ML101270159

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2010-03 Draft Written Outlines
ML101270159
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 03/16/2010
From:
NRC Region 4
To:
Entergy Operations
References
50-313/10-03, 50-368/10-03 license-operator, part 55 exam material
Download: ML101270159 (20)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One - Unit 1 Date of Exam: 3/5/2010 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 3 3 3 3 18 6 Emergency &

Abnormal 2 2 2 1 N/A 1 2 N/A 1 9 4 Plant Evolutions Tier Totals 5 5 4 4 5 4 27 10 1 3 3 2 3 3 2 2 2 2 3 3 28 5 2.

Plant 2 0 1 1 1 1 1 1 1 1 1 1 10 3 Systems Tier Totals 3 4 3 4 4 3 3 3 3 4 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and 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).
2. 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 table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the 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 handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. 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 to 10 CFR 55.43.

ES-401 1 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety K K K A A G K/A Topic(s) IR # QID Type Function 1 2 3 1 2 000007 (BW/E02&E10; X EK3.01 - Actions contained in EOP for 4.0 1 770 M CE/E02) Reactor Trip - reactor trip Stabilization - Recovery / 1 2.2.37 - Ability to determine operability 000008 Pressurizer Vapor X and/or availability of safety related 3.6 2 771 N Space Accident / 3 equipment 000009 Small Break LOCA / 3 X EA1.02 - RB Sump level 3.8 3 772 N 000011 Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 4 198 D 000015/17 RCP Malfunctions / X AK2.10 - RCP indicators and controls. 2.8* 5 609 D 4

000022 Loss of Rx Coolant Not selected N/A Makeup / 2 AK1.01 - Loss of RHRS during all modes of 000025 Loss of RHR System / X operation. 3.9 6 773 N 4

000026 Loss of Component Not selected N/A Cooling Water / 8 AK2.03 - Controllers and positioners.

000027 Pressurizer Pressure X 2.6 7 395 D Control System Malfunction / 3 000029 ATWS / 1 X EA2.02 - Reactor trip alarm. 4.2 8 582 N 000038 Steam Gen. Tube X 2.4.6 - Knowledge of EOP mitigation 3.7 9 364 D Rupture / 3 strategies.

000040 (BW/E05; CE/E05; X AK1.01 - Consequence of PTS. 4.1 10 551 D W/E12) Steam Line Rupture -

Excessive Heat Transfer / 4 AA2.06 - AFW adjustments needed to 000054 (CE/E06) Loss of Main X maintain proper T-ave, and S/G level. 4.0 11 774 M Feedwater / 4 EA1.05 - Battery, when approaching fully 000055 Station Blackout / 6 X discharged. 3.3 12 496 D AK3.01 - Order and time to initiation of 000056 Loss of Off-site Power / X power for the load sequencer. 3.5 13 366 D 6

AA2.05 - S/G pressure and level meters.

000057 Loss of Vital AC Inst. X 3.5 14 624 D Bus / 6 AK1.01 - Battery charger equipment and 000058 Loss of DC Power / 6 X instrumentation. 2.8 15 187 D 000062 Loss of Nuclear Svc X AK3.02 - The automatic actions 3.6 16 281 D Water / 4 (alignments) within the nuclear service water resulting from the actuation of the ESFAS.

000065 Loss of Instrument Air / Not selected N/A 8

W/E04 LOCA Outside Not selected N/A Containment / 3 ES-401 2 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety K K K A A G K/A Topic(s) IR # QID Type Function 1 2 3 1 2 W/E11 Loss of Emergency Not selected N/A Coolant Recirc. / 4 BW/E04; W/E05 Inadequate X EA1.3 - Desired operating results during 3.6 17 335 D Heat Transfer - Loss abnormal and emergency situations.

of Secondary Heat Sink / 4 000077 Generator Voltage and X 2.1.25 - Ability to interpret reference material, 3.9 18 775 N Electric Grid Disturbances / 6 such as graphs, curves, tables, etc.

