Text

2A-3 Exam Administrative Items - Delay Release
	ML22314A093
Person / Time
Site:	Harris
Issue date:	11/10/2022
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-400/22-301 50-400/OL-22
	Download: ML22314A093 (1)
	v • d • e

Form 3.2-1 Administrative Topics Outline-RO

Facility: HARRIS Date of Examination: 9/19/22

Examination Level: RO SRO Operating Test Number: 05000400/20220919

Administrative Topic (Step 1) Activity and Associated K/A (Step 2) Type Code

(Step 3)

Determine the amount of RCS inventory that will be drained from RCS (GP-008)

(JPM ADM-070-b) M, R

Conduct of Operations K/A G.2.1.25

2022 NRC RO A1-1

Determine required boric acid flow (AOP-017, OP-107.01) (JPM ADM-081-a)

P, D, R Conduct of Operations K/A G.2.1.23

2022 NRC RO A1-2

Determine component powered by fuse, fuse location and system impact during fuse removal N, R (AD-OP-ALL-0200)

Equipment Control K/A G.2.2.41

2022 NRC RO A2

Perform channel check on RM-3502ASA following maintenance (OP-118) (JPM ADM-083-a)

Radiation Control K/A G.2.3.5 N, S

2022 NRC RO A3

Emergency Plan NOT SELECTED FOR RO N/A

Rev-0 1

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:

Number of JPMs Topic SRO and

Reactor operator (RO) applicants RO* RO do not need to be evaluated on Retakes every topic (i.e., Equipment Conduct of Control, Radiation Control, or Operations 1 (or 2) 2 Emergency Plan can be omitted by Equipment Control 1 (or 0) 1 doubling up on Conduct of Operations), unless the applicant is Radiation Control 1 (or 0) 1 taking only the administrative topics Emergency Plan 1 (or 0) 1 portion of the operating test (with a waiver or excusal of the other Total 4 5 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)

Rev-0 2

2022 NRC RO Administrative Topics Summary

2022 NRC RO A1 Determine the amount of RCS inventory that will be drained from RCS during the performance of GP-008, Draining the RCS. (GP-008) (JPM ADM-070-b) --

MODIFIED

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

(CFR: 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2

The applicant will be provided with initial plant conditions. The plant is shutdown for refueling and a RCS down is required to remove SG Nozzle dams. The RCS was initially drained down to -70 to install nozzle dams and then refilled to the vessel flange. They will be required to calculate the amount of RCS volume in gallons to drain down with unfilled SGs to -70 below the flange using GP-008 Attachment 5. The candidate will need to realize that refill to the Vessel flange will not refill the SG u-tubes.

NOTE: This JPM was modified by changing RCS drain down from an initial drain to a drain after nozzle dams were installed.

2022 NRC RO A1 Determine required boric acid flow using AOP-017 Attachment 4 and OP-107.01. (AOP-017, OP-107.01) (JPM ADM-081-a) - PREVIOUS

K/A G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation (CFR: 41.10 / 43.5 / 45.2 / 45.6) RO 4.3 SRO 4.4

The plant is in Mode 4 following an instrument air leak. The crew had entered and was working through AOP-017. VCT level is currently 16% and stable. The CRS directed the candidate perform a manual make to the VCT using AOP-017 Attachment 4. The candidate will be provided with initial data and then be required to obtain values from OP-107.01, Attachment 7, calculate the maximum makeup flow rate to achieve the required boron concentration in the VCT along with the required boric acid flow rate and dilution flow rate.

Used on 2020 NRC Exam.

2022 NRC RO A2 - Determine component powered by fuse, fuse location and system impact during fuse removal (AD-OP-ALL-0200) (JPM ADM-082-a) -- NEW

K/A G2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings (reference potential)

(CFR: 41.10 / 45.12 / 45.13) RO 3.5 SRO 3.9

The plant was at 100% power. Based on a vendor advisory notice concerning degradation of fuses manufactured during a certain timeframe, fuse FU/273 must be removed for replacement. The candidate will be required to identify the FU/273 supports 1CS-182 A Charging Safety Injection Pump normal mini flow isolation valve. This valve is a motor operated valve that can be determined with the provided drawings CPL-2165-G-0805 and 2165-S-1305. The fuse location is determined to be MCC B35-SB Compt-4E. The affected equipment will be the A CSIP pump normal mini flow path.

