ML12285A291

ANO2-2012-08 Draft Outlines

ML12285A291
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/27/2012
From:	Operations Branch IV
To:
Osterholtz C O
References
Download: ML12285A291 (22)

Text

Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility: Arkansas Nuclear One Unit 2Date of Examination: 08/27/2012Examination Level: RO X SROOperating Test Number: 2012-1Administrative Topic (see Note)Type Code*Describe activity to be performedA1. Conduct of Operations2.1.25 RO (3.9)D/P/RDetermine any limits for CEA positions using the COLRPDILANO-2-JPM-NRC-ADMIN-PDILA2. Conduct of Operations2.1.23 RO (4.3)D/RCalculate Time to Boil using computer programANO-2-JPM-NRC-ADMIN-TTBCROA3. Equipment Control2.2.42 RO (3.9)D/RReview 2P-89B surveillance to determine operabilityANO-2-JPM-NRC-ADMIN-2P89BSURVA4. Radiation Control2.3.4 RO (3.2)N/RCalculate expected dose for Re-entry during emergencyand if applicable limits will be exceededANO-2-JPM-NRC-ADMIN-EMGRESPEmergency Procedures/PlanNOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:ANO Unit 2 Date of Exam:6/24/2012 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G*Total Total 1 333 33 3 18 6 2 112 22 1 9 4Tier Totals445 55 4 27 10 1 23233332313 28 5 2 11111111011 10 0 1 3Tier Totals34344443324 38 8 1 2 3 4 2 2 1 2 Note: 1.

Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.ES-401, 21 of 33 2.Plant Systems 2 5 SRO-Only Points RO K/A Category Points A2 G*1. Emergency

&Abnormal Plant Evolutions Tier Group 3 N/A N/A 3 2 5For 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.

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.

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

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.

3 2 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.

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).

3 2 4 2 2 3. Generic Knowledge and Abilities Categories 10 3 2 5 1 3 3 7 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.

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.

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

E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)

IR#000007 Reactor Trip / 1 0 3Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip 3.7 CE/E02 Reactor Trip Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 0 6Control of PZR level 3.6 1 000009 Small Break LOCA / 3 3 3RCS water inventory balance and Tech-Spec limits 3.3 1 000011 Large Break LOCA / 3 0 8Flowpath for sump recirculation 3.9 1 000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 1Natural circulation in a nuclear reactor power plant 4.4 1 000022 Loss of Rx Coolant Makeup / 2 0 6CVCS charging pump ammeters and running indicators 2.9 1 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 02.44Ability to interpret control room indications to verify the status andoperation of a system, and understand how operator actions anddirectives affect plant and system conditions.

4.2 1 000027 Pressurizer Pressure Control System Malfunction / 3 0 000029 ATWS / 1 0 5definition of negative temperature coefficient as applied to large PWR coolant systems 2.8 1 000038 Steam Gen. Tube Rupture / 3 0 8Criteria for securing RCP 4.1 1 000040 Steam Line Rupture / 4 0 2 Sensors and detectors 2.6 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 CE/E06 Loss of Feedwater / 4 0 2Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, andrelations between the proper operation of these systems to the

3.5 000055

Station Blackout / 6 0 1Existing valve positioning on a loss of instrument air system 3.4 1 000056 Loss of Off-site Power / 6 04.03Ability to identify post-accident instrumentation.

3.7 1 000057 Loss of Vital AC Inst. Bus / 6 2 0Interlocks in effect on loss of ac vital electrical instrument bus thatmust be bypassed to restore normal equipment operation 3.6 1 000058 Loss of DC Power / 6 04.02Knowledge of system set points, interlocks and automatic actionsassociated with EOP entry conditions.

4.5 1 000062 Loss of Nuclear Svc Water / 4 0 4Effect on the nuclear service water discharge flow header of a loss of CCW 3.5 1 000065 Loss of Instrument Air / 8 0 3Restoration of systems served by instrument air when pressure is regained 2.9 1 000077 Generator Voltage and Electric Grid Disturbances / 6 0 2 Breakers, relays 3.1 1 K/A Category Totals:

3333 3 3 18 ES-401, 22 of 33 Group Point Total:

1 1 1 ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)

IR#000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 02Signal inputs to rod control system 2.7 1 000005 Inoperable/Stuck Control Rod / 1 04.20Knowledge of the operational implications of EOP warnings, cautions, and notes.