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401 3 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR # QID Typ 1 2 3 1 2 e 000001 Continuous Rod Withdrawal / 1 Not selected N/A 000003 Dropped Control Rod / 1 Not selected N/A 000005 Inoperable/Stuck Control Rod / 1 Not selected N/A 000024 Emergency Boration / 1 Not selected N/A 000028 Pressurizer Level Malfunction / 2 X AK1.01 - PZR reference leak 2.8* 19 776 N abnormalities.

000032 Loss of Source Range NI / 7 X AA2.04 - Satisfactory source-range / 3.1 20 777 N intermediate-range overlap 000033 Loss of Intermediate Range NI / 7 Not selected N/A 000036 (BW/A08) Fuel Handling Accident AK2.1 - Changed to randomly selected N/A

/8 System 068 AK2.07 AA1.10 - CVCS makeup tank level 000037 Steam Generator Tube Leak / 3 X indicator 2.9 21 778 N 000051 Loss of Condenser Vacuum / 4 Not selected N/A 000059 Accidental Liquid RadWaste Rel. / Not selected N/A 9

000060 Accidental Gaseous Radwaste AK1.04 - Changed to randomly N/A Rel. / 9 selected System 028 AK1.01 000061 ARM System Alarms / 7 X AK3.02 - Guidance contained in alarm 3.4 22 634 D response for ARM system.

000067 Plant Fire On-site / 8 X AK1.02 - Fire Fighting 3.1 23 695 DR 000068 (BW/A06) Control Room Evac. / 8 X AK2.07 - ED/G 3.3 24 779 D 000069 (W/E14) Loss of CTMT Integrity / Not selected N/A 5

000074 (W/E06&E07) Inad. Core Cooling Not selected N/A

/4 000076 High Reactor Coolant Activity / 9 Not selected N/A W/EO1 & E02 Rediagnosis & SI Not selected N/A Termination / 3 W/E13 Steam Generator Over-pressure / Not selected N/A 4

W/E15 Containment Flooding / 5 Not selected N/A W/E16 High Containment Radiation / 9 Not selected N/A BW/A01 Plant Runback / 1 Not selected N/A BW/A02&A03 Loss of NNI-X/Y / 7 Not selected N/A BW/A04 Turbine Trip / 4 Not selected N/A BW/A05 Emergency Diesel Actuation / 6 X AK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual 4.0 25 349 D features.

AA2.2 - Adherence to appropriate BW/A07 Flooding / 8 X procedures and operation within the 3.3 26 780 N limitations in the facility's license and amendments BW/E03 Inadequate Subcooling Margin / Not selected N/A 4

ES-401 4 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 BW/E08; W/E03 LOCA Cooldown - Not selected N/A Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Not selected N/A Circ. / 4 2.2.22- Knowledge of limiting conditions BW/E13&E14 EOP Rules and Enclosures X for operations and safety limits. 4.0 27 595 N CE/A11; W/E08 RCS Overcooling - PTS / Not selected N/A 4

CE/A16 Excess RCS Leakage / 2 Not selected N/A CE/E09 Functional Recovery Not selected N/A K/A Category Point Totals: 2 2 1 1 2 1 Group Point Total: 9 ES-401 5 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A G K/A Topic(s) IR # QID Ty 1 2 3 4 5 6 1 2 3 4 pe K5.05 - The dependency of 003 Reactor Coolant Pump X X RCS flow rates upon the 2.8* 28 781 N number of operating RCPs A4.08 - RCP cooling water 3.2 29 782 M supplies 2.1.34 changed to 2.2.38 -

