ML080700288
| ML080700288 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/29/2008 |
| From: | Garchow S Operations Branch IV |
| To: | Entergy Operations |
| References | |
| 50-313/08-301, 50-368/08-301, ES-401-2 50-313/08-301, 50-368/08-301 | |
| Download: ML080700288 (11) | |
Text
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:Arkansas Nuclear One Unit 2 Date of Exam:02/22/2008 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *
- 1. Emergency 1 3 3 3 3 3 3 18 3 3 6 Abnormal 2 1 2 1 N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions 5 5 Tier Totals 4 5 4 5 5 4 27 10 1 3 2 3 3 2 2 3 3 2 2 3 28 3 2 5 2.
2 1 1 0 1 1 1 1 1 1 1 1 10 0 2 1 3 Plant Systems Tier Totals 4 3 3 4 3 3 4 4 3 3 4 38 5 3 8 1 2 3 4 1 2 3 4
- 3. Generic Knowledge and Abilities 10 7 Categories 2 3 2 3 2 2 2 1 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).
Note: 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.
Note: 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
Note: 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.
Note: 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.
Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Note: 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.
Note: 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.
Note: 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, 21 of 33
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 0 Ability to operate and/or monitor the following as they apply to a 1/1489 000007 Reactor Trip - Stabilization - Recovery / 1 4.4 1 8 reactor trip: - AFW System.
2.1. Conduct of Operations - Knowledge of the purpose and function 2/1490 000008 Pressurizer Vapor Space Accident / 3 3.2 1 28 of major system components and controls.
2.4. Emergency Procedures/Plan - Knowledge symptom based EOP 3/1491 000009 Small Break LOCA / 3 3.1 1 06 mitigation strategies.
0 Knowledge of the interrelations between the Large Break LOCA 4/1492 000011 Large Break LOCA / 3 2.6 1 2 and the following: - Pumps.
Knowledge of the reasons for the following responses as they 0
5/1493 000015 RCP Malfunctions / 4 apply to the Reactor Coolant Pump Malfunctions: - Potential 2.5 1 damage from high winding and/or bearing temperatures. 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 Not Selected Ability to determine and interpret the following as they apply to 0
6/1494 000022 Loss of Rx Coolant Makeup / 2 the Loss of Reactor Coolant Pump Makeup: - Failures of flow 3.1 1 3 control valve or controller.
Ability to operate and/or monitor the following as they apply to 1
7/1495 000025 Loss of RHR System / 4 the Loss of Residual Heat Removal System: - RCS temperature 3.6 1 2 indicators.
Knowledge of the reasons for the following responses as they 0 apply to the Loss of Component Cooling Water: - The conditions 8/1496 000026 Loss of Component Cooling Water / 8 3.2 1 1 that will initiate the automatic opening and closing of the SWS isolation valves to the CCW/nuclear service water coolers.
Knowledge of the interrelations between the Pressurizer 000027 Pressurizer Pressure Control System 0 9/1497 Pressure Control Malfunctions and the following: - Controllers 2.6 1 Malfunction / 3 3 and positioners.
0 Knowledge of the interrelations between the ATWS and the 10/1498 000029 ATWS / 1 2.9 1 6 following: - Breakers, relays, and disconnects.
0 Knowledge of the operational implications of the following 11/1499 000038 Steam Gen. Tube Rupture / 3 3.9 1 3 concepts as they apply to the SGTR: - Natural circulation.
Knowledge of the operational implications of the following CE/E05 Steam Line Rupture - Excessive Heat Transfer 0 concepts as they apply to the (Excess Steam Demand): -
12/1500 3.2 1
/4 2 Normal, abnormal and emergency operating procedures associated with (Excess Steam Demand).
Ability to operate and/or monitor the following as they apply to 0
13/1501 000054 (CE/E06) Loss of Main Feedwater / 4 the (Loss of Feedwater): - Operating behavior characteristics of 3.4 1 2 the facility.