Rev-0 3

2022 NRC RO Administrative Topics Summary

2022 NRC RO A3 - Perform channel check on RM-3502ASA following maintenance (OP-118)

(JPM ADM-083-a) -- NEW

K/A 2.3.5 - Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 / 41.12 / 43.4 / 45.9) RO 2.9 SRO 2.9

Maintenance has just been completed minor work on Radiation monitor REM-01LT-3502ASA Containment RCS leak detection. The candidate will be directed to perform a channel check using OP-118 section 6.3.3 using the RMS computer in order to support returning the RM to operable status. The channel check will be using the RMS computer in the simulator. The candidate will need to navigate to required screens to perform the channel check. The candidate will discover that there is no sample flow and will need to report that the RM is not ready to be returned to serve.

Rev-0 4

Form 3.2-1 Administrative Topics Outline SRO

Facility: HARRIS Date of Examination: 9/19/22

Examination Level: RO SRO Operating Test Number: 05000400/20220919

Administrative Activity and Associated K/A (Step 2) Type Code Topic (Step 1) (Step 3)

Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002) (JPM ADM-040-a-SRO)

Conduct of K/A G.2.1.20 D, R

Operations 2022 NRC SRO A1-1 During a loss of shutdown cooling, determine the time that the RCS will reach core boiling and core boil-off conditions (AOP-020) (JPM ADM-005-c-SRO)

Conduct of M, R K/A G.2.1.25 Operations 2022 NRC SRO A1-2 Determine affected component, fuse location, actions to prevent system perturbations and Tech spec requirements for fuse Equipment removal (JPM ADM-082-a-SRO)

Control K/A G.2.2.41 & G.2.2.35 N, R

2022 NRC SRO A2 Complete review and approval of OP-120.07, Attachment 3 Waste Gas Decay Tank Release Log (OP-120.07)

(JPM ADM-075-a-SRO)

Radiation Control P, D, R K/A G.2.3.6

2022 NRC SRO A3 Determine Initial Protective Action Recommendations (AD-EP-ALL-0109) (JPM ADM-076-b-SRO)

Emergency Plan K/A G.2.4.44 M, R

2022 NRC SRO A4

Rev-0 1

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:

Number of JPMs Topic SRO and

Reactor operator (RO) applicants RO* RO do not need to be evaluated on Retakes every topic (i.e., Equipment Conduct of Control, Radiation Control, or Operations 1 (or 2) 2 Emergency Plan can be omitted by doubling up on Conduct of Equipment Control 1 (or 0) 1 Operations), unless the applicant is Radiation Control 1 (or 0) 1 taking only the administrative topics portion of the operating test (with a Emergency Plan 1 (or 0) 1 waiver or excusal of the other Total 4 5 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)

Rev-0 2

2022 NRC SRO Administrative Topics Summary

2022 NRC SRO A1 Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002) (JPM ADM-040-a-SRO) - DIRECT

K/A G2.1.20 - Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5 / 45.12) RO 4.6 SRO 4.6

The plant data for current conditions during a plant startup will be provided to the candidate.

The information provided will allow the candidate to complete Attachment 5 of GP-002, Normal Plant Heatup From Cold Solid To Ho t Subcritical Mode 5 To Mode 3. The candidate must review the plant data provided and determine that three items (Boric Acid Tank, RCS/RHR Loops and Safety Related Electrical Buses) do NOT meet the minimum required for entry into Mode 4.

2022 NRC SRO A1 During a loss of shutdown cooling, determine the time that the RCS will reach core boiling and core boil-off conditions (AOP-020) (JPM ADM-005-c-SRO) - MODIFIED

K/A G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2

The candidate will be provided with initial plant conditions. A plant shutdown for refueling is in progress with the Reactor Vessel head off when a loss of RHR has occurred. The crew is implementing AOP-020, Loss of RCS Inventory or Residual Heat Removal While Shutdown.

The SRO candidates must first determine which of the four plant curves to use (H-X-8 through H-X-11) and then calculate the time the RCS will reach core boiling and core boil-off based on the figures.