004 Chemical and Volume X Knowledge of conditions and 3.6 30 796 N Control limitations in the facility license K4.03 - Protection of ion X exchangers (high letdown 2.8* 31 259 D temperatures will isolate ion exchangers) 005 Residual Heat Removal X K2.01 - RHR Pumps 3.0* 32 786 M 006 Emergency Core Cooling X K6.10 - Valves 2.6 33 783 M 007 Pressurizer Relief/Quench X K5.02 - Method of forming a 3.1 34 561 D Tank steam bubble in the PZR 008 Component Cooling Water X A2.08 changed to A2.01 - 3.3 35 787 N Loss of CCW Pump 010 Pressurizer Pressure X K3.02 - RPS 4.0 36 788 N Control 012 Reactor Protection X K6.10 - Permissive circuits 3.3 37 784 N X 2.1.32 - Ability to explain and 3.8 38 785 N apply system limits and precautions 013 Engineered Safety Features X K4.10 - Safeguards 3.3 39 144 D Actuation equipment control reset 022 Containment Cooling X A3.01 - Initiation of 4.1 40 135 D safeguards mode of operation 025 Ice Condenser Not Selected N/A 026 Containment Spray X K1.01 - ECCS 4.2 41 78 D 039 Main and Reheat Steam X A2.04 - Malfunctioning steam 3.4 42 202 D dump 059 Main Feedwater X A3.03 - Feed water pump 2.5 43 195 D suction flow pressure K4.16 - Automatic trips for X MFW pumps 3.1 44 789 N 061 Auxiliary/Emergency X A1.04 changed to A1.01 - 3.9 45 270 D Feedwater S/G level ES-401 6 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A G K/A Topic(s) IR # QID Ty 1 2 3 4 5 6 1 2 3 4 pe 062 AC Electrical Distribution X 2.4.35 - Knowledge 3.8 46 790 N of local auxiliary operator tasks during an emergency and the X resultant operational effects.

3.3 47 316 D K2.01 - Major system loads 063 DC Electrical Distribution X K3.02 - 3.5 48 86 D Components using DC control power 064 Emergency Diesel Generator X K2.01 - Air 2.7 49 791 N compressor X 3.4 50 792 N K1.05 - Starting air system 073 Process Radiation Monitoring X K5.01 - Radiation 2.5 51 672 R theory, including sources, types, units, and effects 076 Service Water X A4.02 - SWS valves 2.6 52 793 D X A1.02 - Reactor and 2.6 53 794 N turbine building closed cooling water temperatures 078 Instrument Air X K1.03 changed to 2.7 54 535 D K1.02 - Service air 103 Containment X A4.06 - Operation of 2.7 55 795 D the containment personnel airlock K/A Category Point Totals: 3 3 2 3 3 2 2 2 2 3 3 Group Point Total: 28 ES-401 7 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

Type System # / Name K K K K K K A A A A G K/A Topic(s) IR # QID 1 2 3 4 5 6 1 2 3 4 K2.05 changed to K2.02 -

001 Control Rod Drive X One-line diagram of power 3.6 56 429 D supply to trip breakers 002 Reactor Coolant X A2.01- Loss of coolant 4.3 57 604 D inventory A3.03- Charging and 011 Pressurizer Level Control X letdown 3.2 58 797 N 014 Rod Position Indication X K4.05 - Rod hold interlocks 3.1 59 308 D 015 Nuclear Instrumentation X K3.04 - ICS 3.4 60 299 D 016 Non-nuclear Instrumentation X K5.01- Separation of control 2.7 61 77 D and protection circuits K6.01- Sensors and 017 In-core Temperature Monitor X detectors. 2.7 62 240 D 027 Containment Iodine Removal Not selected N/A 028 Hydrogen Recombiner Not selected N/A and Purge Control 029 Containment Purge Not selected N/A 033 Spent Fuel Pool Cooling Not selected N/A 034 Fuel Handling Equipment Not selected N/A 035 Steam Generator Not selected N/A 041 Steam Dump/Turbine Not selected N/A Bypass Control 045 Main Turbine Generator X A4.06- Turbine stop valves 2.8 63 138 D 055 Condenser Air Removal Not selected N/A 056 Condensate Not selected N/A 068 Liquid Radwaste K4.01- Safety and environmental precautions for handling hot, acidic, and N/A radioactive liquids Rejected system to 014 Rod Position Indication K3.05 - ARM and PRM 071 Waste Gas Disposal systems Rejected system N/A to 015 Nuclear Instrumentation 072 Area Radiation Monitoring Not selected N/A 075 Circulating Water X 2.4.11- Knowledge of 4.0 64 798 N abnormal condition procedures-079 Station Air Not selected N/A 086 Fire Protection X A1.01- Fire header pressure 2.9 65 542 D K/A Category Point Totals: 0 1 1 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401 8 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-3 Facility: Arkansas Nuclear One - Unit 1 Date of Exam: 3/5/2010 Category K/A # Topic RO IR # QID Type#

