ML20174A606

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05 Draft Outlines
ML20174A606
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/21/2020
From: Greg Werner
Operations Branch IV
To:
Vistra Operating Co. (VistraOpCo)
References
50-445/20-05, 50-446/20-05 50-445/OL-20, 50-446/OL-20
Download: ML20174A606 (21)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 Facility: CPNPP Date of Exam: 05/21/2020 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

3 N/A 3

18 6

2 1

1 1

2 2

2 9

4 Tier Totals 4

4 4

5 5

5 27 10

2.

Plant Systems 1

3 2

3 2

2 2

3 2

3 3

3 28 5

2 1

1 1

1 1

1 0

1 1

1 1

10 3

Tier Totals 4

3 4

3 3

3 3

3 4

4 4

38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

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 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 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 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) Reactor Trip, Stabilization, Recovery / 1 X

EK1.04 Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Decrease in reactor power following reactor trip (prompt drop and subsequent decay) 3.6 39 000008 (APE 8) Pressurizer Vapor Space Accident / 3 X

AA2.12 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PZR level indicators 3.4 40 000009 (EPE 9) Small Break LOCA / 3 X

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.4 41 000011 (EPE 11) Large Break LOCA / 3 X

EK3.14 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:

RCP tripping requirement 4.1 42 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X

2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.5 43 000025 (APE 25) Loss of Residual Heat Removal System / 4 X

AK1.01 Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation 3.9 44 000026 (APE 26) Loss of Component Cooling Water / 8 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 3.6 45 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction 3.7 46 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 X

EA1.04 Ability to operate and monitor the following as they apply to a SGTR: PZR spray, to reduce coolant system pressure 4.3 47 000040 (APE 40; W E12) Steam Line RuptureExcessive Heat Transfer Uncontrolled Depressurization of all Steam Generators / 4 X

AK1.02 Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: Leak rate versus pressure change 3.2 48 000054 (APE 54;) Loss of Main Feedwater

/4 000055 (EPE 55) Station Blackout / 6 X

EA1.06 Ability to operate and monitor the following as they apply to a Station Blackout: Restoration of power with one ED/G 4.1 49 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X

2.1.31 Ability to locate control room switches, controls, and indications, and tol determine that they correctly reflect the desired plant lineup.

4.6 50 000058 (APE 58) Loss of DC Power / 6 X

AA1.03 Ability to operate and / or monitor the following as they apply to the Loss of DC Power:

Vital and battery bus components 3.1 51 000062 (APE 62) Loss of Nuclear Service Water / 4 X

AA2.03 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 2.6 52

ES-401 3

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 000065 (APE 65) Loss of Instrument Air / 8 X

AA2.06 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing 3.6 53 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 X

EK2.2 Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

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

3.8 54 (W E11) Loss of Emergency Coolant Recirculation / 4 X

EK2.01 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.6 55 W E05 Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X

EK2.02 Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

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

3.9 56 K/A Category Totals:

3 3

3 3

3 3

Group Point Total:

18

ES-401 4

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 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 000003 (APE 3) Dropped Control Rod / 1 X

AA2.02 Ability to determine and interpret the following as they apply to the Dropped Control Rod: Signal inputs to rod control system 2.7 57 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 X

AK1.01 Knowledge of the operational implications of the following concepts as they apply to Pressurizer Level Control Malfunctions: PZR reference leak abnormalities 2.8 58 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 X

AA2.02 Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation:

Expected change in source range count rate when rods are moved 3.6 59 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36) Fuel Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 X

AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum 2.8 60 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 X

AA1.10 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation: Power distribution:

ac and dc 2.9 61 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 X

AK2.01 Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors 2.6 62 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 X 2.1.20 Ability to interpret and execute procedure steps.

4.6 63 (W E13) Steam Generator Overpressure / 4 X

EA1.03 Ability to operate and / or monitor the following as they apply to the (Steam Generator Overpressure): Desired operating results during abnormal and emergency situations.