NOTE: Modified by changing the dates and times of plant shutdown and values of the core thermocouples. These changes have made the calculated answer substantially different than the bank JPM answer.

2022 NRC SRO A2 - Determine component powered by fuse, fuse location, system impact during fuse removal and Tech. Spec. requirements. (JPM-ADM-082-a-SRO)

(AD-OP-ALL-0200) - NEW

K/A G.2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 41.10 / 45.12 / 45.13) RO 3.5 SRO 3.9 K/A 2.2.35 Ability to determine TS for mode of operation.

(CFR: 41.7 / 41.10 / 43.2 / 45.13) RO 3.6 SRO 4.5

The plant was at 100% power. Based on a vendor advisory notice concerning degradation of fuses manufactured during a certain timeframe, fuse FU/273 must be removed for replacement. The candidate will be required to identify the FU/273 supports 1CS-182 (A Charging Safety Injection Pump normal mini flow isolation valve. This valve is a Motor operated that can be determined with the provided drawing CPL-2165-G-0805 and 2165-S-1305. The fuse location is determined to be MCC B35-SB Compt-4E. The affected equipment will be the A CSIP pump normal mini flow path. There will be three Tech Specs that will apply for the fuse replacement.

Rev-0 3

2022 NRC SRO Administrative Topics Summary

2022 NRC SRO A3 - Complete review and approval of OP-120.07, Attachment 3 Waste Gas Decay Tank Release Log (OP-120.07) (JPM-ADM-075-a-SRO) - PREVIOUS

K/A G 2.3.6 Ability to approve release permits (CFR: 41.13 / 43.4 / 45.10) RO 2.0 SRO 3.8

The candidate will be provided with the pre-release data provided by the RWCR AO and Shift Chemistry Technician along with the completed OP-120.07, Section 8.39 and Attachment 3 for authorization to commence the release of a Waste Gas Decay tank. They must determine that three items (Estimated release duration, RCDT Vent position, and the RM-11 High (Max) Setpoint) dispositions are not correct and the release should not be approved to commence. Used on 2018 NRC Exam.

2022 NRC SRO A4 - Determine Initial Protective Action Recommendations (AD-EP-ALL-0109)

(JPM-ADM-076-b) - MODIFIED K/A G2.4.44 - Knowledge of emergency plan implementing procedures protective action recommendations (SRO Only) (CFR: 41.10 / 41.12 / 43.5 / 45.11) RO N/A SRO 4.4

Given a set of initial conditions and AD-EP-ALL-0109, the candidate must determine the initial Protective Action Recommendations for the event in progress. This JPM is time critical JPM (15 minutes.)

NOTE: Modified by changing plant conditions resulting in different Protective Action Recommendations.

Rev-0 4

Form 3.2-2 Control Room/In-Plant Systems Outline

Facility: Harris Nuclear Plant Date of Examination: September 19, 2022 Exam Level: RO SRO-I SRO-U (Bold) Operating Test Number: 05000400/20220919

Control Room Systems 8 for RO, 7 for SRO-I, and 2 for SRO-U System/JPM Title Type Code Safety Function

a. Initiate Emergency Boration Following a Reactor Trip (AOP-002) (JPM-CR-037-f) A, L, P, D, S 1

K/A APE024 AA1.17

b. Drain a Cold Leg Accumulator (OP-110) (JPM-CR-133-b) D, S 2

K/A 006 A2.03

c. Transfer to Hot Leg transfer (ES-1.4) (JPM-CR-066-e)

K/A EPE011 EK3.13 A, EN, L, M, S 3

d. Align the RHR System for ECCS Mode (OP-111)

(JPM-CR-290-a) D, L, S 4P

K/A 005 A4.01

e. Isolate Ruptured C SG (E-3)

(JPM-CR-105-a) A, N, L, S 4S

K/A 039 A4.01

f. Reduce Containment Spray Flow (ECA-1.1)

(JPM CR-233-e) M, EN, L, S 5

K/A 026 A4.01

g. Restoration of Offsite Power to Emergency Buses (EOP ECA-0.0) (JPM-CR-291-c) A, P, D, S 6

