelaytypesaddressedinthisevaluationincludethefollowing:

GE12HFA51A41 GE12HFA151A1F GE12HGA11A51F AMERACE7012SB(formerlyAgastat)

TherelayswereevaluatedusingtheguidanceprovidedinEPRINP6041SL[8]forequipmentqualified bytesting(relayGERS).SubjectrelaysweredeterminedtohavehigherHCLPFvaluesthantheplant RLGMaswellastheRLE,withaminimumHCLPFof0.37g.

TheESEPrelayfunctionalevaluationsaredocumentedinaTVAcalculation[13].

6.6 TabulatedESELHCLPFValues(IncludingKeyFailureModes)

TabulatedESELHCLPFvaluesareprovidedinAttachmentB.Thefollowingnotesapplytothe informationinthetables.

ItemspreviouslyincludedintheUSIA46andseismicIPEEEprogramsarenotlisted.Walkby verificationsreconfirmedtheHCLPFcapacitiesfromtheIPEEE,andtheIPEEE0.3gRLEHCLPF capacityexceedstheRLGM.

BrownsFerryNuclearPlantESEPReport Page19 HCLPFcapacityevaluationswereperformedforthenonIPEEEitemsontheESEL,addressing bothstructural/anchorageandfunctionalfailuremodes.TheHCLPFcapacityofeachitemis listedinthetables,withassociatedgoverningfailuremode.

NewpermanentlyinstalledFLEXitemsarenotlisted.TVAdesigncriteriaBFN57360[14]

requiresthatnewFLEXitemshaveHCLPFcapacityexceedingtheRLGM.

AllESEPcomponentshaveaHCLPFcapacitygreaterthantheRLGMforthefrequencyrangeof1to 10Hz.

7.0 INACCESSIBLEITEMS 7.1 IdentificationofESELItemInaccessibleforWalkdowns InsideDrywellwasnotaccessibleduringthewalkbyverifications.ThecomponentsinsidetheDrywell consistoftheseismicallyruggedMainSteamSafetyReliefValves(MSRVs)andassociatedaccumulators andsolenoidvalves.TheMSRVsarelocatedinanupperelevationregionoftheDrywell,andbydesign areremotefromotherplantfeatures.TheBrownsFerryNuclearPlantoperationsgroupmaintains currentphotographsoftheMSRVsandthesephotographsweremadeavailabletotheSRTforreview forESEP.Basedonclosereviewofallofthephotographs,itwasconfirmedthattheMSRVsand associatedsubcomponentsareintact,wellmaintained,andremotefromanynearbyitemandthus freeofseismicinteractionconcerns.Itwasnotedthatthechainfallsfromtheoverheadmonorail crane(usedforMSRVreplacementservice)wasappropriatelysecuredwellawayfromtheMSRVs.

Basedontheseobservations,itisconcludedthatnofurtherinvestigationisrequiredfortheserugged items.

7.2 PlannedWalkdown/EvaluationSchedule/CloseOut Therearenocomponentsthatrequirefollowupseismicwalkdowns.

8.0 ESEPCONCLUSIONSANDRESULTS 8.1 SupportingInformation BrownsFerryNuclearPlantUnits1,2,and3haveperformedtheESEPasaninterimactioninresponse totheNRCs50.54(f)letter[1].ItwasperformedusingthemethodologiesintheNRCendorsed guidanceinEPRI3002000704[2].

TheESEPprovidesanimportantdemonstrationofseismicmarginandexpeditesplantsafety enhancementsthroughevaluationsandpotentialneartermmodificationsofplantequipmentthatcan bereliedupontoprotectthereactorcorefollowingbeyonddesignbasisseismicevents.

TheESEPispartoftheoverallBrownsFerryNuclearPlantUnits1,2,and3responsetotheNRCs 50.54(f)letter.OnMarch12,2014,NEIsubmittedtotheNRCresultsofastudy[16]ofseismiccore damageriskestimatesbasedonupdatedseismichazardinformationasitappliestooperatingnuclear reactorsintheCentralandEasternUnitedStates(CEUS).Thestudyconcludedthat"sitespecific seismichazardsshowthattherehasnotbeenanoverallincreaseinseismicriskforthefleetofU.S.

plants"basedonthereevaluatedseismichazards.Assuch,the"currentseismicdesignofoperating reactorscontinuestoprovideasafetymargintowithstandpotentialearthquakesexceedingthe seismicdesignbasis."

BrownsFerryNuclearPlantESEPReport Page20 TheNRCsMay9,2014NTTF2.1ScreeningandPrioritizationletter[15]concludedthatthefleetwide seismicriskestimatesareconsistentwiththeapproachandresultsusedintheGl199safety/risk assessment.TheletteralsostatedthatAsaresult,thestaffhasconfirmedthattheconclusions reachedinGl199safety/riskassessmentremainvalidandthattheplantscancontinuetooperate whileadditionalevaluationsareconducted.

AnassessmentofthechangeinseismicriskforBrownsFerryNuclearPlantUnits1,2,and3was includedinthefleetriskevaluationsubmittedintheMarch12,2014NEIletter[16]therefore,the conclusionsintheNRCsMay9letteralsoapplytoBrownsFerryNuclearPlantUnits1,2,and3.

Inaddition,theMarch12,2014NEIletterprovidedanattachedPerspectivesontheSeismicCapacity ofOperatingPlants,which(1)assessedanumberofqualitativereasonswhythedesignofStructures, SystemsandComponents(SSCs)inherentlycontainmarginbeyondtheirdesignlevel,(2)discussed industrialseismicexperiencedatabasesofperformanceofindustryfacilitycomponentssimilarto nuclearSSCs,and(3)discussedearthquakeexperienceatoperatingplants.

Thefleetofcurrentlyoperatingnuclearpowerplantswasdesignedusingconservativepractices,such thattheplantshavesignificantmargintowithstandlargegroundmotionssafely.Thishasbeenborne outforthoseplantsthathaveactuallyexperiencedsignificantearthquakes.Theseismicdesignprocess hasinherent(andintentional)conservatismswhichresultinsignificantseismicmarginswithinSSCs.

Theseconservatismsarereflectedinseveralkeyaspectsoftheseismicdesignprocess,including:

Safetyfactorsappliedindesigncalculations DampingvaluesusedindynamicanalysisofSSCs Boundingsynthetictimehistoriesforinstructureresponsespectracalculations Broadeningcriteriaforinstructureresponsespectra ResponsespectraenvelopingcriteriatypicallyusedinSSCanalysisandtestingapplications Responsespectrabasedfrequencydomainanalysisratherthanexplicittimehistorybasedtime domainanalysis Boundingrequirementsincodesandstandards Useofminimumstrengthrequirementsofstructuralcomponents(concreteandsteel)

Boundingtestingrequirements Ductilebehavioroftheprimarymaterials(thatis,notcreditingtheadditionalcapacityof materialssuchassteelandreinforcedconcretebeyondtheessentiallyelasticrange,etc.)

ThesedesignpracticescombinetoresultinmarginssuchthattheSSCswillcontinuetofulfilltheir functionsatgroundmotionswellabovetheSSE.

TheintentoftheESEPistoperformaninterimactioninresponsetotheNRCs50.54(f)letterto demonstrateseismicmarginthroughareviewofasubsetoftheplantequipmentthatcanberelied upontoprotectthereactorcorefollowingbeyonddesignbasisseismicevents.Inordertocomplete theESEPinanexpeditedamountoftime,theRLGMusedfortheESEPevaluationisascaledversionof theplantsSSEratherthantheactualGMRS.Tomorefullycharacterizetheriskimpactsoftheseismic groundmotionrepresentedbytheGMRSonaplantspecificbasis,amoredetailedseismicrisk assessment(SPRA,riskbasedSMA,orotherjustification)canbeperformed.BrownsFerryNuclear

BrownsFerryNuclearPlantESEPReport Page21 PlantUnits1,2,and3willcompletethatevaluationinaccordancewiththescheduleidentifiedinNEIs letterdatedApril9,2013[17]andendorsedbytheNRCintheirMay7,2013letter[18].

8.2 IdentificationofPlannedModifications TherearenoadditionalplantmodificationsrequiredforBrownsFerryNuclearPlantUnits1,2and3.

8.3 ModificationImplementationSchedule TherearenoadditionalplantmodificationsrequiredforBrownsFerryNuclearPlantUnits1,2and3.

8.4 SummaryofRegulatoryCommitments TherearenoadditionalactionstobeperformedasaresultoftheESEP.

BrownsFerryNuclearPlantESEPReport Page22

9.0 REFERENCES

1.

NRC(ELeedsandMJohnson)LettertoAllPowerReactorLicenseesetal.,Requestfor InformationPursuanttoTitle10oftheCodeofFederalRegulations50.54(f)Regarding Recommendations2.1,2.3and9.3oftheNearTermTaskForceReviewofInsightsfromthe FukushimaDaiIchiAccident,March12,2012.