3.1 64

ES-401 5

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 (W E15) Containment Flooding / 5 X

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.3 65 (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 Cooldown-Depressurization / 4 (W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (W E08) RCS Overcooling-Pressurized 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:

1 1

1 2

2 2

Group Point Total:

9

ES-401 6

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 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 X

K5.02 Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects of RCP coastdown on RCS parameters 2.8 1

004 (SF1; SF2 CVCS) Chemical and Volume Control X

K4.16 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Temperature at which the temperature control valve automatically diverts flow from the demineralizer to the VCT; reason for this diversion 2.6 2

005 (SF4P RHR) Residual Heat Removal X

K2.03 Knowledge of bus power supplies to the following: RCS pressure boundary motor-operated valves 2.7 3

006 (SF2; SF3 ECCS) Emergency Core Cooling X

2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

3.8 4

007 (SF5 PRTS) Pressurizer Relief/Quench Tank X

X K1.03 Knowledge of the physical connections and/or cause effect relationships between the PRTS and the following systems: RCS A4.10 Ability to manually operate and/or monitor in the control room: Recognition of leaking PORV/code safety 3.0 3.6 5

6 008 (SF8 CCW) Component Cooling Water X

X K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: Service Water System K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: Loads cooled by CCWS 3.1 3.4 7

8 010 (SF3 PZR PCS) Pressurizer Pressure Control X

A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: Spray nozzle DT 3.2 9

012 (SF7 RPS) Reactor Protection X

K6.02 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Redundant channels 2.9 10 013 (SF2 ESFAS) Engineered Safety Features Actuation X

A1.04 Ability to predict and/or monitor changes in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: S/G level 3.4 11 022 (SF5 CCS) Containment Cooling X

A3.01 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 4.1 12 025 (SF5 ICE) Ice Condenser Not part of CP design 026 (SF5 CSS) Containment Spray X

A4.05 Ability to manually operate and/or monitor in the control room: Containment spray reset switches 3.5 13 039 (SF4S MSS) Main and Reheat Steam X

A3.02 Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS 3.1 14

ES-401 7

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 059 (SF4S MFW) Main Feedwater X

2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.2 15 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners 2.5 16 062 (SF6 ED AC) AC Electrical Distribution X

X K3.01 Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: Major system loads 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

3.5 3.8 17 18 063 (SF6 ED DC) DC Electrical Distribution X

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds 2.5 19 064 (SF6 EDG) Emergency Diesel Generator X

X K3.01 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following: Systems controlled by automatic loader K4.02 Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: Trips for ED/G while operating (normal or emergency) 3.8 3.9 20 21 073 (SF7 PRM) Process Radiation Monitoring X

X K1.01 Knowledge of the physical connections and/or cause effect relationships between the PRM system and the following systems: Those systems served by PRMs K5.02 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Radiation intensity changes with source distance 3.6 2.5 22 23 076 (SF4S SW) Service Water X

A4.02 Ability to manually operate and/or monitor in the control room: SWS valves 2.6 24 078 (SF8 IAS) Instrument Air X

X K2.02 Knowledge of bus power supplies to the following: Emergency air compressor A3.01 Ability to monitor automatic operation of the IAS, including: Air Pressure 3.3 3.1 25 26

ES-401 8

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 103 (SF5 CNT) Containment X

X A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

Containment pressure, temperature, and humidity A2.04 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 Containment evacuation (including recognition of the alarm) 3.7 3.5 27 28 053 (SF1; SF4P ICS*) Integrated Control Not part of CP design K/A Category Point Totals:

3 2

3 2

2 2

3 2

3 3

3 Group Point Total:

28

ES-401 9

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 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 X

K4.07 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following: Rod Stops 3.7 35 002 (SF2; SF4P RCS) Reactor Coolant X

K1.03 Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: Borated water storage tank 3.8 29 011 (SF2 PZR LCS) Pressurizer Level Control X

K5.15 Knowledge of the operational implications of the following concepts as they apply to the PZR LCS: PZR level indication when RCS is saturated 3.6 30 014 (SF1 RPI) Rod Position Indication X

K3.02 Knowledge of the effect that a loss or malfunction of the RPIS will have on the following: Plant computer 2.5 31 015 (SF7 NI) Nuclear Instrumentation X

K2.01 Knowledge of bus power supplies to the following: NIS channels, components, and interconnections 3.3 32 016 (SF7 NNI) Nonnuclear Instrumentation X

A3.02 Ability to monitor automatic operation of the NNIS, including: Relationship between meter readings and actual parameter value 2.9 37 017 (SF7 ITM) In Core Temperature Monitor X

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.

