Text

2017-06 - Proposed Retake Written Exam Outlines
	ML18045A496
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/15/2017
From:	Vincent Gaddy; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML18045A496 (25)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One (Unit 1) Retake Exam Date of Exam: June 2017 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 2 3 3 3 4 3 18 Emergency &

Abnormal 2 2 1 2 N/A 1 2 N/A 1 9 Plant Evolutions Tier Totals 4 4 5 4 6 4 27 1 3 3 2 3 2 2 3 3 2 3 2 28 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 Categories 3 3 2 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

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

7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As Rev 3 Page 1 of 14

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 / SRO)

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

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space X AA1. Ability to operate and / or monitor the following 3.6 1 Accident / 3 as they apply to the Pressurizer Vapor Space 1121 Accident:

MOD AA1.06 Control of PZR level (CFR 41.7 / 45.5 / 45.6) 000009 Small Break LOCA / 3 X EK2. Knowledge of the interrelations between the 3.0 2 small break LOCA and the following:

368 EK2.03 S/Gs Bank (CFR 41.7 / 45.7) 2005 000011 Large Break LOCA / 3 X EA2. Ability to determine or interpret the following 3.9 3 as they apply to a Large Break LOCA:

491 EA2.11 Conditions for throttling or stopping HPI Bank (CFR 43.5 / 45.13) 2013 000015/17 RCP Malfunctions / 4 X AK1. Knowledge of the operational implications of 3.7 4 the following concepts as they apply to Reactor 396 Coolant Pump Malfunctions (Loss of RC Flow):

Bank AK1.02 Consequences of an RCPS failure 2013 (CFR 41.8 / 41.10 / 45.3) 000022 Loss of Rx Coolant Makeup / 2 X AK3. Knowledge of the reasons for the following 3.5 5 responses as they apply to the Loss of Reactor 610 Coolant Makeup:

Bank AK3.02 Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and 2005 abnormal charging (CFR 41.5, 41.10 / 45.6 / 45.13) 000025 Loss of RHR System / 4 X 2.2.42 Ability to recognize system parameters that 3.9 6 are entry-level conditions for Technical 1122 Specifications.

New (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 000026 Loss of Component Cooling X AA1. Ability to operate and / or monitor the following 2.9 7 Water / 8 as they apply to the Loss of Component Cooling 1123 Water:

New AA1.06 Control of flow rates to components cooled by the CCWS (CFR 41.7 / 45.5 / 45.6) 000027 Pressurizer Pressure Control X AK2. Knowledge of the interrelations between the 2.6 8 System Malfunction / 3 Pressurizer Pressure Control Malfunctions and the 933 following:

New AK2.03 Controllers and positioners (CFR 41.7 / 45.7)

Rev 3 Page 2 of 14

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

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

1 2 3 1 2 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12) X AA2. Ability to determine and interpret the following 4.5 9 Steam Line Rupture - Excessive Heat as they apply to the Steam Line Rupture:

1124 Transfer / 4 AA2.04 Conditions requiring ESFAS initiation New (CFR: 43.5 / 45.13) 000054 (CE/E06) Loss of Main X AA2. Ability to determine and interpret the following 4.3 10 Feedwater / 4 as they apply to the Loss of Main Feedwater 623 (MFW):

Bank AA2.01 Occurrence of reactor and/or turbine trip.