2.

EPRI3002000704,SeismicEvaluationGuidance,AugmentedApproachfortheResolutionof FukushimaNearTermTaskForceRecommendation2.1:Seismic,May2013.

3.

TVALettertoU.S.NRC,TennesseeValleyAuthority-OverallIntegratedPlaninResponseto March12,2012,CommissionOrderModifyingLicenseswithRegardtoRequirementsfor MitigationStrategiesforBeyondDesignBasisExternalEvents(OrderNumberEA12049),

February28,2013.

4.

TVALettertoU.S.NRC,ThirdSixMonthStatusReportandRevisedOverallIntegratedPlanin ResponsetoMarch12,2012,CommissionOrderModifyingLicenseswithRegardto RequirementsforMitigationStrategiesforBeyondDesignBasisExternalEvents(OrderNumber EA12049)forBrownsFerryNuclearPlant(TACNos.MF0902,MF0903,andMF0904),August 28,2014.

5.

NRCOrderEA13109,IssuanceofOrdertoModifyLicenseswithRegardtoReliableHardened ContainmentVentsCapableofOperatingUnderSevereAccidentConditions,June6,2013.

6.

AREVANPDocument519217417003,ESEPExpeditedSeismicEquipmentList(ESEL)-Browns FerryNuclearPlantUnits1,2,and3.

7.

TVALettertoU.S.NRC,TennesseeValleyAuthoritysSeismicHazardandScreeningReport (CEUSSites),responsetoNRCRequestforInformationPursuantto10CFR50.54(f)regarding Recommendation2.1oftheNearTermTaskForceReviewofInsightsfromtheFukushimaDai ichiAccident,March31,2014.

8.

EPRINP6041SL,MethodologyforAssessmentofNuclearPowerPlantSeismicMargin, Revision1,August1991.

9.

EPRITR103959,MethodologyforDevelopingSeismicFragilities,July1994.

10.

SeismicIPEEEReport,BrownsFerryNuclearPlant"PreparedbyEQEInc,June1996.

11.

BrownsFerryNuclearPlantUnit1SeismicIPEEEReport,"preparedbyFacilityRiskConsultants, October2004.

12.

U.S.NRCNUREG/CR0098,DevelopmentofCriteriaforSeismicReviewofSelectedNuclear PowerPlants,May1978.

13.

TVACalculationCDQ0009992014000268"BFNExpeditedSeismicEvaluationProcess(ESEP)

HCLPFCapacityCalculation",October2014.

14.

TVADesignCriteriaBFN57360,Revision2,FLEXMitigationSystem.

15.

NRC(E.Leeds)LettertoAllPowerReactorLicenseesetal.,ScreeningandPrioritizationResults RegardingInformationPursuanttoTitle10oftheCodeofFederalRegulations50.54(F)

RegardingSeismicHazardReEvaluationsforRecommendation2.1oftheNearTermTaskForce ReviewofInsightsFromtheFukushimaDaiIchiAccident,May9,2014.

BrownsFerryNuclearPlantESEPReport Page23 16.

NuclearEnergyInstitute(NEI),A.Pietrangelo,LettertoD.SkeenoftheUSNRC,SeismicCore DamageRiskEstimatesUsingtheUpdatedSeismicHazardsfortheOperatingNuclearPlantsin theCentralandEasternUnitedStates,March12,2014.

17.

NuclearEnergyInstitute(NEI),A.Pietrangelo,LettertoD.SkeenoftheUSNRC,ProposedPath ForwardforNTTFRecommendation2.1:SeismicReevaluations,April9,2013.NRCAdams AccessionNo.ML13101A379.

18.

NRC(ELeeds)LettertoNEI(JPollock),ElectricPowerResearchInstituteFinalDraftReport xxxxx,SeismicEvaluationGuidance:AugmentedApproachfortheResolutionofFukushima NearTermTaskForceRecommendation2.1:Seismic,asanAcceptableAlternativetothe March12,2012,InformationRequestforSeismicReevaluations,May7,2013.

BrownsFerryNuclearPlantESEPReport PageA1 ATTACHMENTA-EXPEDITEDSEISMICEQIPMENTLIST(ESEL)FORBROWNSFERRY NUCLEARPLANT

BrownsFerryNuclearPlantESEPReport PageA2 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 1

1FCV7119 RCICPumpCondensate StorageTankSuctionValve Open Closed MustclosetoswapRCICsuctiontothesuppressionpool Power:250VReactorMotorOperatedValve(RMOV)Board 1Cbreaker1BKR0710019 2

1FCV7117 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard1Cbreaker1BKR071 0017 3

1FCV7118 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard1Cbreaker1BKR071 0018 4

1PMP7119 RCICPump Standby Operating ProvidesRPVmakeupinPhase1 5

1FCV7139 RCICDischargeIsolationValve Closed Open Normallyclosed,mustopentosupplyRCICinjectionflow Power:From250VRMOVBoard1Cbreaker1BKR071 0039 6

1PCV7122 RCICLubeOilCoolingWater PressureControlValve Open

ControlscoolingwaterflowtoRCIClubeoilcooler 7

1FCV7125 RCICTurbineLubeOilInlet Valve Closed Open Normallyclosed,openstoallowcoolingwaterflowtoRCIC turbinelubeoilcooler Power:250VRMOVBoard1Cbreaker1BKR0710025 8

1TNK7127 RCICVacuumTank Standby Operating CollectsandcondensesRCICglandsealleakage 9

1CND7127 RCICBarometricCondenser Standby Operating CollectsandcondensesRCICglandsealleakage 10 1CLR7125 RCICLubeOilCooler Standby Operating CoolsRCIClubeoil

BrownsFerryNuclearPlantESEPReport PageA3 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 11 1PMP7129 RCICVacuumTankCondensate Pump Standby Operating Pumpscondensatefromvacuumtanktopumpsuction Power:From250VRMOVBoard1Cbreaker1BKR071 0029 12 1PMP7131 RCICVacuumPump Standby Operating Maintainsvacuumonbarometriccondenser Power:From250VRMOVBoard1Cbreaker1BKR071 0031 13 1FCV718 RCICTurbineSteamInletValve Closed Open OpensonRCICstarttoadmitsteamtoRCICturbine Power:From250VRMOVBoard1Cbreaker1BKR071 0008 14 1FCV719 RCICTurbineSteamThrottle Valve Open Open/Close asneeded TripsclosedonRCICprotectivefunction Power:From250VRMOVBoard1Cbreaker1BKR071 009A 15 1FCV7110 RCICTurbineGovernorValve Open Open/Close asneeded ModulatessteamflowtoRCICturbine 16 1TRB719 RCICTurbine Standby Operating SuppliesmotiveforcetoRCICpump 17 1FT7136 RCICPumpFlowTransmitter forTurbineControl On On TransmitsRCICflowtoflowcontrolcircuit 18 1FIC7136A RCICFlowIndicatingController AutoSetat 620gpm AutoSetat 620gpm ControlsRCICflow 19 1PX7136A PowerSupplyforRCICflow Controller Energized Energized SuppliesACpowertoRCICflowcontrolcircuitry 20 1LPNL925 672 RCICLocalControls Energized Energized LocalcontrolofRCICturbine

BrownsFerryNuclearPlantESEPReport PageA4 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 21 1SC7110 ElectronicGovernorModule Operating Operating

22 113AK15 RCICAutoIsolationSealIn Relay Energized Energized

23 113AK10 RCICHighSpaceTemperature Relay Operable Operable

24 113AK11 RCICHighSpaceTemperature Relay Operable Operable

25 113AK13 RCICLowSteamSupply PressureRelay Operable Operable

26 1271K12 RCICSteamLineHigh DifferentialPressureRelay Operable Operable

27 113AK44 RCICHighRuptureDisc PressureRelay Operable Operable

28 113AK45 RCICHighRuptureDisc PressureRelay Operable Operable

29 113AK12 RCICAutoIsolationSealIn Relay Operable Operable

30 113AK14 RCICAutoIsolationSealIn Relay Operable Operable

31 113AK16 RCICAutoIsolationSealIn Relay Operable Operable

32 113AK38 RCICManualSteamIsolation relay Operable Operable

33 113AK17 RCICAutoDischargeCircuit Resetrelay Operable Operable

BrownsFerryNuclearPlantESEPReport PageA5 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 34 113AK18 RCICAutoDischargeCircuit Resetrelay Operable Operable

35 113AK37 RCICVesselLowWaterLevel relay Operable Operable

36 113AK30 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

37 113AK31 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

38 171K32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

39 113AK32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

40 113AK33 RCICAutoIsolationSignalrelay Operable Operable

RCIC-Unit2 41 2FCV7119 RCICPumpCondensate StorageTankSuctionValve Open Closed MustclosetoswapRCICsuctiontothesuppressionpool Power:From250VRMOVBoard2Cbreaker2BKR071 0019 42 2FCV7117 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard2Cbreaker2BKR071 0017

