ML100670659

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AN2-2009-08-Draft Outlines
ML100670659
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/07/2009
From: Larson B T
Operations Branch IV
To:
Entergy Operations
References
Download: ML100670659 (33)
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ES-401 Facility:Arkansas Nuclear One Unit 2PWR RO Examination OutlineForm ES-401-2 3 3 3 3 3 3 1 2 1 1 2 2 4 5 4 4 5 5 2 2 3 3 3 2 2 3 2 3 3 0 1 1 1 1 1 1 1 1 1 1 2 3 4 4 4 3 3 4 3 4 4 2 3 3 2RO K/A Category PointsTierGroup Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&AbnormalPlantEvolutions 1 1 2 2Tier TotalsTier Totals 2.PlantSystems 1 2 3 43. Generic Knowledge And Abilities Categories2. The point total for each group and tier in the proposed outline must match that specified in the table.The final point total for each group and tier may deviate by +/-1 from that specified in the tablebased on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.4. Select topics from as many systems and evolutions as possible; sample every system or evolutionin the group before selecting a second topic for any system or evolution.3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions thatdo not apply at the facility should be deleted and justified; operationally important, site-specificsystems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or highershall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Note:Date of Exam:

08/07/2009 28 18 9 27 10 38 101. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals"in each K/A category shall not be less than two).7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but thetopics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 forthe applicable K/As.8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics'importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handlingequipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the leftside of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.SRO-Only Points A2 G*0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 3 4 0 0 0 0 0 0 09. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions,IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to10 CFR 55.43.6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0 0 Emergency and Abnormal Evolutions - Tier 1/Group 1 (RO)E/APE # / Name / Safety FunctionK/A Topic(s)

K1 K2 K3 A 1 A 2 G IR #PWR Examination OutlineES-401Form ES-401-2 2 Q ID000008 Pressurizer Vapor SpaceAccident / 3AK3.01 - Knowledge of the reasons for the following responses as theyapply to the Pressurizer Vapor SpaceAccident: - Why PZR level may comeback on scale if RCS is saturated X 3.7 1 1000009 Small Break LOCA / 3EA2.09 - Ability to determine and interpret the following as they apply toa small break LOCA: - Low-pressureSWS activity monitor X 2.8 1 2000011 Large Break LOCA / 3EK1.01 - Knowledge of theoperational implications of thefollowing concepts as they apply to the Large Break LOCA: - Naturalcirculation and cooling, includingreflux boiling X 4.1 1 3000015/000017 RCP Malfunctions / 4AK2.10 - Knowledge of the interrelations between the Reactor C o o lant Pu m p Malfun c ti ons and thefollowing: - RCP indicators andcontrols X 2.8 1 4000022 Loss of Rx Coolant Makeup / 2AK3.05 - Knowledge of the reasons for the following responses as theyapply to the Loss of Reactor Coolant Mak e up: - N e e d to avoi d planttransients X 3.2 1 5000026 Loss of Component Cooling Water / 82.2.44 - Equipment Control - Ability to interpret control room indications toverify the status and operation of a system, and understand how operatoractions and directives affect plant andsystem conditions.

X 4.2 1 6000027 Pressurizer Pressure Control System Malfunction / 3AK1.03 - Knowledge of the operational implications of thefollowing concepts as they apply toPressurizer Pressure Control Malfunctions: - Latent heat ofvaporization/condensation X 2.6 1 7000029 ATWS / 12.2.36 - Equipment Control - Ability to analyze the effect of maintenanceactivities, such as degraded power sources, on the status of limitingconditions for operations.

X 3.1 1 8000038 Steam Gen. TubeRupture / 3EK3.02 - Knowledge of the reasons for the following responses as they apply to the SGTR: - Prevention ofsecondary PORV cycling X 4.4 1 9000054 Loss of Main Feedwater

/ 42.4.6 - Emergency Procedures/Plan -

Knowledge of EOP mitigationstrategies.

X 3.7 1 10ES-401, 22 of 33 Emergency and Abnormal Evolutions - Tier 1/Group 1 (RO)E/APE # / Name / Safety FunctionK/A Topic(s)

K1 K2 K3 A 1 A 2 G IR #PWR Examination OutlineES-401Form ES-401-2 2 QID000055 Station Blackout / 6EA1.05 - Ability to operate and/ormonitor the following as they apply toa Station Blackout: - Battery, whenapproaching fully discharged X 3.3 1 11000056 Loss of Off-site Power / 6AK1.03 - Knowledge of theoperational implications of thefollowing concepts as they apply toLoss of Offsite Power: - Definition of subcooling: use of steam tables todetermine it X 3.1 1 12000057 Loss of Vital AC Inst.

Bus / 6AA1.05 - Ability to operate and/or monitor the following as they apply tothe Loss of Vital AC Instrument Bus: -

Backup instrument indications X 3.2 1 13000058 Loss of DC Power / 6AA2.02 - Ability to determine and interpret the following as they apply to the Loss of DC Power: - 125V dc busvoltage, low/critical low, alarm X 3.3 1 14000062 Loss of Nuclear SvcWater / 4AA1.03 - Ability to operate and/or monitor the following as they apply tothe Loss of Nuclear Service Water(SWS): - SWS as a backup to the CCWS X 3.6 1 15000077 Generator Voltage andElectric Grid Disturbances / 6AK2.06 - Knowledge of the interrelations between GeneratorVoltage and Electric Grid Disturbances and the following: -Reactor power X 3.9 1 16CE/E02 Reactor Trip -Stabilization - Recovery / 1EK2.1 - Knowledge of the interrelations between the (Reactor Trip Recovery) and the following: -Components, and functions of controland safety systems, including instrumentation, signals, interlocks,failure modes, and automatic andmanual features X 3.3 1 17CE/E05 Steam Line Rupture -Excessive Heat Transfer / 4EA2.2 - Ability to determine and interpret the following as they apply tothe (Excess Steam Demand): -

Adherence to appropriate proceduresand operation within the limitations inthe facility's license and amendments X 3.4 1 18K/A Category Totals:

3 3 3 3 3 3 18Group Point Totals:ES-401, 22 of 33 Emergency and Abnormal Evolutions - Tier 1/Group 2 (RO)E/APE # / Name / Safety FunctionK/A Topic(s)

K1 K2 K3 A 1 A 2 G IR #PWR Examination OutlineES-401Form ES-401-2 3 QID000001 Continuous RodWithdrawal / 1AA2.05 - Ability to determine and interpret the following as they apply tothe Continuous Rod Withdrawal: -Uncontrolled rod withdrawal, from available indications X 4.4 1 19000003 Dropped Control Rod / 1AK2.05 - Knowledge of theinterrelations between the DroppedControl Rod and the following: -

Control rod drive power supplies andlogic circuits X 2.5 1 20000032 Loss of Source RangeNI / 72.1.28 - Conduct of Operations -

Knowledge of the purpose and function of major system componentsand controls.

