ML23206A151

2A-3, Exam Administrative Items (Delayed Release), Browns Ferry 2022-301

ML23206A151
Person / Time
Site:	Browns Ferry
Issue date:	07/25/2023
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
Download: ML23206A151 (1)

Text

Form 3.2-1 Administrative Topics Outline ILT 2204 RO ADMIN JPMS Page 1 of 3 Facility Browns Ferry NPP Date of Examination: 5/16/22 Examination Level: RO SRO Operating Test Number: 22-04 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code*

(Step 3)

Conduct of Operations JPM 556 Drywell Leakage Calculation R, M K/A 2.1.7 (RO 4.4)

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

Conduct of Operations JPM 661 Determine Adequate Performance of License Reactivation R, D K/A 2.1.4 (RO 3.3)

Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10 CFR Part 55 Equipment Control JPM 680 Perform 2-SR-3.4.2.1, Jet Pump Mismatch and Operability R, M K/A 2.2.12 (RO 3.7)

Knowledge of surveillance procedures Radiation Control JPM 682 Review a Radiological Work Permit (RWP)

R, P K/A 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.

Emergency Plan N/A N/A ML23206A151

Form 3.2-1 Administrative Topics Outline ILT 2204 RO ADMIN JPMS Page 2 of 3 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:

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

• 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)

Form 3.2-1 Administrative Topics Outline ILT 2204 RO ADMIN JPMS Page 3 of 3 Reactor Operator

1. Conduct of Ops - Drywell Leakage Calculation Using 2-SR-2, Instrument Checks and Observations, and given Floor and Equipment Drain readings calculates leak rates and determines if leak rates are acceptable in accordance with Technical Specifications.

K/A 2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, Reactor behavior, and instrument interpretation. (RO 4.4)

2. Conduct of Ops - Determine Adequate Performance of License Reactivation Using OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions and a provided table determines which Unit Operator has performed the necessary steps to reactivate their license.

K/A 2.1.4: Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10 CFR Part 55. (RO 3.3)

3. Equipment Control - Perform 2-SR-3.4.2.1, Jet Pump Mismatch and Operability Given plant conditions, determine if Jet Pump flow mismatch meets Technical Specification requirements in accordance with 2-SR-3.4.2.1, Jet Pump Mismatch and Operability.

K/A 2.2.12 Knowledge of surveillance procedures. (RO 3.7)

4. Radiation Control - Review a Radiological Work Permit (RWP)

Given an RWP and dose rates for a task to be performed, calculate the expected dose to determine if the task can or cannot be performed in accordance with NPG-SPP-05.18, Radiation Work Permits.

K/A 2.3.12: 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. (RO 3.2)

5. Emergency Plan - N/A

Form 3.2-1 Administrative Topics Outline ILT 2204 SRO ADMIN JPMS Page 1 of 3 Facility Browns Ferry NPP Date of Examination: 5/16/22 Examination Level: RO SRO Operating Test Number: 22-04 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code*

(Step 3)

Conduct of Operations JPM 556 Drywell Leakage Calculation R, M K/A 2.1.7 (SRO 4.7)

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

Conduct of Operations JPM 753 Determine Protected Equipment Requirements R, N K/A 2.1.39 (SRO 4.3)

Knowledge of conservative decision-making practices Equipment Control JPM 746 Review Power Availability Surveillance R, M K/A 2.2.37 (SRO 4.6)

Ability to determine operability or availability of safety-related equipment Radiation Control JPM 749 Determine ACTIONS required to allow releases in accordance with 0-ODCM-001, OFFSITE DOSE CALCULATION MANUAL R, P K/A 2.3.11 (SRO 4.3)

Ability to control radiation releases Emergency Plan JPM 752 Emergency Action Level Classification R, N K/A 2.4.41 (SRO 4.6)

Knowledge of the Emergency Action Level thresholds and Classifications

Form 3.2-1 Administrative Topics Outline ILT 2204 SRO ADMIN JPMS Page 2 of 3 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:

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

• 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)

Form 3.2-1 Administrative Topics Outline ILT 2204 SRO ADMIN JPMS Page 3 of 3 Senior Reactor Operator

1. Conduct of Ops - Drywell Leakage Calculation Using 2-SR-2, Instrument Checks and Observations, and given Floor and Equipment Drain readings calculates leak rates and determines if leak rates are acceptable and if any Technical Specification action(s) must be taken.

K/A 2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, Reactor behavior, and instrument interpretation. (SRO 4.7)

2. Conduct of Ops - Determine Protected Equipment Requirements Given an abnormal plant equipment configuration, uses ODM-4.18, Protected Equipment and NPG-SPP-07.3.4, Protected Equipment to determine the proper administrative barrier(s) to guard against inadvertently rendering equipment important to plant safety inoperable.

K/A 2.1.39: Knowledge of conservative decision-making practices. (SRO 4.3)

3. Equipment Control - Review Power Availability Surveillance Given a completed Surveillance Requirement, 3-SR-3.8.7.1 Monthly Check of Power Availability to Required AC and DC Power Distribution Subsystems, determines that an Acceptance Criteria (AC) step was not met and required Technical Specification actions.

K/A 2.2.37 Ability to determine operability or availability of safety-related equipment (SRO 4.6)

4. Radiation Control - Determine ACTIONS required to allow releases in accordance with 0-ODCM-001, OFFSITE DOSE CALCULATION MANUAL Given that an exhaust radiation monitor is taken out of service for maintenance, determine the governing procedure and determine what ACTIONS must be taken to allow continued releases via the affected pathway.

K/A 2.3.11: Ability to control radiation releases (SRO 4.3)

5. Emergency Plan - Emergency Action Level Classification (3.1-G)

Given plant conditions uses EPIP-1, Emergency Classification Procedure classifies an event and fills out the required notification form.

K/A 2.4.41: Knowledge of the emergency action level thresholds and classifications.

(SRO 4.6)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 1 of 7 Facility:

Browns Ferry NPP Date of Examination:

5/16/22 Exam Level: RO SRO-I SRO-U Operating Test No.:

22-04 Control Room Systems System / JPM Title Type Code Safety Function

a. JPM 708A Inject Boron during an ATWS per EOI-Appendix-3A, SLC Injection A, D, EN, S 1

b. JPM 751A Align RCIC Suction to the Suppression Pool per EOI-Appendix-5C, Injection System Lineup RCIC A, L, N, S 2

c. JPM 627A Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode A, D, EN, L, S 4

d. JPM 750 Vent the Drywell per OI-64, Primary Containment System EN, N, S 5

e. JPM 725 Transfer C 4KV Unit Board from the Start Bus to The USST Per 0-OI-57A, Switchyard And 4160V AC Electrical System D, P, S 6

f. JPM 290A Perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test A, D, EN, P, S 7

g. JPM 39 Align Containment Atmosphere Dilution to Drywell Control Air per EOI-Appendix-8G, Crosstie CAD to Drywell Control Air D, L, S 8

h. JPM 55A Emergency Vent Primary Containment per EOI Appendix-13, Emergency Venting Primary Containment A, D, EN, L, S 9

In-Plant Systems

i. JPM 754 Align Components per AOI-100-2, Control Room Abandonment, Attachment 3, Part B E, L, N, R 6

j. JPM 314 Defeat ARI Logic Trips per EOI Appendix-2, Defeating ARI Logic Trips D, E, L 7

k. JPM 755 Bypass HPCI High Temperature Isolation per EOI Appendix-16L, Bypassing HPCI High Temperature Isolation E, L, N 2

Form 3.2-2 Control Room/In-Plant Systems Outline Page 2 of 7

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:

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.

Form 3.2-2 Control Room/In-Plant Systems Outline Page 3 of 7

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 3.2-2 Control Room/In-Plant Systems Outline Page 4 of 7 Reactor Operator Job Performance Measures

a.

JPM 708A

Title:

Inject Boron during an ATWS per EOI Appendix-3A, SLC Injection

==

Description:==

The candidate will inject Standby Liquid Control (SLC) in accordance with EOI Appendix 3A. When an SLC Pump is started, Reactor Water Cleanup (RWCU) will fail to isolate and the RWCU Pumps will fail to trip. The candidate will manually isolate RWCU and verify the RWCU Pumps are tripped.

K/A:

211000 Standby Liquid Control System A1.08; Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: RWCU system lineup (3.9)

b.

JPM 751A

Title:

Align RCIC Suction to the Suppression Pool per EOI EOI-Appendix-5C, Injection System Lineup RCIC

==

Description:==

The candidate will switch RCIC suction sources in accordance with EOI-Appendix-5C. The RCIC Condensate Storage Tank (CST) Suction Valve (FCV-71-19) will not automatically close, requiring candidate action to close the valve.

K/A 217000 RCIC Reactor Core Isolation Cooling A4.03; Ability to manually operate and/or monitor in the Control Room: System Valves (3.8)

c. JPM 627A

Title:

Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode

==

Description:==

The candidate will place HPCI in Pressure Control in accordance EOI-Appendix-11C. When HPCI is in Reactor Pressure Control mode, a steam leak will develop and HPCI Steam Valves will fail to isolate. The candidate will manually close the HPCI Steam Valves.

K/A 206000 HPCI High-Pressure Coolant Injection System (BWR 2, 3, 4)

A2.10; Ability to (a) predict the impacts of the following on the High-Pressure Coolant Injection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System isolation (4.7)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 5 of 7

d. JPM 750

Title:

Vent the Drywell per OI-64, Primary Containment Systems

==

Description:==

The candidate will vent the Drywell in accordance with OI-64, Primary Containment Systems in order to reduce Drywell Pressure.

K/A 223001 PCS Primary Containment System and Auxiliaries A2.07; Ability to (a) predict the impacts of the following on the Primary Containment System and Auxiliaries and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High Drywell Pressure (4.4)

e. JPM 725

Title:

Transfer C 4KV Unit Board from the Start Bus to The USST In Accordance With 0-OI-57A, Switchyard And 4160V AC Electrical System

==

Description:==

The candidate will transfer C 4KV Unit Board from the Start Bus to the USST in accordance with 0-OI-57A, Switchyard and 4160V AC Electrical System.

K/A 262001 A.C. Electrical Distribution A4.01: Ability to manually operate and/or monitor in the Control Room: Breakers and disconnects (3.7)

f. JPM 290A

Title:

Perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test

==

Description:==

The candidate will perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test. When Reactor Protection System (RPS) B is tested, two (2) Control Rods will SCRAM, requiring the candidate to insert a manual Reactor SCRAM.

K/A 212000 Reactor Protection System A1.04: Ability to predict and/or monitor changes in parameters associated with operation of the Reactor Protection System, including: RPS Bus Status (3.7)

g. JPM 39

Title:

Align CAD to Drywell Control Air per EOI Appendix-8G, Crosstie CAD to Drywell Control Air

==

Description:==

The candidate will cross tie CAD to Drywell Control Air in accordance with EOI Appendix 8G.

K/A 295019 Partial or Complete Loss of Instrument Air AA1.01: Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Backup air supply (3.4)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 6 of 7

h. JPM 55A

Title:

Emergency Vent Primary Containment per EOI-Appendix-13, Emergency Venting Primary Containment

==

Description:==

The candidate will emergency vent Primary Containment in accordance with EOI-Appendix-13. The Suppression Chamber vent lineup will fail, and an alternate vent method must be used.

K/A 288000 PVS Plant Ventilation Systems A2.01; Ability to (a) predict the impacts of the following on the Plant Ventilation Systems and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High Drywell Pressure (3.5)

i. JPM 754

Title:

Align Components per AOI-100-2, Control Room Abandonment,, Part B

==

Description:==

The candidate will perform field operations necessary to align breakers on switchboards as required during Control Room Abandonment in accordance with AOI-100-2, Control Room Abandonment, Attachment 3, Part B.

K/A 295016 Control Room Abandonment AA1.04; Ability to operate and/or monitor the following as they apply to Control Room Abandonment: AC Electrical Distribution. (3.6)

j.

JPM 314

Title:

Perform EOI-Appendix-2, Defeating ARI Logic Trips

==

Description:==

The candidate will perform field operations necessary to defeat Alternate Rod Insertion (ARI) trips in accordance with EOI-Appendix-2, Defeating ARI Logic Trips.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.01; Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Reactor protection system. (4.2)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 7 of 7

k. JPM 755

Title:

Perform 1-EOI-APPENDIX-16L, Bypassing HPCI High Temperature Isolation

==

Description:==

The candidate will perform field operations necessary to bypass High-Pressure Coolant Injection (HPCI) high temperature isolation signals in accordance with EOI-Appendix-16L, Bypassing HPCI High Temperature Isolation.

K/A 206000 HPCI High-Pressure Coolant Injection System A2.10; Ability to (a) predict the impacts of the following on the High-Pressure Coolant Injection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System isolation.

Form 3.2-2 Control Room/In-Plant Systems Outline Page 1 of 7 Facility:

Browns Ferry NPP Date of Examination:

5/16/22 Exam Level: RO SRO-I SRO-U Operating Test No.:

22-04 Control Room Systems System / JPM Title Type Code*

Safety Function

a. JPM 708A Inject Boron during an ATWS per EOI-Appendix-3A, SLC Injection A, D, EN, S 1

b. JPM 751A Align RCIC Suction to the Suppression Pool per EOI-Appendix-5C, Injection System Lineup RCIC A, L, N, S 2

c. JPM 627A Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode A, D, EN, L, S 4

d. JPM 750 Vent the Drywell per OI-64, Primary Containment System EN, N, S 5

e. JPM 725 Transfer C 4KV Unit Board from the Start Bus to The USST Per 0-OI-57A, Switchyard And 4160V AC Electrical System D, P, S 6

f. JPM 290A Perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test A, D, EN, P, S 7

g. N/A

h. JPM 55A Emergency Vent Primary Containment per EOI Appendix-13, Emergency Venting Primary Containment A, D, EN, L, S 9

In-Plant Systems

i. JPM 754 Align Components per AOI-100-2, Control Room Abandonment, Attachment 3, Part B E, L, N, R 6

j. JPM 314 Defeat ARI Logic Trips per EOI Appendix-2, Defeating ARI Logic Trips D, E, L 7

k. JPM 755 Bypass HPCI High Temperature Isolation per EOI Appendix-16L, Bypassing HPCI High Temperature Isolation E, L, N 2

Form 3.2-2 Control Room/In-Plant Systems Outline Page 2 of 7

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:

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.

Form 3.2-2 Control Room/In-Plant Systems Outline Page 3 of 7

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 3.2-2 Control Room/In-Plant Systems Outline Page 4 of 7 Senior Reactor Operator (Instant)

Job Performance Measures

a.

JPM 708A

Title:

Inject Boron during an ATWS per EOI Appendix-3A, SLC Injection

==

Description:==

The candidate will inject Standby Liquid Control (SLC) in accordance with EOI Appendix 3A. When an SLC Pump is started, Reactor Water Cleanup (RWCU) will fail to isolate and the RWCU Pumps will fail to trip. The candidate will manually isolate RWCU and verify the RWCU Pumps are tripped.

K/A:

211000 Standby Liquid Control System A1.08; Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: RWCU system lineup (3.9)

b.

JPM 751

Title:

Align RCIC Suction to the Suppression Pool per EOI EOI-Appendix-5C, Injection System Lineup RCIC

==

Description:==

The candidate will switch RCIC suction sources in accordance with EOI-Appendix-5C. The RCIC Condensate Storage Tank (CST) Suction Valve (FCV-71-19) will not automatically close, requiring candidate action to close the valve.

