ML24026A163

BV1 Draft Submittal: Forms 3.2-1, 3.2-2, 3.3-1, 4.1 & 4.1-1

ML24026A163
Person / Time
Site:	Beaver Valley (DPR-066)
Issue date:	01/10/2023
From:	Energy Harbor Nuclear Generation LLC
To:	Todd Fish NRC/RGN-I/DORS/OB
References
EPID L-2023-OLL-0011
Download: ML24026A163 (1)

Text

ES-3.2, Page 11 of 18 Form 3.2-1 Administrative Topics Outline Facility:

Beaver Valley Unit 1 NRC Exam Date of Examination: 10/2/23-10/13/23 Examination Level:

RO SRO Operating Test Number: 1LOT23 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations (RO A1.1) 2.1.25 RO 3.9 Ability to interpret reference materials, such as graphs, curves, and tables (reference potential)

JPM 1AD-002 Calculating a Reactivity Change R, D Conduct of Operations (RO A1.2) 2.1.7 RO 4.4 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation JPM 1AD-055 Perform the Daily Heat Balance R, N Equipment Control (RO A2) 2.2.12 RO 3.7 Knowledge of surveillance procedures JPM 1AD-049 Complete Surveillance of RHS Pump R, D Radiation Control (RO A3) 2.3.12 RO 3.2 Knowledge of radiological safety principles and 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, or alignment of filters JPM 3AD-025 Perform a Stay Time Calculation R, D Emergency Plan

ES-3.2, Page 12 of 18 Form 3.2-1 Administrative Topics Outline Facility:

Beaver Valley Unit 1 NRC Exam Date of Examination: 10/2/23 - 10/13/23 Examination Level:

RO SRO Operating Test Number: 1LOT23 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations (SRO A 1.1) 2.1.3 SRO 3.9 Knowledge of shift or short-term relief turnover practices JPM 1AD-048 Determine Availability for Call-In (3 ROs) (SRO ONLY)

R, D Conduct of Operations (SRO A 1.2) 2.1.43 SRO 4.3 Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion JPM 1AD-019 Evaluate 1/M Data and Determine Required Actions (SRO Only)

R, D Equipment Control (SRO A 2) 2.2.41 SRO 3.9 Ability to obtain and interpret station electrical and mechanical drawings (reference potential)

JPM 1AD-039 Identify Isolation Boundary Points on Plant VOND, then determine diesel operability. (SRO Only)

R, D Radiation Control (SRO A 3) 2.3.14 SRO 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only)

JPM 1AD-038 Determine Emergency Exposure Limits (SRO ONLY)

R, M Emergency Plan (SRO A 4) 2.4.40 SRO 4.5 Knowledge of SRO responsibilities in emergency plan implementing procedures (SRO Only)

JPM 1AD-015 Complete Initial Notification Form for a General Emergency R, D

ES-3.2, Page 13 of 18 Instructions for completing Form 3.2-1, Administrative Topics Outline

1. For each license level, determine the number of administrative job performance measures (JPMs) and topic areas as follows:

• Reactor operator (RO) applicants do not need to be evaluated on every topic (i.e., Equipment Control, Radiation Control, or Emergency Plan can be omitted by doubling up on Conduct of Operations), unless the applicant is taking only the administrative topics portion of the operating test (with a waiver or excusal of the other portions).

2. Enter the associated knowledge and abilities (K/A) statement and summarize the administrative activities for each JPM.

3. For each JPM, specify the type codes for location and source as follows:

Location:

(C)ontrol room, (S)imulator, or Class(R)oom Source and Source Criteria:

(P)revious two NRC exams (no more than one JPM that is randomly selected from last two NRC exams)

(D)irect from bank (no more than three for ROs, no more than four for SROs and RO retakes)

(N)ew or Significantly (M)odified from bank (no fewer than one)

Topic Number of JPMs RO*

SRO and RO Retakes Conduct of Operations 1 (or 2) 2 Equipment Control 1 (or 0) 1 Radiation Control 1 (or 0) 1 Emergency Plan 1 (or 0) 1 Total 4

5

ES-3.2, Page 13 of 18 Form 3.2-2 Control Room/In-Plant Systems Outline Facility: Beaver Valley Unit 1 NRC Exam Date of Examination: 10/2/23 - 10/13/23 Operating Test Number: 1LOT23 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 RCS Dilution (1CR-589)

A, L, N 1

S2 Place Excess Letdown in Service (1CR-056)

D 2

S3 Drain SIS Accumulator A (Low Pressure Alarm Received)

(1CR-659)

A, D, EN, L 3

S4 Establish RHR System Flow (1CR-062)

D, L 4P S5 Respond to High PRT Temperature (High PRT Level Alarm Received during Spray Down)

(1CR-661)

A, D 5

S6 X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent occurs and EDG auto actions fail to occur)

(1CR-660)

A, D 6

S7 Verify CREVS Actuation (1CR-662)

A, D, L 9

S8 Restore RCP CCR Cooling Following CIB (1CR-155)

D, L 8

In-Plant Systems P1 Respond to Spent Fuel Pool Low Level Alarm (1PL-074)

D, E, R 8

P2 Turbine Pedestal Mechanical Overspeed Trip Test (1PL-153)

D 4S P3 Start #1 DG from SSPS (1PL-178)

N 6

ES-3.2, Page 14 of 18 Form 3.2-2 Control Room/In-Plant Systems Outline Facility: Beaver Valley Unit 1 NRC Exam Date of Examination: 10/2/23 - 10/13/23 Operating Test Number: 1LOT23 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 RCS Dilution (1CR-589)

A, L, N 1

S2 Place Excess Letdown in Service (1CR-056)

D 2

S3 Drain SIS Accumulator A (Low Pressure Alarm Received)

(1CR-659)

A, L, D, EN 3

S4 S5 Respond to High PRT Temperature (High PRT Level Alarm Received during Spray Down)

(1CR-661)

A, D 5

S6 X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent occurs and EDG auto actions fail to occur)

(1CR-660)

A, D 6

S7 Verify CREVS Actuation (1CR-662)

A, D, L 9

S8 Restore RCP CCR Cooling Following CIB (1CR-155)

D, L 8

In-Plant Systems P1 Respond to Spent Fuel Pool Low Level Alarm (1PL-074)

D, E, R 8

P2 Turbine Pedestal Mechanical Overspeed Trip Test (1PL-153)

