ML081370143

Feb-Mar 05000259/2008301 Exam Final Written Exam Outlines

ML081370143
Person / Time
Site:	Browns Ferry
Issue date:	04/08/2008
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-259/08-301 50-259/08-301
Download: ML081370143 (18)

See also: IR 05000259/2008301

Text

Final Submittal(BluePaper)

FINAL OUTLINES'

ES-401 Written Examination

Outline n NA-t..Form ES-401-1 Facility: 0610 NRC Exam Outline Date of Exam: 02/25/2008

RO KJ A Category Points SRO-Only Points Tier GroupKKKKKKAAAAG Total12 3 4561 2 3 4*A2 G*Total l.I333 3 4 4 20 437 Emergency 2 1 I 1 1 217 I 2 3&Plant Tier Evolutions

Totals444 4 6 5 275510 1 2 3222 2233322632 5 2.Plant211 1 I121111112021 3 Systems Tier Totals 3 4333 4 3444 3 3853 8 3.Generic Knowledge&Abilities 1 2 3 4123 4 10 7 Categories

3 223 I 2 2 2 Note: l.Ensurethatatleasttwotopicsfromevery

applicable

KIAcategoryaresampledwithineachtier

oftheROand SRO-onlyoutlines(i.e.,exceptforonecategoryinTier3

oftheSRO-onlyoutline,the"Tier Totals"ineach KIAcategoryshallnotbelessthantwo).

2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthatspecifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby

+/-lfromthatspecifiedinthetablebasedonNRCrevisions

.ThefinalROexammusttotal75pointsandtheSRO-onlyexammusttotal25points

.3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;systemsor

evolutionsthatdonotapplyatthefacilityshouldbedeletedand

justified;

operationallyimportant,site-specificsystemsthatarenotincludedontheoutlineshouldbeadded.RefertosectionD.l.b ofES-401 ,forguidance

regarding elimination

of inappropriate

KIA statements.

4.Selecttopicsfromasmanysystemsandevolutionsaspossible;sampleeverysystemor

evolutioninthegroupbeforeselectingasecondtopicforanysystemor

evolution.5.Absentaplantspecificpriority,onlythose

KAshavinganimportancerating(IR)

of2.5orhighershallbe

selected.UsetheROandSROratingsfortheROandSRO-onlyportions,respectively.

6.SelectSROtopicsforTiers1and2fromtheshadedsystemsand

KIA categories.

7.*Thegeneric(G)

KlAsinTiers1and2shallbeselectedfromSection2

of the KIACatalog,butthetopicsmustberelevanttotheapplicableevolutionorsystem.RefertoSectionD.l.b ofES-401forthe applicable

KIA's 8.Onthefollowingpages,enterthe

KIAnumbers,a brief description

ofeachtopic,the

topics'importanceratings(IR)fortheapplicablelicenselevel,andthepointtotals

(#)foreachsystemandcategory

.Enterthegroupandtiertotalsforeachcategoryinthetableabove.

IffuelhandlingequipmentissampledinotherthanCategoryA2orG*ontheSRO-onlyexam,enteritontheleftside

ofColumnA2forTier2,Group2(Note

1. 1doesnotapply)

.UseduplicatepagesforROandSRO-onlyexams.

9.ForTier3,selecttopicsfromSection2

of the KIACatalog,andenterthe

KIAnumbers,descriptions,IRs,andpointtotals

(#)onFormES-401-3

.LimitSROselectionsto

KlAsthatarelinkedtoIOCFR55.43

ES-401 20610NRCExamOutline

Written Examination

Outline EmergencyandAbnormalPlantEvolutions-

Tier 1 Group 1FormES-401-1EAPE#I Name Safety FunctionK1K2K3A1 I A2 I G KIA Topic(s)Imp.I Q#AA2.01-Abilitytodetermineand/orinterpret295006SCRAM

I I XthefollowingastheyapplytoSCRAM

4.6 76Reactorpower

AA2.07-Abilitytodetermineand/orinterpret29502ILoss

ofShutdownCooling

I 4 XthefollowingastheyapplytoLOSSOF

3.1 77SHUTDOWNCOOLING

Reactorrecirculationflow

2.I.28-Conduct ofOperationsKnowledge

of295024HighDrywelIPressureI5 Xthepurposeandfunction

ofmajorsystem3.378componentsandcontrols.EA2.01-Abilitytodetermineand/orinterpret295026SuppressionPoolHighWater

XthefollowingastheyapplytoSUPPRESSION

4.2 79 Temp.1 5POOLHIGHWATER

TEMPERATURE

SuppressionpoolwatertemperatureEA2.05-Abilitytodetermineand/orinterpret295037SCRAMConditionPresentthefollowingastheyapplytoSCRAMandPowerAboveAPRMDownscale

XCONDITIONPRESENTANDREACTOR4.380orUnknown I IPOWERABOVEAPRMDOWNSCALEOR

UNKNOWN:Controlrodposition

2.2.22-EquipmentControlKnowledge

of295038HighOff-siteReleaseRate

1 9 Xlimitingconditionsforoperationsandsafety4.181

limits.2.2.24-EquipmentControlAbilitytoanalyze600000PlantFireOn-site I 8 Xtheaffect ofmaintenanceactivitiesonLCO3

.8 82 status.29500IPartialorCompleteLoss

of 2.I.14-Conduct

ofOperationsKnowledge

of Xsystemstatuscriteriawhichrequirethe2.539ForcedCoreFlowCirculation

I I&4 notification

ofplantpersonnel.