X 4.1 1 21000036 Fuel Handling Accident /

8AA1.03 - Ability to operate and/or monitor the following as they apply tothe Fuel Handling Incidents: - Reactorbuilding containment evacuation alarm enable switch X 3.5 1 22000051 Loss of CondenserVacuum / 4AA2.02 - Ability to determine and interpret the following as they apply tothe Loss of Condenser Vacuum: -

Conditions requiring reactor and/orturbine trip X 3.9 1 23000060 Accidental GaseousRadwaste Rel. / 92.1.27 - Conduct of Operations -

Knowledge of system purpose and/or function.X 3.9 1 24000074 Inad. Core Cooling / 4EK3.05 - Knowledge of the reasons for the following responses as theyapply to the Inadequate CoreCooling: - Activating the HPI system X 4.2 1 25CE/A11 RCS Overcooling - PTS

/ 4EK2.1 - Knowledge of the interrelations between the (RCSOvercooling) and the following: -

Components, and functions of controland safety systems, includinginstrumentation, signals, interlocks, failure modes, and automatic andmanual features X 3.2 1 26CE/E09 Functional RecoveryEK1.1 - Knowledge of the operationalimplications of the following concepts as they apply to the (FunctionalRecover): - Components, capacity,and function of emergency systems X 3.4 1 27K/A Category Totals:

1 2 1 1 2 2 9Group Point Totals:ES-401, 23 of 33 Plant Systems - Tier 2/Group 1 (RO)System # / NameK/A Topic(s)

K1 K2 K3 A1 A2 G IR #PWR Examination OutlineES-401Form ES-401-2 4K4K5K6 A3 A3 QID003 Reactor Coolant PumpK5.03 - Knowledge of theoperational implicationsof the following conceptsas they apply to the RCPS: - Effects of RCPshutdown on T-ave.,including the reason for the unreliability of T-ave.in the shutdown loop 3.1 1 X 28004 Chemical and Volume ControlK1.17 - Knowledge of the physical connections and/or cause-effectrelationships between theCVCS and the following systems: - PZR X 3.4 1 29005 Residual Heat RemovalK6.03 - Knowledge of the effect of a loss ormalfunction of thefollowing will have on the RHRS: - RHR heatexchanger 2.5 1 X 30006 Emergency Core CoolingK1.03 - Knowledge of the physical connectionsand/or cause-effect relationships between theECCS and the followingsystems: - RCS X 4.2 1 31007 Pressurizer Relief/Quench TankK4.01 - Knowledge of PRTS design feature(s)and/or interlock(s) whichprovide for the following: -Quench tank cooling 2.6 1 X 32008 Component Cooling WaterA1.01 - Ability to predict and/or monitor changesin parameters (to prevent exceeding design limits)associated with operatingthe CCWS controls including: - CCW flow rate X 2.8 1 33010 Pressurizer Pressure

ControlK4.02 - Knowledge of PZR PCS design feature(s) and/orinterlock(s) which providefor the following: -

Prevention of uncoveringPZR heaters 3.0 1 X 34010 Pressurizer Pressure

ControlA4.01 - Ability to manually operate and/ormonitor in the control room: - PZR spray valve 3.7 1 X 35ES-401, 24 of 33 Plant Systems - Tier 2/Group 1 (RO)System # / NameK/A Topic(s)

K1 K2 K3 A1 A2 G IR #PWR Examination OutlineES-401Form ES-401-2 4K4K5K6 A3 A3 QID012 Reactor ProtectionK2.01 - Knowledge of buspower supplies to thefollowing: - RPSchannels, components, and interconnections X 3.3 1 36013 Engineered SafetyFeatures Actuation2.2.44 - Equipment Control - Ability tointerpret control room indications to verify thestatus and operation of asystem, and understand how operator actions anddirectives affect plant andsystem conditions.

X 4.2 1 37013 Engineered Safety Features ActuationK5.02 - Knowledge of the operational implicationsof the following conceptsas they apply to the ESFAS: - Safety systemlogic and reliability 2.9 1 X 38022 Containment CoolingA4.02 - Ability to manually operate and/ormonitor in the control room: - CCS pumps 3.2 1 X 39022 Containment CoolingA2.01 - Ability to (a) predict the impacts of the following malfunctions oroperations on the CCSand (b) based on those predictions, useprocedures to correct,control, or mitigate the consequences of thosemalfunctions oroperations: - Fan motorover-current X 2.5 1 40026 Containment SprayK3.02 - Knowledge of the effect that a loss ormalfunction of the CSS will have on thefollowing: - Recirculationspray system X 4.2 1 41039 Main and Reheat SteamK3.04 - Knowledge of the effect that a loss ormalfunction of the MRSSwill have on the following: - MFW pumps X 2.5 1 42ES-401, 24 of 33 Plant Systems - Tier 2/Group 1 (RO)System # / NameK/A Topic(s)

K1 K2 K3 A1 A2 G IR #PWR Examination OutlineES-401Form ES-401-2 4K4K5K6 A3 A3 QID059 Main FeedwaterK4.19 - Knowledge ofMFW System designfeature(s) and/orinterlock(s) which provide for the following: -Automatic feedwaterisolation of MFW 3.2 1 X 43059 Main FeedwaterA3.03 - Ability to monitorautomatic operation ofthe MFW System,including: - Feedwaterpump suction flow pressure 2.5 1 X 44061 Auxiliary/Emergency FeedwaterK5.02 - Knowledge of the operational implicationsof the following conceptsas they apply to the AFW System: - Decay heatsources and magnitude 3.2 1 X 45062 AC Electrical DistributionA1.03 - Ability to predict and/or monitor changesin parameters (to prevent exceeding design limits)associated with operatingthe A.C. Distribution System controlsincluding: - Effect oninstrumentation and controls of switchingpower supplies X 2.5 1 46063 DC ElectricalDistribution2.1.27 - Conduct of Operations - Knowledgeof system purpose and/orfunction.X 3.9 1 47063 DC ElectricalDistributionA3.01 - Ability to monitor automatic operation ofthe D.C. Electrical System, including: -Meters, annunciators,dials, recorders, and indicating lights 2.7 1 X 48064 Emergency Diesel GeneratorA4.01 - Ability to manually operate and/or monitor in the controlroom: - Local and remoteoperation of the ED/G 4.0 1 X 49064 Emergency DieselGeneratorK6.08 - Knowledge of the effect of a loss ormalfunction of the following will have on theED/G System: - Fuel oilstorage tanks 3.2 1 X 50ES-401, 24 of 33 Plant Systems - Tier 2/Group 1 (RO)System # / NameK/A Topic(s)