Knowledge of the operational implications of the following 0
14/1502 000055 Station Blackout / 6 concepts as they apply to the Station Blackout: - Effect of 3.3 1 1 battery discharge rates on capacity.
2.1. Conduct of Operations - Knowledge of the purpose and function 15/1503 000056 Loss of Off-site Power / 6 3.2 1 28 of major system components and controls.
Ability to determine and interpret the following as they apply to 2 the Loss of Vital AC Instrument Bus: - Interlocks in effect on loss 16/1504 000057 Loss of Vital AC Inst. Bus / 6 3.6 1 0 of ac vital electrical instrument bus that must be bypassed to restore normal equipment operation.
Ability to determine and interpret the following as they apply to 0
17/1505 000058 Loss of DC Power / 6 the Loss of DC Power: - That a loss of dc power has occurred; 3.7 1 1 verification that substitute power sources have come on line.
Knowledge of the reasons for the following responses as they 0 apply to the Loss of Nuclear Service Water: - The conditions 18/1506 000062 Loss of Nuclear Svc Water / 4 3.2 1 1 that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers.
000065 Loss of Instrument Air / 8 Not Selected 0 W/E04 LOCA Outside Containment / 3 Not Selected 0 W/E11 Loss of Emergency Coolant Recirc. / 4 Not Selected 0 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Not Selected 0 Secondary Heat Sink / 4 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401, 22 of 33
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 Not Selected 0 000003 Dropped Control Rod / 1 Not Selected 0 000005 Inoperable/Stuck Control Rod / 1 Not Selected 0 000024 Emergency Boration / 1 Not Selected 0 Knowledge of the interrelations between the Pressurizer Level 19/1507 000028 Pressurizer Level Malfunction / 2 03 Control Malfunctions and the following: - Controllers and 2.6 1 positioners.
000032 Loss of Source Range NI / 7 Not Selected 0 000033 Loss of Intermediate Range NI / 7 Not Selected 0 Knowledge of the operational implications of the following 20/1508 000036 Fuel Handling Accident / 8 03 concepts as they apply to Fuel Handling Incidents: - Indications 4 1 of approaching criticality.
000037 Steam Generator Tube Leak / 3 Not Selected 0 Ability to determine and interpret the following as they apply to 21/1509 000051 Loss of Condenser Vacuum / 4 02 the Loss of Condenser Vacuum: - Conditions requiring reactor 3.9 1 and/or turbine trip.
000059 Accidental Liquid RadWaste Rel. / 9 Not Selected 0 Ability to operate and/or monitor the following as they apply to 22/1510 000060 Accidental Gaseous Radwaste Rel. / 9 02 the Accidental Gaseous Radwaste Release: - Ventilation 2.9 1 system.
Knowledge of the reasons for the following responses as they 23/1511 000061 ARM System Alarms / 7 02 apply to the Area Radiation Monitoring (ARM) System Alarms: - 3.4 1 Guidance contained in alarm response for ARM system.
000067 Plant Fire On-site / 8 Not Selected 0 000068 Control Room Evac. / 8 Not Selected 0 000069 Loss of CTMT Integrity / 5 Not Selected 0
W/E14 High Containment Pressure / 5 Not Selected Ability to determine and interpret the following as they apply to 24/1512 000074 Inad. Core Cooling / 4 02 an Inadequate Core Cooling: - Availability of main or auxiliary 4.3 feedwater.
1 W/E06 Degraded Core Cooling / 4 Not Selected W/E07 Saturated Core Cooling / 4 Not Selected 000076 High Reactor Coolant Activity / 9 Not Selected 0 W/E01 Rediagnosis / 3 Not Selected 0
W/E02 SI Termination / 3 Not Selected W/E13 Steam Generator Over-pressure / 4 Not Selected 0 W/E15 Containment Flooding / 5 Not Selected 0 W/E16 High Containment Radiation / 9 Not Selected 0 W/E03 LOCA Cooldown - Depress. / 4 Not Selected 0 Knowledge of the interrelations between the (Natural Circulation Operations) and the following: - Facility's heat removal systems, 25/1513 CE/A13 Natural Circulation Operations / 4 02 including primary coolant, emergency coolant, the decay heat 3.4 1 removal systems, and relations between the proper operation of these systems to the operation of the facility.
