Text

Administered Examination Files - Administered Operating Test
	ML22243A229
Person / Time
Site:	Peach Bottom
Issue date:	05/27/2022
From:	; NRC/RGN-I/DORS/OB
To:	; Constellation Nuclear
Shared Package
ML21020A063	List: ML22136A021; ML22206A258; ML22206A264; ML22206A269; ML22235A720; ML22243A107; ML22243A229; ML22250A683;
References
	EPID L-2022-OLL-0004
	Download: ML22243A229 (187)
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RO CO1 Page 1 of 7 Constellation Energy OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-264C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

006 AUTHOR:

D. Adams TYPIST:

dwa TITLE:

2022 ILT NRC RO ADMIN JPM CO1 APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: __________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

RO CO1 Page 2 of 7 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2020010201 / PLOR-264C K/A:

G2.1.20 RO: 4.6 SRO: 4.6 TASK DESCRIPTION:

Perform DAILY JET PUMP OPERABILITY Surveillance A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

RO CO1 Page 3 of 7 B.

TOOLS AND EQUIPMENT

1.

In-progress copy of ST-O-02F-560-2, AT 2 (Candidate Copy); Completed up to and including step 6.1.1, with data inserted into Data Sheets 1-5.

2.

JPOD Printout, AT 3

3.

Calculator C.

REFERENCES

1.

ST-O-02F-560-2 Rev 20, DAILY JET PUMP OPERABILITY D.

TASK STANDARD

1.

Satisfactory task completion is indicated when ST-O-02F-560-2, Daily Jet Pump Operability is completed and turned in for supervisory review.

2.

Estimated time to complete: 30 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to complete ST-O-02F-560-2, Daily Jet Pump Operability, and turn it in for supervisor review. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is at 100% power.

2.

Surveillance ST-O-02F-560-2, DAILY JET PUMP OPERABILITY, is in progress, and is complete up to and including step 6.1.1.

3.

Data recording for step 6.2.1 is also complete.

4.

The required information on Data Sheets 1 - 5 has been recorded.

5.

NO CALCULATIONS HAVE BEEN PERFORMED.

6.

Current day/time is 0800 on Sunday.

G.

INITIATING CUE Complete Section 6.0 of Surveillance ST-O-02F-560-2, DAILY JET PUMP OPERABILITY, starting at step 6.1.2. When complete, provide to Shift Management to perform an independent verification in Section 7.0.

RO CO1 Page 4 of 7 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Review ST to ensure all data is recorded and in Normal Band.

(Cue: N/A)

P ST reviewed.

Note: There may be very small differences from the STANDARDS due to rounding.

2 CALCULATE average Jet Pump differential pressure for each loop AND RECORD in AVG space on Data Sheet 1 and 2.

(Cue: N/A)

P CALCULATEs average Jet Pump differential pressure for each loop AND RECORD in AVG space on Data Sheet 1 and 2.

Calculation performed; value recorded.

See Master Data Sheet for values.

3 CALCULATE LOOP AVG DRIVE FLOW as follows AND RECORD as Item 12 on Data Sheet 3 and 4:

(Item 10 + Item 11)/2 = AVG DRIVE FLOW (Cue: N/A)

P Calculates LOOP AVG DRIVE FLOW as follows AND RECORD as Item 12 on Data Sheet 3 and 4.

Calculation performed; value recorded.

See Master Data Sheet for values.

- - Note ***

Procedure Step 6.2.1, entry of information from PMS printout onto Datasheet 5, has been completed.

4 DETERMINE the absolute difference between the jet pump loop flow values (Item 7 on Data Sheet 3 and 4) AND RECORD as Item 7 on Data Sheet 5.

(Cue: N/A)

P Determines the absolute difference between the jet pump loop flow values (Item 7 on Data Sheet 3 and 4) AND RECORD as Item 7 on Data Sheet 5.

Calculation performed; value recorded.

See Master Data Sheet for values.

5 IF TOTAL CORE FLOW (Item 3 on Data Sheet 5) is greater than or equal to 71.75 Mlb/hr, THEN PERFORM the following.

VERIFY the absolute difference between jet pump loop flows (Item 7 on Data Sheet 5) is less than or equal to 5.125 Mlb/hr.

SIGNOFF on Data Sheet 8 P

IF TOTAL CORE FLOW (Item 3 on Data Sheet 5) is greater than or equal to 71.75 Mlb/hr, THEN PERFORMs the following.

VERIFY the absolute difference between jet pump loop flows (Item 7 on Data Sheet 5) is less than or equal to 5.125 Mlb/hr.

SIGNOFF on Data Sheet 8

RO CO1 Page 5 of 7 STEP NO STEP ACT STANDARD (Cue: N/A)

6 PLOT LOOP A AVG DRIVE FLOW (MLB/HR) versus A PUMP SPEED on Figure 1 AND PERFORM the following:

1.

VERIFY the point is within the Acceptable Range.

2.

SIGNOFF on Data Sheet 8.

(Cue: N/A)

P Plots LOOP A AVG DRIVE FLOW (MLB/HR) versus A PUMP SPEED on Figure 1 AND PERFORM the following:

1. Identifies the point is NOT within the Acceptable Range.

2. Signs off on Data Sheet 8.

7 PLOT LOOP B AVG DRIVE FLOW (MLB/HR) versus B PUMP SPEED on Figure 1 AND PERFORM the following:

1.

VERIFY the point is within the Acceptable Range.

2.

SIGNOFF on Data Sheet 8.

(Cue: N/A)

P PLOTs LOOP B AVG DRIVE FLOW (MLB/HR) versus B PUMP SPEED on Figure 1 AND PERFORM the following:

1.

Verifies the point is within the Acceptable Range.

2.

Signs off on Data Sheet 8.

8 PLOT LOOP A JET PUMP TOTAL FLOW (MLB/HR) versus A PUMP SPEED on Figure 1 AND PERFORM the following:

1.

VERIFY the point is within the Acceptable Range.

2.

SIGNOFF on Data Sheet 8.

(Cue: N/A)

P PLOTs LOOP A JET PUMP TOTAL FLOW (MLB/HR) versus A PUMP SPEED on Figure 1 AND PERFORM the following:

1.

Verifies the point is within the Acceptable Range.

2.

Signs off on Data Sheet 8.

9 PLOT LOOP B JET PUMP TOTAL FLOW (MLB/HR) versus B PUMP SPEED on Figure 1 AND PERFORM the following:

1.

VERIFY the point is within the Acceptable Range.

2.

SIGNOFF on Data Sheet 8.

(Cue: N/A)

P PLOTs LOOP B JET PUMP TOTAL FLOW (MLB/HR) versus B PUMP SPEED on Figure 1 AND PERFORM the following:

1.

Verifies the point is within the Acceptable Range.

2.

Signs off on Data Sheet 8.

RO CO1 Page 6 of 7 STEP NO STEP ACT STANDARD

- - NOTE ***

Calculation performed in Step 10 below may be done with the Jet Pump Operability Data program on the PC at the URO station OR with the formula provided in the procedure. IF the PC is used, ensure any printed data sheet is controlled as Exam Material. Alternately, the JPOD datasheet (AT3) may be provided to candidate if this JPM is being completed in a classroom.

10 If the JPOD computer program is available to calculate Jet Pump D/P %

Deviation, then perform the following:

Record See Attached in the %

DEVIATION column on Data Sheets 6 and 7 for Sunday.

(Cue: JPOD computer program output is provided as a handout to the student.)

P Records See Attached in the %

DEVIATION column on Data Sheets 6 and 7 for Sunday.

11 VERIFY all JET PUMP D/P %

DEVIATIONS on the attached printout OR recorded on Data Sheets 6 and 7 are within the LOW and HIGH ACCEPTABLE DEVIATION and SIGNOFF on Data Sheet 8.

(Cue: N/A)

P VERIFYs all JET PUMP D/P %

DEVIATIONS on the attached printout OR recorded on Data Sheets 6 and 7 are within the LOW and HIGH ACCEPTABLE DEVIATION and signs-off on Data Sheet

8.

12 VERIFY either ST Steps 6.3.2.1 through 6.3.5.1 OR ST Step 6.3.8 is satisfactorily met and SIGNOFF on Data Sheet 8.

(Cue: N/A)

P VERIFIES either ST Steps 6.3.2.1 through 6.3.5.1 OR ST Step 6.3.8 is satisfactorily met and signoffs on Data Sheet 8.

13.

VERIFY that no more than one jet pump differential pressure indicator is inoperable, as indicated by 0 psid OR downscale reading recorded on Data Sheets 1 AND 2 AND SIGNOFF on Data Sheet 8.

P Verifies that no more than one jet pump differential pressure indicator is inoperable, as indicated by 0 psid OR downscale reading recorded on Data Sheets 1 AND 2 AND signs off on Data Sheet 8.

RO CO1 Page 7 of 7 STEP NO STEP ACT STANDARD 14 VERIFY Daily Jet Pump Operability completed each applicable day between the hours of 0700 and 1300 AND SIGNOFF on Data Sheet 8.

(Cue: Time is 0800 on Sunday)

P Verifies Daily Jet Pump Operability completed each applicable day between the hours of 0700 and 1300 AND SIGNOFF on Data Sheet 8.

15 VERIFY Shift Management review of test results AND SIGNOFF on Data Sheet 8.

(Cue: Accept ST for review)

P VERIFY Shift Management review of test results AND SIGNOFF on Data Sheet 8.

16 As an evaluator, ensure you have positive control of all exam material provided to the examinee (Task Conditions /

Prerequisites) AND procedures AND any Data Sheets or scrap paper used for calculations.

Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When then Surveillance has been turned over for Shift Management review, the evaluator will terminate the exercise.

RO CO2 Page 1 of 5 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-415C COURSE:

Initial License Training REV #:

000 AUTHOR:

S. Andersen TYPIST:

sra TITLE:

2022 ILT NRC RO ADMIN JPM CO2 APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

RO CO2 Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator TASK-JPM DESIGNATOR:

2610080201/ PLOR-415C K/A:

G2.1.18 RO: 3.6 TASK DESCRIPTION:

Standby Gas Treatment Filter Train Operation Log A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

RO CO2 Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

ST-O-09A-500-2, Rev. 7, Standby Gas Treatment Filter Train Operation Log C.

REFERENCES

1.

ST-O-09A-500-2, Rev. 7, Standby Gas Treatment Filter Train Operation Log D.

TASK STANDARD

1.

Satisfactory task completion is indicated when Section 6 of ST-O-09A-500-2, Standby Gas Treatment Filter Train Operation Log, is completed, and deficiencies and associated corrective actions are identified.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, review the provided data and complete ST-O-09A-500-2, Standby Gas Treatment Filter Train Operation Log as directed. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

It is day shift on Wednesday.

2.

The C SBGT Fan and the B Train of SBGT were placed in at 1152 and removed from service at 1522.

G.

INITIATING CUE The Control Room Supervisor directs you complete Section 6 of ST-O-09A-500-2, Standby Gas Treatment Filter Train Operation Log. Determine what actions are required, if any. If actions are required, state which Steps require action, and the action required.

RO CO2 Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain open copy of ST-O-09A-500-2.

(Cue: Provide marked-up copy of ST-O-09A-500-2 (AT2) to the Examinee)

P Obtains copy of ST-O-09A-500-2.

2 RECORD In Service Time, Out of Service Time, AND date for SBGT System Filter Trains A and B on Data Sheet 1.

P Records the following on Data Sheet 1, SBGT System Train B Filter:

In Service: Todays Date / 1152 Out of Service: Todays Date / 1522

3 CALCULATE AND RECORD Total Time in Service for each filter train by subtracting Out of Service Time from In Service Time on Data Sheet 1.

P Records the following on Data Sheet 1, SBGT System Filter Train B Filter:

Total Time In Service: 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (or 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 30 minutes)

4 CALCULATE Total Time since Filter Test by adding Total Time In Service AND Accumulated Total Time since DOP Test AND RECORD on Data Sheet 1.

P Records the following on Data Sheet 1, SBGT System Filter Train B Filter:

Accumulated Total Time Since Filter Test:

551 hours0.00638 days 0.153 hours 9.11045e-4 weeks 2.096555e-4 months 48 minutes.

5 NOTIFY SBGT System Manager once accumulated time is greater than 550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months .

(Cue: Acknowledge the communication.)

P Records on cue sheet that System Manager notification is required per step 6.1.4 and/or Data Sheet 1 Note 1.

6 VERIFY that Total Accumulated Time since DOP test is less than 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months .

P Initials Sat on Data Sheet 1, SBGT System Filter Train B Filter.

7 RECORD filter use OR non-use AND Date once per shift on Data Sheet 2.

P Records the following on Data Sheet 2, row WED D:

Todays Date

X or Check in the Filters Used, Yes column

Initials in Sat column 8

Inform Control Room Supervisor of completion of Section 6 of ST-O-09A-500-2.

(Cue: Acknowledge the communication.)

P Informs Control Room Supervisor of completion of Section 6 of ST-O-09A-500-2.

RO CO2 Page 5 of 5 STEP NO STEP ACT STANDARD 9

As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control maintained.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When Section 6 of ST-O-09A-500-2 has been completed and actions required are noted, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

RO EC Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-XXXC COURSE:

Licensed Operator Requalification REV #:

000 AUTHOR:

D.W. Adams TYPIST:

DWA TITLE:

2022 ILT NRC RO ADMIN JPM EC APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

RO EC Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator TASK-JPM DESIGNATOR:

2100070201/ PLOR-XXXC K/A:

2.2.22 RO: 4.0 SRO: 4.7 TASK DESCRIPTION:

Review Reactor Vessel Temperatures During Cooldown A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

RO EC Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

Completed copy of ST-O-080-500-2, Recording and Monitoring Reactor Vessel Temperatures and Pressure

2.

Calculator C.

REFERENCES

1.

ST-O-080-500-2 Rev. 20, Recording and Monitoring Reactor Vessel Temperature and Pressure

2.

Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits

3.

Technical Requirements Manual, Appendix D, Pressure and Temperature Limits Report (PTLR)

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when steps 6.1.6 through 6.1.11 of ST-O-080-500-2 have been completed.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, verify compliance with ST-O-080-500-2, Recording and Monitoring Reactor Vessel Temperatures and Pressure. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

A reactor cooldown is in progress with a stable cooldown rate established.

2.

Data for ST-O-080-500-2, Recording and Monitoring Reactor Vessel Temperatures and Pressure has been recorded on Data Sheet 1 of the procedure copy to be provided to you.

G.

INITIATING CUE Perform steps 6.1.6 through 6.1.11 of ST-O-080-500-2 and complete Data Sheet 1 of ST-O-080-500-2, Recording and Monitoring Reactor Vessel Temperatures and Pressure.

Document any identified issues and required actions on the cue sheet.

RO EC Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - - NOTE****

Provide the examinee with a consumable copy of ST-O-080-500-2 with five lines of temperature data complete on Data Sheet 1.

1 Determine which required temperature points are valid for 100°F/hr compliance.

(Cue: Both Recirc Pumps are running.

Acknowledge selection of temperature points.)

P Determine that Steam Dome Saturation Temperature, Bottom Head Drain Temperature, and both Recirc Pump Suction Temperature are valid for 100°F/hr compliance. Column 11 is marked N/A (due to Recirc Pump operation).

2 Review/Calculate the difference between the current valid temperature points and the values taken 15 minutes ago.

P A calculation of the 15-minute differential temperature for Steam Dome Saturation Temperature, Bottom Head Drain Temperature, and both Recirc Pump Suction Temperature is made.

3 Review the value of the largest 15-minute change from the valid temperature points on Data Sheet 1.

P Reviews the value of the largest 15-minute change from the valid temperature points on Data Sheet 1.

4 Verify the largest 15-minute temperature change is less than or equal to 20°F.

P Review the largest 15-minute temperature change.

Acknowledge that there are points that exceed 20°F/15 min at 0130 and 0215.

Column 13 is verified to be initialed for these times.

5 Determine that Steam Dome Saturation Temperature has changed by more than 100°F in the last hour.

TSAT (Column 8) lowered by 103°F between 0215 and 0115.

P Documents the following on the cue sheet:

Steam Dome Saturation Temperature change is greater than the allowable 100°F per hour.

Cooldown rate must be lowered.

6 Initials in the UNSAT block for exceeding the cooldown rate.

P Initials in the black box (Column 14) for the 0215 temperature line.

RO EC Page 5 of 5 STEP NO STEP ACT STANDARD 7

Determine the appropriate P-T Curve Figure for the current plant conditions.

P Table 4 is determined to be the appropriate P-T curve.

8 Determine the required valid temperature points per Table 4.

P Table 4 is used to determine the following valid points:

- Curve B - Saturation Temperature

- Curve BBH - Recirc Pump Suction Temperature 9

Verify reactor pressure and the required valid temperatures are on the safe side of the required P-T Curve.

P Reactor Pressure versus Steam Dome Saturation Temperature are verified to be on the right side of Table 4 Curve B.

Recirc Pump Suction Temperatures are verified to be on the right side of Table 4 Curve BBH.

10 Initials in Column 6 for P/T Curve Compliance.

P Initials all lines as Satisfactory in Column 6.

11 Inform the Evaluator of task completion.

(Cue: Evaluator acknowledges report.)

P Task completion reported.

12 As the evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the evaluation and entry of data on ST-O-080-500-2 are complete including evaluation and documentation of issues and required actions, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

RO EP Page 1 of 6 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-XXXC COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

000 AUTHOR:

D.W. Adams TYPIST:

dwa TITLE:

2022 ILT NRC RO ADMIN JPM EP APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

Employee ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

RO EP Page 2 of 6 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator TASK-JPM DESIGNATOR:

2950110501/PLOR-XXXC K/A:

2.4.39 RO: 3.9 TASK DESCRIPTION:

Verification of EONS Transmittal A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

RO EP Page 3 of 6 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

EP-MA-114-100 Rev. 29, Mid-Atlantic State/Local Notifications

7.

EP-MA-114-100-F-01 Rev T, "State/Local Notification Form D.

TASK STANDARD

1.

Satisfactory task completion is indicated when EP-MA-114-100-F-01, State/Local Event Notification Form has been communicated to all offsite agencies accurately.

2.

Estimated time to complete: State/Local Notification - 15 minutes: Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to make the EONS transmittal. I will describe initial plant conditions and provide you access to the materials required to complete this task.

RO EP Page 4 of 6 F.

TASK CONDITIONS/PREREQUISITES NOTE: This is a time critical JPM.

1.

The Shift Manager has declared a Site Area Emergency and has completed the EONS form.

G.

INITIATING CUE As the Shift Communicator, perform the NARS Notification of the declared event in accordance with EP-MA-114-100, Mid-Atlantic State/Local Notifications.

RO EP Page 5 of 6 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - NOTE ***

Time Start = ________

1 Obtain a copy of EP-MA-114-100-F-07, Mid-Atlantic EONS NARS Roll Call Form, and the completed EONS Form.

P Procedure EP-MA-114-100-F-07, Mid-Atlantic EONS NARS Roll Call Form and completed EONS form are obtained.

2 Verify completeness of the EONS Form.

P Verifies EONS Form is complete and approved.

3 Press the NOTIFY button on the EMnet telephone.

P Presses the NOTIFY button on the EMnet telephone.