2.1.23 Ability to perform specific system and integrated plant 4.3 66 482 D procedures during all modes of plant operation.

1. 2.1.31 Ability to locate control room switches, controls, and indications, 4.6 67 800 N Conduct and to determine that they correctly reflect the desired plant of Operations lineup.

2.1.32 Ability to explain and apply system limits and precautions. 3.8 68 799 N Subtotal 3 2.2.1 Ability to perform pre-startup procedures for the facility, including 4.5 69 160 D operating those controls associated with plant equipment that could effect reactivity.

2. 2.2.37 Ability to determine operability and / or availability of safety 3.6 70 801 N Equipment related equipment Control Subtotal 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 71 802 N emergency conditions.

2.3.11 Ability to control radiation releases. 3.8 72 436 R 3.

Radiation Control Subtotal 2 2.4.6 Knowledge of EOP mitigation strategies. 3.7 73 803 N 2.4.11 Knowledge of abnormal condition procedures. 4.0 74 161 D 4.

Emergency 2.4.50 Ability to verify system alarm setpoints and operate controls 4.2 75 804 M Procedures / identified in the alarm response manual.

Plan Subtotal 3 Tier 3 Point Total 10 3ES-401 9 Form ES-401-3

ES-401 PWR Examination Outline Form ES-401-4 Tier / Randomly Selected K/A Reason for Rejection Group 1/2 036 Fuel Handling Could not write a credible question since only RO Accident - AK2.01 Fuel action is to suspend fuel movement and exit.

Handling Equipment.

Randomly selected new system 068 Control Room Evacuation - AK2.07 ED/G.

1/2 060 Accidental Gaseous The RO would not perform this function.

Radwaste Release -

Randomly selected new system 028 Pressurizer AK1.04 Calculation of Level Malfunction - AK1.01 Pressurizer reference Offsite Doses due to leak abnormalities.

release from the power plant.

2/1 004 Chemical and Volume Could not write a credible question to match the K/A Control - 2.1.34 and tie to that system.

Knowledge of primary and secondary chemistry Randomly selected - 2.2.38 Knowledge of conditions limits. and limitations in the facility license.

2/1 008 Component Cooling No credible tie for this K/A exists for the System.

Water - A2.08 Effects of Randomly selected A2.01 - Loss of CCW Pump.

shutting (automatically or otherwise) the isolation valves of the letdown cooler.

2/1 061 Emergency/Auxiliary Not possible to prepare a psychometrically sound Feedwater - A1.04 AFW question related to the subject K/A.

source tank level Randomly selected - A1.01 S/G level.

2/1 078 Instrument Air System Not possible to prepare a psychometrically sound (IAS) - K1.03 question related to the subject K/A.

Containment Air.

Randomly selected - K1.02 Service Air.

2/2 001 Control Rod Drive - No credible tie for this K/A exists for the System.

K2.05 M/G Sets Randomly selected - K2.02 One-line diagram of power supply to trip breakers.

3ES-401 10 Form ES-401-4

ES-401 PWR Examination Outline Form ES-401-4 Tier / Randomly Selected K/A Reason for Rejection Group 2/2 068 Liquid Radwaste - The RO would not perform this function.

