ML062070539

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AN2-07-2006 - Draft - Outline
ML062070539
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 02/23/2006
From:
Operations Branch IV
To:
Entergy Operations
References
50-368/06-302 50-368/06-302
Download: ML062070539 (26)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 2 RO Written Outline Date of Exam: 07/14/2006 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. 1 3 3 3 3 3 3 18 Emergency &

Abnormal Plant Evolutions 2 1 2 N/A 1 1 N/A 2 9 2

Tier Totals 5 4 5 4 4 5 27 1 2 2 3 3 3 2 2 3 2 3 3 28 2.

Plant 1 1 1 0 1 1 1 1 1 1 1 10 2

Systems Tier Totals 3 3 4 4 4 3 3 4 2 4 4 38

3. Generic Knowledge and Abilities Catergories 1 2 3 4 10 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 Outline and the 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 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.
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.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) 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. 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 number, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43 NUREG-1021, Revision 9 Page 1 of 11

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group1 (RO /SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 00007 (BW/E02 & E10; CE/E02) Reactor Trip X Knowledge of the reasons for the following responses as 3.2 1

- Stabilization - Recovery / 1 they apply to the (Reactor Trip Recovery):

EK3.4 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated 00008 Pressurizer Vapor Space Accident / 3 X Ability to determine and interpret the following as they apply 3.6 2 to the Pressurizer Vapor Space Accident:

AA2.09 PZR spray block valve controls and indicators 000009 Small Break LOCA / 3 X Knowledge of the interrelations between the small break 3.0 3 LOCA and the following:

EK2.03 S/Gs 000011 Large Break LOCA / 3 X Ability to determine and interpret the following as they apply 3.3* 4 to a Large Break LOCA:

EA2.02 Consequences to RHR of not resetting safety injection 000015/17 RCP Malfunctions / 4 X Knowledge of the interrelations between the Reactor 2.6 5 Coolant Pump Malfunctions and the following:

AK2.08 CCWS 000022 Loss of Rx Coolant Makeup / 2 X Knowledge of the operational implications of the following 3.0 6 concepts as they apply to Loss of Reactor Coolant Pump Makeup:

AK1.03 Relationship between charging flow and PZR level.

000025 Loss of RHR System / 4 X Knowledge of the operational implications of the following 3.9 7 concepts as they apply to Loss of Residual Heat Removal System:

AK1.01 Loss of RHRS during all modes of operation 000026 Loss of Component Cooling X Generic: 3.1 8 Water / 8 2.4.6 Knowledge symptom based EOP mitigation strategies.

000027 Pressurizer Pressure Control X Generic: 3.4 9 System Malfunction / 3 2.4.11 Knowledge of abnormal condition procedures.

000029 ATWS / 1 X Ability to operate and/or monitor the following as they apply 3.4* 10 to a ATWS:

EA1.01 Charging pumps 000038 Steam Gen. Tube Rupture / 3 Not Selected 000040 (BW/E05; CE/E05; W/E12) X 040 3.2 11 Steam Line Rupture - Excessive Heat Knowledge of the operational implications of the following Transfer / 4 concepts as they apply to Steam Line Rupture:

AK1.04 Nil ductility temperature 000040 (BW/E05; CE/E05; W/E12) X CE/E05 3.9 12 Steam Line Rupture - Excessive Heat Ability to operate and/or monitor the following as they apply Transfer / 4 to the (Excess Steam Demand):

EA1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

NUREG-1021, Revision 9 Page 2 of 11

ES-401 PWR Examination Outline Form ES-401-2 054 000054 (CE/E06) Loss of Main X 4.3 13 Feedwater / 4 Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

AA2.01 Occurrence of reactor and/or turbine trip CE/E06 000054 (CE/E06) Loss of Main X 3.5 14 Feedwater / 4 Knowledge of the interrelations between the (Loss of Feedwater) and the following:

EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

000055 Station Blackout / 6 Not Selected 000056 Loss of Off-site Power / 6 X Knowledge of the reasons for the following responses as 3.5 15 they apply to the Loss of Offsite Power:

AK3.01 Order and time to initiation of power for the load sequencer 000057 Loss of Vital AC Inst. Bus / 6 X Knowledge of the reasons for the following responses as 4.1 16 they apply to the Loss of Vital AC Instrument Bus:

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus.

Ability to operate and/or monitor the following as they apply 000058 Loss of DC Power / 6 X to the Loss of DC Power: 3.1* 17 AA1.02 Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector 000062 Loss of Nuclear Svc Water / 4 X Generic 3.2 18 2.1.28 Knowledge of the purpose and function of major system components and controls.

Not selected 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 Not applicable to this Unit.

W/E11 Loss of Emergency Coolant Not applicable to this Unit.

Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer Not applicable to this Unit.

- Loss of Secondary Heat Sink / 4 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 NUREG-1021, Revision 9 Page 3 of 11

ES-401 PWR Examination Outline Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group2 (RO /SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 X Knowledge of the interrelations between the 3.0* 19 Continuous Rod Withdrawal and the following:

AK2.06 T-ave./ref. deviation meter 000003 Dropped Control Rod / 1 Not Selected.