4 Reads the following message:

This is the Exelon Nuclear Peach Bottom Atomic Power Station. Please standby for confirmation of a NARS message.

P Reads the following message into the EMnet phone:

This is the Exelon Nuclear Peach Bottom Atomic Power Station. Please standby for confirmation of a NARS message.

5 Conduct an initial roll call for the affected agencies listed in EP-MA-114-100-F-07, and document the time completed.

(Cue: Respond Here as each agency is called. All agencies listed are present on the call.)

P Performs a roll call for the following agencies:

Pennsylvania EMA

Maryland EMA

York County

Harford County

Cecil County

Lancaster County

Chester County Writes the time verified by each agency and the time the initial roll call was completed.

6 Announce This is a drill.

P States This is a drill to all agencies.

7 Ask all agencies on the phone the following questions:

1. Did any agency not receive the emergency notification form from Peach Bottom?

2. For those agencies that did receive the emergency message, are there any questions about the information in the emergency notification sent by Peach Bottom?

(Cue: York County and Cecil County did not receive the electronic transmittal.)

P Asks all agencies on the phone the following questions:

1. Did any agency not receive the emergency notification form from Peach Bottom?

2. For those agencies that did receive the emergency message, are there any questions about the information in the emergency notification sent by Peach Bottom?

Identifies that York and Cecil Counties did not receive the electronic transmittal.

8 Transmit the message to any agency that did not receive the electronic transmittal.

P Reads the entire completed EONS form for York County and Cecil County.

RO EP Page 6 of 6 STEP NO STEP ACT STANDARD 9

Perform a final roll call to verify all agencies received the message.

P Performs a final roll call for the following agencies:

Pennsylvania EMA

Maryland EMA

York County

Harford County

Cecil County

Lancaster County

Chester County Writes the time verified by each agency and the time the final roll call was completed.

11 Verify there are no further questions.

(Cue: No further questions.)

P Asks all agencies if there are any further questions.

12 Announce This completes the call, thank you., and ends the call.

P Announces This completes the call, thank you., and hang up the EMnet phone.

- - NOTE ***

Time Stop = _____

Determine if the elapsed time since the initial cue exceeds 15 minutes.

13 As the evaluator, ensure that you have positive control of all exam material provided to the examinee (Task condition/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the emergency notification has been completed, the evaluator will then terminate the exercise.

SRO CO1 Page 1 of 5 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-273C COURSE:

Licensed Operator Requalification REV #:

001 AUTHOR:

D.W. Adams TYPIST:

dwa TITLE:

2022 ILT NRC SRO ADMIN JPM CO1 APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ___________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID#: ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

CONSTELLATION ENERGY X

SRO CO1 Page 2 of 5 PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

3410170302 / PLOR-273C K/A:

G2.1.19 SRO: 3.8 TASK DESCRIPTION:

Ability to determine actions required for an Inoperable Fire Door A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

SRO CO1 Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

A copy of ST-O-037-390-2, Rev 5, Fire Door Electrical Supervisory Alarm System

2.

Drawing A-486 Barrier Plan Elev. 135

3.

Technical Requirements Manual section 3.14 C.

REFERENCES

1.

ST-O-037-390-2, Rev 5, Fire Door Electrical Supervisory Alarm System

2.

Drawing A-486 Barrier Plan Elev. 135

3.

Technical Requirements Manual section 3.14 D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the Technical Requirements Manual compensatory measures have been identified.

2.

Estimated time to complete: 15 minutes Non-Time Critical.

E.

DIRECTIONS TO EXAMINEE When given the initiating cue, determine any actions required to be taken for Fire Door #217 Supervisory Alarm System failing to alarm.

F.

TASK CONDITIONS/PREREQUISITES

1.

Fire Door supervisory alarm testing is in progress in accordance with ST-O-037-390-2 Fire Door Electrical Supervisory Alarm System.

2.

You have just been notified that Fire Door #217 has been fully open for eleven minutes and has failed to alarm.

3.

Previous fire surveillance testing has determined that multiple smoke detectors on Turbine Building 135 are inoperable on both sides of the door.

4.

A fire watch patrol has been established.

G.

INITIATING CUE As the Unit 2 Control Room Supervisor review ST-O-037-390-2 Fire Door Electrical Supervisory Alarm System and identify any required action(s) for Fire Door #217. Document required action(s) on the cue sheet.

SRO CO1 Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of ST-O-037-390-2 Fire Door Electrical Supervisory Alarm System.

(Cue: Provide the candidate with a copy of ST-O-037-390-2)

P ST-O-037-390-2 Fire Door Electrical Supervisory Alarm System obtained.

2 Determine Fire Door location.

P Review ST-O-037-390-2 Data Sheet 1 and determine Fire Door 217 is located on TB2 elevation 135 in the 2A & 2C Battery Room.

3 Review ST-O-037-390-2 sections 4 and

5.

P Review ST-O-037-390-2 Fire Door Electrical Supervisory Alarm System for Precautions, Limitations, General Instructions, and Acceptance Criteria.

4 Identify Fire Door #217 classification.

P Review ST-O-037-390-2 section 4 and determine Fire Door #217 is a Safety Related door identified by an

on Data Sheet 1.

5 Review ST-O-037-390-2 Performance Steps and Corrective actions.

P Review ST-O-037-390-2 section 6 for Test Requirements and Corrective Actions.

6 Identify alarm requirements for Fire Door

217.

P Determine Fire Door #217 is required to alarm in less than or equal to 10 minutes and is INOPERABLE.

7 Obtain a copy of the Unit 2 Technical Requirements Manual.

(Cue: Provide the candidate with a copy of the Unit 2 Technical Requirements Manual.)

P Obtain a copy of the Unit 2 Technical Requirements Manual and review section 3.14 Fire Protection Systems.

SRO CO1 Page 5 of 5

8 Determine Unit 2 Technical Requirements Manual required action.

P Review Technical Requirements Manual section 3.14.8 condition A Determines a continuous fire watch is required within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

9 Inform the Evaluator of task completion.

(Cue: The Control Room Supervisor acknowledges the report.)

P The operator informs the Evaluator of task completion.

10 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the Technical Requirement Manual compensatory actions have been identified, and the evaluator has been informed, the evaluator will terminate the exercise.

SRO CO2 Page 1 of 5 CONSTELLATION OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR -279C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

003 AUTHOR:

D.W. Adams TYPIST:

dwa TITLE:

2022 ILT NRC SRO ADMIN JPM CO2 APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ___________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID#: ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

CONSTELLATION X

SRO CO2 Page 2 of 5 PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2991120301 - PLOR-279C K/A:

G2.1.5 SRO: 3.9 TASK DESCRIPTION:

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

SRO CO2 Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

LS-AA-119 Fatigue Management and Work Hour Limits

2.

OP-PB-101-111-1002, Peach Bottom Operations Overtime Guidelines C.

REFERENCES

1.

LS-AA-119, Rev. 15, Fatigue Management and Work Hour Limits

2.

OP-PB-101-111-1002, Rev. 12, Peach Bottom Operations Overtime Guidelines D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the candidate successfully assesses the work hour limits and documents findings on the cue sheet.

2.

Estimated time to complete: 20 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review the work history provided, determine if you can cover the requested shift AND determine if any work hour limits have already been violated, using appropriate procedures. I will describe initial conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

The present time/date is 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on 2/16.

2.

In accordance with OP-PB-101-111-1002, Peach Bottom Operations Overtime Guidelines, the Shift Manager has directed the WECS to review the availability of RO #1 to work Dayshift 2/16 for load drop coverage.

3.

RO #1 was on vacation for two weeks, returning to work on Sunday, 2/3.

4.

RO #1 has been verified to be in compliance with the 54-Hour Rule.

5.

RO #1 work history for the previous two weeks is as follows, with all hours having been in posted Licensed Reactor Operator positions.

SRO CO2 Page 4 of 5 Sunday 2/3 Monday 2/4 Tuesday 2/5 Wednesday 2/6 Thursday 2/7 Friday 2/8 Saturday 2/9 Worked 1900 - 0700 Worked 1900 - 0700 OFF Worked 1900 - 1100 Worked 1900 - 0700 OFF OFF Sunday 2/10 Monday 2/11 Tuesday 2/12 Wednesday 2/13 Thursday 2/14 Friday 2/15 Saturday 2/16 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Worked 0700 - 1900 Request:

0700 to 1900 G.

INITIATING CUE Using the work history provided, document your responses to the following on the cue sheet:

1.

Determine if RO #1 can cover the required shift.

2.

If applicable, document all work hour limits that would be exceeded if RO #1 works Dayshift on Saturday 2/16.

3.

Determine if RO #1 has already violated any work hour limits.

4.

If applicable, document all work hour limits that have already been exceeded.

SRO CO2 Page 5 of 5 H.

PERFORMANCE CHECKLIST Evaluator Cue:

Along with the Cue Sheet, provide candidate with copy of procedures OP-PB-101-111-1002, Peach Bottom Operations Overtime Guidelines AND LS-AA-119 Fatigue Management and Work Hour Limits.

1 Review work history, OP-PB-101-111-1002, and LS-AA-119 to determine if able to work requested shift.

P Candidate reviews procedures for Work Hour limits and reviews work history provided.

2 Determine that working the requested future shift will result in exceeding work hour limits.

P Circles Cannot on the cue sheet for question #1.

3 Identifies work hour limits exceeded if RO

1 works on Saturday 2/16.

P Determines that working the requested shift would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period (Sunday, 2/10 through Friday, 2/15 shows 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months worked.

Working Saturday would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the 7-day period)

4 Determines whether or not RO #1 has already violated any work hour limits.

P Circles Yes on the cue sheet for question #3.

5 Determine that the break between shifts from Thursday 2/7 to Friday 2/8 was less than the required 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

P Documents less than a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break between 2/6 to 2/7 on the cue sheet for question #4.

6 Determine that shifts Thursday 2/7 to Friday 2/8 were greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months worked in 48-hour period.

P Documents greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months worked (actual of 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months ) in the 48-hour period over 2/6 to 2/8.

7 As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform I.

TERMINATING CUE When review is complete and the cue sheet has been completed, the evaluator will terminate the exercise.

SRO EC Page 1 of 5 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-206C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

001 AUTHOR:

D.W. Adams TYPIST:

dwa TITLE:

2022 ILT NRC SRO ADMIN JPM EC APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ________/________/________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

SOC. SEC. NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

PIMS CODE:

Signature/Date PIMS ENTRY:

X

SRO EC Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

3431710102 / PLOR-206C K/A:

2.2.23 SRO: 4.6 TASK DESCRIPTION:

Complete Tech Spec Log Entries A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

SRO EC Page 3 of 5 B.

TOOLS AND EQUIPMENT Blank copies of OP-PB-108-104, Attachment 1, Technical Specification Action Log.

M-356 Sh. 1, Rev. 75, P&ID Control Rod Drive Hydraulic System C.

REFERENCES

1.

M-356 Sh. 1, Rev. 75, P&ID Control Rod Drive Hydraulic System

2.

ST-O-003-450-2, Rev. 10, Scram Discharge Vent and Drain Valve Functional Test

3.

Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves

4.

OP-PB-108-104, Rev 2, Attachment 1, Technical Specification Action Log D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the Tech Spec Action Log Sheet has been completed for SDV vent valves AO-2-03-32A and AO-203-35A.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, complete the manual Tech Spec Action Log sheet for SDV vents AO-203-32A and AO-2-03-35A. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is operating at full power.

2.

At 0800 this morning AO-2-03-032A and AO-2-03-35A were declared inoperable due to failing ST-O-003-450-2, Scram Discharge Vent and Drain Valve Functional Test, steps 6.1.3 and 6.2.3 due to excessive stroke times.

3.

AR A1188549 has been initiated to repair the valves.

4.

All other Tech Spec plant equipment is operable.

5.

The Unified Control Room Log Computer is not operating.

G.

INITIATING CUE Determine the Tech Spec impact of these inoperable components, make manual Tech Spec Action Log entries per OP-PB-108-104, Regulatory Compliance Action Logs, for the MOST LIMITING CONDITION and submit the completed form to the Shift Manger for review.

SRO EC Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Determine the applicable Tech Spec for SDV vents AO-2-03-32A and AO-2-03-035A INOP.

P It is determined that Tech Spec 3.1.8 SDV Vent and Drain Valves is applicable.

2 Determine the location of AO-2-03-032A and 35A.

P It is determined that both vent valves are in the same line using P&IDs or Control Room panel mimics.

3 Determine the applicable Tech Specs for AO-2-03-32A and AO-2-03-035A being inoperable.

P Determines the following:

T.S. 3.1.8, Condition A, is applicable for AO-2-03-032A.

T.S. 3.1.8, Condition A, is applicable for AO-2-03-035A.

T.S. 3.1.8, Condition B, is applicable for AO-2-03-032A and 35A.

4 Determine the most limiting condition of Tech Spec 3.1.8.

P Determines that Tech Spec 3.1.8 Condition B is the most limiting condition.

5 Determine the required completion time for Required Action B.1.

P Determines that the completion time for Required Action B.1 is 1600 today.

- - NOTE ***

The following OP-PB-108-104, Attachment 1, Technical Specification Action Log entries may differ slightly from those listed in the task standard as long as the important information is included.

5 Complete OP-PB-108-104, Attachment 1, Technical Specification Action Log for AO-2-03-032A and 35A:

P The following data is entered in the fields listed below on OP-PB-108-104,, Technical Specification Action Log.

Unit - Unit 2

Entry # 2 - next TSA number

Tech Spec number - 3.1.8

Discovery Date/Time - todays date/0800

SRO EC Page 5 of 5 STEP NO STEP ACT STANDARD

Equipment ID - AO-2-03-032A and AO-2-03-035A

System # - 3

Reference # - AR 1188549

Condition - B, one or more SDV vent or drain lines with both valves inoperable.

SFD not required.

No other active SFDs. (See note below)

Reason - failed step 6.1.3 and 6.2.3 of ST-O-003-450-2

Required Action 1 - Isolate the associated line

Completion Time - 1600/todays date (NOTE: If queried by candidate, indicate no other SFDs are currently active.)

7 Submit the completed form to the Shift Manger for review.

(Cue: Role play as the Shift Manager and acknowledge receipt of the completed TSA log for review.)

P Completed form is given to the Shift Manger for review.

8 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When a Tech Spec Action Log sheet for AO-2-03-32A and AO-2-03-35A has been submitted to the Shift Manager, the evaluator will terminate the exercise.

SRO EP Page 1 of 7 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-XXXC COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

000 AUTHOR:

D.W. Adams TYPIST:

dwa TITLE:

2022 ILT NRC SRO ADMIN JPM EP APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

Employee ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

SRO EP Page 2 of 7 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2007510502/PLOR-235C K/A:

2.4.41 SRO: 4.6 TASK DESCRIPTION:

Classification of Emergencies and PARs A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

SRO EP Page 3 of 7 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

EP-AA-111 Rev. 23, Emergency Classification and Protective Action Recommendations

2.

EP-AA-111-F-08 Rev. I, Limerick / Peach Bottom Plant Based PAR Flowchart

3.

EP-AA-112-100 Rev. 19, Control Room Operations

4.

EP-AA-112-100-F-01 Rev. AD, Shift Emergency Director Checklist

5.

EP-AA-114-F-02 Rev A, BWR Release in Progress Determination Guidance

6.

EP-MA-114-100 Rev. 29, Mid-Atlantic State/Local Notifications

7.

EP-MA-114-100-F-01 Rev T, "State/Local Notification Form

8.

EP-AA-1007 Rev. 35, Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station

9.

EP-AA-1007, ADDM 3 Rev. 11, Exelon Nuclear Emergency Action Levels for Peach Bottom Atomic Power Station D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the plant conditions have been classified correctly and EP-MA-114-100-F-01, State/Local Event Notification Form has been completed accurately.

2.

Estimated time to complete: Event Classification - 15 minutes: Time Critical State/Local Notification - 13 minutes: Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to make the EAL classification and complete the State/Local Event Notification form (if required). I will describe initial plant conditions and provide you access to the materials required to complete this task.

SRO EP Page 4 of 7 F.

TASK CONDITIONS/PREREQUISITES NOTE: This is a time critical JPM.

1.

Unit 2 is in Mode 4.

2.

Unit 3 is operating at 100% power.

3.

An earthquake is felt in the plant.

4.

Alarm 316 A-5, Operating Basis Earthquake Exceeded, is in.

5.

MO-2-10-16A came off its closed seat and RPV water level lowered to -55 before operators manually closed it.

6.

RPV water level was then restored to the normal band.

7.

Wind speed is 10mph. Wind direction is 80 degrees.

G.

INITIATING CUE As the Emergency Director, make the EAL classification and complete the State/Local Event Notification form (if required).

SRO EP Page 5 of 7 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD

- - NOTE ***

Time Start = ________

1 Obtain procedures EP-AA-112-100-F-01, Shift Emergency Director Checklist, EP-AA-1007, Radiological Emergency Plan Annex for PBAPS, and EP-AA-1007, ADDM 3, Exelon Nuclear Emergency Action Levels for Peach Bottom Atomic Power Station P

Procedures EP-AA-112-100-F-01, EP-AA-1007, and EP-AA-107 ADDM 3 are obtained.

2 Determine the appropriate EAL IC.

(Cue: Classification is acknowledged.)

P EALs HU4 (Seismic event greater than OBE levels) and CA6 (Loss of RPV Inventory) are referenced.

Event is classified as an ALERT per CA6.

3 Announce the event classification to the facility staff.

P Announces the event classification to the Control Room crew.

- - NOTE ***

The following steps are associated with EP-MA-114-100-F-01, State/Local Event Notification Form.

Time Classification Completed = ___________

4 Opens EONS on the computer.

P Opens the yellow EONS icon.

5 Selects the appropriate site.

P Selects Peach Bottom in EONS.

6 Ensure an appropriate message number is entered, starting at 1 for the initial notification.

P Verifies Message Number 1 is annotated.

7 Enter Emergency Directors name.

P Enters name in Emergency Director block.

8 Enter the Call Status P

This is a drill is checked 9

Verify the appropriate affected station is displayed.

P Verifies Peach Bottom is listed as the affected station.

10 Identify the affected unit for the classification.

P Selects Unit 2.

11 Identify the level of the event classification.

P Alert is selected.

12 Enter the time and select the date of the declaration.

P Declaration time (in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock nomenclature) and todays date are entered in Block #4.

13 Select the notification type for the declaration.

P Initial Declaration is checked.

14 Select the applicable EAL number.

P EAL# CA6 is selected from the drop down menu.

15 Select the appropriate event description from the EAL Matrix.

P RCS Leakage/Inventory is selected.

SRO EP Page 6 of 7 STEP NO STEP ACT STANDARD

16 Select the appropriate release status.

P NO radiological release in-progress is selected. EP-AA-114-F-02, BWR Release in Progress Determination Guidance may be referenced.

17 Enter the wind direction Degrees from.

(Cue: Wind direction is from 80 degrees.)

P Wind direction of 80 degrees is obtained from either PMS Met data or Control Room panel OOC767 and is entered.

Minor discrepancy in parameter value is acceptable.

18 Enter the wind speed.

(Cue: Wind speed is 10 mph.)

