Text

2016-09-FINAL Outlines
	ML16260A221
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/01/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16260A221 (35)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 1 Date of Exam: August 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 4 2 3 3 4 2 18 6 Emergency &

Abnormal 2 1 0 3 N/A 2 1 N/A 2 9 4 Plant Evolutions Tier Totals 5 2 6 5 5 4 27 10 1 3 2 2 3 4 2 3 1 4 2 2 28 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO 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 Page 1 of 16

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)

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) X 2.1.28 Knowledge of the purpose and 4.1 7 Reactor Trip - Stabilization - Recovery / function of major system components 1 608 and controls.

2005 (CFR 41.7)

AK3.03 Knowledge of the reasons for the 000008 Pressurizer Vapor Space X 4.1 1 following responses as they apply to the Accident / 3 Pressurizer Vapor Space Accident: 324 Actions contained in EOP for PZR vapor 2005 space accident/ LOCA.

(CFR 41.5, 41.10 / 45.6 / 45.13)

EK3.23 Knowledge of the reasons for the 000009 Small Break LOCA / 3 X 4.2 2 following responses as they apply to the small break LOCA: RCP tripping 1089 requirements.

1998 (CFR 41.5 / 41.10 / 45.6 / 45.13)

EA2.11 Ability to determine or interpret 000011 Large Break LOCA / 3 X 3.9 3 the following as they apply to a Large Break LOCA: Conditions for throttling or 684 stopping HPI.

2008 (CFR 43.5 / 45.13) 000015/17 RCP Malfunctions / 4 AK1.01 Knowledge of the operational 000022 Loss of Rx Coolant Makeup / 2 X 2.8 4 implications of the following concepts as they apply to Loss of Reactor Coolant 183 Makeup: Consequences of thermal shock to RCP seals. 2008 (CFR 41.8 / 41.10 / 45.3)

AA1.03 Ability to operate and / or monitor 000025 Loss of RHR System / 4 X 3.4 5 the following as they apply to the Loss of Residual Heat Removal System: LPI New pumps.

1091 (CFR 41.7 / 45.5 / 45.6)

AA2.01 Ability to determine and interpret 000026 Loss of Component Cooling X 2.9 6 the following as they apply to the Loss of Water / 8 Component Cooling Water: Location of a 8 leak in the CCWS.

2004 (CFR: 43.5 / 45.13) 000027 Pressurizer Pressure Control System Malfunction / 3 Replaced with system 001 due to conflict 000029 ATWS / 1 (7) with operating exam.

Page 2 of 16

EK1.02 Knowledge of the operational 000038 Steam Gen. Tube Rupture / 3 X 3.2 8 implications of the following concepts as they apply to the SGTR: Leak rate vs. 2007 pressure drop.

332 (CFR 41.10 )

EK2.1. Knowledge of the interrelations 000040 (BW/E05; CE/E05; W/E12) X 3.8 9 between the (Excessive Heat Steam Line Rupture - Excessive Heat Transfer / 4 Transfer) and the following: 686 Components, and functions of control and safety systems, including instrumentation, 2008 signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7) 2.4.4 Ability to recognize abnormal 000054 (CE/E06) Loss of Main X 4.5 10 indications for system operating Feedwater / 4 parameters that are entry-level 146 conditions for emergency and abnormal operating procedures. 2004 (CFR: 41.10 / 43.2 / 45.6)

EA2.03 Ability to determine or interpret 000055 Station Blackout / 6 X 3.9 11 the following as they apply to a Station Blackout: Actions necessary to restore New power.

1097 (CFR 43.5 / 45.13)

AK3.01 Knowledge of the reasons for the 000056 Loss of Off-site Power / 6 X 3.5 12 following responses as they apply to the Loss of Offsite Power: New Order and time to initiation of power for the 1057 load sequencer.

(CFR 41.5,41.10 / 45.6 / 45.13)

AA1.06 Ability to operate and / or monitor 000057 Loss of Vital AC Inst. Bus / 6 X 3.5 13 the following as they apply to the Loss of Vital AC Instrument Bus: Manual control New of components for which automatic control 1095 is lost.

(CFR 41.7 / 45.5 / 45.6)

AA2.03 Ability to determine and interpret 14 000058 Loss of DC Power / 6 X 3.5 the following as they apply to the Loss of DC Power: DC loads lost; impact on ability 513 to operate and monitor plant systems.