000005 Inoperable/Stuck Control Rod / 1 X Knowledge of the interrelations between the 3.4 20 Inoperable/Stuck Control Rod and the following:

AA1.05 RPI 000024 Emergency Boration / 1 Not Selected.

000028 Pressurizer Level Malfunction / 2 Not Selected.

000032 Loss of Source Range NI / 7 Not Selected.

000033 Loss of Intermediate Range NI / 7 Not applicable to this Unit.

Knowledge of the reasons for the following responses 000036 (BW/A08) Fuel Handling Accident / 8 X as they apply to the Fuel Handling Incidents: 3.7 21 AK3.03 Guidance contained in EOP for fuel handling incident.

000037 Steam Generator Tube Leak / 3 X Generic 3.4 22 2.2.22 Knowledge of limiting conditions for operations and safety limits.

000051 Loss of Condenser Vacuum / 4 X Generic 3.4 23 2.1.32 Ability to explain and apply all system limits and precautions.

Not Selected.

000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 Not Selected.

000061 ARM System Alarms / 7 X Knowledge of the operational implications of the 2.5* 24 following concepts as they apply to Area Radiation Monitoring (ARM)

AK1.01 Detector limitations 000067 Plant Fire On-site / 8 Not Selected.

000068 (BW/A06) Control Room Evac. / 8 Not Selected.

000069 (W/E14) Loss of CTMT Integrity / 5 Not Selected.

000074 (W/E06&E07) Inad. Core Cooling / 4 Not Selected.

000076 High Reactor Coolant Activity / 9 X Ability to determine and interpret the following as they 2.8 25 apply to the High Reactor Coolant Activity:

AA2.02 Corrective actions required for high fission product activity in RCS W/EO1 & E02 Rediagnosis & SI Termination / 3 Not applicable to this Unit.

W/E13 Steam Generator Over-pressure / 4 Not applicable to this Unit.

W/E15 Containment Flooding / 5 Not applicable to this Unit.

NUREG-1021, Revision 9 Page 4 of 11

ES-401 PWR Examination Outline Form ES-401-2 W/E16 High Containment Radiation / 9 Not applicable to this Unit.

BW/A01 Plant Runback / 1 Not applicable to this Unit.

BW/A02&A03 Loss of NNI-X/Y / 7 Not applicable to this Unit.

BW/A04 Turbine Trip / 4 Not applicable to this Unit.

BW/A05 Emergency Diesel Actuation / 6 Not applicable to this Unit.

BW/A07 Flooding / 8 Not applicable to this Unit.

BW/E03 Inadequate Subcooling Margin / 4 Not applicable to this Unit.

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not applicable to this Unit.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not Selected.

BW/E13&E14 EOP Rules and Enclosures Not applicable to this Unit.

Knowledge of the operational implications of the CE/A11; W/E08 RCS Overcooling - PTS / 4 X following concepts as they apply to the (RCS 3.1 26 Overcooling):

EK1.1 Components, capacity, and function of emergency systems CE/A16 Excess RCS Leakage / 2 X Knowledge of the reasons for the following responses 2.8 27 as they apply to the (Excess RCS Leakage):

EK3.2 Normal, abnormal and emergency operating procedures associated with (Excess RCS Leakage)

CE/E09 Functional Recovery Not Selected.

K/A Category Point Totals: 2 1 2 1 1 2 9 NUREG-1021, Revision 9 Page 5 of 11

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

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump X Knowledge of RCPS design feature(s) and/or 2.8 28 interlock(s) which provide for the following:

K4.04 Adequate cooling of RCP motor and seals Ability to predict and/or monitor changes in 004 Chemical and Volume Control X parameters (to prevent exceeding design 3.0 29 limits) associated with operating the CVCS controls including:

A1.06 VCT level Knowledge of bus power supplies to the 005 Residual Heat Removal X following: 2.7* 30 K2.03 RCS Pressure boundary motor operated valves.

Ability to manually operate and/or monitor in 005 Residual Heat Removal X the control room: 2.8* 31 A4.03 RHR temperature, PZR heaters and flow, and nitrogen 006 Emergency Core Cooling X Ability to (a) predict the impacts of the 4.2 32 following malfunctions or operations on the ECCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A3.08 Automatic transfer of ECCS flowpaths 007 Pressurizer Relief/ Quench Tank X Knowledge of the operational implications of 3.1 33 the following concepts as they apply to the PRTS:

K5.02 Method of forming a steam bubble in the PZR.

008 Component Cooling Water X Ability to (a) predict the impacts of the 3.3* 34 following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.05 Effect of loss of instrument and control air on the position of the CCW valves that are airoperated Knowledge of bus power supplies to the 010 Pressurizer Pressure Control X following: 3.0 35 K2.01 PZR heaters.

