ML080720506
| ML080720506 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/05/2008 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/08-301, 50-328/08-301 | |
| Download: ML080720506 (32) | |
See also: IR 05000328/2008301
Text
Final Submittal(BluePaper)
FINAL OUTLINES£5-1.j()/-cJ.-
SctyLltJyAI-f
02 CJD&-cl 0/
Printed:01/13/2008
SRO-Only Points A2G*Total 000 000000000 010000001234 00000 ES-401PWRExaminationOutline
Facility: SequoyahDateOfExam:01/28/2008ROKiA Category PointsTierGroup K1K2K3K4K5K6 A1A2A3A4G*Total1.133333318 Emergenc 2 1 2 112 2 9&N/A N/A Abnormal Tier Plant Totals 4 5 4 4 5 5 27 Evolutions
2.12233 322 3 2 3 3 28 Plant 2 1 1 111 1 1011 1 10 Systems Tier3344 4333 344 38 Totals 3.Generic Knowledge And1234 10 Abilities Categories3232 Note:---------------------------------------
Form ES-401-2 (1.EnsurethatatleasttwotopicsfromeveryKIAcategoryaresampledwithineach
tieroftheROand
SRO-only outlines(Le.,exceptforonecategoryinTier3ofthe
SRO-onlyoutline,the"Tier Totals"ineachKIA categoryshallnotbelessthantwo).2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthatspecifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby+/-1fromthatspecifiedinthetablebasedonNRC
revisions.ThefinalROexammusttotal75pointsandthe
SRO-only exammusttotal25points.
3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;systemsor
evolutions
thatdonot applyatthe facility should bedeletedand
justified;
operationally
important, site-specific
systemsthatarenotincludedontheoutlineshould
beadded.RefertoES-401, Attachment2,for guidanceregardingthe
elimination
of inappropriate
KIA statements.
4.Select topicsfromasmanysystemsandevolutionsaspossible;sampleeverysystemor
evolutioninthegroupbeforeselectingasecondtopic
foranysystemor
evolution.
5.Absent a plant-specificpriority,onlythoseKlAshavingan
importancerating(IR)
of2.5orhighershallbeselected.UsetheROandSROratingsfortheROandSRO-onlyportions,respectively.
6.SelectSROtopicsforTiers1and2fromtheshadedsystemsandKIA
categories.7.*The generic(G)KlAsinTiers1and2shallbeselectedfromSection2oftheKIACatalog,butthetopicsmust
berelevanttotheapplicable
evolutionorsystem.8.Onthefollowingpages,entertheKIAnumbers,abrief
descriptionofeachtopic,thetopics'
importanceratings(IRs)forthe
applicablelicenselevel,andthepointtotals(#)foreachsystem
and category.Enterthegroupandtiertotalsforeachcategoryinthetableabove;iffuelhandling
equipment is sampled in other than CategoryA2orGonthe
SRO-onlyexam,enteritontheleftsideofColumnA2forTier2,Group2(Note#1doesnotapply).Useduplicatepages
forROand SRO-onlyexams.
(9.ForTier3,selecttopicsfrom
Section 2 oftheKIAcatalog,andentertheKIA
numbers, descriptions,IRs,andpointtotals(#)onFormES-401-3.LimitSROselectionstoKlAsthatarelinkedto10CFR55.43.
Facility: SequoyahES-401 PWR RO Examination
Outline Emergency and Abnormal PlantEVOlutions-
Tier I 1 Group I Printed: 01/13/2008
Form ES-401-2 ((I TCJ APE#1 Name 1 Safety Function KI K2 K3 AlA2G KA Topic Imp.Points 000007 Reactor Trip-Stabilization
-X EAl.08-AFWSystem 4.4 1 Recovery 11 000008 Pressurizer
Vapor Space Accident 1 X AA2.29-Theeffects
of bubble in 3.9 1 3 reactor vessel 000009 Small Break LOCA13 X EA2.24-RCP temperature
setpoints 2.6 1 000011 Large Break LOCA13 X EK3.13-Hot-leg injection/recirculation
3.8 1 000015/000017
RCP Malfunctions14 XAK2.08-CCWS
2.6 1 000022 Loss of Rx Coolant Makeup12 XAA2.03-Failures of flow control valve 3.1 1 or controller
000025 Loss of RHR System14 XAK2.05-Reactor building sump 2.6 1 000026 Loss of Component Cooling Water 1 XAK3.03-Guidance actions contained in 4.0 1 8EOPforLoss
of CCW 000027 Pressurizer
Pressure Control System X AAl.02-SCR-controlled
heaters in3.1*1 Malfunction13manualmode
000038 Steam Gen.Tube Rupture13 X2.1.3-Knowledge of shift turnover 3.0 1 practices.
000040 Steam Line Rupture-Excessive X AKl.03-RCSshrinkand
consequent
3.8 1 Heat Transfer14 depressurization
)0055 Station Blackout 16 X2.4.29-Knowledge of the emergency 2.6 1 plan.000056 Loss of Off-site Power16 X AKl.03-Definition
of subcooling:
use 3.1*1 ofsteamtablesto
determine it 000058 Loss of DC Power 16 X AKl.Ol-Battery charger equipment 2.8 1 and instrumentation
000062 Loss of Nuclear Svc Water14 X AAl.Ol-Nuclear service water 3.1 1 temperature
indications
W IE04 LOCA Outside Containment13 X2.4.48-Ability to interpret control 3.5 1 room indicationstoverifythestatusand
operation ofsystem,and
understand
how operatoractionsand
directives
affect plantandsystem conditions.