K/A 217000 RCIC Reactor Core Isolation Cooling A4.03; Ability to manually operate and/or monitor in the Control Room: System Valves (3.8)

c. JPM 627A

Title:

Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode

==

Description:==

The candidate will place HPCI in pressure Control in accordance EOI-Appendix-11C. When HPCI is in Reactor Pressure Control mode, a steam leak will develop and HPCI Steam Valves will fail to isolate. The candidate will manually close the HPCI Steam Valves.

K/A 206000 HPCI High-Pressure Coolant Injection System (BWR 2, 3, 4)

A2.10; Ability to (a) predict the impacts of the following on the High-Pressure Coolant Injection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System isolation (4.0)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 5 of 7

d. JPM 750

Title:

Vent the Drywell per OI-64, Primary Containment Systems

==

Description:==

The candidate will vent the Drywell in accordance with OI-64, Primary Containment Systems in order to reduce Drywell Pressure.

K/A 223001 PCS Primary Containment System and Auxiliaries A2.07; Ability to (a) predict the impacts of the following on the Primary Containment System and Auxiliaries and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High Drywell Pressure (4.3)

e. JPM 725

Title:

Transfer C 4KV Unit Board from the Start Bus to The USST In Accordance With 0-OI-57A, Switchyard And 4160V AC Electrical System

==

Description:==

The candidate will transfer C 4KV Unit Board from the Start Bus to the USST in accordance with 0-OI-57A, Switchyard and 4160V AC Electrical System.

K/A 262001 A.C. Electrical Distribution A4.01: Ability to manually operate and/or monitor in the Control Room: Breakers and disconnects (3.7)

f. JPM 290A

Title:

Perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test

==

Description:==

The candidate will perform SR-3.3.1.1.8(11), Reactor Protection System Manual SCRAM Functional Test. When Reactor Protection System (RPS) B is tested, two (2) Control Rods will SCRAM, requiring the candidate to insert a manual Reactor SCRAM.

K/A 212000 Reactor Protection System A1.04: Ability to predict and/or monitor changes in parameters associated with operation of the Reactor Protection System, including: RPS Bus Status (3.7)

g. N/A

Form 3.2-2 Control Room/In-Plant Systems Outline Page 6 of 7

h. JPM 55A

Title:

Emergency Vent Primary Containment per EOI-Appendix-13, Emergency Venting Primary Containment

==

Description:==

The candidate will emergency vent Primary Containment in accordance with EOI-Appendix-13. The Suppression Chamber vent lineup will fail, and an alternate vent method must be used.

K/A 288000 PVS Plant Ventilation Systems A2.01; Ability to (a) predict the impacts of the following on the Plant Ventilation Systems and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High Drywell Pressure (3.6)

i. JPM 754

Title:

Align Components per AOI-100-2, Control Room Abandonment,, Part B

==

Description:==

The candidate will perform field operations necessary to align breakers on switchboards as required during Control Room Abandonment in accordance with AOI-100-2, Control Room Abandonment, Attachment 3, Part B.

K/A 295016 Control Room Abandonment AA1.04; Ability to operate and/or monitor the following as they apply to Control Room Abandonment: AC Electrical Distribution. (3.6)

j.

JPM 314

Title:

Perform EOI-Appendix-2, Defeating ARI Logic Trips

==

Description:==

The candidate will perform field operations necessary to defeat Alternate Rod Insertion (ARI) trips in accordance with EOI-Appendix-2, Defeating ARI Logic Trips.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.01; Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Reactor protection system. (4.2)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 7 of 7

k. JPM 755

Title:

Perform 1-EOI-APPENDIX-16L, Bypassing HPCI High Temperature Isolation

==

Description:==

The candidate will perform field operations necessary to bypass High-Pressure Coolant Injection (HPCI) high temperature isolation signals in accordance with EOI-Appendix-16L, Bypassing HPCI High Temperature Isolation.

K/A 206000 HPCI High-Pressure Coolant Injection System A2.10; Ability to (a) predict the impacts of the following on the High-Pressure Coolant Injection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System isolation. (4.0)

Form 3.2-2 Control Room/In-Plant Systems Outline Page 1 of 5 Facility:

Browns Ferry NPP Date of Examination:

5/16/22 Exam Level: RO SRO-I SRO-U Operating Test No.:

22-04 Control Room Systems: @ 8 for RO, 7 for SRO-I, 2 or 3 for SRO-U, including 1 ESF System / JPM Title Type Code*

Safety Function

a. JPM 708A Inject Boron during an ATWS per EOI-Appendix-3A, SLC Injection A, D, EN, S 1

b. JPM 751A Align RCIC Suction to the Suppression Pool per EOI-Appendix-5C, Injection System Lineup RCIC A, L, N, S 2

c. JPM 627A Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode A, D, EN, L, S 4

d. N/A

e. N/A

f. N/A

g. N/A

h. N/A In-Plant Systems: @ 3 for RO, 3 for SRO-I, 3 or 2 for SRO-U

i. JPM 754 Align Components per AOI-100-2, Control Room Abandonment, Attachment 3, Part B E, L, N, R 6

j. JPM 314 Defeat ARI Logic Trips per EOI Appendix-2, Defeating ARI Logic Trips D, E, L 7

k. N/A

Form 3.2-2 Control Room/In-Plant Systems Outline Page 2 of 5

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:

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.

Form 3.2-2 Control Room/In-Plant Systems Outline Page 3 of 5

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 3.2-2 Control Room/In-Plant Systems Outline Page 4 of 5 Senior Reactor Operator (Upgrade)

Job Performance Measures

a.

JPM 708A

Title:

Inject Boron during an ATWS per EOI Appendix-3A, SLC Injection

==

Description:==

The candidate will inject Standby Liquid Control (SLC) in accordance with EOI Appendix 3A. When an SLC Pump is started, Reactor Water Cleanup (RWCU) will fail to isolate and the RWCU Pumps will fail to trip. The candidate will manually isolate RWCU and verify the RWCU Pumps are tripped.

K/A:

211000 Standby Liquid Control System A1.08; Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: RWCU system lineup (3.9)

b.

JPM 751A

Title:

Align RCIC Suction to the Suppression Pool per EOI EOI-Appendix-5C, Injection System Lineup RCIC

==

Description:==

The candidate will switch RCIC suction sources in accordance with EOI-Appendix-5C. The RCIC Condensate Storage Tank (CST) Suction Valve (FCV-71-19) will not automatically close, requiring candidate action to close the valve.

K/A 217000 RCIC Reactor Core Isolation Cooling A4.03: Ability to manually operate and/or monitor in the Control Room: System Valves (3.8)

c. JPM 627A

Title:

Place HPCI in Reactor Pressure Control per EOI-Appendix-11C, Alternate RPV Pressure Control Systems HPCI Test Mode

==

Description:==

The candidate will place HPCI in pressure Control in accordance EOI-Appendix-11C. When HPCI is in Reactor Pressure Control mode, a steam leak will develop and HPCI Steam Valves will fail to isolate. The candidate will manually close the HPCI Steam Valves.

K/A 206000 HPCI High-Pressure Coolant Injection System (BWR 2, 3, 4)

A2.10: Ability to (a) predict the impacts of the following on the High-Pressure Coolant Injection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System isolation (4.0)

d. N/A

e. N/A

f. N/A

Form 3.2-2 Control Room/In-Plant Systems Outline Page 5 of 5

g. N/A

h. N/A

i. JPM 754

Title:

Align Components per AOI-100-2, Control Room Abandonment,, Part B

==

Description:==

The candidate will perform field operations necessary to align breakers on switchboards as required during Control Room Abandonment in accordance with AOI-100-2, Control Room Abandonment, Attachment 3, Part B.

K/A 295016 Control Room Abandonment AA1.04; Ability to operate and/or monitor the following as they apply to Control Room Abandonment: AC Electrical Distribution. (3.6)

j.

JPM 314

Title:

Perform EOI-Appendix-2, Defeating ARI Logic Trips

==

Description:==

The candidate will perform field operations necessary to defeat Alternate Rod Insertion (ARI) trips in accordance with EOI-Appendix-2, Defeating ARI Logic Trips.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.01; Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Reactor protection system. (4.2)

k. N/A

Form 3.4-1 A

E P

V P

E L

N I

T C

A T

N Y

T P

S A

B S

A B

S A

B S

A B

E R

T O

R T

O R

T O

R T

O O

C P

O C

P O

C P

O C

P R

I U

RO RX 1

6 6

2 0

NOR 2

1 1

2 1

SRO-I I/C 5,7,8 3,4b,8 3,4,8 6

2 MAJ 6

7 7

2 1

SRO-U MC 0

0 1

TS 3,4 2,5 2,5 4

2 RO RX 1

6 6

2 0

NOR 2

1 1

2 1

SRO-I I/C 5,7,8 3,4b,8 3,4,8 6

2 MAJ 6

7 7

2 1

SRO-U MC 0

0 2

TS 3,4 2,5 2,5 4

2 RO RX 1

5 2

1 NOR 1

1 1

SRO-I I/C 5,7 2,4,7,9, 10 7

4 1

MAJ 6

8 2

2 SRO-U MC 5,7 2

1 TS 3,6 2

2 RO RX 1

5 2

1 NOR 1

1 1

SRO-I I/C 5,7 2,4,7,9, 10 7

4 2

MAJ 6

8 2

2 SRO-U MC 5,7 2

1 TS 3,6 2

2 RO RX 1

5 2

1 NOR 2

1 1

2 1

SRO-I I/C 5,7,8 2,6,10 3,4b,8 5,8 9

4 3

MAJ 6

8 7

7 3

2 SRO-U MC 2,10 3,4b 5

4 1

TS 3,4 2

2 RO RX 1

5 6

6 3

1 NOR 1

1 1

2 1

SRO-I I/C 5,7 2,4,7,9, 10 3,4b,8 3,4,8 10 4

4 MAJ 6

8 7

7 3

2 SRO-U MC 5,7 2

1 TS 3,6 2,5 2,5 4

2 RO RX 5

1 1

1 NOR 1

1 1

1 SRO-I I/C 2,6,10 3,4b,8 5,8 6

4 MAJ 8

7 7

2 2

SRO-U MC 2,10 3,4b 5

4 1

TS 0

0 KEY:

Events and Evolutions Checklist POSITION 3

POSITION Form 3.4-1 Instructions for the Events and Evolutions Checklist

1. Mark the applicant license level for each simulator operating test number.

RX = Reactivity Manipulation; NOR = Normal Evolution; I/C = Instrument/Component Failure; MAJ = Major Transient; MC = Manual Control of Automatic Function; TS = Technical Specification Evaluation; RO = Reactor Operator; SRO-I = Instant Senior Reactor Operator; SRO-U = Upgrade Senior Reactor Operator; SRO = Senior Reactor Operator; ATC =

At the Controls; and BOP = Balance of Plant 1

4 2**

T O

T A

L M

I N

I M

U M

POSITION Scenarios POSITION

2. For the set of scenario columns, fill in the associated event number from Form 3.3 1, Scenario Outline, to show the specific event types being used for the applicant while in the assigned crew position for that scenario.

Facility: Browns Ferry NPP Operating Test No.: 2204 Date of Exam: 16 MAY 2022

• Minimums are subject to the instructions in Section C.2, License Level Criteria.

• • NOTE: Scenario 2 is a spare and was not counted in the TOTALS. The Scenario 4 watchbill was used for Scenario 2.

Form 3.4-1 A

E P

V P

E L

N I

T C

A T

N Y

T P

S A

B S

A B

S A

B S

A B

E R

T O

R T

O R

T O

R T

O O

C P

O C

P O

C P

O C

P R

I U

RO RX 5

1 1

2 NOR 1

1 1

1 SRO-I I/C 2,6,10 3,4b,8 5,8 6

4 MAJ 8

7 7

2 2

SRO-U MC 2,10 3,4b 5

4 1

TS 0

0 RO RX 6

6 1

1 3

NOR 2

1 2

1 SRO-I I/C 3,8 4,7,9 4a,5 3,4 7

4 MAJ 6

8 7

7 3

2 SRO-U MC 3,8 4,7 4a 4

5 1

TS 0

0 RO RX 6

6 1

1 4

NOR 2

1 2

1 SRO-I I/C 3,8 4,7,9 4a,5 3,4 7

4 MAJ 6

8 7

7 3

2 SRO-U MC 3,8 4,7 4a 4

5 1

TS 0

0 RO RX 6

6 1

1 5

NOR 2

1 2

1 SRO-I I/C 3,8 4,7,9 4a,5 3,4 7

4 MAJ 6

8 7

7 3

2 SRO-U MC 3,8 4,7 4a 4

5 1

TS 0

0 KEY:

RX = Reactivity Manipulation; NOR = Normal Evolution; I/C = Instrument/Component Failure; MAJ = Major Transient; MC = Manual Control of Automatic Function; TS = Technical Specification Evaluation; RO = Reactor Operator; SRO-I = Instant Senior Reactor Operator; SRO-U = Upgrade Senior Reactor Operator; SRO = Senior Reactor Operator; ATC =

At the Controls; and BOP = Balance of Plant Form 3.4-1 Instructions for the Events and Evolutions Checklist

1. Mark the applicant license level for each simulator operating test number.

2. For the set of scenario columns, fill in the associated event number from Form 3.3 1, Scenario Outline, to show the specific event types being used for the applicant while in the assigned crew position for that scenario.

• Minimums are subject to the instructions in Section C.2, License Level Criteria.

POSITION POSITION POSITION POSITION 4

2**

M I

N I

M U

M T

O T

A L

3 1

• • NOTE: Scenario 2 is a spare and was not counted in the TOTALS. The Scenario 4 watchbill was used for Scenario 2.

Scenarios Events and Evolutions Checklist Facility: Browns Ferry NPP Date of Exam: 16 MAY 2022 Operating Test No.: 2204

Form 4.1-BWR Boiling-Water Reactor Examination Outline 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: Browns Ferry NPP Date of Exam: May 2022 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

4 N/A 4

20 4

3 7

2 1

1 1

1 1

1 6

2 1

3 Tier Totals 4

4 4

4 5

5 26 6

4 10

2.

Plant Systems 1

2 3

2 2

2 3

2 3

2 2

3 26 2

3 5

2 1

1 1

1 1

1 1

1 1

1 1

11 0

2 1

3 Tier Totals 3

4 3

3 3

4 3

4 3

3 4

37 4

4 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

1 2

2 2

4. Theory Reactor Theory Thermodynamics 6

3 3

NOTE: This combined Form 4.1 Outline file includes a question re-order enacted after written question approvals.

Listed Form 4.1 "#" corresponds to "previous #" or "old #" columns in re-order document (starts on pdf pg 15).