Knowledge of the effect that a loss or 012 Reactor Protection X malfunction of the RPS will have on the 3.1* 36 following:

K3.03 SDS 013 Engineered Safety Features Actuation X Knowledge of the physical connections 3.7 37 and/or cause-effect relationships between the ESFAS and the following systems:

K1.18 Premature reset of ESF actuation 013 Engineered Safety Features Actuation X Generic 2.8 38 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

NUREG-1021, Revision 9 Page 6 of 11

ES-401 PWR Examination Outline Form ES-401-2 Ability to manually operate and/or monitor in 022 Containment Cooling X the control room: 3.2* 39 A4.02 CCS pumps Ability to manually operate and/or monitor in 022 Containment Cooling X the control room: 3.1* 40 A4.04 Valves in the CCS 025 Ice Condenser Not applicable to this unit.

026 Containment Spray X Ability to monitor automatic operation of the 3.9* 41 CSS, including:

A3.02 Verification that cooling water is supplied to the containment spray heat exchanger Knowledge of the effect that a loss or 039 Main and Reheat Steam X malfunction of the MRSS will have on the 2.5* 42 following:

K3.04 MFW pumps 059 Main Feedwater X Knowledge of the effect that a loss or 3.6 43 malfunction of the MFW System will have on the following:

K3.02 AFW System 059 Main Feedwater X Generic 3.0 44 2.4.14 Knowledge of general guidelines for EOP flowchart use.

061 Auxiliary/Emergency Feedwater X Knowledge of the physical connections 2.6* 45 and/or cause-effect relationships between the AFW System and the following systems:

K1.09 PRMS 062 AC Electrical Distribution X Ability to predict and/or monitor changes in 2.5 46 parameters (to prevent exceeding design limits) associated with operating the A.C.

Distribution System controls including:

A1.03 Effect on instrumentation and controls of switching power supplies 063 DC Electrical Distribution X Ability to (a) predict the impacts of the 2.5 47 following malfunctions or operations on the D.C. Electrical System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Grounds 064 Emergency Diesel Generator X Knowledge of the effect of a loss or 3.2 48 malfunction of the following will have on the ED/G System:

K6.08 Fuel oil storage tanks 064 Emergency Diesel Generator X Knowledge of the effect of a loss or 2.7 49 malfunction of the following will have on the ED/G System:

K6.07 Air receivers 073 Process Radiation Monitoring X Knowledge of the operational implications of 2.5 50 the following concepts as they apply to the PRM System:

K5.01 Radiation theory, including sources, types, units, and effects NUREG-1021, Revision 9 Page 7 of 11

ES-401 PWR Examination Outline Form ES-401-2 073 Process Radiation Monitoring X Knowledge of the operational implications of 2.5 51 the following concepts as they apply to the PRM System:

K5.02 Radiation intensity changes with source distance 076 Service Water X Knowledge of SWS design feature(s) and/or 2.9 52 interlock(s) which provide for the following:

K4.02 Automatic start features associated with SWS pump controls 078 Instrument Air X Knowledge of IAS design feature(s) and/or 3.2 53 interlock(s) which provide for the following:

K4.02 Cross-over to other air systems 078 Instrument Air X Generic 2.6 54 2.2.27 Knowledge of the refueling process.

103 Containment X Ability to (a) predict the impacts of the 2.9 55 following malfunctions 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:

A2.05 Emergency Containment Entry K/A Category Point Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28 NUREG-1021, Revision 9 Page 8 of 11

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Not selected 002 Reactor Coolant X Ability to manually operate and/or monitor in the 3.5* 56 control room:

A4.01 RCS leakage calculation program using the computer 011 Pressurizer Level Control X Knowledge of the effect that a loss or malfunction 3.2 57 of the PZR LCS will have on the following:

K3.03 PZR PCS 014 Rod Position Indication Not selected 015 Nuclear Instrumentation X Knowledge of bus power supplies to the 3.3 58 following:

K2.01 NIS channels, components, and interconnections 016 Non-nuclear Instrumentation Not selected 017 In-core Temperature Monitor X Ability to monitor automatic operation of the ITM 3.6* 59 System, including:

A3.01 Indications of normal, natural, and interrupted circulation of RCS 027 Containment Iodine Removal Not applicable to this unit 028 Hydrogen Recombiner and Purge Control Not selected 029 Containment Purge Not selected 033 Spent Fuel Pool Cooling X Knowledge of the physical connections and/or 2.5 60 cause-effect relationships between the Spent Fuel Pool Cooling System and the following systems:

K1.02 RHRS 034 Fuel Handling Equipment Not selected 035 Steam Generator Knowledge of the effect of a loss or malfunction X of the following will have on the S/GS: 3.2 61 K6.01 MSIVs 041 Steam Dump/Turbine Bypass Control Not selected 045 Main Turbine Generator X Ability to (a) predict the impacts of the following 2.7* 62 malfunctions or operations on the MT/G System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.17 Malfunction of electrohydraulic control 055 Condenser Air Removal Not selected 056 Condensate X Generic 2.6 63 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements.