AIG.OI-Knowledge

ofthereasonsforthe295001PartialorCompleteLoss

offollowingresponsesastheyapplytoPARTIAL

XORCOMPLETELOSSOFFORCEDCORE3.4

40ForcedCoreFlowCirculation

I I&4 FLOW CIRCULATION:Reactorwaterlevel

response AA2.01-Abilitytodetermineand/orinterpret295003PartialorCompleteLoss

of XthefollowingastheyapplytoPARTIALOR3.441 AC/6COMPLETELOSSOF

<<c.POWER: Cause ofpartialorcompleteloss

of A.C.power AKl.03-Knowledge

oftheoperational295004PartialorTotalLoss

of DC implications

ofthefollowingconceptsasthey

Pwr/6 XapplytoPARTIALORCOMPLETELOSSOF2.942

D.C.POWER:Electricalbusdivisional

separation

AA 1.04-Abilityto

operate and/or monitor295005MainTurbineGeneratorTrip

I X the following as they applytoMAIN2.743 3 TURBINE GENERATOR TRIP: Main aenerator controlsAK3.05-Knowledge of the reasons for the295006SCRAM

II X following responses as they apply to3.844 SCRAM: Direct turbine generator trip: Plant-Specific

AA2.04-Ability to determine and/or295016ControlRoom

Abandonment!

X interpret the following as they apply to3.945 7 CONTROL ROOM ABANDONMENT:

Suppression

pool temperature

AK2.01-Knowledge of the interrelations295018PartialorTotalLoss

ofCCW I X betweenPARTIALOR COMPLETE LOSS3.346 8 OF COMPONENT COOLING WATER and the following:

System loads295019PartialorTotalLoss

of inst.XAA2.02-Abilityto

determine and/or3.647 Air/8 interpret the following as they apply to

ES-401 20610NRCExamOutline

Written Examination

Outline Emergency and Abnormal Plant Evolutions

-Tier1Group1FormES-401-1EAPE#/NameSafetyFunctionK1K2K3

I A1 I A2 I GKIATopic(s)

Imp.I Q#PARTIALORCOMPLETELOSSOFINSTRUMENTAIR

Statusofsafety-relatedinstrumenta

irsystemloads(see

AK2.1-AK2.19)2.4.50-EmergencyProcedures/Plan

295021 Loss of ShutdownCooling/4 XAbilitytoverifysystemalarmsetpointsand3.348operatecontrolsidentifiedinthealarmresponsemanual.

AK1.02-Knowledgeoftheoperational

295023 RefuelingAceCoolingMode/

Ximplicationsofthefollowingconceptsas

3.2 49 8theyapplytoREFUELINGACCIDENTS

Shutdownmargin

2.1.33-ConductofOperationsAbilityto

295024 H igh Drywell Pres sure/5 Xrecognizeindicationsforsystemoperating

3.4 50parameterswhichareentry-levelconditionsfortechnicalspec

ifications

.EK2.08-Knowledgeoftheinterrelations

295025 High Reactor PressureI3 XbetweenHIGHREACTORPRESSURE3.751andthefollowing:Reactor/turbinepressureregulatingsystem:Plant-Spec

ific EA2.01-Abilitytodetermineand/or

295026 SuppressionPoolH igh Waterinterpretthefollowingastheyapplyto

XSUPPRESSIONPOOLHIGHWATER

4.1 52 Temp.15 TEMPERATURE

Suppressionpoolwater

temperatureEK3.04-Knowledgeofthereasonsforthe

295028H igh Drywell TemperatureI5 XfollowingresponsesastheyapplytoHIGH

3.6 53DRYWELLTEMPERATURE

Increased drywell coolingEA1.06-Abilitytooperateand/ormonitor

295030 Low Suppression

Pool WaterthefollowingastheyapplytoLOW

XSUPPRESSIONPOOLWATERLEVEL

3.454 Level/5Condensatestorageandtransfer(make-uptothesuppressionpool)

Plant-Specific 2.4.6-EmergencyProcedures/Plan

29503 I Reactor Low Water Level/2 XKnowledgesymptombasedEOP

3.1 55mitigationstrategies.