Conduct of Operations - Ability to evaluate plant performance 2.1.
26/1514 CE/A16 Excess RCS Leakage / 2 and make operational judgments based on operating 3.7 1 07 characteristics, reactor behavior, and instrument interpretation.
Ability to operate and/or monitor the following as they apply to 27/1515 CE/E09 Functional Recovery 03 the (Functional Recover): - Desired operating results during 3.6 1 abnormal and emergency situations.
K/A Category Totals: 1 2 1 2 2 1 Group Point Total: 9 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 1 Knowledge of the effect of a loss or malfunction of the following will 28/1516 003 Reactor Coolant Pump have on the RCPS: - Starting requirements.
2.6 1 4
Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS and (b) based on those predictions, use 0
29/1517 003 Reactor Coolant Pump procedures to correct, control, or mitigate the consequences of those 3.7 1 2 malfunctions or operations: - Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown.
0 Knowledge of the effect that a loss or malfunction of the CVCS will 30/1518 004 Chemical and Volume Control have on the following: - RCP seal injection.
3.6 1 8
Knowledge of RHRS design feature(s) and/or interlock(s) which 0
31/1519 005 Residual Heat Removal provide for the following: - System protection logics, including high- 3.2 1 7 pressure interlock, reset controls, and valve interlocks.
0 Knowledge of the operational implications of the following concepts 32/1520 006 Emergency Core Cooling as they apply to the ECCS: - Operation of pumps in parallel.
2.9 1 8
0 Knowledge of PRTS design feature(s) and/or interlock(s) which 33/1521 007 Pressurizer Relief/Quench Tank provide for the following: - Quench tank cooling.
2.6 1 1
Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS and (b) based on those predictions, use 0
34/1522 008 Component Cooling Water procedures to correct, control, or mitigate the consequences of those 3.3 1 5 malfunctions or operations: - Effect of loss of instrument and control air on the position of the CCW valves that are air operated.
Ability to recognize abnormal indications for system operating 2.4.
35/1523 008 Component Cooling Water parameters which are entry-level conditions for emergency and 4 1 04 abnormal operating procedures.
0 Knowledge of the effect that a loss or malfunction of the PZR PCS 36/1524 010 Pressurizer Pressure Control will have on the following: - RCS.
3.8 1 1
2.1.
37/1525 010 Pressurizer Pressure Control Conduct of Operations - Ability to execute procedure steps. 4.3 1 20 0 Knowledge of the operational implications of the following concepts 38/1526 012 Reactor Protection as they apply to the RPS: - Power density.
3.1 1 2
Knowledge of the physical connections and/or cause-effect 013 Engineered Safety Features 1 39/1527 relationships between the ESFAS and the following systems: - MFW 3.4 1 Actuation 5 System.
0 Knowledge of bus power supplies to the following: - Containment 40/1528 022 Containment Cooling cooling fans.
3 1 1
025 Ice Condenser Not Selected 0 Ability to predict and/or monitor changes in parameters (to prevent 0
41/1529 026 Containment Spray exceeding design limits) associated with operating the CSS controls 2.7 1 6 including: - Containment spray pump cooling.
0 Knowledge of the effect that a loss or malfunction of the MRSS will 42/1530 039 Main and Reheat Steam have on the following: - RCS.
3.6 1 5
0 Ability to manually operate and/or monitor in the control room: - MFW 43/1531 039 Main and Reheat Steam pump turbines.
2.8 1 3
Knowledge of MFW System design feature(s) and/or interlock(s) 0 44/1532 059 Main Feedwater which provide for the following: - Control of speed of MFW pump 2.5 1 5 turbine.
