ML12285A291

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ANO2-2012-08 Draft Outlines
ML12285A291
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/27/2012
From:
Operations Branch IV
To:
Osterholtz C
References
Download: ML12285A291 (22)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Examination Level: RO X SRO Operating Test Number: 2012-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine any limits for CEA positions using the COLR PDIL A1. Conduct of Operations D/P/R ANO-2-JPM-NRC-ADMIN-PDIL 2.1.25 RO (3.9)

Calculate Time to Boil using computer program A2. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-TTBCRO 2.1.23 RO (4.3)

Review 2P-89B surveillance to determine operability A3. Equipment Control D/R ANO-2-JPM-NRC-ADMIN-2P89BSURV 2.2.42 RO (3.9)

Calculate expected dose for Re-entry during emergency and if applicable limits will be exceeded A4. Radiation Control N/R ANO-2-JPM-NRC-ADMIN-EMGRESP 2.3.4 RO (3.2)

Emergency Procedures/Plan 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 & RO retakes)

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

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

Revision 0

ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:ANO Unit 2 Date of Exam:6/24/2012 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 1 2 N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions 5 5 Tier Totals 4 4 5 5 5 4 27 10 1 2 3 2 3 3 3 3 2 3 1 3 28 2 3 5 2.

2 1 1 1 1 1 1 1 1 0 1 1 10 0 1 2 3 Plant Systems Tier Totals 3 4 3 4 4 4 4 3 3 2 4 38 3 5 8 1 2 3 4 1 2 3 4

3. Generic Knowledge and Abilities 10 7 Categories 2 2 3 3 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).

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 Section D.1.b of ES-401 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. Refer to Section D.1.b of ES-401 for the applicable K/As.

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

1 2 3 1 2 0 Reasons for closing the main turbine governor valve and the main 000007 Reactor Trip / 1 3.7 3 turbine stop valve after a reactor trip 1

CE/E02 Reactor Trip Recovery / 1 0

000008 Pressurizer Vapor Space Accident / 3 Control of PZR level 3.6 1 6

3 000009 Small Break LOCA / 3 RCS water inventory balance and Tech-Spec limits 3.3 1 3

0 000011 Large Break LOCA / 3 Flowpath for sump recirculation 3.9 1 8

000015 RCP Malfunctions / 4 0 Natural circulation in a nuclear reactor power plant 4.4 1 000017 RCP Malfunctions (Loss of RC Flow) / 4 1 0

000022 Loss of Rx Coolant Makeup / 2 CVCS charging pump ammeters and running indicators 2.9 1 6

000025 Loss of RHR System / 4 0 Ability to interpret control room indications to verify the status and 02.

000026 Loss of Component Cooling Water / 8 operation of a system, and understand how operator actions and 4.2 1 44 directives affect plant and system conditions.

000027 Pressurizer Pressure Control System 0

Malfunction / 3 0 definition of negative temperature coefficient as applied to large 000029 ATWS / 1 2.8 1 5 PWR coolant systems 0

000038 Steam Gen. Tube Rupture / 3 Criteria for securing RCP 4.1 1 8

0 000040 Steam Line Rupture / 4 Sensors and detectors 2.6 2

1 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 1

Facilitys heat removal systems, including primary coolant, 0

CE/E06 Loss of Feedwater / 4 emergency coolant, the decay heat removal systems, and 3.5 2 relations between the proper operation of these systems to the 0

000055 Station Blackout / 6 Existing valve positioning on a loss of instrument air system 3.4 1 1

04.

000056 Loss of Off-site Power / 6 Ability to identify post-accident instrumentation. 3.7 1 03 2 Interlocks in effect on loss of ac vital electrical instrument bus that 000057 Loss of Vital AC Inst. Bus / 6 3.6 1 0 must be bypassed to restore normal equipment operation

04. Knowledge of system set points, interlocks and automatic actions 000058 Loss of DC Power / 6 4.5 1 02 associated with EOP entry conditions.

0 Effect on the nuclear service water discharge flow header of a 000062 Loss of Nuclear Svc Water / 4 3.5 1 4 loss of CCW 0 Restoration of systems served by instrument air when pressure is 000065 Loss of Instrument Air / 8 2.9 1 3 regained 000077 Generator Voltage and Electric 0 Breakers, relays 3.1 1 Grid Disturbances / 6 2 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 E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 02 Signal inputs to rod control system 2.7 1

04. Knowledge of the operational implications of EOP warnings, 000005 Inoperable/Stuck Control Rod / 1 cautions, and notes.