W/E05 Inadequate
Heat Transfer-Lossof XEK3.1-Facility operating 3.4 1 Secondary Heat Sink14 characteristics
during transient conditions, including coolant chemistryandtheeffects
of temperature, pressure, and reactivity
changes and operating limitations
and reasonsforthese operating characteristics
I
Facility: SequoyahES-401PWRRO Examination
Outline EmergencyandAbnormalPlantEvolutions-Tier1/Group1
Printed: 01/13/2008
Form ES-401-2 ((I':/APE#/Name/Safety
Function Kl K2 K3 Al A2 GKATopicImp.PointsW/E11Loss of Emergency CoolantRecirc./XEK2.2-Facility's
heat removal systems, 3.9 1 4 including primary coolant, emergency coolant,thedecay heat removalsystems,and
relations between the proper operation ofthesesystemstothe
operation of the facility KIA Category Totals:333333GroupPointTotal:
18 2
Facility: SequoyahES-401PWRRO Examination
OutlineEmergencyandAbnormalPlantEvolutions-Tier1/Group2
Printed: 01/13/2008
Form ES-401-2 (I 7,/APE#/Name/Safety Function KlK2K3 Al A2 GKATopicImp.Points
000001 Continuous
Rod Withdrawal/1 XAK2.05-Rod
motion lights 2.9*1 000033 Loss of IntermediateRangeNI/7 X2.4.21-Knowledge of the parameters
3.7 1andlogicusedtoassessthestatus
ofsafetyfunctionsincluding:1.
Reactivitycontrol;2.Core
cooling and heatremoval;3.
Reactor coolant systemintegrity;4.
Containment
conditions;
5.Radioactivity
release control.000036 Fuel Handling Accident/8 XAKl.O1-Radiation exposure hazards 3.5 1 000060 Accidental
Gaseous RadwasteReI./XAA1.02-Ventilation
system 2.9 1 9 000069 Loss of CTMT Integrity/5 X2.4.45-Ability to prioritize
and 3.3 1 interpret the significance
of each annunciatororalarm.000074Inad.Core Cooling/4 XEK3.07-Startingup
emergency 4.0 1 feedwaterandRCPs 000076 High Reactor Coolant Activity/9 XAK2.01-Process radiation monitors 2.6 1 W/E09 Natural Circ./4 XEA2.1-Facility conditions
and 3.1 1 selection of appropriate
procedures
during abnormal and emergency operationsW/E14Loss of CTMT Integrity/5 X EA2.2-Adherence to appropriate
3.3 1 procedures
and operationwithinthelimitationsinthefacility's
license and amendments
KIA Category Totals: 1 2 1 1 2 2GroupPointTotal:
9
Facility: Sequoyah ES-401 PWR RO Examination
Outline Plant Systems-Tier2/Group 1 Printed: 01/13/2008
Form ES-401-2 (I Sys/Evol#/Name Kl K2 K3K4K5K6 AlA2A3A4 G KA Topic Imp.Points 003 Reactor Coolant Pump XK3.04-RPS 3.9 1 003 Reactor Coolant Pump X2.3.10-Abilityto
perform 2.9 1 procedurestoreduceexcessivelevels
of radiationandguardagainst
personnel exposure.004ChemicalandVolumeControl
X K5.3l-Purpose of flow 3.0*1patharoundboricacidstoragetank004ChemicalandVolumeControl
XA3.08-Reactor power 3.9 1005ResidualHeatRemoval
XA4.03-RHR temperature, 2.8*1PZRheatersandflow,and
nitrogen 006 EmergencyCoreCooling
XK1.02-ESFAS
4.3 1 007 Pressurizer
Relief/Quench
X K3.0l-Containment
3.3 1 Tank 007 Pressurizer
Relief/Quench
X2.1.1-Knowledgeof
3.7 1 Tankconductof operations
requirements.
008 Component Cooling Water XK4.07-Operationofthe 2.6*1CCWswing-bus
powersupplyandits
associatedbreakersandcontrols
J10 Pressurizer
Pressure Control XK6.03-PZRspraysand
3.2 1 heaters 012 Reactor Protection
XK4.04-Redundancy
3.1 1 013 Engineered
Safety Features X K2.0l-ESFAS/safeguards
3.6*1 Actuationequipmentcontrol
022 Containment
Cooling XA2.04-Loss
of service 2.9*1 water025Ice Condenser XK5.02-Heattransfer2.6*1 026 Containment
Spray XK4.07-Adequatelevelin
3.8*1containmentsumpforsuction(interlock)
026 Containment
Spray X2.4.48-Abilityto
interpret 3.5 1controlroom
indications
toverifythestatusand
operationofsystem,andunderstandhow
operatoractionsand
directives
affectplantandsystemconditions.039MainandReheatSteam
X Al.09-Mainsteamline
2.5*1radiationmonitors
059 Main Feedwater XA2.07-Tripping ofMFW3.0*1pumpturbine059Main Feedwater X A4.0l-MFWturbinetrip3.1*1 indication
Facility: SequoyahES-401 PWR RO Examination
Outline Plant Systems-Tier2/Group 1 Printed: 01/13/2008
Form ES-401-2 ((I Sys/Evol#/Name KlK2K3K4 KS K6 Al A2A3A4G KA Topic Imp.Points 061 Auxiliary/Emergency
X K5.0l-Relationship
3.6 1 Feedwater betweenAFWflowandRCSheat transfer062AC Electrical
Distribution
X Kl.02-ED/G 4.1 1063DC Electrical
Distribution
X K2.0l-MajorDCloads 2.9*1 064 Emergency Diesel Generator XK6.08-Fueloil
storage 3.2 1 tanks 073 Process Radiation Monitoring
X Al.Ol-Radiation levels 3.2 1 076 Service Water XA2.02-Service water 2.7 1 header pressure 076 Service Water X A4.02-SWS valves 2.6 1 078 Instrument
