ML23199A212

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Form 2.3-3 Operating Test Review Worksheet
ML23199A212
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/24/2023
From:
NRC/RGN-III/DORS/OB
To:
Point Beach
Jim Nance
Shared Package
ML22007A028 List:
References
Download: ML23199A212 (1)
v • d • e


Text

Form 2.3-3 Operating Test Review Worksheet (JPMs) 1 Facility: Point Beach Exam Date: February 13 - 18, 2023 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 SRO ADMIN LOD REF IC TSK CUE CS TL A.1.1 - PBN JPM P001.003f.COT -

Shutdown Margin Calculation S

A.1.2 - PBN JPM P001.025a.COT -

Respond to Rod Insertion Limit Alarm E

S NRC: Need to change Initiating Cue to: The Unit Supervisor has directed you to verify Rod Insertion Limits and Tech Spec implications Response: Added and Tech Spec implications A.2 - PBN JPM NUCTAG104a.SR O - Approve a Clearance Order E

S NRC: 1) Step 4, 2P-2C should be 1P-2C; Response: Made requested change A.3 - PBN JPM P119.212a.SRO -

Approve Radioactive Release Permits S

NRC: Validated JPM PBN P028.012.EMR -

Personnel Emergency Dose Authorization during On-Site Validation to replace PBN JPM P119.212a.SRO - Approve Radioactive Release Permits due to recent on two previous NRC exams.

Response: Sat A.4 - PBN JPM P028.001e.EMR -

Classify an Emergency Event in Accordance with EPIP 1.2 S

Early Look Unsat Enhancement Satisfactory

Form 2.3-3 Operating Test Review Worksheet (JPMs) 2 Facility: Point Beach Exam Date: February 13 - 18, 2023 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 RO ADMIN LOD REF IC TSK CUE CS TL A.1.1 - PBN JPM P004.005a.COT -

Perform Boron Concentration E

S NRC: 1) Initial Conditions change 7005 to 7500; 2) Make Performance Steps 3 and 4 Critical Steps; 3) In step 3, change (+/- 1.0) to

(+/- 0.1); 4) Delete Step 5 Response: Made all requested changes A.1.2 - PBN JPM P157.002.AOT -

Receive Fuel Oil E

S NRC: 1) Front Page Check RO for Task Applicability; 2) Also in Step 3 change T-175B level to 40% from 20%.

Response: Made all requested changes A.2 - PBN P000.015.COT -

Respond to a CCW Malfunction E

S NRC: 1) Add P&ID 110E029 Sh.3; 2) Add valves 1CC-741C (Pressure Transmitter) and 1V13D (Vent)

Response: Made all requested changes A.3 - PBN JPM P162.006b.AOT -

Determine a Stay Time for a High Radiation Area E

S NRC: 1) Correct spelling on cover page PERMITS; 2) Check RO on cover page Response: Made all requested changes Early Look Unsat Enhancement Satisfactory

Form 2.3-3 Operating Test Review Worksheet (JPMs) 3 Facility: Point Beach Exam Date: February 13 - 18, 2023 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 CONTROL ROOM/SIM LOD REF IC TSK CUE CS TL GENERAL COMMENTS Ensure that all setups are complete, e.g.,

placards in place, procedures marked up, handouts available, etc.

a. SIM -

P001.020.COT -

Perform Rod Exercise Test (Alt Path)

S

b. SIM -

P004.027a.COT -

Manually Makeup to the VCT/RWST E

S NRC: 1) Performance Step 4 Change to not critical; 2) Performance Steps 12 and 13 are Critical Steps Response: Made requested changes

c. SIM -

P010.010d.COT -

Initiate Low Temperature Overpressure Protection (Alt Path)

E S

NRC: 1) Initiating Cue - should be Step 5.18.6 - also make sure handout is marked up through 5.18.5; 2) Delete Performance Steps 1,2, and 3 i.e., start at 5.18.6 Response: Made requested changes

d. SIM -

P003.001.COT -

Start a Reactor Coolant Pump E

S NRC: 1) Add cue regarding S/G and R/X metal temperatures; 2) Performance Step 10, make clear what is critical and what is not critical; 3) Step 11, cue: AO may be sent to rod drive room Response: Made requested changes

