Text

2018 Donald C. Cook Nuclear Power Plant Exam Forms ES-401-2
	ML20357A509
Person / Time
Site:	Cook
Issue date:	08/13/2018
From:	Chuck Zoia; Operations Branch III
To:	; Indiana Michigan Power Co
	Zoia C
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ML171164A385	List: ML20357A509;
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	Download: ML20357A509 (16)
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ES-401 PWR Examination Outline Form ES-401-2 Facility: D.C. Cook Date of Exam: 06/18/2018 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

2 2

1 9

2 2

4 Tier Totals 4

5 4

5 5

4 27 5

5 10

2.

Plant Systems 1

2 3

2 2

3 3

2 28 3

2 5

2 1

0 1

1 1

10 1

1 1

3 Tier Totals 3

3 3

4 3

3 4

4 4

4 3

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 02 EA2.02 - Ability to determine or interpret the following as they apply to a reactor trip: Proper actions to be taken if the automatic safety functions have not taken place.

(CFR: 41.7 / 45.5 / 45.6) 4.3 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 04.

03 G2.4.3 - Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4) 3.7 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 08 AK2.08 - Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: CCWS (CFR: 41.7 / 45.7) 2.6 4

000022 (APE 22) Loss of Reactor Coolant Makeup / 2 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: Adjustment of RCP seal backpressure regulator valve to obtain normal flow.

(CFR: 41.5 / 41.10 / 45.6 / 45.13) 2.7 5

000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 02 AA1.02 - Ability to operator and/or monitor the following as they apply to a Loss of Component Cooling Water: Loads on the CCWS in the control room.

(CFR: 41.7 / 45.5 / 45.6) 3.2 6

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 1

8 AA2.13 - Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Operable control channel (CFR: 43.5 / 45.13) 3.4 7

000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 02.

22 G2.2.22 - Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2) 4.0 8

000040 (APE 40; BW E05; CE E05; W E12) Steam Line RuptureExcessive Heat Transfer / 4 03 EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Uncontrolled Depressurization of all Steam Generators): Annunciators and conditions indicating signals, remedial actions associated with the (Uncontrolled Depressurization of all Steam Generators)

(CFR: 41.8 / 41.10 / 45.3) 3.4 9

000054 (APE 54; CE E06) Loss of Main Feedwater /4 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Reactor and/or turbine trip, manual and automatic.

(CFR: 41.5,41.10 / 45.6 / 45.13) 4.5 10 000055 (EPE 55) Station Blackout / 6 06 EA2.06 - Ability to determine or interpret the following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses.

(CFR: 43.5 / 45.13) 3.7 11 000056 (APE 56) Loss of Offsite Power / 6 09 AA1.09 - Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power:

CCW Pump (CFR: 41.7 / 45.5 / 45.6) 3.3 12

ES-401 3

Form ES-401-2 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of dc control power by D/Gs.

(CFR: 41.5, 41.10 / 45.6 / 45.1) 3.4 13 000062 (APE 62) Loss of Nuclear Service Water / 4 06 AA1.06 - Ability to operate and/or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): Control of flow rates to components cooled by the SWS.

(CFR: 41.7, 45.5 / 45.6) 2.9 14 000065 (APE 65) Loss of Instrument Air / 8 01.

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

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.3 15 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 03 AK2.03 - Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Sensors, detectors, and indicators.

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 3.0 16 (W E04) LOCA Outside Containment / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the (LOCA Outside Containment): Components, capacity, and function of emergency systems.

(CFR: 41.8, 41.10 / 45.3) 3.5 17 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 02 EK2.2 - Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following: Facilitys 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.

(CFR: 41.7 / 45.7) 3.9 18 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 000003 (APE 3) Dropped Control Rod / 1 16 AK1.16 - Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: MTC (CFR: 41.8, 41.10 / 45.3) 2.9 19 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 03 AK2.03 - Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following:

Controllers and positioners.

(CFR: 41.7 / 45.7) 2.6 20 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 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Fuel Handling Accident: Different inputs that will cause a reactor building evacuation.

3.1 21 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 02 AA1.02 - Ability to operate and/or monitor the following as they apply to Accidental Gaseous Radwaste: Ventilation System (CFR: 41.7 / 45.5, 45.6) 2.9 22 000061 (APE 61) Area Radiation Monitoring System Alarms

/ 7 000067 (APE 67) Plant Fire On Site / 8 01.