3.8 1 000024 Emergency Boration / 1 02Relationship 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 08Criteria 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 000067 Plant Fire On-site / 9 8 16Vital equipment and control systems to be maintained and 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 06Actions 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 9 ES-401, 23 of 33 Group Point Total:

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

System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)

IR#003 Reactor Coolant Pump 0 2 S/G 3.5 1 004 Chemical and Volume Control 01.27 Knowledge of system purpose and/or function.

3.9 1 005 Residual Heat Removal 0 1 0 7 RHR pumps; System protection logics, including high-pressure interlock, reset controls, and valve interlocks 3; 3.2 2 006 Emergency Core Cooling 0 4 ESFAS-operated valves 3.6 1 007 Pressurizer Relief/Quench Tank 0 2 Method of forming a steam bubble in the PZR 3.1 1 008 Component Cooling Water 0 2 01.28 CCW temperature; Knowledge of the purpose and function of major system components and controls.

2.9;4.1 2 010 Pressurizer Pressure Control 0 2 0 1 Constant enthalpy expansion through a valve; Pressure detection systems 2.6;2.7 2 012 Reactor Protection 0 1 RPS channels, components, and interconnections 3.3 1 013 Engineered Safety Features Actuation 0 1 Sensors and detectors 2.7 1 022 Containment Cooling 0 1 Initiation of safeguards mode of operation 4.1 1 025 Ice Condenser 0 026 Containment Spray 02.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system 4.2 1 039 Main and Reheat Steam 0 4 Utilization of steam pressure program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits 2.9 1 059 Main Feedwater 1 1 Failure of feedwater control system 3.0 1 061 Auxiliary/Emergency Feedwater 0 2 Pumps 2.6 1 062 AC Electrical Distribution 0 7 Synchronizing and paralleling of different ac supplies 3.1 1 063 DC Electrical Distribution 0 1 0 1 Battery capacity as it is affected by discharge rate; Meters, annunciators, dials, recorders, and indicating lights 2.5;2.7 2 064 Emergency Diesel Generator 0 1 ED/G lube oil temperature and pressure 3.0 1 073 Process Radiation Monitoring 0 1 0 1 Radiation theory, including sources, types, units, and effects; Erratic or failed power supply 2.5;2.5 2 076 Service Water 0 5 0 2 RHR components, controls, sensors, indicators, and alarms, including rad monitors; Automatic start features associated with SWS pump controls 3; 2.9 2 078 Instrument Air 0 5 0 1 MSIV air; Air pressure 3.4;3.1 2 103 Containment 0 1 CCS 3.6 1 K/A Category Totals:23233332313 28 ES-401, 24 of 33 Group Point Total:

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

System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)

IR#001 Control Rod Drive 0 002 Reactor Coolant 1 1 Relationship between effects of the primary coolant system and the secondary coolant system 4.0 1 011 Pressurizer Level Control 0 014 Rod Position Indication 0 015 Nuclear Instrumentation 0 1 NIS channels, components, and interconnections 3.3 1 016 Non-nuclear Instrumentation 0 017 In-core Temperature Monitor 0 1 Sensors and detectors 2.7 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 033 Spent Fuel Pool Cooling 0 3 Spent fuel temperature 3.0 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 8 Recognition that increasing radiation levels in secondary systems may mean leaking and possibly ruptured S/G tubes 4.1 1 041 Steam Dump/Turbine Bypass Control 0 2 Steam pressure 3.1 1 045 Main Turbine Generator 0 055 Condenser Air Removal 0 6 PRM system 2.6 1 056 Condensate 0 068 Liquid Radwaste 0071 Waste Gas Disposal 01.28 Knowledge of the purpose and function of major system components and controls.

4.1 1 072 Area Radiation Monitoring 0 2 Detector failure 2.8 1 075 Circulating Water 0 1 Heat sink 2.5 1 079 Station Air 0 086 Fire Protection 0 K/A Category Totals:11111111011 10 ES-401, 25 of 33 Group Point Total:

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

E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)

IR#000007 Reactor Trip / 1 0 2Proper actions to be taken if the automatic safety functions have not taken place 4.6 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 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 000022 Loss of Rx Coolant Makeup / 2 02.36Ability to analyze the effect of maintenance activities, such asdegraded power sources, on the status of limiting conditions for operations.

4.2 1 000025 Loss of RHR System / 4 0 000026 Loss of Component Cooling Water / 8 0 000027 Pressurizer Pressure Control System Malfunction / 3 0 4Tech-Spec limits for RCS pressure 4.3 1 000029 ATWS / 1 0 000038 Steam Gen. Tube Rupture / 3 0 000040 Steam Line Rupture / 4 CE/E05 Excessive Steam Demand / 4 000054 Loss of Main Feedwater / 4 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 000058 Loss of DC Power / 6 04.47Ability to diagnose and recognize trends in an accurate and timelymanner utilizing the appropriate control room reference material.

