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| number = ML082200233
| number = ML082200233
| issue date = 08/07/2008
| issue date = 08/07/2008
| title = Harris March 05000400-08-301 Exam Final Outlines
| title = March 05000400-08-301 Exam Final Outlines
| author name =  
| author name =  
| author affiliation = - No Known Affiliation
| author affiliation = - No Known Affiliation

Revision as of 08:59, 17 April 2019

March 05000400-08-301 Exam Final Outlines
ML082200233
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Site: Harris Duke Energy icon.png
Issue date: 08/07/2008
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To:
NRC/RGN-II
References
50-400/08-301
Download: ML082200233 (19)


See also: IR 05000400/2008301

Text

Final Submittal (Blue Paper)l-!Ae.R")S

ZaB-30\Of res\3/10-slrs/ltJ.J8

WI

3/Z//2eKJ o FINAL OUTLINES

ES-301 AdministrativeTopicsOutlineFormES-301-1

Facility: HARRISDateof Examination:March,2008

ExaminationLevel(circleone):

OperatingTestNumber:

NRC Administrative

Topic TypeDescribeactivitytobe

performed(seeNote)Code*Determinethecold,xenonfreeboronconcentration

Conduct of Operations

M requirementpriorto commenc inganaturalcirculationcooldown.(EPP

-005/0ST-1036)

G2.1.25 (2.8/3.1)-Abilitytoobtainand

interpretstationreference

materialssuchasgraphs, monographs,andtableswhichcontain

performance

data.EstimatePrimaryto SecondaryLeakRate.(AOP-016, Conduct of Operations

MCurveBook)

2.1.25(2.8)-Abilitytoobtainandinterpretstationreference

materialssuchasgraphs, monographs,andtableswhichcontain

performance

data.Performa QuadrantPowerTiltRatio(QPTR)

Equipment Control M calculationwithacontrolrod

misaligned.(OST-1039)2.2.12(3.0)-Knowledgeof

surveillance

procedures.Givenan emergency situation, determine theRadiationControl

M applicabledoselimitandthe

numberofpeoplethatwillberequiredtoperformthetask,withnoone

exceedingthelimit.2.3.4(2.5/3.1)-Knowledgeofradiationexposurelimitsand

contaminationcontrol,including

permissiblelimitsinexcessof

those authorized

.Emergency Plan NOT SELECTEDFORRO NOTE:Allitems(5totalarerequiredforSROs.RO

applicantsrequireonly4itemsunlesstheyareretakingonlythe

administrativetopics,when5arerequired.*TypeCodes

&Criteria:(C)ontrolroom (D)irectfrombank3forROs;sforSROs

&ROretakes)(N)ewor (M)odifiedfrombank (>1)(P)revious2exams1;randomly selected)(S)imulator

NUREG-1021

,Revision9HARRIS2008NRCRO301-1,Rev2

ES-301 Administrative

Topics OutlineFormES-301-1

Facility: HARRISDateof Examination:

March,2008

Examination

Level (circle one): RO/lsRq Operating Test Number: NRC Administrative

Topic Type Describe activitytobe performed (see Note)Code*Determinethecold,xenonfreeRCSboron

Conduct of Operations

M concentration

requirement

prior to commencing

a natural circulation

cooldown.(EPP-005/0ST-1036)

G2.1.25 (2.8/3.1)-Abilitytoobtainand

interpretstationreference

materialssuchasgraphs, monographs,andtableswhichcontain

performance

data.PerformaControlRoom

Supervisor

reviewofthe Conduct of Operations

P,M control board readings log.(OST-1021, Attachment

4)G2.1.18(3.0)-Abilitytomakeaccurate, clearandconciselogs,records,statusboards,andreports

.Review the completed surveillance

for Motor Driven Equipment Control N AFWPump"A".(OST-1211)

2.2.12(3.4)-Knowledge of surveillance

procedures

.'Givenan emergency situation, determine the Radiation Control M applicabledoselimitandthe

numberofpeoplethatwillbe required to performthetask,withnoone

exceedingthelimit.2.3.4(2.5/3

.1)-Knowledgeofradiation

exposurelimitsand contamination

control, including permissiblelimitsinexcessofthoseauthorized.

Evaluateachangein conditionswithanEALineffect

Emergency Plan Mandtaketherequired

actions.2.2.41(4.1)

-Knowledgeofthe emergencyactionlevelthresholds

and classifications

.NOTE:Allitems(5

total)are requiredforSROs.RO

applicants

requireonly4itemsunless

they are retakingonlythe administrative

topics, when5arerequired.