4.0 33 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling X

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Inadequate SDM 3.0 34 034 (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 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X

K6.10 Knowledge of the effect of a loss or malfunction on the following will have on the Liquid Radwaste System: Radiation monitors 2.5 36 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air

ES-401 10 Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 086 Fire Protection X

A4.02 Ability to manually operate and/or monitor in the control room: Fire detection panels 3.5 38 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

1 1

1 1

1 1

0 1

1 1

1 Group Point Total:

10

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

Form ES-401-3 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2 Facility: CPNPP Date of Exam: 05/21/2020 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.9 66 2.1.40 Knowledge of refueling administrative requirements.

2.8 67 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

3.3 68 Subtotal 3

2. Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status.

3.9 69 2.2.38 Knowledge of conditions and limitations in the facility license.

3.6 70 Subtotal 2

3. Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 71 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.4 72 Subtotal 2

4. Emergency Procedures/Plan 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.

3.0 73 2.4.13 Knowledge of crew roles and responsibilities during EOP usage.

4.0 74 2.4.43 Knowledge of emergency communications systems and techniques.

3.2 75 Subtotal 3

Tier 3 Point Total 10 7

ES-401 1

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 2 Facility: CPNPP Date of Exam: 05/21/2020 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

N/A N/A 18 3

3 6

2 9

2 2

4 Tier Totals 27 5

5 10

2.

Plant Systems 1

28 2

3 5

2 10 2

1 3

Tier Totals 38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 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 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 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 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 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

4.3 84 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

AA2.18 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Operable control channel 3.5 85 000029 (EPE 29) Anticipated Transient Without Scram / 1 X 2.2.22 Knowledge of limiting conditions for operations and safety limits.

4.0 86 000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line Rupture-Excessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X

AA2.03 Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Conditions and reasons for AFW pump startup 4.1 87 000055 (EPE 55) Station Blackout / 6 000056 (APE 56) Loss of Offsite Power / 6 X

AA2.04 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

Operational status of service water pump 3.7 88 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 X 2.1.32 Ability to explain and apply system limits and precautions.

4.0 89 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat Transfer-Loss of Secondary Heat Sink / 4 K/A Category Totals:

3 3

Group Point Total:

6

ES-401 3

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 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 X

AA2.03 Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions to be taken if automatic safety functions have not taken place 4.8 90 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 X

2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 91 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X 2.1.20 Ability to interpret and execute procedure steps.

4.6 92 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 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 & W/E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 X

EA2.2 Ability to determine and interpret the following as they apply to the (High Containment Radiation): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.3 93 (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

ES-401 4

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 2 (BW E08; W E03) LOCA Cooldown-Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11 W E08) RCS Overcooling-Pressurized 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 5

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 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 X

2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

4.1 76 004 (SF1; SF2 CVCS) Chemical and Volume Control X

A2.27 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: Improper RWST boron concentration 4.2 77 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS) Emergency Core Cooling X 2.4.18 Knowledge of the specific bases for EOPs.

4.0 78 007 (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 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam X 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

4.2 79 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical Distribution 063 (SF6 ED DC) DC Electrical Distribution X

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of ventilation during battery charging 3.1 80 064 (SF6 EDG) Emergency Diesel Generator 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:

2 3

Group Point Total:

5

ES-401 6

Form ES-401-2 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 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 X

A2.03 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of stuck rod or Misaligned rod 4.2 81 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation X

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of power supply 3.2 82 017 (SF7 ITM) InCore Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) FuelHandling Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X 2.1.32 Ability to explain and apply system limits and precautions.