2008 (CFR: 43.5 / 45.13)

AA1.06 Ability to operate and / or monitor 000062 Loss of Nuclear Svc Water / 4 X 2.9 15 the following as they apply to the Loss of Nuclear Service Water (SWS): Control of New flow rates to components cooled by the 1058 SWS.

(CFR 41.7 / 45.5 / 45.6)

AA1.02 Ability to operate and / or monitor 000065 Loss of Instrument Air / 8 X 2.6 16 the following as they apply to the Loss of Instrument Air: Components served by MOD instrument air to minimize drain on system 691 (CFR 41.7 / 45.5 / 45.6)

W/E04 LOCA Outside Containment / 3 Page 3 of 16

W/E11 Loss of Emergency Coolant Recirc. / 4 EK1.3. Knowledge of the operational BW/E04; W/E05 Inadequate Heat X 4.0 17 implications of the following concepts as Transfer - Loss of Secondary Heat Sink /

4 they apply to the (Inadequate Heat 626 Transfer): Annunciators and conditions indicating signals, and remedial actions 2005 associated with the (Inadequate Heat Transfer).

(CFR: 41.8 / 41.10 / 45.3)

AK2.07 Knowledge of the interrelations 000077 Generator Voltage and Electric X 3.6 18 between Generator Voltage and Electric Grid Disturbances / 6 Grid Disturbances and the following: 891 Turbine / generator control 2014 (CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) Repeat K/A Category Totals: 4 2 3 3 4 2 Group Point Total: 18 Page 4 of 16

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)

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 000003 Dropped Control Rod / 1 X AK1.13 Knowledge of the operational 3.2 19 implications of the following concepts as they apply to Dropped 320 Control Rod: Interaction of ICS control 1999 stations as well as purpose, function, and modes of operation of ICS.

(CFR 41.8 / 41.10 / 45.3) 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 X AK3.02 Knowledge of the reasons for 3.7 20 the following responses as they apply to the Loss of Source Range 184 Nuclear Instrumentation: Guidance 2001 contained in EOP for loss of source-range nuclear instrumentation.

(CFR 41.5, 41.10 / 45.6 / 45.13) 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 X AA2.14 Ability to determine and 4.0 21 interpret the following as they apply to the Steam Generator Tube Leak: New Actions to be taken if S/G goes solid 1061 and water enters steam lines (CFR: 43.5 / 45.13) 000051 Loss of Condenser Vacuum / 4 X 2.4.2 Knowledge of system set 4.5 22 points, interlocks and automatic actions associated with EOP entry MOD conditions. 1062 (CFR: 41.7 / 45.7 / 45.8) 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 Page 5 of 16

000076 High Reactor Coolant Activity / 9 X AK3.05 Knowledge of the reasons for 2.9 23 the following responses as they apply to the High Reactor Coolant New Activity : Corrective actions as a result 1096 of high fission-product radioactivity level in the RCS (CFR 41.5,41.10 / 45.6 / 45.13)

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 BW/A01 Plant Runback / 1 X AA1.2 Ability to operate and / or 3.2 24 monitor the following as they apply to the (Plant Runback): Operating MOD behavior characteristics of the facility. 162 (CFR: 41.7 / 45.5 / 45.6)

BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 X AA1.1 Ability to operate and / or 4.3 25 monitor the following as they apply to the (Emergency Diesel Actuation) 276 Components, and functions of control 2005 and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5,45.6)

BW/A07 Flooding / 8 X AK3.2 Knowledge of the reasons for 3.2 26 the following responses as they apply to the (Flooding): Normal, New abnormal and emergency operating 1064 procedures associated with (Flooding).

(CFR: 41.5 / 41.10, 45.6, 45.13)

BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X 2.2.39 Knowledge of less than or 3.9 27 equal to one hour Technical Specification action statements for MOD systems. 1105 (CFR: 41.5 / 41.7 / 41.10)

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 1 0 3 2 1 2 Group Point Total: 9 Page 6 of 16

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 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 K6.02 Knowledge of the effect of 003 Reactor Coolant Pump X a loss or malfunction on the 2.7 28 following will have on the RCPS: 326 RCP seals and seal water supply.