068 Liquid Radwaste Not selected 071 Waste Gas Disposal Not selected NUREG-1021, Revision 9 Page 9 of 11

ES-401 5 Form ES-401-2 072 Area Radiation Monitoring X Knowledge of the operational implications of the 2.7 64 following concepts as they apply to the ARM system:

K5.01 Radiation theory, including sources, types, units, and effect.

075 Circulating Water Not selected 079 Station Air Not selected 086 Fire Protection X Ability to predict and/or monitor changes in 2.9 65 parameters (to prevent exceeding design limits) associated with operating the Fire Protection System controls including:

A1.05 FPS lineups K/A Category Totals: 1 1 1 0 1 1 1 1 1 1 1 Group Point Total: 10 NUREG-1021, Revision 9 Page 10 of 11

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One Unit 2 RO Written Outline Date of Exam: 07/14/2006 Category K/A # Topic RO IR #

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 3.7 66 characteristics, reactor behavior, and instrument interpretation.

1. 2.1.22 2.8 67 Ability to determine Mode of Operation.

Conduct of Operations 2.1.27 Knowledge of system purpose and or function 2.8 68 Subtotal 3 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls 3.7 69 associated with plant equipment that could affect reactivity.

2.2.26 2.5 70 Knowledge of refueling administrative requirements 2.

Equipment Control Subtotal 2 2.3.9 Knowledge of the process for performing a containment purge. 2.5 71 2.3.11 Ability to control radiation releases. 2.7 72 3.

Radiation Control Subtotal 2 2.4.35 Knowledge of local auxiliary operator tasks during emergency operations including system 3.3 73 geography and system implications.

2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 3.4 74

4. appropriate control room reference material.

Emergency 2.4.49 4.0 75 Procedures/ Plan Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Subtotal 3 Tier 3 Point Total 10 NUREG-1021, Revision 9 Page 11 of 11

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 2 SRO Written Outline Date of Exam: 07/14/2006 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. 1 4 2 6 Emergency &

Abnormal Plant Evolutions N/A N/A 3 4 2 1 Tier Totals 7 3 10 1 3 2 5 2.

Plant 1 3 2 2 Systems Tier Totals 4 4 8

3. Generic Knowledge and Abilities Catergories 1 2 3 4 7 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 Outline and the 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 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.
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.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) 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. 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 number, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43 NUREG-1021, Revision 9 1 of 7

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group1 (RO /SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 00007 (BW/E02 & E10; CE/E02) Reactor Trip X 2.1.19 Ability to use plant computer to obtain and 3.0 76

- Stabilization - Recovery / 1 evaluate parametric information on system or component status.

Not selected 00008 Pressurizer Vapor Space Accident / 3 Not selected 000009 Small Break LOCA / 3 000011 Large Break LOCA / 3 Not selected Not selected 000015/17 RCP Malfunctions / 4 Not selected 000022 Loss of Rx Coolant Makeup / 2 Not selected 000025 Loss of RHR System / 4 Not selected 000026 Loss of Component Cooling Water / 8 Not selected 000027 Pressurizer Pressure Control System Malfunction / 3 Not selected 000029 ATWS / 1 Ability to determine and interpret the following as 000038 Steam Gen. Tube Rupture / 3 X they apply to a SGTR: 4.8 77 EA2.02 Existence of an S/G tube rupture and its potential consequences Ability to determine and interpret the following as 000038 Steam Gen. Tube Rupture / 3 X they apply to a SGTR: 4.2 78 EA2.12 Status of MSIV activating system 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Not selected Transfer / 4 Not selected 000054 (CE/E06) Loss of Main Feedwater / 4 000055 Station Blackout / 6 X 2.2.20 Knowledge of the process for managing 3.3 79 troubleshooting activities.

000056 Loss of Off-site Power / 6 Not selected 000057 Loss of Vital AC Inst. Bus / 6 Not selected 000058 Loss of DC Power / 6 Not selected 000062 Loss of Nuclear Svc Water / 4 Not selected Ability to determine and interpret the following as 000065 Loss of Instrument Air / 8 X they apply to the Loss of Instrument Air: 2.6* 80 AA2.02 Relationship of flow readings to system operation Ability to determine and interpret the following as 000065 Loss of Instrument Air / 8 X they apply to the Loss of Instrument Air: 4.1 81 AA2.05 When to commence plant shutdown if instrument air pressure is decreasing Not applicable to this Unit.

W/E04 LOCA Outside Containment / 3 Not applicable to this Unit.

W/E11 Loss of Emergency Coolant Recirc. / 4 Not applicable to this Unit.