Air X K3.0l-Containment
air3.1*1 system 103 Containment
X A3.0l-Containment
3.9 1 isolation KIA Category Totals: 2 233322 3 233 Group Point Total: 28 2
Facility: Sequoyah ES-401PWRRO Examination
Outline Plant Systems-Tier 2 1 Group 2 Printed: 01/13/2008
Form ES-401-2 ((I Sys/Evol#1 Name Kl K2K3K4K5K6 AlA2A3A4G KA Topic Imp.Points 011 Pressurizer
Level Control X K6.05-Function ofPZR 3.1 1 level gauges as postaccident
monitors 015 Nuclear Instrumentation
XK2.01-NIS channels, 3.3 1 components, and interconnections
016 Non-nuclear
Instrumentation
X K1.l0-CCS3.1*1 017 In-core Temperature
Monitor XK4.03-Range
of 3.1 1 temperature
indication
045 Main Turbine Generator X K5.17-Relationship
2.5*1 between moderator temperature
coefficient
and boron concentrationinRCSasT IG load increases 055 Condenser Air Removal XA3.03-Automatic diversion 2.5*1 of CARS exhaust 068 Liquid Radwaste XA4.01-Control board for 2.7*1 boron recovery 071 Waste Gas Disposal X K3.04-Ventilation
system 2.7 1 075 Circulating
Water X2.2.11-Knowledge of the 2.5 1 process for controlling
temporary changes.086Fire Protection
XA1.01-Fire
header pressure 2.9 1 I KIA Category Totals:111111 1 0 111 Group Point Total: 10
Facility: Sequoyah Generic KnowledgeandAbilities
Outline(Tier3)PWRRO Examination
Outline Printed: 01/13/2008FormES-401-3
Generic Catezorv KAKATopic Points (Conduct of Operations
2.1.3 Knowledge of shift turnover practices.
3.0 I 2.1.27 Knowledgeofsystem purposeandorfunction.2.8
I 2.1.28 Knowledge of the purpose and function of major 3.2 I system components
and controls.Category Total: 3 Equipment Control 2.2.26 Knowledge of refueling administrative
2.5 I requirements.
2.2.33 Knowledge of control rod programming.
2.5 I Category Total: 2 Radiation Control 2.3.2 Knowledge of facility ALARA program.2.5 I 2.3.9 Knowledge of the process for performing
a 2.5 I containment
purge.2.3.10 Ability to perform procedures
to reduce excessive 2.9 I levels of radiationandguard against personnel exposure.Category Total: 3 Emergency Procedures/Plan
2.4.16 Knowledge of EOP implementation
hierarchy and 3.0 I coordination
with other support procedures.
2.4.22 Knowledge ofthebasesfor
prioritizing
safety 3.0 Ifunctionsduring
abnormal/emergency
operations.
Category Total: 2 (GenericTotal:
10
(FormES-401-2Printed:01/13/2008
SRO-Only Points A2G*Total 000 000 000 000 01000 000 1234 000001.Ensure thatatleasttwo
topicsfromeveryKIAcategoryaresampledwithineach
tieroftheROand
SRO-only outlines(Le.,except
foronecategoryin
Tier3ofthe SRO-onlyoutline,the"Tier Totals"ineachKIA categoryshallnot belessthantwo).2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthat
specifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby+/-1from
thatspecifiedinthetablebasedonNRCrevisions.ThefinalROexam
musttotal75pointsandthe
SRO-only exam musttotal25points.
3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;systemsor
evolutions
thatdonot applyatthe facility should bedeletedand
justified;
operationally
important, site-specific
systems thatarenotincludedontheoutlineshould
be added.RefertoES-401, Attachment2,for guidanceregardingthe
elimination
of inappropriateKIAstatements.
4.Select topicsfromasmany
systems and evolutionsaspossible;sampleeverysystemor
evolutioninthe groupbeforeselectingasecondtopic
foranysystemorevolution.
5.Absent a plant-specificpriority,onlythoseKlAshavingan
importancerating(IR)of2.5orhigher
shall beselected.UsetheROandSROratingsfortheROandSRO-onlyportions,respectively.
6.SelectSROtopicsforTiers1and2fromtheshadedsystemsandKIA
categories.7.*The generic(G)KlAsinTiers1and2shallbeselectedfromSection2oftheKIA
Catalog,butthetopicsmustberelevanttotheapplicable
evolutionorsystem.8.Onthefollowingpages,entertheKIAnumbers,abrief
descriptionofeachtopic,thetopics'
importanceratings(IRs)forthe
applicablelicenselevel,andthepointtotals(#)foreachsystem
and category.Enterthegroupandtiertotalsforeachcategoryinthetableabove;iffuelhandling
equipment is sampled in otherthanCategoryA2orGonthe
SRO-onlyexam,enteritontheleft
side ofColumnA2forTier2,Group2(Note#1
doesnotapply).Useduplicatepages
forROand SRO-onlyexams.9.For Tier3,selecttopicsfrom
Section2oftheKIAcatalog,andentertheKIA
numbers, descriptions,IRs,andpointtotals(#)onFormES-401-3.LimitSRO
selectionstoKlAsthatarelinkedto10CFR55.43.