4.2 1 000062 Loss of Nuclear Svc Water / 4 0 5The normal values for SWS-header flow rate and the flow rates to the components cooled by the SWS 2.5 1 000065 Loss of Instrument Air / 8 02.42Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

4.6 1 000077 Generator Voltage and Electric Grid Disturbances / 6 0 K/A Category Totals:

0000 3 3 6 ES-401, 22 of 33 Group Point Total:

0 1 0 ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s)

IR#000001 Continuous Rod Withdrawal / 1 0 000003 Dropped Control Rod / 1 03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements 3.8 1 000005 Inoperable/Stuck Control Rod / 1 0 000024 Emergency Boration / 1 0 000028 Pressurizer Level Malfunction / 2 02.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

4.2 1 000032 Loss of Source Range NI / 7 04.11 Knowledge of abnormal condition procedures.

4.2 1 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 0000060 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 0CE/A16 Excess RCS Leakage / 2 0 CE/E09 Functional Recovery 0 K/A Category Totals:

0 0 0 0 2 2 4 ES-401, 23 of 33 Group Point Total:

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

System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)

IR#003 Reactor Coolant Pump 0 004 Chemical and Volume Control 0 005 Residual Heat Removal 0 006 Emergency Core Cooling 0 007 Pressurizer Relief/Quench Tank 0 2 Abnormal pressure in the PRT 3.2 1 008 Component Cooling Water 0 010 Pressurizer Pressure Control 0 012 Reactor Protection 0 013 Engineered Safety Features Actuation 0 022 Containment Cooling 0 025 Ice Condenser 0 026 Containment Spray 02.12 Knowledge of surveillance procedures.

4.1 1 039 Main and Reheat Steam 0 059 Main Feedwater 01.30 Ability to locate and operate components, including local controls.4.0 1 061 Auxiliary/Emergency Feedwater 0 062 AC Electrical Distribution 0 063 DC Electrical Distribution 0 2 Loss of ventilation during battery charging 3.1 1 064 Emergency Diesel Generator 04.06 Knowledge of EOP mitigation strategies.

4.7 1 073 Process Radiation Monitoring 0 076 Service Water 0 078 Instrument Air 0 103 Containment 0 K/A Category Totals:00000002003 5 ES-401, 24 of 33 Group Point Total:

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

System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s)

IR#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 0 017 In-core Temperature Monitor 0 2 Core damage 4.1 1 027 Containment Iodine Removal 0 028 Hydrogen Recombiner and Purge Control 0 029 Containment Purge 0 033 Spent Fuel Pool Cooling 02.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

4.6 1 034 Fuel Handling Equipment 0 035 Steam Generator 0 041 Steam Dump/Turbine Bypass Control 0 045 Main Turbine Generator 0 055 Condenser Air Removal 01.13 Knowledge of facility requirements for controlling vital/controlled access.

3.2 1 056 Condensate 0 068 Liquid Radwaste 0071 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:00000001002 3 ES-401, 25 of 33 Group Point Total:

ES-401Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3Facility Name:ANO Unit 2 Date of Exam:6/24/2012 IR#IR#2.1.20 Ability to interpret and execute procedure steps.

4.6 12.1.03 Knowledge of shift or short-term relief turnover practices.

3.7 12.1.03 Knowledge of shift or short-term relief turnover practices.

3.9 12.1.13 Knowledge of facility requirements for controlling vital/controlled access.

3.2 1 2.1.2.1.Subtotal 2 22.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.

3.9 12.2.40 Ability to apply Technical Specifications for a system.

3.4 12.2.11 Knowledge of the process for controlling temporary design changes.

3.3 12.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

3.9 1 2.2.2.2.Subtotal 2 22.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such ascontainment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2 12.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 12.3.07 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

3.5 12.3.06 Ability to approve release permits.

3.8 1 2.3.2.3.Subtotal 3 12.4.01 Knowledge of EOP entry conditions and immediate action steps.

4.6 12.4.42 Knowledge of emergency response facilities.

2.6 12.4.47Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 12.4.14 Knowledge of general guidelines for EOP usage.

