ML082200166

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March 05000400-08-301 Exam Draft ES-401-6 Checklist & Sample Plan
ML082200166
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/07/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
50-400/08-301
Download: ML082200166 (15)


See also: IR 05000400/2008301

Text

Draft Submittal(PinkPaper)

DRAFTWrittenExamQualityChecklist (ES-401-6)

&WrittenExam

Sample Plan II ri££/S,;=X/i-M{):;-(.nrD L./t70?008 c1 0/

d{)o8

ES-401FormES-401-6

Facility: HarrisDateofExam:

3/10/2008 Exam RO/SRO Level: Initial Item Description

a b*C#1.Questions and answers technically

accurate and applicabletofacilitv.2.a.NRCKJAs referencedforall questions.

<J"bc<l b.Facilitv learninq objectives

referenced

as available.

3.SRO questions are appropriate

in accordancewithSectionD.2.dofES-401

VJ.,{4.The sampling process was random and systematic.(Ifmorethan4ROand2SRO

questions were repeatedfromthelast2NRC

licensing exams, consulttheNRROL eJM Proqram Office)5.Question duplicationfromthe license screening/auditexamwas controlled

as indicated below (checktheitemthat

applies)and appears appropriate:

---the audit exam was systematically

and randomly developed, or OM the audit exam was completed before the licenseexamwas started, or------the examinations

were developed independently, orthe licensee certifies that thereisno duplication, or other (explain)6.Bank use meets limits(nomorethan75

percent Bank Modified Newfromthe bankatleast10 percentnew,andtherest

GW{new or modified);

entertheactualRO/

SRO-only 31/9 13/10 31/6 question distribution(s)atriqht, 7.Between50and60 percentofthe questiononthe Memory CIAROexamare writtenatthe comprehension!

<JPt4 analysislevel;theSROexammay

exceed 60 33/4 42/21 percentifthe randomly selected KJAs support the higher cognitive levels;entertheactualRO/SRO

question distributiorus)atriqht 8.References/handouts

provideddonotgiveaway

answersoraidinthe

elimination

of Jl,.4 distractors.

9.Question content conforms with specific KJA statementsinthe previously

approved examination

outlineandis appropriateforthe tiertowhich they are assigned;deviations

are iustified.

10.Question psychometric

quality and format meet the guidelinesinES Appendix B.WAIf I I 11.The exam contains the required number of one-point, multiple choiceitems;the OM 1totalis correct and aarees with valueoncoversheet.

I Printed Name/

Date a.Author Joseph G.Arsenault LW 1/4108 b.Facility Reviewer (*)(/I , c.NRC Chief Examiner (#)d.NRC Regional Supervisor

Note:*The facility reviewer's

initials/signaturearenot applicable

for NRC-developed

examinations.

  1. Independent

NRC reviewerinitialitemsinColumn"c";

chief examiner concurrence

reauired.DRAFT NUREG-1021,Revision9

ES-401 PWR Examination

Outline Form ES-401-2 I(\(Facility:Harris2008NRCOutlineDateofExam:3/10/08ROKIACategoryPoints

SRO-Only PointsTierGroupKKKK KKAAAAG TotalA2G*Total1234 5 61234*1.1333 3 3 3 18 3 3 6 Emergency&Abnormal 222111 2 9 224 Plant EvolutionsTier554445275510 Totals 2.Plant 1313332323 2 3 28 235 Systems 2111 01102111100213 Tier4243 4334 434384 4 8 Totals 3.Generic KnowledgeandAbilities1

2 3 4 10 123 4 7 Categories

2 2 2 4221 2Note:1.EnsurethatatleasttwotopicsfromeveryapplicableKIAcategoryaresampledwithineachtieroftheROandSRO-onlyoutlines(i.e.,exceptforonecategoryinTier3ofthe

SRO-only outline, the"TierTotals"ineachKIAcategoryshallnotbelessthantwo).