P Wind speed of 10 mph is obtained from either PMS Met data or Control Room panel OOC767 and is entered in Block

10. Minor discrepancy in parameter value is acceptable.

19 Check the utility Protective Action Recommendation.

P NONE is selected.

20 Enter the name of the individual who will be communicating the information to the off-site organizations.

(Cue: Durand Adams will be performing the communication.)

P Durand Adams is entered into Block

13.

21 Select the Display/Review Notification Form ICON to create the completed form.

P Selects the Display/Review Notification Form ICON.

22 Reviews the completed state and local form.

P Reviews the information displayed on the state and local form.

23 Select Emergency Director Approval ICON to approve the form and prints out the Notification Form.

P Depresses the Emergency Director Approval ICON and prints out the notification form.

24 Transmits notification form to state and local agencies.

P Selects SEND ICON and YES.

- - NOTE ***

Time Stop = _____

Determine if the elapsed time since the classification exceeds 13 minutes.

19 As the evaluator, ensure that you have positive control of all exam material provided to the examinee (Task condition/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate

SRO EP Page 7 of 7 I.

TERMINATING CUE When plant conditions have been classified and EP-MA-114-100-F-01, State/Local Event Notification Form has been completed, the evaluator will then terminate the exercise.

SRO RM Page 1 of 6 CONSTELLATION ENERGY OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-265C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

002 AUTHOR:

R. J. Artus TYPIST:

jlr TITLE:

2022 ILT NRC SRO ADMIN JPM RM APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ___________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

SRO RM Page 2 of 6 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

27301300202 / PLOR265C K/A:

2.3.6 SRO: 3.8 TASK DESCRIPTION:

Knowledge of the requirements for reviewing and approving release permits.

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

SRO RM Page 3 of 6 B.

TOOLS AND EQUIPMENT

1.

Calculator

2.

AT2 - In-progress ST-C-095-805-2 complete through step 6.14, with a calculation error made in steps 6.11.3, 6.11.4, 6.11.5, 6.11.6 and 6.12.1.2.

C.

REFERENCES

1.

ST-C-095-805-2, Rev. 19, "Liquid Radwaste Discharge" D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the Shift Management review has been completed, the errors in the procedure have been identified, and the release is disapproved pending resolution of the problems.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review a Liquid Radwaste Discharge, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Both units are operating at 100% power.

2.

The Floor Drain Sample Tank (FDST) needs to be discharged.

3.

Chemistry has completed ST-C-095-805-2, "Liquid Radwaste Discharge" through step 6.14.

4.

Gamma Isotopic Analysis Report has been reviewed and is currently being held by Chemistry.

5.

A Pre-Release Liquid Permit has been generated and is being held by Chemistry.

6.

RIS-0-17-350 "Radwaste Effluent" Radiation Monitor is operable.

7.

FS-0-20-493 "RWS Low Purity Waste" High Flow Trip Set Pot and the associated flow control valve are operable.

8.

The discharge Canal-To-Intake Pond crosstie gate is open.

9.

The Shift Management review and approval has not been completed.

SRO RM Page 4 of 6 G.

INITIATING CUE You are the Control Room Supervisor. Complete Section 6.15 of ST-C-095-805-2, "Liquid Radwaste Discharge". Document any discrepancies on Attachment 1.

SRO RM Page 5 of 6 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD NOTE For purposes of this JPM, satisfactory completion of critical steps 3 through 6 are met by DOCUMENTING the associated discrepancies on the JPM cue sheet, as instructed in the initial conditions.

1 Review ST-C-095-805-2 for completeness.

P Verify all CT actions in steps 6.1 through 6.14 have been completed satisfactorily and initial step 6.15.1 SAT.

- - NOTE ***

IF examinee asks about Gamma Isotopic Analysis Report or Pre-Release Liquid Permit, inform them that Chemistry removed this paperwork after it was reviewed, and they should proceed without it. If asked, inform the examinee that the max discharge flow has been verified to be 300 gpm for Data Sheet 4.

2 Verify calculations.

P Perform all calculations that were done in section 6.10 and verify they are correct and recorded on Data Sheet 3 and 4.

3 Recognize the calculation error for the Log CPS reading in step 6.11.3.

P Recognize error in step 6.11.3 for Log CPS. Initial step 6.15.2 as UNSAT.

4 Recognize the error made in step 6.11.3 is carried forward through steps 6.11.4, 6.11.5 and 6.11.6.

P Recognize the error made in step 6.11.3 is carried forward through steps 6.11.4, 6.11.5 and 6.11.6.

5 Recognize calculation error for Low Flow Discharge setting.

P Recognize error in step 6.12.1.2 for Low Flow Discharge setting. Initial step 6.15.2 UNSAT.

6 Disapprove the Liquid Radwaste Discharge.

(Cue: Acknowledge the disapproval.)

P Disapprove the discharge and return the paperwork to the Chemistry Department.

7 As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

SRO RM Page 6 of 6 Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the review of ST-C-095-805-2 has been completed, and the release is disapproved, terminate the exercise.

JPM A Page 1 of 6 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-301CA COURSE:

Licensed Operator Requalification REV #:

014 AUTHOR:

C. A. Buer TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM A APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ______________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM A Page 2 of 6 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2001840501 / PLOR-301CA K/A:

211000A3.06 RO: 4.1 SRO: 4.1 TASK DESCRIPTION:

Inject Boron into RPV (Alternate Path - RWCU Fails to Isolate)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-150-J040 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM A Page 3 of 6 B.

TOOLS AND EQUIPMENT

1.

Key for SBLC System keylock switch on Control Room panel C005A.

C.

REFERENCES

1.

RRC 11.1-2, Rev. 1, Standby Liquid System Initiation During a Plant Event D.

TASK STANDARD

1.

Satisfactory task completion is indicated when a SBLC pump is running, boron is injecting into the Reactor vessel and RWCU system flow is secured.

2.

Estimated time to complete: 4 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to inject boron into the Reactor vessel using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

SBLC injection required by T-117, ATWS RPV Control.

G.

INITIATING CUE The Control Room Supervisor directs you to inject boron into the Reactor vessel using Rapid Response Card RRC 11.1-2, Standby Liquid System Initiation During a Plant Event.

JPM A Page 4 of 6 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain copy of procedure RRC 11.1-2.

P Copy of RRC 11.1-2 is obtained.

2 Verify AO-2-02-039, Recirc Sample Inboard Isol valve, is closed.

(Cue: AO-2-02-039 green light is on, red light is off.)

P AO-2-02-039 green light verified ON at panel 20C004A.

3 Verify AO-2-02-040, Recirc Sample Inboard Isol valve, is closed.

(Cue: AO-2-02-040 green light is on; red light is off.)

P AO-2-02-040 green light verified ON at panel 20C004A.

4 Verify key is inserted into 2(A)BP040 keylock switch.

(Cue: Key is in keylock switch.)

P Key verified inserted into 2(A)BP040 keylock switch at panel 20C005A.

5 Turn keylock switch to START SYS A(B)".

(Cue: Acknowledge keylock switch operation.)

P Keylock switch turned to the "START SYS A(B)" position at panel 20C005A.

- - - NOTE ****

The Alternate Path portion of this JPM begins with the next step.

6 Verify RWCU system isolated.

(Cue: MO-15, MO-18, and MO-68 red lights are on, green lights are off.)

P RWCU failure to isolate is recognized.

7*

Trip all running RWCU pumps.

(Cue: Acknowledge control switch operations.)

P All running RWCU Pump control switches are momentarily placed in the STOP position at panel 20C004A.

8 Verify all RWCU pumps are secured.

(Cue: A and B RWCU Pumps green lights are on, red lights are off.

P A and B RWCU pump green lights verified ON and flow drops to 0/ on FI-2-12-141A and FI-2-12-141B at panel 20C004A.

JPM A Page 5 of 6 STEP NO STEP ACT STANDARD

9 Close RWCU Isolation valves MO-2 15, MO-2-12-18, and MO-2-12-68.

(Cue: Acknowledge control switch operations.)

P MO-2-12-15, AND/OR MO-2-12-18 AND/OR MO-2-12-68 control switch(es) is(are) momentarily placed in the CLOSE position at panel 20C004A. Closing any one of the listed valves isolates the RWCU system and satisfies the Performance Standard.

10 Verify MO-2-12-15, MO-2-12-18 and MO-2-12-68 are closed.

(Cue: MO-15, MO-18, and MO-68 green lights are on, red lights are off.)

P MO-2-12-15, AND/OR MO-2-12-18, AND/OR MO-2-12-68 green light(s) verified ON at panel 20C004A.

11 Acknowledge the "CLEAN-UP FILTER/DEMIN SYSTEM TROUBLE" annunciator.

(Cue: Annunciators 215 C-3 is lit solid.)

P The annunciator "ACKNOWLEDGE" pushbutton is depressed on panel 20C012.

12 Verify SBLC Pump A(B) starts and injects.

(Cue: SBLC Pump A(B) red light is on, green light is off; PI-065 reads approximately 100 psig above Reactor pressure; LI-66 indication is slowly lowering; Reactor power is slowly lowering.)

P

SBLC Pump A(B) red light is verified ON.

SBLC Pump discharge pressure verified approximately 100 psig above reactor pressure on PI-2-11-065.

Lowering Reactor power verified.

All at panel 20C005A.

13 Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknow-ledges report.)

P Task completion reported.

14 As an evaluator ensure that you have positive control of all exam material provide to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate

JPM A Page 6 of 6 I.

TERMINATING CUE When a SBLC pump is running and boron is injecting into the Reactor vessel with RWCU flow secured, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM B Page 1 of 9 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Requalification CODE #:

PLOR-303CA COURSE:

Licensed Operator Requalification REV #:

012 AUTHOR:

R. J. Artus TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM B APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ________________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM B Page 2 of 9 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2590010401 / PLOR-303CA K/A:

259001A4.02 RO: 4.0 SRO: 4.0 TASK DESCRIPTION:

SHUTDOWN THE A RFP TURBINE (ALTERNATE PATH - MIN FLOW VALVE FAILS CLOSED)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

SO 6D.2.A-2 Rev. 40, Reactor Feedwater Pump Shutdown

2.

AO 6D.1-2 Rev. 7, Reactor Feedwater Pump Shutdown with Failed Minimum Flow Valve D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the A RFP is secured, and its suction valve (MO-2140A) closed.

2.

Estimated time to complete: 25 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to shutdown the A RFP to the point of having its suction valve (MO-2140A) closed, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

A normal plant shutdown is in progress IAW GP-3, Normal Plant Shutdown.

2.

Three Reactor Feed Pumps running.

3.

Reactor power is approximately 78%.

4.

Feedwater Master Level Controller is in AUTO.

5.

All RFP M/A Stations are in AUTO.

6.

The Zinc Injection system is shutdown.

7.

Heat balance is in Venturi mode for all three RFP strings IAW AO 59C.2-2, "Transfer Core Thermal Power Calculation LEFM/Venturi Mode and Maximum Allowable Power Level Adjustments".

8.

An Equipment Operator is stationed at the Unit 2 Condensate Demineralizer Panel for Condensate Demineralizer management.

9.

Hydrogen Water Chemistry steps will be performed by another Reactor Operator.

G.

INITIATING CUE The Control Room Supervisor directs you to shutdown the A RFP using SO 6D.2.A-2, Reactor Feedwater Pump Shutdown to the point of having its suction valve (MO-2140A) closed.

H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of procedure SO 6D.2.A-2.

P A copy of procedure SO 6D.2.A-2 is obtained.

2 Equalize the Bias on the "B" and "C" RFPs without exceeding 0.5 x 106 lb/hr between the "B" and "C" RFPs.

(Cue: When BIAS is selected on the B M/A station the value is 0.

When BIAS is selected on the C M/A station the value is 0.)

P Depress the display pushbutton and select "BIAS" on the B and C RFP M/A stations. Adjust Bias using up/down arrows until the Bias is matched on both RFPs while observing feedwater flow at panel 20C005A.

3 Open AO-2139A, Feed Pump A Recirc valve.

(Cue: Acknowledge control switch operation.)

P AO-2139A control switch is placed in the "OPEN" position at panel 20C006A.

4 Verify AO-2139A, Feed Pump A Recirc valve is open.

(Cue: AO-2139A green light is on, red light is off.)

P Recognize by reporting failure of AO-2139A to open at panel 20C006A.

- - NOTE***

IT IS EXPECTED THAT THE CANDIDATE WILL RECOGNIZE THAT AO-2139A DID NOT OPEN, AND OBTAIN A COPY OF AO 6D.1-2 REACTOR FEEDWATER PUMP SHUTDOWN WITH FAILED MINIMUM FLOW VALVE TO COMPLETE THE EVOLUTION. SELECTION OF THE APPROPRIATE PROCEDURE IS THE RESPONSIBILITY OF THE CANDIDATE.

IF NECESSARY, PROVIDE THE FOLLOWING CUE:

CONTINUE TO SHUTDOWN THE A RFP USING APPROPRIATE PLANT PROCEDURES TO THE POINT OF HAVING ITS SUCTION VALVE (MO-2140A)

CLOSED

STEP NO STEP ACT STANDARD

- - - NOTES ****

(1) The Alternate Path portion of this JPM begins with the next step.

(2) The CUE in the following step must be provided to the candidate independent of plant response.

5 Obtain a copy of procedure AO 6D.1-2, Reactor Feedwater Pump Shutdown with Failed Minimum Flow Valve (Cue: The System Manager and the Shift Manager have determined the Min Flow valve to be FAILED CLOSED.)

P A copy of procedure AO 6D.1-2 is obtained.

6 Place "A" RFP M/A Station in MANUAL.

(Cue: Acknowledge pushbutton operation.)

P "A" RFP M/A Station Manual select pushbutton is momentarily depressed at panel 20C005A.

7 Verify the "A" RFP controller is in "MANUAL".

(Cue: The M light is on and the A light is off on the M/A Station.)

P "A" RFP controller Manual pushbutton M light is ON at panel 20C005A.

8 Reduce "A" RFP flow to 2.0 - 2.5 x 106 lbm/hr using the RFP M/A Station.

(Cue: RFP A flow indicates 2.3 x 106 lbm/hr on DFW HMI.)

P "A" RFP M/A Station output is lowered until A RFP flow indicates 2.0 - 2.5 x 106 lbm/hr at panel 20C005A.

9 Verify Reactor water level is stable and remaining RFPs can supply feedwater for existing steam loads.

(Cue: LI-2-06-94A, B, and C indicate 23" and stable.

Feedwater flow indicates less than 14.0 x 106 lbm/hr on DFW HMI.)

P Reactor level is verified to be stable on LI-2-06-94A, B, C, and total feedflow verified to be less than 14.0 x 106 lbm/hr at panel 20C005A.

10 Place the control switch for AO-2147A, Feedpump Check valve, in "CLOSE".

(Cue: Acknowledge control switch operation.)

P AO-2147A control switch is placed in the "CLOSE" position at panel 20C006A.

STEP NO STEP ACT STANDARD 11 Check AO-2147A, Feedpump Check valve response.

(Cue: AO-2147A green light is on, red light is on.)

P AO-2147 red and green lights are verified ON at panel 20C006A.

12 Bump closed MO-2149A, Feedpump "A" Discharge valve.

(Cue: Acknowledge control switch operation.)

P MO-2149A control switch is momentarily placed in the "CLOSE" position at panel 20C006A. Valve Red Indicating Light/Stop Pushbutton is depressed to stop valve travel.

Repeat IAW procedure guidance.

13 Monitor Reactor Feed Pumps and RPV level response (Cue: Discharge flow of A RFP is dropping, discharge flow of B and C RFPs are rising, RPV water level is stable.)

P

Checks discharge flow of A RFP is dropping

Checks discharge flow of B and C RFPs are rising

Monitors RPV water level, allow RPV water level to stabilize

14 When RFP flow lowers to 1 x 106 lbm/hr, then trip "A" RFP.

(Cue: "A" RFPT TRIP" annunciator on panel 201 is up.)

P When "A" RFP flow lowers to 1 x 106 lbm/hr, "A" RFPT Turbine Trip pushbutton (PBA1) is momentarily DEPRESSED at panel 20C005A.

15 Verify the "A" RFP tripped.

(Cue: The "A" RFP green turbine trip lights are lit; SPI-2621A reads

0. Annunciators 201 G-4, 202 G-3, and 210 A-3 are lit.)

P The "A" RFP green turbine trip lights are verified lit and "A" RFPT speed is verified to drop to 0 on SPI-2621A at panel 20C005A.

16 Verify MO-2149A is fully closed.

(Cue: MO-2149A green light is on, red light is off.)

P MO-2149A green light is verified ON at panel 20C006A.

STEP NO STEP ACT STANDARD 17 Verify AO-8633A, A H2 FDW INJ closes when flow is less than the low flow alarm setpoint of 1.1 Mlbm/hr or if AO-8633A does not close, then place the control switch for AO-8633A to off and apply an Equipment Status Tag.

(Cue: Report that Step 4.12 of AO 6D.1-2 was completed by another operator. AO-8633A is closed, green light is on, red light is off.

If candidate starts to go to the Hydrogen Water Chemistry panel, remind them that another Reactor Operator is performing the Hydrogen Water Chemistry steps.)

P Directs another Reactor Operator to complete step 4.12 of AO 6D.1-2.

18 Verify "A" RFP Turning Gear control switch in AUTO.

(Cue: Turning gear control switch is in AUTO.)

P "A" RFP Turning Gear control switch is verified in the AUTO (normal) position at panel 20C005A.

19 Close MO-2140A, "Feed Pump `A' Suct" valve.

(Cue: Acknowledge control switch operation.)

P MO-2140A control switch is momentarily placed in the close position at panel 20C006A.

20 Verify MO-2140A, "Feed Pump `A' Suct" valve is closed.

(Cue: MO-2140A green light is on, red light is off.)

P MO-2140A green light is verified ON at panel 20C006A.

21 Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

P Task completion reported.

22 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the A Reactor Feed Pump is secured, and its suction valve (MO-2140A) closed the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLORXXXCA Rev000 Page 1 of 8 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-COURSE:

Licensed Operator Requalification REV #:

000 AUTHOR:

S. Andersen TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM C APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

Employee ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM C Page 2 of 8 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2060050101 / PLOR-XXXCA K/A:

295025EA1.04 RO: 3.6 SRO: 3.6 TASK DESCRIPTION:

Startup HPCI in the CST to CST Mode (Alternate Path - High Oil Temperature)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-150-J040 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM C Page 3 of 8 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

RRC 23.1-2, Rev. 8, HPCI System Operation during a Plant Event D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the HPCI Turbine has been started and then manually tripped due to high oil temperature.

2.

Estimated time to complete: 16 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to steps to startup HPCI in the CST to CST mode using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

GP-4 was performed due to a steam leak in the Reactor Building steam tunnel.

2.

MSIVs have been closed and the leak is isolated.

3.

RCIC is being used to maintain RPV level.

4.

Torus Cooling has been maximized.

5.

SBGT is in service.

6.

The HPCI System is aligned for operation in accordance with SO 23.1.A-2, "HPCI System Setup for Automatic or Manual Operation".

7.

Drywell Instrument Nitrogen has been bypassed and restored.

8.

RPV pressure is approximately 1100 psig with SRVs cycling automatically.

G.