K1 K2 K3 A1 A2 G IR #PWR Examination OutlineES-401Form ES-401-2 4K4K5K6 A3 A3 QID073 Process RadiationMonitoringK3.01 - Knowledge of the effect that a loss ormalfunction of the PRMSystem will have on the following: - Radioactiveeffluent releases X 3.6 1 51076 Service WaterA2.02 - Ability to (a) predict the impacts of thefollowing malfunctions or operations on the SWSand (b) based on thosepredictions, useprocedures to correct,control, or mitigate the consequences of thosemalfunctions oroperations: - Service water header pressure X 2.7 1 52078 Instrument AirK2.01 - Knowledge of buspower supplies to thefollowing: - Instrument air compressor X 2.7 1 53103 ContainmentA2.05 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on theContainment System and (b) based on thosepredictions, useprocedures to correct, control, or mitigate theconsequences of thosemalfunctions or operations: - Emergencycontainment entry X 2.9 1 54103 Containment2.1.23 - Conduct of Operations - Ability toperform specific system and integrated plantprocedures during allmodes of plant operation.

X 4.3 1 55K/A Category Totals:

2 2 3 2 3 3 28Group Point Totals:

3 3 2 2 3ES-401, 24 of 33 Plant Systems - Tier 2/Group 2 (RO)System # / NameK/A Topic(s)

K1 K2 K3 A1 A2 G IR #PWR Examination OutlineES-401Form ES-401-2 5K4K5K6 A3 A3 QID001 Control Rod DriveK2.05 - Knowledge of buspower supplies to thefollowing: - M/G sets X 3.1 1 56014 Rod Position IndicationK4.06 - Knowledge of RPIS design feature(s)and/or interlock(s) whichprovide for the following: -Individual and group misalignment 3.4 1 X 57016 Non-nuclear InstrumentationA4.02 - Ability to manually operate and/or monitor in the controlroom: - Recorders 2.7 1 X 58017 In-core Temperature MonitorK6.01 - Knowledge of the effect of a loss ormalfunction of thefollowing will have on the ITM Systemcomponents: - Sensorsand detectors 2.7 1 X 59028 Hydrogen Recombinerand Purge ControlA1.02 - Ability to predict and/or monitor changesin parameters (to prevent exceeding design limits)associated with operatingthe HRPS controlsincluding: - Containmentpressure X 3.4 1 60034 Fuel Handling EquipmentA3.03 - Ability to monitor automatic operation ofthe Fuel HandlingSystem, including: - High flux at shutdown 2.9 1 X 61045 Main TurbineGeneratorK3.01 - Knowledge of the effect that a loss ormalfunction of the MT/G System will have on thefollowing: - Remainder ofthe plant X 2.9 1 62068 Liquid RadwasteA2.02 - Ability to (a) predict the impacts of the following malfunctions oroperations on the LiquidRadwaste System and (b) based on thosepredictions, useprocedures to correct,control, or mitigate theconsequences of those malfunctions oroperations: - Lack of tankrecirculation prior to release X 2.7 1 63ES-401, 25 of 33 Plant Systems - Tier 2/Group 2 (RO)System # / NameK/A Topic(s)K1K2K3A1A2 G IR#PWR Examination OutlineES-401Form ES-401-2 5K4K5K6 A3 A3 Q075 Circulating Water2.1.28 - Conduct ofOperations - Knowledgeof the purpose andfunction of major systemcomponents and controls.

X 4.1 1 64086 Fire ProtectionK5.04 - Knowledge of theoperational implicationsof the following conceptsas they apply to the FireProtection System: -Hazards to personnel asa result of fire type andmethods of protection 2.9 1 X 65K/A Category Totals:

0 1 1 1 1 1 10Group Point Totals:

1 1 1 1 1ES-401, 25 of 33 CategoryTopic IR#Facility:ES-401Form ES-401-3Generic Knowledge and Abilities Outline (Tier 3)Date of Exam:

IR#K/A #ROSRO Only QID1 - Conduct ofOperationsKnowledge of administrative requirements for temporary management directives, such as standing orders, night orders,Operations memos, etc.

2.7 12.1.15 66Ability to make accurate, clear, and concise logs, records, status boards, and reports.

3.6 12.1.18 67Subtotal 22 - Equipment ControlKnowledge of the process for conducting special or infrequent tests.2.9 12.2.7 68Knowledge of pre- and post-maintenance operability requirements.

2.9 12.2.21 69Ability to track Technical Specification limiting conditions for operations.

3.1 12.2.23 70Subtotal 33 - Radiological ControlsKnowledge of radiation exposure limits under normal or emergency conditions.

3.2 12.3.4 71Ability to control radiation releases.

3.8 12.3.11 72Knowledge of radiological safety principles pertaining to licensedoperator duties, such as containment entry requirements, fuelhandling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2 12.3.12 73Subtotal 34 - Emergency Procedures/PlanKnowledge of EOP mitigation strategies.

3.7 12.4.6 74Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.

3.1 12.4.26 75Subtotal 2Tier 3 Point Total 10ES-401, 26 of 33 ES-401 Facility:Arkansas Nuclear One Unit 2PWR SRO Examination OutlineForm ES-401-2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0RO K/A Category PointsTierGroup Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&AbnormalPlantEvolutions 1 1 2 2Tier TotalsTier Totals 2.PlantSystems 1 2 3 43. Generic Knowledge And Abilities Categories2. The point total for each group and tier in the proposed outline must match that specified in the table.The final point total for each group and tier may deviate by +/-1 from that specified in the tablebased on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.4. Select topics from as many systems and evolutions as possible; sample every system or evolutionin the group before selecting a second topic for any system or evolution.3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions thatdo not apply at the facility should be deleted and justified; operationally important, site-specificsystems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or highershall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Note:Date of Exam:

08/07/2009 0 0 0 0 0 0 01. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals"in each K/A category shall not be less than two).7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but thetopics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 forthe applicable K/As.8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics'importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handlingequipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the leftside of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.SRO-Only Points A2 G*3 3 2 2 5 5 3 2 2 1 3 2 2 2 1 1 2 3 4 10 4 6 5 3 8 79. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions,IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to10 CFR 55.43.6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0 5 Emergency and Abnormal Evolutions - Tier 1/Group 1 (SRO)E/APE # / Name / Safety FunctionK/A Topic(s)K1K2K3A1A2 G IR#PWR Examination OutlineES-401Form ES-401-2 2 Q000007 Reactor Trip -Stabilization - Recovery / 12.4.45 - Emergency Procedures/Plan -

Ability to prioritize and interpret thesignificance of each annunciator oralarm.X 4.3 1 76000025 Loss of RHR System / 4AA2.04 - Ability to determine andinterpret the following as they apply tothe Loss of Residual Heat RemovalSystem: - Location and isolability of leaks X 3.6 1 77000040 Steam Line Rupture -Excessive Heat Transfer / 4AA2.01 - Ability to determine and interpret the following as they apply tothe Steam Line Rupture: - Occurrence and location of a steam line rupturefrom pressure and flow indications X 4.7 1 78000058 Loss of DC Power / 62.4.20 - Emergency Procedures/Plan -Knowledge of operational implications of EOP warnings, cautions, and notes.

X 4.3 1 79 000065 Loss of Inst rum e nt Ai r / 8 A A 2.0 1 - A bility to d e t e rm ine a n d i n t e rp r et t h e foll ow ing as th e y a p p ly to the L o s s o f In s trum e nt A ir: - Cause and effect of low pressure instrument air alarm X 3.2 1 80CE/E06 Loss of Main Feedwater

/ 42.1.23 - Conduct of Operations -

Ability to perform specific system andintegrated plant procedures during all modes of plant operation.

X 4.4 1 81K/A Category Totals:

0 0 0 0 3 3 6Group Point Totals:ES-401, 22 of 33 Emergency and Abnormal Evolutions - Tier 1/Group 2 (SRO)E/APE # / Name / Safety FunctionK/A Topic(s)K1K2K3A1A2 G IR#PWR Examination OutlineES-401Form ES-401-2 3 Q000037 Steam Generator TubeLeak / 3AA2.06 - Ability to determine andinterpret the following as they apply tothe Steam Generator Tube Leak: -S/G tube failure X 4.5 1 82000059 Accidental LiquidRadWaste Rel. / 92.4.41 - Emergency Procedures/Plan -Knowledge of the emergency actionlevel thresholds and classifications.

X 4.6 1 83000068 Control Room Evac. / 8AA2.05 - Ability to determine andinterpret the following as they apply tothe Control Room Evacuation: -Availability of heat sink X 4.3 1 84000069 Loss of CTMT Integrity /

52.4.46 - Emergency Procedures/Plan -Ability to verify that the alarms areconsistent with the plant conditions.

X 4.2 1 85K/A Category Totals:

0 0 0 0 2 2 4Group Point Totals:ES-401, 23 of 33 Plant Systems - Tier 2/Group 1 (SRO)System # / NameK/A Topic(s)K1K2K3A1A2 G IR#PWR Examination OutlineES-401Form ES-401-2 4K4K5K6 A3 A3 Q006 Emergency CoreCoolingA2.07 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on the ECCSand (b) based on thosepredictions, useprocedures to correct,control, or mitigate theconsequences of thosemalfunctions oroperations: - Loss of heattracing X 3.1 1 86012 Reactor ProtectionA2.01 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on the RPSand (b) based on thosepredictions, useprocedures to correct,control, or mitigate theconsequences of thosemalfunctions oroperations: - Faultybistable operation X 3.6 1 87039 Main and ReheatSteam2.4.11 - EmergencyProcedures/Plan -Knowledge of abnormalcondition procedures.

X 4.2 1 88061 Auxiliary/EmergencyFeedwaterA2.03 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on the AFWSystem and (b) based onthose predictions, useprocedures to correct,control, or mitigate theconsequences of thosemalfunctions oroperations: - Loss of dcpower X 3.4 1 89078 Instrument Air2.2.36 - EquipmentControl - Ability toanalyze the effect ofmaintenance activities,such as degraded power sources, on the status oflimiting conditions foroperations.

X 4.2 1 90K/A Category Totals:

0 0 0 0 3 2 5Group Point Totals:

0 0 0 0 0ES-401, 24 of 33 Plant Systems - Tier 2/Group 2 (SRO)System # / NameK/A Topic(s)K1K2K3A1A2 G IR#PWR Examination OutlineES-401Form ES-401-2 5K4K5K6 A3 A3 Q071 Waste Gas DisposalA2.09 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on the WasteGas Disposal Systemand (b) based on thosepredictions, useprocedures to correct,control, or mitigate theconsequences of thosemalfunctions oroperations: - Stuck-openrelief valve X 3.5 1 91072 Area RadiationMonitoring2.2.40 - EquipmentControl - Ability to applyTechnical Specificationsfor a system.

X 4.7 1 92029 Containment PurgeA2.01 - Ability to (a)predict the impacts of thefollowing malfunctions oroperations on theContainment PurgeSystem and (b) based onthose predictions, useprocedures to correct,control, or mitigate theconsequences of thosemalfunctions oroperations: -Maintenance or otheractivity taking placeinside containment X 3.6 1 93K/A Category Totals:

0 0 0 0 2 1 3Group Point Totals:

0 0 0 0 0ES-401, 25 of 33 CategoryTopic IR#Facility:ES-401Form ES-401-3Generic Knowledge and Abilities Outline (Tier 3)Date of Exam:

IR#K/A #ROSRO Only Q1 - Conduct ofOperationsAbility to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior,and instrument interpretation.

4.7 12.1.7 94Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.4 12.1.23 95Subtotal 22 - Equipment Control Knowl e dge of the process for controlling temporary design changes.

3.3 1 2.2. 1 1 96Knowledge of the process used to track inoperable alarms.

3.3 12.2.43 97Subtotal 23 - Radiological Controls Abil it y to approve release permits.

3.8 1 2.3.6 98Knowledge of radiation monitoring systems, such as fixed radiationmonitors and alarms, portable survey instruments, personnelmonitoring equipment, etc.

3.1 12.3.15 99Subtotal 24 - Emergency Procedures/PlanKnowledge of EOP mitigation strategies.