D 4S P3 Start #1 DG from SSPS (1PL-178)

N 6

ES-3.2, Page 15 of 18 Form 3.2-2 Control Room/In-Plant Systems Outline Facility: Beaver Valley Unit 1 NRC Exam Date of Examination: 10/2/23 - 10/13/23 Operating Test Number: 1LOT23 Exam Level:

RO SRO-I SRO-U System/JPM Title Type Code Safety Function Control Room Systems S1 RCS Dilution (1CR-589)

A, L, N 1

S2 S3 Drain SIS Accumulator A (Low Pressure Alarm Received)

(1CR-659)

A, D, EN, L 3

S4 S5 S6 S7 S8 In-Plant Systems P1 Respond to Spent Fuel Pool Low Level Alarm (1PL-074)

D, E, R 8

P2 Turbine Pedestal Mechanical Overspeed Trip Test (1PL-153)

D 4S P3 Start #1 DG from SSPS (1PL-178)

N 6

ES-3.2, Page 16 of 18 Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline

1. Determine the number of control room system and in-plant system job performance measures (JPMs) to develop using the following table:

License Level Control Room In-Plant Total Reactor Operator (RO) 8 3

11 Senior Reactor Operator-Instant (SRO-I) 7 3

10 Senior Reactor Operator-Upgrade (SRO-U) 2 or 3 3 or 2 5

2. Select safety functions and systems for each JPM as follows:

Refer to Section 1.9 of the applicable knowledge and abilities (K/A) catalog for the plant systems organized by safety function. For pressurized-water reactor operating tests, the primary and secondary systems listed under Safety Function 4, Heat Removal from Reactor Core, in Section 1.9 of the applicable K/A catalog, may be treated as separate safety functions (i.e., two systems, one primary and one secondary, may be selected from Safety Function 4). From the safety function groupings identified in the K/A catalog, select the appropriate number of plant systems by safety functions to be evaluated based on the applicants license level (see the table in step 1).

For RO/SRO-I applicants: Each of the control room system JPMs and, separately, each of the in-plant system JPMs must evaluate a different safety function, and the same system or evolution cannot be used to evaluate more than one safety function in each location. One of the control room system JPMs must be an engineered safety feature.

For SRO-U applicants: Evaluate SRO-U applicants on five different safety functions.

One of the control room system JPMs must be an engineered safety feature, and the same system or evolution cannot be used to evaluate more than one safety function.

3. Select a task for each JPM that supports, either directly or indirectly and in a meaningful way, the successful fulfillment of the associated safety function. Select the task from the applicable K/A catalog (K/As for plant systems or emergency and abnormal plant evolutions) or the facility licensees site-specific task list. If this task has an associated K/A, the K/A should have an importance rating of at least 2.5 in the RO column. K/As that have importance ratings of less than 2.5 may be used if justified based on plant priorities; inform the NRC chief examiner if selecting K/As with an importance rating less than 2.5.

The selected tasks must be different from the events and evolutions conducted during the simulator operating test and tasks tested on the written examination. A task that is similar to a simulator scenario event may be acceptable if the actions required to complete the task are significantly different from those required in response to the scenario event.

Apply the following specific task selection criteria:

ES-3.2, Page 17 of 18 Form 3.2-2 Instructions for Control Room/In-Plant Systems Outline (continued)

At least one of the tasks shall be related to a shutdown or low-power condition.

Four to six of the tasks for RO and SRO-I applicants shall require execution of alternative paths within the facility licensees operating procedures. Two to three of the tasks for SRO-U applicants shall require execution of alternative paths within the facility licensees operating procedures.

At least one alternate path JPM must be new or modified from the bank.

At least one of the tasks conducted in the plant shall evaluate the applicants ability to implement actions required during an emergency or abnormal condition.

At least one of the tasks conducted in the plant shall require the applicant to enter the radiologically controlled area. This provides an excellent opportunity for the applicant to discuss or demonstrate radiation control administrative subjects.

If it is not possible to develop or locate a suitable task for a selected system, return to step 2 and select a different system.

4. For each JPM, specify the codes for type, source, and location:

Code License Level Criteria RO SRO-I SRO-U (A)lternate path 4-6 4-6 2-3 (C)ontrol room (D)irect from bank 9

8 4

(E)mergency or abnormal in-plant 1

1 1

(EN)gineered safety feature (for control room system) 1 1

1 (L)ow power/shutdown 1

1 1

(N)ew or (M)odified from bank (must apply to at least one alternate path JPM) 2 2

1 (P)revious two exams (randomly selected) 3 3

2 (R)adiologically controlled area 1

1 1

(S)imulator

Form 3.3-1 Scenario Outline NUREG-1021, Revision 12 Energy Harbor Facsimile Rev. draft Facility:

BVPS Unit 1 Source:

NEW Scenario No. 1 Op Test No.:

1LOT23 NRC Examiners:

Candidates:

SRO ATC BOP Initial Conditions:

IC-160(15): 48% steady state operations MOL, Bank D - 164 steps, RCS boron - 1220 ppm Charging pump 1CH-P-1B in service.

Turnover:

Due to an oil leak, 1CC-P-3A needs to be removed from service.

IAW 1OM-28.4.B part E, Startup 1CC-P-3B and Shutdown 1CC-P-3A.

DLCo is performing Preventative maintenance tasks in the Switchyard.

PCV-1RC-455D isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks:

1. CT-22 (ECA-0.0.A) - Manually close PORV

2. CT-23 (ECA-0.0.B) - Establish Feedwater flow

3. CT-25 (ECA-0.0.F) - Starts RPRW pump before EDG failure Event No.

Malf. No.

Event Type Event Description 1

N/A (N) BOP, SRO Swap inservice CCT pumps. (1OM-28.4.B, part E) 2 XMT-MSS035A (I,A, MC) BOP, SRO A SG, selected Main steam flow transmitter, 1MS-FT-474 fails low, requires manual control of feedwater and placing alternate channel in service.

3 SIS05B (C,A) ATC, SRO (TS) SRO Charging pump 1CH-P-1B spurious trip.

4 TUR01 CRF02A EPS19 (C,A) BOP, SRO (TS) SRO (R) ATC Spurious turbine trip with auto rod insertion failure and auto open failure of Exciter circuit breaker, ACB-41.