Facility: Sequoyah PWR RO Examina.Outline Printed: 01/13/200 EES401-merzencyandAbnormalPlant
Evolutions-Tier1/Group1FormES-401-2
E/APE#/Name/Safety
Function KAKATopic Comment 000007 ReactorTrip-Stabilization
-Recovery/1 EA1.08 AFW System 000008 Pressurizer
Vapor Space Accident/3 AA2.29Theeffects
of bubble in reactor vessel 000009 Small Break LOCA/3 EA2.24 RCP temperature
setpoints000011Large
Break LOCA/3 EK3.13 Hot-leg injection/recirculation
000015/000017
RCP Malfunctions/4AK2.08CCWS
000022 Loss of Rx Coolant Makeup/2 AA2.03 Failures offlowcontrolvalveor
controller
000025 Loss ofRHRSystem/4 AK2.05 Reactor building sump 000026 Loss of Component Cooling Water/8 AK3.03 Guidance actions containedinEOPforLoss
of CCW 000027 Pressurizer
Pressure Control System Malfunction
/3 AAl.02 SCR-controlledheatersin manual mode 000038SteamGen.Tube
Rupture/3 2.1.3 Knowledge of shift turnover practices.
000040SteamLineRupture-
Excessive Heat Transfer/4 AK1.03RCSshrinkand
consequent
depressurization
Facility: Sequoyah PWRRO Examina.OutlinePrinted:01/13/200
ES 401-Emergency and Abnormal Plant Evolutions
-Tier 1 1 Group 1 Form ES-401-2 E/APE#1 Name 1 Safety FunctionKAKATopic Comment000055StationBlackout
16 2.4.29 Knowledge oftheemergencyplan.KAreplacedwith055
G 2.4.18asdirectedby
Chief Examiner.12/20/2007000056LossofOff-site
Power16 AKl.03Definitionofsubcooling:use
ofsteamtablestodetermineit000058Loss
ofDCPower 16 AK1.01 Batterychargerequipmentandinstrumentation000062Loss
of Nuclear Svc Water14 AA1.01Nuclearservicewatertemperatureindications
W/E04LOCAOutside
Containment132.4.48Abilitytointerpretcontrolroomindicationstoverifythestatusand
operation ofsystem,andunderstandhow
operatoractionsanddirectivesaffectplantandsystemconditions.
W/E05InadequateHeat
Transfer-Loss ofSecondaryHeatSinkEK3.1Facilityoperating
characteristicsduringtransient
14conditions,includingcoolantchemistryandtheeffectsoftemperature,pressure,andreactivitychangesandoperatinglimitationsandreasonsfortheseoperating
characteristics
W/EllLossofEmergency
Coolant Recirc.14EK2.2Facility'sheatremovalsystems,includingprimary
coolant emerzencvcoolantthedecavheatremovalsystems,andrelationsbetweentheproper
operation ofthesesystemstotheoperation
of the facility 2
Facility: SequoyahPWRRO Examim.Outline Printed: 01/13/20llicenseandamendments
A EES401-meraencv andbnormalPlant
Evolutions-Tier1 IGroup2FormES-401-2
E/APE#I Name I Safety Function KAKATopic Comment000001ContinuousRod
Withdrawal
11 AK2.05Rodmotionlights000033Loss
ofIntermediateRangeNI I 7 2.4.21Knowledgeofthe
parametersandlogicusedtoassessthestatus
ofsafetyfunctionsincluding:1.
Reactivitycontrol;2.Corecoolingandheatremoval;3.
Reactorcoolantsystemintegrity;4.Containmentconditions;5.
Radioactivity
release control.000036FuelHandling
Accident I 8AK1.01Radiationexposurehazards
000060 AccidentalGaseousRadwasteReI.I9AA1.02Ventilationsystem000069Loss
of CTMT IntegrityI5 2.4.45Abilityto prioritizeandinterpretthesignificance
of each annunciatororalarm.000074Inad.CoreCoolingI4 EK3.07Startingup
emergencyfeedwaterandRCPs000076High
Reactor Coolant Activity 19AK2.01Process
radiation monitors W/E09NaturalCirc.
14EA2.1Facilityconditionsandselectionofappropriate
proceduresduringabnormalandemergency
operations
W/E14 Loss ofCTMT Integrity 15EA2.2Adherenceto
appropriate
procedures
andonerationwithinthelimitationsinthefacility's
Facility: SequoyahES-401 Plant Systems-Tier2/Group 1Printed:01/13Form ES-401-2 Sys/Evol#/NameKAKA Topic Comment 003 Reactor Coolant Pump K3.04 RPS 003 Reactor Coolant Pump 2.3.10Abilitytoperform
procedurestoreduceexcessivelevelsofradiationandguardagainst
personnel exposure.004ChemicalandVolumeControl
K5.3l Purpose offlowpatharoundboricacidstoragePlantdesigndoesnotprovideaflowpatharound
tanktheBoricAcidStorageTank.Replacewithrandomlyselected
KIA004K5.26.The
selectionwasrandomlyselectedwithintheoriginal
KIA 004 K5.004ChemicalandVolumeControl
A3.08Reactorpower005ResidualHeatRemoval
A4.03RHRtemperature,PZRheatersandflow,and
nitrogen 006 EmergencyCoreCoolingK1.02ESFAS
007 Pressurizer
Relief/Quench
Tank K3.0l Containment
007 Pressurizer
Relief/Quench
Tank2.1.1Knowledge
of conduct ofoperationsrequirements.