K/A 055 EA1.07

h. Restoring Control Room Area HVAC to Normal After a CRIS (OP-173) (JPM-CR-171-d) EN, M, S 8

K/A APE067 AA1.05 RO ONLY

Form 3.2-2 Control Room/In-Plant Systems Outline

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 for SRO-U

i. Lube oil fire (secure seal oil pumps) (AOP-047) A, E, N 4S (JPM-IP-299-a)

K/A 045 G.2.1.30

j. Place a Safety Train Battery Charger on the Alternate D, E, L 6 Power Supply (OP-156.01) (JPM-IP-246)

K/A APE058 AA1.01

k. Locally Isolate The Seal Water Return Heat Exchanger D, E, R 8 (AOP-014) (JPM-IP-288)

K/A 008 A2.02

Rev-0 2

Form 3.2-2 Control Room/In-Plant Systems Outline

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

License Level Control Room In-Plant Total

Reactor Operator (RO) 8 3 11 Senior Reactor Operator-Instant 7 3 10 (SRO-I)

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

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.

Rev-0 3

Form 3.2-2 Control Room/In-Plant Systems Outline

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.

Rev-0 4

Form 3.2-2 Control Room/In-Plant Systems Outline

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

Code License Level Criteria Actual RO SRO-I SRO-U RO SRO-I SRO-U (A)lternate path 4-6 4-6 2-3 5 5 3 (C)ontrol room (D)irect from bank 9 8 4 6 6 3 (E)mergency or abnormal in-1 1 1 3 3 3 plant (EN)gineered safety feature 1 1 1 3 2 1 (for control room system)

(L)ow power/shutdown 1 1 1 6 6 2 (N)ew or (M)odified from bank 2 2 1 5 4 2 (must apply to at least one alternate path JPM)

(P)revious two exams 3 3 2 2 2 1 (randomly selected)

(R)adiologically controlled 1 1 1 1 1 1 area (S)imulator

Rev-0 5

2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs

JPM a - Initiate Emergency Boration following a Reactor Trip (AOP-002)

(JPM-CR-037-f) SRO Upgrade - Alternate Path - DIRECT Previous from the 2018 Exam. (Randomly selected from the Simulator JPM bank)

K/A APE024 AA1.17, Ability to operate and/or monitor the following as they apply to Emergency Boration: Emergency borate control valve (CFR 41.7 / 45.5 / 45.6) (4.1)

Evaluated position: Operator at the Controls (OATC) responsibilities.

Turnover: The plant was operating at 100% power when the A MFW pump tripped. The crew performed a manual Reactor Trip in accordance with AOP-010, Feedwater Malfunctions. The crew has completed the immediate actions of EOP E-0, Reactor Trip or Safety Injection and have transitioned to ES-0.1, Reactor Trip Response. RCS temperature has been stabilized in accordance with EOP-ES-0.1 step 4.

Task: Initiate Emergency Boration following a Reactor Trip after identifying that 2 or more control rods have not fully inserted.

Verifiable actions: The candidate will attempt to start a Boric Acid pump and determines that the pump has failed to start. The pump failure will require the candidate to establish an alternate flow path by opening either of the two RWST valves to the suction of the CSIP, shutting either of the two VCT outlet valves and then raise flow to > 90 gpm using a FCV with the flow rate indication on a meter on the MCB.

Alternate Path - YES - The only available Boric Acid Pump will fail when started requiring the candidate to utilize an alternate boration flow path and also establish a flow rate to the CSIP of > 90 gpm using FK-122.1 in manual.

JPM completion: After the candidate has established and verified at least 90 gpm charging flow from the RWST to the RCS on FI-122A.1, evaluation on this JPM is complete.

JPM b - Drain a Cold Leg Accumulator (Accumulator C) (OP-110)

(JPM-CR-133-b) - DIRECT

K/A 006 A2.03 Ability to (a) predict the impacts of the following on the Emergency Core Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: System leakage (CFR: 41.5 / 45.5)

(3.4, 3.5)

Evaluated position: Operator at the Controls (OATC) responsibilities.

Turnover: The plant is operating at 100% power steady state middle of life (MOL).