Form 4.1-BWR BWR Examination Outline Page 2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X

X AA2.11: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Individual loop flow(s)

AA2.09: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Reactor Pressure 3.6 3.4 1

76 295003 (APE 3) Partial or Complete Loss of AC Power / 6 X G.2.1.7: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (Partial or Complete Loss of AC Power) 4.4 2

295004 (APE 4) Partial or Total Loss of DC Power / 6 X

AK1.02: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Partial or Complete Loss of DC Power:

Redundant DC power supplies 3.8 3

295005 (APE 5) Main Turbine Generator Trip /

3 X

AK2.03: Knowledge of the relationship between Main Turbine Generator Trip and the following systems or components:

Recirculation system 3.5 4

295006 (APE 6) Scram / 1 X

AK3.01: Knowledge of the reasons for the following responses or actions as they apply to SCRAM: Reactor water level response 4.0 5

295016 (APE 16) Control Room Abandonment

/ 7 X

AA1.01: Ability to operate and/or monitor the following as they apply to Control Room Abandonment: RPS 3.8 6

295018 (APE 18) Partial or Complete Loss of CCW / 8 X

AA2.02: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Component Cooling Water: Cooling water temperature 3.7 7

295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 X G2.4.50: Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure. (Partial or Complete Loss of Instrument Air) 4.2 8

295021 (APE 21) Loss of Shutdown Cooling /

4 X

X AK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Loss of Shutdown Cooling: Adequate core cooling G2.4.41: Knowledge of the emergency action level thresholds and classifications (SRO Only) (Loss of Shutdown Cooling) 4.4 4.6 9

77

295023 (APE 23) Refueling Accidents / 8 X

X AK2.01: Knowledge of the relationship between Refueling Accidents and the following systems or components: Fuel handling equipment AA2.03: Ability to determine and/or interpret the following as they apply to Refueling Accidents: Airborne contamination levels 3.5 3.2 10 78 295024 High Drywell Pressure / 5 X

X EK3.02: Knowledge of the reasons for the following responses or actions as they apply to High Drywell Pressure: Suppression pool spray G2.4.2: Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (High Drywell Pressure) 4.1 4.6 11 79 295025 (EPE 2) High Reactor Pressure / 3 X

EA1.10: Ability to operate and/or monitor the following as they apply to High Reactor Pressure: Reactor water cleanup system 2.8 12 295026 (EPE 3) Suppression Pool High Water Temperature / 5 X

EA2.03: Ability to determine and/or interpret the following as they apply to Suppression Pool High Water Temperature: Reactor Pressure 3.5 13 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 X

X G2.2.44: Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions (High Drywell Temperature)

EA2.03: Ability to determine and/or interpret the following as they apply to High Drywell Temperature: Reactor Water Level 4.2 4.0 14 80 295030 (EPE 7) Low Suppression Pool Water Level / 5 X

EK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Low Suppression Pool Water Level: Heat capacity 4.0 15 295031 (EPE 8) Reactor Low Water Level / 2 X

EK2.06: Knowledge of the relationship between Reactor Low Water Level and the following systems or components: High-pressure coolant injection (HPCI) 4.1 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X

X EK3.02: Knowledge of the reasons for the following responses or actions as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Boron injection G2.1.32: Ability to explain and apply system precautions, limitations, notes or cautions (Scram Condition Present and Reactor Power Above APRM Downscale or Unknown) 4.2 4.0 17 81

295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 X

EA1.08: Ability to operate and/or monitor the following as they apply to High Offsite Radioactivity Release Rate: MSIV leakage control 3.1 18 600000 (APE 24) Plant Fire On Site / 8 X

X AA2.05: Ability to determine and/or interpret the following as they apply to Plant Fire on Site: Ventilation alignment necessary to secure affected area Above K/A revised 8/5/2021 from AA2.10.

AA2.18: Assessment of control room habitability (SRO Only) 3.2 3.6 19 82 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 X G2.1.20: Ability to interpret and execute procedure steps (Generator Voltage and Electric Grid Disturbances) 4.6 20 K/A Category Totals:

3 3

3 3

4/4 4/3 Group Point Total:

20/7

Form 4.1-BWR BWR Examination Outline Page 3 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

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

K/A Topic(s)

IR 295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 X

AA1.06: Ability to operate and/or monitor the following as they apply to High Reactor Pressure: Shutdown cooling system (RHR shutdown cooling mode) 3.6 21 295008 (APE 8) High Reactor Water Level / 2 X

AA2.01: Ability to determine and/or interpret the following as they apply to High Reactor Water Level: Reactor water level 4.4 83 295009 (APE 9) Low Reactor Water Level / 2 X G2.4.18: Knowledge of the specific bases for emergency and abnormal operating procedures (Low Reactor Water Level) 4.0 84 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 X

AA2.01: Ability to determine and/or interpret the following as they apply to High Suppression Pool Water Temperature:

Suppression pool temperature 4.3 22 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15**) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 X G2.1.30: Ability to locate and operate components, including local controls (Abnormal Offsite Release Rate) 4.4 23 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 X

AK1.05: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Inadvertent Containment Isolation: Loss of drywell/containment cooling 3.5 24 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 X

EK2.07: Knowledge of the relationship between High Suppression Pool Water Level and the following systems or components: Drywell/containment water level 3.6 25 295032 (EPE 9) High Secondary Containment Area Temperature / 5

295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 X

EK3.06: Knowledge of the reasons for the following responses or actions as they apply to High Secondary Containment Area Radiation Levels: Operating ventilation systems 3.6 26 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 X

EA2.01: Ability to determine and/or interpret the following as they apply to Secondary Containment High Differential Pressure: Secondary containment pressure 3.9 85 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:

1 1

1 1

1/2 1/1 Group Point Total:

6/3

Form 4.1-BWR BWR Examination Outline Page 4 Plant SystemsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode X

K1.16: Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI:

Injection Mode and the following systems:

Component cooling water systems 2.7 27 205000 (SF4 SCS) Shutdown Cooling X

X K2.01: Knowledge of electrical power supplies to the following: Pump motors K2.02: Knowledge of electrical power supplies to the following: Motor-operated valves 3.6 3.3 28 29 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection X

K3.04: Knowledge of the effect that a loss or malfunction of the High-Pressure Coolant Injection System will have on the following systems or system parameters: Reactor power 3.6 30 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray X

K4.05: Knowledge of Low-Pressure Core Spray System design features and/or interlocks that provide for the following:

Pump minimum flow 3.4 31 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control X

X K5.01: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Standby Liquid Control System: Effects of the moderator temperature coefficient of reactivity on boron K6.06: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Standby Liquid Control System:

Redundant reactivity control system 3.0 3.6 32 33 212000 (SF7 RPS) Reactor Protection X

X K6.10: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Reactor Protection System:

Reactor/turbine pressure regulating system G2.1.20: Ability to interpret and execute procedure steps (Reactor Protection System) 3.5 4.6 34 86 215003 (SF7 IRM)

Intermediate-Range Monitor X

A1.08: Ability to predict and/or monitor changes in parameters associated with operation of the Intermediate Range Monitor System, including: IRM back panel switches 3.1 35

215004 (SF7 SRMS) Source-Range Monitor X

A2.02: Ability to (a) predict the impacts of the following on the Source Range Monitor System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: SRMS inoperable condition 3.4 36 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X

A3.03: Ability to monitor automatic operation of the Average Power Range Monitor/Local Power Range Monitor System, including:

Meters and recorders 3.6 37 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X

X A4.12: Ability to manually operate and/or monitor in the control room: Turbine speed control A2.14: Ability to (a) predict the impacts of the following on the Reactor Core Isolation Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Rupture disc failure: exhaust-diaphragm 3.9 3.6 38 87 218000 (SF3 ADS) Automatic Depressurization X G2.1.23: Ability to perform general or normal operating procedures during any plant condition (Automatic Depressurization System) 4.3 39 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff X

X K1.04: Knowledge of the physical connections and/or cause and effect relationships between the Primary Containment Isolation System/Nuclear Steam Supply Shutoff and the following systems: HPCI G2.4.31: Knowledge of annunciator alarms, indications, or response procedures (Primary Containment Isolation/Nuclear Steam Supply Shutoff) 4.2 4.1 40 88 239002 (SF3 SRV) Safety Relief Valves X

K2.01: Knowledge of electrical power supplies to the following: SRV solenoids 3.7 41 259002 (SF2 RWLCS) Reactor Water Level Control X

X K3.04: Knowledge of the effect that a loss or malfunction of the Reactor Water Level Control System will have on the following systems or system parameters:

Recirculation system A2.02: Ability to (a) predict the impacts of the following on the Reactor Water Level Control System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of any number of reactor feedwater flow inputs 3.3 3.8 42 43 261000 (SF9 SGTS) Standby Gas Treatment X

K4.02: Knowledge of Standby Gas Treatment System design features and/or interlocks that provide for the following:

Charcoal bed decay heat removal 3.0 44

262001 (SF6 AC) AC Electrical Distribution X

K5.02: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the AC Electrical Distribution: Breaker control power 3.5 45 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

X X

K6.02: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Uninterruptible Power Supply (AC/DC):

DC electrical distribution 291008, K1.06: Interpreting one-line diagram of control circuitry (Uninterruptible Power Supply (AC/DC))

3.4 3.6 46 47 263000 (SF6 DC) DC Electrical Distribution X

A1.02: Ability to predict and/or monitor changes in parameters associated with operation of the DC Electrical Distribution, including: Lights and alarms 3.3 48 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG X

X A2.08: Ability to (a) predict the impacts of the following on the Emergency Generators and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Initiation of emergency generator room fire protection system A2.10: Ability to (a) predict the impacts of the following on the Emergency Generators and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: LOCA 3.1 4.4 49 89 300000 (SF8 IA) Instrument Air X

A3.04: Ability to monitor automatic operation of the Instrument Air System, including:

Automatic isolation 3.4 50 400000 (SF8 CCS) Component Cooling Water X

X A4.01: Ability to manually operate and/or monitor in the control room: CCW indications and control G2.2.42: Ability to recognize system parameters that are entry-level conditions for technical specifications (Component Cooling Water System) 3.8 4.6 51 90 510000 (SF4 SWS*) Service Water (Normal and Emergency)

X G2.1.2: Knowledge of operator responsibilities during any mode of plant operation (Service Water (Normal and Emergency))

4.1 52 K/A Category Point Totals:

2 3

2 2

2 3

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

26/5

Form 4.1-BWR BWR Examination Outline Page 5 Plant SystemsTier 2/Group 2 (RO/SRO)

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

K/A Topic(s)

IR 201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer X

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

Pushbutton indicating switches 3.2 53 202001 (SF1, SF4 RS) Recirculation X

K5.06: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Recirculation System: ATWS RPT 3.8 54 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup X

A2.05: Ability to (a) predict the impacts of the following on the Reactor Water Cleanup System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

Abnormal valve position 3.0 91 214000 (SF7 RPIS) Rod Position Information X

K6.01: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Rod Position Information System: RPIS power supply 3.2 55 215001 (SF7 TIP) Traversing In-Core Probe X

A1.01: Ability to predict and/or monitor changes in parameters associated with operation of the Traversing In-Core Probe, including: Area radiation levels 3.1 56 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries X

A3.04: Ability to monitor automatic operation of the Primary Containment System and Auxiliaries, including:

Containment/drywell response during LOCA 4.2 57 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode

230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode X

K1.01: Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI: Torus/Suppression Pool Spray Mode and the following systems: Primary containment 3.9 58 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup X

A2.09: Ability to (a) predict the impacts of the following on the Fuel Pool Cooling and Cleanup and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: AC electrical power failures 3.4 59 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating X 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 (Reactor/Turbine Pressure Regulating) 4.1 92 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater X

K4.12: Knowledge of Feedwater System design features and/or interlocks that provide for the following: RFP start permissives 3.1 60 268000 (SF9 RW) Radwaste X 291007, K1.07: Principles of demineralizer operation (Radwaste) 2.5 61 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection X

K2.02: Knowledge of electrical power supplies to the following: Fire pumps Above K/A revised 8/5/2021 from K3.09.

3.2 62 288000 (SF9 PVS) Plant Ventilation X

A2.05: Ability to (a) predict the impacts of the following on the Plant Ventilation Systems and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Extreme outside weather conditions 2.9 93 290001 (SF5 SC) Secondary Containment

290003 (SF9 CRV) Control Room Ventilation X

K3.06: Knowledge of the effect that a loss or malfunction of the Control Room Ventilation will have on the following systems or system parameters: Control room radioactivity Above K/A revised 8/5/2021 from K2.04.

3.5 63 290002 (SF4 RVI) Reactor Vessel Internals 510001 (SF8 CWS*) Circulating Water K/A Category Point Totals:

1 1

1 1

1 1

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

11/3

Form 4.1-BWR BWR Examination Outline Page 6 Generic Knowledge and AbilitiesTier 3 (RO/SRO)

Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements 3.8 64 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, or switches 4.1 65 2.1.36 Knowledge of procedures and limitations involved in core alterations 4.1 94 Subtotal 2

1

2. Equipment Control 2.2.22 Knowledge of limiting conditions for operation and safety limits 4.0 66 2.2.35 Ability to determine technical specification mode of operation 3.6 67 2.2.4 (Multi-unit license) Ability to explain the variations in control room layouts, systems, instrumentation, or procedural actions between units at a facility 3.6 95 2.2.19 Knowledge of maintenance work order requirements 3.4 96 Subtotal 2

2

3. Radiation Control 2.3.12 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 3.2 68 2.3.6 Ability to approve liquid or gaseous release permits 3.8 97 2.3.14 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 analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) 3.8 98 Subtotal 1

2

4. Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of annunciators 3.6 69 2.4.28 Knowledge of procedures relating to a security event (ensure that the test item includes no safeguards information) 4.1 99 2.4.38 Ability to take actions required by the facility emergency plan implementing procedures, including supporting or acting as emergency coordinator 4.4 100 Subtotal 1

2 Tier 3 Point Total 6

7

Form 4.1-BWR BWR Examination Outline Page 7 TheoryTier 4 (RO)

Category K/A #

Topic RO IR

1. Reactor Theory 292001 K1.02 Define prompt and delayed neutrons 3.1 70 292005 K1.12 Describe effects of deep and shallow control rods on axial and radial flux distribution 2.9 71 292007 K1.03 Given a curve of K-effective versus core age, state the reasons for maximum, minimum, and inflection points.

2.7 72 Subtotal 3

2. Thermodynamics 293003 K1.22 Explain the usefulness of steam tables to the control room operator 3.2 73 293005 K1.06 Describe how changes in system parameters affect thermodynamic efficiency 2.6 74 293007 K1.03 Heat Transfer, Explain the manner in which fluid films affects heat transfer 2.8 75 Subtotal 3

Tier 4 Point Total 6

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 1 of 18 Previous System # / Name K/A Topic(s)

IR 1

62 286000 (SF8 FPS) Fire Protection K2.02 (10CFR 55.41.7)

Knowledge of the electrical power supplies to the following:

Fire Pumps 3.2 2

6 295016 (APE 16) Control Room Abandonment /7 A1.01 (10CFR 55.41.7)

Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

RPS 3.8 3

5 259006 (APE 6) SCRAM /1 AK3.01 (10CFR 55.41.5)

Knowledge of the reasons for the following responses or actions as they apply to SCRAM:

Reactor Water Level Response 4.0 4

37 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor A3.03 (10CFR 55.41.7)

Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including:

Meters and recorders 3.6 5

42 259002 (SF2 RWLCS) Reactor Water Level Control K3.04 (10CFR 55.41.7)

Knowledge of the effect that a loss or malfunction of the Reactor Water Level Control System will have on the following systems or system parameters:

Recirculation system 3.3

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 2 of 18 Old System # / Name K/A Topic(s)

IR 6

33 211000 (SF1 SLCS) Standby Liquid Control K6.06 (10CFR 55.41.7)

Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Standby Liquid Control System:

Redundant reactivity control system 3.6 7

64 Conduct of Operations G2.1.1 (10CFR 55.41.10)

Knowledge of conduct of operations requirements 3.8 8

28 205000 (SF4 SCS) Shutdown Cooling K2.01 (10CFR 55.41.7)

Knowledge of the electrical power supplies to the following:

Pump motors 3.6 9

3 295004 (APE 4) Partial or Complete Loss of D.C.

