ML21361A256

ES-401-2

ML21361A256
Person / Time
Site:	Byron
Issue date:	10/28/2021
From:	Gregory Roach NRC/RGN-III/DRS/OLB
To:	Exelon Generation Co
Roach G
Shared Package
ML21055A846	List: BYRON 2021-0033, Submittal on Initial Operator Licensing Examination Outline ML21361A245 ML21361A255 ML21361A256 ML21361A257 ML21361A258 ML21361A271 ML21361A273 ML21361A275
References
Download: ML21361A256 (16)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Byron Nuclear Generating Station Date of Exam: September 2021 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 3

3 6

2 1

1 1

2 2

2 9

2 2

4 Tier Totals 4

4 4

5 5

5 27 5

5 10

2.

Plant Systems 1

2 2

3 2

2 3

3 3

3 3

2 28 3

2 5

2 1

0 1

1 1

1 1

1 1

1 1

10 0

2 1

3 Tier Totals 3

2 4

3 3

4 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 3

2 2

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 03 EK2.03 - Knowledge of the interrelations between a reactor trip and the following: Reactor trip status panel.

(CFR: 41.7 / 45.7) 3.5 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 05 AK3.05 - Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident: ECCS termination or throttling criteria.

(CFR: 41.5, 10 / 45.6, 13) 4.0 2

000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 03 EA1.03 - Ability to operate and monitor the following as they apply to a Large Break LOCA: Securing of RCPs.

(CFR: 41.7 / 45.5, 6) 4.0 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 03 AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:

Increasing reactor building sump level.

(CFR: 43.5 / 45.13) 3.6 4

000026 (APE 26) Loss of Component Cooling Water / 8 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) 4.5 5

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Latent heat of vaporization/condensation.

(CFR: 41.8, 10 / 45.3) 2.6 6

000029 (EPE 29) Anticipated Transient Without Scram / 1 06 EK2.06 - Knowledge of the interrelations between the and the following an ATWS: Breakers, relays, and disconnects.

(CFR: 41.7 / 45.7) 2.9 7

000038 (EPE 38) Steam Generator Tube Rupture / 3 06 EK3.06 - Knowledge of the reasons for the following responses as they apply to the SGTR: Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures.

(CFR: 41.5, 10 / 45.6, 13) 4.2 8

000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 02 WE12 EA1.2 - Ability to operate and/or monitor the following as they apply to the (Uncontrolled Depressurization of all Steam Generators): Operating behavior characteristics of the facility.

(CFR: 41.7 / 45.5, 6) 3.6 9

000054 (APE 54; CE E06) Loss of Main Feedwater /4 02 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

Differentiation between loss of all MFW and trip of one MFW pump.

(CFR: 43.5 / 45.13) 4.1 10 000055 (EPE 55) Station Blackout / 6 04.

35 G2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects (CFR: 41.10 / 43.5 / 45.13) 3.8 11 000056 (APE 56) Loss of Offsite Power / 6 04 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power:

Definition of saturation conditions, implication for the systems.

(CFR: 41.8, 10 /45.3) 3.1 12 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.

(CFR: 41.5, 10 / 45.6, 13) 4.1 13 000058 (APE 58) Loss of DC Power / 6 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, 6) 2.9 14 000065 (APE 65) Loss of Instrument Air / 8 08 AA2.08 - Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Failure modes of air-operated equipment (CFR: 43.5 / 45.13) 2.9 15

ES-401 3

Form ES-401-2 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, indicators.

(CFR: 41.4, 5, 7, 10 / 45.8) 3.0 16 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 04.

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

(CFR: 41.10 / 45.3) 4.2 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 03 WE05 EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink)

(CFR: 41.8, 10 / 45.3) 3.9 18 K/A Category Totals:

3 3

3 3

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 000005 (APE 5) Inoperable/Stuck Control Rod / 1 01 AA1.01 - Ability to operate and/or monitor the following as they apply to the Inoperable / Stuck Control Rod: CRDS (CFR: 41.7 / 45.5, 6) 3.6 19 000024 (APE 24) Emergency Boration / 1 01 AA2.01 - Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions.

(CFR: 43.5 / 45.13) 3.8 20 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 02.

42 G2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

(CFR: 41.7, 10 / 43.2, 3 / 45.3) 3.9 21 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 02 AK1.02 - Knowledge of the operational implications of the following concepts as they apply to Steam Generator Tube Leak: Leak rate vs pressure drop.

(CFR: 41.8, 10 / 45.3) 3.5 22 000051 (APE 51) Loss of Condenser Vacuum / 4 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 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 23 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 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Containment Integrity: Guidance contained in EOP for loss of containment integrity.

