ML081370266

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Feb-Mar 05000259/2008301 Exam Draft Written Exam Outlines
ML081370266
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 04/08/2008
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-259/08-301 50-259/08-301
Download: ML081370266 (15)
v • d • e


See also: IR 05000259/2008301

Text

Draft Submittal(PinkPaper)

ti;DRAFTWrittenExam

Quality Checklist (ES-401-6)

vi&Written Exam Sample Plan

ES-401 Written Examination

Quality Checklist Form ES-401-6 Facility: Browns FerryDateofExam:

2/25/2008ExamLevel:ROSRO 0 Initial Item Description

a b*4.The sampling process was random and systematic(Ifmorethan4ROor2SRO

questions were repeatedfromthelast2NRC

licensing exam, consult the NRR OL program office).3.SRO questions are appropriate

in accordance

with SectionD.2.dofES-401

Date 1/8/2008 1/8/2008 18 New CIA 47 62.6%8 Modified 28 37.40/0 Memo 49 BankBankuse meets limits (no morethan75 percentfromthebank,at

least 10 percentnew,andtherestnewor modified);

enter the actualRO/SRO-only question distribution(s)atright.Between50and60 percentofthe questionsontheROexamare writtenatthe comprehension

/analysis level;theSRO exam may exceed 60 percentifthe randomly selected KAs support the higher cognitive levels;enter the actualRO/SRO question distribution(s)atright.2.a.NRCKlAsare

referencedforall questions.

b.Facility learning objectives

are referenced

as available.

1.Questions and answers are technically

accurate and applicabletothe facility.5.Question duplicationfromthe license screening/audit

exam was controlled

as indicated below (checktheitemthat

applies)and appears appropriate:the audit exam was systematically

and randomly developed;

or_the audit exam was completed before the license exam was started;orthe examinations

were developed independently;

orthe licensee certifies that thereisno duplication;

or_other (explain)11.The exam contains the required number of one-point, multiple choice items;thetotalis

correct and agrees with value on cover sheet 10.Question psychometric

quality and format meet the guidelinesinES Appendix B.7.6.9.Question content conforms with specific KIA statementsinthe previously

approved examination

outlineandis apprcoriateforthe Tiertowhich they are assigned;deviations

are justified 8.References/handouts

provideddonotgive away answersoraidinthe

elimination

of distractors.

a.Author b.Facility Reviewer (*)c.NRC Chief Examiner (#)d.NRC Regional Supervisor

Note:*The facility reviewer's

initials/signaturearenot applicable

for NRGdeveloped

examinations.

  1. Independent

NRC reviewer initial items in Column"c";chief examiner concurrence

required.ES-401,Page29of33

ES-401 Written Examination

Quality Checklist Form ES-401-6Facility:BrownsFerryDateofExam:2/25/2008ExamLevel:RO

D SRO C8J Initial Item Description

a b*4.The sampling processwasrandomand

systematic(Ifmorethan4ROor2SRO

questionswererepeatedfromthelast2NRC

licensing exam, consulttheNRROLprogramoffice).

1.Questions and answers are technically

accurate and applicabletothefacility.

Date 1/8/2008 1/8/2008 11 New CIA 222 Modified 3 120/0 Memo 12 BankE.Robert ScillianBetween50and60percentofthe

questionsontheROexamarewrittenatthe

comprehension

/analysis level;theSROexammay

exceed 60 percentifthe randomly selected KAs support the higher cognitivelevels;entertheactualRO/SRO

question distribution(s)atright.Bankusemeetslimits(nomorethan75

percentfromthebank,atleast10

percentnew,andtherestnewor modified);

entertheactualRO/

SRO-only question distribution(s)atright.11.Theexam

containstherequired

number of one-point,multiplechoiceitems;thetotaliscorrectandagreeswithvalueoncoversheet10.Question

psychometric

quality and formatmeetthe guidelinesinES Appendix B.6.8.References/handouts

provideddonotgiveawayanswersoraidinthe

elimination

of distractors.