3.8 1 20 000024 Emergency Boration / 1 02 Relationship between boron addition and reactor power 3.6 1 000028 Pressurizer Level Malfunction / 2 02 CVCS 3.4 1 000032 Loss of Source Range NI / 7 01 Manual restoration of power 3.1 1 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 0 000037 Steam Generator Tube Leak / 3 08 Criteria for securing RCP 4.1 1 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 Vital equipment and control systems to be maintained and 000067 Plant Fire On-site / 9 8 16 operated during a fire 3.3 1 000068 Control Room Evac. / 8 02 Reactor trip system 3.7 1 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 06 Actions contained in EOP for high reactor coolant activity 3.2 1 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 0

0 0

0 0

0 0

0 0

K/A Category Totals: 1 1 2 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 System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0

003 Reactor Coolant Pump S/G 3.5 1 2

01.

004 Chemical and Volume Control Knowledge of system purpose and/or function. 3.9 1 27 0 0 RHR pumps; System protection logics, including high-005 Residual Heat Removal pressure interlock, reset controls, and valve interlocks 3; 3.2 2 1 7 0

006 Emergency Core Cooling ESFAS-operated valves 3.6 1 4

0 007 Pressurizer Relief/Quench Tank Method of forming a steam bubble in the PZR 3.1 1 2

0 01. CCW temperature; Knowledge of the purpose and function 2.9; 008 Component Cooling Water of major system components and controls.

2 2 28 4.1 0 0 Constant enthalpy expansion through a valve; Pressure 2.6; 010 Pressurizer Pressure Control detection systems 2

2 1 2.7 0

012 Reactor Protection RPS channels, components, and interconnections 3.3 1 1

013 Engineered Safety Features 0 Sensors and detectors 2.7 1 Actuation 1 0

022 Containment Cooling Initiation of safeguards mode of operation 4.1 1 1

025 Ice Condenser 0 Ability to interpret control room indications to verify the 02.

026 Containment Spray status and operation of a system, and understand how 4.2 1 44 operator actions and directives affect plant and system Utilization of steam pressure program control when steam 0

039 Main and Reheat Steam dumping through atmospheric relief/dump valves, including 2.9 1 4 T-ave. limits 1

059 Main Feedwater Failure of feedwater control system 3.0 1 1

0 061 Auxiliary/Emergency Feedwater Pumps 2.6 1 2

0 062 AC Electrical Distribution Synchronizing and paralleling of different ac supplies 3.1 1 7

0 0 Battery capacity as it is affected by discharge rate; Meters, 2.5; 063 DC Electrical Distribution annunciators, dials, recorders, and indicating lights 2

1 1 2.7 0

064 Emergency Diesel Generator ED/G lube oil temperature and pressure 3.0 1 1

0 0 Radiation theory, including sources, types, units, and 2.5; 073 Process Radiation Monitoring effects; Erratic or failed power supply 2

1 1 2.5 RHR components, controls, sensors, indicators, and alarms, 0 0 076 Service Water including rad monitors; Automatic start features associated 3; 2.9 2 5 2 with SWS pump controls 0 0 3.4; 078 Instrument Air MSIV air; Air pressure 2 5 1 3.1 0

103 Containment CCS 3.6 1 1

K/A Category Totals: 2 3 2 3 3 3 3 2 3 1 3 Group Point Total: 28 ES-401, 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 System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 1 Relationship between effects of the primary coolant system and 002 Reactor Coolant 1 the secondary coolant system 4.0 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 0

015 Nuclear Instrumentation 1

NIS channels, components, and interconnections 3.3 1 016 Non-nuclear Instrumentation 0 0

017 In-core Temperature Monitor 1

Sensors and detectors 2.7 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 0

033 Spent Fuel Pool Cooling 3

Spent fuel temperature 3.0 1 034 Fuel Handling Equipment 0 0 Recognition that increasing radiation levels in secondary 035 Steam Generator 8 systems may mean leaking and possibly ruptured S/G tubes 4.1 1 0

041 Steam Dump/Turbine Bypass Control 2

Steam pressure 3.1 1 045 Main Turbine Generator 0 0

055 Condenser Air Removal 6

PRM system 2.6 1 056 Condensate 0 068 Liquid Radwaste 0

01. Knowledge of the purpose and function of major system 071 Waste Gas Disposal 4.1 1 28 components and controls.

0 072 Area Radiation Monitoring 2

Detector failure 2.8 1 0

075 Circulating Water 1

Heat sink 2.5 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 1 1 1 1 1 1 1 1 0 1 1 Group Point Total: 10 ES-401, 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 E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 0 Proper actions to be taken if the automatic safety functions have 000007 Reactor Trip / 1 4.6 2 not taken place 1

CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 000009 Small Break LOCA / 3 0 000011 Large Break LOCA / 3 0 000015 RCP Malfunctions / 4 0

000017 RCP Malfunctions (Loss of RC Flow) / 4 Ability to analyze the effect of maintenance activities, such as 02.

000022 Loss of Rx Coolant Makeup / 2 degraded power sources, on the status of limiting conditions for 4.2 1 36 operations.