  • Type Codes&Criteria: (C)ontrol room (D)irect from bankforROs;sfor

SROs&RO retakes)(N)ew or (M)odifiedfrombank (>1)(P)revious

2 exams1;randomly selected)(S)imulator

NUREG-1021, Revision 9 HARRIS 2008 NRCSRO301-1,Revision2

ES-301 Control Room/ln-Plant

Systems OutlineFormES-301

-2 Facility: HARRISDateofExamination

3/2008ExamLevel(circleone)
RO/SRO(I)/SRO(U)OperatingTestNo.:

NRCControlRoom

Systems@(8forRO;7forSRO-I

2or3forSRO-U

,including1ESF)System/JPMTitleTypeCode*Safety

Function a.InitiateEmergencyBorationfollowingareactortrip(AOP-002)

M,A,S 1System:004/BankJPMCR

-037 b.Align ECCS for long-term recirculation (EPP-010)M,A,S 3 System: EPE011/BankJPMCR-031 c.InitiateRCSFeedandBleed(FRP-H

.1)P,D ,A,S 4PSystem:E05/2007NRCExamJPMd

d.RespondtoalossofNormalServiceWater(AOP-022)

N,A,S 4SSystem:076

e.PlacetheContainmentHydrogenPurgeSysteminoperation(OP-

D ,C 5 125)RO OnlySystem:028/BankJPMCR

-021 f.Transfer an Emergency BustoanEDG due to a degraded grid N,A,S 6 condition (AOP-028, Attachment

2)System: 062 g.RespondtoaFuelHandlingBuildingRMSalarm(AOP-005,OP-170)

N,L,S 7 System: 072 h.Align CCW to support RHR Initiation (OP-145)D,L,S 8 System: 008/BankJPMCR-085 In-Plant Systems@(3forRO;3forSRO-I;3or2forSRO-U)

i.Perform the local actions for a dropped rod recovery (AOP-001)D,E 1 System: 001/BankJPMIP-153NUREG-1021,Revision9HARRIS2008NRC301-2

,Revision2

ES-301 Control Room/ln-Plant

Systems OutlineFormES-301-2

j.IsolatetheECCS

Accumulatorsafteracontrolroom

evacuation

N,E 8'(AOP-004,Step38)

System: APE068 k.Terminate a Waste Gas Release (OP-120.07)

P,O,R 9 System: 071/2007 NRC JPM k@AllROandSRO-Icontrolroom(and

in-plant)systemsmustbe

differentandservedifferent

safety functions;all5SRO-U systemsmustserve different safety functions;in-plantsystemsandfunctionsmayoverlapthosetestedinthecontrolroom

.*TypeCodesCriteriaforRO

1 SRO-I 1 SRO-U (A)lternate

path 4-6 1 4-612-3(C)ontrolroom(D)irectfrombank (E)mergency

or abnormal in-plant:::: 1/:::: 1/:::: 1 (L)ow-Power

1 Shutdown (N)ewor(M)odifiedfrombankincluding1(A)

"2 2/:::.2/?:.1 (P)revious2exams::;3 1:;3 1::: 2 (randomly selected)(R)CA{S)imulator

HARRIS2008NRC 301-2 JPM SUMMARY STATEMENTS

a.Initiate Emergency Boration in accordance

with AOP-002 , EMERGENCY BORATION , following a reactortrip.The alternatepathistotake

corrective

actionfortwoormorestuckrodsas

determined

in EPP-004, REACTORTRIP.ModifiedfromBankJPM037byfailingfirstborationpath

driving candidatetouse secondary means.b.TransfertoColdLeg Recirculation

in accordancewithEPP-010, TRANSFERTOCOLD LEG RECIRCULATION, followingaLBLOCA.The

alternatepathsare corrective

actions for alignment failuresintwo different ftowpaths.ModifyBankJPMCR-031bychanging

the misalignedvalveinoneRNOstepandtherunningpump

combination.

c.InitiateRCSFeedandBleed

lAW FRP-H.1, RESPONSETOLOSSOF SECONDARYHEATSINK.The

alternatepathisto establish an adequateventpathusingRVHead

Vents following failureofone PORVtoopen.Randomly selected repeatfrom2007NRCExam(JPMd)notinthe

facility bank.d.Respondtoalossoftheonly

availableNormalService

WaterPumpin accordance

with AOP-022,LOSSOF SERVICE WATER.The alternatepathistostartoneEssential

Service WaterPumpandtotriptheMain

Turbine with powerlessthanP-10.NewJPM.

e.Placethe Containment

HydrogenPurgeSystemin

operation in accordancewith125,POST ACCIDENT HYDROGEN SYSTEM.BankJPMCR-021.ThisJPMwillbesimulatedintheMainControlRoom(usingcues)becausesome

equipment important tothetaskisnot

simulated.