INITIATING CUE The Control Room Supervisor directs you to start HPCI in the CST to CST Mode in accordance with RRC 23.1-2, HPCI System Operation During a Plant Event, to control RPV pressure 700 to 1000 psig.

JPM C Page 4 of 8 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of RRC 23.1-2, HPCI System Operation During a Plant Event.

P A copy of procedure RRC 23.1-2 is obtained and section D is referenced.

2 Open MO-2-23-024, "Cond. Tank Return".

(Cue: Acknowledge control switch operation.)

P MO-2-23-024 control switch is momentarily placed in the OPEN position at panel 20C004B.

3 Verify MO-2-23-024, "Cond. Tank Return" valve opened.

(Cue: MO-24 red light is ON, green light is OFF.)

P MO-2-23-024 red light is verified ON at panel 20C004B.

4 Verify closed MO-2-23-019, To Feed Line.

(Cue: MO-19 green light is ON and red light is OFF.)

P MO-19 green light is verified ON at panel 20C004B.

5 Start 20K002, Vac Pump.

(Cue: Acknowledge control switch operation.)

P Gland Seal Condenser Vacuum Pump control switch is placed in the "START" position at panel 20C004B.

6 Verify the Gland Seal Condenser Vacuum Pump 20K002 is running.

(Cue: 20K002 red light is ON and green light is OFF.)

P 20K002 red light is verified ON at panel 20C004B.

7 Throttle open MO-2-23-021, "Full Flow Test" until the red "OPEN" indicating light has been lit for 3 to 4 seconds.

(Cue: MO-21 green light is ON; red light has been ON for 3 to 4 seconds.)

P M0-2-23-021 control switch is momentarily placed in the OPEN position.

Approximately 3 to 4 seconds after the red light lit, the red stop travel pushbutton is depressed at the 20C004B panel.

JPM C Page 5 of 8 STEP NO STEP ACT STANDARD

8 Simultaneously start the Auxiliary Oil Pump, 20P026, and open MO-2-23-014 "Supply" valve.

(Cue: Acknowledge control switch operation.)

P Auxiliary oil pump control switch is placed in the START position, while simultaneously placing MO-2-23-014 "Supply" control switch momentarily in the "OPEN" position at panel 20C004B.

9 Verify the Auxiliary Oil pump started.

(Cue: Auxiliary Oil pump red light is ON, green light is OFF and annunciator 222 D-5 is alarming.)

P Auxiliary Oil Pump red light is verified ON at panel 20C004B.

10 Verify MO-2-23-014, "Supply" valve opened.

(Cue: MO-14 red light is ON, green light is OFF, HPCI discharge pressure, flow, speed, and exhaust pressure rise. Aux oil pump red light is OFF, and green light is ON.)

P MO-2-23-14 red light verified ON and HPCI speed, discharge pressure, and flow are verified at panel 20C004B.

11 Acknowledge the "HPCI Auxiliary Oil Pump Running" annunciator.

(Cue: Annunciator 222 D-5 is lit solid.)

P The annunciator "ACKNOWLEDGE" pushbutton is depressed at panel 2OC003-04.

12 Verify the proper start of HPCI.

(Cue: PI-2-23-109, FI-2-23-108, SPI-4505, PI-2-23-112 rising, and Aux Oil Pump red light is OFF, green light is ON.)

P Verify pump discharge pressure, discharge flow, speed and exhaust pressure rise and then stabilize. Verify Aux Oil Pump red light is OFF, green light is ON at panel 2OC004B.

13 Verify "HPCI AUXILIARY OIL PUMP RUNNING" annunciator clears.

(Cue: Annunciator 222 D-5 is not lit.)

P "HPCI AUXILIARY OIL PUMP RUNNING" annunciator is verified clear on alarm panel 222.

14 Verify pump flowrate of 5000 gpm on FI-2-23-108.

(Cue: FI-2-23-108 indicates 5000 gpm.)

P FIC-2-23-108 setpoint is adjusted to obtain 5000 gpm on FI-2-23-108 at panel 20C004B.

JPM C Page 6 of 8 STEP NO STEP ACT STANDARD 15 Throttle MO-2-23-021 and flow controller FIC-2-23-103 as necessary to obtain desired pressure and flow.

(Cue: Acknowledge control switch operation. PI-2-23-109 reads 1250 psig, FI-2-23-108 reads 5000 gpm.)

P MO-2-23-021 control switch and FIC-2 103 are operated as necessary to adjust HPCI speed to achieve the desired RPV pressure, while maintaining turbine speed greater than 2200 rpm at SPI-4505 at panel 20C004B.

- - - NOTE: ****

The Alternate Path portion of this JPM begins with the next step.

16 Recognize HPCI high oil temperature condition.

(Cue: Annunciator 221 B-3 is alarming.

TRS-2-10-131 Pt. 5 reads 180°F.)

P Recognize annunciator 221 B-3 is flashing and consult ARC-221 B-3, or read TRS-2-10-131 Pt. 5 and recognize oil cooler outlet temperature is greater than 160°F.

17 Verify HPCI initiation pushbutton (23A-S105) collar is in "DISARM".

(Cue: HPCI initiation collar is in "DISARM" and annunciator 221 B-2 is not lit.)

P HPCI Manual Initiation (23A-S105) collar is verified in the "DISARM"

[counterclockwise] position on 20C004B or "HPCI IN TEST/ARMED" annunciator 221 B-2 is clear.

18 Verify the Aux oil pump (20P026) control switch is in "START".

(Cue: Aux oil pump control switch (20P026) is in "START".)

P Aux oil pump (20P026) control switch is verified in "START" at panel 20C004B.

19 Verify Gland Seal Condenser Vacuum Pump (20K002) is in "START".

(Cue: Vacuum pump switch is in "Start",

red light is ON and green light is OFF.)

P Gland Seal Condenser Vacuum Pump (20K002) control switch is verified in "START" at panel 20C004B.

20 Depress and hold the HPCI System "Remote Trip" pushbutton.

(Cue: Turbine speed drops and 221 B-1 is alarming "HPCI TURB TRIP".)

P Remote trip pushbutton is DEPRESSED AND HELD in until MO-2-23-014 indicates fully closed at panel 20C004B.

21 Verify HO-4513, "HPCI Turbine Stop" is closed.

(Cue: MO-2-23-019 green light ON, red light OFF.)

P HO-4513 green light verified ON and red light verified OFF on panel 20C004B.

JPM C Page 7 of 8 STEP NO STEP ACT STANDARD 22 Verify Alarm Panel 221 Window B-1, "HPCI TURB TRIP" alarms.

(Cue: Annunciator 221 B-1 is in alarm.)

P Alarm panel 221 B-1 is verified in alarm and is acknowledged by depressing the "ACKNOWLEDGE" pushbutton.

23 Verify HPCI Aux oil pump starts as turbine slows down (1200-1500 RPM).

(Cue: HPCI Aux oil pump red light is ON and green light is OFF. Annunciator 222 D-5 is flashing.)

P HPCI Aux oil pump (20P026) red light is verified ON at panel 20C004B and/or "HPCI AUX OIL PUMP RUNNING" annunciator 222 D-5 is verified lit.

- - - NOTE****

Performance of either of the actions in the following step (closing MO-2-23-014 or placing the Aux Oil Pump in PTL) is acceptable.

24 Close MO-2-23-014, "Supply" valve.

(Cue: Acknowledge control switch operation.)

OR Place the Aux Oil Pump (20P026) control switch is in "PULL-TO-LOCK".

(Cue: Aux Oil Pump control switch (20P026) is in "PULL-TO-LOCK".)

P MO-2-23-014 control switch is momentarily placed in the CLOSE position at panel 20C004B.

OR Aux Oil Pump (20P026) control switch is placed in PULL-TO-LOCK when HPCI turbine speed drops to approximately 0 (zero) RPM.

25 Verify MO-2-23-014, "Supply" valve closed.

(Cue: MO-14 green light is ON, red light is OFF. HPCI speed, discharge pressure, and exhaust pressure have dropped to 0.)

P MO-2-23-014 green light verified ON at panel 20C004B.

26 Verify closed the MO-2-23-019, To Feed Line valve.

(Cue: MO-2-23-019 green light ON, red light OFF.)

P MO-2-23-019 green light verified ON and red light verified OFF on panel 20C004B.

27 When MO-2-23-14 is fully closed, release the HPCI system "Remote Trip" pushbutton.

(Cue: Acknowledge pushbutton is released.)

P Remote trip pushbutton is RELEASED at panel 20C004B.

JPM C Page 8 of 8 STEP NO STEP ACT STANDARD 28 Close MO-2-23-021, Full Flow Test.

(Cue: Acknowledge switch operation.)

P MO-2-23-021 control switch is momentarily placed in the CLOSE position at panel 20C004B.

29 Verify MO-2-23-021 closed.

(Cue: MO-2-23-021 green light is ON, red light is OFF.)

P MO-2-23-021 green light verified ON at panel 20C004B.

30 Depress 23A-S21, Initiation Signal Reset push-button (Cue: Acknowledge pushbutton is depressed.)

P Push-button 23A-S21 is depressed at panel 20C004B.

31 Direct Equipment Operator to verify HPCI Turbine Shaft is Stopped.

(Cue: Acknowledge direction, inform examinee that JPM is concluded)

P Equipment Operator dispatched 32 Inform Control Room Supervisor of high oil temperature and HPCI Turbine trip.

(Cue: Control Room Supervisor acknowledges report.)

P High oil temperature condition and HPCI Turbine trip reported.

NOTE: This step may be performed at any point post-Alarm condition. IF Evaluator Terminates JPM before CRS is informed, then this step is N/A.

33 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the HPCI Turbine has been tripped due to high oil temperature, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM D Page 1 of 7 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-269CA COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

002 AUTHOR:

R. J. Artus TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM D APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM D Page 2 of 7 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2003310501 / PLOR-269CA K/A:

203000A4.02 RO: 4.2 SRO: 4.2 TASK DESCRIPTION:

Place the 2B RHR Loop HX Cross-Tie in Service (Alternate Path)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM D Page 3 of 7 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

T-206-2, Placing the RHR Heat Exchanger Cross Tie(s) In Service (Rev. 0)

2.

SE-11 Sheet 1 and SE-11 Sheet 2, Loss of Offsite Power

3.

SE-11 Attachment O, Operation of RHR and HPSW Backup Power Supplies (Rev. 1)

D.

TASK STANDARD

1. Satisfactory task completion is indicated when the 2B RHR Loop Heat Exchanger cross tie is in service using the 2D RHR Pump and the 2C & 2D HPSW pumps per T-206-2.

2. Estimated time to complete: 12 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to place the 2B RHR Loop Heat Exchanger Cross Tie in service using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1. A previously stuck open SRV on Unit 2 resulted in high torus water temperature.

2. A manual scram was performed on Unit 2 due to the high torus water temperature.

3. T-101 and T-102 are in progress.

4. Shortly after the scram, a complete Loss of Offsite Power (LOOP) occurred.

5. SE-11 Sheets 1 and 2 are in progress. Shift Management has given permission to perform SE-11 Attachment O as necessary.

6. The E-1 EDG failed to start, investigation is in progress. All remaining EDGs auto-started and energized their respective buses.

7. The 2B RHR Loop is in torus cooling using the 2D RHR Pump and 2D HPSW Pump.

8. The 3B RHR pump and 3B HPSW pump are in service on Unit 3.

JPM D Page 4 of 7 G.

INITIATING CUE The Control Room Supervisor directs you to align the 2B RHR Loop into a two heat exchanger lineup using T-206-2, Placing the RHR Heat Exchanger Cross Tie(s) In Service, utilizing the 2C HPSW pump.

JPM D Page 5 of 7 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of T-206-2, Placing the RHR Heat Exchanger Cross Tie(s) in Service P

A controlled copy of procedure T-206-2 has been obtained

- - - NOTE ****

The examinee may realize at this point (or later in the JPM) that there is no power available to the HPSW Loop Cross Tie MO-2-32-2344(10-186). The examinee may perform SE-11 Attachment O at any time during this JPM to provide backup power to the HPSW Loop Cross Tie. Providing backup power to the HPSW Loop Cross Tie using SE-11 Attachment O is the ALTERNATE PATH portion of this JPM.

Actual valve and pump operation MUST be performed in the required order per T-206-2.

2 Verify HPSW flow is at least 4500 gpm on FI-2-10-132B.

(Cue: HPSW flow is reading 4500 gpm on FI-2-10-132B)

P Examinee verifies HPSW flow at least 4500 gpm on FI-2-10-132B.

- - - NOTE ****

The next step in T-206-2 is to open MO-2-32-2344(10-186), "HPSW Loop Cross Tie". If SE-11 Attachment O, Operation of RHR and HPSW Backup Power Supplies has NOT been performed, then MO-2-32-2344 will not have power available. The examinee must recall that use of SE-11 Attachment O has been authorized, and implement it prior to continuing in T-206-2.

- - - NOTE ****

The Alternate Path portion of this JPM begins with the next step.

3 Obtain a copy of SE-11 Attachment O.

P A controlled copy of procedure SE-11 Attachment O has been obtained.

4 Verify alternate power is available to E1/324-R-C, "(20B79) RHR Backup Power Supply Motor Control Center" from E324-R-B at Panel 00C026A.

(Cue: YELLOW light is lit above RMS 56E-E1/324-R-C, "E1/324-R-C Pwr Transfer" at Panel 00C026A)

P Examinee verifies YELLOW light is lit above RMS-2-56E-E1/324-R-C, "E1/324-R-C Pwr Transfer" at Panel 00C026A.

5 Place RMS-2-56E-E1/324-R-C, "E1/324-R-C Pwr Transfer" in ALTERNATE.

(Cue: Switch is in the position indicated)

P Examinee places RMS-2-56E-E1/324-R-C, "E1/324-R-C Pwr Transfer" in ALTERNATE.

JPM D Page 6 of 7 STEP NO STEP ACT STANDARD 6

Verify YELLOW light is lit above RMS 10A-S229, "HPSW Loop Cross Tie 20S1048 Pwr Transfer" at Panel 20C003.

(Cue: YELLOW light is lit above RMS 10A-S229, "HPSW Loop Cross Tie 20S1048 Pwr Transfer" at Panel 20C003)

P Examinee verifies YELLOW light is lit above RMS-2-10A-S229, "HPSW Loop Cross Tie 20S1048 Pwr Transfer" at Panel 20C003.

7 Place RMS-2-10A-S229, "HPSW Loop Cross Tie 20S1048 Pwr Transfer" in ALTERNATE.

(Cue: Switch is in the position indicated)

P Examinee places RMS-2-10A-S229, "HPSW Loop Cross Tie 20S1048 Pwr Transfer" in ALTERNATE.

8 Verify power is available to MO-2-32-2344 (10-186).

(Cue: Green CLOSED light is ON)

P Examinee verifies green closed light

'ON' for MO-2-32-2344(10-186).

9 Open MO-2-32-2344(10-186), "HPSW Loop Cross Tie".

(Cue: Switch is in the position indicated)

P Examinee momentarily places MO-2 2344(10-186) control switch in the OPEN position at panel 20C003-02.

10 Verify open MO-2-32-2344(10-186),

"HPSW Loop Cross Tie".

(Cue: MO-2-32-2344(10-186) red light ON and green light OFF)

P Examinee verifies MO-2-10-2344(10-186) red light ON and green light OFF 11 Ensure the load on the E-3 Diesel Generator is below 2300 KW.

(Cue: E-3 Diesel Generator Loading is 1000 KW)

P Examinee verifies E-3 Diesel Generator load is below 2300 KW.

12 Start the 2C HPSW Pump.

(Cue: Switch is in the position indicated)

P Examinee momentarily places the 2C HPSW pump control switch in the

'START' position at Panel 20C003-02.

13 Verify proper start of the 2C HPSW Pump.

(Cue: ammeter indicates 100 amps, PI-2330C indicates 375 psig)

P Examinee verifies normal pump start parameters.

14 Fully open MO-2-10-089B, "B HPSW Hx Out".

(Cue: Switch is in the position indicated)

P Examinee places MO-2-10-089B control switch in the 'OPEN' position at panel 20C003-02.

JPM D Page 7 of 7 STEP NO STEP ACT STANDARD 15 Verify open MO-2-10-089B, "B HPSW Hx Out".

(Cue: MO-2-10-089B red light verified ON and green light verified OFF at panel 20C003-02)

P Examinee verifies MO-2-10-89B red light ON and green light OFF at Panel 20C003-02.

16 Open MO-2-10-23452B, "B Cross Tie Vlv".

(Cue: Switch is in the position indicated)

P Examinee momentarily places MO-2 23452B control switch in the OPEN position at panel 20C003-02.

17 Verify open MO-2-10-23452B, B Cross Tie Vlv.

(Cue: MO-2-10-23452B red light ON and green light OFF at panel 20C003-02)

P Examinee verifies MO-2-10-23452B red light 'ON' and green light 'OFF' at Panel 20C003-02.

18 Throttle CV-2-10-2677B AND D, B(D)

Control Vlv", to establish at least 4300 gpm though each RHR Heat Exchanger on FI-2-10-81076B AND D.

P Examinee throttles both CV-2-10-2677B and CV-2-10-2677D until at least 4,300 gpm RHR flow is established in each of the B Loop RHR Heat Exchangers (B and D) as read on FI-2-10-81076B and FI-2-10-81076D WITH a maximum of 6,500 gpm RHR flow through the B RHR Heat Exchanger AND a total "B" Loop RHR flow rate that is less than or equal to 12,200 gpm as read on FI-2-10-139B.

19 Inform Control Room Supervisor of task completion.

P Task completion reported.

Cue: Acknowledge receipt of report 20 As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the 2B RHR Heat Exchanger Cross Tie is in service in accordance with T-206-2 using the 2C HPSW pump, along with the applicable steps of SE-11 Attachment O for supplying backup power to the HPSW Loop Cross Tie, the supervisor should be informed. The evaluator will then terminate the exercise.

JPM E Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-034C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

016 AUTHOR:

R. J. Artus TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM E APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ______________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM E Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2240130101 / PLOR-034C K/A:

223001A4.10 URO: 3.5 SRO: 3.5 TASK DESCRIPTION:

CAD System Nitrogen Addition to Containment During Normal Operations A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM E Page 3 of 5 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

SO 7C.1.B-2, Rev. 23, CAD System Nitrogen Addition to Containment During Normal Operations (R)

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when Nitrogen has been added to containment with an N2 flow of 55-65 scfm.

2.

Estimated time to complete: 14 minutes (A.5) Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perform a normal nitrogen addition to the Drywell from the CAD system using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

All SO 7C.1.B-2, CAD System Nitrogen Addition to Containment During Normal Operations procedural prerequisites are met.

2.

Primary Containment venting is NOT required.

3.

CAD Tank level is 45 inches.

4.

A Analyzer is in service and B is in standby in the CAC MODE.

G.

INITIATING CUE The Control Room Supervisor directs you, a Reactor Operator, to add nitrogen to the Drywell using A loop of the CAD system at 60 scfm in accordance with SO 7C.1.B-2, CAD System Nitrogen Addition to Containment During Normal Operations.

JPM E Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of procedure SO 7C.1.B-2.

P A copy of procedure SO 7C.1.B-2 is obtained. The Examinee should identify step 4.5.1 as the step needing to be performed.