5 EPS001 EPS11A EPS11B (M) All A loss of offsite power after Stm dumps in Stm Press mode OR Rx power is < 13%,

1. 1 EDG autostart failure (trips on overspeed on start)

1. 2 EDG catastrophic failure 90 seconds after EDG start.

6 PRS12 PRS03A (C) ATC, SRO Master pressure controller fails, causing PORV 455C to fail at 37% open., closes on Manual close signal.

7 INH20 INH21 (C,MC) BOP, SRO 1FW-P-2 fails to auto start, TDAFWP steam supply valves TV-1MS-105A and B fail to auto open. Manual opening to start the pump is successful 8

INH32 (C.MC) ATC, SRO 1WR-P-1A fails to autostart on sequencer, Manual start successful.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control, (A)bnormal E-0 ECA-0.0

Form 3.3-1 Scenario Outline NUREG-1021, Revision 12 Energy Harbor Facsimile Rev. draft Facility:

BVPS Unit 1 Source:

NEW Scenario No. 2 Op Test No.:

1LOT23 NRC Examiners:

Candidates:

SRO ATC BOP Initial Conditions:

IC-161 (IC-15): ~52% MOL, S/U in progress. Bank D @ 170, RCS Boron at 1215 ppm.

Turnover:

Power escalation in progress, startup 1FW-P-1B and continue to raise power to 100% IAW 1OM-52.4.B.

DLCo is performing Preventative maintenance tasks in the Switchyard.

PCV-1RC-455D isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks:

1. CT-10 (E-0.M) - Close PORV Block valve

2. CT-13 (E-0.Q) - Crew manually trips turbine

3. CT-33 (ECA-2.1.A) - Crew controls AFW flow to not < 50gpm/SG.

Event No.

Malf. No.

Event Type Event Description 1

N/A (N) BOP, SRO Startup of 1FW-P-1B IAW 1OM-24.4.D.

2 N/A (R) BOP (N) ATC, SRO Normal power increase to 100% IAW 1OM-52.4.B.

3 XMT-CHS012A (I,A,MC) ATC, SRO VCT Level transmitter, LT-1CH-112 fails high.

4 AUX13G (C,A) BOP, SRO (TS) SRO VS-F-4A spurious trip, requires BOP to start VS-F-4B.

5 PRS08D PRS04C (I, A) ATC, SRO (TS) SRO PT-1RC-445 drifts high, PORV PCV-1RC-456 OPENS and fails to reseat after lifting, requires closing MOV Block valve, MOV-1RC-536.

6 MSS18B (M) All B SG Fault outside CNMT requires Rx trip and safety injection.

7 INH48 (C) BOP, SRO Automatic Turbine Trip failure.

8 INH40 (C,MC) ATC, SRO CH-P-1B fails to auto start on SI signal.

9 MSS18A,B,C (M) All Steamline isolation causes faults on the A and C steam generators outside CNMT in the MSVR.

10 VLV-MSS21,22,23 (C,MC) BOP, SRO TV-1MS-111A,B,C fail to close on MSLI signal.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control, (A)bnormal E-0 E-2 ECA-2.1

Form 3.3-1 Scenario Outline NUREG-1021, Revision 12 Energy Harbor Facsimile Rev. draft Facility:

BVPS Unit 1 Source:

NEW Scenario No. 3 Op Test No.:

1LOT23 NRC Examiners:

Candidates:

SRO ATC BOP Initial Conditions:

IC 162(5): ~4.7% power, BOL, Xe increasing, CB D @ 110 steps, RCS boron - 1440 ppm.

Turnover:

Continue power increase IAW reactivity plan and commence turbine roll.

After Mode 1 is achieved, place 1LO-M-9B inservice IAW 1OM-26.4.D, part D DLCo is performing Preventative maintenance tasks in the Switchyard.

PCV-1RC-455D isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks:

1. CT-3 (E-0.E) - Actuate minimum CNMT cooling

2. CT-12 (E-0.P) - Manually Actuate Main Steam Line Isolation

3. CT-17 (E-2.A) - Isolates faulted SG.

Event No.

Malf. No.

Event Type Event Description 1

N/A (R) ATC (N) SRO Normal power increase to 15% IAW 1OM-52.4.B.

2 X06i030L (C,A,MC) ATC, SRO Blender fails to stop after dilution.

3 N/A (N) BOP, SRO S/U B EHC pp, 1LO-M-9B, IAW 1OM-26.4.D, part D 4

XMT-CNS007A (TS) SRO RWST level channel fails low, LT-1QS-100A.

5 FWM08A (C,A,MC) BOP, SRO A Bypass feed regulating valve fails in Auto. Requires manual.

6 PRS06A (I,A) ATC, SRO (TS) SRO LT-1RC-459 drifts high, requires ATC to place alternate channel in service.

7 CRF04BS CRF04BP (C) ATC, SRO (TS) SRO 2 Control Bank D dropped rods (F6 and B8)- requires Manual Rx trip.

8 FWM03C 1.5E6 (M) ALL Large Feedline leak inside CNMT on C SG.

9 INH51 (C,MC) BOP, SRO Main Steam Line Automatic Isolation Failure.

10 INH50 (C,MC) ATC, SRO CIB Auto Actuation failure.

11 VLV-SGB01,02, 03 (C) BOP, SRO SG Blowdown Isolation failure.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control, (A)bnormal E-0 E-2 ES-1.1

Form 3.3-1 Scenario Outline NUREG-1021, Revision 12 Energy Harbor Facsimile Rev. draft Facility:

BVPS Unit 1 Source:

NEW Scenario No. 4 Op Test No.:

1LOT23 NRC Examiners:

Candidates:

SRO ATC BOP Initial Conditions:

IC-163 (18): 100% power, MOL, Equilibrium Xe Conditions, CB D @ 227 steps, RCS boron - 1080 ppm.

Turnover:

Maintain stable plant conditions.

DLCo is performing Preventative maintenance tasks in the Switchyard.

PCV-1RC-455D isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks:

1. CT-50 (FR-S.1.A) - Isolates Main Turbine from SGs

2. CT-51 (FR-S.1.B) - Start AFW pumps

3. CT-52 (FR-S.1.C) - Insert negative reactivity Event No.

Malf. No.