NUREG-1021,Revision9 HARRIS2008NRC301-2,Revision2

ES-301 Control Room/In-Plant

Systems OutlineFormES-301-2f.Witha degradedgridcondition, transfer an emergencybustoanEDGin

accordance

with AOP-028, GRID INSTABILITY

-Attachment

2, ENERGIZING

EMERGENCYBUSESFROMEDGS,by

purposely de-energizingabus.The alternatepathisstartinganEDG following evaluation

of Voltage/Frequencyonan emergencybusandmanuallyresettingtheLoad

Sequencerafterthecycleiscomplete.NewJPM.g.RespondtoaFuel

HandlingBuildingRMSalarmin

accordancewithAOP-005, RADIATION MONITORINGSYSTEM,andOP-170,FUEL

HANDLING BUILDINGHVAC.AFHB monitoralarmsandFHBHVAC

componentsfailtoalignproperly.New

JPM.h.AlignCCWto

supportRHRInitiationin

accordancewithOP-145, COMPONENT COOLING WATER.BankJPMCR-085

.i.Performthelocal

actionsforadroppedrod

recovery in accordancewithAOP-001, MALFUNCTIONOFROD CONTROL AND INDICATIONSYSTEM.BankJPM-IP-153.

j.IsolatetheECCS

Accumulatorsafteracontrolroom

evacuation

in accordance

with AOP-004, REMOTE SHUTDOWN,Step38.NewJPM.

k.Terminate a WasteGasReleasein

accordancewithOP-120.07, WASTE GAS PROCESSING.

Randomlyselectedrepeatfrom2007NRCExam(JPMk).

NUREG-1021

,Revision9HARRIS2008NRC301-2,Revision2

ES-401

PWR Examination

Outline Form ES-401-2 Facility:Harris2008NRCOutlineDateofExam:

3/10108ROKIA Category Points SRO-Only Points Tier GroupKK KKKK AAA A G Total A2 G*Total12 3 4 5 6123 4*1.1 3 3 333 3 1833 6 Emergency&Abnormal 222111 2 922 4 Plant Evolutions

Tier 5 5 44452755 10 Tota ls 2.Plant 1313332323 2 3 28 235 Systems 2 1 1101102 111100213 Tier 4 2 4 3 4 3 3 4 4 3 4 3844 8 Totals 3.GenericKnowledgeandAbilities1

2 3 4 1012 3 4 7 Categories

2 2 2 4 2 2 1 2 Note: 1.Ensurethatatleasttwotopicsfromevery

applicable

KIA categoryaresampledwithineachtieroftheROand

SRO-onlyoutlines(Le.,exceptforone

categoryinTier3oftheSRO-onlyoutline,the"TierTotals"ineachKIA

categoryshallnotbelessthantwo).

2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthatspecifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby+/-1fromthatspecifiedinthetablebasedonNRCrevisions

.ThefinalROexammusttotal75pointsandtheSRO-onlyexammusttotal25points

.3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;systemsor

evolutionsthatdonotapplyatthe

facilityshouldbedeletedandjustified;

operationally

important, site-specificsystemsthatarenotincludedontheoutlineshouldbeadded

.RefertoES-401, Attachment2,for guidanceregardingeliminationof

inappropriate

KIA statements.

4.Selecttopicsfromasmany

systemsandevolutionsasposs

ible;sampleeverysystemorevolutioninthegroupbeforeselectingasecondtopicforanysystemorevolution.

5.Absentaplant specificpriority,onlythoseKAshavingan

importancerating(IR)of2.5orhighershallbeselected

.UsetheROandSROratingsfortheROand

SRO-only portions , respectively.

6.SelectSROtopicsforT

iers1and2fromtheshadedsystemsandKIAcategor

ies.7.*The generic(G)KlAsinTiers1and2shallbeselectedfromSection2oftheKIACatalog,butthetopicsmustberelevanttothe

applicableevolutionorsystem

.8.Onthefollowingpages,entertheKIAnumbers,a

briefdescriptionofeachtopic,thetop

ics'importanceratings(IRs)forthe

applicablelicenselevel

,andthepointtotals(#)foreachsystem

'andcategory.Enterthegroupandtiertotalsforeach

categoryinthetableabove;iffuelhandling

equipmentissampledinotherthan

CategoryA2orG*onthe

SRO-onlyexam,enteritontheleftsideofColumnA2forTier2,Group2(Note#1doesnotapply).Use

duplicatepagesforROand

SRO-only exams.9.ForTier3,selecttopicsfromSect

ion2oftheKIACatalog,andentertheKIAnumbers, descriptions,IRs,andpointtotals(#)onFormES-401-3

.LimitSRO selectionstoKlAsthatarelinkedto 10CFR55,43

NUREG-1021

1

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group1E/APE#/NameSafetyFunctionNumber IKIATopic(s)

limp.Ability to determineandinterpretthefollowingastheyapplytotheLossofResidualHeatRemoval025ILossofResidualHeatRemovalSystemI4 X AA2.02System:LeakageofreactorcoolantfromRHRinto

3.8 7 6closedcoolingwatersystemorintoreactorbuilding

atmosphere

ConductofOperations:Abilitytoevaluateplant057ILossofVitalAC

Instrument

Bus I 8 X 2.1.7 performanceandmakeoperational

judgments4.477basedonoperating

characteristics, reactorbehavior,and

instrument

interpretation.