9.Question content conforms with specific KIA statementsinthe previously

approved examinationoutlineandis

appropriaefortheTiertowhichtheyare

assigned;deviations

are justified2.a.NRCKlAsare

referencedforall questions.b.Facilitylearning

objectives

are referencedasavailable.3.SRO questions are appropriate

in accordancewithSectionD.2.dofES-4015.Question

duplicationfromthe license screening/auditexamwas controlled

as indicated below (checktheitemthatapplies)andappears

appropriate:theauditexamwas

systematically

and randomly developed;

or_theauditexamwas

completed beforethelicenseexamwasstarted;orthe examinations

were developed independently;

orthe licensee certifiesthatthereisno

duplication;

or_other (explain)7.a.Author b.Facility Reviewer (*)c.NRC Chief Examiner (#)d.NRCRegional

SupervisorNote:*The facility reviewer's

initials/signaturearenot applicable

for NRGdeveloped

examinations.

  1. Independent

NRC reviewerinitialitemsinColumn"c";chief

examiner concurrence

required.ES-401,Page29of33

ES-401 Written Examination

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

RO KIA Category Points SRO-Only Points Tier Group K K KKK KAAAAG Total A2 G*Total12345612 3 4*1.1 3 3 3 3 4 4 20 437 Emergency21 1 1121712 3&Plant Tier Evolutions

Totals444 4 6 5 27 5 5 10 1 2 3222223 3 3 2 2632 5 2.Plant21111121111112021 3 Systems Tier Totals 3 4333 4 3444 3 3853 8 3.Generic Knowledge&Abilities1234 1 2 3 4 10 7 Categories

3 223122 2 Note: 1.Ensurethatatleasttwo

topics from every applicable

KIA category are sampled within each tier oftheROand SRO-only outlines (i.e., exceptforone categoryinTier3 of the SRO-only outline, the"Tier Totals"ineach KIA category shall notbeless than two).2.The pointtotalfor eachgroupand tierinthe proposed outline must match that specifiedinthetable.Thefinal

pointtotalforeachgroupand

tiermaydeviateby

+/-l from that specifiedinthetablebasedonNRC

revisions.ThefinalRO

exam musttotal75 pointsandthe SRO-only exam musttotal25points.

3.Systems/evolutions

within eachgroupare identifiedonthe associated

outline;systems or evolutionsthatdonotapplyatthe

facility should be deleted and justified;

operationally

important, site-specific

systems thatarenot includedonthe outline should be added.Referto section D.l.b ofES-401, for guidance regarding elimination

of inappropriate

KIA statements.

4.Select topicsfromasmany

systems and evolutions

as possible;sample every system or evolutioninthegroup

before selecting a second topicforany system or evolution.

5.Absent a plant specific priority, only those KAs having an importance

rating (IR)of2.5 or highershallbe selected.UsetheROandSRO

ratingsfortheROand

SRO-only portions, respectively.

L 6.Select SRO topicsforTiersIand2fromthe

shaded systems and KIA categories.

7.*The generic (G)KIAsin TiersIand2shallbe

selected from Section 2 of the KIACatalog,butthe

topicsmustbe relevanttothe applicable

evolutionorsystem.Refer to Section D.I.b of ES-40 1forthe applicable

KIA's 8.Onthe following pages, enter the KIA numbers, a brief description

of each topic, the topics'importance

ratings (IR)forthe applicable

licenselevel,andthe

point totals (#)for each system and category.Enterthegroupand

tier totalsforeach categoryinthe table above.Iffuel handling equipment is sampled in other than CategoryA2orG*onthe SRO-only exam, enteritontheleftside

of ColumnA2for Tier 2, Group2(Note#1 does not apply).Use duplicate pagesforROand SRO-only exams.9.For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions,IRs,and point totals (#)on Form ES-401-3.Limit SRO selections

to KlAs that are linkedtoIOCFR55.43

ES-401 20610NRCExamOutline

Written Examination

Outline Emergency and Abnormal Plant Evolutions

-Tier1Group1FormES-401-1

I EAPE#I Name Safety Function K1K2K3 I A1 I A2 I G KJA Topic(s)Imp.I Q#I c (AA2.01-Abilitytodetermineand/orinterpret295006SCRAM