AOP-016, Excessive Primary Plant Leakage, has been entered due to a rise in RCS leakage. The C Cold Leg Accumulator level is 90 percent. The CRS has directed the OATC to lower the level in the C Cold Leg Accumulator to 84 percent in accordance with Safety Injection, Section 8.4.

Rev-0 6

2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs (continued)

JPM b (continued)

Task: Drain B Cold Leg Accumulator.

Verifiable actions: The candidate will be required to perform a valve lineup to reduce level in accordance with OP-110, Safety Injection, Section 8.4 while monitoring progress using MCB level indicators and computer screens (ERFIS).

Alternate Path - NO - There are no failures with this task

JPM completion: When level has returned to normal the drain lineup will be secured and the SRO informed that the task is complete.

JPM c - Transfer to Hot Leg transfer (ES-1.4)

(JPM-CR-066-e) SRO Upgrade - Alternate Path - MODIFIED

EPE011 EK3.13 Knowledge of the reasons for the following responses and/or actions as they apply to a Large-Break LOCA: Hot-leg injection/recirculation (3.9)

Evaluated position: Operator at the Controls (OATC) responsibilities.

Turnover: The plant was operating at 100% power steady state middle of life (MOL) when a Large Break LOCA occurred. As a result of the LOCA, an automatic Reactor Trip / Safety Injection has occurred. 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months has elapsed since the event occurred. The ESF equipment is operating and presently aligned per EOP ES-1.3, Transfer to Cold Leg Recirculation. The CRS has directed the OATC to transfer the Cold Leg injection line up to the Hot Leg injection line up in accordance with EOP ES-1.4, Transfer to Hot Leg Recirculation. The A RHR pump tripped on the sequencer start and A Charging pump was secured for a major oil leak.

Task: Align the ECCS injection lineup from Cold Leg Recirc to Hot Leg Recirc.

Verifiable actions: The candidate will be required to perform valve position changes to establish a flow path from the existing ECCS injection flow path lineup to the Hot Legs.

They will have to realign flow to the Cold leg for the low head SI flow path due to the Hot leg valve failing to open. Also they will need to response to a high head SI valve that will be pressure locked. This will require them to start a CSIP and open valves that will allow the pressure locked valve to be opened.

Alternate Path - YES - Part one ALT path is realigning low head SI flow back to the cold legs. The second ALT path is during the valve alignment 1SI-86, High Head SI to Hot Leg will fail to open. This failure will require the operator to use RNO actions to reopen the previously shut BIT outlet valves 1SI-3 and 1SI-4 then restart the Train B CSIP and use Attachment 1 to open 1SI-86 from a pressure locked condition.

JPM completion: When high head SI flow is aligned to the Hot legs via 1SI-86 and B CSIP is in operation.

Rev-0 7

2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs (continued)

JPM c (continued)

Modification: Modified by changing the affected High Head SI to Hot leg valve from 1SI-107 to 1SI-86. These changes require the candidate to complete step 2 of EOP-ES-1.4, Attachment 1, vice step 1 to open the pressure locked valve 1SI-86. Also, added failure of low head Hot leg injection valve to open.

JPM d - Align the RHR System for ECCS Mode (OP-111) (JPM-CR-290-a) - DIRECT 005 A4.01 Ability to manually operate and/or monitor in the control room: Controls and indication for RHR pumps (CFR: 41.7 / 45.5 to 45.8) (4.0)

Evaluated position: Balance of Plant (BOP) Operator responsibilities.

Turnover: The plant is in Mode 4. GP-002, Normal Plant Heatup from Cold Solid to Hot Subcritical Mode 5 to Mode 3 is in progress. Train A RHR is in cooldown mode and Train B RHR is in ECCS mode.

Task: The CRS has directed the BOP to align the A RHR train for ECCS Mode per OP-111 Section 7.2.2 starting at step 19. RHR Pump A-SA discharge temperature indication on ERFIS is < 140°F. Forced cooling of the suction line has been in progress for the last 30 minutes.

Verifiable actions: The candidate will secure a running RHR pump and then establish a valve lineup to change the flow path of the A RHR pump from a RCS cooldown lineup to the ECCS injection flow path lineup.

Alternate Path - NO - There are no failures with this task

JPM completion: A Train RHR ECCS Mode alignment is completed prior to RCS temperature exceeding 350°F.