BW/E04; W/E05 Inadequate Heat Transfer

- Loss of Secondary Heat Sink / 4 K/A Category Totals: 4 2 Group Point Total: 6 NUREG-1021, Revision 9 Page 2 of 7

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group2 (RO /SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 Not selected 000001 Continuous Rod Withdrawal / 1 Ability to determine and interpret the following as 000003 Dropped Control Rod / 1 X they apply to the Dropped Control Rod: 3.8 82 AA2.03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements Not selected 000005 Inoperable/Stuck Control Rod / 1 Ability to determine and interpret the following as 000024 Emergency Boration / 1 X they apply to the Emergency Boration: 4.4 83 AA2.02 When use of manual boration valve is needed Not selected 000028 Pressurizer Level Malfunction / 2 Not selected 000032 Loss of Source Range NI / 7 Not applicable to this Unit 000033 Loss of Intermediate Range NI / 7 Not selected 000036 (BW/A08) Fuel Handling Accident / 8 Not selected 000037 Steam Generator Tube Leak / 3 Not selected 000051 Loss of Condenser Vacuum / 4 Not selected 000059 Accidental Liquid RadWaste Rel. / 9 Not selected 000060 Accidental Gaseous Radwaste Rel. / 9 Not selected 000061 ARM System Alarms / 7 Not selected 000067 Plant Fire On-site / 8 Not selected 000068 (BW/A06) Control Room Evac. / 8 Ability to determine and interpret the following as 000069 (W/E14) Loss of CTMT Integrity / 5 X they apply to the Loss of Containment Integrity: 4.3 84 AA2.01 Loss of containment integrity Not selected 000074 (W/E06&E07) Inad. Core Cooling / 4 Not selected 000076 High Reactor Coolant Activity / 9 Not applicable to this Unit.

W/EO1 & E02 Rediagnosis & SI Termination / 3 Not applicable to this Unit.

W/E13 Steam Generator Over-pressure / 4 Not applicable to this Unit.

W/E15 Containment Flooding / 5 Not applicable to this Unit.

W/E16 High Containment Radiation / 9 Not applicable to this Unit.

BW/A01 Plant Runback / 1 Not applicable to this Unit.

BW/A02&A03 Loss of NNI-X/Y / 7 Not applicable to this Unit.

BW/A04 Turbine Trip / 4 Not applicable to this Unit.

BW/A05 Emergency Diesel Actuation / 6 Not applicable to this Unit.

BW/A07 Flooding / 8 NUREG-1021, Revision 9 Page 3 of 7

ES-401 2 Form ES-401-2 Not applicable to this Unit.

BW/E03 Inadequate Subcooling Margin / 4 Not applicable to this Unit.

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not selected BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not applicable to this Unit.

BW/E13&E14 EOP Rules and Enclosures Not selected CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 Not selected CE/E09 Functional Recovery X 2.3.10 Ability to perform procedures to reduce 3.3 85 excessive levels of radiation and guard against personnel exposure.

K/A Category Point Totals: 3 1 Group Point Total: 4 NUREG-1021, Revision 9 Page 4 of 7

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump X 2.2.18 Knowledge of the process for 3.5 86 managing maintenance activities during shutdown operations.

004 Chemical and Volume Control Not selected 005 Residual Heat Removal Not selected 006 Emergency Core Cooling Ability to (a) predict the impacts of the X following malfunctions or operations 3.2* 87 on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.09 Radioactive release from venting RWST to atmosphere 007 Pressurizer Relief/ Quench Tank Not selected 008 Component Cooling Water Not selected 010 Pressurizer Pressure Control Not selected 012 Reactor Protection Not selected 013 Engineered Safety Features Actuation Not selected Not selected 022 Containment Cooling 025 Ice Condenser Not applicable to this Unit 026 Containment Spray X 2.4.46 Ability to verify that the alarms are 3.6 88 consistent with the plant conditions.

039 Main and Reheat Steam Not selected 059 Main Feedwater Not selected 061 Auxiliary/Emergency Feedwater Ability to (a) predict the impacts of the X following malfunctions or operations 3.4* 89 on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.05 Automatic control malfunction 062 AC Electrical Distribution Not selected 063 DC Electrical Distribution Not selected 064 Emergency Diesel Generator Not selected 073 Process Radiation Monitoring Not selected 076 Service Water Not selected 078 Instrument Air Not selected 103 Containment Ability to (a) predict the impacts of the X following malfunctions or operations 3.6* 90 on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Containment evacuation (including recognition of the alarm)

K/A Category Point Totals: 3 2 Group Point Total: 5 NUREG-1021, Revision 9 Page 5 of 7

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive Not selected 002 Reactor Coolant Not selected 011 Pressurizer Level Control Not selected 014 Rod Position Indication Not selected 015 Nuclear Instrumentation Not selected 016 Non-nuclear Instrumentation Ability to (a) predict the impacts of the X following malfunctions or operations 3.3* 91 on the NNIS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Interruption of transmitted signal 017 In-core Temperature Monitor Not selected 027 Containment Iodine Removal Not applicable to this Unit 028 Hydrogen Recombiner and Purge Control Not selected 029 Containment Purge Not selected 033 Spent Fuel Pool Cooling Not selected 034 Fuel Handling Equipment Not selected 035 Steam Generator Not selected 041 Steam Dump/Turbine Not selected Bypass Control 045 Main Turbine Generator Not selected 055 Condenser Air Removal Not selected 056 Condensate Not selected 068 Liquid Radwaste X 2.4.41 Knowledge of the emergency 4.1 92 action level thresholds and classifications.