2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthatspecifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby+/-1fromthatspecifiedinthetablebasedonNRCrevisions.ThefinalROexammusttotal75pointsandthe

SRO-only exammusttotal25points.

3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;

systems or evolutionsthatdonotapplyatthefacilityshouldbedeletedandjustified;

operationally

important, site-specificsystemsthatarenotincludedontheoutlineshouldbeadded.RefertoES-401, Attachment2,for guidanceregardingeliminationof

inappropriateKIAstatements.

4.Selecttopicsfromasmanysystemsandevolutionsaspossible;sampleeverysystemorevolutioninthegroupbeforeselectingasecondtopicforanysystemorevolution.

5.Absentaplantspecificpriority,onlythoseKAshavingan

importancerating(IR)of2.5orhighershallbeselected.UsetheROandSROratingsfortheROand

SRO-onlyportions,respectively.

6.SelectSROtopicsforTiers1and2fromtheshadedsystemsandKIAcategories.7.*Thegeneric(G)KlAsinTiers1and2shallbeselectedfromSection2oftheKIACatalog,butthetopicsmustberelevanttotheapplicableevolutionorsystem.

8.Onthefollowingpages, entertheKIAnumbers,abriefdescriptionofeachtopic,thetopics'

importanceratings(IRs)fortheapplicablelicenselevel,andthepointtotals(#)foreachsystemandcategory.Enterthegroupandtiertotalsforeachcategoryinthetableabove;iffuelhandling

equipmentissampledin

otherthanCategoryA2orG*ontheSRO-onlyexam,enteritontheleftsideofColumnA2for

Tier2,Group2(Note#1doesnotapply).UseduplicatepagesforROandSRO-onlyexams.

9.ForTier3,selecttopicsfromSection2oftheKIACatalog,andentertheKIAnumbers, descriptions,IRs,andpointtotals(#)onFormES-401-3.LimitSRO

selectionstoKlAsthatarelinkedto 10CFR55.43

(NUREG-1021

D D ,A.IT'""""" 1 D.\J.(Hi"" i HARRIS 2008 NRC 401-2 SUBMITTAL

ESA01 ,,-,,, Harris 2008 NRCWrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group1

Form ES-401-2E/APE#INameSafetyFunction

I G I K1 I K2 I K3 I A1 I A2 I Number IKIATopic(s)

I Imp.[§!J Ability to determine and interpretthefollowingastheyapplytotheLossof

ResidualHeatRemoval025/LossofResidualHeatRemovalSystem

/4 X AA2,02 System: LeakageofreactorcoolantfromRHRinto

3,8 76closedcoolingwatersystemorintoreactorbuilding

atmosphere026/Lossof

ComponentCoolingWater/8

X 2.1.27 Conduct of Operations:Knowledgeofsystem

2.9 77purposeandorfunction, Conduct of Operations:Knowledgeofsystemstatus038/Steam GeneratorTubeRupture/3

X 2.1,14criteriawhichrequirethenotificationofplant

3,3 78 personnel.

Ability to determine and interpretthefollowingas040/SteamLineRupture

/4 X AA2.05theyapplytotheSteamLineRupture:When

4,5 79 ESFAS systemsmaybesecured

Conduct of Operations:AbilitytorecognizeE04/LOCAOutside

Containment/3 X 2.1,33 indicationsforsystemoperating

parameters

which 4.0 80 are entry-levelconditionsfor

technical specifications.

Ability to determine and interpretthefollowingastheyapplytothe(Lossof

Emergency CoolantE11/Lossof

Emergency Coolant Recirculation

/4 X EA2.2 Recirculation):

Adherence to appropriate4.281 proceduresandoperationwithinthelimitationsinthefacility'slicenseand

amendments.