ConductofOperations:Knowledgeofsystemstatus038I Steam GeneratorTubeRupture

I 3 X2.1.14criteriawhichrequirethenotificationofplant

3.3 7 8 personnel.

Ability to determineandinterpretthefollowingas

040 ISteamLineRuptureI4 X AA2.05theyapplytotheSteamLineRupture:When

4.57 9ESFASsystemsmaybesecuredAbilitytooperateand

I or monitorthefollowingas

E04 I LOCA Outside Containment

I 3 X EA1.3theyapplytoLOCAOutsideContainment:Desired

4.0 80operatingresultsduringabnormaland

emergency situations.Abilityto determine and interpretthefollowingastheyapplytothe(Lossof

Emergency Coolant E11 ILossof Emergency Coolant Recirculation

14 X EA2.2 Recirculation):

Adherence to appropriate

4.2 8 1 proceduresandoperationwithinthe

limitations

inthefacility'slicenseandamendments.

ConductofOperations:Abilitytoperform

specific007IReactorTrip

11 X2.1.23systemandintegratedplantproceduresduringall3.939modesofplantoperation.Knowledgeofthe

interrelationsbetweenthe008I PressurizerVaporSpace

Accident I 3 X AK2.03 Pressurizer

Vapor Space Accidentandthe2.540 following:

Controllersandpositioners009ISmallBreakLOCA

I 3 X EK2.03Knowledgeofthe

interrelationsbetweenthesmall3.041breakLOCAandthefollowing:

S/GsAbilitytooperateand

monitorthefollowingasthey011ILargeBreakLOCA

I 3 XEA1.15applytoaLargeBreakLOCA:RCS

temperature4.242andpressure

NUREG-1021

2

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group1E/APE#INameSafetyFunction

@IK1IK2IK3IA1I

A2 I Number IKIATopic(s)

I Imp.I Q#KnowledgeoftheoperationalimplicationsofthefollowingconceptsastheyapplytotheReactor

015/17/ReactorCoolantPump

Malfunctions

/4 X AK1.05 Coolant Pump Malfunctions(LossofRCFlow)

2.7 43Effectsof unbalancedRCSflowonin-coreaverage

temperature,coreimbalance

, and quadrant power tilt ConductofOperations

Knowledgeofthepurpose022/LossofReactor

CoolantMakeup/2 X 2.1.28andfunctionofmajorsystem

components

and 3.2 44 controls.Abilitytooperateand/or

monitorthefollow ing as025/LossofResidualHeatRemovalSystem/4

X AA1.20theyapplytotheLossofResidualHeatRemoval2.645System:HPJpumpcontrolswitch,indicators, ammeterrunninglights,andflowmeter

Abilitytooperateand/or

monitorthefollow ing as027/PressurizerPressureControlSystem

Malfunction

X AA1.03theyapplytothe

PressurizerPressureControl

3.6 46/3 Malfunctions

Pressurecontrolwhenonasteam

bubble Ability to determine or interpretthefollowingasthey

029/Anticipated

Trans ient WithoutScram(ATWS)

/1 X EA2.05applytoaATWS

System componentvalveposition3.447 ind icationsKnowledgeoftheoperationalimplicationsofthe

038/Steam GeneratorTubeRupture/3

X EK1.03followingconceptsastheyapplytotheSGTR

3.948 Natural CirculationKnowledgeoftheoperational

implicationsofthe040/SteamLineRupture/4

X AK1.07followingconceptsastheyapplytoSteamLine3.449 Rupture:Effectsof feedwater introduct ionondry S/G Ability to determine and interpretthefollow

ing as054/LossofMain

Feedwater/4 X AA2.04theyapplytotheLossofMainFeedwater(MFW)

4.2 50Properope rationofAFWpumpsandregulating

valves 056/LossofOff-sitePower/6

X 2.1.2 ConductofOperations:Knowledgeof

operator 3.0 51 responsibilitiesduringallmodesofplantoperation

.Knowledgeofthereasonsforthefollowing058/LossofDCPower/6

X AK3.02 responsesastheyapplytotheLossofDCPower:4.052

Act ionscontainedinEOPforlossofDCpower

NUREG-1021

3

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group1

I I*E/APE#/NameSafetyFunctionNumber IKIATopic(s)

limp.@!J Knowledgeofthereasonsforthe

following responsesastheyapplytotheLossof

Nuclear062/Lossof

Nuclear Service.Water/4 X AK3.02 ServiceWater:The automatic actions (alignments)

3.6 53withinthe nuclear service water resultingfromthe actuationoftheESFAS

Knowledgeofthe interrelationsbetweenthe (LOCA Outside Containment)andthefollowing:

Facility'sheatremoval

systems, including primary coolant,E04/LOCA Outside Containment/3 X EK2.2 emergencycoolant,the

decayheatremoval

3.8 54 systems, and relationsbetweenthe

proper operationofthese systemstothe operationofthe facility.Knowledgeofthe reasonsforthefollowing

responsesasthey applytothe(Lossof

SecondaryE05/Lossof

SecondaryHeatSink/4XEA2.2HeatSink):

Adherence to appropriate

procedures

3.7 55 and operationwithinthe limitationsinthe facility's

license and amendments.