BrownsFerryNuclearPlantESEPReport PageA6 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 43 2FCV7118 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard2Cbreaker2BKR071 0018 44 2PMP7119 RCICPump Standby Operating ProvidesRPVmakeupinPhase1 45 2FCV7139 RCICDischargeIsolationValve Closed Open Normallyclosed,mustopentosupplyRCICinjectionflow Power:From250VRMOVBoard2Cbreaker2BKR071 0039 46 2PCV7122 RCICLubeOilCoolingWater PressureControlValve Open Open/Close asneeded ControlscoolingwaterflowtoRCIClubeoilcooler 47 2FCV7125 RCICTurbineLubeOilInlet Valve Closed Open Normallyclosed,openstoallowcoolingwaterflowtoRCIC turbinelubeoilcooler Power:From250VRMOVBoard2Cbreaker2BKR071 0025 48 2TNK7127 RCICVacuumTank Standby Operating CollectsandcondensesRCICglandsealleakage 49 2CND7127 RCICBarometricCondenser Standby Operating CollectsandcondensesRCICglandsealleakage 50 2CLR7125 RCICLubeOilCooler Standby Operating CoolsRCIClubeoil 51 2PMP7129 RCICVacuumTankCondensate Pump Standby Operating Pumpscondensatefromvacuumtanktopumpsuction Power:From250VRMOVBoard2Cbreaker2BKR0710029 52 2PMP7131 RCICVacuumPump Standby Operating Maintainsvacuumonbarometriccondenser Power:From250VRMOVBoard2Cbreaker2BKR071 0031

BrownsFerryNuclearPlantESEPReport PageA7 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 53 2FCV718 RCICTurbineSteamInletValve Closed Open OpensonRCICstarttoadmitsteamtoRCICturbine Power:From250VRMOVBoard2Cbreaker2BKR071 0008 54 2FCV719 RCICTurbineSteamThrottle Valve Open Open/Close asneeded TripsclosedonRCICprotectivefunction Power:From250VRMOVBoard2Cbreaker2BKR071 009A 55 2FCV7110 RCICTurbineGovernorValve Open Open/Close asneeded ModulatessteamflowtoRCICturbine 56 2TRB719 RCICTurbine Standby Operating SuppliesmotiveforcetoRCICpump 57 2FT7136 RCICPumpFlowTransmitter forTurbineControl On On TransmitsRCICflowtoflowcontrolcircuit 58 2FIC7136A RCICFlowIndicatingController AutoSetat 620gpm AutoSetat 620gpm ControlsRCICflow 59 2PX7136A PowerSupplyforRCICFlow Controller Energized Energized SuppliesACpowertoRCICflowcontrolcircuitry 60 2LPNL925 672 RCICLocalControls Energized Energized LocalcontrolofRCICturbine 61 2SC7110 ElectronicGovernorModule Operating Operating

62 213AK15 RCICAutoIsolationSealIn Relay Operable Operable

63 213AK10 RCICHighSpaceTemperature Relay Operable Operable

64 213AK11 RCICHighSpaceTemperature Relay Operable Operable

BrownsFerryNuclearPlantESEPReport PageA8 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 65 213AK13 RCICLowSteamSupply PressureRelay Operable Operable

66 2271K12 RCICSteamLineHigh DifferentialPressureRelay Operable Operable

67 213AK44 RCICHighRuptureDiscPres.

Relay Operable Operable

68 213AK45 RCICHighRuptureDisc PressureRelay Operable Operable

69 213AK12 RCICAutoIsolationSealIn Relay Operable Operable

70 213AK14 RCICAutoIsolationSealIn Relay Operable Operable

71 213AK16 RCICAutoIsolationSealIn Relay Operable Operable

72 213AK38 RCICManualSteamIsolation relay Operable Operable

73 213AK17 RCICAutoDischargeCircuit Resetrelay Operable Operable

74 213AK18 RCICAutoDischargeCircuit Resetrelay Operable Operable

75 213AK37 RCICVesselLowWaterLevel relay Operable Operable

76 213AK30 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

77 213AK31 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

BrownsFerryNuclearPlantESEPReport PageA9 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 78 271K32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

79 213AK32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

80 213AK33 RCICAutoIsolationSignalrelay Operable Operable

RCIC-Unit3 81 3FCV7119 RCICPumpCondensate StorageTankSuctionValve Open Closed MustclosetoswapRCICsuctiontothesuppressionpool Power:From250VRMOVBoard3Cbreaker3BKR071 0019 82 3FCV7117 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard3Cbreaker3BKR071 0017 83 3FCV7118 RCICSuctionfromTorus Closed Open Normallyclosed,mustopentosupplyRCICsuctionfrom torus Power:From250VRMOVBoard3Cbreaker3BKR071 0018 84 3PMP7119 RCICPump Standby Operating ProvidesRPVmakeupinPhase1 85 3FCV7139 RCICDischargeIsolationValve Closed Open Normallyclosed,mustopentosupplyRCICinjectionflow Power:From250VRMOVBoard3Cbreaker3BKR071 0039 86 3PCV7122 RCICLubeOilCoolingWater PressureControlValve Open Open/Close asneeded ControlscoolingwaterflowtoRCIClubeoilcooler

BrownsFerryNuclearPlantESEPReport PageA10 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 87 3FCV7125 RCICTurbineLubeOilInlet Valve Closed Open Normallyclosed,openstoallowcoolingwaterflowtoRCIC turbinelubeoilcooler Power:From250VRMOVBoard3Cbreaker3BKR071 0025 88 3TNK7127 RCICVacuumTank Standby Operating CollectsandcondensesRCICglandsealleakage 89 3CND7127 RCICBarometricCondenser Standby Operating CollectsandcondensesRCICglandsealleakage 90 3CLR7125 RCICLubeOilCooler Standby Operating CoolsRCIClubeoil 91 3PMP7129 RCICVacuumTankCondensate Pump Standby Operating Pumpscondensatefromvacuumtanktopumpsuction Power:From250VRMOVBoard3Cbreaker3BKR071 0029 92 3PMP7131 RCICVacuumPump Standby Operating Maintainsvacuumonbarometriccondenser Power:From250VRMOVBoard3Cbreaker3BKR071 0031 93 3FCV718 RCICTurbineSteamInletValve Closed Open OpensonRCICstarttoadmitsteamtoRCICturbine Power:From250VRMOVBoard3Cbreaker3BKR071 0008 94 3FCV719 RCICTurbineSteamThrottle Valve Open Open/Close asneeded TripsclosedonRCICprotectivefunction Power:From250VRMOVBoard3Cbreaker3BKR071 009A 95 3FCV7110 RCICTurbineGovernorValve Open Open/Close asneeded ModulatessteamflowtoRCICturbine 96 3TRB719 RCICTurbine Standby Operating SuppliesmotiveforcetoRCICpump

BrownsFerryNuclearPlantESEPReport PageA11 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 97 3FT7136 RCICPumpFlowTransmitter forTurbineControl On On TransmitsRCICflowtoflowcontrolcircuit 98 3FIC7136A RCICFlowIndicatingController AutoSetat 620gpm AutoSetat 620gpm ControlsRCICflow 99 3PX7136A PowerSupplyforRCICflow Controller Energized Energized SuppliesACpowertoRCICflowcontrolcircuitry 100 3LPNL925 672 RCICLocalControls Energized Energized LocalcontrolofRCICturbine 101 3SC7136A ElectronicGovernorModule Operating Operating

102 313AK15 RCICAutoIsolationSealIn Relay Operable Operable

103 313AK10 RCICHighSpaceTemperature Relay Operable Operable

104 313AK11 RCICHighSpaceTemperature Relay Operable Operable

BrownsFerryNuclearPlantESEPReport PageA12 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 105 313AK13 RCICLowSteamSupply PressureRelay Operable Operable

106 371K12 RCICSteamLineHigh DifferentialPressureRelay Operable Operable

107 313AK44 RCICHighRuptureDisc PressureRelay Operable Operable

108 313AK45 RCICHighRuptureDisc PressureRelay Operable Operable

109 371K12 RCICManualSteamIsolation Relay Operable Operable

110 313AK14 RCICAutoIsolationSealIn Relay Operable Operable

111 313AK16 RCICAutoIsolationSealIn Relay Operable Operable

112 313AK38 RCICManualSteamIsolation relay Operable Operable

113 313AK17 RCICAutoDischargeCircuit Resetrelay Operable Operable

114 313AK18 RCICAutoDischargeCircuit Resetrelay Operable Operable

115 313AK37 RCICVesselLowWaterLevel relay Operable Operable

BrownsFerryNuclearPlantESEPReport PageA13 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 116 313AK30 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