EK2.11-KnOWledgeoftheinterrelations

295037 SCRAM Condition PresentbetweenSCRAMCONDITIONPRESENT

and PowerAboveAPRM Downscale XANDREACTORPOWERABOVEAPRM

3.8 56 or Unknown I IDOWNSCALEORUNKNOWNandthe

following: RMCS: Plant-SpecificEK1.01-Knowledgeoftheoperationalimplicationsofthefollow

ingconceptsas

295038 H igh Off-site Release Rate 19 XtheyapplytoHIGHOFF-SITERELEASE2

.5 57 RATE:Biologicaleffectsofradioisotope

ingestionAA1.08-Abilitytooperateand/ormonitor

600000 Plant Fire On-site 18 XthefollowingastheyapplytoPLANTFIRE

2.6 58ONSITE: F irefightingequipmentusedoneachclassoffire

KiA Category Totals:33338 7 Group Po int Total: I 20/7

ES-401 30610NRC Exam Outline Written Examination

Outline Emergency and Abnormal Plant Evolutions-Tier1 Group 2 Form ES-401-1 II EAPE#/NameSafetyFunctionK1K2K3A1A2GKIATopic(s)

Imp.I Q#2.4.6-Emergency Procedures

/Plan295002Loss

ofMainCondenserVac

/3 X KnowledgesymptombasedEOPmitigation4.0

83 strategies.

2.4.31-Emergency Procedures

/Plan295009LowReactorWater

Level/2 X Knowledge of annunciatorsalarmsand 3.4 84 indications,anduseofthe

response instructions

.EA2.02-Abilitytodetermineand

/orinterpret500000HighCTMTHydrogenCone

./the followingastheyapplytoHIGH

X PRIMARY CONTAINMENT

HYDROGEN3.585 5 CONCENTRATIONS:Oxygenmonitoringsystemavailability

AK2.01-Knowledgeofthe interrelations295009LowReactorWater

Level/2 XbetweenLOW

REACTORWATERLEVEL

3.9 59andthe following:Reactorwaterlevelindication2.2.22-EquipmentControlKnowledgeof295012HighDrywellTemperature

/5 Xlimitingconditionsforoperationsandsafety

3.4 60 limits.AKI.02-Knowledgeoftheoperational295015IncompleteSCRAM/1

X implicationsofthefollowingconceptsasthey

3.9 61 appl y to INCOMPLETESCRAM:(CFR41.8to41.10)CooldowneffectsonreactorpowerAK3.08-Knowledgeofthereasonsforthe295020InadvertentCont.Isolation/5

&followingresponsesastheyapplyto

7 X INADVERTENT

CONTAINMENT3.362 ISOLATION:Suppressionchamberpressure

response EAI.OI-Abilitytooperateand/ormonitorthe295032HighSecondaryContainment

X followingastheyapplytoHIGH

SECONDARY 3.6 63AreaTemperature/5

CONTAINMENT

AREA TEMPERATURE

Area temperaturemonitoringsystem

EA2.01-Abilitytodetermineand/orinterpret295033HighSecondaryContainment

X the followingastheyapplytoHIGH

3.8 64AreaRadiationLevels/9

SECONDARY CONTAINMENT

AREA RADIATION LEVELS:Arearadiationlevels

EA2.02-Abilitytodetermineand/orinterpret295035SecondaryContainmentHigh

the followingastheyapplyto

SECONDARY X CONTAINMENT

HIGH DIFFERENTIAL

2.8 65DifferentialPressure/5

PRESSURE:Off-sitereleaserate

Plant-Spec ific KIACategoryTotals

1 11133GroupPointTotal

I 713

ES-401 40610NRCExamOutline

Written Examination

OutlinePlantSystems-

Tier2Group1FormES-401-1

System#/NameKKKKKKAAAA G Imp.Q#12 34561234 A2.16-Abilityto(a)predicttheimpactsofthefollowingonthe

RHRlLPCI: INJECTIONMODE(PLANTSPECIFIC)

203000 RHRILPCI

Injection X and (b)basedonthose

predictions, use4.586 Modeprocedurestocorrect,control,ormitigate

the consequencesofthoseabnormalconditionsoroperations

Lossofcoolant

accident 2.1.14-ConductofOperations

Knowledge 2150031RM Xofsystemstatuscriteriawhichrequirethe3.387notificationofplant

personnel.

2.1.23-ConductofOperationsAbilityto259002ReactorWaterLevel

Xperformspecificsystemandintegrated

4.0 88 Controlplantproceduresduringallmodesofplant

operation.A2.06-Abilityto(a)predicttheimpactsofthefollowingonthe

SHUTDOWNCOOLINGSYSTEM(RHR

SHUTDOWN259002ReactorWaterLevel

XCOOLINGMODE);and

(b)basedon 3.5 89 Control those predictions,useprocedurestocorrect, control ,ormitigatethe

consequences

ofthoseabnormalconditions

SDCIRHRpumptripsA2.12-Abilityto(a)predicttheimpactsofthefollowingonthe

REACTOR PROTECTIONSYSTEM;and(b)based259002ReactorWaterLevel

Xonthosepredictions

,useproceduresto

4.1 90 Controlcorrect,control

,ormitigatethe

consequencesofthoseabnormalconditionsoroperations

MainturbinestopcontrolvalveclosureAI.OI-Abilitytopr

edictand/ormonitor

203000 RHRlLPCI: Injection changesinparametersassociatedwi th Xoperatingthe

RHRlLPCI: INJECTION 4.2 I ModeMODE(PLANTSPECIFIC)controls

including:ReactorwaterlevelK4.02-KnowledgeofSHUTDOWNCOOLINGSYSTEM(RHR205000ShutdownCooling