(CFR: 41.5, 10 / 45.6, 13) 3.8 24 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 01 WE13 EA1.1 - Ability to operate and/or monitor the following as they apply to the (Steam Generator Overpressure): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5, 6) 3.1 25 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 01 WE16 EA2.1 - Ability to determine and interpret the following as they apply to the (High Containment Radiation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13) 2.9 26 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7

ES-401 5

Form ES-401-2 (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 (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 01.

25 G2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12) 3.9 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

1 2

2 2

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 K3.01 - Knowledge of the effect that a loss or malfunction of the RCPS will have on the following:

RCS (CFR: 41.7 / 45.6) 3.7 28 004 (SF1; SF2 CVCS) Chemical and Volume Control 14 20 K4.14 - Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following:

Control interlocks on letdown system (letdown tank bypass valve).

(CFR: 41.7)

K6.20 - Knowledge of the effect of a loss or malfunction on the following CVCS components:

Function of demineralizer, including boron loading and temperature limits.

(CFR: 41.7 / 45.7) 2.8 2.5 29 30 005 (SF4P RHR) Residual Heat Removal 09 K5.09 - Knowledge of the operational implications of the following concepts as they apply to RHRS:

Dilution and boration considerations.

(CFR: 41.5 / 45.7) 3.2 31 006 (SF2; SF3 ECCS) Emergency Core Cooling 01 12 K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the ECCS:

BIT/borated water sources.

(CFR: 41.7 / 45.7)

A1.12 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: RHR heatup limits.

(CFR: 41.5 / 45.5) 3.4 2.9 32 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: Maintaining quench tank pressure.

(CFR: 41.5 / 45.5) 2.7 34 008 (SF8 CCW) Component Cooling Water 05 A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated.

(CFR: 41.5 / 43.5 / 45.3, 13) 3.3 35 010 (SF3 PZR PCS) Pressurizer Pressure Control 02 A3.02 - Ability to monitor automatic operation of the PZR PCS, including PZR pressure.

(CFR: 41.7 / 45.5) 3.6 36 012 (SF7 RPS) Reactor Protection 04 A4.04 - Ability to manually operate and/or monitor in the control room: Bistable, trips, reset and test switches.

(CFR: 41.7 / 45.5 to 45.8) 3.3 37 013 (SF2 ESFAS) Engineered Safety Features Actuation 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 38 022 (SF5 CCS) Containment Cooling 01 02 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: SWS/cooling systems (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K3.02 - Knowledge of the effect that a loss or malfunction of the CCS will have on the following:

Containment instrumentation readings.

(CFR: 41.7 / 45.6) 3.5 3.0 39 40 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 02 K2.02 - Knowledge of bus power supplies to the following: MOVs.

(CFR: 41.7) 2.7 41 039 (SF4S MSS) Main and Reheat Steam 04 K3.04 - Knowledge of the effect that a loss or malfunction of the MRSS will have on the following:

MFW pumps.

(CFR: 41.7 / 45.6) 2.5 42

ES-401 7

Form ES-401-2 059 (SF4S MFW) Main Feedwater 16 03 K4.16 - Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:

Automatic trips for MFW pumps.

(CFR: 41.7)

A3.03 - Ability to monitor automatic operation of the MFW, including: Feedwater pump suction flow pressure.

(CFR: 41.7 / 45.5) 3.1 2.5 43 44 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 05 K5.05 - Knowledge of the operational implications of the following concepts as they apply to the AFW:

Feed line voiding and water hammer (CFR: 41.5 / 45.7) 2.7 45 062 (SF6 ED AC) AC Electrical Distribution 01 15 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating AC distribution system control including: Significance of D/G load limits (CFR: 41.5 / 45.5)

A2.15 - Ability to (a) predict the impacts of the following malfunctions or operations on the AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequence of paralleling out-of-phase/mismatch in volts (CFR: 41.5 / 43.5 / 45.3, 13) 3.4 2.8 46 47 063 (SF6 ED DC) DC Electrical Distribution 01 01 K2.01 - Knowledge of bus power supplies to the following: Major DC loads (CFR: 41.7)

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.

(CFR: 41.5 / 43.5 / 45.3, 13) 2.9 2.5 48 49 064 (SF6 EDG) Emergency Diesel Generator 07 K6.07 - Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers.

(CFR: 41.7 / 45.7) 2.7 50 073 (SF7 PRM) Process Radiation Monitoring 02 A4.02 - Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR: 41.7 / 45.5 to 45.8) 3.7 51 076 (SF4S SW) Service Water 02 A3.02 - Ability to monitor automatic operation of the SWS, including: Emergency heat loads.

(CFR: 41.7 / 45.5) 3.7 52 078 (SF8 IAS) Instrument Air 01.

30 G2.1.30 - Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7) 4.4 53 103 (SF5 CNT) Containment 08 03 K1.08 - Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: SIS, including actions of safety injection reset.