117 313AK31 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

118 371K32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

119 313AK32 RCICSteamLineSpaceExcess TemperatureIsolationrelay Operable Operable

120 313AK33 RCICAutoIsolationSignalrelay Operable Operable

ADS-Unit1 121 TBD FLEXNitrogenBottleRackfor MSRVOperation Operable Operable UNIDtobeestablishedinDCN71387 122 1PCV14 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 123 1PSV14 MS/SolenoidValveforPCV14 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1A 124 1PCV15 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 125 1PSV15 MS/SolenoidValveforPCV15 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1C 126 1ACC32 6106 CA/AccumulatorforPSV15 Operable Operable HoldsoperatingnitrogenforSRV 127 1PCV118 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown

BrownsFerryNuclearPlantESEPReport PageA14 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 128 1PSV118 MS/SolenoidValveforPCV1 18 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1B 129 1PCV119 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 130 1PSV119 MS/SolenoidValveforPCV1 19 Deenergized Energized PilotValveforassociatedSRV Power:From250VDCRMOVBoard1B 131 1ACC32 6105 CA/AccumulatorforPSV119 Operable Operable HoldsoperatingnitrogenforSRV 132 1PCV122 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 133 1PSV122 MS/SolenoidValveforPCV1 22 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1B 134 1ACC32 6107 CA/AccumulatorforPSV122 Operable Operable HoldsoperatingnitrogenforSRV 135 1PCV123 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 136 1PSV123 MS/SolenoidValveforPCV1 23 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1C 137 1PCV130 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 138 1PSV130 MS/SolenoidValveforPCV1 30 Deenergized Energized PilotValveforassociatedSRV Power:From250VDCRMOVBoard1B 139 1ACC32 6108 CA/AccumulatorforPSV130 Operable Operable HoldsoperatingnitrogenforSRV

BrownsFerryNuclearPlantESEPReport PageA15 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 140 1PCV131 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 141 1PSV131 MS/SolenoidValveforPCV1 31 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1B 142 1ACC32 6111 CA/AccumulatorforPSV131 Operable Operable HoldsoperatingnitrogenforSRV 143 1PCV134 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 144 1PSV134 MS/SolenoidValveforPCV1 34 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1C 145 1ACC32 6109 CA/AccumulatorforPSV134 Operable Operable HoldsoperatingnitrogenforSRV 146 1PCV141 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 147 1PSV141 MS/SolenoidValveforPCV1 41 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1A 148 1PCV142 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 149 1PSV142 MS/SolenoidValveforPCV1 42 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1B 150 1PCV1179 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 151 1PSV1179 MS/SolenoidValveforPCV1 179 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1B

BrownsFerryNuclearPlantESEPReport PageA16 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 152 1PCV1180 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 153 1PSV1180 MS/SolenoidValveforPCV1 180 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard1C 154 1HS14 1PCV14ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1A 155 2XS14 TransferSwitchfor2PCV14 Closed Closed

156 1HS15A 1PCV15ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1C 157 1XS15 TransferSwitchfor1PCV15 Closed Closed

158 1HS118 1PCV118ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 159 1XS118 TransferSwitchfor1PCV118 Closed Closed

160 1HS119A 1PCV119ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 161 1XS119 TransferSwitchfor1PCV1 19A Closed Closed

162 1HS122A 1PCV122ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 163 1XS122 TransferSwitchfor2PCV1 22A Closed Closed

164 1HS123A 1PCV123ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1C

BrownsFerryNuclearPlantESEPReport PageA17 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 165 1XS123 TransferSwitchfor2PCV1 23A Closed Closed

166 1HS130A 1PCV130ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 167 1XS130 TransferSwitchfor1PCV1 30A Closed Closed

168 1HS131A 1PCV131ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 169 1XS131 TransferSwitchfor1PCV1 30A Closed Closed

170 1HS134A 1PCV134ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1C 171 1XS134 TransferSwitchfor1PCV134 Closed Closed

172 1HS141 1PCV141ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1A 173 1XS141 TransferSwitchfor1PCV141 Closed Closed

174 1HS142 1PCV142ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 175 1XS142 TransferSwitchfor1PCV142 Closed Closed

176 1HS1179A 1PCV1179ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1B 177 1XS1179 TransferSwitchfor1PCV1 179 Closed Closed

BrownsFerryNuclearPlantESEPReport PageA18 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 178 1HS1180A 1PCV1180ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard1C 179 1XS1180 TransferSwitchfor1PCV1 180 Closed Closed

180 1XS1159A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard1B 181 1XS1161A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard1B 182 1LPNL925 0032 LocalPanel2532:Backup Control Operable Operable FailureofpanelorcomponentscanpreventopeningSRVs ADS-Unit2 183 TBD FLEXNitrogenBottleRackFor MSRVOperation Operable Operable UNIDtobeestablishedinDCN70810 184 2PCV14 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown Power:From250VDCRMOVBoard2A 185 2PSV14 MS/SolenoidValveforPCV14 Deenergized Energized PilotvalveforassociatedSRV 186 2PCV15 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 187 2PSV15 MS/SolenoidValveforPCV15 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2C 188 2ACC32 6106 CA/AccumulatorforPSV15 Operable Operable HoldsoperatingnitrogenforSRV 189 2PCV118 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown

BrownsFerryNuclearPlantESEPReport PageA19 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 190 2PSV118 MS/SolenoidValveforPCV1 18 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B 191 2PCV119 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 192 2PSV119 MS/SolenoidValveforPCV1 19 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B 193 2ACC32 6105 CA/AccumulatorforPSV119 Operable Operable HoldsoperatingnitrogenforSRV 194 2PCV122 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 195 2PSV122 MS/SolenoidValveforPCV1 22 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B 196 2ACC32 6107 CA/AccumulatorForPSV122 Operable Operable HoldsoperatingnitrogenforSRV 197 2PCV123 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 198 2PSV123 MS/SolenoidValveforPCV1 23 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2C 199 2PCV130 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 200 2PSV130 MS/SolenoidValveforPCV1 30 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2A 201 2ACC32 6111 CA/AccumulatorforPSV130 Operable Operable HoldsoperatingnitrogenforSRV

BrownsFerryNuclearPlantESEPReport PageA20 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 202 2PCV131 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 203 2PSV131 MS/SolenoidValveforPCV1 31 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B 204 2ACC32 6108 CA/AccumulatorforPSV131 Operable Operable HoldsoperatingnitrogenforSRV 205 2PCV134 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 206 2PSV134 MS/SolenoidValveforPCV1 34 Deenergized Energized PilotValveforassociatedSRV Power:From250VDCRMOVBoard2C 207 2ACC32 6109 CA/AccumulatorforPSV134 Operable Operable HoldsoperatingnitrogenforSRV 208 2PCV141 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 209 2PSV141 MS/SolenoidValveforPCV1 41 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2A 210 2PCV142 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 211 2PSV142 MS/SolenoidValveforPCV1 42 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B 212 2PCV1179 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 213 2PSV1179 MS/SolenoidValveforPCV1 179 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2B

BrownsFerryNuclearPlantESEPReport PageA21 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 214 2PCV1180 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 215 2PSV1180 MS/SolenoidValveforPCV1 30 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard2C 216 2HS14 2PCV14ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2A 217 2XS14 TransferSwitchfor2PCV14 Closed Closed

218 2HS15A 2PCV15ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2C 219 2XS15 TransferSwitchfor2PCV15 Closed Closed

220 2HS118 2PCV118ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 221 2XS118 TransferSwitchfor2PCV118 Closed Closed

222 2HS119A 2PCV119ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 223 2XS119A TransferSwitchfor2PCV119 Closed Closed

224 2HS122A 2PCV122ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 225 2XS122A TransferSwitchfor2PCV1 22A Closed Closed

226 2HS123 2PCV123ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2C

BrownsFerryNuclearPlantESEPReport PageA22 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 227 2XS123 TransferSwitchfor2PCV123 Closed Closed

228 2HS130A 2PCV130ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2A 229 2XS130 TransferSwitchfor2PCV130 Closed Closed

230 2HS131A 2PCV131ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 231 2XS131 TransferSwitchfor2PCV130 Closed Closed

232 2HS134A 2PCV134ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2C 233 2XS134 TransferSwitchfor2PCV134 Closed Closed

234 2HS141 2PCV141ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2A 235 2XS141 TransferSwitchfor2PCV141 Closed Closed

236 2HS42 2PCV142ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 237 2XS142 TransferSwitchfor2PCV142 Closed Closed

238 2HS1179A 2PCV1179ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2B 239 2XS1179 TransferSwitchfor2PCV1 179 Closed Closed

BrownsFerryNuclearPlantESEPReport PageA23 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 240 2HS1180A 2PCV1180ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard2C 241 2XS1180 TransferSwitchfor2PCV1 180 Closed Closed

242 2XS1159A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard2B 243 2XS1161A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard2B 244 2LPNL2532 LocalPanel2532:Backup Control Operable Operable FailureofpanelorcomponentscanpreventopeningSRVs ADS-Unit3 245 TBD FLEXNitrogenBottleRackfor MSRVOperation Operable Operable UNIDtobeestablishedinDCN71386 246 3PCV14 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 247 3PSV14 MS/SolenoidValveforPCV14 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3A 248 3PCV15 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 249 3PSV15 MS/SolenoidValveforPCV15 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3C 250 3ACC32 6106 CA/AccumulatorforPSV15 Operable Operable HoldsoperatingnitrogenforSRV