Conduct of Operations:Abilitytoperformspecific007/ReactorTrip/1

X 2.1.23systemand integrated

plant proceduresduringall 3,9 39modesofplantoperation.Knowledgeofthe

interrelationsbetweenthe

008/Pressurizer

Vapor Space Accident/3 X AK2.03 Pressurizer

Vapor Space Accidentandthe 2,5 40 following:

Controllers

and positioners009/SmallBreakLOCA/3

X EK2.03 Knowledgeofthe interrelationsbetweenthesmall

3.0 41breakLOCAandthefollowing:S/Gs

Abilitytooperateand

monitorthefollowingasthey011/LargeBreakLOCA/3

X EA1,15applytoaLargeBreakLOCA:RCS

temperature4.242 and pressure Knowledgeofthe operational

implicationsofthe following conceptsastheyapplytotheReactor

015/17/ReactorCoolantPump

Malfunctions

/4 X AK1.05CoolantPump

Malfunctions(LossofRCFlow):

2,7 43Effectsof unbalancedRCSflowonin-coreaverage

temperature,coreimbalance,andquadrantpower

tilt NUREG-1021

2 HARRIS 2008 NRC 401-2 SUBMITTAL

ES-401 Harris 2008 NRC Form ES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlant

Evolutions-Tier1Group1E/APE#INameSafetyFunction

I G I K1 I K2 I K3 IA1 I A2 I Number IKIATopic(s)

I Imp.l§!J Conduct of Operations:Knowledgeofthepurpose022/LossofReactor

Coolant Makeup/2 X2.1.28andfunctionofmajorsystem

components

and 3.2 44 controls.Abilitytooperate and/or monitorthefollowingas025/LossofResidualHeatRemovalSystem

/4 X AA1.20 theyapplytotheLossofResidualHeatRemoval2.645System:HPIpumpcontrolswitch,indicators, ammeterrunninglights,andflowmeter

Abilitytooperateand/or

monitorthefollowingas

027/Pressurizer

PressureControlSystem

Malfunction

X AA1.03theyapplytothe

PressurizerPressureControl

3.6 46/3 Malfunctions:

Pressurecontrolwhenonasteam

bubble Ability to determine or interpretthefollowingasthey029/Anticipated

Transient WithoutScram(ATWS)/1

XEA2.05applytoaATWS:System

componentvalveposition

3.4 47 indications

Knowledgeofthe operational

implicationsofthe 038/Steam GeneratorTubeRupture/3

X EK1.03 following conceptsastheyapplytotheSGTR:

3,9 48 Natural Circulation

Knowledgeofthe operational

implicationsofthe 040/SteamLineRupture/4

X AK1.07 following conceptsastheyapplytoSteamLine3.449Rupture:Effectsof

feedwaterintroductionondry

S/G Ability to determine and interpretthefollowingas054/LossofMain

Feedwater/4 X AA2.04theyapplytotheLossofMain

Feedwater (MFW): 4.2 50 ProperoperationofAFWpumpsandregulating

valves056/LossofOff-sitePower/6

X 2.1,2 Conduct of Operations:Knowledgeof

operator 3.0 51 responsibilitiesduringallmodesofplantoperation.

Knowledgeofthereasonsforthefollowing058/LossofDC

Power/6 X AK3.02 responses as theyapplytotheLossofDCPower:4.052 Actionscontainedin

EOPforlossofDCpower

Knowledgeofthereasonsforthefollowing

responsesastheyapplytotheLossof

Nuclear062/Lossof

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

3.6 53withinthe nuclear service waterresultingfromthe

actuationoftheESFAS

NUREG-1021

3 HARRIS 2008 NRC 401-2 SUBMITTAL

..,.---..",!.-.--.......