000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System 0 Tech-Spec limits for RCS pressure 4.3 1 Malfunction / 3 4 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture / 4 0

CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 0

CE/E06 Loss of Feedwater / 4 000055 Station Blackout / 6 0 000056 Loss of Off-site Power / 6 0 000057 Loss of Vital AC Inst. Bus / 6 0

04. Ability to diagnose and recognize trends in an accurate and timely 000058 Loss of DC Power / 6 4.2 1 47 manner utilizing the appropriate control room reference material.

0 The normal values for SWS-header flow rate and the flow rates to 000062 Loss of Nuclear Svc Water / 4 2.5 1 5 the components cooled by the SWS

02. Ability to recognize system parameters that are entry-level 000065 Loss of Instrument Air / 8 4.6 1 42 conditions for Technical Specifications.

000077 Generator Voltage and Electric 0

Grid Disturbances / 6 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 E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 0 Dropped rod, using in-core/ex-core instrumentation, in-core or 000003 Dropped Control Rod / 1 03 loop temperature measurements 3.8 1 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 Ability to analyze the effect of maintenance activities, such as 02.

000028 Pressurizer Level Malfunction / 2 degraded power sources, on the status of limiting conditions for 4.2 1 36 operations.

04.

000032 Loss of Source Range NI / 7 Knowledge of abnormal condition procedures. 4.2 1 11 000033 Loss of Intermediate Range NI / 7 0 000036 Fuel Handling Accident / 8 02 Occurrence of a fuel handling incident 4.1 1 000037 Steam Generator Tube Leak / 3 0 000051 Loss of Condenser Vacuum / 4 0 000059 Accidental Liquid RadWaste Rel. / 9 0 000060 Accidental Gaseous Radwaste Rel. / 9 0 000061 ARM System Alarms / 7 0 000067 Plant Fire On-site / 9 8 0 000068 Control Room Evac. / 8 0 000069 Loss of CTMT Integrity / 5 0 000074 Inad. Core Cooling / 4 0 000076 High Reactor Coolant Activity / 9 0 CE/A13 Natural Circ. / 4 0 CE/A11 RCS Overcooling / 4 0 CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 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 System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0 005 Residual Heat Removal 0 006 Emergency Core Cooling 0 0

007 Pressurizer Relief/Quench Tank Abnormal pressure in the PRT 3.2 1 2

008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features 0

Actuation 022 Containment Cooling 0 025 Ice Condenser 0 02.

026 Containment Spray Knowledge of surveillance procedures. 4.1 1 12 039 Main and Reheat Steam 0

01. Ability to locate and operate components, including local 059 Main Feedwater controls.

4.0 1 30 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 0

063 DC Electrical Distribution Loss of ventilation during battery charging 3.1 1 2

04.

064 Emergency Diesel Generator Knowledge of EOP mitigation strategies. 4.7 1 06 073 Process Radiation Monitoring 0 076 Service Water 0 078 Instrument Air 0 103 Containment 0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total: 5 ES-401, 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 System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0 002 Reactor Coolant 0 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 016 Non-nuclear Instrumentation 0 0

017 In-core Temperature Monitor 2

Core damage 4.1 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0

02. Ability to recognize system parameters that are entry-level 033 Spent Fuel Pool Cooling 4.6 1 42 conditions for Technical Specifications.

034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0

01. Knowledge of facility requirements for controlling 055 Condenser Air Removal 3.2 1 13 vital/controlled access.

056 Condensate 0 068 Liquid Radwaste 0 071 Waste Gas Disposal 0 072 Area Radiation Monitoring 0 075 Circulating Water 0 079 Station Air 0 086 Fire Protection 0 K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3 ES-401, 25 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:ANO Unit 2 Date of Exam:6/24/2012 RO SRO-Only Category K/A # Topic IR # IR #

2.1. 20 Ability to interpret and execute procedure steps. 4.6 1 2.1. 03 Knowledge of shift or short-term relief turnover practices. 3.7 1

1. 2.1. 03 Knowledge of shift or short-term relief turnover practices. 3.9 1 Conduct of 2.1. 13 Knowledge of facility requirements for controlling vital/controlled access. 3.2 1 Operations 2.1.