BrownsFerryNuclearPlantESEPReport PageA24 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 251 3PCV118 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 252 3PSV118 MS/SolenoidValveforPCV1 18 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 253 3ACC32 6104 CA/AccumulatorforPsv118 Operable Operable HoldsoperatingnitrogenforSRV 254 3PCV119 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 255 3PSV119 MS/SolenoidValveforPCV1 19 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 256 3ACC32 6105 CA/AccumulatorforPSV119 Operable Operable HoldsoperatingnitrogenforSRV 257 3PCV122 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 258 3PSV122 MS/SolenoidValveforPCV1 22 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 259 3ACC32 6107 CA/AccumulatorforPSV122 Operable Operable HoldsoperatingnitrogenforSRV 260 3PCV123 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 261 3PSV123 MS/SolenoidValveforPCV1 23 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3C 262 3PCV130 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown

BrownsFerryNuclearPlantESEPReport PageA25 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 263 3PSV130 MS/SolenoidValveforPCV1 30 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3A 264 3ACC32 6111 CA/AccumulatorforPSV130 Operable Operable HoldsoperatingnitrogenforSRV 265 3PCV131 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 266 3PSV131 MS/SolenoidValveforPCV1 31 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 267 3ACC32 6108 CA/AccumulatorforPSV131 Operable Operable HoldsoperatingnitrogenforSRV 268 3PCV134 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 269 3PSV134 MS/SolenoidValveforPCV1 34 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3C 270 3ACC32 6109 CA/AccumulatorforPSV134 Operable Operable HoldsoperatingnitrogenforSRV 271 3PCV141 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 272 3PSV141 MS/SolenoidValveforPCV1 41 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3C 273 3ACC32 6110 CA/AccumulatorforPSV141 Operable Operable HoldsoperatingnitrogenforSRV 274 3PCV142 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown

BrownsFerryNuclearPlantESEPReport PageA26 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 275 3PSV142 MS/SolenoidValveforPCV1 42 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 276 3PCV1179 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 277 3PSV1179 MS/SolenoidValveforPCV1 179 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3B 278 3PCV1180 MS/MainSteamSafetyRelief Valve Shut Open Usedforpressurecontrolandcooldown 279 3PSV1180 MS/SolenoidValveforPCV1 180 Deenergized Energized PilotvalveforassociatedSRV Power:From250VDCRMOVBoard3A 280 3HS14 3PCV14ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3A 281 3XS14 TransferSwitchfor3PCV14 Closed Closed

281 3HS15A 3PCV15ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3C 282 3XS15 TransferSwitchfor3PCV15 Closed Closed

283 3HS118 3PCV119ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B 284 3XS118 TransferSwitchfor2PCV118 Closed Closed

285 3HS119A 3PCV119ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B

BrownsFerryNuclearPlantESEPReport PageA27 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 286 3XS119 TransferSwitchfor3PCV119 Closed Closed

287 3HS122A 3PCV122ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B 288 3XS122 TransferSwitchfor3PCV122 Closed Closed

289 3HS123 3PCV123ControlRoomHand Switch Closed Closed OpenSRVforcooldown Power:From250VDCRMOVBoard3C 290 3XS123 TransferSwitchfor3PCV123 Closed Closed

291 3HS130A 3PCV130ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3A 292 3XS130 TransferSwitchfor3PCV130 Closed Closed

293 3HS131A 3PCV131ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B 294 3XS131 TransferSwitchfor3PCV131 Closed Closed

295 3HS134A 3PCV134ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3C 296 3XS134 TransferSwitchfor3PCV134 Closed Closed

297 3HS141 3PCV141ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3C 298 3XS141 TransferSwitchfor3PCV141 Closed Closed

BrownsFerryNuclearPlantESEPReport PageA28 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 299 3HS142 3PCV142ControlRoomHand Switch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B 300 3XS142 TransferSwitchfor3PCV142 Closed Closed

301 3HS1179A 3PCV1179ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3B 302 3XS1179 TransferSwitchfor3PCV1 179 Closed Closed

303 3HS1180A 3PCV1180ControlRoom HandSwitch Auto Open OpenSRVforcooldown Power:From250VDCRMOVBoard3A 304 3XS1180 TransferSwitchfor3PCV1 180 Closed Closed

305 3XS1159A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard3B 306

Numbernotused.DuplicateUNIDremoved.

307 3XS1161A ADSInhibitSwitch Normal Inhibit UsedtoinhibitautomaticinitiationofADS Power:From250VDCRMOVBoard3B 308 3LPNL2532 LocalPanel2532:Backup Control Operable Operable FailureofpanelorcomponentscanpreventopeningSRVs Instrumentation-Unit1 309 1LI358B RPVLevelInstrument Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 310 1LIS358B RPVLevelIndication Switch Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC

BrownsFerryNuclearPlantESEPReport PageA29 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 311 1LT358B RPVLevelTransmitter Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 312 1LS358B RPVLevelSwitch Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 313 1LI355 RPVShutdownFloodupRange Operating Operating

314 1LT355 RPVShutdownFloodupRange Operating Operating

315 1PI374B RPVPressureIndicator Operating Operating GivesindicationofRPVpressure Power:FromDivisionII250VDC 316 1PIS374B RPVPressureIndication/

Switch Operating Operating GivesindicationofRPVpressure Power:FromDivisionII250VDC 317 1PT374B RPVPressureTransmitter Operating Operating GivesindicationofRPVpressure Power:FromDivisionII250VDC 318 1TIS64 52AA DrywellTemperatureIndicator Switch Operating Operating

319 1TI6452AB DrywellTemperatureIndicator Operating Operating

320 1PI06467B DrywellPressureIndicator Operating Operating Givesindicationofdrywellpressure 321 1PT06467 DrywellPressureTransmitter Operating Operating Givesindicationofdrywellpressure 322 1LI064 159A SuppressionPoolLevel Indicator(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower

BrownsFerryNuclearPlantESEPReport PageA30 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 323 1LT064 159A SuppressionPoolLevel Transmitter(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower 324 1TI064161 TorusBulkWaterTemperature (DivisionI)

Operating Operating Givesindicationofbulktoruswatertemperature 325 1TM64 161A TorusTemperatureModuleA Operating Operating Feedstheindicationofbulktoruswatertemperature 326 1TE64161A TorusTemperatureElementA Operating Operating Feedstheindicationofbulktoruswatertemperature 327 1TM64 161B TorusTemperatureModuleB Operating Operating Feedstheindicationofbulktoruswatertemperature 328 1TE64161B TorusTemperatureElementB Operating Operating Feedstheindicationofbulktoruswatertemperature 329 1TM64 161C TorusTemperatureModuleC Operating Operating Feedstheindicationofbulktoruswatertemperature 330 1TE64161C TorusTemperatureElementC Operating Operating Feedstheindicationofbulktoruswatertemperature 331 1TM64 161D TorusTemperatureModuleD Operating Operating Feedstheindicationofbulktoruswatertemperature 332 1TE64161D TorusTemperatureElementD Operating Operating Feedstheindicationofbulktoruswatertemperature 333 1TM64 161E TorusTemperatureModuleE Operating Operating Feedstheindicationofbulktoruswatertemperature 334 1TE64161E TorusTemperatureElementE Operating Operating Feedstheindicationofbulktoruswatertemperature 335 1TM64 161F TorusTemperatureModuleF Operating Operating Feedstheindicationofbulktoruswatertemperature

BrownsFerryNuclearPlantESEPReport PageA31 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 336 1TE64161F TorusTemperatureElementF Operating Operating Feedstheindicationofbulktoruswatertemperature 337 1TM64 161G TorusTemperatureModuleG Operating Operating Feedstheindicationofbulktoruswatertemperature 338 1TE64161G TorusTemperatureElementG Operating Operating Feedstheindicationofbulktoruswatertemperature 339 1TM64 161H TorusTemperatureModuleH Operating Operating Feedstheindicationofbulktoruswatertemperature 340 1TE64161H TorusTemperatureElementH Operating Operating Feedstheindicationofbulktoruswatertemperature 341 1TM64161J TorusTemperatureModuleJ Operating Operating Feedstheindicationofbulktoruswatertemperature 342 1TM64 161K TorusTemperatureModuleK Operating Operating Feedstheindicationofbulktoruswatertemperature 343 1TM64 161L TorusTemperatureModuleL Operating Operating Feedstheindicationofbulktoruswatertemperature 344 1PNLA009 0003A ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 345 1PNLA009 0003B ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 346 1PNLA009 009 I&CBus1Aand1B(Cabinet2 and3ofPanel199)

Operable Operable PowerforI&CBuses1Aand1B 347 1PNLA009 0032 RHR,CS,HPCI(ChannelA),