..c" ES-401 Harris 2008 NRC Form ES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlant

Evolutions-Tier1Group1

!E/APE#INameSafetyFunction

I G I K1 I K2 I K3 IA1 I A2 I Number IKIATopic(s)

I Imp.I Q#i Knowledgeofthe interrelationsbetweenthe(LOCA

Outside Containment)andthefollowing:

Facility'sheatremovalsystems, includingprimarycoolant,E04/LOCAOutside

Containment/3 X EK2.2 emergencycoolant,the

decayheatremoval3.854systems,andrelationsbetweentheproperoperationofthese

systemstotheoperationofthe

facility.Knowledgeofthereasonsforthefollowing

responsesastheyapplytothe(Lossof

SecondaryE05/Lossof

SecondaryHeatSink/4

X EA2.2HeatSink):

Adherence to appropriate

procedures3.755 and operationwithinthe limitationsinthefacility'slicenseand

amendments.

Knowledgeofthereasonsforthefollowing

responsesastheyapplytothe(Lossof

EmergencyE11/Lossof

Emergency Coolant Recirculation

/4 X EK3.3 Coolant Recirculation):

Manipulationofcontrols3.856requiredtoobtain

desiredoperatingresultsduring

abnormal and emergency situations.

KIA CategoryPointTotals:

3/333333/3GroupPointTotal:

I 18/6 NUREG-1021

4 HARRIS 2008 NRC 401-2 SUBMITTAL

/--"\ES-401 Harris 2008 NRC Form ES-401-2WrittenExaminationOutlineEmergencyandAbnormalPlant

Evolutions-Tier1Group2E/APE#INameSafety

Function I G I K1 I K2 I K3 I A1 I A2 I Number IKIATopic(s)

I Imp.I Q#i Emergency Procedures/Plan:Abilitytoverifysystem

005/Inoperable/StuckControlRod/1

X 2.4.50 alarm setpointsandoperatecontrolsidentifiedinthe3.382alarmresponsemanual.

Ability to determine and interpret the following as068/ControlRoomEvacuation/8

X AA2.10theyapplytotheControlRoomEvacuation:Source

4.4 83rangecountrate

E06/DegradedCoreCooling

/4 X 2.1.2 Conduct of Operations:

Knowledge of operator4.084 responsibilitiesduringallmodesofplantoperation.

Ability to determine and interpretthefollowingasE10/Natural

CirculationwithSteamVoidinVesseltheyapplytothe(Natural

CirculationwithSteam with/withoutRVLlS/4 X EA2.1VoidinVessel

with/withoutRVLlS):Facility

3.9 85 conditionsandselectionof

appropriate

procedures

during abnormal and emergency operations.

Knowledgeofthe operational

implicationsofthe003/DroppedControlRod/1

X AK1.11 following conceptsastheyapplytoDroppedControl

2.5 57 Rod: Long-rangeeffectsofcore

quadrantpowertilt Knowledgeofthe interrelationsbetweenthe024/EmergencyBoration/1

X AK2.03 EmergencyBorationandthefollowing:

Controllers

2.6 58 and positionersKnowledgeofthereasonsforthefollowing

033/Lossof Intermediate

Range Nuclear responsesastheyapplytotheLossof

Intermediate

X AK3.02 Range Nuclear Instrumentation:

Guidance 3.6 59 Instrumentation

/7 containedinEOPforlossof

intermediate

range instrumentation

Ability to determine and interpretthefollowingas036/FuelHandlingIncidents/8

XAA2.01theyapplytotheFuel

HandlingIncidents:ARM

3.2 60 system indications

Emergency Procedures/Plan:

Abilitytoverifysystem059/AccidentalLiquidRadWasteRelease/9

X 2.4.50 alarm setpoints and operatecontrolsidentifiedinthe3.361alarmresponsemanual.060/Accidental

GaseousRadWasteRelease/9

X 2.1.32 Conduct of Operations:

Abilitytoexplainandapply

3.4 62allsystemlimitsand

precautions.Knowledgeofthe

interrelationsbetweentheLossof

069/Lossof Containment

Integrity/5 X AK2.03 ContainmentIntegrityandthefollowing:

Personnel2.863accesshatchand

emergencyaccesshatchKnowledgeofthe

operational

implicationsofthe 074/InadequateCoreCooling

/4 X EK1.06 following conceptsastheyapplytothe

Inadequate3.064CoreCooling:Definitionof

superheated

steam NUREG-1021

5 HARRIS 2008 NRC 401-2 SUBMITTAL

r>ES-401Harris 2008 NRCWrittenExaminationOutlineEmergencyandAbnormalPlantEvolutions-Tier1Group2

/'-',,-Form ES-401-2 II E/APE#I NameSafetyFunction

I G I K1 I K2 I K3 IA1 I A2 I Number IKIATopic(s)

I Imp.@!J Abilitytooperateand/or

monitorthefollowingas

E10/NaturalCirculationwithSteamVoidinVesseltheyapplytothe(NaturalCirculationwithSteam

X EAUVoidinVessel

with/withoutRVLlS):Desired

3.4 65 with/withoutRVLlS/4operatingresultsduringabnormaland

emergency situations.KiACategoryPointTotal:

2/222111/2GroupPointTotal:

I 9/4 NUREG-1021

6 HARRIS 2008 NRC 401-2 SUBMITTAL

(/,,-,,\ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlinePlantSystems-Tier2Group1System#/Name

[G]K1 I K2 I K3 I K4 I K5 I K6 I A1 I A2 I A3 I A4 I Number IKIATopics I Imp.I Q#i Conduct of Operations:

Ability to recognize 006 EmergencyCoreCooling

X 2.1.33 indicationsforsystem operating parameters

which 4.0 86 are entry-level

conditions

for technical specifications.

Abilityto(a)predictthe

impactsofthefollowing

malfunctions

or operationsontheRPS;and(b)

012 Reactor Protection

X A2.04basedonthose

predictions, use procedures

to 3.2 87correct,control,or

mitigate the consequences

of those malfunctionsoroperations:

Erratic powersupplyoperation

Emergency Procedures/Plan:Knowledgeof

026 Containment

Spray X 2.4.31 annunciators,alarmsandindications,anduseof3.488theresponse

instructions.

073 Process Radiation Monitoring

X 2.1.32Conductof Operations:

Abilitytoexplainand

3.8 89applyallsystemlimitsand

precautions.Abilityto(a)predictthe

impactsofthefollowing

malfunctions

or operationsonthelAS;and(b)

078 Instrument

Air X A2.01basedonthose

predictions, use procedures

to 2.9 90correct,control,or

mitigate the consequences

of those malfunctions

or operations:Airdryerand

filter malfunctions.Knowledgeofthe

operational

implicationsofthe following conceptsastheyapplytotheRCPS:

003 Reactor Coolant Pump XK5.03EffectsofRCPshutdownonTave,includingthe

3.1 1reasonforthe

unreliabilityofTaveintheshutdown

loop 004 Chemical and VolumeKnowledgeofthe

operational

implicationsofthe XK5.19followingconceptsastheyapplytotheCVCS:

3.5 2 ControlConceptofSOMKnowledgeofthephysical

connections

and/or005ResidualHeatRemoval

X K1.11 cause-effect

relationshipsbetweentheRHRSand

3.5 3thefollowingsystems:

RWSTKnowledgeofthe

effectofalossor malfunction

005 Residual Heat Removal XK6.03onthefollowingwillhaveontheRHRS:RHRheat2.5

4 exchangerKnowledgeofthe

physical connections

and/or 006 EmergencyCoreCooling

XK1.08causeeffect

relationshipsbetweentheECCSand3.6

5thefollowingsystems:CVCSKnowledgeofECCSdesignfeature(s)and/or

006 EmergencyCoreCooling

X K4.05 interlock(s)

which provideforthefollowing:Auto4.36startof HPI/LPI/SIP

NUREG-1021

7HARRIS2008NRC401-2

SUBMITI AL

,"'-"'" ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlinePlantSystems-Tier2Group1