2014 (CFR: 41.7 / 45/5)

Repeat 004 Chemical and Volume X K5.26 Knowledge of the 3.1 29 Control operational implications of the 258 following concepts as they apply to the CVCS: Relationship between 1999 VCT pressure and NPSH for charging pumps.

(CFR: 41.5/45.7)

A3.02 Ability to monitor 004 Chemical and Volume X automatic operation of the CVCS, 3.6 30 Control including: Letdown isolation. 654 (CFR: 41.7 / 45.5) 2007 K1.09 Knowledge of the physical 005 Residual Heat Removal X connections and/or cause-effect 3.6 31 relationships between the RHRS New and the following systems: RCS.

1068 (CFR: 41.2 to 41.9 / 45.7 to 45.8)

A1.05 Ability to predict and/or 005 Residual Heat Removal X monitor changes in parameters 3.3 32 (to prevent exceeding design 611 limits) associated with operating the RHRS controls including: 2013 Detection of and response to Repeat presence of water in RHR emergency sump.

(CFR: 41.5 / 45.5)

K2.04 Knowledge of bus power 006 Emergency Core Cooling X supplies to the following: ESFAS- 3.6 33 operated valves. MOD (CFR: 41.7) 1090 K5.02 Knowledge of the 007 Pressurizer Relief/Quench X operational implications of the 3.1 34 Tank following concepts as they apply 561 to the PRTS: Method of forming a steam bubble in the PZR. 2010 (CFR: 41.7)

Page 7 of 16

A3.04 Ability to monitor 008 Component Cooling Water X automatic operation of the 2.9 35 CCWS, including: Requirements 627 on and for the CCWS for different conditions of the power plant. 2005 (CFR: 41.7 / 45.5) 2.4.31 Knowledge of annunciator 008 Component Cooling Water X alarms, indications, or response 4.2 36 procedures. MOD (CFR: 41.10 / 45.3) 1070 K6.03 Knowledge of the effect of 010 Pressurizer Pressure Control X a loss or malfunction of the 3.2 37 following will have on the PZR New PCS: PZR sprays and heaters.

1071 (CFR: 41.7 / 45.7)

K2.01 Knowledge of bus power 012 Reactor Protection X supplies to the following: RPS 3.3 38 channels, components, and 85 interconnections.

2002 (CFR: 41.7)

A4.04 Ability to manually operate 012 Reactor Protection X and/or monitor in the control 3.3 39 room: Bistable, trips, reset and 1093 test switches.

bank (CFR: 41.7 / 45.5 to 45.8)

K3.03 Knowledge of the effect 013 Engineered Safety Features X that a loss or malfunction of the 4.3 40 Actuation ESFAS will have on the New following: Containment.

1073 (CFR: 41.7 / 45.6) 2.1.28 Knowledge of the purpose 013 Engineered Safety Features X and function of major system 4.1 41 Actuation components and controls. New (CFR: 41.7) 1103 K4.03 Knowledge of CCS design 022 Containment Cooling X feature(s) and/or interlock(s) 3.6 42 which provide for the following: 909 Automatic containment isolation.

2014 (CFR: 41.7)

Repeat 025 Ice Condenser A1.03 Ability to predict and/or 026 Containment Spray X 3.5 43 monitor changes in parameters (to prevent exceeding design New limits) associated with operating the CSS controls including: 1075 Containment sump level.

(CFR: 41.5 / 45.5)

Page 8 of 16

K5.05 Knowledge of the 039 Main and Reheat Steam X operational implications of the 2.7 44 following concepts as they apply MOD to the MRSS: Bases for RCS cooldown limits. 1074 (CFR: 41.5 / 45.7)

A4.10 Ability to manually operate 059 Main Feedwater X and monitor in the control room: 3.9 45 ICS. 565 (CFR: 41.7 / 45.5 to 45.8) 2005 K1.07 Knowledge of the physical 061 Auxiliary/Emergency X connections and/or cause-effect 3.6 46 Feedwater relationships between the AFW 269 and the following systems:

Emergency water source. 1999 (CFR: 41.2 to 41.9 / 45.7 to 45.8)

A1.01 Ability to predict and/or 061 Auxiliary/Emergency X monitor changes in parameters 3.9 47 Feedwater (to prevent exceeding design MOD limits) associated with operating the AFW controls 1076 including: S/G level.