RCIC,ADSPanel Operable Operable LogicforRHR,corespray,HighPressureCoreInjection (HPCI),RCIC,ADS 348 1PNLA009 0033 RHR,CS,HPCI(ChannelB),

RCIC,ADSLogicPanel Operable Operable LogicforEmergencyCoreCoolingSystem(ECCS)

BrownsFerryNuclearPlantESEPReport PageA32 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 349 1PNLA009 0081 DivisionIECCSATUCabinet Operable Operable AnalogTripUnit(ATU)forRPVandcontainmentinstrument signals 350 1PNLA009 0082 DivisionIIECCSATUCabinet Operable Operable ATUforRPVandcontainmentinstrumentsignals 351 1PNLA009 0087 DivisionITorusTemperature Monitoring Operable Operable Providesindicationoftoruswatertemperature 352 1LPNL925 005A LocalPanel255A Operable Operable Localinstrumentationrack/panel 353 1LPNL925 005B LocalPanel255B Operable Operable Localinstrumentationrack/panel 354 1LPNL925 0058 RCICInstrumentationPanel Operable Operable RCIClocalinstrumentationpanel 355 1LPNL925 006B InstrumentationRack256B Operable Operable Localinstrumentationrack/panel(drywellpressure) 356 1PNLA925 0031 LocalPanel2531 Operable Operable RCIClocalisolationinstrumentation 357 1LPNL925 672 RCICLocalControls Operable Operable Canfailandblockcontrolroomoperation Instrumentation-Unit2 358 2LI358B RPVLevelInstrument Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 359 2LIS358B RPVLevelIndication/Switch Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 360 2LT358B RPVLevelTransmitter Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC

BrownsFerryNuclearPlantESEPReport PageA33 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 361 2LS358B RPVLevelSwitch Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 362 2LI355 RPVShutdownFloodupRange Operating Operating

363 2LT355 RPVShutdownFloodupRange Operating Operating

364 2PI374B RPVPressureIndicator Operating Operating Power:FromDivisionII250VDC 365 2PIS374B RPVPressureIndication/

Switch Operating Operating GivesindicationofRPVpressure 366 2PT374B RPVPressureTransmitter Operating Operating GivesindicationofRPVpressure 367 2TIS64 52AA DrywellTemperatureIndicator Switch Operating Operating

368 2TI6452AB DrywellTemperatureIndicator Operating Operating

369 2PI06467B DrywellPressureIndicator Operating Operating Givesindicationofdrywellpressure 370 2PT06467B DrywellPressureTransmitter Operating Operating Givesindicationofdrywellpressure 371 2LI064 159A SuppressionPoolLevel Indicator(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower 372 2LT064 159A SuppressionPoolLevel Transmitter(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower 373 2TI064161 TorusBulkWaterTemperature (DivisionI)

Operating Operating Givesindicationofbulktoruswatertemperature

BrownsFerryNuclearPlantESEPReport PageA34 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 374 2TM64 161A TorusTemperatureModuleA Operating Operating Feedstheindicationofbulktoruswatertemperature 375 2TE64161A TorusTemperatureElementA Operating Operating Feedstheindicationofbulktoruswatertemperature 376 2TM64 161B TorusTemperatureModuleB Operating Operating Feedstheindicationofbulktoruswatertemperature 377 2TE64161B TorusTemperatureElementB Operating Operating Feedstheindicationofbulktoruswatertemperature 378 2TM64 161C TorusTemperatureModuleC Operating Operating Feedstheindicationofbulktoruswatertemperature 379 2TE64161C TorusTemperatureElementC Operating Operating Feedstheindicationofbulktoruswatertemperature 380 2TM64 161D TorusTemperatureModuleD Operating Operating Feedstheindicationofbulktoruswatertemperature 381 2TE64161D TorusTemperatureElementD Operating Operating Feedstheindicationofbulktoruswatertemperature 382 2TM64 161E TorusTemperatureModuleE Operating Operating Feedstheindicationofbulktoruswatertemperature 383 2TE64161E TorusTemperatureElementE Operating Operating Feedstheindicationofbulktoruswatertemperature 384 2TM64 161F TorusTemperatureModuleF Operating Operating Feedstheindicationofbulktoruswatertemperature 385 2TE64161F TorusTemperatureElementF Operating Operating Feedstheindicationofbulktoruswatertemperature 386 2TM64 161G TorusTemperatureModuleG Operating Operating Feedstheindicationofbulktoruswatertemperature

BrownsFerryNuclearPlantESEPReport PageA35 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 387 2TE64161G TorusTemperatureElementG Operating Operating Feedstheindicationofbulktoruswatertemperature 388 2TM64 161H TorusTemperatureModuleH Operating Operating Feedstheindicationofbulktoruswatertemperature 389 2TE64161H TorusTemperatureElementH Operating Operating Feedstheindicationofbulktoruswatertemperature 390 2TM64161J TorusTemperatureModuleJ Operating Operating Feedstheindicationofbulktoruswatertemperature 391 2TM64 161K TorusTemperatureModuleK Operating Operating Feedstheindicationofbulktoruswatertemperature 392 2TM64 161L TorusTemperatureModuleL Operating Operating Feedstheindicationofbulktoruswatertemperature 393 2PNLA009 0003A ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 394 2PNLA009 0003B ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 395 2PNLA009 009 I&CBus1Aand1B(Cabinet2 and3ofpanel199)

Operable Operable PowerforI&CBuses1Aand1B 396 2PNLA009 0032 RHR,CS,HPCI(ChannelA),

RCIC,ADSPanel Operable Operable LogicforECCSsystems 397 2PNLA009 0033 RHR,CS,HPCI(ChannelB),

RCIC,ADSLogicPanel Operable Operable LogicforECCSsystems 398 2PNLA009 0081 DivisionIECCSATUCabinet Operable Operable ATUforRPVandcontainmentinstrumentsignals 399 2PNLA009 0082 DivisionIIECCSATUCabinet Operable Operable ATUforRPVandcontainmentinstrumentsignals

BrownsFerryNuclearPlantESEPReport PageA36 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 400 2PNLA009 0087 DivisionITorusTemperature Monitoring Operable Operable Providesindicationoftoruswatertemperature 401 2LPNL925 005A LocalPanel255A Operable Operable Localinstrumentationrack/panel 402 2LPNL925 005B LocalPanel255B Operable Operable Localinstrumentationrack/panel 403 2LPNL925 0058 RCICInstrumentationPanel Operable Operable RCIClocalinstrumentationpanel 404 2LPNL925 006A InstrumentationRack256A Operable Operable Localinstrumentationrack/panel(RPVlevel) 406 2PNLA925 0031 LocalPanel2531 Operable Operable RCIClocalisolationinstrumentation 406 2LPNL925 672 RCICLocalControls Operable Operable Canfailandblockcontrolroomoperation Instrumentation-Unit3 407 3LI358B RPVLevelInstrument Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 408 3LIS358B RPVLevelIndication Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 409 3LT358B RPVLevelTransmitter Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 410 3LS358B RPVLevelSwitch Operating Operating GivesindicationofRPVlevel Power:FromDivisionII250VDC 411 3LI355 RPVShutdownFloodupRange Operating Operating

BrownsFerryNuclearPlantESEPReport PageA37 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 412 3LT355 RPVShutdownFloodupRange Operating Operating

413 3PI374B RPVPressureIndicator Operating Operating Power:FromDivisionII250VDC 414 3PIS374B RPVPressureIndication/

Switch Operating Operating GivesindicationofRPVpressure 415 3PT374B RPVPressureTransmitter Operating Operating GivesindicationofRPVpressure 416 3TIS64 52AA DrywellTemperatureIndicator Switch Operating Operating

417 3TI6452AB DrywellTemperatureIndicator Operating Operating

418 3PI06467B DrywellPressureIndicator Operating Operating Givesindicationofdrywellpressure 419 3PT06467 DrywellPressureTransmitter Operating Operating Givesindicationofdrywellpressure 420 3LI064 159A SuppressionPoolLevel Indicator(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower 421 3LT064 159A SuppressionPoolLevel Transmitter(DivisionII)

Operating Operating Givesindicationofsuppressionpoollevel Power:FromDivisionII250VDCPower 422 3TI064161 TorusBulkWaterTemperature (DivisionI)

Operating Operating Givesindicationofbulktoruswatertemperature 423 3TM64 161A TorustemperaturemoduleA Operating Operating Feedstheindicationofbulktoruswatertemperature 424 3TE64161A TorusTemperatureElementA Operating Operating Feedstheindicationofbulktoruswatertemperature