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

A4.03 - Ability to manually operate and/or monitor in the control room: ESF slave relays.

(CFR: 41.7 / 45.5 to 45.8) 3.6 2.7 54 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:

2 2

3 2

2 3

3 3

3 3

2 Group Point Total:

28

ES-401 8

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 47 K5.47 - Knowledge of the following operational implications as they apply to the CRDS: Factors affecting SUR: b-eff, l, p (CFR: 41.5 / 45.7) 2.9 56 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 03 K6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the PZR LCS: Relationship between PZR level and PZR heater control circuit.

(CFR: 41.7 / 45.7) 2.9 57 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 04 A1.04 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the NIS controls including:

Quadrant Power Tilt Ratio.

(CFR: 41.5 / 45.5) 3.5 58 016 (SF7 NNI) Nonnuclear Instrumentation 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 033 (SF8 SFPCS) Spent Fuel Pool Cooling 03 A2.03 - 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: Abnormal spent fuel pool water level or loss of water level (CFR: 41.5 / 43.5 / 45.3, 13) 3.1 59 034 (SF8 FHS) Fuel-Handling Equipment 02 A3.02 - Ability to monitor automatic operation of the Fuel Handling System, including: Load limits (CFR: 41.7 / 45.5) 2.5 60 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 06 A4.06 - Ability to manually operate and/or monitor in the control room: Turbine stop valves.

(CFR: 41.7 / 45.5 to 45.8) 2.8 61 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 01.

27 G2.1.27 - Knowledge of system purpose and/or function.

(CFR: 41.7) 3.9 62 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 04 K4.04 - Knowledge of design feature(s) and/or interlock(s) which provide for the following: Isolation of waste gas release tanks (CFR: 41.7) 2.9 63 072 (SF7 ARM) Area Radiation Monitoring 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 64 079 (SF8 SAS**) Station Air 01 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the SAS and the following systems: IAS.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.0 65

ES-401 9

Form ES-401-2 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:

1 0

1 1

1 1

1 1

1 1

1 Group Point Total:

10

ES-401 10 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 14 EA2.14 - Ability to determine and interpret the following as they apply to a small break LOCA: Actions to be taken if PTS limits are violated (CFR: 43.5 / 45.13) 4.4 76 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 08 AA2.08 - Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high bearing temperature.

(CFR: 43.5 / 45.13) 3.5 77 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 04.

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

(CFR: 41.10 / 43.5 / 45.3, 12) 4.3 78 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 000038 (EPE 38) Steam Generator Tube Rupture / 3 01.

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

(CFR: 41.10 / 43.5 / 45.12) 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 000058 (APE 58) Loss of DC Power / 6 03 AA2.03 - Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems.

(CFR: 43.5 / 45.13) 3.9 80 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 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, 13) 4.7 81 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4

ES-401 11 Form ES-401-2 K/A Category Totals:

3 3

Group Point Total:

6

ES-401 12 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 02.

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

(CFR: 41.7, 10 / 43.1 / 45.13) 4.5 82 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 02 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip.

(CFR: 43.5 / 45.13) 4.1 83 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 000074 (EPE 74; W E06 & E07)

Inadequate Core Cooling / 4 000076 (APE 76) High Reactor Coolant Activity / 9 02 AA2.02 - Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:

Corrective actions required for high fission product activity in RCS.

(CFR: 43.5 / 45.13) 3.4 85 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 02.

4.1 Knowledge of EOP entry conditions and immediate action steps.

4.8 84 (W E13) Steam Generator Overpressure / 4 (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 Cooldown Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4

ES-401 13 Form ES-401-2 (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 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 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: Pressure transient protection during cold shutdown.

(CFR: 41.5 / 43.5 / 45.3, 13) 3.7 86 006 (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 04.

30 G2.4.30 - 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.

(CFR: 41.10 / 43.5 / 45.11) 4.1 87 013 (SF2 ESFAS) Engineered Safety Features Actuation 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 08 A2.08 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray when it can be done.

(CFR: 41.5 / 43.5 / 45.3, 13) 3.7 88 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 07 A2.07 - 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: Air or MOV failure (CFR: 41.5 / 43.5 / 45.3, 13) 3.5 89 062 (SF6 ED AC) AC Electrical Distribution 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator 073 (SF7 PRM) Process Radiation Monitoring

ES-401 15 Form ES-401-2 076 (SF4S SW) Service Water 02.

12 G2.2.12 - Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13) 4.1 90 078 (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 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 03 A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of forced circulation (CFR: 41.5 / 43.5 / 45.3, 5) 4.3 91 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 02.

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

(CFR: 41.10 / 43.2, 5 / 45.3) 4.7 92 017 (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 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 02 A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam valve stuck open (CFR: 41.5 / 43.5 /45.3, 13) 3.9 93 045 (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