Knowledge of the physical connections and/or cause-effect 0
45/1533 061 Auxiliary/Emergency Feedwater relationships between the AFW System and the following systems: - 2.6 1 5 Condensate system.
Knowledge of the physical connections and/or cause-effect 0
46/1534 062 AC Electrical Distribution relationships between the A.C. Distribution System and the following 3.7 1 4 systems: - Off-site power sources.
Ability to (a) predict the impacts of the following malfunctions or 0 operations on the D.C. Electrical System and (b) based on those 47/1535 063 DC Electrical Distribution predictions, use procedures to correct, control, or mitigate the 2.5 1 1
consequences of those malfunctions or operations: - Grounds.
2.4. Emergency Procedures/Plan - Knowledge of annunciators alarms and 48/1536 063 DC Electrical Distribution indications, and use of the response instructions.
3.3 1 31 0 Knowledge of the effect of a loss or malfunction of the following will 49/1537 064 Emergency Diesel Generator have on the ED/G System: - Air receivers.
2.7 1 7
1 Ability to monitor automatic operation of the ED/G System, including: -
50/1538 064 Emergency Diesel Generator Purpose of automatic load sequencer.
3.3 1 2
Ability to predict and/or monitor changes in parameters (to prevent 0
51/1539 073 Process Radiation Monitoring exceeding design limits) associated with operating the PRM System 3.2 1 1 controls including: - Radiation levels.
0 52/1540 076 Service Water Knowledge of bus power supplies to the following: - Service water. 2.7 1 1
0 Ability to monitor automatic operation of the IAS, including: - Air 53/1541 078 Instrument Air pressure.
3.1 1 1
Ability to predict and/or monitor changes in parameters (to prevent 0 exceeding design limits) associated with operating the Containment 54/1542 103 Containment System controls including: - Containment pressure, temperature, and 3.7 1 1
humidity.
0 Ability to manually operate and/or monitor in the control room: -
55/1543 103 Containment Operation of the containment personnel airlock door.
2.7 1 6
K/A Category Totals: 3 2 3 3 2 2 3 3 2 2 3 Group Point Total: 28 ES-401, Page 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Not Selected 0 002 Reactor Coolant Not Selected 0 011 Pressurizer Level Control Not Selected 0 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS and (b) based on those 0
56/1544 014 Rod Position Indication predictions, use procedures to correct, control, or mitigate the 3.6 1 3 consequences of those malfunctions or operations: -
Dropped rod.
0 Knowledge of the effect of a loss or malfunction of the 57/1545 015 Nuclear Instrumentation 3.1 1 4 following will have on the NIS: - Bistables and logic circuits.
016 Non-nuclear Instrumentation Not Selected 0 017 In-core Temperature Monitor Not Selected 0 027 Containment Iodine Removal Not Selected 0 0 Ability to manually operate and/or monitor in the control room:
58/1546 028 Hydrogen Recombiner and Purge Control 4 1 1 - HRPS controls.
Knowledge of Containment Purge System design feature(s) 0 59/1547 029 Containment Purge and/or interlock(s) which provide for the following: - Automatic 3.2 1 3 purge isolation.
033 Spent Fuel Pool Cooling Not Selected 0 0 Ability to monitor automatic operation of the Fuel Handling 60/1548 034 Fuel Handling Equipment 2.5 1 1 System, including: - Travel limits.
035 Steam Generator Not Selected 0 041 Steam Dump/Turbine Bypass Control Not Selected 0 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating 0
61/1549 045 Main Turbine Generator the MT/G System controls including: - Expected response of 3.8 1 5 primary plant parameters (temperature and pressure) following T/G trip.
055 Condenser Air Removal Not Selected 0 2.1. Conduct of Operations - Knowledge of system purpose and 62/1550 056 Condensate 2.8 1 27 or function.