2.1.

Subtotal 2 2 Ability to determine the expected plant configuration using design and configuration 2.2. 15 control documentation, such as drawings, line-ups, tag-outs, etc. 3.9 1 2.2. 40 Ability to apply Technical Specifications for a system. 3.4 1

2. 2.2. 11 Knowledge of the process for controlling temporary design changes. 3.3 1 Equipment Knowledge of the process for managing maintenance activities during shutdown 2.2. 18 operations, such as risk assessments, work prioritization, etc. 3.9 1 Control 2.2.

2.2.

Subtotal 2 2 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Ability to comply with radiation work permit requirements during normal or abnormal

3. 2.3. 07 conditions. 3.5 1 Radiation Control 2.3. 06 Ability to approve release permits. 3.8 1 2.3.

2.3.

Subtotal 3 1 2.4. 01 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 2.4. 42 Knowledge of emergency response facilities. 2.6 1

4. Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 2.4. 47 appropriate control room reference material. 4.2 1 Emergency Procedures 2.4. 14 Knowledge of general guidelines for EOP usage. 4.5 1

/ Plan 2.4. 08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs. 4.5 1 2.4.

Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 (RO) 003/AA2.05 A TC map for Unit 2 (simulator) does not show an appreciable difference between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.02 as the replacement KA.

1/2 (RO) 028/AA1.01 This KA states "Ability to operate and/or monitor the following as they apply to the Pressurizer Level Control Malfunctions: PZR level reactor protection bistables" Unit 2 does not have reactor protection bistables for PZR level.

Selected KA 028 AA1.02 2/1 (RO) 073/A2.02 This KA is too close to the other KA selected for this system. Selected KA 073 K 5.01 as a replacement.

2/1 (RO) 076/K4.03 Unit 2 does not have an auto opening feature for SWS valves to CCW heat exchangers. Selected 076 K4.02 as the replacement KA.

2/2 (RO) 071/2.4.3 This KA was also chosen in T1G1 for system 056 and is therefore redundant. Selected 071 2.1.28 as the replacement KA.

3 (RO) G/2.2.5 This KA has too low of a KA value for the RO position to be used for this system (KA 2.2.5), replaced with KA 2.2.40 (RO rating 3.4).

1/2 005/AA2.04 A TC map for Unit 2 (simulator) does not show an appreciable difference (SRO) between the location for a dropped CEA as compared to other core locations. Selected 003 AA2.03 as the replacement KA.

1/2 032/2.1.19 This generic KA states: Ability to use plant computer to evaluate system or (SRO) component status. This KA is best evaluated on the operating exam vs.

the written exam. Selected 2.4.11 as the replacement KA.

2/2 055/2.2.3 This KA applies to multi-unit sites with similar units, ANO is a multi-unit site (SRO) but with dissimilar units. A KA with a value >2.5 could not be selected from the CARS system (055) for the SRO so KA 055 2.1.13 was selected.

3 (SRO) 2.1.6 This KA states: Ability to manage the control room crew during plant transients. This KA does not lend itself to written exam evaluation but should be reserved for the operating exam. Replaced with KA 2.1.13.

ES-401, Page 27 of 33

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO X SRO-I SRO-U Operating Test No.: 2012-1 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 S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01 8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S Plant service systems S5. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 A/D/P/S Containment Drain the containment sump Integrity S6. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/P/S Reactivity control Perform a CEA exercise S7. ANO-2-JPM-NRC-CPC06 7 012 A4.02 RO-3.3/SRO-3.4 D/S Place #1 CEAC to inop on B CPC Instrumentation S8. ANO-2-JPM-NRC-AOP3 3 010 A2.02 RO-3.9/SRO-3.9 A/D/P/S Pressure Control Isolate failed PZR spray valve In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-EDDCB 6 064 A4.01 RO-4.0/SRO-4.3 A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I 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)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 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 Revision 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Examination Level: RO SRO X Operating Test Number: 2012-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Review performing transferring Unit Auxiliary Calculation and determine if it they can be transferred.

A5. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-SU2LOADSRO 2.1.32 SRO (4.0)

Review Time to Boil Calculation.

A6. Conduct of Operations D/R ANO-2-JPM-NRC-AMDIN-TTBCSRO 2.1.23 SRO (4.4)

Supervisory review of maintenance activities for configuration control A7. Equipment Control D/R ANO-2-JPM-NRC-ADMIN-MAINT 2.2.14 SRO (4.3)

Calculate expected dose for Re-entry during an emergency and determine if entry is allowed.

