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)


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