Knowledge of the physical connections and/or cause-effect 0
63/1551 068 Liquid Radwaste relationships between the Liquid Radwaste System and the 2.7 1 7 following systems: - Sources of liquid wastes for LRS.
071 Waste Gas Disposal Not Selected 0 Knowledge of the operational implications of the following 0
64/1552 072 Area Radiation Monitoring concepts as they apply to the ARM system: - Radiation 2.7 1 1 theory, including sources, types, units, and effects.
0 Knowledge of bus power supplies to the following: -
65/1553 075 Circulating Water 2.6 1 3 Emergency/essential SWS pumps.
079 Station Air Not Selected 0 086 Fire Protection Not Selected 0 K/A Category Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401, Page 25 of 33
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 Emergency Procedures/Plan - Ability to interpret control room
- 04. indications to verify the status and operation of system, and 76/1564 000007 Reactor Trip - Stabilization - Recovery / 1 understand how operator actions and directives affect plant and 3.8 1 48 system conditions.
000008 Pressurizer Vapor Space Accident / 3 Not Selected 0 000009 Small Break LOCA / 3 Not Selected 0 000011 Large Break LOCA / 3 Not Selected 0 000015 RCP Malfunctions / 4 Not Selected 1
- 02. Equipment Control - Knowledge of limiting conditions for 77/1589 000017 RCP Malfunctions (Loss of RC Flow) / 4 operations and safety limits.
4.1 22 000022 Loss of Rx Coolant Makeup / 2 Not Selected 0 000025 Loss of RHR System / 4 Not Selected 0 000026 Loss of Component Cooling Water / 8 Not Selected 0 000027 Pressurizer Pressure Control System Not Selected 0 Malfunction / 3 Equipment Control - Knowledge of the process for determining if 02.
78/1565 000029 ATWS / 1 the proposed change, test, or experiment involves an unreviewed 3.3 1 08 safety question.
000038 Steam Gen. Tube Rupture / 3 Not Selected 0 000040 Steam Line Rupture - Excessive Heat Transfer / 0 Ability to determine and interpret the following as they apply to the 79/1566 Steam Line Rupture: - Conditions requiring a reactor trip.
4.7 4 2 1 WE12 Uncontrolled Depressurization of all Steam Not Selected Generators / 4 000054 (CE/E06) Loss of Main Feedwater / 4 Not Selected 0 000055 Station Blackout / 6 Not Selected 0 000056 Loss of Off-site Power / 6 Not Selected 0 000057 Loss of Vital AC Inst. Bus / 6 Not Selected 0 000058 Loss of DC Power / 6 Not Selected 0 000062 Loss of Nuclear Svc Water / 4 Not Selected 0 Ability to determine and interpret the following as they apply to the 0
80/1568 000065 Loss of Instrument Air / 8 Loss of Instrument Air: - When to commence plant shutdown if 4.1 1 5 instrument air pressure is decreasing.
W/E04 LOCA Outside Containment / 3 Not Selected 0 W/E11 Loss of Emergency Coolant Recirc. / 4 Not Selected 0 Ability to determine and interpret the following as they apply to the 0 (Reactor Trip Recovery): - Adherence to appropriate procedures 81/1569 CE/E02 Reactor Trip - Stabilization - Recovery / 1 and operation within the limitations in the facility's license and 4 1 2
amendments.
K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 22 of 33
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 Not Selected 0 000003 Dropped Control Rod / 1 Not Selected 0 000005 Inoperable/Stuck Control Rod / 1 Not Selected 0
- 04. Emergency Procedures/Plan - Knowledge symptom based EOP 82/1570 000024 Emergency Boration / 1 4 1 06 mitigation strategies.