XSHUTDOWNCOOLINGMODE)

3.7 2 design feature(s)

and/or interlockswhichprovideforthe

following:

High pressure isolation: Plant-Specific

K6.09-Knowledgeoftheeffectthatalossormalfunctionofthe

following will206000HPCI

XhaveontheHIGH

PRESSURE 3.5 3COOLANTINJECTION

SYSTEM: Condensate

storage and transfer system: BWR-2 ,3,4K5.04-Knowledgeofthe

operationalimplicationsofthe

following concepts 209001 LPCS X astheyapplytoLOW

PRESSURE2.84CORESPRAYSYSTEM

Heatremoval(transfer)

mechanisms211000SLC XK2.01-Knowledgeofelectricalpower2.95 suppliestothe following:

SBLC pumps

ES-401 40610NRCExamOutline

Written Examination

OutlinePlantSystems-

Tier2Group1FormES-401-1

System#/NameKKKKKKAAAA G Imp.Q#12345 6 1 2 3 4 K6.03-Knowledgeoftheeffectthatalossor malfunctionofthefollowingwill

212000RPS XhaveontheREACTOR

PROTECTION

3.5 6 SYSTEM:Nuclearboiler

instrumentationA4.04-Abilityto

manually operate 2150031RM X and/or monitorinthecontrolroom:IRM

3.1 7backpanelswitches,meters,andindicatinaIiahtsA3.03-Abilityto

monitor automatic 215004 Source Range Monitor XoperationsoftheSOURCERANGE

3.6 8 MONITOR(SRM)SYSTEMincluding:RPSstatusA2.03-Abilityto(a)predicttheimpactsofthefollowingonthe

AVERAGEPOWERRANGE

MONITOR/LOCALPOWERRANGE

MONITOR SYSTEM;215005APRM/LPRM

Xand(b)basedonthose

predictions, use 3.6 9 procedurestocorrect ,control,ormitigatethe

consequencesofthose abnormal conditions

Inoperativetrip(all causes)K2.03-Knowledgeof

electrical

power217000RCIC

Xsuppliestothefollowing

RCICflow 2.7 10 controllerK1.05-Knowledge

ofthe physical connectionsand/orcause-effect218000ADS X relationships between AUTOMATIC 3.9 II DEPRESSURIZATION

SYSTEM andthefollowing:Remote

shutdown system: Plant-Specific

2.1.24-Conduct of Operations

Ability218000ADS Xtoobtainandinterpretstation

electrical

2.8 12 and mechanical

drawinas.A2.06-Abilityto(a)predicttheimpactsofthefollowingonthe

PRIMARY CONTAINMENT

ISOLATION223002PCISlNuclear

Stearn SYSTEM/NUCLEAR

STEAM SUPPLY X SHUT-OFF;and(b)basedonthose

3.0 I3 Supply Shutoffpredictions,use

procedures

to correct ,control,ormitigatethe

consequencesofthoseabncondorops

.Conta inment instrumentat

ion failuresA3.01-Abilityto

monitor automaticoperationsofthe

PRIMARY223002PCISlNuclear

Stearn X CONTAINMENT

ISOLATION 3.4 14 Suppl y Shutoff SYSTEM/NUCLEAR

STEAM SUPPLY SHUT-OFF including: System indicatinaIiahtsandalarmsA3.03-Abilityto

monitor automat ic239002SRVs

X operations

ofthe RELIEF/SAFETY

3.6 15 VALVES including:Tailpipe temperatures

A4.08-Ability to manually operate239002SRVs

X and/or monitorinthecontrolroom

3.2 16Plantairsystempressure

Plant-Soecific

ES-401 40610NRCExamOutline

Written Examinat ion OutlinePlantSystems-

Tier2Group1FormES-401-1

System#/NameKKKKKKAAAA G Imp.Q#123456123 4A4.03-Abilityto

manually operate259002ReactorWaterLevel

and/or monitor inthecontrolroom

All Control X individual

component controllers

when 3.817 transferringfrommanualto

automatic modes K3.06-Knowledgeoftheeffectthatalossorma lfunctionofthe STANDBY 261000SGTS