008 ComponentCoolingWaterK4.07OperationoftheCCWswing-buspowersupplyanditsassociatedbreakersandcontrols
010 Pressurizer
Pressure ControlK6.03PZRspraysandheaters
012 Reactor ProtectionK4.04Redundancy
013 EngineeredSafetyFeaturesActuation
K2.0lESFAS/safeguards
equipment control
OutlinePrinted:0
Facility: Sequoyah Form ES-401-2 Plant Systems-Tier2/Group 1ES-401 Sys/Evol#/Name KA KA Topic Comment 022 Containment
Cooling A2.04 Loss ofservicewater025Ice CondenserK5.02Heattransfer
026 Containment
Spray K4.07Adequatelevelin
containmentsumpforsuction (interlock)
026 Containment
Spray 2.4.48Abilityto interpretcontrolroomindicationstoverifythestatusand
operation ofsystem,and
understand
how operatoractionsanddirectivesaffectplantandsystemconditions.039Mainand
Reheat Steam Al.09Mainsteamline
radiation monitors KA replacedwith039 Al.05asdirectedby
ChiefExaminer.12/20/2007059Main Feedwater A2.07 Tripping ofMFWpumpturbine059Main FeedwaterA4.01MFWturbinetrip
indication
061 Auxiliary/Emergency
FeedwaterK5.01Relationship
betweenAFWflowandRCSheat
transfer062AC Electrical
Distribution
Kl.02 ED/G063DC Electrical
DistributionK2.01MajorDCloads
064 Emergency Diesel Generator K6.08Fueloilstoragetanks
073 Process Radiation Monitoring
Al.OlRadiationlevels076ServiceWaterA2.02Servicewater
header pressure 2
OutlinePrinted:01/13Facility: Sequoyah Form ES-401-2 PlantSystems-Tier2/Group 1ES-401 Sys/Evol#/NameKAKA Topic Comment076ServiceWaterA4.02SWSvalves078InstrumentAir
K3.01Containmentairsystem103Containment
A3.01Containmentisolation
3
Outline Printed: OlI1Y-'Q Facility: Sequoyah Form ES-401-2 Plant Systems-Tier2/Group 2ES-401 Sys/Evol#/NameKAKA Topic Comment 011 Pressurizer
Level Control K6,05FunctionofPZRlevelgaugesas
postaccident
monitors 015 Nuclear Instrumentation
K2,01NISchannels,components,and
interconnections
016 Non-nuclear
Instrumentation
KUO CCS017In-core
Temperature
MonitorK4.03Rangeoftemperature
indication045Main Turbine Generator K5,17Relationshipbetween
moderator temperature
coefficientandboron concentrationinRCSasT/Gloadincreases055CondenserAir
Removal A3,03AutomaticdiversionofCARSexhaust068LiquidRadwaste
A4,01ControlboardforboronrecoveryTheBoron RecoverySystemhasbeenabandonedattheSequoyah
PlantReplacewithrandomlyselectedKIA068A4,02.TheselectionwasrandomlyselectedwithintheoriginalKIA068A4,071WasteGas
Disposal K3.04 Ventilation
system075Circulating
Water2.2,11Knowledge
oftheprocessfor
controlling
KAreplacedwith075G
2.2,13asdirectedby
Chieftemporarychanges.
Examiner.12/20/2007086Fire Protection
ALOIFireheaderpressure
Facility: Sequoyah Generic Category Conduct of Operations
KA Generic Knowledge.AbilitiesOutline(Tier3)PWRRO Examination
OutlineKATopic Knowledge of shift turnover practices.
Knowledge of system purposeandorfunction.
Knowledge of the purposeandfunction
ofmajorsystem
componentsPrinted:01/13/20
Form ES-401-3 CommentCategoryTotal:3
Equipment Control Radiation Control Emergency Procedures/Plan
Knowledge of refueling administrative
requirements.
2.2.33 I Knowledge ofcontrolrod
programming.
Knowledge offacilityALARAprogram.
Knowledge oftheprocessfor
performing
a containment
purge.Abilityto perform procedurestoreduceexcessivelevels
of radiation Knowledge of EOP implementation
hierarchy and coordination
with Knowledge ofthebasesfor
prioritizingsafetyfunctionsduringCategoryTotal:2CategoryTotal:3CategoryTotal:2GenericTotal:10
(ES-401RecordofRejectedKIAs
Form ES-401-4 ((Tier/RandomlyReasonfor Rejection Group Selected KIA 2/1004K5.31Plantdesigndoesnot
provideaflowpath aroundtheBoricAcidStorageTank.Replacewith
randomly selected KJ A004K5.26 2/2068A4.01The
Boron RecoverySystemhasbeen
abandonedattheSequoyahplant.Replacewith
randomly selected KJA068 A4.02 2/1039A1.09KA
replacedwith039A1.05
duringexamreviewasdirectedby
Chief Examiner.12/20/2007
1/1055G2.4.29KA
replacedwith055G2.4.18
during exam review as directed by Chief Examiner.12/20/2007
2/2075G2.2.11
KA replacedwith075G2.2.13duringexam
review asdirectedby
Chief Examiner.12/20/2007
ES-401, Page 27of33
((HItvJ ES-401PWRExaminationOutline
Form ES-401-2 Facility: SequoyahPrinted:01/13/2008DateOfExam:
01/28/2008ROKIA Category Points SRO-Only Points Tier Group K1 K2K3K4K5K6A1
A2 A3A4G*Total A2G*Total 1.100 00000 437 Emergenc 2 0 0 0 0 0 0 0 3 2 5&N/A N/A Abnormal Tier Plant Totals00000 0 0 7 5 12 Evolutions
2.1000 0 00000 0 0 0 2 2 4 2 0 0 0 0 0 0 000 0 0 0 01112 Plant Systems Tier00000 0 000 0 0 0336 Totals 3.Generic Knowledge And1234 1234 0 7 Abilities Categories
0000212 2 Note:1.EnsurethatatleasttwotopicsfromeveryKIAcategoryaresampledwithineach
tieroftheROand
SRO-only outlines(Le.,except
foronecategoryin
Tier3ofthe SRO-onlyoutline,the"Tier Totals"ineachKIA categoryshallnotbelessthantwo).2.Thepointtotalforeachgroupandtierintheproposedoutlinemustmatchthat
specifiedinthetable.Thefinalpointtotalforeachgroupandtiermaydeviateby+/-1fromthatspecifiedinthetablebasedonNRC
revisions.