Power / 6 AK1.02 (10CFR 55.41.10)

Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Partial or Complete Loss of DC Power:

Redundant DC power supplies 3.8 10 12 295025 (EPE 2) High Reactor Pressure / 3 EA1.10 (10CFR 55.41.7)

Ability to operate and/or monitor the following as they apply to High Reactor Pressure:

Reactor water cleanup system 2.8

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 3 of 18 Old System # / Name K/A Topic(s)

IR 11 38 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling A4.12 (10CFR 55.41.7)

Ability to manually operate and/or monitor in the control room:

Turbine speed control 3.9 12 35 215003 (SF7 IRM) Intermediate-Range Monitor A1.08 (10CFR 55.41.5)

Ability to predict and/or monitor changes in parameters associated with operation of the Intermediate Range Monitor system, including:

IRM back panel switches 3.1 13 24 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 AK1.05 (10CFR 55.41.9)

Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Inadvertent Containment Isolation:

Loss of drywell/containment cooling system 3.5 14 48 263000 (SF6 DC) DC Electrical Distribution A1.02 (10CFR 55.41.5)

Ability to predict and/or monitor changes in parameters associated with operation of the DC Electrical Distribution, including:

Lights and alarms 3.3 15 2

295003 (APE 3) Partial or Complete Loss of A.C.

Power / 6 G2.1.7 (10CFR 55.41.5)

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

4.4

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 4 of 18 Old System # / Name K/A Topic(s)

IR 16 14 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 G2.2.44 (10CFR 55.41.5)

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

4.2 17 19 600000 (APE 24) Plant Fire On Site / 8 AA2.05 (10CFR 55.41.10)

Ability to determine and/or interpret the following as they apply to Plant Fire on Site:

Ventilation alignment necessary to secure affected area 3.2 18 44 261000 (SF9 SGTS) Standby Gas Treatment K4.02 (10CFR 55.41.7)

Knowledge of Standby Gas Treatment System design features and/or interlock that provide for the following:

Charcoal bed decay heat removal 3.0 19 56 215001 (SF7 TIP) Traversing In-Core Probe A1.01 (10CFR 55.41.7)

Ability to predict and/or monitor changes in parameters associated with operation of the Traversing In-Core Probe, including Area radiation levels 3.1 20 54 202001 (SF1, SF4 RS) Recirculation K5.06 (10CFR 55.41.5)

Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Recirculation System:

ATWS RPT 3.8

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 5 of 18 Old System # / Name K/A Topic(s)

IR 21 8

295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 G2.4.50 (10CFR 55.41.10)

Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure.

4.2 22 29 205000 (SF4 SCS) Shutdown Cooling K2.02 (10CFR 55.41.7)

Knowledge of electrical power supplies to the following:

Motor-Operated valve 3.3 23 1

295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation/1 & 4 AA2.11 (10CFR 55.41.10)

Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation:

Individual loop flow(s) 3.6 24 15 295030 (EPE 7) Low Suppression Pool Water Level / 5 EK1.03 (10CFR 55.41.8)

Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Low Suppression Pool Water Level:

Heat capacity 4.0 25 27 203000 (SF2, SF4 RHR/LPCI) RHR/LPCI: Injection Mode K1.16 (10CFR 55.41.7)

Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI Injection Mode and the following systems:

Component cooling water systems 2.7 26 41 239002 (SF3 SRV) Safety Relief Valves K2.01 (10CFR 55.41.7)

Knowledge of electrical power supplies to the following:

SRV solenoids 3.7

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 6 of 18 Old System # / Name K/A Topic(s)

IR 27 25 295029 (EPE 6) High Suppression Pool Water Level / 5 EK2.07 (10CFR 55.41.7)

Knowledge of the relationship between High Suppression Pool Water Level and the following systems or components:

Drywell/containment water level 3.6 28 26 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 EK3.06 (10CFR 55.41.5)

Knowledge of the reasons for the following responses or actions as they apply to High Secondary Containment Area Radiation Levels:

Operating ventilation systems 3.6 29 17 295037 (EPE 14) SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 EK3.02 (10CFR 55.41.5)

Knowledge of the reasons for the following responses or actions as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or UNKNOWN:

Boron Injection 4.2 30 16 295031 (EPE 8) Reactor Low Water Level / 2 EK2.06 (10CFR 55.41.7)

Knowledge of the relationship between Reactor Low Water Level and the following systems or components:

High-pressure coolant injection (HPCI) 4.1 31 30 206000 (SF2, SF4 HPCIS) High-Pressure Coolant Injection K3.04 (10CFR 55.41.7)

Knowledge of the effect that a loss or malfunction of the High-Pressure Coolant Injection System will have on the following systems or system parameters:

Reactor Power 3.6

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 7 of 18 Old System # / Name K/A Topic(s)

IR 32 9

295021 (APE 21) Loss of Shutdown Cooling / 4 AK1.03 (10CFR 55.41.9)

Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to LOSS OF SHUTDOWN COOLING:

Adequate Core Cooling 4.4 33 31 209001 (SF2, SF4 LPCS) Low-Pressure Core Spray K4.05 (10CFR 55.41.7)

Knowledge of Low-Pressure Core Spray System design features and/or interlocks that provide for the following:

Pump minimum flow 3.4 34 18 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 EA1.08 (10CFR 55.41.7)

Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RADIOACTIVITY RELEASE RATE:

MSIV leakage control 3.1 35 34 212000 (SF7 RPS) Reactor Protection K6.10 (10CFR 55.41.7)

Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Reactor Protection System:

Reactor/turbine pressure regulating system 3.5 36 20 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 G2.1.20 (10CFR 55.41.10)

Ability to interpret and execute procedure steps 4.6 37 23 295017 (APE 17) High Off-Site Radioactive Release Rate / 9 G2.1.30 (10CFR 55.41.7)

Ability to locate and operate components, including local controls.

4.4

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 8 of 18 Old System # / Name K/A Topic(s)

IR 38 39 218000 (SF3 ADS) Automatic Depressurization G2.1.23 (10CFR 55.41.10)

Ability to perform general or normal operating procedures during any plant condition.

4.3 39 63 290003 (SF9 CRV) Control Room Ventilation K3.06 (10CFR 55.41.7)

Knowledge of the effect that a loss or malfunction of the Control Room Ventilation will have on the following systems or system parameters:

Control room radioactivity 3.5 40 40 223002 (SF5 PCIS) Primary Containment Isolation

/ Nuclear Steam Supply Shutoff K1.04 (10CFR 55.41.7)

Knowledge of the physical connections and/or cause and effect relationships between the Primary Containment Isolation System/Nuclear Steam Supply Shutoff and the following systems:

HPCI 4.2 41 4

295005 (APE 5) Main Turbine Generator Trip /3 AK2.03 (10CFR 55.41.7)

Knowledge of the relationship between Main Turbine Generator trip and the following systems and components:

Recirculation System 3.5 42 22 295013 (APE 13 IRM) High Suppression Pool Temperature / 5 AA2.01 (10CFR 55.41.10)

Ability to determine and/or interpret the following as they apply to High Suppression Pool Water Temperature:

Suppression Pool Temperature 4.3

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 9 of 18 Old System # / Name K/A Topic(s)

IR 43 36 215004 (SF 7 SRMS) Source-Range Monitor A2.02 (10CFR 55.41.5)

Ability to (a) predict the impacts of the following on the Source Range Monitor System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

SRMS inoperable condition 3.4 44 43 259002 (SF2 RWLCS) Reactor Water Level Control A2.02 (10CFR55.41.5)

Ability to (a) predict the impacts of the following on the Reactor Water Level Control System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

Loss of any number of Reactor feedwater flow inputs 3.8 45 45 262001 (SF6 AC) AC Electrical Distribution K5.02 (10CFR 55.41.5)

Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the AC Electrical Distribution:

Breaker control power 3.5 46 10 295023 (APE 23) Refueling Accidents / 8 AK2.01 (10CFR 55.41.7)

Knowledge of the relationship between Refueling Accidents and the following systems or components:

Fuel Handling Equipment 3.5 47 13 295026 (EPE 3) Suppression Pool High Water Temperature / 5 EA2.03 (10CFR 55.41.10)

Ability to determine and/or interpret the following as they apply to Suppression Pool High Water Temperature:

Reactor Pressure 3.5

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 10 of 18 Old System # / Name K/A Topic(s)

IR 48 32 211000 (SF1, SLCS) Standby Liquid Control K5.01 (10CFR 55.41.5)

Knowledge of the operational implications and cause and effect relationships of the following concepts as they apply to the Standby Liquid Control System:

Effects of moderator temperature coefficient of reactivity on boron 3.0 49 51 400000 (SF8 CCS) Component Cooling Water A4.01 (10CFR 55.41.7)

Ability to manually operate and/or monitor in the control room:

CCW indications and control 3.8 50 50 300000 (SF8 IA) Instrument Air A3.04 (10CFR 55.41.8)

Ability to monitor automatic operation of the Instrument Air System, including:

Automatic Isolation 3.4 51 52 510000 (SF4 SWS*) Service Water (Normal and Emergency)

G2.1.2(10CFR 55.41.10)

Knowledge of operator responsibilities during any mode of plant operation 4.1 52 55 214000 (SF7 RPIS) Rod Position Information K6.01 (10CFR 55.41.7)

Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Rod Position Information System:

RPIS Power Supply 3.2

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 11 of 18 Old System # / Name K/A Topic(s)

IR 53 53 201006 (SF7 RWMS) Rod Worth Minimizer A4.02 (10CFR 55.41.7)

Ability to manually operate and/or monitor in the control room:

Pushbutton indicating switches 3.2 54 21 295007 (APE 7) High Reactor Pressure / 3 AA1.06 (10CFR 55.41.7)

Ability to operate and/or monitor the following as they apply to High Reactor Pressure:

Shutdown cooling system (RHR shutdown cooling mode) 3.6 55 49 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG A2.08 (10CFR 55.41.5)

Ability to predict the impacts of the following on the Emergency Generators and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

Initiation of emergency generator room fire protection system 3.1 56 57 223001 (SF5 PCS) Primary Containment and Auxiliaries A3.04 (10CFR 55.41.7)

Ability to monitor automatic operation of the Primary Containment System and Auxiliaries, including:

Containment/drywell response during LOCA 4.2 57 58 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode K1.01 (10CFR 55.41.7)

Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI:

Torus/Suppression Pool Spray Mode and the following systems:

Primary containment 3.9

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 12 of 18 Old System # / Name K/A Topic(s)

IR 58 59 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup A2.09 (10CFR 55.41.5)

Ability to (a) predict the impacts of the following on the Fuel Pool Cooling and Cleanup and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

AC electrical power failures 3.4 59 60 259001 (SF2 FWS) Feedwater K4.12 (10CFR 55.41.7)

Knowledge of Feedwater System design features and/or interlocks that provide for the following:

RFP start permissives 3.1 60 7

295018 (APE 18) Partial or Complete Loss of CCW / 8 AA2.02 (10CFR 55.41.10)

Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Component Cooling Water:

Cooling Water Temperature 3.7 61 69 Emergency Procedures/Plan G2.4.32 (10CFR 55.41.10)

Knowledge of operator response to loss of annunciators.

3.6 62 66 Equipment Control G2.2.22 (10CFR 55.41.5)

Knowledge of limiting conditions for operation and safety limits.

4.0 63 11 295024 (EPE 1) High Drywell Pressure / 5 EK3.02 (10CFR 55.41.5)

Knowledge of the reasons for the following responses or actions as they apply to High Drywell Pressure:

Suppression Pool Spray 4.1

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 13 of 18 Old System # / Name K/A Topic(s)

IR 64 68 Radiation Control G2.3.12 (10CFR 55.41.12)

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.

3.2 65 65 Conduct of Operations G2.1.29 (10CFR 55.41.10)

Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

4.1 66 74 293005 Thermodynamics K1.06 (10CFR 55.41.14)

Describe how changes in system parameters affect thermodynamic efficiency.

2.6 67 67 Equipment Control G2.2.35 (10CFR 55.41.10)

Ability to determine Technical Specification Mode of Operation.

3.6 68 75 293007 Thermodynamics K1.03 (10CFR 55.41.14)

Heat Transfer, Explain the manner in which fluid films affect heat transfer.

2.8 69 61 268000 (SF9 RW) Radwaste 291007, K1.07 (10CFR 55.41.4)

Principles of demineralizer operation.

2.5 70 47 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 291008, K1.06 (10CFR 55.41.7)

Interpreting one-line diagram of control circuitry.

3.6 71 70 292001 Reactor Theory K1.02 (10CFR 55.41.1)

Describe prompt and delayed neutrons.

3.1

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 14 of 18 Old System # / Name K/A Topic(s)

IR 72 72 292007 Fuel Depletion and Burnable Poisons K1.03 (10CFR 55.41.1)

Given a curve of K-effective versus core age, state the reasons for maximum, minimum, and inflection points.

2.7 73 73 293003 Thermodynamics - Steam K1.22 (10CFR 55.41.14)

Explain the usefulness of steam tables to the control room operator.

3.2 74 46 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

K6.02 (10CFR 55.41.7)

Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Uninterruptible Power Supply (AC/DC):

DC electrical distribution 3.4 75 71 292005 Reactor Theory K1.12 (10CFR 55.41.1)

Describe the effects of deep and shallow control rods on axial and radial flux distribution.

2.9 76 76 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 AA2.09 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Reactor Pressure 3.4 77 77 295021 (APE 21) Loss of Shutdown Cooling / 4 G2.4.41 (10CFR 55.43.5 - SRO Only)

Knowledge of the emergency action level thresholds and Classifications 4.6 78 78 295023 (APE 23) Refueling Accidents / 8 AA2.03 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to Refueling Accidents Airborne Contamination levels 3.2

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 15 of 18 Old System # / Name K/A Topic(s)

IR 79 79 295024 (EPE 1) High Drywell Pressure / 5 G2.4.2 (10CFR 55.43.5 - SRO Only)

Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions.

4.6 80 80 295028 (EPE 5) High Drywell Temperature / 5 EA2.03 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE:

Reactor Water Level 4.0 81 81 295037 (EPE 14) SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 G2.1.32 (10CFR 55.43.2 - SRO Only)

Ability to explain and apply system precautions, limitations, notes, or cautions.

4.0 82 82 600000 (APE 24) Plant Fire On Site / 8 AA2.18 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to Plant Fire on Site:

Assessment of control room habitability 3.6 83 83 295008 (APE 8) High Reactor Water Level / 2 AA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to High Reactor Water Level:

Reactor Water Level 4.4 84 84 295009 (APE 9) Low Reactor Water Level / 2 G2.4.18 (10CFR 55.43.1 - SRO Only)

Knowledge of the specific bases for emergency and abnormal operating procedures.

4.0 85 85 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 EA2.01 (10CFR 55.43.5 - SRO Only)

Ability to determine and/or interpret the following as they apply to Secondary Containment High Differential Pressure:

Secondary Containment Pressure 3.9

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 16 of 18 Old System # / Name K/A Topic(s)

IR 86 86 212000 (SF7 RPS) Reactor Protection G2.1.20 (10CFR 55.43.5 - SRO Only)

Ability to interpret and execute procedure steps.

4.6 87 87 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling A2.14 (10CFR 55.43.5 - SRO Only)

Ability to (a) predict the impacts of the following on the Reactor Core Isolation Cooling System (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Rupture disc failure: exhaust-diaphragm 3.6 88 94 Conduct of Operations (2.1)

G2.1.36 (10CFR 55.43.6 - SRO Only)

Knowledge of procedures and limitations involved in core alterations.

4.1 89 89 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG A2.10 (10CFR 55.43.5 - SRO Only)

Ability to (a) predict the impacts of the following on the Emergency Generators; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

LOCA 4.4 90 90 400000 (SF8 CCS) Component Cooling Water G2.2.42 (10CFR 55.43.2 - SRO Only)

Ability to recognize system parameters that are entry-level conditions for technical specifications.