X GAS TREATMENT SYSTEMwillhave 3.0 18onfollowing

Primary containmentoxvcencontent:Mark-I&II

K4.04-KnowledgeofA.C

.26200IACElectrical

ELECTRICAL

DISTRIBUTION

design Distributi

on X feature(s)

and/orinterlockswhich

2.8 19provideforthefollowing

Protective

relay ingA1.02-Abilitytopredictand/or

monitorchangesin parameters

associated

with262002UPS (ACIDC)Xoperatingthe

UNINTERRUPTABLE2.520 POWER SUPPLY (A.C.lD.C.)controls includinCl

Motor cenerator cutouts K1.02-Knowledgeofthephysical263000DCElectrical

connect ions and/orcause-effect

Distribution

X relationshipsbetweenD.C

.3.2 21 ELECTRICAL

DISTRIBUTIONandthe following: Battery chargerandbattery

K5.06-Knowledgeoftheoperat

ional implicationsofthefollow

ing concepts264000EDGs

Xastheyapplyto

EMERGENCY3.422 GENERATORS (DIESEUJET)

Load sequencing

K2.02-Knowledgeof

electr ical power300000InstrumentA

ir Xsuppliestothefollowing

Emergency 3.0 23 air comcressor

K3.01-Knowledgeoftheeffectthatalossor malfunctionofthe300000Instrument

Air X (INSTRUMENT

AIR SYSTEM)will2.724haveonthefollowing

Containment

air system 2.4.31-Emergency Procedures/Plan 400000 Component Cooling XKnowledgeof

annunciatorsalarmsand3.325 Waterindications,anduseoftheresponse

instructions

.A2.02-Abilityto(a)predicttheimpactsofthefollowingontheCCWSand(b)400000ComponentCoolingbasedonthose

predictions

, use X procedurestocorrect ,control,or2.826 Water m itigate the consequencesofthoseabnormaloperation

Highllow surgetanklevel KiACategoryTotal

s:2322222633

4GroupPointTotal

I 26/5

ES-401 50610NRCExamOutline

Written Examination

Outline Plant Systems-Tier2Group2FormES-401-1

System#/NameKKKKKKA AAA G Imp.Q#1234561234A2.01-Ability to(a)predicttheimpacts

of the followingonthe RADWASTE;and268000Radwaste

X(b)basedonthosepredictions,use

3.5 91procedurestocorrect,control,ormitigate

the consequences

ofthoseabnormalconditionsoro

perations: S vstem ru oture2.4.36-Emergency

Procedures/Plan271000Off-gas

X Knowledge ofchemistry/healthphysics

2.8 92tasksdurin

g emergencv o perations.A2.03-Abilityto(a)predicttheimpacts

of the followingonthe PLANT VENTILATION

SYSTEMS;and(b)288000Plant

Ventilation

Xbasedonthosepredictions,useprocedures

3.7 93tocorrect,control,ormitigatethe

consequences

ofthoseabnormalconditionsoroperations

Loss ofcoolantaccident:

Plant-S pecific K3.03-Knowledge

oftheeffectthata201003ControlRodand

Drive Xlossor malfunction

of the CONTROL 3.2 27 Mechanism ROD AND DRIVE MECHANISM willhaveon following:Shutdownmarg

inK4.09-Knowledge

of ROD WORTH MINIMIZER SYSTEM (RWM)(pLANT 201006RWM XSPECIFIC)designfeature(s)and/or

3.2 28interlockswhichprov

ideforthe following: System initialization

P-Spec(Not-BWR6)

K6.09-Knowledge

oftheeffectthata202001Recirculation

Xlossormalfunction

of the following will 3.4 29haveonthe RECIRCULATION

SYSTEM:ReactorwaterlevelA1.01-Ability to predict and/or monitor changes in parameters

assoc iated with21500ITravers

ingIn-coreProbe

X operating the TRAVERSING

IN-CORE2.830 PROBE controls including: Radiation levels: (Not-BWR1)

K1.10-Knowledge ofthe physical connections

and/or cause-effect216000Nuclear

Boiler Inst.X relationships

between NUCLEAR 3.2 31 BOILER INSTRUMENTATIONandthe following: Recirculation

flow control system 219000 RHRILPCI: ToruslPool

X K2.02-Knowledge of electrical

power3.132 Cooling Mode suppliestothe following: Pumps 226001 RHRILPCI: CTMT Spray A4.12-Ability to manually operate X and/or monitorinthe control room: 3.8 33 Mode Conta inmenVdrvwell

pressure 2.4.50-Emergency Procedures/Plan234000Fuel

Handling Equipment X Ability to verify system alarm setpoints 3.3 34 and operate controls identifiedinthe alarm response manual.K6.04-Knowledgeofthe effect that alossor malfunctionofthe following will245000MainTurbineGen

./Aux.Xhaveonthe MAIN TURBINE 2.6 35 GENERATOR AND AUXILIARY SYSTEMS: Hydrogen cooling