BrownsFerryNuclearPlantESEPReport PageA38 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 425 3TM64 161B TorusTemperatureModuleB Operating Operating Feedstheindicationofbulktoruswatertemperature 426 3TE64161B TorusTemperatureElementB Operating Operating Feedstheindicationofbulktoruswatertemperature 427 3TM64 161C TorusTemperatureModuleC Operating Operating Feedstheindicationofbulktoruswatertemperature 428 3TE64161C TorusTemperatureElementC Operating Operating Feedstheindicationofbulktoruswatertemperature 429 3TM64 161D TorusTemperatureModuleD Operating Operating Feedstheindicationofbulktoruswatertemperature 430 3TE64161D TorusTemperatureElementD Operating Operating Feedstheindicationofbulktoruswatertemperature 431 3TM64 161E TorusTemperatureModuleE Operating Operating Feedstheindicationofbulktoruswatertemperature 432 3TE64161E TorusTemperatureElementE Operating Operating Feedstheindicationofbulktoruswatertemperature 433 3TM64 161F TorusTemperatureModuleF Operating Operating Feedstheindicationofbulktoruswatertemperature 434 3TE64161F TorusTemperatureElementF Operating Operating Feedstheindicationofbulktoruswatertemperature 435 3TM64 161G TorusTemperatureModuleG Operating Operating Feedstheindicationofbulktoruswatertemperature 436 3TE64161G TorusTemperatureElementG Operating Operating Feedstheindicationofbulktoruswatertemperature 437 3TM64 161H TorusTemperatureModuleH Operating Operating Feedstheindicationofbulktoruswatertemperature

BrownsFerryNuclearPlantESEPReport PageA39 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 438 3TE64161H TorusTemperatureElementH Operating Operating Feedstheindicationofbulktoruswatertemperature 439 3TM64161J TorusTemperatureModuleJ Operating Operating Feedstheindicationofbulktoruswatertemperature 440 3TM64 161K TorusTemperatureModuleK Operating Operating Feedstheindicationofbulktoruswatertemperature 441 3TM64 161L TorusTemperatureModuleL Operating Operating Feedstheindicationofbulktoruswatertemperature 442 3PNLA009 0003A ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 443 3PNLA009 0003B ReactorShutdown&

ContainmentCoolingPanel Operable Operable Indicationsandcontrols 444 3PNLA009 009 I&CBus1Aand1B(Cabinet2 and3ofPanel199)

Operable Operable PowerforI&CBuses1Aand1B 445 3PNLA009 0032 RHR,CS,HPCI(ChannelA),

RCIC,ADSPanel Operable Operable LogicforECCSsystems 446 3PNLA009 0033 RHR,CS,HPCI(ChannelB),

RCIC,ADSLogicPanel Operable Operable LogicforECCSsystems 447 3PNLA009 0081 DivisionIECCSATUCabinet Operable Operable ATUforRPVandcontainmentinstrumentsignals 448 3PNLA009 0082 DivisionIIECCSATUCabinet Operable Operable ATUforRPVandcontainmentinstrumentsignals 449 3PNLA009 0087 DivisionITorusTemp Monitoring Operable Operable Providesindicationoftoruswatertemperature 450 3LPNL925 005A LocalPanel255A Operable Operable Localinstrumentationrack/panel

BrownsFerryNuclearPlantESEPReport PageA40 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 451 3LPNL925 005B LocalPanel255B Operable Operable Localinstrumentationrack/panel 452 3LPNL925 0058 RCICInstrumentationPanel Operable Operable RCIClocalinstrumentationpanel 453 3LPNL925 006B InstrumentationRack256B Operable Operable Localinstrumentationrack/panel(drywellpressure) 454 3PNLA925 0031 LocalPanel2531 Operable Operable RCIClocalisolationinstrumentation 455 3LPNL925 672 RCICLocalControls Operable Operable Canfailandblockcontrolroomoperation ElectricPower-AllThreeUnits 456 1BDBB281 0001A 250VRMOVBoard1A Energized Energized Power:ForRCICandADS 457 1BDBB281 0001B 250VRMOVBoard1B Energized Energized Power:ForRCICandADS 458 1BDBB281 0001C 250VRMOVBoard1C Energized Energized Power:ForRCICandADS 459 2BDBB281 0002A 250VRMOVBoard2A Energized Energized Power:ForRCICandADS 460 2BDBB281 0002B 250VRMOVBoard2B Energized Energized Power:ForRCICandADS 461 2BDBB281 0002C 250VRMOVBoard2C Energized Energized Power:ForRCICandADS 462 3BDBB281 0003A 250VRMOVBoard3A Energized Energized Power:ForRCICandADS

BrownsFerryNuclearPlantESEPReport PageA41 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 463 3BDBB281 0003B 250VRMOVBoard3B Energized Energized Power:ForRCICandADS 464 3BDBB281 0003C 250VRMOVBoard3C Energized Energized Power:ForRCICandADS 465 0BDDD280 0001 250VBatteryBoard1 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 466 0BATA248 0001 250VMainBattery1 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 467 0CHGA248 0001 UnitBatteryCharger1 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 468 0BDDD280 0002 250VBatteryBoard2 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 469 0BATA248 0002 250VMainBattery2 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 470 0CHGA248 0002A UnitBatteryCharger2A Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 471 0BDDD280 0003 250VBatteryBoard3 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 472 0BATA248 0003 250VMainBattery3 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 473 0CHGA248 0003 UnitBatteryCharger3 Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 474 0PNLA248 0000A 250VDistributionPanelSBA Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 475 0BATA248 0000A 250VBatterySBA Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower

BrownsFerryNuclearPlantESEPReport PageA42 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 476 0CHGA248 0000A 250VBatteryChargerSBA Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 477 0PNLA248B 250VDistributionPanelSBB Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 478 0BATA248 0000B 250VBatterySBB Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 479 0CHGA248 0000B 250VBatteryChargerSBB Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 480 0BATA248 0000C 250VBatterySBC Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 481 0PNLA248 0000C 250VDistributionPanelSBC Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 482 0CHGA248 0000C 250VBatteryChargerSBC Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 483 0BATA248 0000D 250VBatterySBD Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 484 0PNLA248 0000D 250VDistributionPanelSBD Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 485 0CHGA248 0000D 250VBatteryChargerSBD Energized Energized 250VDCpowerfor250VDCbusesandACcontrolpower 486 1BDBB231 0001A 480VShutdownBoard1A Energized Energized ActsastheconnectionpointfortheUnit1480VFLEXdiesel generatorandprovides480VACforFLEXloads 487 1BDBB231 0001B 480VShutdownBoard1B Energized Energized Provides480VACforFLEXloads 488 2BDBB231 0002A 480VShutdownBoard2A Energized Energized ActsastheconnectionpointfortheUnit2480VFLEXdiesel generatorandprovides480VACforFLEXloads

BrownsFerryNuclearPlantESEPReport PageA43 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 489 2BDBB231 0002B 480VShutdownBoard2B Energized Energized Provides480VACforFLEXloads 490 3BDBB231 0003A 480VShutdownBoard3A Energized Energized Provides480VACforFLEXloads 491 3BDBB231 0003B 480VShutdownBoard3B Energized Energized Provides480VACforFLEXloads 492 1BDBB268 0001A 480VRMOVBoard1A Energized Energized Provides480VACforFLEXloads 493 1BDBB268 0001B 480VRMOVBoard1B Energized Energized Provides480VACforFLEXloads 494 2BDBB268 0002A 480VRMOVBoard2A Energized Energized Provides480VACforFLEXloads 495 2BDBB268 0002B 480VRMOVBoard2B Energized Energized Provides480VACforFLEXloads 496 3BDBB268 0003A 480VRMOVBoard3A Energized Energized Provides480VACforFLEXloads 497 3BDBB268 0003B 480VRMOVBoard3B Energized Energized Provides480VACforFLEXloads 498 0BDAA211 0000A 4kVShutdownBoardA Operable Operable

499 0BDAA211 0000B 4kVShutdownBoardB Operable Operable

500 0BDAA211 0000C 4kVShutdownBoardC Operable Operable

501 0BDAA211 0000D 4kVShutdownBoardD Operable Operable

BrownsFerryNuclearPlantESEPReport PageA44 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 502 0BDAA211 0000EA 4kVShutdownBoard3EA Operable Operable

503 0BDAA211 0000EC 4kVShutdownBoard3EC Operable Operable

504 1XFA231 TS1A 4KV/480TransformerTS1A Operable Operable

505 1XFA231 TS1B 4KV/480TransformerTS1A Operable Operable

506 2XFA231 TS2A 4KV/480TransformerTS1A Operable Operable

507 2XFA231 TS2B 4KV/480TransformerTS1A Operable Operable

508 3XFA231 TS2A 4KV/480TransformerTS1A Operable Operable

509 3XFA231 TS2B 4KV/480TransformerTS1A Operable Operable

510 3XFA231 TS1E 4KV/480TransformerTS1E Operable Operable

511 TBD FLEX480VDieselGenerator BatteryChargingDistribution Panel Operable Operable UNIDtobeestablishedinDCN71470 RHR-Unit1 512 1FCV7471 RHR/LoopIITorus ContainmentCooling/Spray Valve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard1B