4.7 12.4.6 100Subtotal 1Tier 3 Point Total 7ES-401, 26 of 33 ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 1 of 6Tier /GroupRandomlySelected K/AReason for RejectionQID #6026 Loss of CCWGeneric 2.2.17 -Knowledge of themaintenanceactivities duringpower operations,such as riskassessments, workprioritation.This K&A is more directed to the SRO applicant and is not one ofthe required Generic K&As to be used in Tier 1 and 2 as directedby NUREG 1021 ES-410 section D.1.b. therefore, it was rejectedand another generic 2.2 K&A was randomly selected form the listin NUREG 1021 ES-401 Section D1.b.Generic 2.2.44 - Ability to interpret control room indications toverify the status and operation of a system, and understand howoperator actions and directives affect plant and system conditionswas randomly selected from the Generic K&A list in NUREG1021 ES-401 Section D1.b. for this category.QID #9 038 SteamGenerator TubeRuptureEK3.07 - Knowledgeof the reasons for thefollowing responsesas they apply to theSGTR: - RCS loopisolation valuesThis K&A is not applicable to ANO since the RCS at ANO doesnot have RCS loop isolation valves therefore, a credible andoperationally valid question can not be developed on this K&A.EK3.02 - Knowledge of the reasons for the following responses asthey apply to the SGTR: - Prevention of secondary PORV cyclingwas randomly selected as a replacement from the other EK3 K&Astatements under this category with a RO importance rating of >2.5.RO ExamTier 1Group 1QID #10054 Loss of MainFeedwater2.3.7 - Ability tocomply with radiationwork permitrequirements duringnormal or abnormalconditions.This K&A does not directly tie to the MFW system and is not oneof the required Generic K&As to be used in Tier 1 and 2 asdirected by NUREG 1021 ES-401 section D.1.b. therefore, it wasrejected and another generic K&A was randomly selected form thelist in NUREG 1021 ES-401 Section D1.b.2.4.6 Emergency Procedures/Plan - Knowledge of EOP mitigationstrategieswas randomly selected from the Generic K&A list inNUREG 1021 ES-401 Section D1.b. for this category.

ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 2 of 6Tier /GroupRandomlySelected K/AReason for RejectionQID #37013 ESF Actuation2.3.7Ability to complywith radiation workpermit requirementsduring normal orabnormal conditions.This K&A is not one of the required Generic K&As to be usedin Tier 1 and 2 as directed by NUREG 1021 ES-401 sectionD.1.b. therefore, it was rejected and another generic K&A wasrandomly selected form the list in NUREG 1021 ES-401 SectionD1.b.2.2.44 Equipment Control - Ability to interpret control roomindications to verify the status and operation of a system, andunderstand how operator actions and directives affect plant andsystem conditionswas randomly selected from the Generic K&Alist in NUREG 1021 ES-401 Section D1.b. for this category.QID #49064 Emergency DieselGenerator.A4.04 -Ability tomanually operateand/or monitor in thecontrol room: - Remoteoperation of the aircompressor switch(different modes)ANO Unit 2 does not have the capability to operate theEmergency Diesel Generator air compressors remotely;therefore, a credible and operationally valid question can not bedeveloped on this K&A; therefore, it was rejected and anothergeneric K&A was randomly selected from the A4 section ofK&As for EDGsA4.01 - Ability to manually operate and/or monitor in thecontrol room: - Local and remote operation of the ED/Gwasrandomly selected as a replacement from the other A4 K&Astatements under this category with a RO importance rating of >2.5.QID #50064 Emergency DieselGenerator.K6.07 Knowledge ofthe effect of a loss ormalfunction of thefollowing will have onthe ED/G System: - AirreceiversThis K&A statement was randomly selected on the last 2 NRCexams given to Unit 2 and 2 different questions on EDG airreceivers was used. This K&A was rejected due to oversampling of this K&A statement on the 2 previous NRC Examsand no additional operationally valid questions could begenerated.K6.08 - Knowledge of the effect of a loss or malfunction of thefollowing will have on the ED/G System: - Fuel oil storage tankswas selected as a replacement from the other K6 K&Astatements under this category with a RO importance rating of >2.5.RO ExamTier 2Group 1QID #53078 Instrument AirSystemK2.02 Knowledge ofbus power supplies toemergency aircompressors.ANO Unit 2 does not have an emergency air compressor for anIA backup. Unit 2 and Unit 1 IA systems are normally cross tiedto allow for backup air in case of a problem on the oppositeunit.; therefore, a credible and operationally valid question cannot be developed on this K&A.

K2.01- Knowledge of bus power supplies to the following: -Instrument air compressorwas selected as a replacement fromthe other K2 K&A statements under this category with a ROimportance rating of > 2.5.

ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 3 of 6QID #54103 ContainmentSystemA2.04 Ability to (a)predict the impacts of the following malfunctions or operations on the Containment System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of thosemalfunctions oroperations: -

Containment evacuation (including recognition of the

alarm)This K&A was rejected due to the similarities between question

  1. 22 K&A 036 AA1.03 and over sampling of the containment evacuation alarm.A2. 05- Ability to (a) predict the impacts of the followingmalfunctions or operations on the Containment System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Emergency Containment Entrywas randomly sel ect ed a s a r epla cem en t f r om th e oth er A 2 K&A s t at em en t sunder this category with a RO importance rating of > 2.5.RO ExamTier 2Group 1QID #55103 ContainmentSystem2.1.34 Conduct ofOperations -

Knowledge of primary and secondary plant chemistry limits.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.2.1.23 Conduct of Operations - Ability to perform specificsystem and integrated plant procedures during all modes of plant operationwas randomly selected from the Generic K&Alist in NUREG 1021 ES-401 Section D1.b. for this category.RO ExamTier 2Group 2QID #64075 Circulating Water Generic 2.2.3 -Equipment Control -

(multi-unit license)

Knowledge of the design, procedural, and operational differences between units.Although there are 2 units here at ANO, they are not of the same vender design and a Unit 2 operator cannot operate the Unit 1 plant; therefore, this K&A statement does not apply and is being rejected as directed by NUREG 1021 ES-401 section D.1.b. This K&A was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.Generic 2.1.28 - Conduct of Operations - Knowledge of thepurpose and function of major system components and control was randomly selected from the Generic K&A list in NUREG 1021 ES-401 Section D1.b. for this category.

ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 4 of 6Tier /GroupRandomlySelected K/AReason for RejectionQID #76007 Reactor Trip -Stabilization -

RecoveryGeneric 2.2.19 -Knowledge ofmaintenance work order requirementsThis K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 SectionD1.b.Generic 2.4.45 - Emergency Procedures/Plan - Ability toprioritize and interpret the significance of each annunciator or

alarm was randomly selected from the Generic K&A list inNUREG 1021 ES-401 Section D1.b. for this category.QID #79058 Loss of DC Power Generic 2.4.16 -Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures,abnormal operatingprocedures, and severe accident management guidelines.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.Generic 2.4.20 - Emergency Procedures/Plan - Knowledge ofoperational implications of EOP warnings, cautions, and notes was randomly selected from the Generic K&A list in NUREG 1021 ES-401 Section D1.b. for this category.QID #80CE/E06 Loss ofInstrument Air AA2.05 Ab i li t y to in t erpret t h e fo l l o w ing as t h ey ap p lyto the Loss of Instrument Air: - Whento commence plantshutdown if instrument air pressure is decreasingThis K&A statement was randomly selected on the last 2 NRC exams given to Unit 2 and 2 different questions on when to shutdown on loss of IA was used. This K&A was rejected due to over sampling of this K&A statement on the 2 previous NRC Exams and no additional operationally valid questions could be generated.AA2.01 Ability to determine and interpret the following as theyapply to the Loss of Instrument Air: - Cause and effect of low-pressure instrument air alarmwas randomly selected as areplacement from the other AA2 K&A statements under thiscategory with a SRO importance rating of > 2.5.SRO ExamTier 1Group 1QID #81CE/E06 Loss of MainFeedwaterGeneric 2.2.23 -Equipment Control -

Ability to track Technical Specification limiting conditions for operations.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.Generic 2.1.23 - Conduct of Operations - Ability to performspecific system and integrated plant procedures during all modes of plant operation was randomly selected from theGeneric K&A list in NUREG 1021 ES-401 Section D1.b. forthis category.

ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 5 of 6SRO ExamTier 1Group 2QID #83059 Accidental LiquidRad waste Release.Generic 2.4.5 -Emergency Procedures/Plan -

Knowledge of the organization of theoperating proceduresnetwork for normal, abnormal, and emergency evolutions.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.Generic 2.4.41 - Emergency Procedures/Plan - Knowledge ofthe emergency action level thresholds and classifications wasrandomly selected from the Generic K&A list in NUREG 1021ES-401 Section D1.b. for this category.SRO ExamTier 2Group 1QID #88039 Main and ReheatSteamGeneric 2.2.6 -Equipment Control -

Knowledge of the process for making changes to procedures.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A was randomly selected form the list in NUREG 1021 ES-401 Section D1.b.Generic 2.4.11 - Emergency Procedures/Plan - Knowledge ofabnormal condition procedures was randomly selected from theGeneric K&A list in NUREG 1021 ES-401 Section D1.b. for this category.QID #92072 Area RadiationMonitoringGeneric 2.2.35Equipment Control -Ability to determine Technical Specification Mode of Operation.This K&A is not one of the required Generic K&As to be used in Tier 1 and 2 as directed by NUREG 1021 ES-401 section D.1.b. therefore, it was rejected and another generic K&A wasrandomly selected form the list in NUREG 1021 ES-401 SectionD1.b.Generic 2.2.40 - Equipment Control - Ability to apply TechnicalSpecifications for a systemwas randomly selected from theGeneric K&A list in NUREG 1021 ES-401 Section D1.b. for this category.SRO ExamTier 2Group 2QID #93079 Station Air System A2.01 Ability to (a)predict the impacts of the following malfunctions or operations on the SASand (b) based on thosepredictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: - Cross-connection with IAS

.Un i t 2 does n ot h a ve a cr oss con n ect i on w i th the IAS and the Sta ti on A ir System, th er ef o r e, a c r ed i ble an d oper a t i o n al l y va l i dquestion can not be developed on this K&A statement or any others Station Air K&A statements. (most have an importance rating of less than 2.5)

Therefore , t he Co n tain m e n t Pu r ge S y s t e m w asrandomly selected from the Tier 2 Group 2 systems and theoriginally selected A2.01 K&A statement was retained:Abilityto (a) predict the impacts of the following malfunctions or operations on the Containment Purge System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: -

Maintenance or other activity taking place inside Containment.

ES-401Record of Rejected K/As Form ES-401-4NUREG-1021, Revision 9 Supplement 1 Page 6 of 6SRO ExamTier 3QID #100Generic 2.4.35EmergencyProcedures/Plan -Knowledge of localauxiliary operator tasksduring an emergencyand the resultantoperational effects.This K&A is not SRO only knowledge and does not allow anSRO only question to be developed thus this K&A was rejected.Generic K&A 2.4.6,Emergency Procedures/Plan - Knowledgeof EOP mitigation strategies was randomly selected as areplacement from the required section 2.4 generic K&Astatements.

ES-301Administrative Topics OutlineForm ES-301-1Facility: _______ Arkansas Nuclear One_____________Date of Examination: ____8-10-09

_Examination Level: RO X SROOperating Test Number: 2009-1Administrative Topic (see Note)Type Code*Describe activity to be performedConduct of Operations2.1.23 RO (4.3)

P/RDetermine volume of Boric acid and DI water to makeupto RWT.ANO-2-JPM-NRC-ADMIN RWTConduct of Operations2.1.25 RO (3.9)N/RDetermine any applicable technical specifications forCEA positions using the COLR PDILANO-2-JPM-NRC-ADMIN-PDILEquipment Control2.2.12 RO (3.7)D/RSurveillance reviewANO-2-JPM-NRC-2P-35A REVIEWRadiation Control2.3.14 RO (3.4)D/RReview RWP and determine requirements for tagging'B' LPSI pump.ANO-2-JPM-NRC-RWPEmergency Procedures/PlanNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

ES-301Administrative Topics OutlineForm ES-301-1Facility: _______ Arkansas Nuclear One_____________Date of Examination: ____8-10-09

_Examination Level: RO SRO XOperating Test Number: 2009-1Administrative Topic (see Note)Type Code*Describe activity to be performedConduct of Operations2.1.25 SRO (4.2)N/RDetermine if COLR DNBR limit is being met during aloss of COLSS and what action is required.ANO-2-JPM-NRC-ADMIN-DNBRLConduct of Operations2.1.23 SRO (4.4)D/RReview and approve calculation of volume needed toraise SFP level.ANO-2-JPM-NRC-ADMIN-SFPMUEquipment Control2.2.40 SRO (4.7)

P/RDetermine RPS trip set point due to inoperable MSSV iscorrect using Technical Specifications.Ability to apply technical specification for a systemANO-2-JPM-NRC-ADMIN-MSSVINOPRadiation Control2.3.14 SRO (3.8)D/RReview RWP and determine requirements for tagging'B' LPSI pump.ANO-2-JPM-NRC-RWPEmergency Procedures/Plan2.4.44 SRO (4.4)D/RIssue Protective Action Recommendation to OffsiteAuthorities (Time Critical)ANO-2-JPM-NRC-PAR3NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: __Arkansas Nuclear One______________Date of Examination: ____8-10-09