K4.01 Safety and Randomly selected new system 014 Rod position environmental precautions indication - K4.05 Rod hold interlocks.

for handling hot, acid, and radioactive liquids.

2/2 071 Waste Gas Disposal - Not possible to prepare a psychometrically sound K3.05 ARM and PRM question related to the subject K/A.

systems.

Randomly selected new system 015 Nuclear Instrumentation - K3.04 ICS.

3ES-401 11 Form ES-401-4

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One - Unit 1 Date of Exam: 3/5/2010 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 6 Emergency &

Abnormal Plant 2 3 1 4 Evolutions Tier Totals N/A N/A 6 4 10 1 3 2 5 2.

Plant Systems 2 0 1 2 3 Tier Totals 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and 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).
2. 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 table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the 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 handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. 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 to 10 CFR 55.43.

ES-401 1 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR # QID T 1 2 3 1 2 y p

e 000007 (BW/E02&E10; CE/E02) Reactor X EA2.1- Facility conditions and selection of 4.0 76 588 D Trip - Stabilization - Recovery / 1 appropriate procedures during abnormal and emergency operations 000008 Pressurizer Vapor Space Not selected N/A Accident / 3 000009 Small Break LOCA / 3 Not selected N/A 000011 Large Break LOCA / 3 Not selected N/A 000015/17 RCP Malfunctions / 4 Not selected N/A 000022 Loss of Rx Coolant Makeup / 2 X AA2.04- How long PZR level can be 3.8 77 805 N maintained within limits 2.4.31 Knowledge of annunciator alarms, 000025 Loss of RHR System / 4 X indications, or response procedures. 4.1 78 806 N 000026 Loss of Component Cooling X AA2.01- Location of a leak in the CCWS 3.5 79 807 N Water / 8 000027 Pressurizer Pressure Control Not selected N/A System Malfunction / 3 000029 ATWS / 1 Not selected N/A 000038 Steam Gen. Tube Rupture / 3 X 2.4.18 - Knowledge of the specific bases for 4.0 80 585 N EOPs.

000040 (BW/E05; CE/E05; W/E12) X 2.4.6- Knowledge of symptom based EOP 4.7 81 584 D Steam Line Rupture - Excessive Heat mitigation strategies Transfer / 4 000054 (CE/E06) Loss of Main Not selected N/A Feedwater / 4 000055 Station Blackout / 6 Not selected N/A 000056 Loss of Off-site Power / 6 Not selected N/A 000057 Loss of Vital AC Inst. Bus / 6 Not selected N/A 000058 Loss of DC Power / 6 Not selected N/A 000062 Loss of Nuclear Svc Water / 4 Not selected N/A 000065 Loss of Instrument Air / 8 2.4.18 - Knowledge of the specific bases for N/A EOPs Rejected system to 038 Steam Gen Tube Rupture W/E04 LOCA Outside Containment / 3 Not selected N/A ES-401 2 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR # QID T 1 2 3 1 2 y p