11 XthefollowingastheyapplytoSCRAM

4.6 76 Reactor powerAA2.07-Abilitytodetermineand/orinterpret295021Loss

ofShutdownCoolingI4 XthefollowingastheyapplytoLOSSOF

3.1 77 SHUTDOWN COOLING: Reactor recirculation

flow 2.1.28-ConductofOperations

Knowledge of295024HighDrywellPressureI5 Xthepurposeandfunctionofmajorsystem3.378 com ponentsandcontrols

.EA2.01-Abilitytodetermineand/orinterpret295026SuppressionPoolHighWater

Xthefollowingastheyapplyto

SUPPRESSION

4.2 79 Temp.15POOLHIGHWATER

TEMPERATURE

Suppressionpoolwatertem

perature EA2.05-Abilitytodetermineand/orinterpret295037SCRAMConditionPresentthefollowingastheyapplytoSCRAMandPowerAboveAPRMDownscale

X CONDITIONPRESENTANDREACTOR4

.3 80orUnknown 11POWERABOVEAPRM

DOWNSCALE ORUNKNOWN:Controlrod

position 2.2.22-EquipmentControl

Knowledge of295038HighOff-siteReleaseRate

19 Xlimitingconditionsforoperationsandsafety4.1

81 limits.2.2.24-EquipmentControlAbilitytoanalyze600000PlantFireOn-siteI8 Xtheaffectof

maintenanceactivitiesonLCO

3.8 82 status.295001PartialorCompleteLossof

2.1.14-ConductofOperationsKnowledgeofForcedCoreFlowCirculation

II&4 Xsystemstatuscriteriawhichrequirethe

2.5 39notificationofplant

personnel.AK3.01-Knowledgeofthereasonsforthe29500IPartialorCompleteLossoffollowingresponsesastheyapplytoPARTIALForcedCoreFlowCirculation

II&4 XORCOMPLETELOSSOFFORCEDCORE3.440 FLOW CIRCULATION

Reactorwaterlevel

response AA2.01-Abilitytodetermineand/orinterpret295003PartialorCompleteLoss

of XthefollowingastheyapplytoPARTIALOR3.441 AC/6COMPLETELOSSOF

AC.POWER: CauseofpartialorcompletelossofAC.powerAKI.03-Knowledgeoftheoperational295004PartialorTotalLossofDCimplicationsofthefollowingconceptsasthey

Pwr/6 XapplytoPARTIALOR

COMPLETELOSSOF2.942 D.C.POWER:Electricalbusdivisional

separationAA1.04-Abilityto

operate and/or monitor295005MainTurbineGeneratorTrip

I Xthefollowing

astheyapplyto

MAIN2.743 3TURBINEGENERATORTRIP

Main generator controlsAK3.05-Knowledgeofthe

reasonsforthe295006SCRAM

I 1 X following responses astheyapplyto

3.8 44 SCRAM:Directturbine

generator trip: Plant-5pecific

AA2.04-Abilityto

determine and/or295016ControlRoomAbandonment

I Xinterpretthefollowing

astheyapplyto

3.9 45 7CONTROLROOM

ABANDONMENT

Suppression

pool temoeratureAK2.01-Knowledgeofthe

interrelations295018PartialorTotalLoss

ofCCW I X betweenPARTIALORCOMPLETELOSS3.346 8OFCOMPONENTCOOLINGWATERand

the following:

System loads295019PartialorTotalLossofInst.

XAA2.02-Ability to determine and/or 3.6 47 Air I 8 interpretthefollowing

astheyapplyto

ES-401 20610NRCExamOutline

Written Examination

Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 1FormES-401-1

I EAPE#INameSafety

Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s)Imp.I Q#I (PARTIAL OR COMPLETELOSSOF INSTRUMENT

AIR:Statusof safety-related instrumentairsystemloads(see

""AK2.1-AK2.19)2.4.50-Emergency Procedures

I Plan295021Loss

ofShutdownCoolingI4 X Abilitytoverifysystemalarm

setpoints and 3.3 48 operate controls identifiedinthealarm

I'"responsemanual.