JPM e - Isolate Ruptured C SG (E-3) (JPM-CR-105-a) - Alternate Path - NEW 039 A4.01 Ability to manually operate and/or monitor in the control room: MSIVs and bypass valves (3.9)

Evaluated position: Balance of plant (BOP) responsibilities.

Rev-0 8

2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs (continued)

JPM e (continued)

Turnover: A Reactor trip and Safety Injection have occurred. EOP-E-0, Reactor Trip or Safety Injection, was entered and a transition has been made to EOP-E-3, Steam Generator Tube Rupture. EOP-E-3 has been implemented through Step 4.

The C SG has been identified as the ruptured SG. The CRS directs the BOP to continue implementing EOP-E-3 starting at step 5.

Task: C SG isolated per EOP-E-3 attachment 1 for main control room steps only.

Verifiable actions: The candidate will be required to perform valve manipulations and change a SG PORV opening setpoint to isolate the C SG. The C MSIV will fail to shut and require the candidate to implement Attachment 1 to isolate steam release paths.

Alternate Path - YES - The C MSIV will fail to shut and will require the candidate to perform the RNO steps to isolate steam release paths. This will involve shutting A and B SG MSIV and isolating valves on the Moisture Separator Reheater.

JPM completion: When the BOP directs the Radwaste control room operator to shut 1AS-244 the JPM is completed.

Modification: New JPM

JPM f - Reduce Containment Spray Flow (ECA-1.1) (JPM-CR-233-e) - MODIFIED 026 A4.01 Ability to manually operate and/or monitor in the control room: CSS controls (3.9)

Evaluated position: Operator at the Controls (OATC) responsibilities..

Turnover: A large break LOCA has occurred. Both RHR Pump breakers have tripped.

Maintenance is investigating. The RED on Integrity has been addressed and FR-P.1 was exited. The crew has transitioned to ECA-1.1, Loss of Emergency Coolant Recirculation, and has completed Step 4.

Task: Start the non-running containment fan cooler and secure both CNMT Spray pumps to conserve RWST water.

Verifiable actions: The candidate will reset RWST auto swap over, start one CNMT fan cooler, secure both CNMT spray pumps and isolate discharge valves.

Alternate Path - NO - There are no failures with this task

JPM completion: Once Containment Spray Pump flow reduced to no pumps running, evaluation on this JPM is complete.

Modification: Added steps to reset RWST switchover and to start one CNMT fan cooler.

Rev-0 9

2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs (continued)

JPM g - Restoration of Offsite Power to Emergency Buses (EOP-ECA-0.0)

(JPM-CR-291-c) Alternate Path - PREVIOUS Previous from the 2018 NRC Exam. (Randomly selected from the Simulator JPM bank)

055 EA1.07 Ability to operate and monitor as they apply to station blackout: Restoration of power from offsite (CFR: 41.7 / 45.5 / 45.6) (4.3, 4.5)

Evaluated position: Balance of Plant (BOP) Operator responsibilities.

Turnover: The plant was operating at 100% power. A EDG is under clearance due to the generator field not flashing during OST-1013. The failure of a major line on the Duke grid resulted in the cascading trip of several units and low grid frequency. A loss of offsite power occurred. B EDG failed to start and the problem is being investigated. The crew is implementing EOP-ECA-0.0. The load dispatch er has stabilized the grid and has given permission to restore offsite power to 6.9 KV buses and to reset any tripped Start Up XFMR lockout relays (there are currently no lockout relays tripped).

Task: Energizing ONE Emergency Bus from the SUT (either the 1A-SA energized or 1B-SB energized).

Verifiable actions: The candidate will be manipulating electrical supply breaker switches on the MCB to restore power to the dead Emergency Bus.

Alternate Path: - YES - During the lineup for power restoration on the A-SA Emergency Bus the supply breaker from offsite (Breaker 105) will fail to close. The candidate will be required to continue Attachment 1 using the guidance for the B-SB Emergency Bus to complete restoration of offsite power to a (one) AC emergency bus.

JPM completion: Emergency Bus 1B-SB is being powered via offsite power and the 480 V breakers powering emergency equipment is energized and the CRS is informed, evaluation on this JPM is complete.