e W/E11 Loss of Emergency Coolant Not selected N/A Recirc. / 4 BW/E04; W/E05 Inadequate Heat Not selected N/A Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Not selected N/A Grid Disturbances / 6 K/A Category Totals: 3 3 Group Point Total: 6 ES-401 3 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR # QID Typ 1 2 3 1 2 e 000001 Continuous Rod Withdrawal / 1 AA2.05- Uncontrolled rod N/A withdrawal from available indications Rejected system to 005 Inoperable/Stuck Control Rod 000003 Dropped Control Rod / 1 Not selected N/A 000005 Inoperable/Stuck Control Rod / 1 X AA2.03 - Required actions if more 4.4 82 589 D than one rod is stuck or inoperable 000024 Emergency Boration / 1 X AA2.05 - Amount of boron to add 3.9 83 808 M to achieve the required SDM 000028 Pressurizer Level Malfunction / 2 Not selected N/A 000032 Loss of Source Range NI / 7 Not selected N/A 000033 Loss of Intermediate Range NI / 7 Not selected N/A 000036 (BW/A08) Fuel Handling Accident / 8 Not selected N/A 000037 Steam Generator Tube Leak / 3 Not selected N/A 000051 Loss of Condenser Vacuum / 4 Not selected N/A 000059 Accidental Liquid RadWaste Rel. / 9 Not selected N/A 000060 Accidental Gaseous Radwaste Rel. / 9 Not selected N/A 000061 ARM System Alarms / 7 Not selected N/A 000067 Plant Fire On-site / 8 Not selected N/A 000068 (BW/A06) Control Room Evac. / 8 Not selected N/A 000069 (W/E14) Loss of CTMT Integrity / 5 Not selected N/A 000074 (W/E06&E07) Inad. Core Cooling / 4 Not selected N/A 000076 High Reactor Coolant Activity / 9 Not selected N/A W/EO1 & E02 Rediagnosis & SI Termination / 3 Not selected N/A W/E13 Steam Generator Over-pressure / 4 Not selected N/A W/E15 Containment Flooding / 5 Not selected N/A W/E16 High Containment Radiation / 9 Not selected N/A BW/A01 Plant Runback / 1 Not selected N/A BW/A02&A03 Loss of NNI-X/Y / 7 X AA2.1 - Facility conditions and 4.0 84 591 D selection of appropriate procedures during abnormal and emergency operations BW/A04 Turbine Trip / 4 Not selected N/A BW/A05 Emergency Diesel Actuation / 6 Not selected N/A BW/A07 Flooding / 8 Not selected N/A BW/E03 Inadequate Subcooling Margin / 4 Not selected N/A ES-401 4 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X 2.4.47- Knowledge of EOP 4.0 85 592 D implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe management guidelines BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not selected N/A BW/E13&E14 EOP Rules and Enclosures Not selected N/A CE/A11; W/E08 RCS Overcooling - PTS / 4 Not selected N/A CE/A16 Excess RCS Leakage / 2 Not selected N/A CE/E09 Functional Recovery Not selected N/A K/A Category Point Totals: 3 1 Group Point Total: 4 ES-401 5 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A G K/A Topic(s) IR # QID T 1 2 3 4 5 6 1 2 3 4 y p

e 003 Reactor Coolant Pump X A2.02 - Conditions which 3.9 86 809 N exist for an abnormal shutdown of a RCP in comparison to a normal shutdown of RCP 004 Chemical and Volume Not Selected N/A Control 005 Residual Heat Removal Not Selected N/A 006 Emergency Core Cooling Not Selected N/A 007 Pressurizer Relief/Quench Not Selected N/A Tank 008 Component Cooling Water Not Selected N/A 010 Pressurizer Pressure Control X A2.02 - Spray failures 3.9 87 762 R 012 Reactor Protection Not Selected N/A 013 Engineered Safety Features X A2.06 - Inadvertent ESFAS 4.0 88 812 N Actuation actuation 022 Containment Cooling Not Selected N/A 025 Ice Condenser Not Selected N/A 026 Containment Spray Not Selected N/A 039 Main and Reheat Steam Not Selected N/A 059 Main Feedwater Not Selected N/A 061 Auxiliary/Emergency X 2.2.22 - Knowledge of 4.7 89 811 N Feedwater limiting conditions for operations and safety limits 062 AC Electrical Distribution Not Selected N/A 063 DC Electrical Distribution X 2.2.42 - Ability to recognize 4.6 90 810 N system parameters that are entry-level conditions for Technical Specifications 064 Emergency Diesel Generator Not Selected N/A 073 Process Radiation Not Selected N/A Monitoring 076 Service Water Not Selected N/A 078 Instrument Air Not Selected N/A 103 Containment Not Selected N/A K/A Category Point Totals: 3 2 Group Point Total: 5 ES-401 6 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