Event Type Event Description 1

NIS03D (I,A) ATC, SRO (TS) SRO N44 fails high, control rods auto insert. (AOP 1.1.3) 2 N/A (N) BOP, SRO N44 removal from service. (AOP 1.2.1C) 3 AUX02A (C,A,MC) BOP, SRO A Station air compressor trips, B fails to auto start -

BOP manually starts B air compressor, Diesel Air compressor fails to auto start but will start locally. (AOP 1.34.1) 4 RCS02A (C,A) ATC, SRO (TS) SRO 35 GPM RCS leak, "A" Loop, unisolable (AOP 1.6.7) 5 N/A (R) ATC (C,A) BOP, SRO Management orders plant S/D @ 5%/min. due to RCS leakage. (AOP 1.51.1) 6 SIS08 CRF12A (M) ALL Spurious safety injection signal with automatic reactor trip failure.

7 CRF12B CRF02A (M) ALL Failure of manual Reactor Trip from the control room requires entry into FR-S.1. Auto control rod insertion failure requires manual rod insertion.

8 TUR04D to 15 TUR06B to 100 (C) BOP, SRO Turbine TV #2 and GV #4 fail to close, requires manual MSIV closure.

9 INH20, INH21 INH35, INH36 (C) BOP, SRO All Aux Feedwater pumps fail to automatically start, requires BOP to start AFW pumps.

10 INH37 INH38 (C) ATC, SRO LHSI pumps fail to start on SI, requires ATC to start LHSI pumps.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control, (A)bnormal E-0 FR-S.1 E-0 E-1 ES-1.2

Form 4.1-PWR Pressurized-Water Reactor Examination Outline Page 1 Notes: CO = Conduct of Operations; EC = Equipment Control; RC = Radiation Control; EM = Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan Facility: Beaver Valley Unit 1 Date of Exam: 10/2/20223 - 10/13/2023 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 2

1 2

1 8

2 2

4 Tier Totals 4

4 5

4 5

4 26 5

5 10

2.

Plant Systems 1

3 1

2 3

3 3

3 3

3 2

2 28 2

3 5

2 1

1 1

1 1

1 0

1 0

1 1

9 0

2 1

3 Tier Totals 4

2 3

4 4

4 3

4 3

3 3

37 4

4 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

2 2

1 2

4. Theory Reactor Theory Thermodynamics 6

3 3

Form 4.1-PWR PWR Examination Outline Page 2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR 000007 (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X

(000007EK3.06) Knowledge of the reasons for the following responses and/or actions as they apply to (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY (CFR: 41.5 / 41.10 / 45.6 / 45.13):

Stopping an RCP 3.5 1

000008 (APE 8) Pressurizer Vapor Space Accident X (000008) (APE 8) Pressurizer Vapor Space Accident (G2.4.18)

EMERGENCY PROCEDURES/PLAN: Knowledge of the specific bases for emergency and abnormal operating procedures (CFR:

41.10 / 43.1 / 45.13) 4.0 76 000009 (EPE 9) Small Break LOCA X

(000009EA1.16) Ability to operate and/or monitor the following as they apply to (EPE 9) SMALL-Break LOCA (CFR: 41.5 / 41.7 / 45.5 to 45.8): SCM monitors 3.8 2

00001) (EPE 11) Large Break LOCA X

(000011EK2.05) Knowledge of the relationship between (EPE 11)

LARGE-Break LOCA and the following systems or components (CFR:

41.8 / 41.10 / 45.3): ECCS 4.3 3

000015 (APE 15) Reactor Coolant Pump Malfunctions X

(000015AA2.09) Ability to determine and/or interpret the following as they apply to (APE 15) REACTOR COOLANT Pump Malfunctions (CFR: 41.10 / 43.5 / 45.13): RCP high stator temperature 3.4 77 000022 (APE 22) Loss of Reactor Coolant Makeup X

(000022AK2.08) Knowledge of the relationship between (APE 22)

LOSS OF REACTOR Coolant Makeup and the following systems or components (CFR: 41.8 / 41.10 / 45.3): RCS 3.8 4

000025 (APE 25) Loss of Residual Heat Removal System X

(000025AK3.06) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 25) LOSS OF RESIDUAL Heat Removal System (CFR: 41.5 / 41.10 / 45.6 / 45.13): Start an RHR pump 3.8 5

000026 (APE 26) Loss of Component Cooling Water X

(000026AA2.02) Ability to determine and/or interpret the following as they apply to (APE 26) LOSS OF Component Cooling Water (CFR:

41.10 / 43.5 / 45.13): The cause of possible CCW loss 3.6 6

000027 (APE 27)

Pressurizer Pressure Control System Malfunction X (000027) (APE 27) Pressurizer Pressure Control System Malfunction (G2.1.17) CONDUCT OF OPERATIONS: Ability to make accurate, clear, and concise verbal reports (CFR: 41.10 /

45.12 / 45.13) 4.0 78 000029 (EPE 29)

Anticipated Transient Without Scram X

(000029EA1.22) Ability to operate and/or monitor the following as they apply to (EPE 29) ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) (CFR: 41.5 / 41.7 / 45.5 to 45.8): RPS 4.1 7

000038 (EPE 38) Steam Generator Tube Rupture X (000038) (EPE 38) Steam Generator Tube Rupture (G2.4.31)

EMERGENCY PROCEDURES/PLAN: Knowledge of annunciator alarms, indications, or response procedures (CFR: 41.10 / 45.3) 4.2 8

000040 (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer X (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture -

Excessive Heat Transfer (G2.1.38) CONDUCT OF OPERATIONS:

Knowledge of the stations requirements for verbal communications when implementing procedures (CFR: 41.10 / 45.13) 3.7 9

000054 (APE 54; CE E06) Loss of Main Feedwater X

(000054AK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 54) LOSS OF Main Feedwater (CFR: 41.5 / 41.7 / 45.7 /

45.8): RCS parameters on a complete loss of feedwater (all S/Gs dried out) 3.9 10 000055 (EPE 55) Station Blackout X

(000055EA1.02) Ability to operate and/or monitor the following as they apply to (EPE 55) Station Blackout (CFR: 41.5 / 41.7 / 45.5 to 45.8):

Manual EDG start 4.3 11 000056 (APE 56) Loss of Offsite Power X (000056) (APE 56) Loss of Offsite Power (G2.4.47) EMERGENCY PROCEDURES/PLAN: Ability to diagnose and recognize trends in an accurate and timely manner using the appropriate control room reference material (reference potential) (CFR: 41.10 / 43.5 / 45.12) 4.2 12 000057 (APE 57)

Loss of Vital AC Instrument Bus X

(000057AK2.10) Knowledge of the relationship between (APE 57)

LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS and the following systems or components (CFR: 41.8 / 41.10 / 45.3): ESFAS 4.4 13 000057 (APE 57)

Loss of Vital AC Instrument Bus X

(000057AA2.09) Ability to determine and/or interpret the following as they apply to (APE 57) LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS (CFR: 41.10 / 43.5 / 45.13): T-ave.

and T-ref.