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

(CFR: 41.7) 4.1 23 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 02 EA2.2 - Ability to determine and interpret the following as they apply to the (Degraded Core Cooling): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

(CFR: 43.5 / 45.13) 3.5 24 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3

ES-401 5

Form ES-401-2 (W E13) Steam Generator Overpressure / 4 03 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 25 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW E08; W E03) LOCA CooldownDepressurization / 4 01 EK2.1 - Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) 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) 3.6 26 (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 01 EA2.1 - Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13) 3.4 27 K/A Category Point Totals:

1 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 04 K6.04 - Knowledge of the effect of a loss of malfunction on the following will have on the RCPS: Containment isolation valves affecting RCP operation.

(CFR: 41.7 / 45.5) 2.8 28 004 (SF1; SF2 CVCS) Chemical and Volume Control 03 06 K2.03 - Knowledge of bus power supplies to the following: Charging pumps (CFR 41.7)

A1.06 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: VCT level (CFR: 41.5 / 45.5) 3.3 3.0 29 30 005 (SF4P RHR) Residual Heat Removal 04 AA2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.9 31 006 (SF2; SF3 ECCS) Emergency Core Cooling 18 08 K4.18 - Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Valves normally isolated from their control power.

(CFR: 41.7)

A3.08 - Ability to monitor automatic operation of the ECCS, including: Automatic transfer of ECCS flowpaths.

(CFR: 41.7 / 45.5) 3.6 4.2 32 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 10 A4.10 - Ability to manually operate and/or monitor in the control room: Recognition of leaking PORV/code safety.

(CFR: 41.7 / 45.5 to 45.8) 3.6 34 008 (SF8 CCW) Component Cooling Water 01.

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

(CFR: 41.10 / 43.5 / 45.12) 4.6 35 010 (SF3 PZR PCS) Pressurizer Pressure Control 02 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures.

(CFR: 41.5 / 43.5 / 45.3, 45.13)

A4.02 - Ability to manually operate and/or monitor in the control room: PZR heaters.

(CFR: 41.7 / 45.5 to 45.8) 3.9 3.6 36 37 012 (SF7 RPS) Reactor Protection 06 A3.06 - Ability to monitor automatic operation of the RPS, including: Trip logic.

(CFR: 41.7 / 45.5) 3.7 38 013 (SF2 ESFAS) Engineered Safety Features Actuation 06 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of instrument bus.

(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.6 39 022 (SF5 CCS) Containment Cooling 01 01 K2.01 - Knowledge of power supplies to the following: Containment cooling fans.

(CFR: 41.7)

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

(CFR: 41.5 / 45.5) 3.0 3.6 40 41

ES-401 7

Form ES-401-2 025 (SF5 ICE) Ice Condenser 01 K6.01 - Knowledge of the effect of a loss or malfunction of the following will have on the ice condenser system: Upper and lower doors of the ice condenser.

(CFR: 41.7 / 45.7) 3.4 42 026 (SF5 CSS) Containment Spray 04 01 K4.04 - Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following: Reduction of temperature and pressure in containment after a LOCA by condensing steam, to reduce radiological hazard, and protect equipment from corrosion damage (spray).

(CFR 41.7)

A3.01 - Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning.

(CFR: 41.7, 45.5) 3.7 4.3 43 44 039 (SF4S MSS) Main and Reheat Steam 08 K5.08 - Knowledge of the operational implications of the following concepts as they apply to the MRSS: Effect of steam removal on reactivity.

(CFR: 41.5 / 45.7) 3.6 45 059 (SF4S MFW) Main Feedwater 03 K3.03 - Knowledge of the effect that a loss or malfunction of the MFW will have on the following: S/Gs.

(CFR: 41.7 / 45.6) 3.5 46 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 03 K5.03 - Knowledge of the operational implications of the following concepts as they apply to the AFW: Pump head effects when control valve is shut.

(CFR: 41.5 / 45.7) 2.6 47 062 (SF6 ED AC) AC Electrical Distribution 02 K1.02 - Knowledge of the physical connection and/or cause-effect relationships between the ac distribution system and the following systems: ED/G.

(CFR: 41.2 to 41.9) 4.1 48 063 (SF6 ED DC) DC Electrical Distribution 01 K2.01 - Knowledge of bus power supplies to the following: Major DC loads.

(CFR: 41.7) 2.9 49 064 (SF6 EDG) Emergency Diesel Generator 02 09 K3.02-Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following: ESFAS controlled or actuated systems.

(CFR: 41.7 / 45.6)

A4.09 - Ability to manually operate and/or monitor in the control room: Establishing power from the ring bus (to relieve ED/G)

(CFR: 41.7 / 45.5 to 45.8) 4.2 3.2 50 51 073 (SF7 PRM) Process Radiation Monitoring 01 K4.01 - Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint.