The fnalROexammusttotal75pointsandthe
SRO-only exam musttotal25points.
3.Systems/evolutionswithineachgroupareidentifiedontheassociatedoutline;systemsor
evolutions
thatdonot applyatthe facilityshouldbedeletedand
justified;
operationally
important, site-specific
systems thatarenotincludedontheoutlineshouldbeadded.
RefertoES-401, Attachment2,for guidanceregardingthe
elimination
of inappropriateKIAstatements.
4.Select topicsfromasmany
systems and evolutionsaspossible;sampleeverysystem
or evolutioninthegroupbeforeselectingasecondtopic
foranysystemorevolution.
5.Absent a plant-specificpriority,onlythoseKlAshavingan
importancerating(IR)
of2.5or highershallbeselected.UsetheROandSROratingsfortheROandSRO-onlyportions,respectively.
6.SelectSROtopicsforTiers1and2fromtheshadedsystemsandKIA
categories.7.*The generic(G)KlAsinTiers1and2shallbeselectedfromSection2oftheKIA
Catalog,butthetopicsmustberelevanttotheapplicable
evolutionorsystem.8.Onthe followingpages,entertheKIAnumbers,abrief
descriptionofeachtopic,thetopics'
importanceratings(IRs)forthe
applicablelicenselevel,andthepointtotals(#)foreachsystem
and category.Enterthegroupandtiertotalsforeach
categoryinthetableabove;iffuelhandling
equipment is sampled in other than CategoryA2orGonthe
SRO-onlyexam,enteritontheleftsideof ColumnA2forTier2,Group2(Note#1doesnotapply).Useduplicatepages
forROand SRO-onlyexams.
9.For Tier3,selecttopicsfrom
Section2oftheKIAcatalog,andentertheKIAnumbers, descriptions,IRs,andpointtotals(#)onFormES-401-3.LimitSRO
selectionstoKlAsthatarelinkedto10CFR55.43.
Facility: SequoyahPWRSRO Examir, In OutlinePrinted:0l/13/20CalarmstoaSteamLineRupture
ExcessiveHeatTransfer.
Replace with W/E12New KIA supplied by Chief Examiner 8/23/07 dAb EES401-merzency annormalPlantEvolutions-Tier1
1Group1FormES-401-2
EI APE#1 Name 1 Safety Function KAKATopic Comment 000008 Pressurizer
Vapor Space Accident13 2.4.49Abilitytoperformwithout
reference to procedures
KA replacedwith008G2.4.41thoseactionsthatrequireimmediate
operation of as directed by Chief Examiner.system componentsandcontrols.
12120/2007000029ATWS
11 EA2.09 Occurrence
ofamain turbine/reactor
trip000054Loss
of Main Feedwater14 AA2.05 Status ofMFW pumps, regulatingandstopvalves
000057 Loss ofVitalACInst.Bus16AA2.17Systemand
componentstatus,usinglocalorremotecontrols000065Loss
of Instrument
Air 1 8 AA2.01Causeandeffect
of low-pressureinstrumentair
alarm W/Ell Loss of Emergency Coolant Recirc.14 2.4.48Abilityto interpretcontrolroom
indications
toverifythestatusand
operation ofsystem,and
understand
how operatoractionsanddirectivesaffectplantandsystemconditions.
W/E12-SteamLine Rupture-ExcessiveHeat
Transfer14 2.4.33 Knowledge of the processusedtrackinoperableUnabletowritequestionthattied
alarms.processfortrackingINOP
Facility: Sequoyah PWR SRO Examin n OutlinePrinted:01/13/20(,ES401-EmerzencvandAbnormalPlant
Evolutions-Tier1/Group2FormES-401-2
E/APE#/Name/Safety
Function KAKATopic Comment 000003 Dropped ControlRod/1 2.2.26 Knowledge of refueling administrativeUnabletowritequestionthat
requirements.
connected Refueling AdministrativeRequirementstotheAbnormalPlant
Evolution of DroppedControlRod.Replacewith003G2.2.22-NewKIA
supplied by Chief Examiner 8/23/07 000005 Inoperable/Stuck
ControlRod/1 AA2.03 Required actions ifmorethanonerodisstuckor
inoperable000051Loss
of Condenser Vacuum/4 AA2.02 Conditions
requiring reactor and/orturbinetripW/E02SI Termination/3 EA2.2 Adherence to appropriate
procedures
and operationwithinthe limitationsinthefacility'slicenseand
amendmentsW/E16High Containment
Radiation/92.2.31Knowledge
of proceduresandlimitationsinvolvedininitialcoreloading.
PWR SROC--.lmination
OutlinePrinted:0 1/1Facility: SequoyahFormES-401-2PlantSystems-Tier2/Group1ES-401 Sys/Evol#/Name KAKATopic Comment 008 Component Cooling Water A2.09 Results of excessive exit temperaturefromtheletdowncooler, including the temperature
effects on ion-exchange
resins 010 Pressurizer
Pressure Contra 1 2.4.38 Abilitytotakeactions
calledforinthefacility
emergency plan, including (if required)supportingoractingas
emergency coordinator.