AK1.02-Knowledgeofthe operational295023RefuelingAceCoolingMode

I X implications

ofthefollowing

concepts as 3.2 49 8theyapplyto

REFUELING ACCIDENTS: Shutdown margin 2.1.33-Conduct of Operations

Ability to295024HighDrywelI

PressureI5 X recognize indicationsforsystemoperating

3.4 50 parameterswhichare entry-level

'"conditionsfor

technical specifications

.EK2.08-Knowledgeofthe interrelations295025HighReactor

Pressure 13 XbetweenHIGH

REACTOR PRESSURE3.751andthefollowing:

Reactor/turbine

pressure regulating

system: Plant-SpecificEA2.01-Ability to determine and/or 295026 SuppressionPoolHighWater

interpretthefollowingastheyapplyto

X SUPPRESSIONPOOLHIGH WATER4.152 Temp.15 TEMPERATURE:

Suppression

pool water temperatureEK3.04-Knowledgeofthereasonsforthe295028HighDrywelI

TemperatureI5 X following responsesastheyapplytoHIGH

3.6 53 DRYWELL TEMPERATURE:

IncreaseddrywellcoolingEA1.06-Abilitytooperate and/or monitor295030Low SuppressionPoolWater"thefollowingastheyapplytoLOW

X SUPPRESSION

POOL WATER LEVEL: 3.4 54 Levell 5'" Condensate

storage and transfer (make-uptothe suppression

pool): Plant-Specific2.4.6-Emergency Procedures

I Plan 295031ReactorLowWater

Level/2 X Knowledge symptombasedEOP 3.1 55'"mitigationstrateg

ies.EK2.11-Knowledgeofthe interrelations295037SCRAMCondition

PresentbetweenSCRAM

CONDITION PRESENTandPowerAboveAPRMDownscale

X WI AND REACTOR POWER ABOVE APRM 3.8 56orUnknown 11DOWNSCALE OR UNKNOWNandthe following: RMCS: Plant-SpecificEK1.01-Knowledgeoftheoperational implicationsofthefollowing

concepts as295038HighOff-site

Release Rate 19 XtheyapplytoHIGH

OFF-SITE RELEASE2.557 RATE: Biological

effectsofrad ioisotope inaestion"AA1.08-Abilitytooperateand

I or monitor600000PlantFireOn-site

I 8 X the follOWingastheyapplytoPLANTFIRE

2.6 58ONSITE: Fire fighting equipmentusedoneachclassoffire

KIACategoryTotals:

33338 7GroupPointTotal:

I 20/7

ES-401 30610NRCExam

Outline Written Examination

Outline Emergency and Abnormal Plant Evolutions

-Tier 1 Group 2FormES-401-1

I EAPE#/NameSafetyFunctionK1K2K3A1A2GKIATopic(s)

Imp.I Q#I (2.4.6-Emergency

Procedures

I Plan295002Loss

of Main Condenser Vac 13 XKnowledgesymptombasedEOPmitigation4.0

83 strategies.

2.4.31-EmergencyProcedures

I Plan295009LowReactorWaterLevel

12 X Knowledge ofannunciatorsalarmsand3.484indications,anduseoftheresponseinstructions.

EA2.02-Abilitytodetermineand

Iorinterpret500000HighCTMTHydrogen

Cone, IthefollowingastheyapplytoHIGH

X PRIMARY CONTAINMENTHYDROGEN3.5

85 5 CONCENTRATIONS

Oxygenmonitoring

system availabilitvAK2.01-Knowledge

oftheinterrelations295009LowReactorWaterLevel

12 XbetweenLOW

REACTORWATERLEVEL3.959andthefollowing

Reactorwaterlevelindication2.2.22-EquipmentControlKnowledge

of295012HighDrywell

Temperature

15 X limiting conditions

for operationsandsafety 3.4 60 limits.AK1.02-Knowledge oftheoperational295015Incomplete