(CFR: 41.7) 4.0 52 076 (SF4S SW) Service Water 21 K1.21 - Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems:

Auxiliary backup SWS.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 53 078 (SF8 IAS) Instrument Air 04.

31 G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

(CFR 41.10 / 45.3) 3.6 54 103 (SF5 CNT) Containment 01 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.

(CFR: 41.5 / 45.5) 3.7 55

ES-401 8

Form ES-401-2 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

2 3

2 2

3 3

2 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 12 K4.12 - Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following: Re-zeroing rod demand position counters.

(CFR: 41.7) 2.5 56 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 01 K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the NIS: Sensors, detectors, and indicators.

(CFR: 41.7 / 45.7) 2.9 57 016 (SF7 NNI) Nonnuclear Instrumentation 03 A2.03 - 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: Interruption of transmitted signal (CFR: 41.5 / 43.5 / 45.3, 45.5) 3.0 58 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 02.

12 G2.2.12 - Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13) 3.7 59 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 01 A3.01 - Ability to monitor automatic operation of the S/G including: S/G water level control (CFR: 41.7 / 45.5) 4.0 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 05 A4.05 - Ability to manually operator and/or monitor in the control room: Main steam header pressure (CFR: 41.7 / 45.5 to 45.8) 3.1 61 045 (SF 4S MTG) Main Turbine Generator 18 K5.18 - Knowledge of the operational implications of the following concepts as they apply to the MT/B System: Purpose of low-power reactor trips (limited to 25% power) 2.7 62 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 05 K3.05 - Knowledge of the effect that a loss or malfunction of the Waste Gas Disposal System will have on the following: ARM and PRM systems.

(CFR: 41.7 / 45.6) 3.2 63

ES-401 10 Form ES-401-2 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 02 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems: Liquid radwaste discharge (CFR 41.2 to 41.9 / 45.7 to 45.8) 2.9 64 079 (SF8 SAS**) Station Air 086 Fire Protection 01 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure.

(CFR: 41.5 / 45.5) 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 04.

45 G2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3, 45.12) 4.3 76 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 15 EA2.15 - Ability to determine or interpret the following as they apply to a small break LOCA: RCS parameters.

(CFR: 43.5 / 45.13) 3.4 77 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 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 04.

04 G2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6) 4.7 78 000038 (EPE 38) Steam Generator Tube Rupture / 3 16 EA2.16 - Ability to determine or interpret the following as they apply to a SGTR: Actions to be taken if S/G goes solid and water enters steam line.

(CFR: 43.5 / 45.13) 4.6 79 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 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 04.

08 G2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

(CFR: 41.10 / 43.5 45.13) 4.5 80 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 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 01 EA2.01 - Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13) 4.2 81

ES-401 12 Form ES-401-2 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals:

0 0

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 02 AA2.02 - Ability to determine and interpret the following as they apply to the Emergency Boration:

When use of manual boration valve is needed.

(CFR: 43.5 / 45.13) 4.4 82 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 02.

25 G2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5, 41.7 / 43.2) 4.2 83 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 02 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions for requiring reactor and/or turbine trip.

(CFR: 43.5 / 45.13) 4.1 84 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 04.

21 G2.4.21 - 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 85 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 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW E08; W E03) LOCA CooldownDepressurization / 4 (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 K/A Category Point Totals:

0 0

2 2

Group Point Total:

4

ES-401 14 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 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.7 86 006 (SF2; SF3 ECCS) Emergency Core Cooling 04.

09 G2.4.9 - Knowledge of low power/shutdown implications in accident (e.g, loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 4.2 87 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 03 A2.03 - Ability to (a) predict the impacts of the following malfunctions on the RPS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Incorrect channel bypassing (CFR: 41.5 / 43.5 / 45.3 / 45.5) 3.7 88 013 (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 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 064 (SF6 EDG) Emergency Diesel Generator 01.

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

(CFR: 41.10 / 43.2 / 45.12) 4.0 89

ES-401 15 Form ES-401-2 073 (SF7 PRM) Process Radiation Monitoring 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions on the PRM 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) 3.2 90 076 (SF4S SW) Service Water 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

0 0

0 3

0 0

2 Group Point Total:

5

ES-401 16 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 014 (SF1 RPI) Rod Position Indication 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions on the RPIS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Misaligned rod.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.9 91 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 02.

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

(CFR: 41.10 / 43.2, 43.5 / 45.3) 4.7 92 027 (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) Fuel-Handling Equipment 02 A4.02 - Ability to manually operate and/or monitor in the control room: Neutron levels.

(CFR: 41.7 / 45.5 to 45.8) 3.9 93 035 (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 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:

0 0

0 1

1 Group Point Total:

3

ML20357A509

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