2 Open SV-4948A Drywell Nitrogen Supply valve.

(Cue: Acknowledge control switch operation.)

P SV-4948A control switch is placed in the OPEN position at panel 20C484A.

3 Verify SV-4948A Drywell Nitrogen Supply valve is open.

(Cue: SV-4948A red light is on and green light is off.)

P SV-4948A red light is verified ON at panel 20C484A.

4 Open SV-4949A Drywell Nitrogen Supply Valve.

(Cue: Acknowledge control switch operation.)

P SV-4949A control switch is placed in the OPEN position at panel 20C484A.

5 Verify SV-4949A Drywell Nitrogen Supply Valve is open.

(Cue: SV-4949A red light is on and green light is off.)

P SV-4949A red light is verified ON at panel 20C484A.

6 Open CV-4947A using HCS-4947A to obtain a flow rate of 60 scfm on FI-4947A.

(Cue: [CLOCKWISE HCS-4947A manual adjustment knob is rotated.] HCS-4947A indicates 55% controller output; FI-4947A indicates 60 scfm; FR-4947A indicates 62 scfm.

P HCS-4947A manual adjustment knob is rotated clockwise until 55 to 65 scfm is obtained on FI-4947A at panel 20C484A.

7 Inform the Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknow-ledges report.)

P Task completion reported.

8 As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

JPM E Page 5 of 5 Under ACT P - must perform S - must simulate I.

TERMINATING CUE When nitrogen is being added to the Drywell at a flow rate of 60 scfm, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM F Page 1 of 6 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-113C COURSE:

LICENSED OPERATOR REQUALIFICATION REV #:

004 AUTHOR:

G. W. Zellmer TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM F APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ______________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

Employee ID. NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM F Page 2 of 6 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2004140401 / PLOR-113P K/A:

295003AA1.02 URO: 4.5 SRO: 4.5 TASK DESCRIPTION:

Diesel Generator Lockout from the Main Control Room A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM F Page 3 of 6 B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

Procedure SE-11 Attachment A, Rev. 2, Diesel Generator Lockout from the Main Control (R)

2.

Procedure SE-11, Rev. 17, Loss of Off-Site Power (A)

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when E1 and E4 diesel generator jumpers have been installed in the associated panels.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to shutdown and lockout the E1 and E4 diesel generators from the main control room using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

A loss of off-site power has occurred.

2.

E1 and E4 diesel generators started but do not have cooling water.

3.

E2 and E3 diesel generators have failed to start and are not available.

4.

Drywell pressure is 3 psig on Unit 2 and 3.

G.

INITIATING CUE The Control Room Supervisor directs you to install jumpers to lockout the E1 and E4 diesel generators from the main control room in accordance with SE-11 Attachment A Steps 1 through 7.

JPM F Page 4 of 6 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain the key for the Shift Managers key cabinet.

(Cue: When examinee requests key, evaluator should provide the key.)

S Shift Managers key cabinet key requested and obtained from SSV.

2 Open the Shift Managers key cabinet and obtain the SE-11 Attachment A jumper package.

(Cue: Jumper package obtained.)

S Shift Managers key cabinet is unlocked, opened and the SE-11 Attachment "A" package is located.

(Note: Instructor should obtain the jumpers from the SM Office and provide them to the examinee) 3 Open panel 00C029A back panel door.

(Cue: Panel 00C029A back panel door is open.)

P Door handle turned; door pulled outward to gain access to terminal block T35 at back of panel 00C029A in main control room.

4 Install a jumper from terminal 1 to terminal 2 at terminal block T35 inside Panel 00C029A in the Main Control Room.

(Cue: Jumpers installed.)

P Jumper ends are attached from terminal 1 to 2 on terminal block T35.

5 Close panel 00C029A back panel door.

(Cue: Panel 00C029A door is closed and latched.)

P Door closed and relatched using handle.

6 Open panel 00C029D back panel door.

(Cue: Panel 00C029D back panel door is open.)

P Door handle turned; door pulled outward to gain access to terminal block T35 at back of panel 00C029D in main control room.

7 Install a jumper from terminal 1 to terminal 2 at terminal block T35 inside Panel 00C029D in the Main Control Room.

(Cue: Jumpers installed.)

P Jumper ends are attached from terminal 1 to 2 on terminal block T35.

JPM F Page 5 of 6 STEP NO STEP ACT STANDARD 8

Close panel 00C029D back panel door.

(Cue: Panel 00C029D door is closed and latched.)

P Door closed and relatched using handle.

9 Take E1 diesel generator control switch out of PULL TO LOCK and allow to spring return to NORMAL.

(Cue: E1 diesel generator control switch is taken out of PULL TO LOCK and allowed to spring return to NORMAL.)

P E1 diesel generator control switch taken out of PULL TO LOCK and allowed to spring return to normal.

10 Take E4 diesel generator control switch out of PULL TO LOCK and allow to spring return to NORMAL.

(Cue: E4 diesel generator control switch is taken out of PULL TO LOCK and allowed to spring return to NORMAL.)

P E4 diesel generator control switch taken out of PULL TO LOCK and allowed to spring return to normal.

11 Verify that all diesels are shutdown.

(Cue: E1, E2, E3, and E4 diesel generator green lights are on, red lights are off.)

P E1, E2, E3, and E4 diesel generator green lights are verified on.

12 Inform Shift Supervisor of task completion.

(Cue: Shift Supervisor acknowledges report.)

P Task completion reported.

13 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

JPM F Page 6 of 6 Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the E1 and E4 Diesel Generators are shutdown, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM G Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-406C COURSE:

INITIAL LICENSED OPERATOR TRAINING REV #:

000 AUTHOR:

S. Andersen TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM G APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ________________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

PIMS CODE:

Signature/Date PIMS ENTRY:

X

JPM G Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2010930101/ PLOR-406C K/A:

201006 A4.07 RO: 3.2 SRO: 3.2 TASK DESCRIPTION:

Inputting an INOP Control Rod in the RWM A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM G Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

Mark-up of AO 59A.2-2 will be provided to examinee.

C.

REFERENCES

1.

AO 59A.2-2, Rev 13, Adding and Removing Substitute Control Rod Positions and Declaring Control Rods RWM Inoperable and Operable D.

TASK STANDARD

1.

Satisfactory completion of this task is inputting the correct control rod as inoperable in the RWM in accordance with procedure.

2.

Estimated time to complete: 10 minutes. (Not time-critical)

E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to enter an inoperable control rod into the RWM using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is at 100% power.

2.

Control Rod 06-43 has been declared inoperable due to a significant accumulator leak and has been inserted to position 00.

3.

All required Tech Spec entries have been made.

4.

No other control rods are inoperable.

G.

INITIATING CUE You are directed by the Control Room Supervisor to enter control rod 06-43 into the RWM as an inoperable control rod in accordance with AO 59A.2-2, Adding and Removing Substitute Control Rod Positions and Declaring Control Rods RWM Inoperable and Operable, steps 4.3.7 through 4.3.14.

JPM G Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of AO 59A.2-2.

(Cue: a copy of AO 59A.2-2 is obtained.)

P Obtains a copy of AO 59A.2-2.

2 Navigate to RWM Sub/Inop Control Rod from the RWM Functions Plant Computer Interface (subcr).

(Cue: RWM Sub/Inop Control Rod screen is displayed).

P Navigates to the RWM Sub/Inop Control Rod screen from the RWM Functions Plant Computer Interface.

3 Select the quadrant containing the control rod that will be declared RWM Inop.

(Cue: Upper left quadrant is selected)

P Quadrant containing control rod 06-43 is selected.

4 Record the # Inop Rods on Attachment

3.

(Cue: 0 is recorded on Attachment 3 at step marked 4.3.9.)

P Records 0 as the Number of Inop Rods on Attachment 3 of AO 59A.2-2.

5 Select the grey box under the control rod ID that will be declared RWM Inop.

(Cue: Grey box under control rod 06-43 is selected.)

P Selects grey box under control rod 06-43.

6 Select the INOP touch area AND verify a magenta X appears in the selected rod position AND signoff Attachment 3.

(Cue: Magenta X appears in position of control rod 06-43.)

P Selects the INOP touch area and verifies a magenta X is displayed for control rod 06-43.

Initials and dates Attachment 3 of AO 59A.2-2.

7 Verify the # Inop Rods increases by one.

(Cue: 1 is displayed for the # Inop Rods)

P Verifies the number of inoperable rods displayed by the RWM is 1.

JPM G Page 5 of 5 STEP NO STEP ACT STANDARD 8

Notify RO the next step may cause Alarm Panel 211 Window F-5, RWM ROD BLOCK to ALARM.

(Cue: Communication acknowledged.)

P Notifies the RO that the next step may cause Alarm 211 F-5.

9 Select SCAN/LATCH (Cue: SCAN/LATCH is selected.)

P Selects SCAN/LATCH 10 Notify CRS of task completion.

(Cue: Acknowledge the report.)

P Notifies CRS of task completion.

11 As an evaluator, ensure that you have positive control of all exam material provided to examinees.

P Positive Control Maintained.

Under ACT P - must perform S - must simulate TERMINATING CUE:

When the candidate informs the CRS that the INOP control rod has been entered into the RWM, the evaluator will terminate the exercise.

JPM H Page 1 of 6 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: LICENSED OPERATOR TRAINING CODE #:

PLOR-407CA COURSE:

INITIAL LICENSED OPERATOR TRAINING REV #:

000 AUTHOR:

S. Andersen TYPIST:

sra TITLE:

2022 ILT NRC EXAM SIMULATOR JPM H APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _____________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM H Page 2 of 6 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2006900501/ PLOR-407CA K/A:

271000 A4.09 RO: 3.0 SRO: 3.0 TASK DESCRIPTION:

Restore SJAE Steam Supply Pressure to Normal A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM H Page 3 of 6 B.

TOOLS AND EQUIPMENT

1.

None C.

REFERENCES

1.

OT-106-2, Rev 7, Condenser Low Vacuum - Procedure D.

TASK STANDARD

1.

Satisfactory completion of this task is placing the standby SJAE in service in accordance with procedure.

2.

Estimated time to complete: 15 minutes. (Not time-critical)

E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to restore SJAE steam supply pressure to normal using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is at 100% power.

2.

OT-106-2 has been entered due to degrading condenser vacuum.

3.

The Reactor Operator will lower power as necessary to mitigate degrading condenser vacuum.

4.

AO-2540A, Air Eject Inter Cdsr Drain to Condenser Hotwell is blocked open via its handjack.

5.

It has been determined that SJAE steam supply pressure is low (30 psig).

G.

INITIATING CUE You are directed by the Control Room Supervisor to restore SJAE steam supply pressure to normal in accordance with OT-106-2, Condenser Low Vacuum, starting at step 3.10.

JPM H Page 4 of 6 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of OT-106-2.

(Cue: a copy of OT-106-2 is obtained.)

P Obtains a copy of OT-106-2.

2 Place PIC-2239A, A STEAM PRESS in MANUAL.

(Cue: red light is lit next to the A/M pushbutton).

P Places PIC-2239A in MANUAL by depressing A/M pushbutton.

3 Restore SJAE steam supply pressure within the range of 115 to 125 psig.

(Cue: Pressure remains at 30 psig despite attempt to adjust.)

Attempts to raise SJAE steam supply pressure using control knob on PIC-2239A.

4 Rapidly lower PIC-2239A setpoint to minimum.

(Cue: PIC-2239A setpoint is adjusted to minimum. Pressure remains at 30 psig.)

P Lowers PIC-2239A setpoint S to minimum.

5 Rapidly close the following valves for the in-service SJAE:

AO-2236A/B/C, Air Ejector Off Gas Inlet A

AO-2238A/B/C/AO-2540A, Air Ejector Inlet A 1st Stage

AO-2244/45/47A, Air Ejector Inlet A 2nd Stage (Cue: For AO-2236A/B/C and AO-2244/45/47A, green lights are ON, red lights are OFF.

For AO-2238A/B/C/AO-2540A both the red and green lights are ON.)

P Closes the following valves for the A SJAE:

AO-2236A/B/C, Air Ejector Off Gas Inlet A

AO-2238A/B/C/AO-2540A, Air Ejector Inlet A 1st Stage

AO-2244/45/47A, Air Ejector Inlet A 2nd Stage

JPM H Page 5 of 6 STEP NO STEP ACT STANDARD

6 Open the following second stage valves using the common control switch for the standby SJAE:

AO-2244/45/47B, Air Ejector Inlet B 2nd Stage (Cue: AO-2244/45/47B red light is ON, green light is OFF.)

P Opens the following valves for the B SJAE:

AO-2244/45/47B, Air Ejector Inlet B 2nd Stage

7 Raise the setpoint on PIC-2239B to establish SJAE steam supply pressure to within the range of 115 to 125 psig.

(Cue: PIC-2239B setpoint is approximately 120 psig)

P Uses PIC-2239B control knob to adjust setpoint S to 115 to 125 psig.

8 Perform the following to place PIC-2239B in AUTO:

1. Verify the process P and setpoint S vertical bars match

2. Place PIC-2239B, B Steam Press in AUTO (Cue: The process P and setpoint S vertical bars match.

Green light is lit next to the A/M pushbutton.)

P Verifies process P and setpoint S vertical bars are matched.

Places PIC-2239B in AUTO by depressing A/M pushbutton.

9 When SJAE 2nd Stage pressure is greater than 13 Hgv on PI-2246B at Panel 20C006B for the SJAE being placed in service, then open the following valves using the common control switch:

AO-2238D/E/F/AO-2540B, Air Ejector Inlet B 1st Stage (Cue: AO-2238D/E/F/AO-2540B red light is ON, green light is OFF.)

P Opens the following valves for the B SJAE:

AO-2238D/E/F/AO-2540B, Air Ejector Inlet B 1st Stage

JPM H Page 6 of 6 STEP NO STEP ACT STANDARD

10 Place the control switch for the following valves in AUTO for the SJAE being placed in service:

AO-2236D/E/F, Air Ejector Off-Gas Inlet B (Cue: Control switch is in AUTO. Valves cycle open, red light ON, green light OFF.)

P Places AO-2236D/E/F control switch in AUTO.

Observes valve operation and Offgas parameters.

NOTE:

The following step may need to be repeated several times until the SJAE remains in service.

The evaluator may terminate the exercise after two attempts if desired.

11 If required, then Place the control switch for the following valves to CLOSE and then AUTO for the SJAE being placed in service:

AO-2236D/E/F, Air Ejector Off-Gas Inlet B (Cue: Control switch is placed in CLOSE and then returned to AUTO. Valves cycle open, red light ON, green light OFF.)

P Places AO-2236D/E/F control switch in CLOSE and then AUTO.

Observes valve operation and Offgas parameters.

12 Inform CRS that the standby SJAE has been placed in service and that steam supply pressure is normal.

(Cue: Communication acknowledged.)

P Notifies CRS of task completion.

13 As an evaluator, ensure that you have positive control of all exam material provided to examinees (Task Conditions/

Prerequisites AND procedures.

P Positive Control Maintained.

Under ACT P - must perform S - must simulate TERMINATING CUE:

When the candidate informs the Control Room Supervisor that the standby SJAE is in service, then the evaluation may be terminated.

JPM I Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-408P COURSE:

Initial Licensed Operator Training REV #:

000 AUTHOR:

S. Andersen TYPIST:

sra TITLE:

2022 ILT NRC EXAM IN-PLANT JPM I APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: _________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM I Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2001400401 / PLOR-408P K/A:

201001A2.07 URO: 4.0 SRO 3.6 TASK DESCRIPTION:

Place the Alternate CRD Flow Control Valve in Service A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM I Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

SO 3.6.D-2, Control Rod Drive Hydraulic System Flow Control Valve Swapping C.

REFERENCES

1.

ON-107, Rev 26, Loss of CRD Regulating Function

2.

SO 3.6.D-2, Rev 4, Control Rod Drive Hydraulic System Flow Control Valve Swapping D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the Unit 2 B CRD Flow Control Valve is placed in service in accordance with SO 3.6.D-2, Control Rod Drive Hydraulic System Flow Control Valve Swapping.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform the necessary steps to place the Unit 2 alternate CRD flow control valve in service. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

The Unit 2 A CRD Flow Control Valve has failed closed and ON-107, Loss of CRD Regulating Function, has been entered.

2.

It has been determined that the alternate CRD Flow Control Valve should be placed in service.

3.

A Reactor Operator is standing by to perform required actions in the Control Room.

4.

Another Equipment Operator will complete SO 3.8.A-2, Control Rod Drive Hydraulic System Routine Inspection.

G.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to place the Unit 2 B CRD Flow Control Valve in service in accordance with SO 3.6.D-2, Control Rod Drive Hydraulic System Flow Control Valve Swapping.

JPM I Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain SO 3.6.D-2, Control Rod Drive Hydraulic System Flow Control Valve Swapping.

(Cue: When examinee describes how they would obtain the procedure, a copy may then be provided by the examiner.)

S Obtains SO 3.6.D-2.

2 Open HV-2-3-68B, CRDHS Inlet Block Vv to Flow Ctrl Stat AO-2-3-19B.

(Cue: When examinee indicates valve handle turned counterclockwise, then inform examinee that the valve is positioned as described.)

S Opens HV-2-3-68B by turning the handle counterclockwise until it stops.

3 Open HV-2-3-69B, CRDHS Outlet Block Vv from Flow Ctrl Stat AO-2-3-19B.

(Cue: When examinee indicates valve handle turned counterclockwise, then inform examinee that the valve is positioned as described.)

S Opens HV-2-3-69B by turning the handle counterclockwise until it stops.

4 Contact the Reactor Operator in the Main Control Room to perform Step 4.1.2 of SO 3.6.D-2.

(Cue: Reactor Operator acknowledges communication and reports to examinee that Step 4.1.2 has been completed.)

S Contacts the Reactor Operator in the Main Control Room for performance of Step 4.1.2 of SO 3.6.D-2.

5 Place HV-2-3-126, I/A Directional Control Vv to Flow Control Station, in the position to supply AO-2-3-19B.

(Cue: HV-2-3-126 is in the position to supply AO-2-3-19B.)

S Places HV-2-3-126 in the position to supply AO-2-3-19B.

6 Place local flow control station selector switch to valve B position.

(Cure: Selector switch is in valve B position.)

S Places local flow control station selector switch to valve B position.

JPM I Page 5 of 5 STEP NO STEP ACT STANDARD 7

Contact the Reactor Operator in the Main Control Room to perform Step 4.1.4 of SO 3.6.D-2.

(Cue: Reactor Operator acknowledges communication and reports to examinee that Step 4.1.4 has been completed.)

S Contacts the Reactor Operator in the Main Control Room for performance of Step 4.1.4 of SO 3.6.D-2.

8 Close HV-2-3-68A, CRDHS Inlet Block Vv to Flow Ctrl Stat AO-2-3-19A.

(Cue: When examinee indicates valve handle turned clockwise, then inform examinee that the valve is positioned as described.)

S Closes HV-2-3-68A by turning the handle clockwise until it stops.

9 Close HV-2-3-69A, CRDHS Outlet Block Vv from Flow Ctrl Stat AO-2-3-19A.

(Cue: When examinee indicates valve handle turned clockwise, then inform examinee that the valve is positioned as described.)

S Closes HV-2-3-69A by turning the handle clockwise until it stops.