013 Engineered
Safety Features Actuation A2.05 Loss of de control power 103 Containment
2.2.14 Knowledge of the processformaking confizuration
chances.
Facility: SequoyahES-401 PWR SRO-'Unination
OutlinePlantSystems-Tier2
1Group2 Printed:FormES-401-2
Sys/Evol#1 Name KAKATopic Comment 029 Containment
Purge2.4.38AbilitytotakeactionscalledforinthefacilityUnabletowritequestion
relatedtakingactions
emergencyplan,including (if required)supportingcalledforinthe
EmergencyPlanto Containmentoractingas
emergency coordinator.
Purge.Replacewith029G2.4.46-New
KIA supplied by Chief Examiner 8/23/07034FuelHandling
Equipment A2.02 Dropped cask
Facility: SequoyahGenericCategoryConductofOperationsEquipmentControlRadiationControl
Emergency Procedures/Plan
KA Generic KnowledgeAbilitiesOutline(Tier3)PWRSROExaminationOutlineKATopicAbilitytoapplyteclmicalspecificationsforasystem.Abilitytorecognizeindicationsforsystem
operating parameters
Knowledge oftheprocessfordeterminingifthe
proposed change, Knowledge of10CFR:20andrelatedfacility
radiation control Knowledge of the requirementsforreviewingandapprovingrelease
Knowledge oflowpower/shutdownimplicationsinaccident(e.g.Abilityto performwithoutreferenceto
proceduresthoseactionsthatPrinted:01/13/20, Form E8-401-3 CommentCategoryTotal:2CategoryTotal:1CategoryTotal:2CategoryTotal:2GenericTotal:7
ES-401PWRExaminationOutline
Facility: SequoyahDateOfExam:
01/28/2008ROKIA Category Points Tier GroupK1K2K3K4K5
K6 A1A2A3A4G*Total
1.10000000 Emergenc 2 0 0 00000&N/A N/A Abnormal Tier Plant Totals00000 0 0 Evolutions
2.10000 000000 0 0 2 0 0 0 000 000 0 0 0 Plant Systems Tier000000000000 Totals 3.Generic Knowledge And1234 0 Abilities Categories0000 Note: Form ES-401-2 Printed: 01/13/2008
SRO-Only Points A2G*Total 437 3 2 575 12 2 2 4 0111233 61234 72122 (1.Ensure that at least two topicsfromeveryKIA
category are sampledwithineach
tieroftheROand
SRO-only outlines (i.e., except for one category in Tier3ofthe SRO-only outline, the"Tier Totals"ineachKIA categoryshallnotbe
lessthantwo).2.The pointtotalforeach
groupandtierinthe
proposedoutlinemustmatch
that specifiedinthetable.Thefinal
pointtotalforeachgroupandtiermay
deviateby+/-1from that specifiedinthe tablebasedon NRC revisions.ThefinalROexam
musttotal75pointsandthe
SRO-only exam musttotal25points.
3.Systems/evolutionswithineachgroupare
identifiedonthe associated
outline;systems or evolutions
thatdonot applyatthe facility shouldbedeletedand
justified;
operationally
important, site-specific
systems thatarenot includedontheoutline
shouldbeadded.RefertoES-401, Attachment2,for guidance regarding the elimination
of inappropriate
KIA statements.
4.Select topicsfromasmany
systems and evolutions
as possible;sampleeverysystemor
evolutioninthe group before selecting a second topic foranysystemor
evolution.
5.Absent a plant-specific
priority, only those KlAshavingan importancerating(IR)
of2.5or highershallbe selected.UsetheROandSRO
ratingsfortheROand
SRO-only portions, respectively.
6.Select SRO topics for Tiers1and2fromtheshaded
systemsandKIA categories.7.*The generic (G)KlAs in Tiers1and2shallbe
selectedfromSection2oftheKIA
Catalog,butthetopicsmustbe
relevanttothe applicable
evolution or system.8.Onthe following pages, entertheKIAnumbers,abrief
descriptionofeachtopic,the
topics'importanceratings(IRs)forthe
applicable
licenselevel,andthepointtotals(#)for
each system and category.Enterthe groupandtiertotalsforeach
categoryinthe table above;iffuelhandling
equipment is sampled in other than Category A2 orGonthe SRO-only exam, enteritontheleft
side of ColumnA2forTier2,Group2(Note#1
doesnotapply).Use
duplicate pages forROand SRO-onlyexams.9.For Tier 3, select topics from Section2oftheKIAcatalog,and
entertheKIA numbers, descriptions,IRs,andpointtotals(#)on
Form ES-401-3.LimitSRO selections
toKlAsthatarelinkedto10CFR55.43.
Facility: SequoyahES-401PWRSRO Examination
Outline Emergency and Abnormal Plant Evolutions-TierI/GroupI
Printed: 01/13/2008
Form ES-401-2 ('IAPE#/Name/Safety FunctionKIK2K3 Al A2 GKATopic Imp.Points 000008 Pressurizer
Vapor Space Accident/X2.4.49-Abilityto
perform without 4.0 1 3referenceto
proceduresthoseactionsthatrequireimmediate
operation ofsystemcomponentsandcontrols.
000029ATWS/1 XEA2.09-Occurrence
ofamain 4.5 1 turbine/reactor
trip000054Loss
of Main Feedwater/4 XAA2.05-Status
ofMFW pumps, 3.7 1regulatingandstopvalves
000057 Loss ofVitalACInst.Bus/6
XAA2.17-Systemand
component status, 3.4 1usinglocalorremotecontrols000065Loss
of InstrumentAir/8 XAA2.01-Causeandeffect
of 3.2 1low-pressureinstrumentairalarmW/E11Loss of Emergency CoolantRecirc./X2.4.48-Abilitytointerpretcontrol
3.8 1 4roomindicationstoverifythestatusand
operationofsystem,and
understand
how operatoractionsanddirectivesaffectplantandsystemconditions.