(CFR: 41.5 / 45.5)

K4.03 Knowledge of AC 062 AC Electrical Distribution X distribution system design 2.8 48 feature(s) and/or interlock(s) New which provide for the following:

Interlocks between automatic bus 1077 transfer and breakers.

(CFR: 41.7)

A2.01 Ability to (a) predict the 062 AC Electrical Distribution X impacts of the following 3.4 49 malfunctions or operations on 140 the ac distribution system; and (b) based on those predictions, 2005 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Types of loads that, if de-energized, would degrade or hinder plant operation.

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A3.01 Ability to monitor 063 DC Electrical Distribution X automatic operation of the DC 2.7 50 electrical system, including: New Meters, annunciators, dials, recorders, and indicating lights. 1078 (CFR: 41.7 / 45.5)

K1.05 Knowledge of the physical 064 Emergency Diesel Generator X connections and/or cause-effect 3.4 51 relationships between the ED/G 792 system and the following systems: Starting air system. 2010 (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Page 9 of 16

K5.01 Knowledge of the 073 Process Radiation Monitoring X operational implications of the 2.5 52 following concepts as they apply New to the PRM system: Radiation theory, including sources, types, 1065 units, and effects.

(CFR: 41.5 / 45.7)

K4.02 Knowledge of SWS design 076 Service Water X 2.9 53 feature(s) and/or interlock(s) which provide for the following: Bank Automatic start features associated with SWS pump controls. 1079 (CFR: 41.7)

K3.03 Knowledge of the effect 078 Instrument Air X that a loss or malfunction of 3.0 54 the IAS will have on the 227 following: Cross-tied units.

2011 (CFR: 41.7 / 45.6)

A3.01 Ability to monitor 103 Containment X automatic operation of the 3.9 55 containment system, including: 104 Containment isolation.

2004 (CFR: 41.7 / 45.5)

K/A Category Point Totals: 3 2 2 3 4 2 3 1 4 2 2 Group Point Total: 28 Page 10 of 16

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 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 A2.17 Ability to (a) predict the 001 Control Rod Drive X impacts of the following 3.3 56 malfunction or operations on the 674 CRDS and (b) based on those predictions, use procedures to 2007 correct, control, or mitigate the consequences of those malfunctions or operations:

Rod-misalignment alarm.

(CFR: 41.5/43.5/45.3/45.13)

K5.10 Knowledge of the operational 002 Reactor Coolant X implications of the following 3.6 57 concepts as they apply to the RCS: 193 Relationship between reactor power and RCS differential temperature. 2005 (CFR: 41.5 / 45.7) 011 Pressurizer Level Control 014 Rod Position Indication K2.01 Knowledge of bus power 015 Nuclear Instrumentation X 3.3 58 supplies to the following: NIS channels, components, and New interconnections.

1066 (CFR: 41.7) 016 Non-Nuclear Instrumentation X K3.04 Knowledge of the effect that a 2.6 65 loss or malfunction of the NNIS will 309 have on the following: MFW system.

2007 (CFR: 41.7 / 45.6)

A2.02 Ability to (a) predict the 017 In-Core Temperature Monitor X impacts of the following 3.6 59 malfunctions or operations on the New ITM system; and (b) based on those predictions, use procedures to 1067 correct, control or mitigate the consequences of those malfunctions or operations:

Core damage.

(CFR: 41.5 / 43.5 / 45.3 / 45.5) 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge Page 11 of 16

K4.01 Knowledge of design 033 Spent Fuel Pool Cooling X feature(s) and/or interlock(s) which 2.9 60 provide for the following: 200 Maintenance of spent fuel level.

2011 (CFR: 41.7) 034 Fuel Handling Equipment A4.02 Ability to manually operate 035 Steam Generator X and/or monitor in the control room: 2.7 61 Fill of dry S/G. New 1094 (CFR: 41.7 / 45.5 to 45.8)

A1.02 Ability to predict and/or 041 Steam Dump/Turbine Bypass X monitor changes in parameters 3.1 62 Control (to prevent exceeding design limits) MOD associated with operating the SDS controls including: 1080 Steam pressure.

(CFR: 41.5 / 45.5) 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste K4.04 Knowledge of design 071 Waste Gas Disposal X feature(s) and/or interlock(s) which 2.9 63 provide for the following: Isolation of MOD waste gas release tanks. 470 (CFR: 41.7)

A1.01 Ability to predict and/or 072 Area Radiation Monitoring X monitor changes in parameters (to 3.4 64 prevent exceeding design limits) 379 associated with operating the ARM system controls including: 2008 Radiation levels.

