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2020 DC Cook Ile Written Exam Outlines ES-401-2 and ES-401-3
	ML20356A152
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Site:	Cook
Issue date:	08/25/2020
From:	David Reeser; Operations Branch III
To:	; Indiana Michigan Power Co, NRC/RGN-III/DRS/OLB
	Reeser D
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ES-401 PWR Examination Outline Form ES-401-2 Facility: DC Cook Date of Exam: July 2020 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

3 3

3 N/A 3

18 3

3 6

2 1

1 2

2 2

1 9

2 2

4 Tier Totals 4

4 5

5 5

4 27 5

5 10

2.

Plant Systems 1

2 3

2 2

3 3

2 3

3 28 3

2 5

2 1

0 1

1 1

10 0

2 1

3 Tier Totals 3

3 3

4 3

3 4

4 3

4 4

38 5

3 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

2 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it 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 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 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 These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 01 EA2.01 - Ability to determine or interpret the following as they apply to a reactor trip: Decreasing power level, from available indications.

(CFR: 41.7 / 45.5 / 45.6) 4.1 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 01.

07 G2.1.7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12, 45.13) 4.4 2

000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

(CFR: 41.8 / 41.10 / 45.3) 4.1 3

000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 10 AK2.10 - Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls.

(CFR: 41.7 / 45.7) 2.8 4

000022 (APE 22) Loss of Reactor Coolant Makeup / 2 03 AK3.03 - Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: Performance of lineup to establish excess letdown after determining need.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.1 5

000025 (APE 25) Loss of Residual Heat Removal System / 4 09 AA1.09 - Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators.

(CFR: 41.7 / 45.5, 45.6) 3.2 6

000026 (APE 26) Loss of Component Cooling Water / 8 04 AA2.04 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The normal values and upper limits for the temperatures of the components cooled by CCW.

(CFR: 43.5 / 45.13) 2.5 7

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 04.

02 G2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

(CFR: 41.7 / 45.7, 45.8) 4.5 8

000029 (EPE 29) Anticipated Transient Without Scram / 1 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the ATWS: Reactor nucleonics and thermo-hydraulic behavior.

(CFR: 41.8, 41.10 / 45.3) 2.8 9

000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 01 (W E12) EK2.1 - Knowledge of the interrelations between the (Uncontrolled Depressurization of all Steam Generators) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7) 3.4 10 000054 (APE 54; CE E06) Loss of Main Feedwater /4 03 AK3.03 - Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Manual control of AFW flow control valves.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.8 11

ES-401 3

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000055 (EPE 55) Station Blackout / 6 05 EA1.05 - Ability to operate and monitor the following as they apply to a Station Blackout:

Battery, when approaching fully discharged.

(CFR: 41.7 / 45.5, 45.6) 3.3 12 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 14 AA2.14 - Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: That substitute power sources have come on line on a loss of initial AC.

(CFR: 43.5 / 45.13) 3.2 13 000058 (APE 58) Loss of DC Power / 6 04.

34 G2.4.34 - Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13) 4.2 14 000062 (APE 62) Loss of Nuclear Service Water / 4 07 AA1.07 - Ability to operate and/or monitor the following as they apply the Loss of Nuclear Service Water (SWS): Flow rates to the components and systems that are serviced by the SWS; interactions among the components.

(CFR: 41.7 / 45.5, 45.6) 2.9 15 000065 (APE 65) Loss of Instrument Air / 8 08 AK3.08 - Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.7 16 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 02 EK2.2 - Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and the relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7 / 45.7) 3.8 17 (W E11) Loss of Emergency Coolant Recirculation / 4 01 EK1.1 - Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation): Components, capacity, and function of emergency systems.

(CFR: 41.8, 41.10 / 45.3) 3.7 18 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals:

3 3

Group Point Total:

18

ES-401 4

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal:

Manually driving rods into position that existed before start of casualty.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.2 19 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 04 AA1.04 - Ability to operate and/or monitor the following as they apply to the Inoperable / Stuck Control Rod: Reactor and turbine power.

(CFR: 41.7 / 45.5, 45.6) 3.9 20 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 08 AA2.08 - Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunction: PZR level as a function of power level.

(CFR: 43.5 / 45.13) 3.1 21 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 01.

20 G2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 4.6 22 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release: Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant.

(CFR: 41.8, 41.10 / 45.3) 2.7 23 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms

/ 7 01 AK2.01 - Knowledge of the interrelations between the Area Radiation Monitoring (ARM)

System Alarms and the following:

Detectors at each ARM system location.

(CFR: 41.7 / 45.7) 2.5 24 000067 (APE 67) Plant Fire On Site / 8 04 AK3.04 - Knowledge of the reasons for the following as they apply to the Plant Fire on Site:

Actions contained in EOP for plant fire on site.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.3 25 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3

ES-401 5

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 03 (W E13) EA1.3 - Ability to operate and/or monitor the following as they apply to the (Steam Generator Overpressure):

Desired operating results during abnormal and emergency situations.