!System#/Name

I G I K1 I K2 I K3 IK4,K5 I K6 I A1 I A2 I A3 I A4 I Number IKIATopics I Imp.I Q#i 007 Pressurizer

Relief/QuenchKnowledgeofPRTSdesign

feature(s)

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

which provideforthefollowing:2.67Quenchtankcooling

Abilityto(a)predictthe

impactsofthefollowing

malfunctions

or operationsontheCCWS,and(b)basedonthose

predictions, use procedures

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

mitigate the consequences

of2.58 those malfunctions

or operations:Effectsof shutting (automatically

or otherwise)theisolationvalvesoftheletdown

cooler 010 Pressurizer

Pressure Control X K2.01Knowledgeofbuspower

suppliestothefollowing:3.09 Pressurizer

HeatersKnowledgeoftheeffectofalossor

malfunction

of 012 Reactor Protection

XK6.03thefollowingwillhaveontheRPS:Triplogic3.110 circuits 012 Reactor Protection

X A3.02 Ability to monitor automatic operationoftheRPS, 3.6 11including:Bistables

013 Engineered

Safety FeaturesKnowledgeoftheeffectthatalossor

malfunction

XK3.03oftheESFASwillhaveonthefollowing:4.312 Actuation Containment

Abilitytopredict and/or monitorchangesin 022 Containment

Cooling X A1.01 parameters (to prevent exceedingdesignlimits)

3.6 13 associated

with operatingtheCCScontrols

including:

Containment

temperatureKnowledgeofthephysical

connections

and/or 022 Containment

Cooling X K1.01 cause-effect

relationshipsbetweentheCCSand3.5

14thefollowing

systems: SWS/cooling

system Ability to monitor automaticoperationoftheCSS, 026 Containment

Spray XA3.01including:Pumpstartsand

correct MOV 4.3 15 positioning

026 Containment

Spray X 2.2.22 Equipment Control: Knowledgeoflimiting3.416 conditions

for operations

and safety limits.039MainandReheatSteam

X A4.01 Ability to manually operate and/or monitorinthe2.917controlroom:MainSteamsupplyvalves059Main Feedwater X A3.02 Ability to monitor automaticoperationoftheMFW, 2.9 18 including:

ProgrammedlevelsoftheS/G059Main Feedwater X K3.03Knowledgeofthe

effectthatalossor

malfunction3.519oftheMFWwillhaveonthefollowing:S/GS

NUREG-1021

8HARRIS2008NRC401-2

SUBMITIAL

!ES-401Harris2008NRCFormES-401-2WrittenExaminationOutlinePlantSystems-Tier2Group1

!System#/Name

I G I K1 I K2 Li§J K4 I K5 I KG I A1 I A2 I A3 I A4 I Number I KIA Topics I Imp.I Q#i 061 Auxiliary/Emergency

X 2.2.22 Equipment Control: Knowledgeoflimiting

3.4 20 Feedwater conditions

for operations

and safety limits.Knowledgeofthe operational

implicationsofthe 061 Auxiliary/Emergency

X K5.01 following conceptsastheyapplytotheAFW:

3.6 21 Feedwater Relationship

between AFWflowandRCSheat

transfer Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)062AC Electrical

Distribution

X A1.03 associated

with operatingtheAC distribution

2.5 22systemcontrols

including:

Effect on instrumentation

and controls of switching power supplies Knowledgeofthe effect thatalossor malfunction063DC Electrical

Distribution

X K3.02oftheDC electricalsystemwillhaveonthe

3.5 23 following:

ComponentsusingDCcontrol

power KnowledgeofED/G system design feature(s)

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

which provideforthe following:3.124 Overload ratings Ability to manually operate and/or monitorinthe 073 Process Radiation Monitoring

X A4.02controlroom:

Radiation monitoringsystemcontrol3.725 panel Abilityto(a)predict the impactsofthe following malfunctions

or operationsontheSWS;and(b)

076 Service Water XA2.01basedonthose

predictions, use procedures

to3.526correct,control,or

mitigate the consequences

of those malfunctions

or operations:LossofSWS Conduct of Operations:

Knowledgeofthe 078 Instrument

Air X2.1.28purposeand

function of major system3.327 componentsandcontrols.