(CFR: 41.5 / 45.5)

K3.07. REPLACED, See system 016 075 Circulating Water (65) 079 Station Air 086 Fire Protection K/A Category Point Totals: 0 1 1 2 1 0 2 2 0 1 0 Group Point Total: 10 Page 12 of 16

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One Unit 1 Date of Exam: August 2016 Category K/A # Topic RO SRO-Only IR # IR #

2.1. 2.1.2 Knowledge of operator responsibilities 4.1 66 during all modes of plant operation.

New (CFR: 41.10 / 45.13) 1083 2.1. 2.1.4 Knowledge of individual licensed operator 3.3 67 responsibilities related to shift staffing, such as medical requirements, no-solo operation, 838

1. maintenance of active license status, 10CFR55, 2011 Conduct of etc.

Operations (CFR: 41.10 / 43.2) 2.1. 2.1.37 Knowledge of procedures, guidelines, or 4.3 68 limitations associated with reactivity management. New 1084 (CFR: 41.1 / 43.6 / 45.6)

Subtotal 3 2.2. 2.2.13 Knowledge of tagging and clearance 4.1 69 procedures.

(CFR: 41.10 / 45.13) 231

2. 2007 Equipment 2.2. 2.2.6 Knowledge of the process for making 3.0 70 Control changes to procedures.

(CFR: 41.10 / 43.3 / 45.13) New 1082 Subtotal 2 2.3. 2.3.12 Knowledge of radiological safety 3.2 71 principles pertaining to licensed operator duties, such as containment entry requirements, New fuel handling responsibilities, access to locked 1081 high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 45.9 / 45.10) 3.

Radiation 2.3. 2.3.4 Knowledge of radiation exposure limits Control 3.2 72 under normal or emergency conditions.

751 (CFR: 41.12 / 43.4 / 45.10) 2008 Subtotal 2

4. 2.4. 2.4.3 Ability to identify post-accident 3.7 73 Emergency instrumentation.

Procedures / (CFR: 41.6 / 45.4) 242 Plan 2010 Page 13 of 16

2.4. 2.4.12 Knowledge of general operating crew 4.0 74 responsibilities during emergency operations.

(CFR: 41.10 / 45.12) 51 1998 2.4. 2.4.25 Knowledge of fire protection procedures.

3.3 75 (CFR: 41.10 / 43.5 / 45.13) 848 2011 Subtotal 3 Tier 3 Point Total 10 7 Page 14 of 16

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO 1/1 008 AK3.01 (Q1) This KA is for a Pressurizer Vapor Space Accident and states, Why PZR level may come back on scale if RCS is saturated. Could not develop a question for this K/A with one correct answer and three incorrect but plausible distractors. Replaced with K/A AK3.03.

RO 1/1 025 AA1.23 (Q5) This K/A is for monitoring/operating RHR heat exchangers as they apply to a loss of RHR. Another question relating the DH heat exchangers is being asked on another system so to remove this duplication the K/A was replaced with AA1.03.

RO 1/1 029 2.1.20 (Q7) This K/A is on the topic of ATWS which is being evaluated on several different levels in the operating exam. Replaced with system 007 Reactor Trip, K/A 2.1.28.

RO 1/1 038 EK1.03 (Q8) The question developed for the original K/A resulted in overlap with the SRO exam. NRC examiner comment: overlap between Q8 and Q85.

Replaced with K/A EK1.02.

RO 1/1 062 AA1.03 (Q15) ANO-1 does not use the Service Water System as a backup to CCWS. The Unit 1 equivalent of CCWS is Intermediate Cooling Water (ICW) and Service Water provides cooling to the ICW heat exchangers but it is not considered a backup system to ICW. Replaced with K/A AA1.06.

RO 1/2 003 AK1.21 (Q19) ANO-1equivalent of Delta Flux (DI) is Axial Power Imbalance. The Technical Specification (3.2.3) is used in conjunction with the Core Operating Limits Report (COLR). COLR Figures 6A-C, 7A-C, 8A-C give such broad limits for Axial Power Imbalance such that a single dropped control rod would have little operational implications other than performing the surveillance for TS 3.2.3. Replaced with K/A AK1.13.