071 Waste Gas Disposal X 2.3.8 Knowledge of process for 3.2 93 performing a planned gaseous radioactive release.

072 Area Radiation Monitoring Not selected 075 Circulating Water Not selected 079 Station Air Not selected 086 Fire Protection Not selected K/A Category Totals: 1 2 Group Point Total: 3 NUREG-1021, Revision 9 Page 6 of 7

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One Unit 2 SRO Written Outline Date of Exam: 07/14/2006 Category K/A # Topic SRO-Only IR #

2.1.11 Knowledge of less than one hour technical specification action statements for systems. 3.8 94 2.1.30 Ability to locate and operate components, including local controls. 3.4 95 1.

Conduct of Operations Subtotal 2 2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis of 3.3 96 any technical specification is reduced by a proposed change, test, or experiment.

2.2.11 3.4* 97 Knowledge of the process for controlling temporary changes.

2.

Equipment Control Subtotal 2 2.3.6 Knowledge of the requirements for reviewing and approving release permits. 3.1 98 3.

Radiation Control Subtotal 1 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations. 2.8 99 2.4.48 Ability to interpret control room indications to verify the status and operation of system, and 3.8 100 understand how operator actions and directives affect plant and system conditions.

4.

Emergency Procedures/ Plan Subtotal 2 Tier 3 Point Total 7 NUREG-1021, Revision 9 Page 7 of 7

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO-2 Date of Examination: 07/17/2006 Examination Level: RO SRO Operating Test Number: 1 Type Administrative Topic Describe activity to be performed Code*

(see note)

Conduct of Operations Ability to perform specific system and integrated plant 2.1.23 RO (3.9) procedures during all modes of plant operation.

N Determine volume of Boric acid and DI water to makeup to RWT.

JPM-ANO-2-JPM-NRC-ADMIN RWT Ability to perform specific system and integrated plant Conduct of Operations procedures during all modes of plant operation.

2.1.23 RO (3.9) M Determine CEDM temperature using OP 2105.009.

Modified-JPM-ANO-2-JPM-NRC-ADMIN XTCEA Knowledge of Surveillance procedures.

Equipment Control 2.2.12 RO (3.0) D/P Review 2P89B Surveillance as RO.

Direct-JPM-ANO-2-NRC-ADMIN-Surveillance review 2P89B Radiation Control Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure.

2.3.10 RO (2.9)

M Review survey map and RWP to determine radiological requirements JPM-ANO-2-NRC-ADMIN-2P60B isolation requirements Emergency Plan NA NA NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking 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 & ROretakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 Exams ( 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO-2 Date of Examination: 07/17/2006 Examination Level: RO SRO Operating Test Number: 1 Type Administrative Topic Code* Describe activity to be performed (see note)

Determine RPS trip set point due to inoperable MSSV is correct using Technical Specifications.

Conduct of Operations D Ability to apply technical specification for a system 2.1.12 SRO (4.0) Direct- ANO-2-JPM-NRC-ADMIN MSSVINOP Ability to perform specific system and integrated plant Conduct of Operations procedures during all modes of plant operation.

M Approve CEDM temperature calculation using OP 2105.009.

2.1.23 SRO (4.0)

Modified-ANO-2-JPM-NRC-ADMIN XTCEA Equipment Control Knowledge of Surveillance procedures.

D/P Review 2P89B Surveillance.

2.2.12 SRO (3.4)

Direct-ANO-2-JPM-NRC-ADMIN-Surveillance review 2P89B Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure.

Radiation Control Review survey map and RWP to determine radiological D

2.3.10 SRO (3.3) requirements Modified-JPM-ANO-2-JPM-NRC-ADMIN-2P60B Radiological requirements Knowledge of the emergency plan.

Emergency Plan Classify EAL and complete applicable Shift Manager forms.

N 2.4.29 SRO (4.0) New-ANO-2-JPM-NRC-ADMIN-Classify event and Complete SM E-plan forms NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking 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 & ROretakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 Exams ( 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________ Date of Examination: _07/17/2006____