(CFR: 41.7 / 45.5, 45.6) 3.1 26 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Subcooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 02 (W E08) EA2.2 - Ability to determine and interpret the following as they apply to the (Pressurizer Thermal Shock):

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

(CFR: 43.5 / 45.13) 3.5 27 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals:

1 1

2 2

2 1

Group Point Total:

9

ES-401 6

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump 01 A3.01 - Ability to monitor automatic operation of the RCPs, including: Seal injection flow.

(CFR: 41.7 / 45.5) 3.3 28 004 (SF1; SF2 CVCS) Chemical and Volume Control 16 18 A2.16 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: T-ave. and T-ref. deviations.

(CFR: 41.5 / 43.5 / 45.3, 45.5)

A4.18 - Ability to manually operate and/or monitor in the control room: Emergency borate valve.

(CFR: 41.7 / 45.5 to 45.8) 3.2 4.3 29 30 005 (SF4P RHR) Residual Heat Removal

04.

46 G2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3, 45.12) 4.2 31 006 (SF2; SF3 ECCS) Emergency Core Cooling 08 10 K1.08 - Knowledge of the physical connections and/or cause-effect relationship between ECCS and the following systems:

CVCS.

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K6.10 - Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Valves.

(CFR: 41.7 / 45.7) 3.6 2.6 32 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 01 K3.01 - Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment.

(CFR: 41.7 / 45.6) 3.3 34 008 (SF8 CCW) Component Cooling Water 02 K2.02 - Knowledge of the power supplies to the following: CCW pump, including emergency backup.

(CFR: 41.7) 3.0 35 010 (SF3 PZR PCS) Pressurizer Pressure Control 02 K4.02 - Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for the following: Prevention of uncovering PZR heaters.

(CFR: 41.7) 3.0 36 012 (SF7 RPS) Reactor Protection 01

04.

49 K5.01 - Knowledge of the operational implications of the following concepts as they apply to the RPS: DNB.

(CFR: 41.5 / 45.7)

G2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

(CFR: 41.10 / 43.2 / 45.6) 3.3 4.6 37 38 013 (SF2 ESFAS) Engineered Safety Features Actuation 01 K6.01 - Knowledge of the effect or a loss or malfunction on the following will have on the ESFAS: Sensors and detectors.

(CFR: 41.7 / 45.5 to 45.8) 2.7 39 022 (SF5 CCS) Containment Cooling 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment pressure.

(CFR: 41.5 / 45.5) 3.6 40

ES-401 7

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 025 (SF5 ICE) Ice Condenser 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the ice condenser system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Containment isolation.

(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.0 41 026 (SF5 CSS) Containment Spray 01 A3.01 - Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning.

(CFR: 41.7 / 45.5) 4.3 42 039 (SF4S MSS) Main and Reheat Steam 07 A4.07 - Ability to manually operate and/or monitor in the control room: Steam dump valves.

(CFR: 41.7 / 45.5 to 45.8) 2.8 43 059 (SF4S MFW) Main Feedwater 07

01.

32 A1.07 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including: Feed pump speed, including normal control speed for ICS.

(CFR: 41.5 / 45.5)

G2.1.32 - Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 2.5 3.8 44 45 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 07 K1.07 - Knowledge of the physical connections and/or cause-effect relationship between the AFW and the following systems:

Emergency water source.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.6 46 062 (SF6 ED AC) AC Electrical Distribution 01 07 K2.01 - Knowledge of bus power supplies to the following: Major system loads.

(CFR: 41.7)

A4.07 - Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different AC supplies.

(CFR: 41.7 / 45.5 to 45.8) 3.3 3.1 47 48 063 (SF6 ED DC) DC Electrical Distribution 02 K3.02 - Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: Components using DC control power.

(CFR: 41.7 / 45.6) 3.5 49 064 (SF6 EDG) Emergency Diesel Generator 01 K4.01 - Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: Trips while loading the ED/G (frequency, voltage, speed).

(CFR: 41.7) 3.8 50 073 (SF7 PRM) Process Radiation Monitoring 03 K5.03 - Knowledge of the operational implications as they apply to the concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits (CFR: 41.5 / 45.7) 2.9 51 076 (SF4S SW) Service Water 08 02 K2.08 - Knowledge of the bus power supplies to the following: ESF-actuated MOVs.

(CFR: 41.7)

A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

(CFR: 41.5 / 45.5) 3.1 2.6 52 53

ES-401 8

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 078 (SF8 IAS) Instrument Air 03 K4.03 - Knowledge of IAS design feature(s) and/or interlock(s) which provide for the following: Securing of SAS upon loss of cooling water.

