ML082200233

March 05000400-08-301 Exam Final Outlines

ML082200233
Person / Time
Site:	Harris
Issue date:	08/07/2008
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To:	NRC/RGN-II
References
50-400/08-301
Download: ML082200233 (19)

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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