Exam Level (circle one): RO SRO(I) SRO(U) Operating Test No.: ____1_________

Control Room Systems@ ( 8 for RO; 7 for SRO-I; 2 or 3 for SRO- U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. ANO-2-JPM-NRC-ELEC EOP 2 A/L/N/S 6 062 A4.01 RO-3.3 SRO-3.1 Electrical Energize 2A2, non-vital 4160VAC bus following a Loss Of Offsite Power
b. ANO-2-JPM-NRC-SIT006 A/L/D/S 2 006 A4.08 RO-4.2 SRO-4.3 Inventory Isolate Safety Injection Tanks with Safety Injection Actuation System actuated
c. ANO-2-JPM-NRC-LTOP L/N/S 3 010 K4.03 RO-3.8 SRO-4.1 Reactor Pressure Control Respond to Annunciator 2K10 C-4 and place low temperature overpressure relief valves inservice
d. ANO-2-JPM-NRC-RCP03 A/L/D/P/S 8 Plant Service Systems 008 A4.01 RO-3.3 SRO-3.1 Restore Component Cooling Water to Reactor Coolant Pumps
e. ANO-2-JPM-NRC-CEA1 D/S 1 Reactivity 001 A4.03 RO-4.0 SRO-3.7 Exercise a Control Element Assembly
f. ANO-2-JPM-NRC-FWCS1 D/S 4 Heat Removal 035 A4.01 RO-3.7 SRO- 3.6 Place Feed Water Control System in Automatic
g. ANO-2-JPM-NRC-H2001 C/D 5 028 A4.01 RO-4.0 SRO-4.0 Containment Integrity Manually start Hydrogen analyzer
h. ANO-2-JPM-NRC-ICI01 7 D/P/S 015 A2.02 RO-3.1 SRO-3.5 Instrumentation Remove Incore instrument from scan for Core Operating Limits Supervisory System In- Plant Systems@ ( 3 for RO; 3 for SRO-I; 3 or 2 for SRO- U)
i. ANO-2-JPM-NRC-AACGLS 064 A3.06 RO-3.3 SRO-3.4 A/D 6 Electrical Local start of Station Blackout Diesel
j. ANO-2-JPM-NRC-P36ASD 004 A4.08 RO-3.8 SRO-3.4 D/E/R 2 Inventory Operate Charging Pump 2P36B Locally During Alternate Shutdown
k. ANO-2-JPM-NRC-PRHTR 3 D/E Reactor Pressure 006 A2.01 RO-3.3 SRO-3.6 Control Locally control pressurizer proportional heaters

@ All control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________ Date of Examination: _07/17/2006____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ____1_________

Control Room Systems@ ( 8 for RO; 7 for SRO-I; 2 or 3 for SRO- U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. ANO-2-JPM-NRC-ELEC EOP 2 A/L/N/S 6 062 A4.01 RO-3.3 SRO-3.1 Electrical Energize 2A2, non-vital 4160VAC bus following a Loss Of Offsite Power
b. ANO-2-JPM-NRC-SIT006 A/L/D/S 2 006 A4.08 RO-4.2 SRO-4.3 Inventory Isolate Safety Injection Tanks with Safety Injection Actuation System actuated
c. ANO-2-JPM-NRC-LTOP L/N/S 3 010 K4.03 RO-3.8 SRO-4.1 Reactor Pressure Control Respond to Annunciator 2K10 C-4 and place low temperature overpressure relief valves inservice
d. ANO-2-JPM-NRC-RCP03 A/L/D/P/S 8 Plant Service Systems 008 A4.01 RO-3.3 SRO-3.1 Restore Component Cooling Water to Reactor Coolant Pumps
e. ANO-2-JPM-NRC-CEA1 D/S 1 Reactivity 001 A4.03 RO-4.0 SRO-3.7 Exercise a Control Element Assembly
f. ANO-2-JPM-NRC-FWCS1 D/S 4 Heat Removal 035 A4.01 RO-3.7 SRO- 3.6 Place Feed Water Control System in Automatic
g. ANO-2-JPM-NRC-H2001 C/D 5 028 A4.01 RO-4.0 SRO-4.0 Containment Integrity Manually start Hydrogen analyzer h.

In- Plant Systems@ ( 3 for RO; 3 for SRO-I; 3 or 2 for SRO- U)

i. ANO-2-JPM-NRC-AACGLS 064 A3.06 RO-3.3 SRO-3.4 A/D 6 Electrical Local start of Station Blackout Diesel
j. ANO-2-JPM-NRC-P36ASD 004 A4.08 RO-3.8 SRO-3.4 D/E/R 2 Inventory Operate Charging Pump 2P36B Locally During Alternate Shutdown
k. ANO-2-JPM-NRC-PRHTR 3 D/E Reactor Pressure 006 A2.01 RO-3.3 SRO-3.6 Control Locally control pressurizer proportional heaters

@ All control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________ Date of Examination: _7/17/2006____

Exam Level : RO / SRO(I) / SRO(U) Operating Test No.: ____1_________

Control Room Systems@ ( 8 for RO; 7 for SRO-I; 2 or 3 for SRO- U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. ANO-2-JPM-NRC-ELEC EOP 2 A/L/N/S 6 062 A4.01 RO-3.3 SRO-3.1 Electrical Energize 2A2, non-vital 4160VAC bus following a Loss Of Offsite Power
b. ANO-2-JPM-NRC-SIT006 A/L/D/S 2 006 A4.08 RO-4.2 SRO-4.3 Inventory Isolate Safety Injection Tanks with Safety Injection Actuation System actuated
c. ANO-2-JPM-NRC-LTOP L/N/S 3 010 K4.03 RO-3.8 SRO-4.1 Reactor Pressure Control Respond to Annunciator 2K10 C-4 and place low temperature overpressure relief valves inservice 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-AACGLS 064 A3.06 RO-3.3 SRO-3.4 A/D 6 Electrical Local start of Station Blackout Diesel
j. ANO-2-JPM-NRC-P36ASD 004 A4.08 RO-3.8 SRO-3.4 D/E/R 2 Inventory Operate Charging Pump 2P36B Locally During Alternate Shutdown k.