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)103 Containment

X A1.01 associated

with operating the containment

system 3.7 28 controls including:

Containment

pressure, temperature, and humidity KIA CategoryPointTotals:3/33133323 2/232GroupPointTotal:

I 28/5 NUREG-1021

9HARRIS2008NRC401-2SUBMITTAL

r--., (ES-401Harris2008NRC

Form ES-401-2 Written Examination

OutlinePlantSystems-Tier2Group2System#/NameKIATopics 002 Reactor Coolant X 2.2.22 EquipmentControl:Knowledgeoflimiting

4.1 91 conditionsforoperationsandsafetylimits.

Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsontheNIS;and(bbasedonthose

predictions, use procedures

to 015 Nuclear Instrumentation

X A2.02correct,control,ormitigatethe

consequences

of 3.5 92 those malfunctions

or operations:Faultyorerraticoperationof

detectors or compensating

components

Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsontheNNIS;and(b

016 Non-nuclear

Instrumentation

X A2.03basedonthose

predictions, use procedures

to 3.3 93correct,control,ormitigatethe

consequences

of those malfunctionsoroperations:

Interruption

of transmitted

signal001ControlRodDrive

X A3.04 Ability to monitor automaticoperationofthe

3.5 29CROS,including:Radial

imbalance Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsontheRCS;and(b)

002 Reactor Coolant X A2.02basedonthosepredictions,use

procedures

to 4.2 30correct,control,ormitigatethe

consequences

of those malfunctionsoroperations:Lossofcoolant

pressure 011 PressurizerLevelControl

X K2.02Knowledgeofbuspower

suppliestothefollowing:

3.1 31PZRheaters

016 Non-nuclear

Instrumentation

X K3.03Knowledgeoftheeffectthatalossor

malfunction

3.0 32oftheNNISwillhaveonthefollowing:SOSKnowledgeoftheeffectofalossor

malfunction

of017In-core

Temperature

Monitor X K6.01thefollowing

ITM system components:

Sensors2.733anddetectorsKnowledgeofthephysical

connections

and/or041SteamDump

X K1.05 cause-effect

relationshipsbetweentheSOSand

3.5 34thefollowingsystems:RCS

029 Containment

Purge X A4.01 Ability to manuallyoperateand/or

monitorinthe2.535controlroom:

ContainmentPurgeflowrateConductofOperations:

Knowledgeofsystem034Fuel Handling Equipment X 2.1.14statuscriteriawhichrequirethe

notificationof2.5 36plantpersonnel.

NUREG-1021

10HARRIS2008NRC

401-2 SUBMITI AL

(ES-401Harris2008NRC

Written Examination

OutlinePlantSystems-Tier2Group2FormES-401-2

System#/Name G K1 K2K3K4K5K6A1A2A3

A4 NumberKIATopics Imp.Q#Knowledgeofthe

operational

implicationsofthefollowingconceptsastheapplytotheMT/G045Main Turbine Generator X K5.23 System: Relationshipbetweenrodcontroland

2.7 37RCSboron concentrationduringT/Gload

increases Abilityto(a)predicttheimpactsofthefollowing

malfunctions

or operationsonthe CondensateSystem;and(b)basedonthose

predictions, use 056 Condensate

System X A2.12 procedurestocorrect,control,ormitigatethe2.838 consequencesofthose malfunctions

oroperations:Openingoftheheaterstringbypass

valve KIA CategoryPointTotals:1/11110 1102/211GroupPointTotal:

I 10/3 NUREG-1021

11HARRIS2008NRC401-2

SUBMITTAL

I ES-401GenericKnowledgeandAbilitiesOutline(Tier3)

IFormES-401-3

I ((Facility: IHarris2008NRCOutline

IDateofExam:

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

secondary plant 2.9 94 chemistrywithinallowablelimits.2.1.20Abilitytoexecuteproceduresteps.