A8. Radiation Control N/R ANO-2-JPM-NRC-ADMIN-EMGRESPSRO 2.3.4 SRO (3.7)

Determine Emergency Action Level for given conditions.

A9. Emergency D/P/R ANO-2-JPM-NRC-ADMIN-EAL11 Procedures/Plan 2.4.41 SRO (4.6)

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 & RO retakes)

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

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

Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2012-1 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 S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I 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)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 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 Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012 Exam Level: RO SRO-I X SRO-U Operating Test No.: 2012-1 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 S1. ANO-2-JPM-NRC-SIT09 2 006 A4.02 RO-4.0/SRO-3.8 A/D/EN/L/S Inventory Control Isolate SITs following SIAS with SIAS reset S2. ANO-2-JPM-NRC-ELEC05 6 062 A4.01 RO3.3/SRO3.1 N/S Electrical Transfer Auxiliaries from SU#2 to SU#3 for 2A-1 S3. ANO-2-JPM-NRC-SDBC2 4 041 A4.05 RO-3.1/SRO-3.3 A/L/N/S Heat Removal Manually Operate SDBCS valves S4. ANO-2-JPM-NRC-CCW01 8 008 A4.01 RO-3.3/SRO-3.1 Secure CCW system using EOP D/L/S Plant service systems S5. ANO-2-JPM-NRC-CNMT2 5 103 A3.01 RO-3.9/SRO-4.2 A/D/P/S Containment Drain the containment sump Integrity S6. ANO-2-JPM-NRC-CEA01 1 001 A4.03 RO-4.0/SRO-3.7 D/P/S Perform a CEA exercise Reactivity control S7. ANO-2-JPM-NRC-CPC06 7 012 A4.02 RO-3.3/SRO-3.4 D/S Instrumentation Place #1 CEAC to inop on B CPC In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1. ANO-2-JPM-NRC-EDDCB 6 064 A4.01 RO-4.0/SRO-4.3 A/D/E/L Electrical Start EDG 2K-4B without DC P2. ANO-2-JPM-NRC-MGSU 1 001 A4.08 RO-3.7/SRO-3.4 D/L Reactivity control Start the First MG set P3. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 D/E/R Plant service Perform emergency SW make up to SFP systems

@ All RO and SRO-I 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)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 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 Revision 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Arkansas Nuclear One Date of Exam: 8-27-12 Operating Test No.: 2012-1 A E Scenarios P V 1 2 4 T M 3(currently selected P E as spare) O I L N T N CREW CREW CREW CREW I I T A POSITION POSITION POSITION POSITION M C L U A T S A B S A B S A B S A B M(*)

R T O R T O R T O R T O N Y R I U O C P O C P O C P O C P T P E

RO RX 3 1 1 1 1 0 NOR 1 1 1 1 1 SRO-I X I/C 2,3,4, 6,9 3,6 7 4 4 2 5,8 SRO-U MAJ 6,7 5,7 5 4 2 2 1 TS 2,5 2 0 2 2 RX 3 1 1 1 0 RO NOR 1 1 1 1 1 1 SRO-I 4,5 2,3,4, 2,3,4, I/C 8 4 4 2 X 6,8,9 6,7 SRO-U 6,7 5,7 5 MAJ 4 2 2 1 TS 2,4 2,4 2 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

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ES-301 Transient and Event Checklist Form ES-301-5 Facility: Arkansas Nuclear One Date of Exam: 8-27-12 Operating Test No.: 2012-1 A E Scenarios P V 1 2 4 T M 3(currently selected P E as spare) O I L N T N CREW CREW CREW CREW I I T A POSITION POSITION POSITION POSITION M C L U A T S A B S A B S A B S A B M(*)

R T O R T O R T O R T O N Y R I U O C P O C P O C P O C P T P E

RO RX 3 1 1 1 0 X 1 1 SRO-I NOR 1 1 1 1 I/C 4,5 2,3,8 2,4,7 5 4 4 2 SRO-U 6,7 5,7 5 MAJ 4 2 2 1 TS 0 0 2 2 RO RX 4 1 1 1 1 0 X NOR 1 1 1 1 1 SRO-I I/C 2,3,8 6,9 3,6 5 4 4 2 SRO-U MAJ 6,7 5,7 5 4 2 2 1 TS 0 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2,3,4, 5 4 4 2 5,8 SRO-U MAJ 6,7 2 2 2 1 X

TS 2,5 2 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 1 SRO-I I/C 2,3,4, 2,3,4, 6 4 4 2 6,8,9 6,7 SRO-U MAJ 5,7 5 2 2 2 1 X

TS 2,4 2,4 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

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