ML082200233
| ML082200233 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/07/2008 |
| From: | - No Known Affiliation |
| 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
,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
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
evacuation
in accordance
with AOP-004, REMOTE SHUTDOWN,Step38.NewJPM.
k.Terminate a WasteGasReleasein
accordancewithOP-120.07, WASTE GAS PROCESSING.
Randomlyselectedrepeatfrom2007NRCExam(JPMk).
,Revision9HARRIS2008NRC301-2,Revision2
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
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
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
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
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.
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.
13