2005 (CFR 41.7 / 43.5 / 45.13) 000055 Station Blackout / 6 X EK1. Knowledge of the operational implications of 4.1 11 the following concepts as they apply to the Station 1125 Blackout :

MOD EK1.02 Natural circulation cooling (CFR 41.8 / 41.10 / 45.3) 000056 Loss of Off-site Power / 6 X 2.4.4 Ability to recognize abnormal indications for 4.5 12 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6) 000057 Loss of Vital AC Inst. Bus / 6 X AA1. Ability to operate and / or monitor the following 3.5 13 as they apply to the Loss of Vital AC Instrument Bus:

AA1.06 Manual control of components for which automatic control is lost (CFR 41.7 / 45.5 / 45.6) 000058 Loss of DC Power / 6 X AA2. Ability to determine and interpret the following 3.5 14 as they apply to the Loss of DC Power:

41 AA2.03 DC loads lost; impact on ability to operate Bank and monitor plant systems 2001 (CFR 43.5 / 45.13) 000062 Loss of Nuclear Svc Water / 4 X AK3. Knowledge of the reasons for the following 3.6 15 responses as they apply to the Loss of Nuclear 947 Service Water:

Bank AK3.02 The automatic actions (alignments) within the nuclear service water resulting from the 2013 actuation of the ESFAS (CFR 41.4, 41.8 / 45.7 )

000065 Loss of Instrument Air / 8 X AK3. Knowledge of the reasons for the following 2.9 16 responses as they apply to the Loss of Instrument 108 Air:

MOD AK3.03 Knowing effects on plant operation of isolating certain equipment from instrument air (CFR 41.5, 41.10 / 45.6 / 45.13)

Rev 3 Page 3 of 14

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

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

1 2 3 1 2 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat X EK2. Knowledge of the interrelations between the 3.8 17 Transfer - Loss of Secondary Heat Sink / 4 (Inadequate Heat Transfer) and the following:

EK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7) 000077 Generator Voltage and Electric X 2.1.25 Ability to interpret reference materials, such 3.9 18 Grid Disturbances / 6 as graphs, curves, tables, etc.

1126 (CFR: 41.10 / 43.5 / 45.12) New K/A Category Totals: 2 3 3 3 4 3 Group Point Total: 18 Rev 3 Page 4 of 14

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 / 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 AA2. Ability to determine and interpret the 4.5 19 following as they apply to the Continuous 397 Rod Withdrawal :

Bank AA2.03 Proper actions to be taken if 2001 automatic safety functions have not taken place (CFR: 43.5 / 45.13) 000003 Dropped Control Rod / 1 X AK3. Knowledge of the reasons for the 3.8 20 following responses as they apply to the 1127 Dropped Control Rod:

New AK3.04 Actions contained in EOP for a dropped control rod.

(CFR: 41.5, 41.10 / 45.6 / 45.13) 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 X AK1. Knowledge of the operational 2.7 21 implications of the following concepts as they 1128 apply to Loss of Intermediate Range Nuclear New Instrumentation:

AK1.01 Effects of voltage changes on performance (CFR: 41.8 / 41.10 / 45.3) 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 Rev 3 Page 5 of 14

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

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

1 2 3 1 2

BW/A01 Plant Runback / 1 X AK2. Knowledge of the interrelations 3.7 22 between the (Plant Runback) and the following:

AK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7)

BW/A02&A03 Loss of NNI-X/Y / 7 X AA1. Ability to operate and / or monitor the 4.0 23 following as they apply to the (Loss of NNI-X)

AA1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5 / 45.6)

BW/A04 Turbine Trip / 4 X 2.1.27 Knowledge of system purpose and/or 3.9 24 function.

(CFR: 41.7)

BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 X AA2. Ability to determine and interpret the 3.3 25 following as they apply to the (Flooding)

AA2.2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

(CFR: 43.5 / 45.13)

BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X EK3. Knowledge of the reasons for the 3.0 26 following responses as they apply to the (LOCA Cooldown):

EK3.2 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown).

(CFR: 41.5 / 41.10, 45.6, 45.13)

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures X EK1. Knowledge of the operational 3.0 27 implications of the following concepts as they apply to the (EOP Rules)

EK1.3 Annunciators and conditions, indicating signals, and remedial actions associated with the (EOP Rules).