000028 Pressurizer Level Malfunction / 2 Not Selected 0 000032 Loss of Source Range NI / 7 Not Selected 0 000033 Loss of Intermediate Range NI / 7 Not Selected 0 000036 Fuel Handling Accident / 8 Not Selected 0 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: - System status, using 83/1571 000037 Steam Generator Tube Leak / 3 09 independent readings from redundant Condensate air ejector 3.4 1 exhaust monitor.
000051 Loss of Condenser Vacuum / 4 Not Selected 0 000059 Accidental Liquid RadWaste Rel. / 9 Not Selected 0 000060 Accidental Gaseous Radwaste Rel. / 9 Not Selected 0 000061 ARM System Alarms / 7 Not Selected 0 000067 Plant Fire On-site / 8 Not Selected 0 Emergency Procedures/Plan - Ability to recognize abnormal
- 04. indications for system operating parameters which are entry-84/1572 000068 Control Room Evac. / 8 4.3 1 04 level conditions for emergency and abnormal operating procedures.
Ability to determine and interpret the following as they apply to 85/1573 000069 Loss of CTMT Integrity / 5 01 the Loss of Containment Integrity: - Loss of containment 4.3 integrity. 1 W/E14 High Containment Pressure / 5 Not Selected 000074 Inad. Core Cooling / 4 Not Selected W/E06 Degraded Core Cooling / 4 Not Selected 0 W/E07 Saturated Core Cooling / 4 Not Selected 000076 High Reactor Coolant Activity / 9 Not Selected 0 W/E01 Rediagnosis / 3 Not Selected 0
W/E02 SI Termination / 3 Not Selected W/E13 Steam Generator Over-pressure / 4 Not Selected 0 W/E15 Containment Flooding / 5 Not Selected 0 W/E16 High Containment Radiation / 9 Not Selected 0 W/E03 LOCA Cooldown - Depress. / 4 Not Selected 0 W/E09 Natural Circulation Operations / 4 Not Selected 0
W/E10 Natural Circulation with Steam Voide in Not Selected Vessel with/without RVLIS. / 4 W/E08 RCS Overcooling - PTS / 4 Not Selected 0 K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 23 of 33
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump Not Selected 0 004 Chemical and Volume Control Not Selected 0 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS and (b) based on 0
86/1574 005 Residual Heat Removal those predictions, use procedures to correct, control, or 3.1 1 3 mitigate the consequences of those malfunctions or operations: - RHR pump/motor malfunction.
006 Emergency Core Cooling Not Selected 0 007 Pressurizer Relief/Quench Tank Not Selected 0 008 Component Cooling Water Not Selected 0 010 Pressurizer Pressure Control Not Selected 0 012 Reactor Protection Not Selected 0 013 Engineered Safety Features Not Selected 0 Actuation Ability to (a) predict the impacts of the following malfunctions or operations on the CCS and (b) based on 0
87/1575 022 Containment Cooling those predictions, use procedures to correct, control, or 3.2 1 4 mitigate the consequences of those malfunctions or operations: - Loss of service water.
025 Ice Condenser Not Selected 0 04.
88/1576 026 Containment Spray Knowledge of symptom based EOP mitigation strategies 3.8 1 06 039 Main and Reheat Steam Not Selected 0 059 Main Feedwater 0 Emergency Procedures/Plan - Knowledge of which events 04.
89/1577 061 Auxiliary/Emergency Feedwater related to system operations/status should be reported to 3.6 1 30 outside agencies.
062 AC Electrical Distribution Not Selected 0 063 DC Electrical Distribution Not Selected 0 064 Emergency Diesel Generator Not Selected 0 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM System and (b) 0 90/1578 073 Process Radiation Monitoring based on those predictions, use procedures to correct, 3.2 1 2 control, or mitigate the consequences of those malfunctions or operations: - Detector failure 076 Service Water Not Selected 0 078 Instrument Air Not Selected 0 103 Containment Not Selected 0 K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 24 of 33
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 Emergency Procedures/Plan - Ability to take actions called for 04.