4.6 91 91 204000 (SF2 RWCU) Reactor Water Cleanup A2.05 (10CFR 55.43.5 - SRO Only)

Ability to (a) predict the impacts of the following on the Reactor Water Cleanup System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Abnormal Valve Position 3.0

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 17 of 18 Old System # / Name K/A Topic(s)

IR 92 92 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating G2.4.30 (10CFR 55.43.5 - SRO Only)

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 transmission system operator.

4.1 93 93 288000 (SF9, PVS) Plant Ventilation A2.05 (10CFR 55.43.5 - SRO Only)

Ability to (a) predict the impacts of the following on the Plant Ventilation SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Extreme outside weather conditions 2.9 94 88 223002 (SF5, PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff G2.4.31 (10CFR 55.43.5 - SRO Only)

Knowledge of annunciation alarms, indications, or response procedures.

4.1 95 95 Equipment Control (2.2)

G2.2.4 (10CFR 55.43.2 - SRO Only)

(Multi-unit license) Ability to explain the variations in control room layouts, systems, instrumentation, or procedural actions taken between units at a facility.

3.6 96 96 Equipment Control (2.2)

G2.2.19 (10CFR 55.43.5 - SRO Only)

Knowledge of maintenance work order requirements.

3.4 97 97 Radiation Control (2.3)

G2.3.6 (10CFR 55.43.4 - SRO Only)

Ability to approve liquid or gaseous release permits 3.8

BFN ILT 2204 Sample Plan (in Question Order)

SRO only K/As shown in italics 2/2/2022 Page 18 of 18 Old System # / Name K/A Topic(s)

IR 98 98 Radiation Control (2.3)

G2.3.14 (10CFR 55.43.4 - SRO Only)

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 analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits.

3.8 99 99 Emergency Procedures / Plan (2.4)

G2.4.28 (10CFR 55.43.5 - SRO Only)

Knowledge of the procedures relating to a security event (ensure that the test item contains no safeguards information).

4.1 100 100 Emergency Procedures / Plan (2.4)

G2.4.38 (10CFR 55.43.5 - SRO Only)

Ability to take actions required by the facility emergency plan implementing procedures, including supporting or acting as emergency coordinator 4.4

Form 4.1-BWR Boiling-Water Reactor Examination Outline 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: Browns Ferry NPP Date of Exam: May 2022 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

4 N/A 4

20 4

3 7

2 1

1 1

1 1

1 6

2 1

3 Tier Totals 4

4 4

4 5

5 26 6

4 10

2.

Plant Systems 1

2 3

2 2

2 3

2 3

2 2

3 26 2

3 5

2 1

1 1

1 1

1 1

1 1

1 1

11 0

2 1

3 Tier Totals 3

4 3

3 3

4 3

4 3

3 4

37 4

4 8

3.

Generic Knowledge and Abilities Categories CO EC RC EM 6

CO EC RC EM 7

2 2

1 1

1 2

2 2

4. Theory Reactor Theory Thermodynamics 6

3 3

Form 4.1-BWR BWR Examination Outline Page 2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X

X AA2.11: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Individual loop flow(s)

AA2.09: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Reactor Pressure 3.6 3.4 23 76 295003 (APE 3) Partial or Complete Loss of AC Power / 6 X G.2.1.7: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (Partial or Complete Loss of AC Power) 4.4 15 295004 (APE 4) Partial or Total Loss of DC Power / 6 X

AK1.02: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Partial or Complete Loss of DC Power:

Redundant DC power supplies 3.8 9

295005 (APE 5) Main Turbine Generator Trip /

3 X

AK2.03: Knowledge of the relationship between Main Turbine Generator Trip and the following systems or components:

Recirculation system 3.5 41 295006 (APE 6) Scram / 1 X

AK3.01: Knowledge of the reasons for the following responses or actions as they apply to SCRAM: Reactor water level response 4.0 3

295016 (APE 16) Control Room Abandonment

/ 7 X

AA1.01: Ability to operate and/or monitor the following as they apply to Control Room Abandonment: RPS 3.8 2

295018 (APE 18) Partial or Complete Loss of CCW / 8 X

AA2.02: Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of Component Cooling Water: Cooling water temperature 3.7 60 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 X G2.4.50: Ability to verify system alarm setpoints and operate controls identified in the alarm response procedure. (Partial or Complete Loss of Instrument Air) 4.2 21 295021 (APE 21) Loss of Shutdown Cooling /

4 X

X AK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Loss of Shutdown Cooling: Adequate core cooling G2.4.41: Knowledge of the emergency action level thresholds and classifications (SRO Only) (Loss of Shutdown Cooling) 4.4 4.6 32 77

295023 (APE 23) Refueling Accidents / 8 X

X AK2.01: Knowledge of the relationship between Refueling Accidents and the following systems or components: Fuel handling equipment AA2.03: Ability to determine and/or interpret the following as they apply to Refueling Accidents: Airborne contamination levels 3.5 3.2 46 78 295024 High Drywell Pressure / 5 X

X EK3.02: Knowledge of the reasons for the following responses or actions as they apply to High Drywell Pressure: Suppression pool spray G2.4.2: Knowledge of system setpoints, interlocks and automatic actions associated with emergency and abnormal operating procedure entry conditions (High Drywell Pressure) 4.1 4.6 63 79 295025 (EPE 2) High Reactor Pressure / 3 X

EA1.10: Ability to operate and/or monitor the following as they apply to High Reactor Pressure: Reactor water cleanup system 2.8 10 295026 (EPE 3) Suppression Pool High Water Temperature / 5 X

EA2.03: Ability to determine and/or interpret the following as they apply to Suppression Pool High Water Temperature: Reactor Pressure 3.5 47 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 X

X G2.2.44: Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions (High Drywell Temperature)

EA2.03: Ability to determine and/or interpret the following as they apply to High Drywell Temperature: Reactor Water Level 4.2 4.0 16 80 295030 (EPE 7) Low Suppression Pool Water Level / 5 X

EK1.03: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Low Suppression Pool Water Level: Heat capacity 4.0 24 295031 (EPE 8) Reactor Low Water Level / 2 X

EK2.06: Knowledge of the relationship between Reactor Low Water Level and the following systems or components: High-pressure coolant injection (HPCI) 4.1 30 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X

X EK3.02: Knowledge of the reasons for the following responses or actions as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Boron injection G2.1.32: Ability to explain and apply system precautions, limitations, notes or cautions (Scram Condition Present and Reactor Power Above APRM Downscale or Unknown) 4.2 4.0 29 81

295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 X

EA1.08: Ability to operate and/or monitor the following as they apply to High Offsite Radioactivity Release Rate: MSIV leakage control 3.1 34 600000 (APE 24) Plant Fire On Site / 8 X

X AA2.05: Ability to determine and/or interpret the following as they apply to Plant Fire on Site: Ventilation alignment necessary to secure affected area Above K/A revised 8/5/2021 from AA2.10.

AA2.18: Assessment of control room habitability (SRO Only) 3.2 3.6 17 82 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 X G2.1.20: Ability to interpret and execute procedure steps (Generator Voltage and Electric Grid Disturbances) 4.6 36 K/A Category Totals:

3 3

3 3

4/4 4/3 Group Point Total:

20/7

Form 4.1-BWR BWR Examination Outline Page 3 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

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

K/A Topic(s)

IR 295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 X

AA1.06: Ability to operate and/or monitor the following as they apply to High Reactor Pressure: Shutdown cooling system (RHR shutdown cooling mode) 3.6 54 295008 (APE 8) High Reactor Water Level / 2 X

AA2.01: Ability to determine and/or interpret the following as they apply to High Reactor Water Level: Reactor water level 4.4 83 295009 (APE 9) Low Reactor Water Level / 2 X G2.4.18: Knowledge of the specific bases for emergency and abnormal operating procedures (Low Reactor Water Level) 4.0 84 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 X

AA2.01: Ability to determine and/or interpret the following as they apply to High Suppression Pool Water Temperature:

Suppression pool temperature 4.3 42 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15**) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 X G2.1.30: Ability to locate and operate components, including local controls (Abnormal Offsite Release Rate) 4.4 37 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 X

AK1.05: Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to Inadvertent Containment Isolation: Loss of drywell/containment cooling 3.5 13 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 X

EK2.07: Knowledge of the relationship between High Suppression Pool Water Level and the following systems or components: Drywell/containment water level 3.6 27 295032 (EPE 9) High Secondary Containment Area Temperature / 5

295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 X

EK3.06: Knowledge of the reasons for the following responses or actions as they apply to High Secondary Containment Area Radiation Levels: Operating ventilation systems 3.6 28 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 X

EA2.01: Ability to determine and/or interpret the following as they apply to Secondary Containment High Differential Pressure: Secondary containment pressure 3.9 85 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:

1 1

1 1

1/2 1/1 Group Point Total:

6/3

Form 4.1-BWR BWR Examination Outline Page 4 Plant SystemsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode X

K1.16: Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI:

Injection Mode and the following systems:

Component cooling water systems 2.7 25 205000 (SF4 SCS) Shutdown Cooling X

X K2.01: Knowledge of electrical power supplies to the following: Pump motors K2.02: Knowledge of electrical power supplies to the following: Motor-operated valves 3.6 3.3 8

22 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection X

K3.04: Knowledge of the effect that a loss or malfunction of the High-Pressure Coolant Injection System will have on the following systems or system parameters: Reactor power 3.6 31 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray X

K4.05: Knowledge of Low-Pressure Core Spray System design features and/or interlocks that provide for the following:

Pump minimum flow 3.4 33 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control X

X K5.01: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Standby Liquid Control System: Effects of the moderator temperature coefficient of reactivity on boron K6.06: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Standby Liquid Control System:

Redundant reactivity control system 3.0 3.6 48 6

212000 (SF7 RPS) Reactor Protection X

X K6.10: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Reactor Protection System:

Reactor/turbine pressure regulating system G2.1.20: Ability to interpret and execute procedure steps (Reactor Protection System) 3.5 4.6 35 86 215003 (SF7 IRM)

Intermediate-Range Monitor X

A1.08: Ability to predict and/or monitor changes in parameters associated with operation of the Intermediate Range Monitor System, including: IRM back panel switches 3.1 12

215004 (SF7 SRMS) Source-Range Monitor X

A2.02: Ability to (a) predict the impacts of the following on the Source Range Monitor System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: SRMS inoperable condition 3.4 43 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X

A3.03: Ability to monitor automatic operation of the Average Power Range Monitor/Local Power Range Monitor System, including:

Meters and recorders 3.6 4

217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X

X A4.12: Ability to manually operate and/or monitor in the control room: Turbine speed control A2.14: Ability to (a) predict the impacts of the following on the Reactor Core Isolation Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Rupture disc failure: exhaust-diaphragm 3.9 3.6 11 87 218000 (SF3 ADS) Automatic Depressurization X G2.1.23: Ability to perform general or normal operating procedures during any plant condition (Automatic Depressurization System) 4.3 38 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff X

X K1.04: Knowledge of the physical connections and/or cause and effect relationships between the Primary Containment Isolation System/Nuclear Steam Supply Shutoff and the following systems: HPCI G2.4.31: Knowledge of annunciator alarms, indications, or response procedures (Primary Containment Isolation/Nuclear Steam Supply Shutoff) 4.2 4.1 40 94 239002 (SF3 SRV) Safety Relief Valves X

K2.01: Knowledge of electrical power supplies to the following: SRV solenoids 3.7 26 259002 (SF2 RWLCS) Reactor Water Level Control X

X K3.04: Knowledge of the effect that a loss or malfunction of the Reactor Water Level Control System will have on the following systems or system parameters:

Recirculation system A2.02: Ability to (a) predict the impacts of the following on the Reactor Water Level Control System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of any number of reactor feedwater flow inputs 3.3 3.8 5

44 261000 (SF9 SGTS) Standby Gas Treatment X

K4.02: Knowledge of Standby Gas Treatment System design features and/or interlocks that provide for the following:

Charcoal bed decay heat removal 3.0 18

262001 (SF6 AC) AC Electrical Distribution X

K5.02: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the AC Electrical Distribution: Breaker control power 3.5 45 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

X X

K6.02: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Uninterruptible Power Supply (AC/DC):

DC electrical distribution 291008, K1.06: Interpreting one-line diagram of control circuitry (Uninterruptible Power Supply (AC/DC))

3.4 3.6 74 70 263000 (SF6 DC) DC Electrical Distribution X

A1.02: Ability to predict and/or monitor changes in parameters associated with operation of the DC Electrical Distribution, including: Lights and alarms 3.3 14 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG X

X A2.08: Ability to (a) predict the impacts of the following on the Emergency Generators and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Initiation of emergency generator room fire protection system A2.10: Ability to (a) predict the impacts of the following on the Emergency Generators and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: LOCA 3.1 4.4 55 89 300000 (SF8 IA) Instrument Air X

A3.04: Ability to monitor automatic operation of the Instrument Air System, including:

Automatic isolation 3.4 50 400000 (SF8 CCS) Component Cooling Water X

X A4.01: Ability to manually operate and/or monitor in the control room: CCW indications and control G2.2.42: Ability to recognize system parameters that are entry-level conditions for technical specifications (Component Cooling Water System) 3.8 4.6 49 90 510000 (SF4 SWS*) Service Water (Normal and Emergency)

X G2.1.2: Knowledge of operator responsibilities during any mode of plant operation (Service Water (Normal and Emergency))

4.1 51 K/A Category Point Totals:

2 3

2 2

2 3

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

26/5

Form 4.1-BWR BWR Examination Outline Page 5 Plant SystemsTier 2/Group 2 (RO/SRO)

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

K/A Topic(s)

IR 201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer X

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

Pushbutton indicating switches 3.2 53 202001 (SF1, SF4 RS) Recirculation X

K5.06: Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the Recirculation System: ATWS RPT 3.8 20 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup X

A2.05: Ability to (a) predict the impacts of the following on the Reactor Water Cleanup System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations:

Abnormal valve position 3.0 91 214000 (SF7 RPIS) Rod Position Information X

K6.01: Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the Rod Position Information System: RPIS power supply 3.2 52 215001 (SF7 TIP) Traversing In-Core Probe X

A1.01: Ability to predict and/or monitor changes in parameters associated with operation of the Traversing In-Core Probe, including: Area radiation levels 3.1 19 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries X

A3.04: Ability to monitor automatic operation of the Primary Containment System and Auxiliaries, including:

Containment/drywell response during LOCA 4.2 56 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode

230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode X

K1.01: Knowledge of the physical connections and/or cause and effect relationships between the RHR/LPCI: Torus/Suppression Pool Spray Mode and the following systems: Primary containment 3.9 57 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup X

A2.09: Ability to (a) predict the impacts of the following on the Fuel Pool Cooling and Cleanup and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: AC electrical power failures 3.4 58 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating X 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 (Reactor/Turbine Pressure Regulating) 4.1 92 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater X

K4.12: Knowledge of Feedwater System design features and/or interlocks that provide for the following: RFP start permissives 3.1 59 268000 (SF9 RW) Radwaste X 291007, K1.07: Principles of demineralizer operation (Radwaste) 2.5 69 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection X

K2.02: Knowledge of electrical power supplies to the following: Fire pumps Above K/A revised 8/5/2021 from K3.09.

3.2 1

288000 (SF9 PVS) Plant Ventilation X

A2.05: Ability to (a) predict the impacts of the following on the Plant Ventilation Systems and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Extreme outside weather conditions 2.9 93 290001 (SF5 SC) Secondary Containment

290003 (SF9 CRV) Control Room Ventilation X

K3.06: Knowledge of the effect that a loss or malfunction of the Control Room Ventilation will have on the following systems or system parameters: Control room radioactivity Above K/A revised 8/5/2021 from K2.04.