Knowledgeofthereasonsforthe

following responsesastheyapplytothe(LossofE11/Lossof

Emergency Coolant Recirculation

/4 X EK3.3 Coolant Recirculation):

Manipulation

of controls3.856requiredtoobtain

desired operatingresultsduring

abnormal and emergency situations.

KIA Category Point Totals:3/333333/3GroupPointTotal:

I 18/6 NUREG-1021

4

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group2E/APE#INameS afety Function I G I K1 I K2[K3]A1 I A2 I Numbe r IKIATopic(s)

I Imp.Emergency Procedures/Plan

Abilitytoverifysystem

005/Inoperable/StuckControlRod

/1 X 2.4.50alarmsetpointsandoperatecontrolsidentifiedinthe

3.3 8 2alarmresponsemanual.Abilityto determineandinterpretthefollowingas068/ControlRoomEvacuation

/8 X AA2.10theyapplytotheControlRoomEvacuation

Source 4.4 83rangecountrateE06/DegradedCoreCool

ing/4 X 2.1.2 ConductofOperations:Knowledgeof

operator 4.0 84 respons ibilitiesduringallmodesofplantoperation

.Abilityto determine and interpretthefollowingasE10/Natural

Circulation

w ithSteamVoidinVesseltheyapplytothe(NaturalCirculationwithSteam

with/withoutRVLlS/4 X EA2.1VoidinVessel

with/withoutRVLlS):Facility

3.9 8 5conditionsandselectionof

appropriate

procedures

during abnormal and emergency operations.Knowledgeoftheoperational

implicationsofthe003/DroppedControlRod/1

X AK1.11followingconceptsastheyapplytoDroppedControl2.557 Rod:Long-rangeeffectsofcore

quadrantpowertiltKnowledgeofthe

interrelationsbetweenthe024/Emergency Bo ration/1 X AK2.03 EmergencyBorationandthefollowing:

Controllers2.658andpositionersKnowledgeofthereasonsforthefollowing033/Lossof

Intermediate

Range Nuclear responsesastheyapplytotheLossof

Intermediate

X AK3.02 Range Nuclear Instrumentation

Guidance3.659 Instrumentation/7containedInEOPforlossof

Intermediate

range Instrumentation

Abilitytodeterm ine and interpretthefollowingas036/FuelHandling

Incidents/8 X AA2.01theyapplytotheFuelHandlingIncidents

ARM3.260systemindications

Emergency Procedures/Plan

Abilitytoverifysystem059/Accidental

Liquid RadWasteRelease/9 X 2.4.50 alarm setpointsandoperatecontrolsidentifiedinthe3.361alarmresponsemanual.060/Acc idental Gaseous RadWasteRelease/9 X 2.1.32 ConductofOperations:Abilitytoexplainandapply

3.4 62allsystemlimitsandprecautions.Knowledgeofthe

interrelationsbetweentheLossof

069/Lossof Containment

Integrity/5 X AK2.03 ContainmentIntegrityandthefollowing

Personnel2.863accesshatchand

emergencyaccesshatchKnowledgeoftheoperational

implicationsofthe 074/lnadequateCoreCooling

/4 X EK1.06followingconceptsastheyapplytothe

Inadequate

3.0 64CoreCooling

Definitionof

superheated

steam NUREG-1021

5

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutline

EmergencyandAbnormalPlantEvolutions-Tier1Group2

IE/APE#INameSafetyFunction

I GK3 I A1 I A2 I Number IKIATop ic(s)I Imp.I Q#Abilitytooperate and/or monitorthefollowingas

E10/NaturalCirculationw

ithSteamVoid inVesseltheyapplytothe(NaturalCirculationwithSteam

with/without

RVLlS/4 X EA1.3VoidinVessel

with/withoutRVLlS):Desired

3.4 65operatingresultsduringabnormaland

emergency situations

.KIA CategoryPointTotal:

2/222111/2GroupPo int Total: I 9/4 NUREG-1021

6

ES-401Harris2008NRC

Form ES-401-2 Written Examination

OutlinePlantSystems

-Tier2Group1System#/Name""" N-u-m-b-e-r....1ConductofOperations:Abilitytorecognize