___Exam Level: RO X SRO-I SRO-UOperating Test No.: 2009-1Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction a. ANO-2-JPM-NRC-EOP01026 A2.03 RO 4.1 SRO 4.4Secure Containment Spray System (inadvertent)EN/L/P/S 5ContainmentIntegrityb. ANO-2-JPM-NRC-RCP04003 A2.02 RO-3.7/SRO-3.9RCP ShutdownA/L/M/S 4Heat Removalc. ANO-2-JPM-NRC-SIT01006 A2.03 RO-3.3 SRO-3.7High pressure fill of Safety Injection TankA/P/S 2RCS Inventoryd. ANO-2-JPM-NRC-PZR01010 A4.01 RO-3.7/SRO-3.5Equalize Pressurizer boronD/S 3Pressure Controle. ANO-2-JPM-NRC- VCTMU004 A4.15 RO-3.6 SRO-3.7Perform Manual Makeup to the VCTD/S 1Reactivity controlf. ANO-2-JPM-NRC-ELECXT062 A4.01 RO-3.3/SRO-3.1Cross connect 2B-1 and 2B-2.

A/M/S 6Electrical g.ANO-2-JPM-NRC-CCW02008 A4.01 RO 3.3/SRO 3.1Shift running CCW pumps M/S 8Plant servicesystemsh. ANO-2-JPM-NRC-CPC02015 A3.03 RO-3.9/SRO-3.9DNBR/LPD limits with COLSS out of serviceD/S 7InstrumentationIn-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i.ANO-2-JPM-NRC-AACLS064 A4.01 RO-4.0/SRO-4.3Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6Electricalj. ANO-2-JPM-NRC-XFCEA001 A2.14 RO-3.7/SRO-3.9Transfer a CEA to the hold busD/E 1Reactivity controlk. ANO-2-JPM-NRC-69REL068 A4.02 RO-3.2/SRO-3.1Perform a release of 2T-69A Boric Acid Condensate TankN/R 9RadioactivityRelease@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: __Arkansas Nuclear One______________Date of Examination: ____8-10-09

___Exam Level: RO SRO-I X SRO-UOperating Test No.: 2009-1Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction a. ANO-2-JPM-NRC-EOP01026 A2.03 RO 4.1 SRO 4.4Secure Containment Spray System (inadvertent)EN/L/P/S 5ContainmentIntegrityb ANO-2-JPM-NRC-RCP04003 A2.02 RO-3.7/SRO-3.9RCP Shutdown A/M/S 4Heat Removalc. ANO-2-JPM-NRC-SIT01006 A2.03 RO-3.3 SRO-3.7High pressure fill of Safety Injection TankA/D/P/S 2RCS Inventoryd. ANO-2-JPM-NRC-PZR01010 A4.01 RO-3.7/SRO-3.5Equalize Pressurizer boronD/S 3Pressure Controle. ANO-2-JPM-NRC- VCTMU004 A4.15 RO-3.6 SRO-3.7Perform Manual Makeup to the VCTD/S 1Reactivity controlf. ANO-2-JPM-NRC-ELECXT062 A4.01 RO-3.3/SRO-3.1Cross connect 2B-1 and 2B-2.

A/M/S 6Electrical g.ANO-2-JPM-NRC-CCW02008 A4.01 RO 3.3/SRO 3.1Shift running CCW pumps M/S 8Plant servicesystems h.In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)i. ANO-2-JPM-NRC-AACLS062 A4.01 RO-4.0/SRO-4.3Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6Electricalj. ANO-2-JPM-NRC-XFCEA001 A2.14 RO-3.7/SRO-3.9Transfer a CEA to the hold busD/E 1Reactivity controlk. ANO-2-JPM-NRC-69REL068 A4.02 RO-3.2/SRO-3.1Perform a release of 2T-69A Boric Acid Condensate TankN/R 9RadioactivityRelease@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: __Arkansas Nuclear One______________Date of Examination: ____8-10-09

___Exam Level: RO SRO-I S R O-U X O perat i ng T e s t No.: ____2009-1_________Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunctiona. ANO-2-JPM-NRC-EOP01026 A2.03 RO 4.1 SRO 4.4Secure Containment Spray System (inadvertent)EN/L/P/S 5ContainmentIntegrityb. ANO-2-JPM-NRC-RCP04003 A2.02 RO-3.7/SRO-3.9 RCP ShutdownA/L/M/S 4Heat Removal c.d.e.f.g.h.In-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)i. ANO-2-JPM-NRC-AACLS062 A4.01 RO-4.0/SRO-4.3 Start up AAC diesel generator manually locally during a LOOPA/P/E/L 6Electricalj. ANO-2-JPM-NRC-XFCEA001 A2.14 RO-3.7/SRO-3.9 Transfer a CEA to the hold bus D/E 1Reactivity controlk. ANO-2-JPM-NRC-69REL068 A4.02 RO-3.2/SRO-3.1 Perform a release of 2T-69A Boric Acid Condensate TankN/R 9RadioactivityRelease@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank (E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 ES-301Transient and Event ChecklistForm ES-301-5 Faci l i ty: Arkans a s N u c l e ar One Date of E x a m : 8-10-09 O per ati ng Test No.: 2009-1Scenarios 1 2 3 4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION M I N

I M U M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 5 11 1 0NOR 1 4 2 21 1 1 I/C 3,4 1,2,8 3,7,8 54 4 2 MAJ 6,8 5,6 5 32 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 4 1 11 1 0NOR 1,5 21 1 1 I/C 2,7,9 3,7 4,6 54 4 2 MAJ 6,8 5,6 5 32 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 01 1 0NOR 1,5 4 21 1 1 I/C 2,3,4, 7,9 1,2,3, 7,8 54 4 2 MAJ 6,8 5,6 22 2 1 ROSRO-ISRO-U X TS 2,5 1,3 20 2 2 RX 01 1 0NOR 1,2 21 1 1 I/C 3,4,6, 7,8 54 4 2 MAJ 5 12 2 1 ROSRO-ISRO-U X TS 3,5 20 2 2Instructions:

1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.