3.5 39 290002 (SF4 RVI) Reactor Vessel Internals 510001 (SF8 CWS*) Circulating Water K/A Category Point Totals:

1 1

1 1

1 1

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

11/3

Form 4.1-BWR BWR Examination Outline Page 6 Generic Knowledge and AbilitiesTier 3 (RO/SRO)

Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements 3.8 7

2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, or switches 4.1 65 2.1.36 Knowledge of procedures and limitations involved in core alterations 4.1 88 Subtotal 2

1

2. Equipment Control 2.2.22 Knowledge of limiting conditions for operation and safety limits 4.0 62 2.2.35 Ability to determine technical specification mode of operation 3.6 67 2.2.4 (Multi-unit license) Ability to explain the variations in control room layouts, systems, instrumentation, or procedural actions between units at a facility 3.6 95 2.2.19 Knowledge of maintenance work order requirements 3.4 96 Subtotal 2

2

3. Radiation Control 2.3.12 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 3.2 64 2.3.6 Ability to approve liquid or gaseous release permits 3.8 97 2.3.14 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 analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only) 3.8 98 Subtotal 1

2

4. Emergency Procedures/Plan 2.4.32 Knowledge of operator response to loss of annunciators 3.6 61 2.4.28 Knowledge of procedures relating to a security event (ensure that the test item includes no safeguards information) 4.1 99 2.4.38 Ability to take actions required by the facility emergency plan implementing procedures, including supporting or acting as emergency coordinator 4.4 100 Subtotal 1

2 Tier 3 Point Total 6

7

Form 4.1-BWR BWR Examination Outline Page 7 TheoryTier 4 (RO)

Category K/A #

Topic RO IR

1. Reactor Theory 292001 K1.02 Define prompt and delayed neutrons 3.1 71 292005 K1.12 Describe effects of deep and shallow control rods on axial and radial flux distribution 2.9 75 292007 K1.03 Given a curve of K-effective versus core age, state the reasons for maximum, minimum, and inflection points.

2.7 72 Subtotal 3

2. Thermodynamics 293003 K1.22 Explain the usefulness of steam tables to the control room operator 3.2 73 293005 K1.06 Describe how changes in system parameters affect thermodynamic efficiency 2.6 66 293007 K1.03 Heat Transfer, Explain the manner in which fluid films affects heat transfer 2.8 68 Subtotal 3

Tier 4 Point Total 6

Form 4.1-1 Record of Rejected Knowledge and Abilities Tier /

Group Randomly Selected K/A Reason for Rejection RO 1/1 600000 (APE 24) Plant Fire On Site / 8 AA2.10 Ability to determine and/or interpret the following as they apply to Plant Fire on Site: Time limit of long-term-breathing air system for control room.

Rejected K/A AA2.10 on the premise that there is not a long-term breathing air system at Browns Ferry, and there are no time-limits specified in plant procedures for breathing air systems; therefore, a valid question cannot be written for this K/A.

Resolution: Replaced K/A AA2.10 with a randomly chosen K/A from the same Plant Systems Section, yielding AA2.05: Ventilation alignment necessary to secure affected area.

RO 2/2 286000 (SF8 FPS) Fire Protection K3.09 Knowledge of the effect that a loss or malfunction of the Fire Protection System will have on the following systems or system parameters: AC electrical distribution systems.

Rejected K/A K3.09 on the premise that the fire protection system has no system inter-relations with AC Distribution at Browns Ferry, therefore a valid question cannot be written for this K/A.

Resolution: Replaced K/A K3.09 with a randomly chosen K/A from the same Plant System, section K2, yielding K2.02: Knowledge of electrical power supplies to the following: Fire pumps.

RO 2/2 290003 (SF9 CRV) Control Room Ventilation K2.04 Knowledge of electrical power supplies to the following:

Control room HVAC logic.

Rejected K/A K2.04 on the premise that the topic is minutia, therefore a valid question cannot be written for this K/A.

Resolution: Replaced K/A K2.04 with a randomly chosen K/A from the same Plant System, section K3, yielding K3.06: Knowledge of the effect that a loss or malfunction of the Control Room Ventilation will have on the following systems or system parameters: Control room radioactivity

Facility: Browns Ferry Exam Date: 5/16/2022 1

JPM # or title 2

Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6

U/E/S 7

Explanation LOD REF IC TSK CUE CS TL RO COO-1 A

N 3

S

1. 556, DW leakage calc (M)

- Task standard: and determine if leak rates are met IAW (?) TS AC (modified)

- Validation time appears exceptionally long for directed task (revised)

RO COO-2 A

N 3

S

1. 661, License Reactivation

- revise RO2, Pre-activation meeting attendees block to read Shift Manager And Ops Superintendent

- Prep Week position chart update (modified)

RO EC A

N 3

S

1. 680, Perform JP SR (M)

- Can 2-XR-68-50 Red/Green pen indications be provided as a control board indication?

- JPM Steps 1 through 4 are not CRITICAL

- JPM Step 9 is not critical, band is now 0-2 Mlbm/hr

- Discussion required on how to coordinate administration of this JPM as examiner cues (JPM Steps 21 and 23) will not be performed as written

- Will utilize original EC JPM with JPM Steps 21-23 and evaluate during Prep Week RO RC A

N 3

S

1. 682, Review RWP (P)

- same JPM administered 2021 exam

SRO COO-1 A

N 3

S

1. 556-SRO, DW leakage calc (M)

SRO COO-2 A

N 3

S

1. 753-SRO, Prot Equip Reqs

- Very low LOD for this JPM. Initiating cue and stem information provide component (SBGT) and cue required answers (uncomplicated TS and Prot Eq matrix lookup)

- Can this JPM be modified (with same given information), for applicant to identify how PE would be placed for pending SBGT tagout (i.e.

completion of NPG-SPP-07.3.4, Attachment 2, tagged component & location/method columns used as listed critical steps)

- JPM modified

- Remove initiating cue concerning 3.0.3 entry

- Modify third bullet to read: Additional/Modified Protected Equipment Requirement(s) (if any)

- Modify answer choices for designated PE, CRITICAL to identify DG-3D and SBGT-A with note that applicant can identify SBGT-C (but not critical)

- JPM Step 1 no longer critical

- 3D EDG INOP with appropriate TSs entered SRO EC A

N 3

S

1. 746-SRO, Review SR (M)

- modified from 2021-301 performance (surv reading/TS)

SRO RC A

N 3

S

1. 749-SRO, ODCM Release Reqs (P)

- same JPM administered 2021 exam SRO EP A

N 3

S

1. 752-SRO, EAL class

- Is tornado strike in switchyard classified as within the protected area at BFN? (i.e. plausibility of HU3). Also, SA1. (discussion)

- Use original IC, no other changes

1 JPM # or title 2

Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6

U/E/S 7

Explanation LOD REF IC TSK CUE CS TL A, SF1 U

S Y

3 S

1. 708A, ATWS boron inj per APP-3A B, SF2 U

S Y

3 S

1. 751A, Align RCIC to SP per APP-5C C, SF4 U

S Y

3 S

1. 627A, Align HPCI to Press Cont per App-11C (Steam Leak)

- Initiating cue requires a directed applicant target for RPV pressure control (i.e. lower/control RPV pressure to x#), needed when JPM Step 12 reached

- Control band (800-1000#) directed in Initiating Cue D, SF5 S

N 3

S

1. 750, Vent DW

- What is the basis for the second bullet? DW-SP d/p is abnormal? Cant the applicant make that determination using simulator indications?

(modified)

- 3rd bullet needs completion to statement Section 4.0 is complete(?) (modified)

- Insert new initial condition that states another operator is standing by for data logging (as necessary) (can remove examiner cue in JPM Step 12) (modified)

E, SF6 S

N 3

S

1. 725, Xfer 2C 4kV Unit Bd from start bus to USST

- This JPM can be completed after JPM Step 10 (another operator will continue from here), field communication with little evaluation value (modified)

Form 2.3 -3 Operating Test Review Worksheet (JPMs)

F, SF7 S

Y 3

S

1. 290A, RPS SCRAM functional test

- Add in expected annunciators at JPM Step 14 (i.e. Rod Drift alarm, RWM Trouble(?), B Logic alarm, etc), dont need clarifying/detailed annunciator info just a short list to be on the lookout for G, SF8 RO Only S

N 3

S

1. 39, Align CAD to DW pneumatics per APP-8G

-Discussion, JPM can likely be terminated at JPM Step 9 (modified)

H, SF9 S

Y 3

S

1. 55A, Emergency Venting 1o cont per APP-13

- Is it expected that applicants will be directing JPM Step 8 examiner cue via call/radio? Or directly to examiner? There may need to be additional scripting for this activity (i.e. 30 seconds after being dispatched report RB 565 elev not accessible), prep week discussion point I, SF6 RCA, U I

N 3

S

1. 754, Elec comp align following CR abandon

- This JPM can be terminated after JPM Step 3.

It appears that all components for this procedure are located in the same SWGR room? (modified)

J, SF7 U

I N

3 S

1. 314, Perform APP-2 (ARI defeat interlock)

K, SF2 I

N 3

E

1. 755, Perform APP-16L (BYP HPCI Hi Temp interlock)

- Have a picture available (doesnt need to be included in JPM guide) for Prep Week discussion on contact relay insulating sleeves

Form 2.3-3 Instructions for Completing the JPM Table

1. Enter the JPM number and/or title.

2. Enter the type of JPM(S)imulator, (P)lant, or (A)dministrative.

3. Enter (Y)es or (N)o for an Alternate Path JPM.

4. Rate the level of difficulty (LOD) of each JPM using a scale of 1-5 (easy-difficult). A JPM containing less than two critical steps, a JPM that tests solely for recall or memorization, or a JPM that involves directly looking up a single correct answer is likely LOD = 1 (too easy).

Conversely, a JPM with over 30 steps or a JPM that takes more than 45 minutes to complete is likely LOD = 5 (too difficult).

5. Check the appropriate block for each JPM error type, using the following criteria:

LOD = 1 or 5 is unsatisfactory (U).

REF: The JPM lacks required references, tools, or procedures (U).

IC: The JPM initial conditions are missing or the JPM lacks an adequate initial cue (U).

CUE: The JPM lacks adequate evaluator cues to allow the applicant to complete the task, or the evaluator cues are subjective or leading (U).

TSK: The JPM lacks a task standard or lacks completion criteria for a task standard (U).

CS: The JPM contains errors in designating critical steps, or the JPM lacks an adequate performance standard for a critical step (U).

TL: The JPM validation times are unreasonable, or a time-critical JPM lacks a completion time (U).

6. Mark the JPM as unsatisfactory (U), satisfactory (S), or needs enhancements (E). A JPM is (U) if it has one or more (U) errors as determined in step 5. Examples of enhancements include formatting, spelling, or other minor changes.

7. Briefly describe any JPM determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a satisfactory (S) resolution on this form.

Form 2.3-3 Operating Test Review Worksheet (Scenarios)

Facility: Browns Ferry Scenario: NRC-1 Exam Date: 5/16/2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS 1, Lower power, ATC S

- Remove NRC/driver cues on (D-2) Event 1, Pg 1 2, 2C CBP s/u, BOP S

- Remove NRC/driver cues on Event 2, Pg 1 3, HPCI init, BOP, MC x

S

- Just to clarify the TS call here (due to concurrent RHR inop) is C.1&C.2 & D.1 OR D.2.

4, LOP RHR Inbd Spray vlv, TS only x

S

- Discussion required. The way this event is scripted may not be operationally valid. Why is WCC directing ECCS component status?

Control of equipment status would normally be run from the Control Room. Without flat out instructing applicants that this WCC component manipulation requires TS evaluation, how would an applicant crew conclude that one is even required?

- Event may need to be rescripted for WCC to request tagout of FCV-74-61 and for applicant crew to authorize activity. Like how it would be done normally.

- Or insert additional TS evaluation elsewhere (event 5??) in scenario and remove this event.

- TS only, no verifiable action

- Look to Scenario 4 Event 3.

5, Loss of Unit Preferred, ATC

?

S

- Where is the verifiable action claimed for this event? Are you crediting the CRD actions? Where is the TS associated with loss of power (distribution) for this event?

6, Earthquake/

FW leak/

LOCA, Major

CT1, CT2 S

- Critical Tasks:

1. To prevent an uncontrolled RPV depressurization when Reactor Water Level cannot be restored and maintained above (-) 122 inches, inhibit ADS. - this is LOCA scenario where ED is required for mitigation strategy, why is this designated as a CT?, doesnt meet CT criteria, new CT required (revised)

2. With an injection system(s) operating and the Reactor shutdown and at pressure, after Reactor Water Level lowers to (-)162 inches, direct Emergency Depressurization before Reactor Water Level lowers to (-)180 inches.- meets CT criteria (2) 7, Elec ATWS, ATC S

- Auto inserted on man SCR 8, RCIC controller malfn, BOP S

- Auto initiation at 500 rpm

Facility: Browns Ferry Scenario: NRC-2 Exam Date: 5/16/2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS 1, BYP vlv test, BOP S

- Discussion on need for NRC/Driver cues event 1 pg 1, what about using the turnover sheet?

- Use SR vs OI steps 2, BYP vlv TS eval, TS only x

S

- No verifiable action, TS only 3, APRM fails high, ATC S

- low level event 4, CRD pump trip, ATC, MC S

- Verify designated applicants for scenarios 1 (BOP, MC) & 2 (ATC, MC) 5, faulted RCIC isolation, BOP x

S

- PCIV and RCIC specs 6, MT vibs, ATC S

- Power reduction

- This event is credited to BOP operator in error (board response performed by ATC operator) 7, ATWS on RPS demand, major

CT1, CT2 S

- Modify D-2 to add timekeeping spaces for RR pump stops for CT time tracking (130 sec)

- Critical Tasks:

1. When Reactor Power is greater than 5% or unknown during an ATWS, STOP and PREVENT all injection into the Reactor except for RCIC, CRD, and SLC within 130 seconds of the loss of forced recirculation to prevent possible fuel damage. - meets CT criteria (2)

2. With a Reactor SCRAM required and the Reactor not shutdown, to prevent an uncontrolled Reactor depressurization and subsequent power excursion inhibit ADS or control Reactor Water Level such that no automatic ADS actuation occurs. - meets CT criteria (2, potentially 3 due to reactivity excursion depending on scope/duration of ATWS) 8, BYP vlv fail, BOP S

Facility: Browns Ferry Scenario: NRC-3 Exam Date: 5/16/2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS 1, TGOP test, BOP S

- NRC/driver notes 2, CRD flow xmitter fail hi, ATC S

- Why is this event not tagged as manual control of automatic function?

3, 3A SLC pump, TS only x

S

- Can this event be modified to provide SLC inoperability as an alarm (vs a field call of cracked/empty sight-glass), i.e. loss of tank heater/distribution panel

- Modify to trip bkr (booth) and call control room to inform 4, SRV fails open, BOP S

5, power reduction, ATC S

- Can SRV cycling be performed before directed downpower IAW rules of procedure usage? Complicate flow of scenario?