006 EmergencyCoreCooling

X 2.1.33 indicationsforsystemoperating

parameters

which 4.0 8 6areentry-levelconditionsfortechn

ical specifications.Abilityto(a)predicttheimpactsofthefollowing

malfunctionsoroperationsontheRPS

and(b)012 Reactor Protection

X A2.04basedonthosepredictions,use

procedures

to 3.2 8 7correct,control,ormitigatethe

consequences

of those malfunctions

or operations

Erraticpowersupplyoperation

Emergency Procedures/Plan:Knowledgeof

026 Containment

Spray X 2.4.31 annunciators,alarmsand indications

,anduseof3.488theresponseinstructions.073ProcessRadiationMonitoring

X 2.1.32 ConductofOperations:

Abilitytoexplainand

3.8 89applyallsystemlimitsand

precautions.Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsonthelAS;and(b)008 Component Cooling Water X A2.01basedonthosepredictions,use

procedures

to 3.6 90 correct ,control,ormitigatethe

consequences

of those malfunctionsoroperat ions:LossofCCW PumpKnowledgeoftheoperational

implicationsofthefollowingconceptsastheyapplytotheRCPS:

003 Reactor Coolant Pump X K5.03EffectsofRCP

shutdownonTave ,includingthe3.11reasonforthe

unreliabilityofTaveintheshutdown

loop 004 ChemicalandVolumeKnowledgeoftheoperational

implicationsofthe Control X K5.19followingconceptsastheyapplytotheCVCS:3.52 ConceptofSDMKnowledgeofthephysicalconnect

ions and/or005ResidualHeatRemoval

X K1.11 cause-effect

relationshipsbetweentheRHRSand

3.5 3thefollowingsystems:RWSTKnowledgeoftheeffectofalossor

malfunction005ResidualHeatRemoval

XK6.03onthefollowingwillhaveontheRHRS:RHRheat2.5

4 exchangerKnowledgeofthephysical

connections

and/or 006 EmergencyCoreCooling

X K1.08 cause effect relationshipsbetweentheECCSand

3.6 5thefollowingsystems:CVCSKnowledgeofECCSdesign

feature(s)

and/or 006 EmergencyCoreCooling

X K4.05 interlock(s)whichprovideforthefollowing

Auto4.3 6startof HPIILPI/SIP

NUREG-1021

7

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlinePlantSystems-Tier2Group1System#/Name

Number IKIATopics I Imp.007 Pressurizer

Relief/QuenchofPRTSdesign

feature(s)

and/or Tank X K4.01 interlock(s)whichprovideforthefollowing:

2.6 7Quenchtankcooling

Abilityto(a)predict the impactsofthefollowing

malfunctions

or operationsontheCCWS,and(b)basedonthose

predictions, use procedures

to 008 Component Cooling Water X A2.08correct,control,ormitigatethe

consequences

of 2.5 8 those malfunctions

or operations:Effectsof shutting (automatically

or otherwise)theisolationvalvesoftheletdown

cooler 010 Pressurizer

Pressure Control X K2.01 Knowledgeofbuspower

suppliestothefollowing:

3.0 9 Pressurizer

Heaters Knowledgeoftheeffectofalossor

malfunction

of 012 Reactor Protection

XK6.03thefollowingwillhaveontheRPS:Triplogic

3.1 10 circuits 012 Reactor Protection

X A3.02 Ability to monitor automaticoperationoftheRPS,3.611 including:

Bistables 013 Engineered

Safety Features Knowledgeoftheeffectthatalossor

malfunction

X K3.03oftheESFASwillhaveonthefollowing:4.312 Actuation Containment

Ability to predict and/or monitor changes in 022 Containment

Cooling X A1.01 parameters (to prevent exceedingdesignlimits)3.613 associated

with operatingtheCCS controls including:

Containment

temperature

Knowledgeofthephysical

connections

and/or 022 Containment

Cooling X K1.01 cause-effect

relationshipsbetweentheCCSand3.514thefollowingsystems:

SWS/cooling

system Ability to monitor automaticoperationoftheCSS, 026 Containment

Spray X A3.01 including:Pumpstartsand

correct MOV4.315 positioning

026 Containment

Spray X 2.2.22 EquipmentControl:Knowledgeoflimiting3.416 conditions

for operations

and safety limits.039Mainand

Reheat Steam X A4.01 Ability to manually operate and/or monitorinthe2.917controlroom:MainSteam

supply valves059Main Feedwater X A3.02 Ability to monitor automatic operationoftheMFW,2.918 including:

ProgrammedlevelsoftheS/G059Main Feedwater X K3.03 Knowledgeofthe effectthatalossor

malfunction3.519oftheMFWwillhaveonthefollowing:S/GS

061 Auxiliary/Emergency

X 2.2.22 Equipment Control: Knowledgeoflimiting3.420 Feedwater conditions

for operations

and safety limits.NUREG-1021

8

ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlinePlantSystems-Tier2Group1