3.8 79 000058 (APE 58) Loss of DC Power X

(000058AK3.02) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 58) LOSS OF DC Power (CFR:

41.5 / 41.10 / 45.6 / 45.13): Actions contained in AOPs or EOPs for loss of DC power 4.1 14

Form 4.1-PWR PWR Examination Outline Page 3 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR 000062 (APE 62) Loss of Nuclear Service Water X

(000062AA2.07) Ability to determine and/or interpret the following as they apply to (APE 62) LOSS OF SERVICE WATER (CFR: 41.10

/ 43.5 / 45.13): Implementation of TS requirements for loss of service water 4.0 80 000065 (APE 65) Loss of Instrument Air X

(000065AK1.03) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 65) LOSS OF Instrument Air (CFR: 41.5 / 41.7 / 45.7 / 45.8):

Failure modes of air-operated equipment 3.7 15 000077 (APE 77) Generator Voltage and Electric Grid Disturbances X

(000077AA2.09) Ability to determine and/or interpret the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.10 / 43.5 / 45.13): Status of EDGs 4.0 16 (W E04) LOCA Outside Containment X

(WE04EA2.03) Ability to determine and/or interpret the following as they apply to (W E04) LOCA Outside Containment (CFR: 41.10 / 43.5

/ 45.13): RCS pressure 3.9 17 (W E11) Loss of Emergency Coolant Recirculation X (W E11) Loss of Emergency Coolant Recirculation (G2.4.14)

EMERGENCY PROCEDURES/PLAN: Knowledge of general guidelines for emergency and abnormal operating procedures usage (CFR: 41.10 / 43.1 / 45.13) 4.5 81 (BW E04; W E05) Inadequate Heat Transfer - Loss of Secondary Heat Sink X

(WE05EK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (W E05) Loss of Secondary Heat Sink (CFR: 41.5 / 41.7 / 45.7 /

45.8): Total feed flow less than minimum AFW requirement due to operator action 3.9 18 K/A Category Totals:

3 3

3 3 3/3 3/3 Group Point Total:

18/6

Form 4.1-PWR PWR Examination Outline Page 4 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR 000001 (APE 1)

Continuous Rod Withdrawal 000003 (APE 3) Dropped Control Rod 000005 (APE 5)

Inoperable/Stuck Control Rod 000024 (APE 24)

Emergency Boration 000028 (APE 28)

Pressurizer (PZR) Level Control Malfunction X

(000028AK3.01) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 28) PRESSURIZER (PZR) Level Control Malfunction (CFR: 41.5 / 41.10 / 45.6 / 45.13): Relationship between the letdown flow rate and capacity rating of orifices 3.2 19 000032 (APE 32) Loss of Source Range Nuclear Instrumentation 000033 (APE33) Loss of Intermediate Range Nuclear Instrumentation 000036 (APE 36; BW/A08)

Fuel-Handling Incidents X

(000036AK1.03) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 36) FUEL HANDLING INCIDENTS (CFR: 41.5 / 41.7 / 45.7 /

45.8): Indications of approaching criticality 3.9 20 000037 (APE 37) Steam Generator Tube Leak X (000037) (APE 37) Steam Generator Tube Leak (G2.4.51)

EMERGENCY PROCEDURES/PLAN: Knowledge of emergency operating procedure exit conditions (e.g., emergency condition no longer exists or severe accident guideline entry is required) (CFR:

41.10 / 43.5 /45.13) 3.0 21 000051 (APE51) Loss of Condenser Vacuum 000059 (APE 59) Accidental Liquid Radwaste Release X

(000059AK2.04) Knowledge of the relationship between (APE 59)

ACCIDENTAL LIQUID Radwaste Release and the following systems or components (CFR: 41.8 / 41.10 / 45.3): Liquid radwaste flow instruments 3.2 22 000060 (APE 60) Accidental Gaseous Radwaste Release X

(000060AA2.01) Ability to determine and/or interpret the following as they apply to (APE 60) ACCIDENTAL GASEOUS Radwaste Release (CFR: 41.10 / 43.5 / 45.13): A radiation-level alarm indicating whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a spike), inclu 3.4 82 000067 (APE 67) Plant Fire On Site X

(000067AK3.02) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 67) PLANT Fire On Site (CFR:

41.5 / 41.10 / 45.6 / 45.13): Steps called out in the site fire protection plan, FPS manual, and fire zone manual 3.3 23 000068 (APE 68; BW A06)

Control Room Evacuation X

(000068AA2.01) Ability to determine and/or interpret the following as they apply to (APE 68) Control Room Evacuation (CFR: 41.10 / 43.5 /

45.13): S/G level 4.1 24 000069 (APE 69; W E14) Loss of Containment Integrity 000074 (EPE 74; W E06 &

E07) Inadequate Core Cooling X

(000074EA2.08) Ability to determine and/or interpret the following as they apply to (EPE 74) Inadequate Core Cooling (CFR: 41.10 / 43.5 /

45.13): ITM and/or RCS pressure 4.1 25 000074 (EPE 74; W E06 &

E07) Inadequate Core Cooling X (000074) Inadequate Core Cooling (G2.1.6) CONDUCT OF OPERATIONS: Ability to manage the control room crew during plant transients (SRO Only) (CFR: 43.5 / 45.12 / 45.13) 4.8 83 000076 (APE 76) High Reactor Coolant Activity 000078 (APE 78*) RCS Leak X

(000078AA2.10) Ability to determine and/or interpret the following as they apply to (APE 78) REACTOR COOLANT SYSTEM LEAK (CFR: 41.10 / 43.5 / 45.13): Leak rate from change in various tank levels 3.6 84 (W E01 & E02) Rediagnosis &

SI Termination (W E13) Steam Generator Overpressure

Form 4.1-PWR PWR Examination Outline Page 5 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 E/APE # / Name K1 K2 K3 A1 A2 G K/A Topic(s)