W/EI2-SteamLineRupture-
Excessive X2.4.33-Knowledge
oftheprocessused
2.8 1 Heat Transfer/4trackinoperablealarms.
KIA Category Totals: 000 0 4 3GroupPointTotal:
7
Facility: SequoyahES-401PWRSRO Examination
OutlineEmergencyandAbnormalPlantEvolutions-Tier1/Group2
Printed: 01/13/2008
Form ES-401-2 (((I#/Name/Safety
Function KlK2K3 Al A2 GKATopicImp.Points
000003 Dropped ControlRod/1 X2.2.26-Knowledge of refueling 3.7 1 administrative
requirements.
000005 Inoperable/Stuck
ControlRod/1 XAA2.03-Required actions ifmorethan 4.4 1onerodis stuck or inoperable000051Loss
of Condenser Vacuum/4 XAA2.02-Conditions
requiring reactor 4.1 1 and/orturbinetrip
W/E02 SI Termination
/3 XEA2.2-Adherence to appropriate
4.0 1 procedures
and operationwithinthe limitationsinthefacility'slicenseand
amendmentsW/E16 High Containment
Radiation/9 X2.2.31-Knowledge of procedures
and 2.9*1 limitations
involvedininitialcore
loading.KIA Category Totals: 000 0 3 2GroupPointTotal:
5
Facility: Sequoyah ES-401 PWR SRO Examination
Outline Plant Systems-Tier 2 1 Group 1 Printed: 01/13/2008
Form ES-401-2 ((I Sys/Evol#1 Name KlK2K3 K4KSK6 AlA2A3A4G KA Topic Imp.Points 008 ComponentCoolingWater
XA2.09-Results
of excessive 2.8 1 exit temperaturefromtheletdowncooler,including
the temperatureeffectson ion-exchange
resins 010 Pressurizer
Pressure Control X2.4.38-Abilitytotake
4.0 1actionscalledforinthe
facility emergency plan, including (if required)supportingoractingas
emergency coordinator.
013 Engineered
Safety Features XA2.05-Loss
ofdecontrol 4.2 1 Actuation power 103 Containment
X2.2.14-Knowledge of the 3.0 1processformaking
configuration
changes.KIA Category Totals:000 0 00020 0 2 Group Point Total: 4
Facility: SequoyahES-401PWRSRO Examination
OutlinePlantSystems-Tier2
1Group2 Printed: 01/13/2008
Form ES-401-2 f\(I Sys/Evol#1 NameKIK2K3K4K5
K6 AlA2A3A4 GKATopic Imp.Points 029 Containment
Purge X2.4.38-Abilitytotake 4.0 1 actions calledforinthe facility emergency plan, including (if required)supportingoractingas
emergency coordinator.
034 Fuel Handling Equipment XA2.02-Dropped cask 3.9 1 KIA Category Totals:0000000 I00 IGroupPointTotal:
2
Facility: Sequoyah Generic Category Generic Knowledge and Abilities Outline(Tier3)PWR SRO Examination
OutlineKATopic Printed: 01/13/2008
Form ES-401-3 (Conduct of Operations2.1.12Abilitytoapplytechnical
specificationsfora4.0 1 system.2.1.33Abilitytorecognizeindicationsforsystem
4.0 1operatingparameterswhichareentry-levelconditionsfortechnicalspecifications.
Category Total: 2 Equipment Control2.2.8Knowledge
oftheprocessfordeterminingifthe
3.3 I proposedchange,test,or
experimentinvolvesanunreviewedsafetyquestion.
Category Total: 1 Radiation Control2.3.1Knowledge
of10CFR:20and
relatedfacility3.0
Iradiationcontrolrequirements.2.3.6Knowledge
of the requirementsforreviewingand
3.1 Iapprovingreleasepermits.
Category Total: 2 Emergency Procedures/Plan2.4.9Knowledge
oflowpower/shutdown implications
3.9 Iinaccident(e.g.LOCAorloss
ofRHR)mitigationstrategies.2.4.49Abilitytoperformwithout
reference to 4.0 I proceduresthoseactionsthatrequireimmediate
operation of system componentsandcontrols.
Category Total: 2GenericTotal:
7
ES-401RecordofRejectedKlAs
Form ES-401-4 (Tier/RandomlyReasonforRejection
Group Selected KJ A 1/2 003,G2.2.26Unabletowrite
question that connected Refueling Administrative
Requirementstothe Abnormal Plant Evolution ofDroppedControlRod.
Replacewith003G2.2.22-New
KiA supplied by Chief Examiner 8/23/07 1/1008G2.4.49
KA replacedwith008G2.4.41duringexam
review asdirectedby
ChiefExaminer.12/20/2007
2/2029G2.4.38Unabletowrite
question related taking actions calledforin the EmergencyPlanto Containment
Purge.Replacewith029G2.4.46-New
KiA supplied by Chief Examiner 8/23/07 1/1E12G2.4.33Unabletowritequestionthattied
process for trackingINOPalarmstoaStearnLine
Rupture-Excessive Heat Transfer.Replace with W/EI2G2.1.32-New
KiAsuppliedby
Chief Examiner 8/23/07 3 G2.4.49 KA replacedwithG2.4.40duringexamreviewas
directed by ChiefExaminer.12/20/2007ES-401,Page27of33