IISystem#/Name

Number IKIATopics I Imp.L:9!JKnowledgeofthe

operational

implicationsofthe 061 Auxiliary/Emergency

X K5.01followingconceptsastheyapplytotheAFW:3.621 Feedwater RelationshipbetweenAFWflowandRCSheat

transfer Abilitytopredictand/or

monitorchangesin parameters(topreventexceedingdesignlimits)062ACElectricalDistribution

X A1.03 associatedwithoperatingtheACdistribution2.522systemcontrolsincluding:Effecton

instrumentationandcontrolsofswitchingpower

suppliesKnowledgeoftheeffectthatalossor

malfunction063DCElectricalDistribution

X K3.02oftheDC electricalsystemwillhaveonthe3.523 following:

ComponentsusingDCcontrolpowerKnowledgeofED/Gsystemdesign

feature(s)

064 Emergency Diesel Generator X K4.04 and/or interlock(s)whichprovideforthefollowing:

3.1 24Overloadratings

Ability to manuallyoperateand/or

monitorinthe073ProcessRadiationMonitoring

X A4.02controlroom:Radiation

monitoringsystemcontrol3.725 panel Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsontheSWS;and(b)076Service

Water X A2.01basedonthosepredictions,use

proceduresto3.526correct,control,ormitigatethe

consequences

of those malfunctionsoroperations:LossofSWS

ConductofOperations:Knowledgeofthe

078 Instrument

Air X2.1.28purposeandfunctionofmajorsystem3.327 componentsandcontrols.

Ability to predict and/or monitorchangesin parameters(topreventexceedingdesignlimits)

103 Containment

X A1.01 associatedwithoperatingthe

containmentsystem3.728controlsincluding:

Containment

pressure, temperature, and humidity KIA CategoryPointTotals:3/33133323

2/232GroupPointTotal:

I 28/5 NUREG-1021

9

ES-401Harris2008NRCFormES-401

-2 Written Examination

OutlinePlantSystems-Tier2Group

2 Imp.002 Reactor Coolant X 2.2.22 EquipmentControl:Knowledgeoflimiting

4.1 9 1 conditions

for operationsandsafetylimits

.Abilityto(a)predicttheimpactsofthefollowing

malfunctionsoroperationsontheNIS;and(bbasedonthosepredictions,use

procedures

to 015 Nuclear Instrumentation

X A2.02correct,control,ormitigatethe

consequences

of 3.5 92 those malfunctions

or operations

Faultyorerraticoperationofdetectorsor

compensating

components

Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsontheNNIS;and(b

016 Non-nuclear

Instrumentation

X A2.03basedonthosepredictions,use

procedures

to 3.3 93correct,control,ormitigatethe

consequences

of those malfunctionsoroperations:Interruptionoftransmittedsignal001ControlRodDrive

X A3.04 Ability to monitor automaticoperationofthe

3.5 29CRDS,including:RadialimbalanceAbilityto(a)

predicttheimpactsofthefollow

ing malfunctions

or operationsontheRCS;and(b)

002 Reactor Coolant X A2.02basedonthosepredict

ions, use procedures

to4.230correct,control,ormitigatethe

consequences

of those malfunctions

or operations

Lossofcoolant

pressure 011 PressurizerLevelControl

X K2.01Knowledgeofbuspowersuppliestothefollowing:3.131 Charg ing Pumps 016 Non-nuclear

Instrumentation

X K3.03Knowledgeoftheeffectthatalossor

malfunction3.032oftheNNISwillhaveonthefollow

ing: SDSKnowledgeoftheeffectofalossor

malfunction

of017In-core

Temperature

Monitor X K6.01thefollowingITMsystem

components

Sensors2.7

33 and detectorsKnowledgeofthephysical

connections

and/or041SteamDump

XK1.05cause-effect relationshipsbetweentheSDSand3.534thefollowingsystems:RCS

029 Containment

Purge X A4.04Abilityto manuallyoperateand/or

monitorInthe 3.5 35controlroom:

ContainmentEvacuationS

ignal ConductofOperations:Knowledgeofsystem034FuelHandling

Equipment X 2.1.14statuscriteriawhichrequirethe

notificat ionof2.5 36plantpersonnel.