(CFR: 41.8 / 41.10 / 45.3)

CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 2 1 2 1 2 1 Group Point Total: 9 Rev 3 Page 6 of 14

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 Knowledge of the operational 3.2 28 implications of the following concepts as they apply to the RCPS:

K5.04 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow (CFR: 41.5 / 45.7) 003 Reactor Coolant Pump X Knowledge of RCPS design feature(s) 2.5 29 and/or interlock(s) which provide for the following: :

K4.02 Prevention of cold water accidents or transients (CFR: 41.7) 004 Chemical and Volume Control X Knowledge of the effect of a loss or 4.4 30 malfunction on the following CVCS components:

K6.17 Flow paths for emergency boration (CFR: 41.7 / 45.7) 005 Residual Heat Removal X Knowledge of the effect that a loss or 3.2 31 malfunction of the RHRS will have on the following:

K3.07 Refueling operations (CFR: 41.7 / 45.6) 006 Emergency Core Cooling X Ability to predict and/or monitor changes 3.5 32 in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including:

A1.13 Accumulator pressure (level, boron concentration)

(CFR: 41.5 / 45.5) 007 Pressurizer Relief/Quench X Ability to monitor automatic operation of 2.7 33 Tank the PRTS, including:

A3.01 Components which discharge to the PRT (CFR: 41.7 / 45.5) 008 Component Cooling Water X Ability to (a) predict the impacts of the 3.2 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:

A2.02 High/low surge tank level (CFR: 41.5 / 43.5 / 45.3 / 45.13)

Rev 3 Page 7 of 14

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 4 008 Component Cooling Water X Knowledge of bus power supplies to the 3.0 35 following:

K2.02 CCW pump, including emergency backup (CFR: 41.7) 010 Pressurizer Pressure Control X A3. Ability to monitor automatic 3.6 36 operation of the PZR PCS, including:

A3.02 PZR pressure (CFR: 41.5 / 43.5 / 45.3 / 45.13) 012 Reactor Protection X K6. Knowledge of the effect of a loss or 3.1 37 malfunction of the following will have on the RPS:

K6.03 Trip logic circuits (CFR: 41.7 / 45.7) 013 Engineered Safety Features X 013 Engineered Safety Features 3.9 38 Actuation Actuation System (ESFAS) 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

013 Engineered Safety Features X Ability to manually operate and/or 4.5 39 Actuation monitor in the control room:

A4.01 ESFAS-initiated equipment which fails to actuate (CFR: 41.7 / 45.5 to 45.8) 022 Containment Cooling X Knowledge of the physical connections 3.5 40 and/or cause-effect relationships between the CCS and the following systems:

K1.01 SWS/cooling system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 025 Ice Condenser 026 Containment Spray X Knowledge of bus power supplies to the 2.7 41 following:

K2.02 MOVs (CFR: 41.7) 039 Main and Reheat Steam X Knowledge of the operational 3.6 42 implications of the following concepts as they apply to the MRSS:

K5.08 Effect of steam removal on reactivity (CFR: 41.5 / 45.7)

Rev 3 Page 8 of 14

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 4 039 Main and Reheat Steam X Knowledge of MRSS design feature(s) 3.7 43 and/or interlock(s) which provide for the following:

(CFR: 41.7)

K4.05 Automatic isolation of steam line 059 Main Feedwater X Ability to (a) predict the impacts of the 2.7 44 following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Overfeeding event (CFR: 41.5 / 43.5 / 45.3 / 45.13) 061 Auxiliary/Emergency Feedwater X Ability to predict and/or monitor changes 3.6 45 in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

A1.05 AFW flow/motor amps (CFR: 41.5 / 45.5) 062 AC Electrical Distribution X Knowledge of the effect that a loss or 3.7 46 malfunction of the ac distribution system will have on the following:

K3.03 DC system (CFR: 41.7 / 45.6) 063 DC Electrical Distribution X Knowledge of DC electrical system 2.7 47 design feature(s) and/or interlock(s) which provide for the following:

K4.01 Manual/automatic transfers of control (CFR: 41.7) 063 DC Electrical Distribution X 063 DC Electrical Distribution 3.9 48 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12) 064 Emergency Diesel Generator X Ability to manually operate and/or 3.3 49 monitor in the control room:

A4.10 Need for, and consequences of, manually shedding (loads) safeguards bus (CFR: 41.7 / 45.5 to 45.8) 073 Process Radiation Monitoring X Knowledge of the physical connections 3.6 50 and/or cause effect relationships between the PRM system and the following systems:

K1.01 Those systems served by PRMs (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Rev 3 Page 9 of 14

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 4 073 Process Radiation Monitoring X Ability to predict and/or monitor changes 3.2 51 in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including:

A1.01 Radiation levels (CFR: 41.5 / 45.7) 076 Service Water X Ability to manually operate and/or 2.6 52 monitor in the control room:

A4.02 SWS valves (CFR: 41.7 / 45.5 to 45.8) 076 Service Water X Knowledge of bus power supplies to the 3.1 53 following:

K2.08 ESF-actuated MOVs (CFR: 41.7) 078 Instrument Air X K1 Knowledge of the physical 3.4 54 connections and/or cause-effect relationships between the IAS and the following systems:

K1.05 MSIV air (CFR: 41.2 to 41.9 / 45.7 to 45.8) 103 Containment X A2. Ability to (a) predict the impacts of 3.5 55 the 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 03 Phase A and B isolation (CFR: 41.5 / 43.5 / 45.3 / 45.13)

K/A Category Point Totals: 3 3 2 3 2 2 3 3 2 3 2 Group Point Total: 28 Rev 3 Page 10 of 14

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 X Knowledge of the physical connections 2.8 56 and/or cause effect relationships between the CRDS and the following systems:

K1.09 CCWS must be cut in before energizing CRDS (CFR: 41.2 to 41.9 / 45.7 to 45.8) 002 Reactor Coolant X Knowledge of the effect that a loss or 4.2 57 malfunction of the RCS will have on the following:

K3.02 Fuel (CFR: 41.7) 011 Pressurizer Level Control 014 Rod Position Indication X Knowledge of the operational implications 2.8 58 of the following concepts as they apply to the RPIS:

K5.02 RPIS independent of demand position (CFR: 41.5 / 45.7) 015 Nuclear Instrumentation X A1. Ability to predict and/or monitor 3.5 59 changes in parameters to prevent exceeding design limits associated with operating the NIS controls including:

A1.02 SUR (CFR: 41.5 . 45.5) 016 Non-Nuclear Instrumentation X Ability to monitor automatic operation of 2.9 60 the NNIS, including:

A3.01 Automatic selection of NNIS inputs to control systems (CFR: 41.7 / 45.5) 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X 2.4.46 Ability to verify that the alarms are 4.2 61 consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass X Ability to manually operate and/or monitor 3.0 62 Control in the control room:

A4.08 Steam dump valves (CFR: 41.7 / 45.5 to 45.8)

Rev 3 Page 11 of 14

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 4 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste X Ability to (a) predict the impacts of the 3.3 63 following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Failure of automatic isolation (CFR: 41.5 / 43.5 / 45.3 / 45.13) 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air X Knowledge of SAS design feature(s) 2.9 64 and/or interlock(s) which provide for the following:

K4.01 Cross-connect with IAS (CFR: 41.7) 086 Fire Protection X Knowledge of the effect of a loss or 2.6 65 malfunction on the Fire Protection System following will have on the :

K6.04 Fire, smoke, and heat detectors (CFR: 41.7 / 45.7)

K/A Category Point Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 Rev 3 Page 12 of 14

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One (Unit 1) Retake Exam Date of Exam: June 2017 Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of shift or short-term relief turnover practices. 66 2.1.3 3.7 (CFR: 41.10 / 45.13)