BrownsFerryNuclearPlantESEPReport PageA45 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 513 1FCV7472 RHR/LoopIISuppressionPool SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard1B 514 1FCV7473 RHR/LoopIIRecirculation PumpTestValve Shut Open Power:From480VRMOVBoard1B 515 1FCV7474 RHR/LoopIIOutboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard1B 516 1FCV7475 RHR/LoopIIInboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard1B 517 1FCV7467 Unit1RHROutboardInjection ValvetoRecirculationLoopA forShutdownCooling Shut Open OpentoprovideshutdowncoolinginPhases2and3 Power:From480VRMOVBoard1B 519 1FCV74101 CrosstietoUnit2RHRHeat Exchanger Shut Open OpentoprovideshutdowncoolinginPhases2and3 Power:From480VRMOVBoard1B 519 1HEX900B BRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion 520 1HEX900D BRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion RHR-Unit2 521 2FCV7471 RHR/LoopIITorus ContainmentCooling/Spray Valve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard2B 522 2FCV7472 RHR/LoopIISuppressionPool SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard2B 523 2FCV7473 RHR/LoopIIRecirculation PumpTestValve Shut Open Power:From480VRMOVBoard2B

BrownsFerryNuclearPlantESEPReport PageA46 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 524 2FCV7474 RHR/LoopIIOutboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard2B 525 2FCV7475 RHR/LoopIIInboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard2B 526 2FCV7467 Unit2RHROutboardInjection ValveToRecirculationLoopA ForShutdownCooling Shut Open Opentoprovideshutdowncoolinginphases2and3 Power:From480VRMOVBoard2E 527 2FCV74100 CrosstietoUnit1RHRHeat Exchanger Shut Open OpenedtoprovideflowpathforRHRservicewatertoRHR injection.

Power:From480VRMOVBoard1B 528 2FCV74101 CrosstietoUnit3RHRHeat Exchanger Shut Open OpenedtoprovideflowpathforRHRservicewatertoRHR injection.

Power:From480VRMOVBoard3B 529 2HEX900A ARHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion 530 2HEX900C CRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion 531 2HEX900B BRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion 532 2HEX900D DRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion RHR-Unit3 533 2FCV7457 RHR/LoopIITorus ContainmentCooling/Spray Valve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard3A

BrownsFerryNuclearPlantESEPReport PageA47 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State 534 3FCV7458 RHR/LoopIISuppressionPool SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard3A 535 3FCV7459 RHR/LoopIRecirculationPump TestValve Shut Open Power:From480VRMOVBoard3A 536 3FCV7460 RHR/LoopIIOutboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard3A 537 3FCV7461 RHR/LoopIIInboardDrywell SprayValve Shut Open Opentoprovidecontainmentheatremoval Power:From480VRMOVBoard3A 538 3FCV7453 Unit3RHROutboardInjection ValvetoRecirculationLoopA forShutdownCooling Closed Open OpentoprovideshutdowncoolinginPhases2and3 Power:From480VRMOVBoard3D 539 3FCV74100 CrosstietoUnit3RHRHeat Exchanger Closed Open OpentoprovideshutdowncoolinginPhases2and3 Power:From480VRMOVBoard3B 540 3HEX900A ARHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion 541 3HEX900C CRHRHeatExchanger Operable Operable Failurecouldresultinflowdiversion RHRServiceWater-Unit1 542 1FCV2357 RHR/RHRServiceWaterCross ConnectValve Closed Open 480RMOVBoard1B RHRServiceWater-Unit2 543 2FCV2357 RHR/RHRServiceWaterCross ConnectValve Closed Open 480RMOVBoard3B

BrownsFerryNuclearPlantESEPReport PageA48 TableA1:ExpeditedSeismicEquipmentList(ESEL)forBrownsFerryNuclearPlant(Continued)

ESEL Item Number Equipment OperatingState Notes/Comments ID Description Normal State Desired State ContainmentVent-Unit1 544 1FCV64221 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly 545 1FCV64222 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly ContainmentVent-Unit2 546 2FCV64221 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly 547 2FCV64222 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly ContainmentVent-Unit3 548 3FCV64221 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly 549 3FCV64222 ContainmentHardenedVent Valve Closed Open Tobeoperatedmanuallywalkbyonly

BrownsFerryNuclearPlantESEPReport PageB1 ATTACHMENTB-ESEPHCLPFVALUESANDFAILUREMODESTABULATIONFOR BROWNSFERRYNUCLEARPLANT

BrownsFerryNuclearPlantESEPReport PageB2 TableB1:ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant Equipment ID EquipmentDescription Equipment Class Building Floor Elevation FailureMode HCLPF Capacity (g) 1FCV7119 RCICPumpCondensate StorageTankSuction Valve 8A U1RB 528 Functional 0.69g 2FCV7119 U2RB 3FCV7119 U3RB 1FCV7117 RCICSuctionfromTorus 8A U1RB 528 Functional 0.69g 2FCV7117 U2RB 3FCV7117 U3RB 1FCV7118 RCICSuctionfromTorus 8A U1RB 528 Functional 0.69g 2FCV7118 U2RB 3FCV7118 U3RB 1PMP7119 RCICPump 5

U1RB 519 Functional 0.85g 2PMP7119 U2RB 3PMP7119 U3RB 1FCV7139 RCICDischargeIsolation Valve 8A U1RB 541 Functional 0.69g 2FCV7139 U2RB 3FCV7139 U3RB 1PCV7122 RCICLubeOilCooling WaterPressureControl Valve 7

U1RB 519 Functional 0.67g 2PCV7122 U2RB 3PCV7122 U3RB

BrownsFerryNuclearPlantESEPReport PageB3 TableB1:ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

Equipment ID EquipmentDescription Equipment Class Building Floor Elevation FailureMode HCLPF Capacity (g) 1FCV7125 RCICTurbineLubeOil InletValve 8A U1RB 528 Functional 0.69g 2FCV7125 U2RB 3FCV7125 U3RB 1TNK7127 RCICBarometric CondenserandVacuum Tank 21 U1RB 519 Functional 1.38g 2TNK7127 U2RB 3TNK7127 U3RB 1CLR7125 RCICLubeOilCooler 21 U1RB 519 Anchorage 1.35g 2CLR7125 U2RB 3CLR7125 U3RB 1PMP7129 RCICVacuumTank CondenserPump 6

U1RB 519 Functional 1.38g 2PMP7129 U2RB 3PMP7129 U3RB 1PMP7131 RCICVacuumPump 5

U1RB 519 Functional 1.38g 2PMP7131 U2RB 3PMP7131 U3RB 1FCV718 RCICTurbineSteamInlet Valve 8A U1RB 528 Functional 0.69g 2FCV718 U2RB 3FCV718 U3RB 1FCV719 RCICTurbineSteam ThrottleValve 8A U1RB 528 Functional 0.69g 2FCV719 U2RB

BrownsFerryNuclearPlantESEPReport PageB4 TableB1:ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

Equipment ID EquipmentDescription Equipment Class Building Floor Elevation FailureMode HCLPF Capacity (g) 3FCV719 U3RB 1FCV7110 RCICTurbineGovernor Valve 7

U1RB 519 Functional 0.85g 2FCV7110 U2RB 3FCV7110 U3RB 1TRB719 RCICTurbine 5

U1RB 519 Functional 0.85g 2TRB719 U2RB 2TRB719 U3RB 1FT7136 RCICPumpFlow TransmitterforTurbine Control 18 U1RB 519 Anchorage 0.74g 2FT7136 U2RB 3FT7136 U3RB 1FIC7136A RCICFlowIndicating Controller 20 U1RB 617 Functional 0.62g 2FIC7136A U2RB 3FIC7136A U3RB 1PX7136A PowerSupplyforRCIC FlowController 20 U1RB 621 Functional 0.62g 2PX7136A U2RB 3PX7136A U3RB 1LPNL925 672 RCICLocalControls 20 U1RB 519 Anchorage 0.74g 2LPNL925 672 U2RB 3LPNL925 672 U3RB 1LPNL25 658 TransferSwitchesfor System1PCVs 20 U1RB 593 Functional 0.62g

BrownsFerryNuclearPlantESEPReport PageB5 TableB1:ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

Equipment ID EquipmentDescription Equipment Class Building Floor Elevation FailureMode HCLPF Capacity (g) 2LPNL25 658 U2RB 3LPNL25 658 U3RB 2FCV74100 CrosstietoU1RHRHeat Exchanger 8A U1RB 565 Functional 0.71g 2FCV74101 CrosstietoU3RHRHeat Exchanger 8A U2RB 565 Functional 0.71g 3FCV74101 CrosstietoU3RHRHeat Exchanger 8A U2RB 565 Functional 0.71g 1LPNL925 0058 RCICInstrumentation Panel 20 U1RB 519 Anchorage 0.74g 2LPNL925 0058 U2RB 3LPNL925 0058 U3RB