RO 1/2 032 AK2.01 (Q20) ANO-1 AOP 1203.021, Loss of Neutron Flux Indication, Section 3 contains no actions for resetting the power supplies for Source Range indication. Since this was the only K2 K/A with a rating greater than or equal to 2.5, replaced this K/A with AK3.02.

RO 1/2 E08 EK1.1 (Q27) Found it difficult to develop a discriminating question for this K/A.

Replaced with K/A 2.2.39.

RO 2/1 004 K5.32 (Q29) This KA concerns purpose and control of heat tracing. This is NLO knowledge. Replaced with K/A K5.26.

RO 2/1 005 K1.01 (Q31) ANO-1 equivalent of CCWS is Intermediate Cooling Water (ICW) and the ICW system has no interconnection with the RHRS equivalent, the Decay Heat System. Replaced with K/A K1.09.

RO 2/1 007 K4.01 (Q34) This K/A concerns the design features which allow for Quench Tank cooling. This is the only K/A in this category with an importance rating greater than 2.5 and as a result this topic has been over-used in exams (2005, 2007, 2011, 2013). Changed to category K5 and replaced with K/A K5.02.

RO 2/1 008 2.2.12 (Q36) Knowledge of surveillance procedures would best be tested via a JPM instead of the written exam, and ANO-1 does not have any surveillances for the ICW system since it is not in Tech Specs. Replaced with K/A 2.4.31.

Page 15 of 16

Tier / Randomly Reason for Rejection Group Selected K/A RO 2/1 022 K4.04 (Q42) This K/A concerns Containment Cooling System design features and/or interlocks which provide for cooling of the control rod drive motors.

ANO-1 does not have direct cooling of the CRDMs via the CCS, therefore no question could be developed for this K/A. Replaced with K/A K4.03.

RO 2/1 026 A1.02 (Q43) This K/A concerns the ability to monitor containment temperature as relates to operating Containment Spray controls. ANO-1 Reactor Building Spray System is not operated based upon containment temperature but upon containment pressure. Replaced with K/A A1.03.

RO 2/1 039 K5.01 (Q44) This K/A concerns the definition and causes of steam/water hammer. A licensed level question could not be developed for this K/A. Replaced with K/A K5.05.

RO 2/1 061 A1.03 (Q47) This K/A concerns Emergency Feedwater System interactions with multi-units. ANO-1 does not have cross-connects with Unit 2 for the EFW system. Replaced with K/A A1.01.

RO 2/1 062 K4.06 (Q48) This K/A concerns 6.9KV one line diagrams. A licensed level question could not be developed for this K/A. Replaced with K/A K4.03.

RO 2/2 002 K5.02 (Q57) This K/A concerns the need for a vent path during draining. A licensed level question could not be developed for this K/A. Replaced with K/A K5.10.

RO 2/2 075 K3.07 (Q65) This K/A concerns the connection between Circulating Water and ESFAS.

ANO-1 has no connection between the two systems. A CW K/A with a rating greater than 2.5 and a lack of conflict with other questions could not be found. Replaced with system 016 and K/A K3.04.

RO 3 2.1.14 (Q66) This K/A concerns the knowledge of things which require plant wide announcements. A licensed level question could not be developed for this K/A. Replaced with K/A 2.1.2.

RO 3 2.1.26 (Q68) This K/A concerns the knowledge of industrial safety requirements. A licensed level question could not be developed for this K/A. Replaced with K/A 2.1.37.

RO 3 2.2.41 (Q70) This K/A concerns the ability to obtain and interpret station electrical and mechanical drawings. This K/A can only be used to develop a system based question. Replaced with K/A 2.2.6.

RO 3 2.3.5 (Q72) This K/A concerns the ability to use portable survey instruments, fixed radiation monitors, and alarms which would result in a radiation monitoring system question. Replaced with K/A 2.3.4.

RO 3 2.4.46 (Q75) This K/A concerns ability to verify alarms are consistent with plant conditions. This K/A can only be used to develop a system based question. Replaced with K/A 2.4.25.

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ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 1 Date of Exam: August 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 18 4 2 6 Emergency &

Abnormal 2 N/A N/A 9 1 3 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 3 2 5 2.

Plant 2 10 3 0 3 Systems Tier Totals 38 6 2 8

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