SCRAM/1 X implications

ofthefollowingconceptsasthey

3.9 61applyto INCOMPLETE

SCRAM: (CPR41.8to41.10)Cooldowneffectsonreactor

DOwer AKJ.08-Knowledge ofthereasonsforthe295020InadvertentCont.Isolation

I 5&followingresponsesastheyapplyto

7 X INADVERTENT

CONTAINMENT

3.3 62 ISOLATION:

Suppressionchamberpressure

responseEA1.01-Abilitytooperateand/or

monitor the295032High

Secondary Containment

XfollowingastheyapplytoHIGH

SECONDARY 3.6 63 Area Temperature

15 CONTAINMENT

AREA TEMPERATURE

Area temperature

monitorinz

svstem EA2.01-Ability to determineand/orinterpret295033HighSecondary

Containment

XthefollowingastheyapplytoHIGH

3.8 64 Area Radiation Levels 19 SECONDARY CONTAINMENT

AREA RADIATION LEVELS:ArearadiationlevelsEA2.02-Abilitytodetermineand/orinterpret295035Secondary

Containment

Highthefollowingastheyapplyto

SECONDARYDifferentialPressureI5 X CONTAINMENT

HIGH DIFFERENTIAL2.865 PRESSURE:Off-sitereleaserate

Plant-Specific KIA Category Totals:111133GroupPointTotal:

I 7/3

(ES-401 40610NRCExamOutline

Written Examination

Outline Plant Systems-Tier2Group1FormES-401-1

((System#/NameKKKKKKAAAA G Imp.Q#123456 1 234 A2.16-Abilityto(a)predicttheimpactsofthe followingonthe RHRILPCI: INJECTIONMODE(pLANT

SPECIFIC);203000 RHRILPCI: Injection X and (b)basedonthose

predictions, use 4.5 86 Mode procedures

to correct, control, or mitigate the consequencesofthose abnormal conditions

or operations:Lossofcoolant

accident2.1.14-Conductof

Operations

Knowledge 215003lRM Xofsystemstatuscriteriawhich

require the 3.3 87 notificationofplant personnel.

2.l.23-Conductof

OperationsAbilityto259002ReactorWaterLevel

Xperformspecificsystemand

integrated

4.0 88 Control plant proceduresduringallmodesofplant

operation.

A2.06-Abilityto(a)predictthe

impactsofthe followingonthe SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN259002ReactorWaterLevel

X COOLINGMODE);and (b)basedon 3.5 89 Control those predictions, use procedurestocorrect , control,ormitigatethe

consequences

of those abnormal conditions

SOCIRHRpumptrips A2.12-Abilityto(a)predictthe

impactsofthe followingonthe REACTOR PROTECTIONSYSTEM;and(b)based259002ReactorWaterLevel

Xonthose predictions, use procedures

to 4.1 90 Control correct, control,ormitigatethe

consequencesofthose abnormal conditions

or operations:Mainturbinestop

controlvalveclosureAl.OI-Abilitytopredictand/ormonitor

203000 RHRILPCI: Injection changes in parameters

associated

with Mode X operating the RHRILPCI: INJECTION 4.2 IMODE(pLANT

SPECIFIC)controls including:ReactorwaterlevelK4.02-KnOWledge of SHUTDOWN COOLINGSYSTEM(RHR

205000 Shutdown Cooling XSHUTDOWNCOOLINGMODE)

3.7 2 design feature(s)

and/or interlockswhichprovideforthe

following:

High pressure isolation:

Plant-Specific

K6.09-Knowledgeoftheeffectthatalossormalfunctionofthe

follOWing will 206000HPCI

XhaveontheHIGH

PRESSURE 3.5 3COOLANTINJECTIONSYSTEM

Condensate

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

following concepts 209001 LPCS X astheyapplytoLOW

PRESSURE2.84CORESPRAYSYSTEM

Heatremoval(transfer)

mechanisms211000SLC X K2.01-Knowledgeofelectricalpower2.95 suppliestothefollow

ing:SBLCpumps

(ES-401 40610NRCExamOutline

Written Examination

Outline Plant Systems-Tier2Group1FormES-401-1

(System#/NameKKKKKKAAAA G Imp.Q#12345612 3 4 K6.03-Knowledgeoftheeffectthatalossor malfunctionofthefollowingwill