10 Inform the Control Room Supervisor that the Unit 2 B CRD Flow Control Valve has been placed in service.

(Cue: Control Room Supervisor acknowledges report.)

S Informs Control Room Supervisor of task completion.

11 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the Unit 2 B CRD Flow Control Valve has been placed in service the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM J Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-238P COURSE:

Licensed Operator Requalification REV #:

002 AUTHOR:

J. R. Felice TYPIST:

sra TITLE:

2022 ILT NRC EXAM IN-PLANT JPM J APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE:

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE ID NO. ________________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM J Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2004740599 / PLOR-238P K/A:

295031 EA1.05 RO: 4.1 SRO 4.1 TASK DESCRIPTION:

Defeating HPCI and RCIC High RPV Level Interlocks (T-229-3)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM J Page 3 of 5 B.

TOOLS AND EQUIPMENT

1.

EOP Tool Locker Key

2.

T-229 Tool Package C.

REFERENCES

1.

T-229-3, Rev. 3, "Defeating RFPT, HPCI and RCIC High Level Interlocks" D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the Unit 3 HPCI and RCIC system high RPV level interlock contacts have been booted per T-229-3.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to defeat the RPV high level interlocks to Unit 3 HPCI and RCIC systems. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES Use of T-229-3, "Defeating RFPT, HPCI, and RCIC High Level Interlocks" has been directed by T-116, RPV Flooding.

A key to the EOP Tool Locker has been obtained.

G.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 4.2 and 4.3 of T-229-3, "Defeating RFPT, HPCI, and RCIC High Level Interlocks" for the Unit 3 HPCI and RCIC systems.

JPM J Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain the T-229 Tool Package and procedure.

(Cue: When knowledge of T-229 Tool Package and procedure location is demonstrated, inform the examinee that materials have been obtained, and provide examinee with procedure copy.)

S T-229 Tool Package and procedure obtained.

2 On the front of panel 30C32, install a boot between contacts 1-2 on relay 23A-K37.

(Cue: Boot is installed as you described.)

S Relay coverplate screws are loosened, coverplate is removed, and boot is slid over contact fingers 1-2 on the 23A-K37 relay on Panel 30C32 (far right contact when viewed from the front of the panel).

3 Inform the Control Room Supervisor that Unit 3 HPCI high RPV level trip signal has been defeated.

(Cue: Control Room Supervisor acknowledges report. If necessary, prompt the examinee to continue performance of T-229-3.)

S Status update reported using telephone or GAI-TRONICS page system.

NOTE: Hand held radio is NOT to be used in the Cable Spreading Room.

4 On the front of panel 30C34, install a boot between contacts 3-4 on relay 13A-K44.

(Cue: Boot is installed as you described.)

S Relay coverplate screws are loosened, coverplate is removed, and boot is slid over contact fingers 3-4 on the 13A-K44 relay on Panel 30C34 (second contact from right when viewed from front of panel).

5 Inform the Control Room Supervisor that Unit 3 RCIC high RPV level interlock signal has been defeated.

(Cue: Control Room Supervisor acknowledges report.)

S Task completion reported using telephone or GAI-TRONICS page system.

NOTE: Handheld radio is NOT to be used in the Cable Spreading Room.

6 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate

JPM J Page 5 of 5 I.

TERMINATING CUE When the Unit 3 HPCI and RCIC system high RPV level interlock contacts have been booted per T-229-3, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

JPM K Page 1 of 5 CONSTELLATION ENERGY Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET TYPE:

JPM QUALIFICATION MANUAL OJT MODULE PROGRAM: Licensed Operator Training CODE #:

PLOR-096P COURSE:

Licensed Operator Requalification Training REV #:

021 AUTHOR:

R. J. Artus TYPIST:

sra TITLE:

2022 ILT NRC EXAM IN-PLANT JPM K APPROVALS:

Signature / Title Date Signature / Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ___________

NAME: __________________________________

Last First M.I.

ISSUE DATE: __________________________

EMPLOYEE I.D. NO. _____________________

COMPLETION DATE: ___________________

COMMENTS:

Training Review for Completeness:

LMS CODE:

Signature/Date LMS ENTRY:

X

JPM K Page 2 of 5 CONSTELLATION ENERGY PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2000200401 / PLOR-096P K/A:

295018AA1.01 RO: 3.3 SRO: 3.3 TASK DESCRIPTION:

LOSS OF RBCCW (PLANT ACTIONS FOR THE INSTRUMENT NITROGEN SYSTEM)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-150-J040 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

JPM K Page 3 of 5 B.

TOOLS AND EQUIPMENT None C.

REFERENCES Procedure ON-113, Rev. 21, Loss of RBCCW D.

TASK STANDARD

1.

Satisfactory task completion is indicated when

a.

The Instrument Air System is supplying the Instrument Nitrogen System.

b.

The Instrument Nitrogen Compressors have been shutdown.

2.

Estimated time to complete: 17 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to lineup the Unit 3 Instrument Air System to supply the Instrument Nitrogen System and trip the Instrument Nitrogen Compressors, using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

RBCCW has been lost on Unit 3.

2.

ON-113, Loss of RBCCW is in progress.

G.

INITIATING CUE The Control Room Supervisor directs you, the Equipment Operator, to perform steps 2.10 and 2.11 of ON-113, Loss of RBCCW on Unit 3.

JPM K Page 4 of 5 H.

PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1

Obtain a copy of procedure ON-113.

(Cue: When knowledge of procedure location is demonstrated, inform the examinee that procedure has been obtained, and provide examinee with procedure copy.)

S A copy of procedure ON-113 is obtained.

2 Open AO-5230A "A Instrument Air Backup to A Instrument N2 Header.

(Cue: The component you identified is in the position you noted.)

S SV-5230A control switch is placed in the OPEN position at the local control station.

3 Verify AO-5230A "A Instrument Air Backup to A Instrument N2 Header valve is open.

(Cue: When the examinee is monitoring the AO-5230A light indications, report the red light is on, and green light is off.)

S AO-5230A red light is verified ON at the local control station.

- - NOTE***

For the next 2 steps, after the examinee identifies the location of the control station for AO-5230B on the TIP Room Roof, have them demonstrate required actions back on the control station for the AO-5230A since it is more accessible.

4 Open AO-5230B "B Instrument Air Backup to B Instrument N2 Header.

(Cue: The component you identified is in the position you noted.)

S SV-5230B control switch is placed in the OPEN position at the local control station.

5 Verify AO-5230B "B Instrument Air Backup to B Instrument N2 Header valve is open.

(Cue: When the examinee is monitoring the AO-5230B light indications, report the red light is on, and green light is off.)

S AO-5230B red light is verified ON at the local control station.

6 Shutdown the 3A Instrument Nitrogen Compressor.

(Cue: The component you identified is in the position you noted.)

S The 3A Instrument Nitrogen Compressor control switch (HS-3-16-5225) is placed in the OFF position at the local control station.

JPM K Page 5 of 5 STEP NO STEP ACT STANDARD 7

Verify the 3A Instrument Nitrogen Compressor is shutdown.

Cue: When the examinee is monitoring the 3A Instrument Nitrogen Compressor for status, report that the green light is on.)

S The 3A Instrument Nitrogen Compressor OFF (green) light is ON at the local control station.

8 Shutdown the 3B Instrument Nitrogen Compressor.

(Cue: The component you identified is in the position you noted.)

S The 3B Instrument Nitrogen Compressor control switch (HS-3-16-5121) is placed in the OFF position at the local control station.

9 Verify the 3B Instrument Nitrogen Compressor is shutdown.

(Cue: When the examinee is monitoring the 3B Instrument Nitrogen Compressor for status, report that the green light is on.)

S The 3B Instrument Nitrogen Compressor OFF (green) light is ON at the local control station.

10 Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

S Task completion reported using telephone, handheld radio, or GAI-TRONICS page system.

11 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

P Positive control established.

Under ACT P - must perform S - must simulate I.

TERMINATING CUE When the Instrument Air backup valves to Instrument Nitrogen, AO-5230A and AO-5230B, are open and the Instrument Nitrogen Compressors have been shutdown, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #1 Form 3.3-1 Rev 0 Simulation Facility PBAPS Scenario No. #1 Op Test No. 2022 NRC Exam Scenario Source NEW Examiners Operator ________________ CRS (SRO)

________________ URO (ATC)

________________ PRO (BOP)

Initial Conditions IC-14 100% Power Turnover A Unit 2 is operating at 100% power.

No equipment is out of service.

Hotwell level was raised to 20.

The A1 Water Box Inlet Valve is to be cycled open and closed per SO 28A.7.E, Cycling of a Water Box Inlet Valve.

Engineering reports that no power reduction is required.

Condenser Cleaning is aligned to the B Water Box.

Critical Tasks Critical Task 1: Commence lowering RPV Water Level below -60 within 5 minutes of ATWS conditions and reactor power above 4%.

Critical Task 2: Commence shutdown of the reactor within 10 minutes of ATWS conditions using one of the following methods:

Insert control rods per T-220, Driving Control Rods Inject SBLC into the RPV Event No.

Malfunction No.

Event Type*

Event Description 1

See Scenario Guide N

PRO CRS Cycling the A1 Water Box Inlet Valve 2

See Scenario Guide I

TS PRO CRS HPCI Spurious Start 2020 NRC Scenario 3 3

See Scenario Guide C

URO CRS CRD Flow Control Valve Failure 4

See Scenario Guide C

TS URO CRS Control Rod Drift 2021 NRC Scenario 1

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #1 Form 3.3-1 Rev 0 5

See Scenario Guide C

R PRO CRS URO 1 Bus Fault 6

See Scenario Guide M

ALL Two Additional Rod Drifts 7

See Scenario Guide C

ALL Hydraulic ATWS 8

See Scenario Guide I

PRO CRS RFP E-Stop Failure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #1 Form 3.3-1 Rev 0 Scenario Summary The scenario begins with the reactor at 100% power with no equipment out of service. Preparations have been made for cycling the A1 Water Box Inlet Valve.

Following shift turnover, the crew will cycle the A1 Water Box Inlet Valve per SO 28A.7.E, Cycling a Water Box Inlet Valve.

Once the water box inlet valve is reopened, a spurious start of the HPCI pump will occur. The crew will enter OT-104, Positive Reactivity Addition, and place HPCI in short term shutdown. The CRS will declare HPCI inoperable per T.S. 3.5.1.C.

Once HPCI is secured and the technical specification call has been made, the A CRD Flow Control Valve will fail closed. The crew will enter ON-107, Loss of CRD Regulating Function, and swap to the B Flow Control Valve.

When the alternate CRD flow control valve is in service, one control rod will begin drifting into the core. The crew will enter ON-121, Drifting Control Rod and fully insert the control rod. The CRS will declare the control rod inoperable per T.S.

3.1.3.C.

Once the technical specification has been declared, a fault will occur on the No. 1 Bus. This will cause a loss of the A recirc pump and A Condensate Pump, along with multiple other pieces of equipment. The crew will enter OT-112, Unexpected/Unplanned Change in Core Flow and insert all GP-9 control rods and restore tripped plant equipment.

While the crew is addressing the loss of the 1 Bus, two additional control rods will drift into the core, requiring a reactor scram. When the reactor is scrammed, the crew will experience a hydraulic ATWS. The crew will enter T-117 and lower RPV water level below -60. The URO will trip the Recirc pumps and initiate SBLC.

When the PRO attempts to emergency stop the feedwater pumps, the E-Stop pushbuttons will fail, requiring the feed pumps to be manually tripped. The trip can be reset, and the feed pumps placed back in service for level control. The URO will perform T-220 to manually insert control rods.

The scenario may be terminated when RPV water level is being controlled in the established control band and control rods are being inserted.

1 SIMULATOR OPERATOR INSTRUCTIONS FOR 2022 NRC SCENARIO #1 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is a new scenario written for the 2022 NRC exam.

INITIAL SETUP Initial Conditions

Reset to IC-14, 100% power

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active

Raise Hotwell level to 20

Align Hotwell level control to the 2B Hotwell Blocking Tags

None Event Triggers ET9, ZGI02A4S01!=4 OR ZGI02A3S01==1 OR ZGI02A3S02==1(Mode Sw or Scram PB)

dmf IPM03

2 Malfunctions INSERTED

IPM03, Anticipated Transient Without Scram (ATWS) - 90%

TRG 2

HPC02, HPCI Spurious Start TRG 3

CRH01A, CRD Flow Control Valve A Failure - 0%

TRG 4

CRM041851, Control Rod (18-51) Drift In TRG 5

CRM042255, Control Rod (22-55) Drift In

CRM042639, Control Rod (26-39) Drift In Overrides TRG 3

ANO205RG4, CRD Charg Wtr Hdr Hi Press - ALARM_ON TRG 5

ZGI02A2A12S7, RFPT C Emer Stop - NOEME

ZGI02A2A12S4, RFPT B Emer Stop - NOEME

ZGI02A2A12S1, RFPT A Emer Stop - NOEME Trip Overrides None Remote Functions TRG 6

CRH03, CRD Flow Control Stat FCV 3 19A/19B Sel - B TRG 8

T221_1, Remove Low PRV Level Gr I Isolation - REMOVE Turnover Procedures SO 28A.7.E-2, Cycling of a Water Box Inlet Valve

3 SIMULATOR OPERATOR DIRECTIONS EVENT 1 Cycle the A1 Water Box Inlet Valve Support the Crew as necessary.

Once the A1 Water Box Inlet Valve is closed and at the discretion of the Lead Examiner, Time Compression may be used to direct the CRS to reopen the water box inlet valve in lieu of the 5 minute wait called for in the procedure.

EVENT 2 HPCI Spurious Start When directed by the Lead Examiner, insert TRG 2 and verify the following event activates:

HPC02, HPCI Spurious Start If directed to inspect the HPCI relays, wait 2 minutes and report no observable issues with HPCI.

EVENT 3 CRD Flow Control Valve Failure When directed by the Lead Examiner, initiate pending events on TRG 3 and verify that the following event activates:

CRH01A, CRD Flow Control Valve A Failure - 0%

ANO205RG4, CRD Charg Wtr Hdr Hi Press - ALARM_ON If directed to investigate failed flow control valve, wait 2 minutes and report theres an unisolable air leak at the valve.

When directed to open the isolation valves for the B CRD Flow Control Valve, (step 4.1.1), wait 1 minute and report the valves are open.

When directed to place the selector switch in position B, (step 4.1.3), insert TRG 6 and verify the following event activates:

CRH03, CRD Flow Control Stat FCV 3 19A/19B Sel - B Report completion to the Control Room. When directed to isolate the A CRD Flow Control Valve, (step 4.1.5), wait 1 minute and report completion.

When the CRD Flow Control Valve is opened, delete the following override:

ANO205RG4, CRD Charg Wtr Hdr Hi Press - ALARM_ON

4 EVENT 4 Control Rod Drift When directed by the Lead Examiner, insert TRG 4 and verify the following event activates:

CRM041851, Control Rod (18-51) Drift In If directed to inspect HCU 18-51, wait 3 minutes and report the Exhaust header is hot to the touch and you hear flow noise.

When Control Rod 18-51 position indicates fully inserted, delete malfunction CRM041851.

EVENT 5 1 Bus Fault At the direction of the Lead Examiner, load the following Batch File:

1_Bus_Fault When directed to investigate the loss of the 1 Bus, wait 3 minutes and report an acrid odor coming from the bus, but no indication of fire.

Support crew actions for starting the C Drywell Chiller.

If directed to reset the A Instrument Air Compressor, insert the following Remote Functions:

IAS03A, A Air Compressor Reset

IAS10A, A IA Compressor 480 Bkr UV Reset If directed to reset the A Drywell Chiller, insert the following Remote Functions:

DCW16A, DW Chiller Trip Reset A

DCW19A, A DW Chiller 480 Bkr UV Reset

5 EVENT 6 2 Control Rods Drifting When directed by the Lead Examiner, insert TRG 5 and verify the following events activate:

CRM042255, Control Rod (22-55) Drift In

CRM042639, Control Rod (26-39) Drift In

ZGI02A2A12S7, RFPT C Emer Stop - NOEME

ZGI02A2A12S4, RFPT B Emer Stop - NOEME

ZGI02A2A12S1, RFPT A Emer Stop - NOEME EVENT 7 Hydraulic ATWS When the Mode Switch is taken to Shutdown, verify the following malfunction deletes:

IPM03, Anticipated Transient Without Scram (ATWS)

When directed to perform T-221, insert TRG 8 and verify the following event activates:

T221_1, Remove Low PRV Level Gr I Isolation - REMOVE Repot completion to the Control Room.

EVENT 8 RFPs Fail to E-Stop TERMINATION The scenario may be terminated when RPV water level is being controlled in the established control band and control rods are being inserted.

6 SHIFT TURNOVER PLANT CONDITIONS:

A Unit 2 is operating at 100% power.

No equipment is out of service.

Hotwell level was raised to 20.

The A1 Water Box Inlet Valve is to be cycled open and closed per SO 28A.7.E, Cycling of a Water Box Inlet Valve.

Engineering reports that no power reduction is required.

Condenser Cleaning is aligned to the B Water Box.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Cycling the A1 Water Box Inlet Valve per SO 28A.7.E-2, Cycling of a Water Box Inlet Valve.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

None GENERAL INFORMATION:

None

7 CRITICAL TASK LIST

1.

Commence lowering RPV Water Level below -60 within 5 minutes of ATWS conditions and reactor power above 4%.

a. Safety Significance - Failure to lower RPV water level will result in damage to the fuel cladding due to thermal hydraulic instabilities.

b. Cue - Reactor scram initiated and control rods not fully inserted.

c. Measurable Performance Indicators - Placing HPCI in PTL, closing the feedwater pump discharge valves, and tripping all 3 feedwater pumps until RPV water level is below -60; at which point, injection may recommence.

d. Performance Feedback - RPV water level lowering.

2.

Commence shutdown of the reactor within 10 minutes of ATWS conditions using one of the following methods:

Insert control rods per T-220, Driving Control Rods

Inject SBLC into the RPV

b. Safety Significance - Failure to lower RPV water level will result in damage to the fuel cladding due to thermal hydraulic instabilities.

c. Cue - Reactor scram initiated and control rods not fully inserted.

d. Measurable Performance Indicators - Initiating SBLC and/or manually inserting control rods.

e. Performance Feedback - Lowering reactor power.

8 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 1 Event

Description:

Cycling the A1 Water Box Inlet Valve Cause:

N/A Effects:

N/A Time Position Applicant's Actions or Behavior CRS

1. Direct the PRO to perform SO 28A.7.E to cycle the A1 Water Box Inlet Valve.

PRO

1. Verifies that all Circulating Water Pumps are in service and that no discharge pressure is greater than 8 psig. (Step 4.1)

2. Verifies per the turnover sheet that no power reduction is required. (Step 4.2)

3. Verifies Condenser Cleaning is aligned to the B Water Box.

(Step 4.3)

4. Verifies Hotwell level is not aligned to the A Hotwell. (Step 4.4.2)

5. Verifies Hotwell level is at 20. (Step 4.4.4)

6. Places the control switch for MO-2-28A-2270A to the CLOSE position. (Step 4.7)

7. Places the control switch for MO-2-28A-2270A to the OPEN position. (Step 4.8)

8. Verifies that no other water box inlet valve is to by cycled. (Step 4.10)

9. Acknowledges any Hotwell Hi Level alarms received.

10. Restores Hotwell level to 15. (Step 4.11)

9 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.:

2 Event

Description:

HPCI Spurious Start Cause:

Failed contacts in the initiation circuit.