IR (W E15) Containment Flooding X (W E15) Containment Flooding (G2.4.3) EMERGENCY PROCEDURES/PLAN: Ability to identify post-accident instrumentation (CFR: 41.6 / 45.4) 3.9 85 (W E16) High Containment Radiation X

(WE16EA1.06) Ability to operate and/or monitor the following as they apply to (W E16) HIGH Containment Radiation (CFR: 41.5 / 41.7 /

45.5 to 45.8): ARM system 3.4 26 K/A Category Point Totals:

1 1

2 1 2/2 1/2 Group Point Total:

8/4

Form 4.1-PWR PWR Examination Outline Page 6 Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 003 (SF4P RCP)

REACTOR COOLANT PUMP SYSTEM X

(003K3.02) Knowledge of the effect that a loss or malfunction of the (SF4P RCP) REACTOR COOLANT PUMP SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4): S/G 3.9 27 003 (SF4P RCP)

REACTOR COOLANT PUMP SYSTEM X (003) (SF4P RCP) REACTOR COOLANT PUMP SYSTEM (G2.4.21) EMERGENCY PROCEDURES/PLAN: Knowledge of the parameters and logic used to assess the status of emergency operating procedures critical safety functions or shutdown critical safety functions (CFR: 41.7 / 43.5 / 45.12) 4.6 86 004 (SF1; SF2 CVCS)

CHEMICAL AND VOLUME CONTROL SYSTEM X

(004K2.03) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF1; SF2 CVCS)

CHEMICAL AND VOLUME CONTROL SYSTEM Charging pumps 3.9 28 005 (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM X

(005A4.02) Ability to manually operate and/or monitor the (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): RHR heat exchanger temperature/bypass control valves 3.9 29 005 (SF4P RHR)

RESIDUAL HEAT REMOVAL SYSTEM X (005) (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM (G2.1.36) CONDUCT OF OPERATIONS:

Knowledge of procedures and limitations involved in core alterations (CFR: 41.10 / 43.6 / 45.7) 4.1 87 006 (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM X

(006K4.26) Knowledge of (SF2; SF3 ECCS)

EMERGENCY CORE COOLING SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): Parallel redundant systems 3.4 30 007 (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

(007K4.03) Knowledge of (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): Nitrogen cover gas 2.7 31 007 (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM X

(007K5.09) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 PRTS)

PRESSURIZER RELIEF/QUENCH TANK SYSTEM (CFR: 41.5 / 45.3): Effects of rupture disc rupture on containment parameters 3.7 32 008 (SF8 CCW)

COMPONENT COOLING WATER SYSTEM X

(008A1.03) Ability to predict and/or monitor changes in parameters associated with operation of the (SF8 CCW) COMPONENT COOLING WATER SYSTEM, including (CFR: 41.5 / 45.5): CCW pressure 3.1 33 008 (SF8 CCW)

COMPONENT COOLING WATER SYSTEM X

(008A3.02) Ability to monitor automatic features of the (SF8 CCW) COMPONENT COOLING WATER SYSTEM, including (CFR: 41.7 / 45.7): Operation of the CCW pumps, including interlocks 3.7 34 010 (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM X

(010A3.04) Ability to monitor automatic features of the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM, including (CFR: 41.7 / 45.7):

PZR normal spray valve operation 3.6 35 010 (SF3 PZR PCS)

PRESSURIZER PRESSURE CONTROL SYSTEM X

(010A2.08) Ability to (a) predict the impacts of the following on the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): Safety valves failure to reseat 3.9 88 012 (SF7 RPS) REACTOR PROTECTION SYSTEM X

(012A3.07) Ability to monitor automatic features of the (SF7 RPS) REACTOR PROTECTION SYSTEM, including (CFR: 41.7 / 45.7): Trip breakers 4.1 36 012 (SF7 RPS) REACTOR PROTECTION SYSTEM X

(012K1.03) Knowledge of the physical connections and/or cause and effect relationships between the (SF7 RPS) REACTOR PROTECTION SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8): CRDS 4.1 37

Form 4.1-PWR PWR Examination Outline Page 7 Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 013 (SF2 ESFAS)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X

(013A2.10) Ability to (a) predict the impacts of the following on the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): Feedline break 3.5 38 022 (SF5 CCS)

CONTAINMENT COOLING SYSTEM X

(022A1.05) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 CCS) CONTAINMENT COOLING SYSTEM, including (CFR: 41.5 / 45.5): Lights and alarms 3.3 39 025 (SF5 ICE) ICE CONDENSER SYSTEM 026 (SF5 CSS)

CONTAINMENT SPRAY SYSTEM X

(026K3.01) Knowledge of the effect that a loss or malfunction of the (SF5 CSS) CONTAINMENT SPRAY SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4): CCS 3.8 40 039 (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM X

(039A2.06) Ability to (a) predict the impacts of the following on the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR:

41.5 / 45.6): Atmospheric relief valve malfunctions 4.2 41 039 (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM X

(039K1.10) Knowledge of the physical connections and/or cause and effect relationships between the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8): Auxiliary steam system 2.7 42 059 (SF4S MFW) MAIN FEEDWATER SYSTEM X

(059K6.21) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4S MFW) MAIN FEEDWATER SYSTEM (CFR: 41.7 / 45.7): MFW pump lube oil pumps 2.9 43 059 (SF4S MFW) MAIN FEEDWATER SYSTEM X (059) (SF4S MFW) MAIN FEEDWATER SYSTEM (G2.2.43) EQUIPMENT CONTROL: Knowledge of the process used to track inoperable alarms (CFR:

41.10 / 43.5 / 45.13) 3.3 89 061 (SF4S AFW) AUXILIARY /

EMERGENCY FEEDWATER SYSTEM X

(061K1.06) Knowledge of the physical connections and/or cause and effect relationships between the (SF4S AFW) AUXILIARY/EMERGENCY FEEDWATER SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8): Cooling water for AFW components 3.4 44 062 (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM X

(062K6.02) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM (CFR: 41.7 / 45.7):

Breakers, relays, and disconnects 3.4 45 063 (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM X (063) (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM (191008K1.09) BREAKERS, RELAYS, AND DISCONNECTS (CFR: 41.7): Effect of racking out breakers on control and indicating circuits and removal of control power on breaker operation 3.1 46 064 (SF6 EDG)