JPM h - Restoring Control Room Area HVAC to Normal after a Control Room Isolation Signal (OP-173) (JPM-CR-171-d) - RO ONLY-MODIFIED

APE 067 AA1.05 Ability to operate and/or monitor the following as they apply to a Plant Fire on Site: Plant and control room ventilation systems (CFR 41.7 / 45.5 / 45.6) (3.5)

Evaluated position: Balance of Plant (BOP) Operator responsibilities.

Rev-0 10 2022 NRC RO/SRO Simulator & In Plant JPM Summary

Simulator JPMs (continued)

JPM h (continued)

Turnover: The plant is at 100% power steady state Middle of Life (MOL). A fire occurred at the Emergency Shutdown Diesel Generator during testing. The smoke from the fire caused a Control Room Ventilation Isolation signal to occur (smoke detected at the normal intake Zone 1-150). The Fire Brigade has put the fire out and the smoke has been cleared. The CRS has directed the BOP to restore the Control Room Area HVAC System to NORMAL in accordance with OP-173, Control Room Area HVAC System, Section 8.4. The initial conditions of the OP section will be satisfied and the HVAC system will be in operation per section 8.1.

Task: Restore Control Room Area HVAC to normal in accordance with OP-173, Control Room Area HVAC System, Section 8.4

Verifiable actions: The candidate must reset the Control Room Ventilation isolation signal with a switch to allow the ventilation system to be placed in its normal configuration. They will open intake valves, shut dampers and start and stop exhaust fans.

Alternate Path - No

JPM completion: Restoration of the Control Room Normal air supply and lineup is complete.

Modification: Removed alternate path of AH-15A tripping after opening a damper valve.

Rev-0 11 2022 NRC RO/SRO Simulator & In Plant JPM Summary

In-Plant JPMs

JPM i - Lube oil fire (secure seal oil pumps) (AOP-047)

(JPM-IP-299-a) - Alternate Path - NEW

K/A 045 G.2.1.30 Ability to locate and operate components, including local controls (4.4, 4.0)

Evaluated position: Safe Shutdown Operator (RAB watchstander)

Turnover: There is a lube oil fire in between the low pressure turbines. The MCR crew manually tripped the reactor and is currently in ES-0.1 and AOP-047 in parallel. The Fire brigade is currently fighting the fire on TB314. There is no smoke or fire on TB 261 or TB 286. You are the Safe Shutdown Operator. The CRS has directed you to perform local actions for AOP-047 to s ecure the Main Generator Hydrogen seal oil pumps. The Main Generator hydrogen pressure is reading ~1 psig.

Task: To secure Main Generator Seal Oil pumps.

Verifiable actions: Candidate will need to secure Main Generator seal oil pumps via local control switches and open up one supply power breaker for the Air Side Seal Oil pump that fails to secure with local control switch.

Alternate Path - YES - When the candidate tries to secure the Air Side Seal Oil pump, the pump will not secure. Therefore the RNO step will need to be completed by opening up the 250VDC power supply breaker.

JPM completion: Once candidate opens the breaker for the Air Seal Oil pump the JPM can be secured.

JPM j - Place a Safety Train Battery Charger on the Alternate Power Supply (OP-156.01)

(JPM-IP-246) - DIRECT APE 058 AA1.01 Ability to operate and/or monitor the following as they apply to Loss of DC Power: Alternate supply (3.6)

Evaluated position: Reactor Auxiliary Building (RAB) operator

Turnover: The unit is in Mode 3 following a reactor trip due to a loss of offsite power and failure of the A and B EDGs to start. The crew entered EOP-ECA-0.0, Loss of all AC Power. The Dedicated Shutdown Diesel Generator started, loaded, and is now supplying the 1D23 bus. You have an Ascom phone, radio, and a set of rounds keys.

Task: Align the A-SA or A-SB Battery Charger to the Alternate Power Supply and place the 1A-SA or 1A-SB Battery Charger in service. Which train will depend on what actuate charger is the protected train.

Verifiable actions: Candidate will need to manipulate switches on a transfer panel to realign power the battery charger to the alternate source. Then the required battery charger will be placed into service.