212000RPS XhaveontheREACTORPROTECTION

3.5 6 SYSTEM:Nuclearboiler

instrumentation

A4.04-Ability to manually operate215003IRM X and/or monitorinthecontrolroom

IRM3.17backpanelswitches

, meters , andindicatinglights

A3.03-Abilityto monitor automatic215004Source

Range Monitor X operationsoftheSOURCERANGE

3.6 8 MONITOR(SRM)SYSTEMincluding

RPSstatus A2.03-Abilityto(a)predicttheimpactsofthefollowingontheAVERAGE

POWER RANGE MONITOR/LOCAL

POWER RANGE MONITOR SYSTEM;215005APRM/LPRM

Xand(b)basedonthosepredictions,use

3.6 9 procedurestocorrect,control,ormitigatethe

consequencesofthose abnormal conditionsInoperativetrip(all

causes)K2.03-Knowledgeofelectricalpower217000RCIC

X suppliestothefollowing:RCICflow

2.7 10 controllerK1.05-Knowledgeofthephysical

connectionsand/orcause-effect218000ADS X relationshipsbetweenAUTOMATIC

3.9 11 DEPRESSURIZATIONSYSTEMandthefollowing:Remoteshutdown

system: Plant-5pecific

2.1.24-ConductofOperations

Ability218000ADS Xtoobtainandinterpretstationelectrical

2.8 12 and mechanical

drawings.A2.06-Abilityto(a)predicttheimpactsofthefollowingonthePRIMARY

CONTAINMENT

ISOLATION223002PCISlNuclearSteam

SYSTEM/NUCLEARSTEAMSUPPLY

Supply Shutoff X SHUT-oFF;and(b)basedonthose

3.0 13 predictions

,useprocedurestocorrect, control ,ormitigatetheconsequencesofthoseabncondorops.

Containment

instrumentation

failures A3.01-Ability to monitor automatic operationsofthePRIMARY223002PCISlNuciearSteam

X CONTAINMENT

ISOLATION 3.4 14 Supply Shutoff SYSTEM/NUCLEAR

STEAM SUPPLY SHUT-OFFincluding

System indicatinQ

IiQhtsandalarms A3.03-Ability to monitor automatic 239002SRVs

X operat ionsofthe RELIEF/SAFETY

3.6 15VALVESincluding

Tailpipe temoeraturesA4.08-Abilitytomanuallyoperate

239002SRVs

X and/or monitorinthecontrolroom

3.216 Plantairsystempressure:Plant-

Specific

(ES-401 40610NRCExamOutline

Written Examination

Outline Plant Systems-Tier2Group1FormES-401-1

(System#/NameKKKKKKAAAA

G Imp.Q#123456 1234A4.03-Abilityto

manually operate 259002 ReactorWaterLevel

and/or monitorinthecontrolroom

All ControlXindividual

componentcontrollerswhen

3.8 17transferringfrommanualto

automatic modes K3.06-Knowledgeoftheeffectthatalossormalfunction

ofthe STANDBY261000SGTS

X GAS TREATMENTSYSTEMwillhave

3.0 18onfollowing

Primary containmentoxygencontent:Mark-I&IIK4.04-KnowledgeofA.C.262001AC Electrical

ELECTRICAL

DISTRIBUTION

design Distribution

Xfeature(s)and/orinterlockswhich

2.8 19provideforthefollowing:Protective

relavinaA1.02-Abilitytopredictand/or

monitorchangesinparametersassociatedwith262002UPS (ACIDC)Xoperatingthe

UNINTERRUPTABLE

2.5 20POWERSUPPLY(A.C.ID.C.)controlsincluding:Motor

generator outputsK1.02-Knowledgeofthephysical263000DC Electrical

connectionsand/orcause-effect

Distribution

X relationshipsbetweenD.C.3.221 ELECTRICAL

DISTRIBUTIONandthefollowing:Battery

chargerandbattery

K5.06-Knowledgeoftheoperational

implicationsofthefollowingconcepts

264oooEOOs

Xastheyapplyto

EMERGENCY 3.4 22 GENERATORS (DIESEUJET):