EMERGENCY DIESEL GENERATOR SYSTEM X (064) (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (G2.2.6) EQUIPMENT CONTROL: Knowledge of the process for making changes to procedures (CFR: 41.10 / 43.3 / 45.13) 3.0 47 064 (SF6 EDG)

EMERGENCY DIESEL GENERATOR SYSTEM X

(064A2.30) Ability to (a) predict the impacts of the following on the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): EDG output breaker failure 4.0 90 073 (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM X

(073A4.03) Ability to manually operate and/or monitor the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM in the control room (CFR:

41.7 / 45.5 to 45.8): Check source for operability demonstration 2.9 48

Form 4.1-PWR PWR Examination Outline Page 8 Plant SystemsTier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s)

IR 073 (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM X

(073K4.02) Knowledge of (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM design features and/or interlocks that provide for the following (CFR:

41.7): System actuations based on PRM signals 3.7 49 076 (SF4S SW) SERVICE WATER SYSTEM X

(076A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4S SW) SERVICE WATER SYSTEM, including (CFR:

41.5 / 45.5): Reactor and turbine building CCW temperatures 3.2 50 076 (SF4S SW) SERVICE WATER SYSTEM X

(076A2.06) Ability to (a) predict the impacts of the following on the (SF4S SW) SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR:

41.5 / 45.6): Pump and/or motor failure 3.9 51 078 (SF8 IAS) INSTRUMENT AIR SYSTEM X

(078K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8 IAS)

INSTRUMENT AIR SYSTEM (CFR: 41.5 / 45.3): Loss of instrument air 3.9 52 103 (SF5 CNT)

CONTAINMENT SYSTEM X

(103K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 CNT)

CONTAINMENT SYSTEM (CFR: 41.5 / 45.3):

Hydrogen concentration inside containment 3.5 53 103 (SF5 CNT)

CONTAINMENT SYSTEM X

(103K6.15) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF5 CNT) CONTAINMENT SYSTEM (CFR: 41.7 / 45.7): MRSS 3.1 54 K/A Category Point Totals:

3 1

2 3

3 3

3 3/2 3 2 2/3 Group Point Total:

28/5

Form 4.1-PWR PWR Examination Outline Page 9 Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K / A T o p i c ( s )

IR 001 (SF1 CRDS) CONTROL ROD DRIVE SYSTEM 002 (SF2; SF4P RCS)

REACTOR COOLANT SYSTEM X (002) (SF2; SF4P RCS) REACTOR COOLANT SYSTEM (G2.1.31) CONDUCT OF OPERATIONS:

Ability to locate control room switches, controls, and indications and to determine whether they correctly reflect the desired plant lineup (CFR: 41.10 / 45.12) 4.6 55 011 (SF2 PZR LCS)

PRESSURIZER LEVEL CONTROL SYSTEM 014 (SF1 RPI) ROD POSITION INDICATION SYSTEM X

(014A2.03) Ability to (a) predict the impacts of the following on the (SF1 RPI) ROD POSITION INDICATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 to 41.7 / 43.5 / 43.6 / 45.3 /

45.12 / 45.13): Dropped rod 4.0 91 015 (SF7 NI) NUCLEAR INSTRUMENTATION SYSTEM X

(015K6.10) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF7 NI) NUCLEAR INSTRUMENTATION SYSTEM (CFR: 41.7 / 45.7):

T-cold RTD 3.1 56 016 (SF7 NNI)

NONNUCLEAR INSTRUMENTATION SYSTEM 017 (SF7 ITM) IN-CORE TEMPERATURE MONITORING SYSTEM 027 (SF5 CIRS)

CONTAINMENT IODINE REMOVAL SYSTEM X

(027K1.01) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CIRS) CONTAINMENT IODINE REMOVAL SYSTEM and the following systems (CFR: 41.7 to 41.9 / 45.7 / 45.8): CCS 3.2 57 028 (SF5 HRPS)

HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM 029 (SF8 CPS)

CONTAINMENT PURGE SYSTEM 033 (SF8 SFPCS) SPENT FUEL POOL COOLING SYSTEM 034 (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM X

(034A4.06) Ability to manually operate and/or monitor the (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM in the control room (CFR:

41.7 / 45.5 to 45.8): Fuel transfer system operation 2.6 58 035 (SF4P SG) STEAM GENERATOR SYSTEM 041 (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X

(041A2.02) Ability to (a) predict the impacts of the following on the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): Steam valve stuck open 3.8 92 045 (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM X

(045A2.12) Ability to (a) predict the impacts of the following on the (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): Control rod insertion limits exceeded (stabilize secondary) 3.0 59 055 (SF4S CARS)

CONDENSER AIR REMOVAL SYSTEM

Form 4.1-PWR PWR Examination Outline Page 10 Plant SystemsTier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K / A T o p i c ( s )

IR 056 (SF4S CDS)

CONDENSATE SYSTEM 068 (SF9 LRS) LIQUID RADWASTE SYSTEM X

(068K5.07) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF9 LRS)

LIQUID RADWASTE SYSTEM (CFR: 41.5 / 45.3):

Loss of secondary mixing water system 2.6 60 071 (SF9 WGS)

WASTE GAS DISPOSAL SYSTEM X

(071K3.04) Knowledge of the effect that a loss or malfunction of the (SF9 WGS) WASTE GAS DISPOSAL SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4):

PVS 2.8 61 072 (SF7 ARM)

AREA RADIATION MONITORING SYSTEM 075 (SF8 CW) CIRCULATING WATER SYSTEM X

(075K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF8 CW)

CIRCULATING WATER SYSTEM Circulating water 2.8 62 079 (SF8 SAS**) STATION AIR SYSTEM 086 (SF8 FPS) FIRE PROTECTION SYSTEM X

(086K4.07) Knowledge of (SF8 FPS) FIRE PROTECTION SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):

Protection of plant areas and equipment 3.3 63 050 (SF9 CRV*) CONTROL ROOM VENTILATION SYSTEM X (050) (SF9 CRV*) CONTROL ROOM VENTILATION (G2.1.32) CONDUCT OF OPERATIONS: Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 / 43.2 / 45.12) 4.0 93 K/A Category Point Totals:

1 1

1 1

1 1

0 1/2 0 1 1/1 Group Point Total:

9/3

Form 4.1-COMMON Common Examination Outline Page 1 Facility: Beaver Valley Unit 1 Date of Exam: 10/2/2023 - 10/13/2023 Generic Knowledge and AbilitiesTier 3 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations G2.1.18 (G2.1.18) CONDUCT OF OPERATIONS: Ability to make accurate, clear, and concise logs, records, status boards, and reports (CFR:

41.10 / 45.12 / 45.13) 3.6 64 G2.1.45 (G2.1.45) CONDUCT OF OPERATIONS: Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7 / 43.5 / 45.4) 4.3 65 G2.1.20 (G2.1.20) CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) 4.6 94 G2.1.43 (G2.1.43) CONDUCT OF OPERATIONS: Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion (CFR: 41.10 / 43.6

/ 45.6) 4.3 95 Subtotal N/A 2

N/A

2.