6, CR drift out, ATC x

S 7, SCW pump trip, BOP, MC CT1 S

- Critical Tasks:

1. Start the Standby Stator Cooling Water Pump before the Turbine Trip Timer times out and trips the Main Turbine, resulting in an automatic Reactor SCRAM. - This CT doesnt meet Rev 12 CT criteria. New CT required. (modified)

- This is a BOP only MC scenario 8, SRV fails open, major CT2 S

- Critical Tasks:

2. When Drywell Sprays are required, initiate Drywell Sprays while in the safe region of the Drywell Spray Initiation Limit Curve to prevent challenging Primary Containment negative pressure capability. - The way this CT is worded doesnt make sense. When directed to perform APP-17B, applicant crew will already be within the green area of Curve 5 (or very close to it). Initiation of DW spray wont be to prevent challenging 1o containment negative pressure (thats a basis for securing DW spray, but different discussion). I imagine the CT here is for the DW Spray to be initiated to prevent challenging peak containment pressure during blowdown conditions. i.e.

perform action that is essential to mitigate degrading DW LOCA conditions. - CT criteria (2), rewording required 9, DW spray fail, BOP S

10, 3C RFPT trip, ATC S

Facility: Browns Ferry Scenario: NRC-4 Exam Date: 5/16/2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS 1, Swap vent fans, BOP S

- NRC/driver cues 2, SPE inad isol, BOP, MC S

- Multiple MC scenario 3, RHRSW TS, TS only x

S

- Remove and within three (3) minutes the tags will be hanging from event 3 pg 1 driver cue.

Inform the NUSO that a team has been dispatched to open the ckt bkr and hang tags

- Look to Scenario 1 Event 4.

- What is the TS call here? Looks like A.2 only requires entry but guide is unclear.

4, 2C Unit Bd trip, BOP, ATC, MC S

- Event credit cannot be obtained by multiple board positions for the same event. This event is credited to both the ATC (likely CRD actions) and BOP (verifiable action?) positions. If credit for both positions is desired, this event, with position specific verifiable action, must also be split out.

- Multiple MC scenario

- This appears to be an ATC -only event as written (not sure about basis for multiple D-1 designations) 5, 2B RR pump trip, ATC x

S

- There are typically more actions when responding to a RR pump loss. I.e. request for RE action. What procedure governs making the transition from two loop to single loop operations (i.e. when to make RE request)?

- Event listed as 2B RR pump trip, yet next event is for loss of 3B pump, copy-paste error?

6, Urgent load reduction, ATC S

7, SP WL lo, major

CT1, CT2, CT3 S

- Critical Tasks:

1. With Adequate Core Cooling available, lock out HPCI when Suppression Pool Level cannot be maintained above 12.75 feet to prevent Primary Containment damage. - meets CT criteria (2)

2. Manually insert a Reactor SCRAM before Suppression Pool Level reaches 11.5 feet, to reduce the amount of energy in the vessel on a lowering Suppression Pool Water Level. - wrong reason cited.

(revised) SCRAM is directed here to prevent depress on a non-SCR reactor. Depress on a non-SCR reactor can complicate basis for depress (i.e. limit energy deposition into compromised SP). CT is valid based on criteria (2) but modification required. Ref EOIPM 0-V(G), pg 127

3. Emergency Depressurization is performed when Suppression Pool Water Level cannot be maintained above 11.5 feet to minimize the adverse effects on Suppression Pool heat capacity.- meets CT criteria (2) 8, Inad MSIV closure, BOP S

- All scenarios up to this point have post-major events that meet ES-3.3, B.2.d (pg 8):

- Im not seeing how this event influences mitigation strategy.

Applicant crew is already being driven to ED based on non-isolable unrecoverable SP level drop. MSIVs essentially remove anticipation (which isnt required anyway). Event modification required.

- Modify event to drop power from ECCS (CS &/or RHR) whichever will be needed for core recovery. (modified)

Facility: Browns Ferry Scenario: NRC-5 (3%)

Exam Date: 5/16/2022 1

Scenario Event ID/Name:

2 Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS 1, Warm 3B RFPT, BOP, MC S

- NRC/driver cues

- NRC note prior to step [18] requires modification (pg3), this information should be apparent to applicants (i.e. proc portions already completed, turnover sheet, etc), no direction from exam team

- Why does this event have an MC designation?

2, CR w/d, ATC S

3, CR difficult, ATC S

- What is significance of applicant failing to return CRD DRIVE WTR HDR DP back to a normal value before continuing rod movement at next rod? (discussion) 4, CS inadv s/u, BOP x

S 5, 3A stack dil fan trip FTS, BOP, MC S

6, RPV Press A1 fail hi (1/2 SCR), ATC x

S

- Appears to be a lot of phone calls for this failure, have to see during prep week.

7, LOOP, major CT1 S

- Critical Tasks:

1. With a Loss of Offsite Power and a Station Blackout caused by the failure of two Emergency Diesel Generators (EDGs) to automatically start and tie on to their respective 4KV Shutdown Boards, the crew restores power to one 480V Shutdown Board to exit Station Blackout within 20 minutes of the loss of power. - What bad thing occurs at T+20 min? There could be a CT tie here using criteria (2), but not with the as-stated bounding criteria. Also, cant use SBO coping time analysis here since that timeframe is much too long to justify CT.

8, 3EA EDG fails to tie, BOP, MC S

- Why isnt this event tied to a CT? (Revised) 9, EECW pump FTS, BOP, MC CT2 S

- Critical Tasks:

2. With a loss of EECW Pumps due to a Loss of Offsite Power, the crew restores EECW Flow to the EDGs within 8 minutes. -

insufficient information present to evaluate CT adequacy (basis for 8 minutes), CT adequacy hinges on boundary criteria in Rev 12

Form 2.3-3 Instructions for Completing the Scenario Table

1. For each scenario, enter the scenario event names and descriptions.

2. Review the individual events contained in each scenario, and identify and mark event errors:

The scenario guide event description is not realistic/credibleunsatisfactory (U).

The scenario guide event description lacks adequate crew/operator performance standardsneeds enhancement (E).

The scenario guide event description lacks verifiable actions for a credited normal event, reactivity event instrument/component malfunction, or technical specification (TS) event (or a combination of these) (U).

The scenario guide event description incorrectly designates an event as a critical task (i.e., a noncritical task labeled as critical or a critical task labeled as noncritical). This includes critical tasks that do not meet the critical task criteria (i.e., the critical task does not have a measurable performance standard) (U).

The scenario guide event description incorrectly designates entry into TS actions when not required or does not designate entry into TS actions when required (U).

3. Based on the outcome in step 2, mark the scenario event as unsatisfactory (U), satisfactory (S), or needs enhancements (E). An event is (U) if it has one or more (U) errors as determined in step 2. Examples of enhancements include formatting, spelling, or other minor changes.

4. Briefly describe any scenario event determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario event is marked by a satisfactory (S) resolution on this form.

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 1

H 3

M BF 2021 S

Rev 0:

- Revise question stem to read Unit 2 was operating when the following conditions occurred:

- Note: Second half questions load line answer revised with 2-AOI-68-1A Rev 11, 3-23-2019 Rev 1:

- Comments incorporated. Question is SAT 2

H 3

M Bank S

Rev 0:

- Insert forward slash / into procedure title (.. /Station Blackout) in question stem

- Revise second half question be manually transferred from the Main Control Room )

Rev 1:

- Comments incorporated. Question is SAT 3

H 3

B S

Rev 0: REFERENCE

- As-written, this question doesnt meet the listed Q46 KA. Both halves of this question are related to the impact that loss of an ECCS ATU inverter has on RCIC/HPCI. KA concerns applicant knowledge of how a loss of DC electrical distribution affects UPS.

- A way to hit this KA would be to test applicant knowledge of DC/UPS interrelationship. (ensure no overlap with Q#47)

Rev 1:

- Question swapped with DRAFT Q3 KA (this was originally DRAFT Q46, now Q3). Question is SAT 4

H 3

N S

Rev 0:

- Question is SAT 5

H 3

M Bank S

Rev 0:

- Remove to prevent Reactor Vessel overfill from question statement.

Rev 1:

- Comments incorporated. Question is SAT 6

F 3

N S

Rev 0:

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 7

H 3

N S

Rev 0: REFERENCE

- First half question discussion on KA applicability.

Rev 2:

- Additional information provided in justification.

Question meets KA.

- No need for both bullets 1 (annunciator) and 2 (145F indication) for this question, remove one (recommend removing #2).

Rev 3:

- Question revised. Question is SAT 8

F 3

M BF 2021 S

Rev 0: REFERENCE

- Revise first half question to read, in accordance with the given appropriate Alarm Response Rev 1:

- Comments incorporated. Question is SAT 9

H 3

M BF 2019 S

Rev 0:

- Revise second half question to read: In accordance with 2-OI-74, Residual Heat Removal System (RHR),

the normal Cold Shutdown Reactor Water Level band is maintained to prevent __(2)__.

Rev 1:

- Comments incorporated. Question is SAT 10 H

3 B

BF 2021 S

Rev 0:

- Justification for answer choice C may not be technically correct (2nd rod selected). It is my understanding that selection of a second control rod is not required for refuel bridge interlock to stop when travel over the core is attempted. (i.e. only a single rod not fully inserted stops the bridge)

Rev 2:

- Justification revised. Question is SAT 11 F

3 N

S Rev 0:

- Revise question statement to read, In accordance with the PC Pressure leg of 2-EOI-2, Primary Containment Control and EOI-2, Primary Containment Control Bases, Suppression Chamber Sprays are Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 12 H

3 N

S Rev 0:

- As-written, this question doesnt meet the listed KA.

Both halves of this question are related to the impact that low RPV water level has on RWCU and RPS.

(EHC status information not needed to answer the question, unrelated to KA)

Rev 2:

- Question revised. Question is SAT 13 H

3 M

BF 2021 S

Rev 0: REFERENCE (provided)

- Question is SAT 14 H

3 N

S Rev 0:

- Second half question statement (AUTO RPS actuation setpoint) does not relate to the first half question or the KA.

Rev 2:

- Question revised. Question is SAT 15 H

3 M

BF 2021 S

Rev 0:

- Second half question is unrelated to KA and may not be a technically correct statement. As stated in the references provided (highlighted and un-highlighted portions), HPCI exhaust uncovery due to low SP water level presents a containment adequacy (integrity) concern, not a SP heat capacity concern.

Rev 2:

- Question revised. Question is SAT 16 H

3 B

Bank S

Rev 0:

- Question is SAT 17 H

3 B

BF 2015 S

Rev 0:

- Revise question statement to add IAW EOI-1A,,

and EOI-1A ATWS RPV Control Bases,.

Rev 1:

- Comments incorporated. Question is SAT.

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 18 H

3 M

BF 2018 S

Rev 0: REFERENCE

- Revise given with appropriate in first half question statement.

- First half distractors C.1/D.1 are implausible with the provided annunciators, MSL Rad High-High in conjunction with OG Avg Annual Release Limit Exceeded and the second half question (1.5x/3x normal background).

Rev 2:

- Adding the MSL Rad HI alarm (window 7) does not improve plausibility of first or second half distractors.

Its inclusion cues the correct answer even more.

- Key fix for this question appears to be querying which alarm requires MSIV closure.

Rev 3:

- Question revised. Question is SAT 19 H

3 M

BF 2021 S

Rev 0:

- Remove for damper realignment from first half answer choices.

- Use of the term ORDER OF PREFERENCE in the second half question statement is confusing since each half answer choice contains only one option (as an answer).

- The second half question doesnt appear to be technically correct. Per 0-AOI-26-1, Reactor [step 15.1] and Refuel [step 15.2] zone ventilation is to be started as necessary. Based on the wording of the question, an applicant can contend that use of SGT

[step 15.3] was necessary while the others were not.

- Can correct second half question by modifying to read:

If the Unit 1 Reactor Building needs smoke removal with a Reactor Zone High Pressure Alarm in, operators will be directed to utilize Unit 1 Reactor Zone Supply and Exhaust Fans/ SGT Rev 1:

- Comments incorporated. Question is SAT 20 H

3 B

BF 2018 S

Rev 0:

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 21 H

3 M

Bank S

Rev 0: REFERENCE

- Revise given with appropriate in question statement.

Rev 1:

- Comments incorporated. Question is SAT 22 F

3 N

S Rev 0:

- Question is SAT 23 H

3 M

BF 2021 S

Rev 0: REFERENCE

- Revise the first half question statement to read: One minute after the given conditions above,

- Revise second half question to read: If directed to manually restrain Rev 1:

- Comments incorporated. Question is SAT 24 F

3 B

BF 2021 S

Rev 0:

- Question is SAT 25 H

3 M

BF 2021 S

Rev 0:

- Question is SAT 26 H

3 M

BF 2019 S

Rev 0:

- Question is SAT 27 F

3 M

Bank S

Rev 0:

- Revise question stem to read: To place Suppression Pool Cooling in service, which ONE of the following correctly identifies which RHRSW Pumps are available to provide RHR Heat Exchanger cooling.

- Consider removing the bolding of AND in all answer statements (its presence marginalizes use of the bolded word ONLY, which is critical to answer this question)

- Does the justification statement for answer choice B conflict with whats written for answer choice C (correct answer)? (it implies D1 and D2 are Div 1 pumps), correct answer keyed??

Rev 1:

- Comments incorporated. Question is SAT 28 H

3 M

BF 2021 S

Rev 0:

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 29 H

3 N

S Rev 0:

- Question is SAT 30 H

3 N

S Rev 0:

- Revise the word indicated for the first half question to match its second half question usage:

INDICATED Rev 1:

- Comments incorporated. Question is SAT 31 F

3 M

Bank S

Rev 0:

- Question is SAT 32 F

3 B

Hope Crk 2010 S

Rev 0:

- Question is SAT 33 H

3 B

BF 2013 S

Rev 0: REFERENCE

- Graphic is needed to answer both halves of the provided question. Remove the two listed bullet points and annunciator.

- Revise the word conditions in opening statement &

in first half question statement to indications Rev 2:

- SLC pump 1A bullet required?

Rev 3:

- Question revised. Question is SAT 34 F

3 N

S Rev 0:

- Keyed answer may not be technically correct under all cases. Load Reject sensing signal is dependent on Turbine 1st stage pressure, which may or may not actuate directly at an indicated 26% RTP. I have experience where the bypass alarm failed to clear at either of the official RTP/ETS press setpoints.

- Revise first half question to read: The Generator Load Reject Turbine Control Valve (TCV) Fast Closure RPS SCRAM signal is AUTO bypassed at 5/

50% RTP.

Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 35 H

3 N

S Rev 0:

- 2nd half question tests a very low-level concept where distractors are eroded by use of the word ONLY.

- For plausibility of A.2 and C.2 answer choices, revise the word AND to be OR

- Another way to examine this concept would be to modify question to IRM A bypass operations can/

can NOT be performed on Panel 9-12.

Rev 1:

- Comments incorporated. Question is SAT 36 F

3 M

Bank S

Rev 0:

- Cueing of control board status based on use of the word simultaneously (this information already provided in bullet one)

- Revise second half question to read: SRM A will/

will NOT be bypassed by a Control Room Operator.

Rev 1:

- Comments incorporated. Question is SAT 37 F

3 B

BF 2008 S

Rev 0:

- Question is SAT 38 F

3 N

S Rev 0:

- Question is SAT 39 H

3 M

BF 2018 S

Rev 0:

- Question is SAT 40 H

3 N

S Rev 0:

- Remove the word successfully from second half question statement.

Rev 1:

- Comments incorporated. Question is SAT 41 F

3 B

BF 2010 S

Rev 0:

- Question is SAT 42 H

3 B

BF 2018 S

Rev 0: REFERENCE

- Question is SAT 43 H

3 N

S Rev 0: REFERENCE

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 44 H

3 N

S Rev 0: REFERENCE

- Revise first half question to add: the SGT decay heat removal mode of operation __(1)__ (or just mode)

Rev 1:

- Comments incorporated. Question is SAT 45 H

3 N

S Rev 0:

- B.2/D.2 distractors are not plausible. There is always an option to locally manipulate breakers (i.e. charging springs).

- Can revise second half question to test control power: The affected control power above is provided by an AC/ DC source.