Knowledge of how to conduct system lineups, such as valves, 67

1. 2.1.29 breakers, switches, etc. 4.1 Conduct of (CFR: 41.10 / 45.1 / 45.12)

Operations Knowledge of procedures, guidelines, or limitations associated 68 2.1.37 with reactivity management. 4.3 (CFR: 41.1 / 43.6 / 45.6)

Subtotal 3 Knowledge of the process for making changes to procedures. 69 2.2.6 3.0 CFR: 41.10 / 43.3 / 45.13)

Knowledge of limiting conditions for operations and safety 70 limits. 4.0 115

2. 2.2.22 Bank Equipment (CFR: 41.5 / 43.2 / 45.2) 2004 Control Ability to determine Technical Specification Mode of Operation 71 2.2.35 (CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.6 458 Bank 2011 Subtotal 3 Knowledge of radiological safety principles pertaining to 72 licensed operator duties, such as containment entry 2.3.12 requirements, fuel handling responsibilities, access to locked 3.2 high-radiation areas, aligning filters, etc.

3. (CFR: 41.12 / 45.9 / 45.10)

Radiation Control Knowledge of radiation or contamination hazards that may 73 arise during normal, abnormal, or emergency conditions or 2.3.14 activities. 3.4 (CFR: 41.12 / 43.4 / 45.10)

Subtotal 2 2.4.29 Knowledge of the emergency plan. 74 (CFR: 43.5 / 45.11) 2.6 128 Bank 2005 4.

Emergency Knowledge of EOP implementation hierarchy and coordination 75 Procedures / with other support procedures or guidelines such as, operating Plan procedures, abnormal operating procedures, and severe 3.5 2.4.16 accident management guidelines.

(CFR: 41.10 / 43.5 / 45.13)

Subtotal 2 Tier 3 Point Total 10 Rev 3 Page 13 of 14

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A T1/G1 054 AK1.02 This K/A states Effects of feedwater introduction on dry S/G. ANO-1 does not have any guidance on feeding a dry S/G following a loss of MFW event. ANO-1s only guidance on feeding a dry S/G is if MFW is used to feed a S/G with an unisolable steam leak (not a MFW leak). The only remaining K/A (AK1.01) does not appear to lead to development of a discriminating question without the question being overly complicated.

Replaced with AA2.01 which has high importance values (4.3/4.4).

T1/G1 077 2.4.2 This K/A concerns the knowledge of setpoints associated with EOP entry conditions. This system is also on the SRO exam and development of a question about setpoints could compromise the SRO question. Replaced with K/A 2.1.25 concerning the use of graphs which has an importance rating of 3.9.

T1/G2 003 AK3.09 This K/A states Recording of group bank position for dropped rod (reference point used to withdraw dropped rod to equal height with other rods in the bank). Although a dropped rod will be leveled to be equal to the other rods in its group, ANO-1 does not record the group position therefore a question could not be developed for this K/A. Replaced with K/A AK 3.04 which has a higher importance rating of 3.8. The question developed for this K/A meets the intent of the original K/A.

T2/G1 063 2.1.25 This K/A states: Ability to interpret reference materials, such as graphs, curves, tables, etc. There are no such references used with the DC electrical distribution system at ANO-1. Replaced with K/A 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications with an importance rating of 3.9 (same as 2.1.25).

T2/G2 041 A4.06 This K/A concerns Atmospheric relief valve controllers which, at ANO-1, are controlled by EFIC, not the Steam Dump control system which is part of ICS. Replaced with A4.08 Steam dump valves which meets the intent of the original K/A.

T3 2.4.4 This K/A is the ability to recognize entry level conditions for emergency and abnormal operating procedures. A question could not be developed for this K/A that was not also a system type question. Replaced with K/A 2.4.29, knowledge of the emergency plan.

Rev 3 Page 14 of 14

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One (Unit 1) Retake Exam Date of Exam: June 2017 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 6 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 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 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).