4.5 12.4.08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

4.5 1 2.4.Subtotal 3 2 10 7 ES-401, Page 26 of 33 1.Conduct of Operations RO SRO-Only K/A #Tier 3 Point Total 3.Radiation Control 4.Emergency Procedures

/ Plan 2.Equipment Control Category Topic ES-401Record of Rejected K/AsForm ES-401-4ES-401, Page 27 of 33Tier /GroupRandomlySelected K/AReason for Rejection1/2 (RO)003/AA2.05 A TC map for Unit 2 (simulator) does not show an appreciable differencebetween the location for a dropped CEA as compared to other corelocations. 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 applyto the Pressurizer Level Control Malfunctions: PZR level reactor protectionbistables" Unit 2 does not have reactor protection bistables for PZR level.Selected KA 028 AA1.022/1 (RO)073/A2.02This KA is too close to the other KA selected for this system. Selected KA073 K 5.01 as a replacement.2/1 (RO)076/K4.03Unit 2 does not have an auto opening feature for SWS valves to CCW heatexchangers. Selected 076 K4.02 as the replacement KA.2/2 (RO)071/2.4.3This KA was also chosen in T1G1 for system 056 and is thereforeredundant. Selected 071 2.1.28 as the replacement KA.3 (RO)G/2.2.5This KA has too low of a KA value for the RO position to be used for thissystem (KA 2.2.5), replaced with KA 2.2.40 (RO rating 3.4).

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

1/2 (SRO)032/2.1.19This generic KA states: "Ability to use plant computer to evaluate system orcomponent status." This KA is best evaluated on the operating exam vs.the written exam. Selected 2.4.11 as the replacement KA.

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

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

Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012Exam Level: RO X SRO-I SRO-UOperating Test No.: 2012-1Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalS4.ANO-2-JPM-NRC-CCW01008 A4.01 RO-3.3/SRO-3.1Secure CCW system using EOPD/L/S 8Plant servicesystems S5.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/D/P/S 5ContainmentIntegrity S6.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/P/S 1Reactivity control S7.ANO-2-JPM-NRC-CPC06012 A4.02 RO-3.3/SRO-3.4Place #1 CEAC to inop on "B" CPCD/S 7Instrumentation S8.ANO-2-JPM-NRC-AOP3010 A2.02 RO-3.9/SRO-3.9Isolate failed PZR spray valveA/D/P/S 3Pressure ControlIn-Plant Systems

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

P1.ANO-2-JPM-NRC-EDDCB064 A4.01 RO-4.0/SRO-4.3Start EDG 2K-4B without DCA/D/E/L 6ElectricalP2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 0ES-301Administrative Topics OutlineForm ES-301-1Facility: Arkansas Nuclear One Unit 2Date of Examination: 08/27/2012Examination Level: RO SRO XOperating Test Number: 2012-1Administrative Topic (see Note)Type Code*Describe activity to be performedA5. Conduct of Operations2.1.32 SRO (4.0)D/RReview performing transferring Unit AuxiliaryCalculation and determine if it they can be transferred.ANO-2-JPM-NRC-ADMIN-SU2LOADSROA6. Conduct of Operations2.1.23 SRO (4.4)D/RReview Time to Boil Calculation.ANO-2-JPM-NRC-AMDIN-TTBCSROA7. Equipment Control2.2.14 SRO (4.3)D/RSupervisory review of maintenance activities forconfiguration controlANO-2-JPM-NRC-ADMIN-MAINTA8. Radiation Control2.3.4 SRO (3.7)N/RCalculate expected dose for Re-entry during anemergency and determine if entry is allowed.ANO-2-JPM-NRC-ADMIN-EMGRESPSROA9. EmergencyProcedures/Plan2.4.41 SRO (4.6)D/P/RDetermine Emergency Action Level for given conditions.ANO-2-JPM-NRC-ADMIN-EAL11NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking only the administrative topics, when all 5 are required.* Type Codes & Criteria:(C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)

Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012Exam Level: RO SRO-I SRO-U XOperating Test No.: 2012-1Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalIn-Plant Systems

@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)P2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 0ES-301Control Room/In-Plant Systems OutlineForm ES-301-2Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012Exam Level: RO SRO-I X SRO-UOperating Test No.: 2012-1Control Room Systems