4.2 95 1.2.1.3Knowledgeofshift

turnover practices.3.066 Conduct of Operations

2.1.32Abilitytoexplainandapplyallsystemlimitsand3.467 precautions.

Subtotal 2 2Knowledgeoftheprocessforconductingtestsor

2.2.7 experimentsnotdescribedinthesafetyanalysis

3.2 96 report.2.2.22Knowledgeoflimitingconditionsforoperationsand*

4.1 97safetylimits.

2.Equipment Control2.2.26Knowledgeofrefuelingadministrativerequirements.2.5

682.2.12Knowledgeof

surveillance

procedures.3.069 Subtotal 2 2 2.3.6Knowledgeofthe

requirementsforreviewingand3.198approvinqreleasepermits.Knowledgeofradiationexposurelimitsand

3.2.3.4 contaminationcontrol,including

permissiblelevelsin2.5

70 Radiation Controlexcessofthoseauthorized.2.3.2KnowledgeoffacilityALARAprogram.

2.5 71 Subtotal 2 1Abilitytoperformwithoutreferencetoprocedures2.4.49thoseactionsthatrequireimmediateoperationof

4.0 99 system componentsandcontrols.

2.4.41Knowledgeofthe

emergencyactionlevel

thresholds4.1100 and classifications.

4.2.4.10Knowledgeof

annunciatorresponseprocedures.3.072 Emergency Procedures

2.4.6KnowledgesymptombasedEOPmitigationstrategies.3.173 1 PlanAbilityto interpretcontrolroomindicationstoverifythe

2.4.48statusandoperationofsystem,andunderstandhow

3.5 74 operatoractionsand

directivesaffectplantandsystem

conditions.

2.4.29Knowledgeofthe

emergency plan.2.675 Subtotal 4 2 Tier3PointTotal

10 7 NUREG-1021

12HARRIS2008NRC401-2

SUBMITTAL

ES-401RecordofRejectedKlAsHarrisNRC3/10/08

Form ES-401-4 ((Tier/RandomlyReasonforRejection

Group Selected KIA1/1056 G2.4.30 KIA<2.5forRO.Randomlyreplacedwith056G2.1.2.2/2002K4.09Plantdesign-noloopisolationvalves.

Randomlyreplacedwith002A2.02.2/1078 G2.2.22NoTSforthissystem.Randomlyreplacedwith078G2.1.28.

2/1061K2.03Plantdesign-nodiesel-driven

AFWPump.Randomlyreplacedwith061

K5.01.2/1006K4.22Nodesignfeatureor

interlockrelatedtothesecomponents.

Randomly reselected006K4.052/1022 A1.03Nodesignlimitor

procedurallydirectedactionrelatedto

containment

humidity.Randomlyselected022A1.01

2/2027K1.01 No relationshipbetweensystemsatfacility.No

other027K1topicsavailable.

Randomlyreselected041K1.05toreplace

Too difficulttodevelopan

operationallyrelevanttestitemfortopic,andfacility1/1038EK1.04hasnoreferencematerialrelatedtotopictosupportany

discussionofthe topic.Randomlyselected038EK1.032/1073 G2.4.49 No immediateactionsrequiredrelatedtosystem.

Randomly selected 073 G2.1.322/1005K1.10Nophysicalconnectionbetween

systems selected.Randomly selected 005 K5.11 2/1010K2.04Facilitydoesnothave

indicatorrequiringstandardpowersupply.Randomly

selected010K2.012/2029 A4.04 No relationshipbetweenthesystemandtopicselected, whether by interlock or by operatoraction.Randomly

selected029A4.01 NUREG-1021

13 HARRIS2008NRC401-2

SUBMITTAL