Load secuencinaK2.02-Knowledgeofelectricalpower

300000 Instrument

Air X suppliestothefollowing:Emergency

3.0 23 air compressorK3.01-Knowledgeoftheeffectthatalossormalfunctionofthe

300000 Instrument

Air X (INSTRUMENTAIRSYSTEM)will

2.7 24haveonthefollowing:

Containment

air svstem 2.4.31-EmergencyProcedures/Plan

400000 Component Cooling XKnowledgeofannunciatorsalarmsand3.325 Waterindications,anduseoftheresponse

instructions

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

400000 Component Coolingbasedonthosepredictions,use

Water X procedurestocorrect,control

, or 2.8 26 mitigate the consequencesofthose abnormaloperation:High/lowsurgetanklevel KJ A Category Totals: 2 3222 2 26334GroupPointTotal:

I 26/5

(ES-401 50610NRCExam

Outline Written Examination

Outline Plant Systems-Tier 2 Group 2FormES-401-1

((System#I NameKKKKKKAAAA

G Imp.Q#1234561234

A2.01-Abilityto(a)predictthe

impactsofthe followingonthe RADWASTE;and 268000 Radwaste X(b)basedonthose

predictions

, use3.591 procedures

to correct, control, or mitigate the consequencesofthose abnormal conditions

or operations:

System rupture 2.4.36-Emergency Procedures

I Plan 271000 Off-gas X Knowledge of chemistry I health physics2.892tasksduring

emergency operations.

A2.03-Abilityto(a)predictthe

impactsofthe followingonthe PLANT VENTILATIONSYSTEMS;and (b)288000Plant

Ventilation

Xbasedonthose

predictions, use procedures

3.7 93 to correct, control, or mitigate the consequencesofthose abnormal conditions

or operations

Lossofcoolant

accident: Plant-Specific10.03-Knowledgeoftheeffectthata

201003 ControlRodandDrive

Xlossor malfunctionofthe CONTROL 3.2 27 MechanismRODANDDRIVE

MECHANISM willhaveon following:

Shutdown margin K4.09-KnowledgeofROD WORTH MINIMIZER SYSTEM (RWM)(pLANT 20loo6RWM X SPECIFIC)design feature(s)and/or3.228

interlocks

which provideforthe following: System initialization:

P-Soec(Not-BWR6)

K6.09-Knowledgeoftheeffectthata20200I Recirculation

Xlossor malfunctionofthe following will3.429haveonthe RECIRCULATION

SYSTEM:ReactorwaterlevelA1.01-Abilitytopredictand/ormonitor

changes in parameters

associated

with 215001 TraversingIn-coreProbe

Xoperatingthe

TRAVERSING

IN-CORE 2.8 30PROBEcontrolsincluding:Radiation

levels: (Not-BWR1)K1.10-Knowledgeofthephysical

connections

and/or cause-effect216000NuclearBoilerInst.

Xrelationshipsbetween

NUCLEAR3.231 BOILER INSTRUMENTATIONandthe following:Recirculationflowcontrol

svstem 219000 RHRILPCI: TorusIPool

X K2.02-Knowledgeofelectricalpower

3.1 32CoolingModesuppliestothe

followina: Pumps 226001 RHRILPCI:CTMTSprayA4.12-Abilitytomanually

operate Xand/ormonitorinthecontrolroom:3.833

Mode Containmentldrywell

pressure2.4.50-Emergency Procedures

I Plan234000Fuel

Handling Equipment X Abilitytoverify systemalarmsetpoints3.334 and operatecontrolsidentifiedinthe

alarm response manual.K6.04-Knowledgeoftheeffectthatalossormalfunctionofthe

following will245000MainTurbineGen.