@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)System / JPM TitleType Code*SafetyFunction S1.ANO-2-JPM-NRC-SIT09006 A4.02 RO-4.0/SRO-3.8Isolate SITs following SIAS with SIAS resetA/D/EN/L/S 2Inventory Control S2.ANO-2-JPM-NRC-ELEC05062 A4.01 RO3.3/SRO3.1Transfer Auxiliaries from SU#2 to SU#3 for 2A-1N/S 6Electrical S3.ANO-2-JPM-NRC-SDBC2041 A4.05 RO-3.1/SRO-3.3Manually Operate SDBCS valvesA/L/N/S 4Heat RemovalS4.ANO-2-JPM-NRC-CCW01008 A4.01 RO-3.3/SRO-3.1Secure CCW system using EOPD/L/S 8Plant servicesystems S5.ANO-2-JPM-NRC-CNMT2103 A3.01 RO-3.9/SRO-4.2Drain the containment sumpA/D/P/S 5ContainmentIntegrity S6.ANO-2-JPM-NRC-CEA01001 A4.03 RO-4.0/SRO-3.7Perform a CEA exerciseD/P/S 1Reactivity control S7.ANO-2-JPM-NRC-CPC06012 A4.02 RO-3.3/SRO-3.4Place #1 CEAC to inop on "B" CPCD/S 7InstrumentationIn-Plant Systems

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

P1.ANO-2-JPM-NRC-EDDCB064 A4.01 RO-4.0/SRO-4.3Start EDG 2K-4B without DCA/D/E/L 6ElectricalP2.ANO-2-JPM-NRC-MGSU001 A4.08 RO-3.7/SRO-3.4Start the First MG setD/L 1Reactivity controlP3.ANO-2-JPM-NRC-FPEM1033 A2.03 RO-3.1/SRO-3.5Perform emergency SW make up to SFPD/E/R 8Plant servicesystems@All RO and SRO-I control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.* Type CodesCriteria for RO / SRO-I / SRO-U(A)lternate path(C)ontrol room(D)irect from bank(E)mergency or abnormal in-plant(EN)gineered safety feature(L)ow-Power / Shutdown(N)ew or (M)odified from bank including 1(A)(P)revious 2 exams(R)CA(S)imulator4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 - / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Revision 0Page 2 of 2ES-301Transient and Event ChecklistForm ES-301-5Facility: Arkansas Nuclear OneDate of Exam: 8-27-12Operating Test No.: 2012-1Scenarios 1 2 3(currently selectedas spare)4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION M I N I M U M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 3 1 11 1 0NOR 1 11 1 1 I/C 2,3,4, 5,8 6,9 3,6 74 4 2 MAJ 6,7 5,7 5 42 2 1 ROSRO-I XSRO-U TS 2,5 20 2 2 RX 3 11 1 0NOR 1 1 11 1 1 I/C 4,5 2,3,4, 6,8,9 2,3,4, 6,7 84 4 2 MAJ 6,7 5,7 5 42 2 1 ROSRO-I XSRO-U TS 2,4 2,4 20 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2 RX1 1 0NOR1 1 1 I/C4 4 2 MAJ2 2 1 ROSRO-ISRO-U TS0 2 2Instructions:

1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions,including at least two instrument or component (I/C) malfunctions and one major transient, in the ATCposition. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.

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

Revision 0Page 1 of 2ES-301Transient and Event ChecklistForm ES-301-5Facility: Arkansas Nuclear OneDate of Exam: 8-27-12Operating Test No.: 2012-1Scenarios 1 2 3(currently selectedas spare)4 CREWPOSITION CREWPOSITION CREWPOSITION CREWPOSITION M I N I M U M(*)A P P L I C A N T E V E N T T Y P E S R O A T C B O P S R O A T C B O P S R O A T C B O P S R O A T C B O P T O T A L R I U RX 3 11 1 0NOR 1 1 11 1 1 I/C 4,5 2,3,8 2,4,7 54 4 2 MAJ 6,7 5,7 5 42 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 4 1 11 1 0NOR 1 11 1 1 I/C 2,3,8 6,9 3,6 54 4 2 MAJ 6,7 5,7 5 42 2 1 RO XSRO-ISRO-U TS 00 2 2 RX 01 1 0NOR 1 11 1 1 I/C 2,3,4, 5,8 54 4 2 MAJ 6,7 22 2 1 ROSRO-ISRO-U X TS 2,5 20 2 2 RX 01 1 0NOR 1 1 11 1 1 I/C 2,3,4, 6,8,9 2,3,4, 6,7 64 4 2 MAJ 5,7 5 22 2 1 ROSRO-ISRO-U X TS 2,4 2,4 20 2 2Instructions:

1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for eachevent type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions,including at least two instrument or component (I/C) malfunctions and one major transient, in the ATCposition. If an Instant SROadditionally serves in the BOP position, one I/C malfunction can be creditedtoward the two I/C malfunctions required for the ATC position.

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