4.0 83 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 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 CPNPP 2020-05 NRC ES-401-2 & 3 SRO Written Exam Outline Rev. 2 Facility: CPNPP Date of Exam: 05/21/2020 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.41 Knowledge of the refueling process.

3.7 94 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.7 95 Subtotal 2

2. Equipment Control 2.2.19 Knowledge of maintenance work order requirements.

3.4 96 2.2.20 Knowledge of the process for managing troubleshooting activities.

3.8 97 Subtotal 2

3. Radiation Control 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.7 98 Subtotal 1

4. Emergency Procedures/Plan 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.8 99 2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

4.1 100 Subtotal 2

Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Page 1 of 3 CPNPP 2020-05 NRCRO/SRO ES-401-4 Record of Rejected K/As Rev. 0 Tier /

Group Randomly Selected K/A Reason for Rejection RO EXAM 2/1 008.K3.03 Question 8 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 008.K3.01 2/1 010.A1.09 Question 9 CPNPP does not have acoustic monitors associated with Przr Safeties/PORVs. Replaced original K/A with new K/A 010.A1.08 2/1 062.G.2.4.3 Question 18 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 062.G.2.4.20 2/1 064.K4.08 Question 21 CPNPP does not have auto isolation/control of EDG fuel isolation valves. Replaced original K/A with new K/A 064.K4.02 2/1 073.K5.01 Question 23 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 073.K5.02 2/2 017.G.2.4.34 Question 33 RO has no tasks outside the Control Room related to Incore Temperature Monitoring, for either normal operations or emergency operations. Replaced original K/A with new K/A 017.G.2.4.21 2/2 034.K4.01 Question 35 Unable to write a question at the RO level for original K/A. Randomly reselected from Tier 2/Group 2 K/A Category K4 due to no 034.K4 Knowledge K/As being available to generate a question at the RO level.

Replaced original K/A with new K/A 001.K4.07 2/2 072.A3.01 Question 37 CPNPP does not have any automatic actions that occur from Area Rad Monitors. Randomly reselected from Tier 2/Group 2 K/A Category A3 due to no 072.A3 Ability K/As being available to select. Replaced original K/A with new K/A 016.A3.02 1/1 000008.AA2.09 Question 40 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000008.AA2.12



ES-401 Record of Rejected K/As Form ES-401-4 Page 2 of 3 CPNPP 2020-05 NRCRO/SRO ES-401-4 Record of Rejected K/As Rev. 0 Tier /

Group Randomly Selected K/A Reason for Rejection RO EXAM 1/1 000026.AK3.01 Question 45 CPNPP does not have auto isolation on SSW to CCW valves. Replaced original K/A with new K/A 000026.AK3.02 1/1 000027.AK3.01 Question 46 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000027.AK3.03 1/1 000038.EA1.13 Question 47 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000038.EA1.04 1/1 000062.AA2.04 Question 52 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000062.AA2.03 1/2 000061.AA1.01 Question 61 CPNPP does not have any automatic actions that occur from Area Rad Monitors. Randomly reselected from Tier 1/Group 2 K/A Category AA1 due to no 000061.AA1 Ability K/As being available to select, Replaced original K/A with new K/A 000068.AA1.10







ES-401 Record of Rejected K/As Form ES-401-4 Page 3 of 3 CPNPP 2020-05 NRCRO/SRO ES-401-4 Record of Rejected K/As Rev. 0 Tier /

Group Randomly Selected K/A Reason for Rejection SRO Exam 2/1 004.A2.09 Question 77 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 004.A2.27 2/1 006.G.2.4.40 Question 78 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 006.G.2.4.18 2/2 001.A2.01 Question 81 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 001.A2.03 1/1 000054.AA2.05 Question 87 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000054.AA2.03 1/2 000059.G.2.4.35 Question 92 Did not have appropriate reference material to generate a question that matches K/A. Replaced original K/A with new K/A 000059.G.2.1.20



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