@ All control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 1 Op-Test No.: 2006-1 Page 1 Examiners: Operators:

Initial Conditions:

20% MOL, All Engineered Safety Features systems are in standby. Plant startup following a five day stator water cooling outage. 2P27, MFP standby lube oil pump tagged out for maintenance. Green Train Maintenance Week.

Turnover:

20%. 250 EFPD. EOOS indicates Minimal Risk. Plant Startup in progress; OP 2104.004 section 9, raising power above 20%, is the controlling procedure. 2P27, MFP standby lube oil pump tagged out for maintenance. Green Train Maintenance Week.

Event Malf. No. Event Event No. Type* Description 1 Raise Power R (ATC) Raise reactor and turbine power.

above 20%

2 XRCCHAPCNT I (ATC) Pressurizer control channel pressure fails high.

3 CCWFAILBAUTO C (CBOT) Loop II Component Cooling Water pump C Trips CCW2P33CPWR and B Component Cooling Water pump fails to automatically start.

4 RCP2P32AASLK M (ATC) Reactor Coolant System inter-system leak into N (CBOT) Component Cooling Water system resulting in Loss of Coolant Accident and Safety Injection Actuation System (post reactor trip).

5 BUS2H2 M (ALL) 2H2 lockout. Loss of 2 Reactor Coolant Pumps and one condenser circulating water pump.

6 RPSRXAUTO C (ATC) Reactor Protection System fails to automatically trip the reactor on loss of Reactor Coolant Pumps.

7 XMSHDRPRS I (CBOT) Steam Dump and Bypass Control System fails to automatically open bypass and dump valves to control Steam Generator pressure.

8 HPI2P89AFAL C (CBOT) 2P89A, A High Pressure Safety Injection pump fails to auto-start.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 2 Op-Test No.: 2006-1 Page 1 Examiners: Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. Green Train Maintenance Week.

Turnover:

100%. 250 EFPD. EOOS indicates Minimal Risk. Green Train Maintenance Week. B main chiller is tagged out for oil change out.

Event Malf. No. Event Event No. Type* Description 1 COND2P2AWIND C(CBOT) A Condensate Pump motor winding with rise resulting in manual start of D Condensate Pump and securing A Condensate Pump.

2 XCV2LT4861 I (ATC) Volume Control Tank level instrument fails low resulting in Refueling Water Tank being aligned to Coolant Charging Pump suction.

3 CWS2P3BBOL R (ATC) Trip 2P3B, B Circulating Water Pump, which N (CBOT causes a partial loss of main condenser circulating water flow resulting in a rapid down power to ~ 90%

power.

4 MSSGBLK M (CBOT) B Steam Generator Excess Steam Demand (ESD)

M (ATC) inside containment results in manual reactor trip and control of Reactor Coolant System heat up and Pressurizer pressure post SG blowdown.

5 CEA51STUCK C (ATC) Control Element Assembly #51 stuck on reactor trip results in Emergency Boration.

6 CV1036-2 C (CBOT) B Emergency Feed Water (EFW) Pump to B CV1075-1 Steam Generator valves fail to close from control room resulting in over feeding Steam Generator with ESD cooldown of RCS unnecessarily. Secure B EFW pump.

7 BS2P35BFAL C (CBOT) B Spray Pump fails to start. Can be manually BS2P35AFAULT started.

A Spray Pump cannot be restarted.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 3 Op-Test No.: 2006-1 Page 1 Examiners: Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. Green Train Maintenance Week.

Turnover:

100%. 250 EFPD. EOOS indicates Minimal Risk. Green Train Maintenance Week.

Tornado watch for Pope County in effect until 10:00pm today. Natural Emergency AOP actions have been completed.

Event Malf. No. Event Event No. Type* Description 1 CV-4816 C(ATC) Letdown flow control valve fails closed. Restore Letdown using 2CV 4817.

2 XFW2FIS0735 I (CBOT) A Main Feedwater Pump (MFP) suction flow transmitter fails low. Recirculation valves (A loop condensate and A MFP) to manual and closed.

3 MFWWPMPBTRP R (ATC) B MFP trips on thrust bearing wear. Emergency N (CBOT borate and reduce power to <90%. Start D Condensate Pump.

4 500LOSE500 M (CBOT) Loss of offsite power due to tornado.

500LOSE161 M (ATC) 5 EDGDG1OIL C (CBOT) #1 Emergency Diesel Generator trips on low lube oil pressure. Loss of Red vital AC power. Loss of 2Y1, 120VAC non-vital power. CBOT energize Vital Red AC busses with Station Blackout diesel generator.

6 Channel 1 PZR I (ATC) Pressurizer control channel 1 for level and pressure level and pressure will fail low due to loss of power. Control manually /

channels lose select opposite channel.

power.

7 CV0332 C (CBOT) Over speed trip of A Emergency Feedwater Pump.

Requires starting B Emergency Feedwater Pump.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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