(CFR: 41.7) 3.1 54 103 (SF5 CNT) Containment 03 A2.03 - Ability to (a) predict the impacts of 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: Phase A and B isolation (CFR: 41.5 / 43.5 / 45.3, 45.13) 3.5 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

2 3

2 2

3 3

2 3

3 Group Point Total:

28

ES-401 9

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 03 K6.03 - Knowledge of the effect or a loss or malfunction on the following RCS components:

Reactor vessel level indication.

(CFR: 41.7 / 45.7) 3.1 56 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including: Control rod position indication on control room panels.

(CFR: 41.5 / 45.5) 3.2 57 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 01 A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Thermocouple open and short circuits (CFR: 41.5 / 43.5 / 45.3, 45.5) 3.1 58 027 (SF5 CIRS) Containment Iodine Removal Cook does not have a Containment Iodine Removal System.

028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 02 A4.02 - Ability to manually operate and/or monitor in the control room: Fill of dry S/G.

(CFR: 41.7 / 45.5 to 45.8) 2.7 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 01.

31 G2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12) 4.6 61 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 04 K1.04 - Knowledge of the physical connections and/or cause-effect relationships between the Waste Gas Disposal System and the following systems: Station ventilation.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 62 072 (SF7 ARM) Area Radiation Monitoring 01 A3.01 - Ability to monitor automatic operation of the ARM System including: Changes in ventilation alignment.

(CFR: 41.7 / 45.5) 2.9 59

ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 075 (SF8 CW) Circulating Water 07 K3.07 - Knowledge of the effect that a loss or malfunction of the circulating water system will have on the following: ESFAS.

(CFR: 41.7 / 45.6) 3.4 63 079 (SF8 SAS**) Station Air 01 K4.01 - Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following: Cross-connect with IAS.

(CFR: 41.7) 2.9 64 086 Fire Protection 04 K5.04 - Knowledge of the operational implications of the following concepts as they apply to the Fire Protection System: Hazards to personnel as a result of fire type and methods of protection.

(CFR: 41.5 / 45.7) 2.9 65 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

1 0

1 1

1 Group Point Total:

10

ES-401 11 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 38 EA2.38 - Ability to determine or interpret the following as they apply to a small break LOCA:

Existence of head bubble.

(CFR: 43.5 / 45.13) 4.3 76 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 01.

28 G2.1.28 - Knowledge of the purpose and function of major system components and controls.

(CFR: 41.7) 4.1 77 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 12 EA2.12 - Ability to determine or interpret the following as they apply to a SGTR: Status of MSIV activating system.

(CFR: 43.5 / 45.13) 4.2 78 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout / 6 000056 (APE 56) Loss of Offsite Power / 6 02.

38 G2.2.38 - Knowledge of conditions and limitations in the facility license.

(CFR: 41.7, 41.10 / 43.1 / 45.13) 4.5 79 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 000062 (APE 62) Loss of Nuclear Service Water / 4 000065 (APE 65) Loss of Instrument Air / 8 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 09 AA2.09 - Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Operational status of emergency diesel generators.

(CFR: 41.5 / 43.5 / 45.5, 45.7, 45.8) 4.3 80 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4

ES-401 12 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 04.

47 G2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 / 43.5 / 45.12) 4.2 81 K/A Category Totals:

3 3

Group Point Total:

6

ES-401 13 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 04.

46 G2.4.46 - Ability to verify that the alarms are consistent with the plant conditions (CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 82 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms

/ 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 02 (W E14) EA2.2 - Ability to determine and interpret the following as they apply to the (High Containment Pressure):

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

(CFR: 43.5 / 45.13) 3.8 83 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 04.

06 G2.4.6 - Knowledge of EOP mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 4.7 84 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Subcooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4

ES-401 14 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 01 (W E10) EA2.1 - Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13) 3.9 85 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals:

2 2

Group Point Total:

4

ES-401 15 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCPs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of fluctuation of VCT pressure on RCP seal injection flow.

(CFR: 41.5 / 43.5 / 45.3, 45.13) 2.8 86 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS) Emergency Core Cooling 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 013 (SF2 ESFAS) Engineered Safety Features Actuation

02.

40 G2.2.40 - Ability to apply Technical Specifications for a system.

(CFR: 41.10 / 43.2, 43.5 / 45.13) 4.7 87 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam 03 A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Indications and alarms for main steam and area radiation monitors (during SGTR).

(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.7 88 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)

Auxiliary/Emergency Feedwater

02.

37 G2.2.37 - Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12) 4.6 89 062 (SF6 ED AC) AC Electrical Distribution 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator 11 A2.11 - Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions (minimum load) required for unloading an ED/G (CFR: 41.5 / 43.5 / 45.3, 45.13) 2.9 90

ES-401 16 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

3 2

Group Point Total:

5

ES-401 17 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 10 A2.10 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of PZR level instrument -

high.