91/1579 001 Control Rod Drive in the facility emergency plan, including (if required) supporting 4 1 38 or acting as emergency coordinator.
002 Reactor Coolant Not Selected 0 011 Pressurizer Level Control Not Selected 0 014 Rod Position Indication Not Selected 0 015 Nuclear Instrumentation Not Selected 0 016 Non-nuclear Instrumentation Not Selected 0 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM System and (b) based on those 0
92/1580 017 In-core Temperature Monitor predictions, use procedures to correct, control, or mitigate the 4.1 1 2 consequences of those malfunctions or operations: - Core damage.
027 Containment Iodine Removal Not Selected 0 028 Hydrogen Recombiner and Purge Control Not Selected 0 029 Containment Purge Not Selected 0 033 Spent Fuel Pool Cooling Not Selected 0 034 Fuel Handling Equipment Not Selected 0 035 Steam Generator Not Selected 0 041 Steam Dump/Turbine Bypass Control Not Selected 0 045 Main Turbine Generator Not Selected 0 055 Condenser Air Removal Not Selected 0 056 Condensate Not Selected 0 068 Liquid Radwaste Not Selected 0 Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System and (b) 0 93/1581 071 Waste Gas Disposal based on those predictions, use procedures to correct, control, 2.7 1 4 or mitigate the consequences of those malfunctions or operations: - Loss of Cover Gas.
072 Area Radiation Monitoring Not Selected 0 075 Circulating Water Not Selected 0 079 Station Air Not Selected 0 086 Fire Protection Not Selected 0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 25 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3 SRO) Form ES-401-3 Facility Name:Arkansas Nuclear One Unit 2 Date of Exam:02/22/2008 RO SRO-Only Category K/A # Topic Q# IR # IR #
66/1554 2.1. 03 Knowledge of shift turnover practices. 3 1 67/1555 2.1. 28 Knowledge of the purpose and function of major system components and controls. 3.2 1 94/1582 1.
2.1. 04 Knowledge of shift staffing requirements. 3.4 1 Conduct of 95/1583 Operations 2.1. 32 Ability to explain and apply all system limits and precautions. 3.8 1 2.1.
2.1.
Subtotal 2 2 Ability to perform pre-startup procedures for the facility, including operating those controls associated 68/1556 2.2. 01 with plant equipment that could affect reactivity. 3.7 1 69/1557 2.2. 28 Knowledge of new and spent fuel movement procedures. 2.6 1 70/1558 2.
2.2. 34 Knowledge of the process for determining the internal and external effects on core reactivity. 2.8 1 Equipment Ability to identify and utilize as-built design and configuration change documentation to ascertain 96/1584 Control 2.2. 15 expected current plant configuration and operate the plant. 2.9 1 97/1585 2.2. 21 Knowledge of pre- and post-maintenance operability requirements. 3.5 1 2.2.
Subtotal 3 2 71/1559 2.3. 01 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 2.6 1 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel 72/1560 2.3. 10 exposure. 2.9 1 98/1586 3.
2.3. 02 Knowledge of facility ALARA program. 2.9 1 Radiation 99/1587 Control 2.3. 08 Knowledge of the process for performing a planned gaseous radioactive release. 3.2 1 2.3.
2.3.
Subtotal 2 2 73/1561 2.4. 13 Knowledge of crew roles and responsibilities during EOP flowchart use. 3.3 1 74/1562 2.4. 15 Knowledge of communications procedures associated with EOP implementation. 3 1 Ability to perform without reference to procedures those actions that require immediate operation of 75/1563 4. 2.4. 49 system components and controls. 4 1 Emergency Ability to recognize abnormal indications for system operating parameters which are entry-level 100/1588 Procedures / 2.4. 04 conditions for emergency and abnormal operating procedures. 4.3 1 Plan 2.4.
2.4.
Subtotal 3 1 Tier 3 Point Total 10 7 ES-401, Page 26 of 33
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