ES-401 50610NRC Exam Outline Written Examination

Outline Plant Systems-Tier2 Group 2 Form ES-401-1 System#I NameKKKKKKAAAA

G Imp.Q#123 4 5 6 123 4 A2.01-Abilityto(a)predicttheimpactsofthefollowingonthe

RADWASTE;and(b)basedonthose

268000 Radwaste Xpredictions,use

procedurestocorrect, 2.9 36control,ormitigatethe

consequencesofthoseabnormal

conditions

orooerations:SYstemruotureK5.01-Knowledgeofthe

operational

implicationsofthefollowing

concepts272000Radiation

Monitoring

Xastheyapplyto

RADIATION 3.2 37 MONITORING

SYSTEM: Hydrogen injection operation'seffecton process radiation indications

Plant-SoecificA3.01-Abilityto

monitor automatic290003ControlRoomHVAC

Xoperationsofthe

CONTROL ROOM 3.3 38HVACincluding

Initiation/reconfiguration

KiACategoryTotals

1111121 311 2GroupPointTotal

I 12/3

ES-401 Generic KnowledgeandAbilitiesOutline(Tier3)

Form ES-401-3 Facility:0610NRCExamOutline

Date: KJA#Topic RO SRO-Only Category IR Q#IR Q#2.1.12 Abilitytoapplytechnical

specificationsforasystem.

4.0 94 1.Ability to recognize indicationsforsystem operating 2.1.33 parameterswhichare entry-level

conditions

for3.466 Conduct technical specifications

.of Operations

Ability to operateplantphone, pagingsystem,and

67 2.1.16 two-way radio.2.9 2.1.18Abilitytomake

accurate , clearandconciselogs,2.968 records,statusboards,andreports.

Subtotal 3 1 2.2.22 Knowledge of limiting conditions

for operations

and 4.1 95safetylimits.

2.2.24 Abilitytoanalyzetheaffect

of maintenance

activities

3.8 96onLCOstatus

.2.Equipment Control 2.2.13 Knowledge of tagging and clearance procedures.

3.6 69 2.2.33 Knowledge ofcontrolrod

programming.

2.5 70 Subtotal 2 2 Knowledge ofSRO responsibilities

for auxiliary 2.3.3systemsthatareoutsidethecontrolroom(e.g.,waste

2.9 97 disposal and handling systems).2.3.9 Knowledge of the process for performing

a 3.4 98 containment

purge.3.Radiation A bility to perform procedurestoreduce excessive Control 2.3.10 levels ofra diation an d guard against personnel2.971 exp osure.2.3.9 Knowle dge of the process for p e rforminga 2.5 72 containment

purge.Subtotal 2 2 4.Knowledge of the parametersandlogicusedto

Emergencyassessthestatus

ofsafetyfunctionsincluding:I

Procedures

/2.4.21 Reactivity

control2.Core coolingandheat removal 3.4.3 99 Plan Reactor coolant system integrity 4.Containment

conditions

5.Radioactivity

release control.

ES-401 GenericKnowledgeandAbilitiesOutline(Tier3)

Form ES-401-3 Knowledge ofwhichevents

relatedtosystem 2.4.30 operations/status

should be reportedtooutside 3.6 100 a gencies.Abili ty to diagnose and recognizetrendsinan

2.4.47accurateand

timely manner utilizing the appropriate3.473controlroom

reference material.2.4.15 Knowledge of communications

procedures3.074 assoc iatedwithEOP implementation

Kno wledge ofhowthee vent-based

2.4.8 emergenc y/abnormal operating proceduresareusedin3.0

75 conjunctionwiththe symptom-based

EOPs.Subtotal 3 2 Ti er 3 Point Total 10 7

ES-401Recordof Rejected KIA's Form ES-401-4Tier/Group Randomly SelectedReasonfor Rejection KIA 1/1295016/AA2.07

ReplacedbyNRC Chief Examiner 2/1 218000/2.1.14

ReplacedbyNRC Chief Examiner 2/1600000/2.2.25

ReplacedbyNRC Chief Examiner 2/1 212000/A2.17 ReplacedbyNRC Chief Examiner 2/1205000/A2.04

ReplacedbyNRC Chief Examiner 2/1 400000/2.4.30 ReplacedbyNRC Chief Examiner AdminA1PM501 Replaceddueto conflict with independently

developed Audit lPM examination.

In-plantP1PM63 Removedfromexamby

direction of Chief Examiner.lPM In-plantP1PM66 Removedfromexamby

direction of Chief Examiner.lPM In-plant PJPM 311 Removedfromexamby

direction of Chief Examiner.lPM In-plant PJPM 76F Removedfromexamby

direction of Chief Examiner.lPM In-plantP1PM1-8 Developed for Unit-l by direction of Chief Examiner.lPM In-plant PJPM 1-108 Developed for Unit-l by direction of Chief Examiner.lPM SimulatorHLTS3-3 RevisedtoremoveEvent4at

direction of Chief Examiner.Scenario SimulatorHLTS3-4 Revisedtoadd Event3at direction of Chief Examiner.Scenario AdminA1PM511 Replacedduetounsat

evaluation

by Chief Examiner.lPM

Appendix D Scenario Outline FINAL Form ES-D-lFacility:BFNScenarioNumber:HLTS-3-1Op-TestNumber:HLT0610

Examiners:

Operators:

Initial Conditions:Unit3has been operatingfor192days.Unit2has

been operatingfor56days.