Rev-0 12 2022 NRC RO/SRO Simulator & In Plant JPM Summary

In-Plant JPMs (continued)

JPM j (continued)

Alternate Path - NO - There are no failures with this task.

JPM completion: Only battery charge indications are checked for proper operation the JPM can be secured.

JPM k - Locally Isolate the Seal Water Return Heat Exchanger (AOP-014)

(JPM-IP-288) - DIRECT 008 A2.02 Ability to (a) predict the impacts of the following on the Component Cooling Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: High/low surge tank level (3.8, 3.7)

Evaluated position: Reactor Auxiliary Building (RAB) operator

Turnover: The plant is at 100% power. ALB-005/6-1, CCW Surge Tank High-Low Level, has alarmed. CCW surge tank level is lowering. The CRS has entered AOP-014, Loss of Component Cooling Water.

Task: The CRS directs you to Locally Isolate the Seal Water Return Heat Exchanger in accordance with AOP-014.

Verifiable actions: The candidate will need to verify that seal return is aligned to the top of the VCT. Then the candidate will change locations and operate three manual valves to bypass and isolate RCP seal return heat exchanger.

Alternate Path - NO - There are no failures with this task.

JPM completion: Only RCP seal return heat exchanger is isolated the JPM can be secured.

Rev-0 13 Form 3.2-2 Control Room/In-Plant Systems Outline

Facility: Harris Nuclear Plant Date of Examination: September 19, 2022 Exam Level: RO SRO-I SRO-U (Bold) Operating Test Number: 05000400/20220919

Control Room Systems 8 for RO, 7 for SRO-I, and 2 for SRO-U System/JPM Title Type Code Safety Function

a. Initiate Emergency Boration Following a Reactor Trip (AOP-002) (JPM-CR-037-f) A, L, P, D, S 1

K/A APE024 AA1.17

b. Drain a Cold Leg Accumulator (OP-110) (JPM-CR-133-b) D, S 2

K/A 006 A2.03

c. Transfer to Hot Leg transfer (ES-1.4) (JPM-CR-066-e)

K/A EPE011 EK3.13 A, EN, L, M, S 3

d. Align the RHR System for ECCS Mode (OP-111)

(JPM-CR-290-a) D, L, S 4P

K/A 005 A4.01

e. Isolate Ruptured C SG (E-3)

(JPM-CR-105-a) A, N, L, S 4S

K/A 039 A4.01

f. Reduce Containment Spray Flow (ECA-1.1)

(JPM CR-233-e) M, EN, L, S 5

K/A 026 A4.01

g. Restoration of Offsite Power to Emergency Buses (EOP ECA-0.0) (JPM-CR-291-c) A, P, D, S 6

K/A 055 EA1.07

h. Restoring Control Room Area HVAC to Normal After a CRIS (OP-173) (JPM-CR-171-d) EN, M, S 8

K/A APE067 AA1.05 RO ONLY

Form 3.2-2 Control Room/In-Plant Systems Outline

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 for SRO-U

i. Venting the Main Generator due to D,E, L 4S a loss of All AC Power

K/A 045 G.2.1.30

j. Place a Safety Train Battery Charger on the Alternate D, E, L 6 Power Supply (OP-156.01) (JPM-IP-246)

K/A APE058 AA1.01

k. Locally Isolate The Seal Water Return Heat Exchanger D, E, R 8 (AOP-014) (JPM-IP-288)

K/A 008 A2.02

Rev-0 2

Form 3.2-2 Control Room/In-Plant Systems Outline

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

License Level Control Room In-Plant Total

Reactor Operator (RO) 8 3 11 Senior Reactor Operator-Instant 7 3 10 (SRO-I)

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

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.

Rev-0 3

Form 3.2-2 Control Room/In-Plant Systems Outline

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.

Rev-0 4

Form 3.2-2 Control Room/In-Plant Systems Outline

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

Code License Level Criteria Actual RO SRO-I SRO-U RO SRO-I SRO-U (A)lternate path 4-6 4-6 2-3 5 4 3 (C)ontrol room (D)irect from bank 9 8 4 6 7 3 (E)mergency or abnormal in-1 1 1 3 3 3 plant (EN)gineered safety feature 1 1 1 3 4 1 (for control room system)