Effects:

RPV water level and reactor power rising.

Time Position Applicant's Actions or Behavior PRO

1. Recognize and report the following alarms are in:

a. 221 E-5, Reactor Water Level Low Low

b. 222 D-5, HPCI Auxiliary Oil Pump Running

c. 228 C-5, HPCI Relays Not Reset

2. Reports that HPCI has initiated and is injecting.

TS CRS

1. Enter and execute OT-104, Positive Reactivity Addition.

2. Directs PRO to place HPCI in Short Term Shutdown. (Step 3.3)

3. Determines T.S. 3.5.1, condition C applies and HPCI must be restored within 14 days.

PRO

1. Places the Aux Oil Pump control switch in START. (Step 1)

2. Places the Vac Pump control switch in START. (Step 2)

3. Depresses and holds the Remote Trip pushbutton. (Step 3)

4. Verifies HO-4513, HPCI Turbine Stop, is closed. (Step 4)

5. Verifies annunciator 221 B-1, HPCI Turb Trip, alarms. (Step 5)

6. Places the Aux Oil Pump control switch in PTL when turbine speed reaches 0 rpm. (Step 6)

7. Releases the Remote Trip Pushbutton. (Step 7)

URO

1. Monitors plant conditions.

10 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.:

3 Event

Description:

CRD Flow Control Valve Failure Cause:

Air line rupture to the A Flow Control Valve Effects:

CRD flow lowers to 0 gpm Time Position Applicant's Actions or Behavior URO

1. Update and report alarm 211 G-4, CRD Charging Water Header High Press, is in.

2. Update and report the A CRD Flow Control Valve is fully closed.

3. Updates and enters ON-107, Loss of CRD Regulating Function.

CRS

1. Acknowledges report.

2. Directs URO to place the B CRD Flow Control Valve in service per SO 3.6.D-2, Control Rod Drive Hydraulic System Flow Control Valve Swapping. (Step 2.8)

URO

1. Directs EO to open HV-2-3-68B and HV-2-3-69B to unisolate the B CRD Flow Control Valve. (Step 4.1.1)

2. Places the CRD Flow Controller in MANUAL and dials it to minimum. (Step 4.1.2)

3. Directs EO to place HV-2-3-126 in the Valve B position. (Step 4.1.3)

4. Raises flow on the CRD Flow Controller to 55-65 gpm. (Step 4.1.4)

5. Verifies the B CRD Flow Control Valve is responding. (Step 4.1.4.1)

6. Places the CRD Flow Controller in AUTO. (Step 4.1.4.2)

7. Directs EO to close HV-2-3-68A and HV-2-3-69A to isolate the A CRD Flow Control Valve. (Step 4.1.5)

11 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.:

4 Event

Description:

Control Rod 18-51 Drift Cause:

Failed Exhaust Line Solenoid Valve Effects:

Control Rod will drift into the core Time Position Applicant's Actions or Behavior URO

1. Report annunciator 211 D-4, Rod Drift, alarm is in.

2. Identify rod 18-51 drifting into the core.

3. Updates and enters ON-121, Control Rod Drift.

a. Selects rod 18-51. (Step 2.2)

b. Fully insert Control Rod 18-51 using the Emergency Rod In switch and holds it for 30 seconds. (Step 2.8)

c.

Recognize the control rod settled at position 00. (Step 2.8.3)

d. Resets the Control Rod Drift alarm. (Step 2.11)

TS CRS

1. Acknowledges report.

2. Directs RO to scram the reactor if 2 additional control rods drift.

(Step 2.1)

3. Directs RO to fully insert Control Rod 18-51. (Step 2.8)

4. Notify the Reactor Engineering. (Step 2.5.2)

5. Determines T.S. 3.1.3, condition C applies and the HCU must be disarmed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

PRO

1. Dispatches EO to investigate HCU 18-51. (Step 2.5.1)

2. Provide Peer checks as directed by the CRS.

12 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 5 Event

Description:

1 Bus Fault Cause:

Electrical Fault on the 1 Bus Effects:

A RRP, A Condt Pump, A Drywell Chiller trips, reactor power lowers Time Position Applicant's Actions or Behavior PRO

1. Recognize and report multiple control room alarms are in:

a. 219 B-1, 1 Aux Bus Lo Voltage

b. 203 E-2, A Condensate Pump Bkr Trip

c. 214 C-3, A Recirc 13KV Bkr Trip

d. 214 G-3, B Recirc Flow Limit

e. 217 D-1, Drywell Chiller Trouble URO

2. Recognize and report trip of the A Recirc Pump.

3. Recognize and report the recirc runback is occurring.

4. Updates and enters OT-112, Unexpected/Unexplained Change in Core Flow.

5. Emergency stops RFPs as necessary.

6. Inserts all GP-9 control rods. (OT-112, Step 2.2)

CRS

1. Acknowledges reports from ROs.

2. Directs URO to insert all GP-9 rods and to monitor for THI.

3. Directs PRO to place the C Drywell Chiller in service per SO 44A.6.A-2, Placing an Additional Drywell Chiller in Service.

(ARC 217 D-1, Step 2)

4. Directs PRO to crosstie 480V load centers per RRC 55.1, Crosstie of 480V Load Centers during a Plant Event.

PRO

1. Places the C Drywell Chiller in service as follows:

a. Places the control switch for the C Drywell Chiller to START. (Step 4.9.4)

2. Crossties 480V load centers as follows:

a. Holds closed the tie breaker control switch. (Step 1)

b. Opens the 480V bus breaker. (Step 2)

c. Verifies the tie breaker has closed and releases the bus tie breaker control switch. (Step 3)

13 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 6 Event

Description:

Two Control Rods Drifting Cause:

Failed exhaust line control valve.

Effects:

Control rods drift into the core.

Time Position Applicant's Actions or Behavior CT1 URO

1. Recognize and report 2 additional control rods drifting.

2. Inserts a manual reactor scram.

14 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 7 Event

Description:

Hydraulic ATWS Cause: Water buildup in Scram Discharge Volume Effects: Control rods not fully inserted and power oscillations.

Time Position Applicant's Actions or Behavior URO

1. Reports Mode Switch is in SHUTDOWN, control rods are not fully inserted, and APRMs are not downscale.

CRS

1. Updates and enters T-101, RPV Control.

2. Directs ROs to perform the ATWS Rapid Response Cards.

3. Directs URO to inject SBLC.

4. Directs URO to perform T-216, Rod Insertion by Manual Scram or Individual Scram Test Switches, and T-220, Driving Control Rods during Failure to Scram.

5. Directs PRO to perform T-240, Attachment 1, Figure 1.

6. Directs PRO to establish RPV water level -70 to -130.

7. Directs PRO to perform T-221, Main Steam Isolation Valve Bypass.

CT3 URO

1. Performs ATWS RRC as follows:

a. Emergency stops feedwater pumps as necessary to maintain RPV water level. (Event 8) (Step 2)

b. Initiates ARI. (Step 3)

c. Trips the B Recirc Pump. (Step 7)

d. Report reactor power and states ready to inject SBLC.

(Step 8)

e. Starts a SBLC pump and reports tank level to the CRS.

(Step 9)

f. Verify Scram Discharge Volume Vent and Drains are closed. (Step 11)

15 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 7 (contd)

Event

Description:

Hydraulic ATWS cont.

Time Position Applicant's Actions or Behavior CT2 PRO

1. Performs ATWS RRC as follows:

a. Places ADS Keylock Switches in BYPASS. (Step 1)

b. Reports ADS is bypassed and ready to perform T-240. (Step

2)

c. Verifies Group I, II, and III isolations. (Step 3.1)

d. Bypass and restore Drywell Instrument Nitrogen. (Step 3.3)

e. Verifies HWC is isolated. (Step 3.8)

2. Directs EO to perform T-221.

3. Performs T-240 as follows:

a. Emergency Stops all feedwater pumps. (Event 8) (Step 4.6.1)

b. Closes all RFP discharge valves. (Step 4.6.2)

c. Stops the C RFP discharge valve when RPV level is < 60.

(Step 4.7.1)

d. Resets a feedwater pump and commences injection. (Step 4.7.2)

e. Maintains RPV water level between -70 and -130.

f. Shift DFWS to ATWS Mode. (Step 4.7.5)

CT3 URO

1. Directs EO to perform steps 4.1 and 4.2 of T-216.

2. Performs T-220 as follows:

a. Places the CRD Flow Controller in MANUAL and raises the setpoint to maximum. (Step 4.2)

b. Places the RWM keylock switch in BYPASS. (Step 4.3)

c. Inserts control rods using the Emergency In control switch.

(Step 4.4)

16 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

1 Event No.: 8 Event

Description:

RFPs Fail to E-Stop Cause: Failure of E-Stop pushbutton Effects: RFPs will not E-Stop Time Position Applicant's Actions or Behavior CT2 PRO

1. Attempts to emergency stop the feedwater pumps.

2. Recognize failure of feedwater pumps to stop.

3. Depresses the TRIP pushbutton for all feedwater pumps.

TERMINATION CRITERIA:

The scenario may be terminated when RPV water level is being controlled in the established control band and control rods are being inserted.

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #3 Form 3.3-1 Rev 0 Simulation Facility PBAPS Scenario No. #3 Op Test No. 2022 NRC Exam Scenario Source NEW Examiners Operator ________________ CRS (SRO)

________________ URO (ATC)

________________ PRO (BOP)

Initial Conditions IC-14 85% Power Turnover Unit 2 is at rated power with the B ESW pump tagged out.

The crew will lower reactor power and remove the C Condensate Pump from service.

Critical Tasks Critical Task 1: Close the stuck open SRV prior to Torus Water Temperature reaching 110oF.

Critical Task 2: Manually start ESW pumps to establish cooling to the diesel generators within 10 minutes of the diesel generators automatically starting.

Critical Task 3: Spray the drywell prior to drywell pressure exceeding PSP.

Event No.

Malfunction No.

Event Type*

Event Description 1

See Scenario Guide R

URO CRS Power Reduction 2

See Scenario Guide N

PRO CRS Secure the C Condensate Pump 3

See Scenario Guide C

TS ALL Loss of 2SU-E 4

See Scenario Guide C

TS ALL CRS A SRV Fails Open 5

See Scenario Guide M ALL Loss of Offsite Power 6

See Scenario Guide I

MC PRO CRS E3 DG Fails to Autostart

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #3 Form 3.3-1 Rev 0 7

See Scenario Guide C

MC PRO CRS E22 Breaker Fails to Auto-close 8

See Scenario Guide C

MC PRO CRS DG Cooling Fails to Autostart 9

See Scenario Guide C

ALL CRS Steam Leak in Containment

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #3 Form 3.3-1 Rev 0 Scenario Summary The scenario begins with the reactor at 85% power with the B ESW Pump tagged out for repairs.

Following shift turnover, the crew will reduce reactor power and remove the C Condensate Pump from service.

Once the C Condensate pump is secured, a loss of 2SU-E will occur. The loss of power will affect multiple pieces of equipment. The crew will respond to stabilize plant conditions and the CRS will declare the offsite power source inoperable per T.S. 3.8.1.A and declare the RCS Leakage Detection inoperable per T.S. 3.4.5.A.

Once the technical specification has been declared and plant conditions are stable, the A SRV will fail open. The crew will enter OT-114, Stuck Open SRV, place Torus Cooling into service, and take actions to close the SRV. The SRV will go closed when EHC pressure set is lowered. The CRS will declare the A SRV inoperable per T.S. 3.5.1.E and declare one loop of RHR inoperable due to the Torus Cooling lineup per T.S. 3.5.1.F and 3.5.1.A.

Once plant conditions are stable and the Technical Specification has been declared, a loss of offsite power will occur. The reactor will scram, and the crew will enter T-101, RPV Control, and SE-11, Loss of Offsite Power. The E22 breaker will fail to close, the E3 DG will fail to automatically start, and the ECW pump will fail to start. The crew will act to manually close the E22 breaker and start the E3 DG. Once the buses are energized, the crew will manually start the A ESW pump to establish diesel cooling.

When the reactor scrams, a steam leak will occur in the drywell. A Drywell-Torus vent breaker will fail open and drywell pressure will rise and approach the PSP limit. The crew will enter T-102, Primary Containment Control, and spray the drywell to prevent exceeding the PSP limit.

The scenario may be terminated when RPV water level is being controlled in the established control band and drywell sprays are in service.

1 SIMULATOR OPERATOR INSTRUCTIONS FOR 2022 NRC SCENARIO #3 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is a new scenario written for the 2022 NRC exam.

INITIAL SETUP Initial Conditions

Reset to IC-14, 100% power

Lower reactor power using recirc flow to approx. 85% power

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active Blocking Tags

B ESW Pump Event Triggers ET4, ZGI02A4S01!=4 OR ZGI02A3S01==1 OR ZGI02A3S02==1(Mode Sw or Scram PB)

2 Malfunctions INSERTED

DGA04C, DG C Autostart Failure

DGA02B, DG B Breaker Auto Close Circuit Failure

ECW03, ECW Pump Failure to Autostart

ESW02A, ESW Pump A Failure to Autostart

ESW02B, ESW Pump B Failure to Autostart TRG 1

MAP05A, Startup Source Bus Fault 2SU TRG 2

MSS08A, Reactor Pressure Relief Valve A Failure - 100%

TRG 4

MSS01, Steam Leak in Primary Containment - 20%, 20 Min Ramp

PCS03A, Torus-Drywell Vacuum Breaker A Fails Open Overrides INSERTED

ZLOSW26C0BP57_1, B ESW Pump Green Light - OFF

ZLOSW26C0BP57_2, B ESW Pump Red Light - OFF

ZGI04A6S20, B ESW Pump Control Switch - STOP Trip Overrides None Remote Functions TRG 3

ADS02A, A SRV Control Power Fuse - REMOVE TRG 6

RHR02A, LPCI Line A Stayfull Valve HV-70A - CLOSE

RHR02B, LPCI Line B Stayfull Valve HV-70B - CLOSE TRG 7

T261_1, Backup N2 from CAD System to B N2 Head - OPEN Turnover Procedures SO 5.2.A-2, Condensate System Condensate Pump Shutdown

3 SIMULATOR OPERATOR DIRECTIONS EVENT 1 Power Reduction Support the Crew as necessary to reduce reactor power for removing the C Condensate Pump from service.

EVENT 2 Secure the C Condensate Pump When directed to close HV-2-27A-26022C, (step 4.5) wait 1 minute and report the valve closed.

EVENT 3 Loss of 2SU-E When directed by the Lead Examiner, initiate pending events on TRG 1 and verify that the following event activates:

MAP05A, Startup Source Bus Fault 2SU When directed to investigate the loss of 2 SU-E, report that there are overcurrent flags on the 2SU bus breakers.

If directed to reset the Main Turbine Lift Pumps, wait 2 minutes and insert Remote Function MTA01, Reset Lift Pumps.

4 EVENT 4 A SRV Fails Open When directed by the Lead Examiner, insert TRG 2 and verify the following event activates:

MSS08A, Reactor Pressure Relief Valve A Failure - 100%

When directed to close valves HV-2-10-70A and B, wait 3 minutes and insert TRG 6 and verify the following events activate:

RHR02A, LPCI Line A Stayfull Valve HV-70A - CLOSE

RHR02B, LPCI Line B Stayfull Valve HV-70B - CLOSE Report completion to the control room.

When directed to pull the control power fuse for the A SRV, wait 1 minute and insert TRG 3 and verify the following event activates:

ADS02A, A SRV Control Power Fuse - REMOVE Report completion to the Control Room.

When the crew lowers PAM pressure to 885 psig, delete the following malfunction:

MSS08A, Reactor Pressure Relief Valve A Failure - 100%

5 EVENT 5 Loss of Offsite Power At the direction of the Lead Examiner, load the following Batch File:

LOOP When directed to perform running inspections on all diesel generators, wait 10 minutes and report running inspections completed satisfactory.

When contacted regarding time till return of offsite power, report the loss is still under investigation and a restoration time has not been determined.

If directed to perform T-261, wait 15 minutes and insert TRG 7 and verify the following event activates:

T261_1, Backup N2 from CAD System to B N2 Head - OPEN When directed to monitor Feedwater Pump and the Main Turbine rotors, acknowledge the report.

EVENT 6 E3 DG Fails to Start EVENT 7 E22 Breaker Fails to Auto-Close EVENT 8 DG Cooling Fails to Start EVENT 9 Steam Leak in Containment When the Mode Switch is placed in Shutdown, verify the following events activate:

MSS01, Steam Leak in Primary Containment - 20%, 20 Min Ramp

PCS03A, Torus-Drywell Vacuum Breaker A Fails Open TERMINATION The scenario may be terminated when RPV water level is being controlled in the established control band and drywell sprays are in service.

6 SHIFT TURNOVER PLANT CONDITIONS:

A Unit 2 is operating at 85% power.

B ESW Pump is tagged out for repairs.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Reducing reactor power and removing the C Condensate Pump from service per SO 5.2.A-2, Condensate System Condensate Pump Shutdown.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

B ESW Pump GENERAL INFORMATION:

None

7 CRITICAL TASK LIST

1.

Close the stuck open SRV prior to Torus water temperature reaching 110oF.

a. Safety Significance - Failure to close the SRV will result in Torus water temperature exceeding the design temperature and possible loss of the primary containment.

b. Cue - An open SRV and Torus water temperature rising.

c. Measurable Performance Indicators - Lowering DEHC Pam Pressure to 885 psig.

d. Performance Feedback - SRV indicating closed and Torus water temperature no longer rising.

2.

Manually start ESW pumps to establish cooling to the diesel generators within 10 minutes of the diesel generators automatically starting.

a. Safety Significance - Failure to start diesel generator cooling will result in damage to the diesel generators and a complete loss of all AC power.

b. Cue - Reactor scram initiated and control rods not fully inserted.

c. Measurable Performance Indicators - Diesel generators running and failure of the ESW and ECW pumps to start.

d. Performance Feedback - One ESW or ECW pump running.

3.

Spray the drywell prior to drywell pressure exceeding PSP.

a. Safety Significance - Failure to spray the drywell will result in loss of the suppression function of the drywell and result in a loss of the primary containment.

b. Cue - Rising drywell pressure with a failure of the Torus-Drywell Vacuum Breakers.

c. Measurable Performance Indicators - Initiating drywell sprays.

d. Performance Feedback - Lowering drywell pressure.

8 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 1 Event

Description:

Power Reduction Cause:

N/A Effects:

N/A Time Position Applicant's Actions or Behavior CRS

1. Direct the URO to lower reactor power to 78% per the standing ReMA.

URO

1. Depresses the A and B ASD Speed Lower pushbuttons to lower reactor power.

PRO

1. Peer checks Recirc Pump operations.

9 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.:

2 Event

Description:

Secure the C Condensate Pump Cause:

N/A Effects:

N/A Time Position Applicant's Actions or Behavior CRS

1. Directs PRO to perform SO 5.2.A-2 to secure the C Condensate Pump.

PRO

1. Verifies DFW point RRPA-SPEED-HI-1 indicates LOFLOW(1) on the DFW screen. (Step 4.2)

2. Closes MO-2098C, Condensate Pump Valves Discharge C.

(Step 4.3)

3. Places the C Condensate Pump control switch to STOP. (Step 4.4)

4. Directs EO to close HV-2-27A-26022C, Seal Water Supply Valve for 2C Condensate Pump. (Step 4.5)

10 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.:

3 Event

Description:

Loss of 2SU-E Cause:

Fault in the 2SU-E supply breaker.