I Aux.Xhaveonthe MAIN TURBINE2.635GENERATORAND

AUXILIARY SYSTEMS:Hydrogencooling

(ES-401 50610NRCExam

Outline Written Examination

OutlinePlantSystems-

Tier 2 Group 2FormES-401-1

((System#I NameKKKKKKAAAA

G Imp.Q#12 3 4 5 6123 4 A2.01-Abilityto(a)predicttheimpactsofthefollowingonthe

RADWASTE;and(b)basedonthose268000Radwaste

X predictions,useprocedurestocorrect,2

.9 36 control ,ormitigatethe

consequencesofthoseabnormalconditionsorooerations:SYStemruoture

K5.01-Knowledgeoftheoperational

implicationsofthefollowingconcepts272000RadiationMonitoring

XastheyapplytoRADIATION

3.2 37 MONITORING

SYSTEM: Hydrogeninjectionoperation's

effectonprocessradiationindications:

Plant-5oecificA3.01-Abilitytomonitor automatic290003ControlRoomHVAC

X operationsoftheCONTROLROOM

3.3 38HVACinclUding

Initiationlreconfigurat

ion KIACategoryTotals

11111213112GroupPointTotal
I 1213

ES-401 Generic Knowledge and Abilities Outline (Tier3)Form ES-401-3 ((Facility:0610NRCExam

Outline Date: K/A#TopicROSRO-Only

Category IR Q#IR Q#2.1.12Abilitytoapply

technical specificationsforasystem

.4.094 1.A bility t o recogniz e indicati ons f or system operating 2.1.33 param eterswhichareentry-level conditions

for 3.4 66 Conduct technical specifications

.of OperationsAbilityt o operateplantph one, pagingsystem,and

2.1.16 two-way radi o.2.9 67 2.1.18Abilitytomakeaccurate, clearandconciselogs, 2.9 68 records , status boards ,andreports.

Subtotal 31 2.2.22 Knowledge of limiting conditions

for operations

and 4.1 95safetylimits.

2.2.24Abilityto analyzetheaffect 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 of control rod programming.

2.5 70 Subtotal 2 2 Knowledge of SRO responsibilitiesforauxiliary

2.3.3systemsthatareoutsidethecontrolroom(e.g.,waste

2.9 97disposaland

handling systems).2.3.9 Knowledge ofthe process for performing

a3.498 containment

purge.3.Radiation A bility toperform procedurestoreduce excessive Control 2.3.10 levels ofra diation and guard against personnel 2.9 71 exposure.2.3.9 Knowledgeofthe process f or performinga 2.5 72 containment

purge.Subtotal 2 2 4.Knowledge of the parametersandlogicusedto

Emergencyassessthestatus

ofsafetyfunctionsincluding:I

Procedures/

2.4.21 Reactivity

control2.Corecoolingandheat

removal 3.4.399 Plan Reactor coolantsystemintegrity4

.Containment

conditions

5.Radioactivityreleasecontrol.

ES-401 Generic Knowledge and Abilit ies Outline (Tier3)Form ES-401-3 ((Knowledge ofwhichevents

relatedtosystem 2.4.30 operations/statusshouldbe reported to outside 3.6 100 a gencies.Ability to diagnose and recognize trendsinan 2.4.47accurateandtimely

manner utilizing the appropriate3.473controlroom

reference material.2.4.15 Knowledge of communications

procedures3.074 associatedwithEOP implementation

Knowledge ofhowthe event-based

2.4.8 emergency/abnormal

operating proceduresareusedin3.075 conjunctionwiththe symptom-based

EOPs.Subtotal 3 2 Tier 3 Point Total 10 7

ES-401RecordofRejectedKIA'sFormES-401-4

(('-...Tier!Group Randomly SelectedReasonforRejection

KIA 1/1 295016/AA2.07 Replaced by NRC Chief Examiner 2/1 218000/2.1.14

Replaced by NRC Chief E xaminer 2/1 600000/2.2.25 Replaced by NRC Chief Examiner 2/1 212000/A2.17 Replaced by NRC Chief Examiner 2/1205000/A2.04

Replaced by NRC Chief Examiner 2/1400000/2.4.30

Replaced by NRC Chief Examiner Admin AJPM501 Replaceddueto conflict with independently

developed Audit JPM examination.

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