Equipment Control G2.2.13 (G2.2.13) EQUIPMENT CONTROL: Knowledge of tagging and clearance procedures (CFR: 41.10 / 43.1 / 45.13) 4.1 66 G2.2.39 (G2.2.39) EQUIPMENT CONTROL: Knowledge of less than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS action statements (does not include action statements of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less that follow the expiration of a completion time for a TS condition for which an action statement has already been entered)

(CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.9 67 G2.2.12 (G2.2.12) EQUIPMENT CONTROL: Knowledge of surveillance procedures (CFR: 41.10 / 43.2 / 45.13) 4.1 96 G2.2.15 (G2.2.15) EQUIPMENT CONTROL: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups, or tagouts (reference potential) (CFR: 41.10 / 43.3 / 45.13) 4.3 97 Subtotal N/A 2

N/A

3.

Radiation Control G2.3.14 (G2.3.14) RADIATION CONTROL: Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) (CFR: 43.4 / 45.10) 3.8 68 G2.3.11 (G2.3.11) RADIATION CONTROL: Ability to control radiation releases (CFR: 41.11 / 43.4 / 45.10) 4.3 98 Subtotal N/A 1

N/A

4.

Emergency Procedures/

Plan G2.4.28 (G2.4.28) EMERGENCY PROCEDURES/PLAN: Knowledge of procedures relating to a security event (ensure that the test item includes no safeguards information) (CFR: 41.10 / 43.5 / 45.13) 3.2 69 G2.4.2 (G2.4.2) EMERGENCY PROCEDURES/PLAN: Knowledge of system setpoints, interlocks, and automatic actions associated with emergency and abnormal operating procedure entry conditions (CFR: 41.7 / 45.7 / 45.8) 4.6 99 G2.4.25 (G2.4.25) EMERGENCY PROCEDURES/PLAN: Knowledge of fire protection procedures (CFR: 41.10 / 43.5 / 45.13) 3.7 100 Subtotal N/A 1

N/A Tier 3 Point Total 6

7 TheoryTier 4 Category K/A #

Topic RO IR Reactor Theory 192006 (192006K1.12) FISSION PRODUCT POISONS (CFR: 41.1): Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 versus time for the following: - reactor trip 3.1 70 192007 (192007K1.01) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1): Define burnable poison and state its use in the reactor 2.5 71

192008 (192008K1.10) REACTOR OPERATIONAL PHYSICS (CFR: 41.1): (CRITICALITY)

Describe reactor power and startup rate response once criticality is reached 3.4 72 Subtotal N/A 3

Thermodynamics 193003 (193003K1.14) STEAM (CFR: 41.14): Define the following term: -- superheated vapor 2.5 73 193004 (193004K1.15) THERMODYNAMIC PROCESS (CFR: 41.14): (THROTTLING AND THE THROTTLING PROCESS) Determine the exit conditions for a throttling process based on the use of steam and/or water 2.8 74 193009 (193009K1.05) CORE THERMAL LIMITS (CFR: 41.14): State why thermal limits are necessary.

3.5 75 Subtotal N/A 3

Tier 4 Point Total 6

Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.

Tier/Group Randomly Selected K/A Reason for Rejection T1/G1 000011 EK2.07 Question 3; Unable to write a discriminatory question related to Large Break LOCA and RHR.

EK2.05, ECCS was re-selected.

T1/G2 000074 EA2.05 Question 25; Requested reselection due to overlap with question 84 which tests determining the size of an RCS leak by monitoring the VCT level.

EA2.08, ITM and/or RCS pressure was re-selected.

T1/G2 WE16 EA1.04 Question 26; Unable to write a valid question because the Containment ventilation isolation is prevented by plant procedures at Beaver Valley during plant shutdown.

EA1.06, ARM system was re-selected.

T2/G1 063 191004 K1.15 Question 46; Unable to write a question regarding the relationship between flow from a pump and suction heads for centrifugal pumps tied to the DC Distribution system.

191008 K1.09, Breakers, Relays, and disconnects was re-selected.

T2/G1 076 A1.08 Question 50; Unable to write a discriminatory question regarding Strainer D/P in the Service Water system.

A1.02, Reactor and turbine building CCW temperatures was re-selected.

T2/G1 076 A2.06 Question 51, Unable to write a discriminatory question for Service water controller and positioner failure due to lack of relevant controllers/positioners in the system.

A2.03, Pump and/or motor failure was re-selected.

T2/G1 078 K5.04 Question 52; Unable to write a discriminatory question related to high moisture content in instrument air due to a low level of difficulty.

K5.03, Loss of Instrument Air was re-selected.

T2/G1 103 K6.14 Question 54; Hydrogen recombiner and purge control system is abandoned in place at Beaver Valley.

K6.15, MRSS was re-selected.

T2/G2 027 A1.01 Question 57; Unable to write a question related to Filter temperature because there are no filters associated with the Containment Iodine Removal system at Beaver Valley.

K/A 027 K1.01, CSS was re-selected due to there being no other A1 K/As to select from.

Tier/Group Randomly Selected K/A Reason for Rejection T4 192006 K1.01 Question 70; Reselected K/A due to overlap with question 71 also related to fuel/Rx poisons.

K1.12, was re-selected.

T1/G1 000008 2.4.4 Question 76; Unable to write a discriminatory question at the SRO level for entry-level conditions for emergency and abnormal operating procedures.

2.4.18, was re-selected.

T1/G2 000061 2.1.47 Question 83; Unable to write a discriminatory question at the SRO level for 2.1.47, and Radiation Monitoring was over sampled on the exam.

New system and K/A (000074 2.1.6) were re-selected.

T2/G2 028 A2.03 Question 91; H2 recombiner is retired in place at Beaver valley.

New system (014) was re-selected. K/A A2.03 was kept as the K/A.