Form 2.3-3 Operating Test Review Worksheet (JPMs) 4 Facility: Point Beach Exam Date: February 13 - 18, 2023 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 CONTROL ROOM/SIM LOD REF IC TSK CUE CS TL

e. SIM - PBN JPM P000.037d.COT -

Operate Steam Dumps During Post-Trip Cooldown (Alt Path)

E S

NRC: 1) Modify conditions from 25 degree cooldown rate to 100 degree cooldown rate;

2) clearly define success path and endpoint Response: Made requested changes. Added a minimum of 3 degrees F of cooldown should be observed to evaluate the examinees control of RCS temperature.
f. SIM - PBN JPM P026.002.COT -

Respond to Containment Spray Actuation Failure (Alt Path)

S

g. SIM -

P015.003a.COT -

Return Excore Nuclear Instrument to Service (RO Only)

E S

NRC: 1) Need to have a markup for steps 1 and 2 of Attachment A; 2) Placard was missing from 1C03 see general comment.

Response: Made requested changes

h. SIM -

P008.003a.COT -

Shift CCW Pumps E

S NRC: 1) Change JPM to UNIT 2 Response: Made requested changes Early Look Unsat Enhancement Satisfactory

Form 2.3-3 Operating Test Review Worksheet (JPMs) 5 Facility: Point Beach Exam Date: February 13 - 18, 2023 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 INPLANT LOD REF IC TSK CUE CS TL

i. IP -

P000.039e.AOT -

Fast Start an Emergency Diesel Generator Locally (Alt Path)

S

j. IP -

P000.037d.AOT -

Locally Opening Rx Trip Breakers (Alt Path)

E S

NRC: 1) Add drawing of RPS logic showing various breakers and ways to interrupt the electrical path; 2) show what success looks like Response: Added Evaluator information sheet for administering the JPM showing RPS logic circuitry. For Evaluator use only, not to be given to applicant.

k. IP -

P000.036c.AOT -

Refill RWST (RCA)

S Early Look Unsat Enhancement Satisfactory

7 Facility: Point Beach Scenario: # 1 100% Rx. Power Exam Date: February 13 - 18, 2023 1

Scenario Event ID/Name 2

Scenario Event Errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS

GENERAL COMMENT

Add functions to all Tech Spec Calls

1. Unload G01 EDG following surveillance S

Normal - BOP Normal - SRO

2. High Vibrations on Containment Accident Recirc Fan S

Component - BOP Component / TS - SRO

3. 1RC-431C (PZR PORV)

Sticks open (CT)

S Component - ATC Component / TS - SRO

4. CW Degradation (Fish Intrusion)

S Component - BOP Component - SRO

5. Perform Rapid Power Reduction E

S NRC: Add Reactivity event for BOP Response: Reactivity event for ATC and BOP Reactivity - ATC / BOP

6. Reactor Coolant Leak /

Charging to maximum to control PZR level S

Component / Manual Control - ATC Component / TS - SRO

7. LOCA / SI /

Auto Rx Trip Fails S

Major - Crew

8. Manual Rx Trip successful S

NRC: Break out Event 8 from Event 7 on page 6 and in the guide itself

8 Facility: Point Beach Scenario: # 1 100% Rx. Power Exam Date: February 13 - 18, 2023 1

Scenario Event ID/Name 2

Scenario Event Errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS

GENERAL COMMENT

Add functions to all Tech Spec Calls in inserting Control Rods (CT)

Response: Made requested changes Component / Manual Control - ATC Component - SRO Early Look Unsat Enhancement Satisfactory

9 Facility: Point Beach Scenario: # 2 Low Power Ops Raising Power from 2% to 4%

Exam Date: February 13 - 18, 2023 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. Raise power to 4%

E S

NRC: 1) (R) ATC and BOP; 2) Move Event 1 to Event 2 Response: 1) (R) ATC / BOP; 2) Moved Event 1 to Event 2 Reactivity - ATC / BOP - Event 2

2. Perform Tech Spec Surveillance TS 39 Train A E

S NRC: 1) The simulator setup is unreliable for this event. Swap out this event and add Switch running feed/condensate train; 2) Move Event 2 to Event 1 Response: 1) Swapped out event 2; 2)