Unit1has been operatingfor274days

.3ED Diesel Generator is taggedforwater jacket leakage repair.Day 2 oftheLCO.Expectedtobe returned to servicethisshift.FuelleakersonU3are currently at RFI 60,000.Thunderstorms

are passing through the region , but no watchesarein effectforthe immediate area.The3CRFPwas oscillating

approximating

30 RPMduringlastshift,butis

now working properly and being monitored.The3CRFP Pump is operating in automatic in order to collectdataforthenext24hours.Atrouble

shooting plan is being developed.

Turnover: Support scheduled maintenanceandtesting

activities.

Alternate Stator Cooling Water Pumps per 3-01-35A, Sect 6.4 per scheduled OPA.Event Malfunction

Event Event Number Number Type*Description

la mrfanOIb reset N-ATC Thecrewwill alternate Stator Cooling Water Pumpsusing3-N-BOP 0I-35A.N-SRO lb N/A TS-SROTheUSwill respondtoa HPCI Rupture Diaphragm pressure switch PS-73-20B failure.2 imffw05b100 R-ATCThecrewwill

respondtoa3BHPFW heater isolation using 8:00 C-BOP 3-AOI-6-1.

R-SROThecrewwill

reduce power to-91%usingarecircflow

reduction.Thecrewwillisolate

feedwatertothe3BFW heater string.Thecrewwill

further reduce power to<79%usingarecirc

flow reduction.

3 imfswlOa C-ATC Thecrewwill respondtoatrip ofthe3AFuel Pool Cooling C-SRO pump using 3-AOI-78-1.

TS-SRO 4 imffw13b C-ATCThecrewwill

respondtoatrip ofthe3B Reactor Feedwater C-BOP Pump (RFP)using 3-AOI-3-1 and 3-01-3.C-SRO 5 bat rfpactrip M Thecrewwill respondtoatotalloss

of feedwater and reactor All scram.6 bat MThecrewwill

respondtoa RCIC steamleakinto secondary HLTS3-1 All containmentanda HPCI120VAC power failure.Thecrewwill

anticipate

Emergency Depressurization

or perform Emergency Depressurizationdueto secondary containment

high radiation.

• (N)ormal,(R)eactivity,(Imstrument,(C)omponent,(M)ajor

AppendixDScenarioOutline

Form ES-D-lFacility:BFNScenarioNumber:HLTS-3-3Op-TestNumber:HLT0610

Examiners:

Operators:InitialConditions:TheHPCI system is taggedoutfor14hourstorepairthe

Auxiliary Oil Pump.It is expected backin3 hours.Flow indicator 3-78Bisout of service.Instrument

Mechanics are lookingforanewtransmitter.TheMain Generator voltage regulatorhasbeenplacedin

ManualforPMsonthe

Automatic voltageregulator.Thespare

RBCCW pumpinservicetoUnit2

.Turnover: Reduce powerto95%using

recirculationflowduetolow

system load requirements.PMsonthe voltage regulator are complete.ReturntheMain Generator voltage regulator to Automatic operation.

Event Malfunction

Event Event Number Number Type*Description

1.\oJ N/A R-ATCTheATC operator will reduce reactor powerto95%usingR-SROrecircflowusing

3-01-68.1 b N/A N-BOPTheBOP operator will return the Main Generator voltage N-SRO regulator to Automatic using 3-01-47.2ior zdihs7542aC-BOPThecrewwill

recognize and respondtoan inadvertent

start ofstartC-SROthe3DCoreSpraypump.

TS-SROTheSROwilladdress

Tech Specs.3 imf rd0718-35 C-ATCThecrewwill

recognize and respondtoa controlroddriftingC-SROintothecoreusing

3-AOI-85-5.

TS-SROTheSROwilladdress

Tech Specs.4bat NRC/C-ATCThecrewwill

recognize and respondtoarecircpumptrip

, HLTSIO-l C-SRO power oscillations, scramandATWS.C-BOP 5.TimedoutfromMThecrewwill

recognize and respondtoafuelfailureduring

batchfileAlltheATWS

recovery actions.*(N)onnal,(R)eactivity,(I)nstrument,(C)omponent,(M)ajor

AppendixDScenarioOutline

Form ES-D-lFacility:BFNScenarioNumber:HLTS-3-4Op-TestNumber:HLT0610

Examiners:

Operators:

Initial Conditions:Theunitisstartingupfollowingarefueloutage.Reactor

powerisat-1%."C"RFPis uncoupled for performance

of turbine overspeed testing.Currentlyatstep5.76.8

oO-GOI-IOO-IA.

Turnover:The3CRFPis

uncoupledandthe suctionanddischargevalvesaretaggedfor

performance

of turbine overspeed.