NUREG-1021

10

ES-401Harris2008NRC

Written Examination

OutlinePlantSystems-

Tier2Group2 Form ES-401-2 System#/Name G K1 K2K3K4 K5 K6A1A2A3 A4 Number KIA Topics Imp.Q#Knowledgeoftheoperat

ional implicationsofthefollowingconceptsastheapplytotheMT/G045MainTurbine

Generator X K5.23 System: Relationshipbetweenrodcontroland2.737RCSboronconcentrationduringT/Gload

increases Abilityto(a)predicttheimpactsofthefollowing

malfunctionsoroperationsonthe

CondensateSystem;and(b)basedonthosepredictions,use

056 Condensate

System X A2.12 procedurestocorrect,control,orm

itigatethe2.8 38 consequencesofthose malfunctions

or operations

Openingoftheheaterstringbypass

valve KIA Category Po int Totals:1/111 1 0110 2/211GroupPointTotal:

I 1013 NUREG-1021 11

I ES-401 Generic Knowledge and Abilities Outline (Tier3)Facility: IHarris2008NRCOutline

IDateofExam

I 3/10108 RO SRO-Only Category KIA#Topic IR Q#IR Q#2.1.34 Abilitytomaintainprimaryand

secondary plant2.994 chemist rywithinallowablelimits.

2.1.20 Ability to executeproceduresteps

.4.295 1.2.1.3Knowledgeofshift

turnover practices.

3.0 66 Conduct of Operations

2.1.32 Abilitytoexplainandapplyallsystemlimitsand

3.4 67 precautions

.Subtotal 2 2 2.2.28 Knowledgeo fnewan d spent fuel movement3.596 procedures.

'2.2.22Knowledgeoflimiting

conditions

for operations

and 4.1 97 safe ty lim its.2.Equipment Control 2.2.26Knowledgeofrefueling

administrative

requirements

.2.5 68 2.2.12Knowledgeof

surveillance

procedures

.3.0 69 Subtotal 2 2 2.3.6 Knowledgeoftherequirementsforreviewingan

d 3.1 98 approving release permits.Knowledgeofrad iationexposurelimitsand

3.2.3.4 contaminationcontrol,includingperm

issible levels in2.570 Rad iation Controlexcessofthoseauthorized.2.3.2Knowledgeoffacility

ALARA program.2.571 Subtotal 2 1 Abilitytoperformw

ithoutreferenceto

procedures

2.4.49thoseactionsthatrequire

immediateoperationof4.099 s ystem com ponentsandcontrols.

2.4.41 Knowledgeofthe emergency act ion level thresholds

4.1 100 and classifications.

4.2.4.10 Knowledge of annunciator

response procedures.

3.0 72 Emergency Procedures2.4.6Knowledge

symptombasedEOPm itigation strategies.3.173 1 Plan Ability to interpretcontrolroom

indicationstover

ify the 2.4.48statusandoperationofsystem

, and understand

how3.574 operator actions and directivesaffectplantandsystem

conditions.

2.4.29 Knowledgeofthe emergency plan.2.675 Subtotal 4 2 Tier3PointTotal

10 7 NUREG-1021

12

ES-401RecordofRejectedKlAsHarrisNRC 3/10/08 Form ES-401-4 Tier/Randomly Reason for Rejection Group Selected KIA 1/1 056 G2.4.30 KIA<2.5 for RO.Randomlyreplacedwith056G2.1.2.

2/2002K4.09Plantdesign-noloop

isolation valves.Randomlyreplacedwith002A2.02.

2/1 078 G2.2.22NoTSforthis

system.Randomlyreplacedwith078G2

.1.28.2/1061K2.03 Plant design-no diesel-drivenAFWPump.Randomlyreplacedwith061

K5.01.2/1006K4.22 No design feature or interlockrelatedto these components

.Randomly reselected006K4.05 2/1 022 A1.03 No designlimitor procedurally

directedactionrelatedto

containment

humidity.Randomly selected022A1.01 2/2027K1.01 No relationship

between systemsatfacility.No

other027K1topicsavailable.

Randomly reselected041K1.05 to replace Too difficult to develop an operationally

relevanttestitemfortopic,andfacility

1/1 038 EK1.04hasno reference materialrelatedto topic to support any discussionofthe topic.Randomly selected 038 EK1.03 2/1 073 G2.4.49 No immediate actions requiredrelatedto system.Randomly selected 073 G2.1.32 2/1005K1.10Nophysical

connection

between systems selected.Randomlyselected005

K5.11 2/1010K2.04 Facilitydoesnothave

indicator requiring standard power supply.Randomly selected010K2.01 2/2011K2.02 Duplicate topicwith010K2.01.Randomly selected011K2.01.1/1 E04 G2.1.33 No operational

validity at facility.E04EA1.3 randomly selectedbyCEas replacement.

2/1078A2.01 UnabletowriteSRO-Level questiontothisKA.RequestednewKA.008 A2.01 randomly selectedbyCEas replacement.

3 G2.2.7 Too difficult to develop operationally

relevant test item, facility requested new KA.G2.2.28 randomly selectedbyCEas reolacement.

1/1 026 G2.1.27 Topicresultedin

questions too similartoKA008A2.01, requestednewKA.057G2.1.7 randornlv selectedbvCEas reolacement.

NUREG-1021

13