2.Reactivity manipulations may be conducted under normal orcontrolled abnormal conditions (refer toSection D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3. Whenever practical, both instrument and component malfunctions should be included; only thosethat require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301Transient and Event ChecklistForm ES-301-5 Faci l i ty: Arkans a s N u c l e ar One Date of E x a m : 8-10-09 O per ati ng Test No.: 2009-1Scenarios 1 2 3 4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION M I N

I M U M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 1 11 1 0NOR 1,5 4 21 1 1 I/C 2,3,4, 7,9 1,2,3, 7,8 4,6 74 4 2 MAJ 6,8 5,6 5 32 2 1 ROSRO-I XSRO-U TS 2,5 1,3 20 2 2 RX 5 4 11 1 0NOR 1 1,2 31 1 1 I/C 3,4 3,7 3,4,6, 7,8 74 4 2 MAJ 6,8 5,6 5 32 2 1 ROSRO-I XSRO-U TS 3,5 20 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2Instructions:

1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.

2.Reactivity manipulations may be conducted under normal orcontrolled abnormal conditions (refer toSection D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3. Whenever practical, both instrument and component malfunctions should be included; only thosethat require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

Appendix D Scenario 1Form ES-D-1Page 1 of 26Facility: ANO-2Scenario No.: 1 (New)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:100% MOL, All Engineered Safety Features systems are in standby. 2PCV-0231 jacked closed. GreenTrain Maintenance Week. The 'B' Charging pump seal water pump is in hand and has been running for30 min.Turnover:100%. 260 EFPD. EOOS indicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control sealsteam pressure. Green Train Maintenance Week. 'C' Charging pump will be removed from service forrepack. Place 'B' Charging pump is service and secure 'C' Charging pump. Steps 8.1.1 and 8.1.2 arecomplete.EventNo.Malf. No.EventType*EventDescription 1N (ATC)N (BOP)N (SRO)Place 'B' Charging pump in service and secure 'C'Charging pump.

2XSG2PT10411 I (BOP)I (SRO)'A' Steam generator safety channel pressure transmitterfails low. Tech Spec for CRS.

3 XCVLDNHXOUI (ATC)I (SRO)Letdown Temperature control valve input fails low.

4CVC2P36BFALC (ATC)C (SRO)'B' Charging pump supply breaker trips due to a motorfault 5RCSLOCATCB N (BOP)R (ATC)N (SRO)15 gpm Reactor Coolant system leak on 'B' cold leg.Tech Spec for CRS 6 LOSE500 LOSE161M (ALL)Loss of Off-Site Power.

7CV15042C (BOP)C (SRO)#2 Emergency Diesel Generator service water outletvalve fails to open. This will result in de-energizing redtrain vital 4160VAC(2A-4) and vital 480VAC (2B-6) 8RCSLOCATCBM (ALL)Reactor Coolant system 'B' cold leg leakage ramps upto 225 gpm over 10 minutes.

9HPI2P89AFALC (BOP)C(SRO)2P89A, 'A' High Pressure Safety Injection pump failsto start automatically.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario 2Form ES-D-1Page 1 of 25Facility: ANO-2Scenario No.: 2 (New)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:100% MOL, All Engineered Safety Features systems are in standby. 2PCV-0231 jacked closed. REDTrain Maintenance Week. 2T-6A Boric Acid Make up tank is aligned for acid reducing shut downchemistry for Unit 1Turnover:100%. 260 EFPD. EOOS indicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control sealsteam pressure. RED Train Maintenance Week. 2T-6A Boric Acid Make up tank is aligned for acidreducing shut down chemistry for Unit 1 refueling outage that starts next week. Containment Sumpneeds to be drained due to high level. Steps 20.1.1 and 20.1.2 of OP-2104.014 have been completed.EventNo.Malf. No.EventType*EventDescription 1CV20601 DO_HS_2060_G DO_HS_2060_RC (BOP)C (SRO)Containment sump drain valve breaker trips duringnormal drain evolution. Tech Spec for SRO 2 SW2P-4AC (BOP)C (SRO)2P-4A Service water pump breaker trips 3XRCCHAPLVLI (ATC)I (SRO)'A' Pressurizer level channel fails High. Tech Spec for SRO 4R (ATC)N (BOP)N (SRO)System Dispatcher call with a TLR to reduce power to ~850MWe within 30 min.

5CV10101M (ALL)'A' Steam Generator MSIV 2CV-1010-1 fails closed.

6 MS1002Z SGAMSIVBEFM (ALL)'A' Steam Generator Safety valve 2PSV-1002 sticksopen.7CEA38STUCKCV48731CVC2P39BC (ATC)C (SRO)Control Element Assembly #38 remains fullywithdrawn when the reactor trips. The VCT outlet willnot close and 2P-39B will trip when the reactor trips.

8ESFCCAS2C (BOP)C (SRO)Green train Containment coolers fail to automatically ormanually actuate.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario 3Form ES-D-1Page 1 of 26Facility: ANO-2Scenario No.: 3 (Modified)Op-Test No.: 2009-1Examiners:Operators:Initial Conditions:~60% MOL, Condenser outer waterboxes placed in service after tube plugging. All Engineered SafetyFeatures systems are in standby. 2PCV-0231 jacked closed. RED Train Maintenance Week.Turnover:~60% power Condenser outer waterboxes placed in service after tube plugging. 260 EFPD. EOOSindicates 'Minimal Risk'. 2PCV-0231 jacked closed, manually control seal steam pressure. RED TrainMaintenance Week. The previous shift has completed steps 10.1.1 through 10.1.6 and section 10.2 ofstarting the second heater drain pump and 'B' Heater drain pump needs to be placed in service. 2Condensate pumps are running with Condensate recirculation valves in manual.EventNo.Malf. No.EventType*EventDescription 1(New)N (SRO)R (ATC)Power escalation following a forced outage.

2(New)N (BOP)N (SRO)Place the 'B' Heater Drain pump in service.

3NIBLINEPWR(Modified)

I (BOP)I (SRO)'B' channel nuclear instrument fails high. Tech Spec forSRO.4XRCCHBPCNT(New)I (ATC)I (SRO)Pressurizer control channel pressure fails high.

5SGBTUBE(Modified)M (ALL)'B' Steam Generator tube leakage ramps up to 275 gpmover 25 minutes. Manual reactor trip criteria whengreater than 44 gpm. Tech Spec for SRO 6RPSRXMANRPSRXAUTO(New)C (ATC)C (SRO)Failure of the reactor protection system to automaticallyor manually trip the reactor.

7 OP5130OP5134 (New)C (BOP)C (SRO)Generator output breakers fail to open automatically 8CNDVACPPA CND2C5BC (BOP)C (SRO)2C-5A Vacuum pump trip2C-5B Vacuum pump fails to auto start.* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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