Currentlyatstep5.76.8 oO-GOI-lOO-IAandatstep5.6.13

00-01-3forwarming3BRFP

.Event Malfunction

Event Event Number Number Type*Description

1noneR-ATCCrewwillcontinuetopullrodstoincreasepowerandstartN-BOPwarmingup2BRFP

R-SRO 2 imfrd14a I-ATCCrewwillrespondtoaRWMfailure.I-SROSROreferences

Tech Specs.TS-SRO 3 imfrdOlaC-ATCCrewwill

respondtoatrip of3ACRDpump.

C-SRO 4 imf sw02a tripC-BOPCrewwillrespondtoa

RBCCWpumptrip 7048FTCC-SROCrewmanuallycloses70-48afterfailstoautoclose

5 ior zdihs468aC-BOPCrewwillrespondto

feedwater controller

malfunction

which imfth235C-SROresultsincoldwater

injection 6 imfth235 MCrewrespondstofuelfailureaftercoldwater

injection All 7 imf cu0425 MCrewrespondstoa

RWCU line breakandscramsreactor

ior zdihs69 1 Allbeforeanyareareachesmaxsafevalue.

null*(N)onnal, (Rjeactivity,(I)nstrument,(C)omponent, (Mjajor

ES-301 Administrative

Topics Outline Form ES-301-1 Facility: Browns Ferry Date of Examination:

2/25/08 Examination

Level (circle one): RO/SRO Operating Test NumberHLT0610 Administrative

Topic Type Describe Activitytobe performed (see Note)Code*A.Conduct of Operations

M Perform 2-SR-3.4.9.3&4 Reactor Recirculation

Pwnp 0610 AJPM 542 Start Eimitations (RO/SRO).B.Conduct of Operations

M Determination

'Of Active/InactiveLicenseStatus

0610 AJPM 504

r: I, C.Equipment Control ,..P c Perform 2-SR-3.4.2

.1 Jet Pump Mismatch and 0610 AJPM 12G Operability (OPERA nON)(RO/SRO)""-I;\".'.,-"...D.Radiation Control M CalculateStayTimefor

Emergency Exposure 0610 AJPM 518.(RO/SRO)}.J;,."'..J'"-, ,'i"..-E.Emergency Plan N/SClassifytheEventpertheREP (Torus exceeds 0610 AJPM 487TCFPSPCurve)(SROOnly)

NOTE: All items (5 total)are required for SROs.RO applicants

require only 4 items unless they areretakina

only the administrative

topics, whenall5are required.*Type Codes&Criteria: (C)ontrol room (D)irect from bank (::S3forROs;::s4for SROs&RO retakes)(N)ew or (M)odified

from bank1)(P)revious

2 exams (::s 1;randomly selected)(S)imulator

ES-301, Page 22 of27

ES-301 Control Roomlln Plant Systems Outline f7-v'4r..-

Form ES-301-2Facility:BFN

Date of Examination

2/25/08 E xam Leve l(circleone):

[RO]//SRO-U OperatingTestNumber:

HLT0610 ControlRoomSystems(8forRO

7forSRO-I;2or3forSRO-U)System/lPM Title Type Safety Code*Function A.RespondtoaDualRecircPumpTrip(OPRM'SOperable)

ADES 1(0610SJPM-61OF)

B.PerformControlRoomTransfer

of4KVUnitBoard2BPower

NS 6Supplies(0610

SJPM-222)C.Restorat ion to Normal followingRPSBus PowerLoss(0610 DES 7 SJPM-132)D.Respond t o Offaas Post TreatHIHIHI(0610

SJPM-190)DSP 9 E.Respond to Stuck Open SRV (0610 SJPM-3136F)

AMELS 3 F.Placing StandbySteamJetAir

Ejector in Operation (0610 AMES 4 SJPM-3116F)

G.Respond to Drywell Pressure and/or TemperatureHighor ExcessiveLeakageintothe

Drywell-FAULTED-SBGTCADEMS

5Failed(0610

SJPM-3126F)

H.Injection system Iineup-CSSYSI(0610 SJPM-322F)ADELS 2 (ROOnly)In-PlantS ystems(3fo r RO;3forSRO-I;3or 2forSRO-U)I.Placea250VBattery

Charger inService (0610PJPM-86)DL 6 J.Ventand Re-pressurize

the ScramPilotA irHeader(0610

DEPR 1 PJPM-I-8)K.Remo ve a eRDHCUfrom Service (0610PJPM-I08)NR 1*TypeCodes Criter iaforRO I SRO-I I SRO-U (A)ltematePath

4-6 I 4-6 I 2-3 (C)ontrolR oom (D)irectfromban

kI::: 8 I:s4 (E)mergency

o r abnormal in-plant I I (L)ow-Power I I (N)ew or (M)odified frombankincluding I(A)I I (P)revious 2 e xams 53 I:::3 I:::2 (R)CA I I (Slimulator