(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.6 91 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal Cook does not have a Containment Iodine Removal System.

028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 01.

23 G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2, 45.6) 4.4 92 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

(CFR: 41.5 / 43.5 / 45.3, 45.13) 2.9 93 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

2 1

Group Point Total:

3

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

Form ES-401-3 18 Facility: DC Cook Date of Exam: July 2020 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all modes of plant operation.

(CFR: 41.10 / 45.13) 4.1 66 2.1.39 Knowledge of conservative decision making practices.

(CFR: 41.10 / 43.5 / 45.12) 3.6 67 2.1.41 Knowledge of the refueling process.

(CFR: 41.10 / 43.7 / 45.13) 2.8 68 2.1.6 Ability to manage the control room crew during plant transients.

(CFR: 41.10 / 43.5 / 45.12, 45.13) 4.8 94 2.1.13 Knowledge of facility requirements for controlling vital/controlled access.

(CFR: 41.10 / 43.5 / 45.9, 45.10) 3.2 95 Subtotal 3

2

2. Equipment Control 2.2.3 Knowledge of the design, procedural, and operational differences between units.

(CFR: 41.5, 41.6, 41.7, 41.10 / 45.12) 3.8 69 2.2.43 Knowledge of the process used to track inoperable alarms.

(CFR: 41.10 / 43.5 / 45.13) 3.0 70 2.2.11 Knowledge of the process for controlling temporary design changes.

(CFR: 41.10 / 43.3 / 45.13) 3.3 96 2.2.22 Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2) 4.7 97 Subtotal 2

2

3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10) 3.2 71 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9) 2.9 72 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

(CFR: 41.12 / 43.4 / 45.10) 3.8 98 Subtotal 2

1

4. Emergency Procedures/Plan 2.4.11 Knowledge of abnormal condition procedures.

(CFR: 41.10 / 43.5 / 45.13) 4.0 73 2.4.17 Knowledge of EOP terms and definitions.

(CFR: 41.10 / 45.13) 3.9 74 2.4.27 Knowledge of fire in the plant procedures.

(CFR: 41.10 / 43.5 / 45.13) 3.4 75

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

Form ES-401-3 19 Facility: DC Cook Date of Exam: July 2020 Category K/A #

Topic RO SRO-only IR IR 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12) 4.6 99 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

(CFR: 41.10 / 43.5 / 45.11) 4.5 100 Subtotal 3

2 Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: DC Cook Date of Exam: July 2020 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

34 3

3 N/A 3

3 N/A 32 18 3

3 6

2 1

1 2

2 2

1 9

23 21 4

Tier Totals 45 4

5 5

5 43 27 56 54 10

2.

Plant Systems 1

2 3

2 2

3 3

2 3

3 28 3

2 5

2 1

0 1

1 1

10 0

2 1

3 Tier Totals 3

3 3

4 3

3 4

4 3

4 4

38 5

3 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

2 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it 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 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 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 These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 01 EA2.01 - Ability to determine or interpret the following as they apply to a reactor trip: Decreasing power level, from available indications.

(CFR: 41.7 / 45.5 / 45.6) 4.1 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 01.

07 G2.1.7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12, 45.13) 4.4 2

000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.

(CFR: 41.8 / 41.10 / 45.3) 4.1 3

000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 10 AK2.10 - Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls.

(CFR: 41.7 / 45.7) 2.8 4

000022 (APE 22) Loss of Reactor Coolant Makeup / 2 03 AK3.03 - Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: Performance of lineup to establish excess letdown after determining need.

(CFR: 41.5, 41.10 / 45.6, 45.13) 3.1 5

000025 (APE 25) Loss of Residual Heat Removal System / 4 09 AA1.09 - Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators.

(CFR: 41.7 / 45.5, 45.6) 3.2 6

000026 (APE 26) Loss of Component Cooling Water / 8 04 AA2.04 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The normal values and upper limits for the temperatures of the components cooled by CCW.

(CFR: 43.5 / 45.13) 2.5 7

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 04.

02 G2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

(CFR: 41.7 / 45.7, 45.8) 4.5 8

000029 (EPE 29) Anticipated Transient Without Scram / 1 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the ATWS: Reactor nucleonics and thermo-hydraulic behavior.

(CFR: 41.8, 41.10 / 45.3) 2.8 9

000038 (EPE 38) Steam Generator Tube Rupture / 3 01 Knowledge of the operational implications of the following concepts as they apply to the SGTR: Use of Steam Tables.

(CFR 41.8 / 41.10 / 45.3) 3.1 14 000040 (APE 40; BW E05; CE E05; W E12)