Moved Event 2 to Event 1 Normal - BOP - Event 1

3. Low Gas pressure on ECCS accumulator E

S NRC: Initially the accumulator pressure gauge on the panel showed 700 psig when the simulator program showed 690 psig. Lower simulator computer pressure so that display gauge shows less than 700 psig Response: Simulator pressure now shows gauge less than 700 psig Component - BOP Component / TS - SRO

4. 1CV-135 Letdown Line Backpressure controller oscillations in S

Component / Manual Control - ATC Component - SRO

10 Facility: Point Beach Scenario: # 2 Low Power Ops Raising Power from 2% to 4%

Exam Date: February 13 - 18, 2023 1

Scenario Event ID/Name 2

Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS AUTO; works in manual

5. Component Cooling Pump trip with failure to start standby pump. AOP-9B S

Component / Manual Control - BOP Component / TS - SRO

6. Seismic Event causing multiple CRs to drop / Rx Trip S

Component - ATC Component - SRO

7. After the Reactor Trip, a Steam Line Break occurs downstream of MSIV, 1MS-2017 (CT)

S Major - Crew

8. MSIVs fail to auto close on SLI signal (manual operation not successful, direction of local action required)

(CT)

S Component - Crew

11 Facility: Point Beach Scenario: # 4 100% power Exam Date: February 13 - 18, 2023 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. SW pump shift S

Normal Event - BOP Normal Event - SRO

2. PRNI Channel 1 Fails High PZR Level Channel 2 (controlling) fails low E

S Instrument / - ATC / BOP Instrument / TS - SRO NRC: 1) Replace Event 2 with Event 3 Response: Done

3. PZR Level Channel 2 (controlling) fails low Trip of running EHC Pump/Standby fails to start E

S Component / Manual Control - BOP Component - SRO NRC: 1) Remove Alarm 1CO4 1C 2-3, Pressurizer Level Setpoint Deviation; 2)

Replace Event 3 with Event 4 Response: 1) Removed; 2) Done

4. Trip of running EHC pump and Standby fails to start. B SG Tube Leak (~50 gpd)

IAW AOP 3, S

Component - ATC Component / TS - SRO

5. B SG Tube Leak (~50 gpd)

IAW AOP 3, Rapid Down-power to <50%

Power IAW AOP17A E

S NRC: 1) B SG Tube Leak moves to Event 4 and Rapid Power Reduction becomes Event 5 Response: Done Reactivity - ATC / BOP

12 Facility: Point Beach Scenario: # 4 100% power Exam Date: February 13 - 18, 2023 1

Scenario Event ID/Name 2

Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS

6. B SGTR -

(EOP-0 -> EOP-

3) CT S

Major - Crew

7. Condensate Steam Dump Failure (CSD) requiring use of ADV to Cooldown (2-CTs)

S Component / Manual Control - BOP Component - SRO

13 Facility: Point Beach Scenario: (Spare) # 5 65% power Exam Date: February 13 - 18, 2023 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. Shift Control Room Fans S

Normal - BOP Normal / TS - SRO

2. High feed pump vibrations on 1P-28A SG Feed Pump S

Component - BOP Component - SRO

3. Rapid power reduction to less than 60% power E

S NRC: Add Reactivity Event for BOP Response: Done Reactivity - ATC / BOP

4. Failure Low of LT-462 (Blue)

(Steam Generator Level Loop A)

S Instrument - BOP Instrument / TS - SRO

5. LBLOCA, reactor trip/SI -

(EOP-0 -> EOP-

1)

S Major - Crew

6. SI auto actuation failure.

Requires manual actuation of SI (CT)

S Component / Manual Control - ATC Component - SRO

7. Containment accident cooling unit 1W-1A1 fails to auto start (E0 S

Component / Manual Control - BOP Component - SRO

14 Facility: Point Beach Scenario: (Spare) # 5 65% power Exam Date: February 13 - 18, 2023 1

Scenario Event ID/Name 2

Scenario event errors 3

U/E/S 4

Explanation Realism/

Credibility Performance Standards Verifiable Actions Critical Task TS Attachment A, Step A5 failure)

8. Transfer to Containment Sump Recirc IAW EOP-1.3 (CT)

S Major - Crew

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