Type System # / Name K K K K K K A A A A G K/A Topic(s) IR # QID 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Not selected N/A 002 Reactor Coolant Not selected N/A 011 Pressurizer Level Control Not selected N/A 014 Rod Position Indication Not selected N/A 015 Nuclear Instrumentation Not selected N/A 016 Non-nuclear Instrumentation X 2.2.40 - Ability to apply 4.7 91 599 D technical specifications for a system 017 In-core Temperature Monitor Not selected N/A 027 Containment Iodine Removal Not selected N/A 028 Hydrogen Recombiner 2.4.23 - Knowledge of the N/A and Purge Control bases for prioritizing emergency procedure implementation during emergency operations.

Rejected system replaced with 016 Non-Nuclear Instrumentation 029 Containment Purge Not selected N/A 033 Spent Fuel Pool Cooling Not selected N/A 034 Fuel Handling Equipment X 2.1.40 -Knowledge of 3.9 92 600 D refueling administrative requirements.

035 Steam Generator X A2.01 - Faulted or ruptured 4.6 93 813 N S/Gs.

041 Steam Dump/Turbine Not selected N/A Bypass Control 045 Main Turbine Generator Not selected N/A 055 Condenser Air Removal Not selected N/A 056 Condensate Not selected N/A 068 Liquid Radwaste Not selected N/A 071 Waste Gas Disposal Not selected N/A 072 Area Radiation Monitoring Not selected N/A 075 Circulating Water Not selected N/A 079 Station Air Not selected N/A 086 Fire Protection Not selected N/A K/A Category Point Totals: 1 2 Group Point Total: 3 ES-401 7 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-3 Facility: Arkansas Nuclear One - Unit 1 Date of Exam: 3/5/2010 Category K/A # Topic SRO IR # QID Type#

2.1.7 Ability to evaluate plant performance and make operational 4.7 94 492 D judgments based on operating characteristics, reactor behavior,

1. and instrument interpretation.

Conduct 2.1.35 Knowledge of the fuel-handling responsibilities of SROs 3.9 95 814 N of Operations Subtotal 2 2.2.25 Knowledge of bases and technical specifications for limiting 4.2 96 646 D conditions of operations and safety limits.

2.2.19 Knowledge of maintenance work order requirements. 3.4 97 815 N 2.

Equipment Control Subtotal 2 2.3.14 Knowledge of radiation or contamination hazards that may arise 3.8 98 816 N during normal, abnormal, or emergency conditions or activities.

3.

Radiation Control Subtotal 1 2.4.30 Knowledge of events related to system operation/status that 4.1 99 411 D must be reported to internal organizations or external agencies,

4. such as the state, the NRC, or the transmission system operator.

Emergency 2.4.35 Knowledge of local auxiliary operator tasks during an emergency 4.0 100 750 D Procedures / and the operational resultant effects.

Plan Subtotal 2 Tier 3 Point Total 7 ES-401 8 Form ES-401-3

ES-401 PWR Examination Outline Form ES-401-4 Tier / Randomly Selected K/A Reason for Rejection Group 1/1 065 Loss of Instrument Air Could not write a credible SRO level question.

- 2.4.18 Knowledge of Randomly selected new system 038 Steam the specific bases for Generator Tube Rupture 2.4.18 EOPs 1/2 001 Continuous Rod Could not write a credible SRO level question.

Withdrawal - AA2.05 Randomly selected new system 005 Inoperable stuck Uncontrolled Rod control rod - AA2.03 Required actions if more than withdrawal from available one rod is stuck or inoperable.

indications 2/2 028 Hydrogen Could not write a credible SRO level question.

Recombiner and Purge Randomly selected new system 016 Non-Nuclear Control - 2.4.23 Instrumentation - 2.2.40 Ability to apply Technical Knowledge of the bases Specifications for a system.

for prioritizing emergency procedure implementation during emergency operations.

ES-401 9 Form ES-401-4

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