Rev 1:

- Comments incorporated. Question is SAT 46 H

3 M

BF 2021 S

Rev 0: REFERENCE

- Revise first half question statement. __(1)__ to the its respective EECS Analog

- Revise second half answer statements from supplies to supply Rev 1:

- Question swapped with DRAFT Q46 KA (this was originally DRAFT Q3, now Q46). Comments incorporated. Question is SAT 47 H

3 N

S Rev 0: REFERENCE (provided)

- Question is SAT 48 H

3 B

S Rev 0: REFERENCE

- Question is SAT 49 F

3 N

S Rev 0:

- Question is SAT 50 H

3 B

BF 2019 S

Rev 0: REFERENCE

- Question is SAT 51 H

3 B

BF 2018 S

Rev 0:

- Question is SAT 52 F

3 N

S Rev 0:

- Question is SAT NOTE: 0-OI-23 rev 0105 effective in Apr 2021 used distractor min flow value

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 53 F

3 N

S Rev 0:

- Revise second half question statement to read:

__(2)__ is (are) greater than 22%.

Rev 1:

- Comments incorporated. Question is SAT 54 F

3 B

BF 2018 S

Rev 0:

- Question is SAT 55 H

3 N

S Rev 0: REFERENCE

- Question is SAT 56 F

3 M

BF 2021 S

Rev 0:

- Distractors A.2/C.2 are implausible with respect to EOI entry viability (i.e. ALL detectors on panel 2-9-11 require EOI entry).

- Revise second half question back to its pre-modified form or to another aspect of area radiation level with respect to TIP operation.

Rev 2:

- Question revised. Question is SAT 57 F

3 B

HAT 2012 S

Rev 0:

- Question is SAT 58 H

3 B

S Rev 0:

- Question is SAT 59 F

3 N

S Rev 0:

- Question is SAT 60 H

3 N

S Rev 0:

- What is the basis for providing either (1) the listed annunciators vs (2) actual RWL and MC vacuum values. Alarms dont appear to be necessary to answer this question (+55 RWL vs 7 Hg vacuum setpoint determination)

Rev 1:

- Comments incorporated. Question is SAT 61 F

3 M

GFE 2020 S

Rev 0:

- Use of the words resin bed cues the first half answer. Modify first half question to read:

Demineralizer resin bed operation works on the principle of Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 62 F

3 N

S Rev 0:

- Question is SAT 63 F

3 M

BF 2017 S

Rev 0:

- Why are IF and THEN capitalized and bolded with AUTOMATICALLY. Distracting to read and not consistent with overall exam format.

- Second half distractors are implausible from a physics perspective. Negative d/p applied to a space doesnt produce outflow.

Rev 2:

- Question revised. Question is SAT 64 F

3 N

S Rev 0:

- Capitalize and bold the word REQUIRED in the second half statement (or add IAW OPDP-1 to the second half question statement like the wording used in the first half question, or combine the question statements similar to Q#65)

Rev 1:

- Comments incorporated. Question is SAT 65 F

3 M

S Rev 0:

- Remove the word significant from the second half question since this term is subjective and state a value (i.e. 5 MR or 15 MR), ensure keyed answer (i.e.

can vs can NOT) is correct for value chosen Rev 1:

- Comments incorporated. Question is SAT 66 F

3 M

BF 2021 S

Rev 0:

- Question is SAT 67 F

3 M

BF 2021 S

Rev 0:

- Question is SAT 68 F

3 B

BF 2018 S

Rev 0:

- Question is SAT 69 F

3 B

BF 2017 S

Rev 0:

- Question is SAT 70 F

3 B

GFES S

Rev 0:

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 71 H

3 M

GFES S

Rev 0:

- C.1/D.1 distractors are implausible as-written (and not plant specific). Use of the terms less than and greater than cue the correct answer.

- Justification write-up implies that plausibility of distractors is based on Notch position. If all answer choices included notch positions, e.g. Rod at Position 10 vs Rod at Position 40. Answer choices would then be plausible and plant specific.

- Second half question is not a correct statement.

While true that void content is limited at core periphery, this isnt a driving factor in driving radial flux response using shallow control rods (the opposite would be true for deep control rods since they actually are operating in a high void environment).

- Negating high fuel loading of peripheral cells (since not normally done), the driving reason for radial flux response to shallow rod movement is the relative fuel-moderator ratio, which is lower in the core periphery.

- A way to correct is to revise second half question to read: The radial flux response to withdrawing a shallow Control Rod located at the core periphery is based on increased/ decreased fuel-moderator ratio.

Rev 1:

- Comments incorporated. Question is SAT 72 F

3 B

GFES S

Rev 0:

- Question is SAT 73 H

3 N

S Rev 0: REFERENCE

- This is a direct lookup question with Steam Tables and is non-plant specific.

Rev 3:

- Question replaced. Question is SAT 74 H

3 B

S Rev 0:

- Question is SAT 75 F

3 B

GFES S

Rev 0:

- Add in stem information that Unit x is currently operating at y% reactor power.

Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 76 H

3 M

BF 2021 S

Rev 0:

- Incorrect answer keyed for second half question.

Based on the given condition, only AOI-68 entry is required. AOI-100 isnt entered until the IA of AOI-68 is completed which is not addressed by the question (unstated assumption required to arrive at B.2/D.2, ref ES-1.2, B.8).

- Unclear on justification credit claimed for SRO-only.

It states SRO-only based on information contained in the sites procedures as driving, however, it appears that the procedure information tested is an AOI symptom and IA step (which are both RO LOK).

Additionally, Rev 12 portion quoted (ES-4.2, B.2.a) addresses Tier 1 criteria only. SRO-only criteria can be found in ES-4.2, E.

Rev 2:

- Question revised, remove Reactor Power from first half question Rev 4:

- Question revised. Question is SAT 77 H

3 N

S Rev 0: REFERENCE

- Follow-on statement from first half question is confusing. Revise to read: __(1)__ and from the time of event declaration, NRC notification must NOT exceed __(2)__.

Rev 1:

- Comments incorporated. Question is SAT 78 H

3 N

S Rev 0: REFERENCE

- Neither EAL condition exists until 0915 per justification basis. Revise answer choices B.2/D.2 to read 0945.

Rev 1:

- Comments incorporated. Question is SAT 79 H

3 M

BF 2021 S

Rev 0:

- Question is SAT 80 H

3 N

S Rev 0: REFERENCE

- What is the basis for including Question 80 SRO Reference-3 as a reference for this question. Is this incorporated to reinforce distractor plausibility? Im unsure what value this chart provides to the question.

Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 81 F

3 M

S Rev 0:

- First half question cluttered and confusing.

- Revise given condition to read: ATWS conditions exist on Unit 3 with a Reactor Power of 20% and RWL of 0 inches

- First half question is cluttered, revise to read: 3-EOI-1A, ATWS RPV Control, does/ does NOT direct operators to Stop and Prevent use of EHPM and RCIC.

Rev 1:

- Comments incorporated. Question is SAT 82 H

3 N

S Rev 0: REFERENCE

- C.1/D.1 is an implausible distractor b/c the Incident Commander may/may not be a license level position (which may or may not be present in/near the control room at all times)

Rev 1:

- Comments incorporated. Question is SAT 83 H

3 B

BF 2018 S

Rev 0: REFERENCE

- Since the second half question is only asking for applicant determination of invoking Condition B, may be worth considering adding just that line item to the question as a picture (similar to the pictured indications), instead of providing as a full page reference.

- Question is SAT 84 H

3 M

S Rev 0:

- To conform with stated justification, revise distractors C.1/D.1 to (-) 180 inches Rev 1:

- Comments incorporated. Question is SAT 85 H

3 M

BF 2019 S

Rev 0:

- As-written (modified), neither half of the question rises above RO LOK (SBGT initiation setpoint & EOI-3 entry criteria). Question sourced from a 261000 A2.06 (T2/G1) RO question.

Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 86 H

3 M

BF 2021 S

Rev 0:

- I dont understand why EOI-1A entry is required.

Blue lights are normally extinguished (or dark), so if they have subsequently extinguished, this implies that at some point they were lit (i.e. due to the AUTOMATIC SCRAM). Since no time interval is provided all rods may or may not already be inserted and ATWS conditions are determined by evaluating reactor power (or downscales)/RWM status (neither of which are provided). Conditions for an Electrical ATWS are not clearly evident.

- What is significance of ALL with 185, no need for both terms.

- Reword question:

Unit 2 operators have entered 2-EOI-1A, xxx, with the following plant conditions:

Reactor Power indicates 10%

ALL SCRAM inlet/outlet blue lights are extinguished Given the conditions above, Recirc Pumps __(1)__

To mitigate this condn, the NUSO will direct __(2)__.

Rev 1:

- Comments incorporated. Reword to capitalize and bold extinguished in question stem.

Rev 4:

- Comments incorporated. Question is SAT 87 H

3 B

S Rev 0: REFERENCE

- Question is SAT 88 H

3 M

S Rev 0: REFERENCE

- Revise bullet to read: alarms due to a failed pressure transmitter Rev 2:

- Allowable Value column of Table 3.3.6.1-1 provides cueing of second half answer choices making this a direct lookup (specifically the visible rated steam flow). Remove the Allowable Value column for all pages provided as a reference from Table 3.3.3.6-1.

- Question revised. Question is SAT Rev 4:

- Comments incorporated. Reference is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 89 H

3 N

S Rev 0:

- Remove bullets 2 and 3 (not necessary to answer the question)

Rev 1:

- Comments incorporated. Question is SAT 90 H

3 B

BF 2018 S

Rev 0: REFERENCE

- Question is SAT 91 H

3 N

S Rev 0: REFERENCE (2)

- Remove second bullet under 0615 Both RWCU Pumps remain tripped Rev 1:

- Comments incorporated. Question is SAT 92 H

3 N

S Rev 0: REFERENCE

- Revise starting power to be 50% RTP. (eliminate high steam flow as consideration for MSIV closure)

- Revise first half question to read: The SCRAM occurred directly from a __(1)__ signal.

Rev 1:

- Comments incorporated. Question is SAT 93 H

3 N

S Rev 0: REFERENCE (2)

- Question is SAT 94 H

3 B

BF 2021 S

Rev 0: REFERENCE

- Revise reference note to be consistent across examination: [REFERENCE PROVIDED]

- Revise answer choice A to remove the term ONLY (two SRMs are OPER as given in question stem)

Rev 1:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 95 H

3 M

S Rev 0:

- Remove the term ONLY from A.1/B.1 distractors (cues distractor as being correct in conjunction with use of the singular term location in first half question stem). Also doesnt make sense when read as a coherent statement.

- Consider capitalizing and bolding the term MINIMUM for exam consistency.

Rev 1:

- Comments incorporated. Question is SAT 96 F

3 N

S Rev 0:

- Revise the first half question statement to include:

For a scheduled maintenance work activity and in accordance with NPG-SPP-07.3,

- Use of the phrase deeming an emergency removes viability of B.2/D.2 as distractors. Revise second half question statement to read: __(2)__ has the responsibility for assigning a task as a Priority 1 emergent work order.

Rev 1:

- Comments incorporated. Will revise first half question to include EDG surveillance and ask about Operations involvement in WO process.

Rev 3:

- Question revised. Question is SAT 97 F

3 M

S Rev 0:

- Multiple correct answers since C.1/D.1 can be interpreted as being Unit 2 ONLY. Revise these answer choices to read: Unit 1, 2 or 3 Rev 1:

- 2nd half question requires additional discussion, facility to revise and resubmit Rev 2:

- For exam consistency, capitalize/bold AND used in B.2/D.2 distractors.

Rev 4:

- Comments incorporated. Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level 98 F

3 M

BF 2021 S

Rev 0:

- Revise second half question to read: During implementation of 0-EOI-4 and in accordance with EOI Program Manual Bases.

Rev 1:

- Comments incorporated. Question is SAT 99 F

3 N

S Rev 0: REFERENCE

-B.2/D.2 distractors implausible as-written due to being a direct lookup. Revise question stem to introduce plausibility of distractors. SAE declaration not needed to answer this question.

- Revise question stem to read (i.e. prior to first half question): Site Security personnel are responding to a hostile force in the Protected area. The hostile force has announced their intentions on social media and to local news organizations.

Rev 1:

- Comments incorporated. Facility to add a TVA press notification comment to stem.

Rev 2:

- Question is SAT 100 F

3 B

BF 2021 S

Rev 0:

- Question is SAT

Form 2.3-5 Written Examination Review Worksheet Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. K/A Use Flaws

6. Source (B/M/N)

7. Status (U/E/S)

8. Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job Link Minutia

1. /Units Logic Q-K/A License Level Instructions:

Refer to ES-4.2 for the definitions of terms used in this worksheet for the written examination. Review each question (Q) as submitted and as subsequently revised and document the following in the associated worksheet columns:

1.

Enter the level of knowledge (LOK) as either (F)undamental or (H)igher cognitive level.

2.

Enter the level of difficulty (LOD) from 1 (easy) to 5 (difficult); mark direct lookup questions (applicant can directly determine the answer from the provided reference) as LOD 1. A question is (U)nsatisfactory if it is LOD 1 or LOD 5.

3.

Check the appropriate box if a psychometric flaw is identified:

Stem Focus: The stem lacks enough focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). This is an (U)nsatisfactory question.

Cues: The stem or one or more answer choices contains cues (e.g., clues, specific determiners, phrasing, length). This is an (U)nsatisfactory question.

T/F: All of the answer choices are a collection of unrelated true/false statements. This is an (U)nsatisfactory question.

Cred. Dist.: The distractors are not credible; single implausible distractors require (E)nhancement, and more than one noncredible distractor in the same question results in an (U)satisfactory question.

Partial: One or more distractors are partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by the stem). This is an (U)nsatisfactory question.

4.

Check the appropriate box if a job content flaw is identified:

Job Link: The question is not linked to the job requirements (i.e., the question has a valid knowledge or ability (K/A) but, as written, is not operational in content). This is an (U)nsatisfactory question.

Minutia: The question requires the recall of knowledge that is too specific for the closed-reference test mode (i.e., it is not required to be known from memory). This is an (U)nsatisfactory question.

1. /Units: The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons). This is an (U)nsatisfactory question.

Logic: The question requires backward or reverse logic or application compared to the job requirements. This is an (U)nsatisfactory question.

5.

Check the first box if a K/A mismatch flaw exists. Check the second box if the question is flawed because it is written at the wrong license level. Either condition results in an (U)nsatisfactory question.

6.

Enter the questions source: (B)ank, (M)odified, or (N)ew. Verify that (M)odified questions meet the criteria of ES-4.2.

7.

Based on the review performed in steps 2-5, mark the question as (U)nsatisfactory, in need of (E)nhancement, or (S)atisfactory.

8.

Fully explain the reason for any (U) in column 7 (e.g., how the psychometric attributes are not being met).

Save the initial review comments and detail subsequent comment resolution so that each exam-bound question is marked by an (S) on this form.

LOK (F/H)

LOD SF Cue T/F Cred.

Dist.

Par Job Link Minutia

1. /units Logic Q=K/A SRO only B/M/N U/E/S Revision History 38-45 H

75 B /

10 N @ H Rev 0: 10/14, 10/21, 10/28/21 Rev 1: 12/1 - 12/2/21 discussions

- Outstanding: 7, 10, 12, 14, 15, 18, 33, 56, 63, 73 / 76, 86, 88, 96, 97, 99 / updated references & list of references (per license lvl)

Rev 2: 12/14 submittal

- Outstanding: 7, 18, 33, 73 / 76, 86, 88, 96, 97 Rev 3: 1/4 submittal

- Outstanding: 76, 86, 88, 97 Rev 4: 1/5 submittal RO 42 H 22 B 13N @ H 13 H SRO 19 H 5 B 8N @ H