Effects:

CRD pump trip, Group II/III half isolations, emergency buses transfer to the alternate power supply.

Time Position Applicant's Actions or Behavior PRO

1. Recognize and report the following alarms:

a. 006 J-1, 2 SU-E Bkr Trip

b. 211 F-1, A CRD Water Pump Trip

c. 214 D-1, Group II/III Inboard Isol Relays Not Reset

d. 214 E-1, Group II/III Outboard Isol Relays Not Reset

e. 214 E-4, Clean-Up Recirc Pump Suction Line Break URO

1. Recognize and reports trip of the A CRD pump.

2. Updates and enters ON-107, Loss of CRD Regulating Function.

PRO

1. Recognizes and reports loss of 2SU-E.

2. Verifies all emergency buses transferred to the 3SU-E bus.

3. Recognizes and reports a half Group II/III isolation has occurred.

TS CRS

1. Acknowledges reports

2. Directs PRO to perform GP-8.C, Groups I, II, and III Inboard Half Isolation and SO 53.7.Q, Response to a Loss of No. 2 Off-site Startup Source.

3. Directs URO to restart the A CRD pump.

4. Determines a 7 day LCO is required per T.S. 3.8.1, Condition A.

5. Determines a 7 day LCO is required per T.S. 3.4.5, Condition A.

PRO

1. Performs SO 53.7.Q, Response to a Loss of No. 2 Off-site Startup Source to align emergency bus breakers.

(Note: The crew may or may not perform this action.)

11 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.:

3 Event

Description:

Loss of 2SU-E Cont.

Time Position Applicant's Actions or Behavior URO

1. Places the A CRD Pump in service as follows:

a. Places the CRD Flow Control Valve controller in Manual and dials it down to minimum. (Step 2.5.1.1-

2)

b. Opens MO-2-03-020, Drive Wtr Press. (Step 2.5.1.3)

c. Closes MO-2-8029A and B, Seal Purge. (Step 2.5.1.4-5)

d. Starts the A CRD Pump. (Step 2.5.1.6)

e. Adjusts the CRD Flow Control valve to 55-65 gpm and places the controller in Auto. (Step 2.5.8.a)

f. Throttles MO-2-03-020 to 260-280 psig and verifies cooling water pressure. (Step 2.5.8.c)

2. Opens MO-2-8029A and B. (Step 2.5.8.i)

PRO

1. Performs GP-8.C as follows:

a. Performs COL GP-8.C. (Step 4.1)

b. Places switches 16A-S32 and 16A-S33 to GRP II/III.

(Step 4.3 and 4.4)

c. Verifies alarms 214 D-1 and E-1 clear.

12 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.:

4 Event

Description:

A SRV Fails Open Cause:

Failed Control Switch Effects:

Rising Torus water temperature, lowering steam flow and generator loading Time Position Applicant's Actions or Behavior PRO

1. Reports alarm 210 D-2, Safety Relief Valve Open, is in.

2. Reports the A SRV indicates open.

3. Updates and enters OT-114, Inadvertent Opening of a Relief Valve.

4. Determines the SRV is fully open.

CRS

1. Directs PRO to maximize Torus Cooling. (Step 3.1)

2. Directs URO to lower reactor power to the flow limit. (Step 3.5.3)

3. Directs PRO to cycle the SRV control switch. (Ste 3.5.1)

4. Directs URO to lower DEHC Pam Pressure to 885 psig. (Step 3.5.3.1)

5. Directs PRO to remove the control power fuse for the A SRV.

(Step 3.5.2)

CT1 URO

1. Lowers recirc pump speed to the flow limit per GP-9.

2. Depresses the 885 pushbutton on the DEHC screen.

PRO

1. Performs RRC for Torus Cooling as follows:

a. Opens MO-039A and B, Torus Header. (Step 2)

b. Opens MO-089A(B,C,D). (Step 3)

c. Starts the HPSW pump and the RHR pump. (Step 5-6)

d. Opens MO-034A and B, Full Flow Test (Step 7)

e. Starts additional HPSW Pumps as necessary. (Step 8-9)

f. Starts remaining RHR pumps. (Step 10)

g. Directs EO to close HV-2-10-70A and B. (Step 12)

2. Cycles the A SRV control switch.

3. Directs EO to pull the control power fuse for the A SRV.

4. Reports the SRV is closed.

TS CRS

1. Determines a 14 day LCO is required per T.S. 3.5.1 Condition E.

2. Determines a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO is required per T.S. 3.5.1.F and a 7 day LCO is required per T.S. 3.5.1.A for Torus Cooling.

13 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 5 Event

Description:

Loss of Offsite Power Cause:

Power lost from TSO Effects:

Diesel generator starts, reactor scrams.

Time Position Applicant's Actions or Behavior URO

1. Recognize and report control rods are inserting.

2. Places the Mode Switch in Shutdown.

3. Verifies start of HPCI and RCIC.

4. Controls RPV water level with HPCI and RCIC.

5. Controls RPV pressure with SRVs and HPCI CRS

1. Updates and enters T-101, RPV Control, and SE-11, Loss of Offsite Power.

2. Directs URO to restore and maintain RPV water level between -

35 and +35 with HPCI and RCIC and control RPV pressure 800-1000 psig with SRVs and HPCI.

3. Determines SE-11, Sheet 2 is required to be performed.

4. Directs PRO to secure the EBOPS when the feedwater pumps stop rolling.

5. Directs PRO to perform the following when the Main Turbine stops spinning:

a. Shut down the Main Turbine EBOP.

b. Vent the Main Generator per SE-11, Attachment S.

c. Shut down the ESOP when H2 pressure reaches 0 psig.

6. Directs PRO to perform T-261.

PRO

1. Verifies automatic operation of 4KV buses.

2. Recognizes failure of the E3 DG to start. (Event 6)

3. Recognizes failure of the E22 breaker to close. (Event 7)

4. Recognizes failure of DG cooling water to start. (Event 8)

5. Reports 4KV status to the CRS.

6. Contacts TSO and requests status of offsite power restoration.

7. Bypasses and restores Drywell Instrument Nitrogen.

8. Places the N2 backup bottles in service.

9. Directs EO to perform T-261, Placing the Backup Instrument Nitrogen Supply from the CAD Tank in Service.

14 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 6 Event

Description:

E3 DG Fails to Autostart Cause:

Failed contact in DG start circuit.

Effects:

E3 DG does not automatically start on a loss of power.

Time Position Applicant's Actions or Behavior PRO

1. Recognizes failure of the E3 DG to start.

2. Depresses the E3 DG Quick Start pushbutton.

3. Verifies E3 DG voltage and frequency rises.

4. Verifies the E32 and E33 breakers automatically close.

15 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 7 Event

Description:

E22 Breaker Fails to Auto-close Cause: Failed contact in the autoclose circuit Effects: E22 breaker does not automatically close when the E2 DG is running.

Time Position Applicant's Actions or Behavior PRO

1. Recognizes failure of the E22 breaker to automatically close.

2. Verifies no faults on the E22 bus.

3. Verifies both startup breakers are open.

4. Verifies E2 DG is up to speed and voltage.

5. Places the E22 breaker control switch to TRIP.

6. Places the E22 breaker sync switch to ON.

7. Manually closes the E22 breaker.

16 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 8 Event

Description:

DG Cooling Fails to Autostart Cause: Failed contact in the autostart circuit Effects: ESW and ECW pumps fail to start when the DGs are running.

Time Position Applicant's Actions or Behavior CT2 PRO

1. Recognizes failure of the A ESW Pump and ECW pump to start.

2. Manually starts either the A ESW Pump or the ECW pump.

17 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

3 Event No.: 9 Event

Description:

Steam Leak in Containment Cause: Break in the Main Steam Line piping in the drywell Effects: Rising containment pressure and temperature Time Position Applicant's Actions or Behavior URO

1. Recognize and report rising drywell pressure.

2. Updates and enters OT-101, High Drywell Pressure.

CRS

1. Updates and enters T-102, Primary Containment Control.

2. Directs URO to lower RPV pressure to 500-600 psig.

3. Directs PRO to spray the Torus per T-204, Initiation of Containment Sprays using RHR.

4. Verifies position on the DW Spray Initiation Limit curve.

5. Directs PRO to spray the drywell.

URO

1. Operates SRVs to lower RPV pressure to 500-600 psig.

CT3 PRO

1. Performs T-204 as follows:

a. Places keylock switch 10A-S18A, Ctmt Spray Override 2/3 Core Coverage in Manual Overrd. (Step 4.4.3)

b. Momentarily places 10A-S17A, Ctmt Spray Vlv Cont, switch in MAN. (Step 4.4.4)

c. Shuts down one RHR pump. (Step 4.4.5)

d. Closes MO-2-10-034A(B), Full Flow Test. (Step 4.4.13.1)

e. Throttles open MO-2-10-038A(B), Torus Spray. (Step 4.4.13.2)

f. Verifies both Recirc Pumps are tripped and all Drywell Cooling Fan switches in OFF. (Step 4.4.14.1)

g. Opens MO-2-10-031A(B), D/W Spray Inboard. (Step 4.4.14.2)

h. Opens MO-2-10-026A(B), D/W Spray Outboard. (Step 4.4.14.3)

i. Adjusts flow to maintain drywell pressure between 3-5 psig. (Step 4.4.16)

18 TERMINATION CRITERIA:

The scenario may be terminated when RPV water level is being controlled in the established control band and drywell sprays are in service.

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #4 Form 3.3-1 Rev 0 Simulation Facility PBAPS Scenario No. #4 Op Test No. 2022 NRC Exam Scenario Source NEW Examiners Operator ________________ CRS (SRO)

________________ URO (ATC)

________________ PRO (BOP)

Initial Conditions IC-14 95% Power Turnover Unit 2 is at 95% power.

B APRM is bypassed due to a power supply failure.

Critical Tasks Critical Task 1: Initiate ARI to shut down the reactor within 5 minutes of ATWS conditions.

Critical Task 2: Commence flooding the RPV within 10 minutes of normal indications of RPV water level are lost.

Event No.

Malfunction No.

Event Type*

Event Description 1

See Scenario Guide N

PRO CRS APRM Scram Margin Check 2

See Scenario Guide R

URO CRS Raise Reactor Power to 100% with Recirc 3

See Scenario Guide TS CRS CRD Accumulator Failure 4

See Scenario Guide C

URO CRS High Vibes on an RFP 5

See Scenario Guide C

TS PRO CRS Earthquake/Core Spray A Loop Rupture 6

See Scenario Guide C

PRO CRS Service Water Pump Trip 7

See Scenario Guide C URO CRS Loss of Feedwater Heating

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #4 Form 3.3-1 Rev 0 8

See Scenario Guide M

ALL Thermal Hydraulic Instabilities 9

See Scenario Guide I

URO CRS ATWS 10 See Scenario Guide C

ALL CRS Aftershock/Loss of Level Indication

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec

Form 3.3-1 Scenario Outline 2022 NRC Exam Scenario #4 Form 3.3-1 Rev 0 Scenario Summary The scenario begins with the reactor at 95% power. The B APRM is bypassed due to a failed circuit.

Following shift turnover, the crew will perform an APRM Scram Margin Check per SO 60A.7.C-2.

Once the scram margin check is complete, the crew will raise reactor power to 100% using recirc speed.

While recirc speed is being raised, a control rod accumulator low pressure alarm will come in. The CRS will declare the accumulator inoperable per T.S. 3.1.5.A.

Once the Technical Specification has been declared, the crew will experience high vibrations on the A Reactor Feedwater Pump. The crew will monitor vibrations levels and remove the A RFP from service per SO 6D.2.A-2.

Once the A RFP is out of service, an earthquake will occur. The earthquake will cause a rupture in the A Core Spray room. The crew will also enter T-103, Secondary Containment Control, and isolate the A Core Spray loop to stop the rupture. The CRS will declare the A Core Spray loop inoperable per T.S. 3.5.1.A.

Once the Technical Specification has been declared, the A Service Water Pump will trip. The crew will enter ON-127, Loss of Service Water, and place the C Service Water Pump in service.

Once the C Service Water Pump is in service, a loss of feedwater heating will occur. The crew will enter OT-104, Positive Reactivity Addition, and lower reactor power to the pre-transient level. Thermal hydraulic instabilities will begin to occur and continue to worsen, requiring the crew to scram the reactor.

When the reactor is scrammed, rods will fail to insert. The crew will enter T-117, ATWS RPV control and the URO will initiate ARI. ARI will be successful in fully inserting the control rods.

As the crew are taking their scram actions, an aftershock will occur, which will cause a rupture of the level instrument lines for RPV Water Level. The crew will enter T-116, RPV Flooding, and T-112, RPV Blowdown. Once the RPV is blown down, the crew will initiate injection to raise RPV water level to the Main Steam Lines.

The scenario may be terminated when RPV water level is being raised to the Main Steam Lines.

1 SIMULATOR OPERATOR INSTRUCTIONS FOR 2022 NRC SCENARIO #4 GENERAL REQUIREMENTS

Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY

This scenario is a new scenario written for the 2022 NRC exam.

INITIAL SETUP Initial Conditions

Reset to IC-14, 100% power

Lower reactor power to 95%.

Bypass APRM B.

Ensure recorder power is on; roll recorders as required

Ensure annunciator horns are active Blocking Tags

None Event Triggers

None

2 Malfunctions TRG 1

CRH054635, Control Rod (46-35) Accumulator Trouble TRG 2

MFS02A, Reactor Feedwater Pump A High Vibration - 50%, 20 Min Ramp TRG 3

CSS02C, CS Pmp C Disch Line Brk after the Chk Vlv - 20%

TRG 4

SWS01A, Service Water Pump A Trip TRG 5

ESD01G, Loss of Extraction Steam to Htr A5

ESD01D, Loss of Extraction Steam to Htr A4

RRS24B, Thermal Hydraulic Instabilities in Phase - 50%, 10 Min Ramp, 5 Min Delay TRG 6

RVI08A, Reference Line Break Wide Range Level - 100%

RVI08B, Reference Line Break Wide Range Level - 100%

RVI09A, Reference Line Break Narrow Range Level - 100%

RVI09B, Reference Line Break Narrow Range Level - 100%

RVI10, Reference Line Break Refuel Range Level - 100%

Overrides TRG 3

ANO309LF2, Blank - ALARM_ON

ANO309LG2, Blank-ALARM_ON Trip Overrides INSERTED

RPS01TO, RPS Auto Scram Ch. A1 - OVERRIDE

RPS02TO, RPS Auto Scram Ch. A2 - OVERRIDE

RPS03TO, RPS Auto Scram Ch. B1 - OVERRIDE

RPS04TO, RPS Auto Scram Ch. B2 - OVERRIDE

RPS05TO, RPS Manual Scram Ch. A3 - OVERRIDE

RPS06TO, RPS Manual Scram Ch. B3 - OVERRIDE Remote Functions TRG 7

CSS06A, Core Spray Pump A Control Power Fuse - REMOVED

CSS06C, Core Spray Pump C Control Power Fuse - REMOVED, 1 Min Delay Turnover Procedures SO 60A.7.C-2, APRM Scram Margin Check

3 SIMULATOR OPERATOR DIRECTIONS EVENT 1 APRM Scram Margin Check Support the crew as necessary for the APRM Scram Margin Check.

EVENT 2 Raise Reactor Power to 100%

Support the crew as necessary for raising reactor power.

EVENT 3 CRD Accumulator 46-35 Low Pressure When directed by the Lead Examiner, insert TRG 1 and verify that the following event activates:

CRH054635, Control Rod (46-35) Accumulator Trouble When directed to investigate the accumulator alarm on control rod 46-35, wait 3 minutes and report the alarm is due to low pressure. If asked, accumulator pressure is 900 psig.

EVENT 4 High Vibrations on the A RFP When directed by the Lead Examiner, insert TRG 2 and verify the following event activates:

MFS02A, Reactor Feedwater Pump A High Vibration - 50%, 20 Min Ramp When directed to investigate high vibrations on the A RFP, wait 3 minutes and report the feedwater pump is making abnormal noise.

4 EVENT 5 Earthquake/Core Spray A Loop Rupture At the direction of the Lead Examiner, insert TRG 3 and verify the following events activate:

ANO309LF2, Blank - ALARM_ON

ANO309LG2, Blank-ALARM_ON

CSS02C, CS Pmp C Disch Line Brk after the Chk Vlv - 20%

When directed to walk down plant equipment, acknowledge the direction.

When directed to check alarms in the Cable Spread Room, wait 2 minutes and report multiple yellow triggered lights are lit and the red OBE light is lit.

When directed to reset the alarms, delete the following overrides and reload them under TRG 6:

ANO309LF2, Blank - ALARM_ON

ANO309LG2, Blank-ALARM_ON When directed to investigate high water level in the C Core Spray Pump room, wait 2 minutes and report a rupture downstream of the C Core Spray Pump.

If directed to check the leak rate after the rupture is isolated, wait 1 minute and report the leak is isolated.

If directed to remove the control power fuses for the A and C Core Spray pumps, wait 2 minutes and insert TRG 7 and verify the following events activate:

CSS06A, Core Spray Pump A Control Power Fuse - REMOVED

CSS06C, Core Spray Pump C Control Power Fuse - REMOVED, 1 Min Delay

5 EVENT 6 A Service Water Pump Trip When directed by the Lead Examiner, insert TRG 4 and verify the following event activates:

SWS01A, Service Water Pump A Trip If directed to investigate the trip of the A Service Water Pump, wait 2 minutes and report the pump tripped on overcurrent.

When directed to perform steps 4.2.3 and 4.2.4 of SO 30.1.A-2, wait 2 minutes and report the valves are open.

When directed to report Service Water Pump discharge pressure, report pressure is approximately 75 psig.

If directed to investigate the Generator Stator Coolant/Hydrogen Seal Oil trouble alarm, wait 4 minutes and report that the Machine Gas High Temperature alarm is in (or was in and is now reset if the C Service Water Pump has been started).

EVENT 7/8 Loss of Feedwater Heating/Thermal Hydraulic Instabilities When directed by the Lead Evaluator, insert TRG 5 and verify the following events activate:

ESD01G, Loss of Extraction Steam to Htr A5

ESD01D, Loss of Extraction Steam to Htr A4

RRS24B, Thermal Hydraulic Instabilities in Phase - 50%, 10 Min Ramp, 5 Min Delay If directed to investigate loss of feedwater heating, wait 3 minutes and report no obvious signs of why the heater tripped.

EVENT 9 ATWS

6 EVENT 10 Aftershock/Loss of Level Indication When directed by the Lead Evaluator, insert TRG 6 and verify the following events activate:

ANO309LF2, Blank - ALARM_ON

ANO309LG2, Blank-ALARM_ON

RVI08A, Reference Line Break Wide Range Level - 100%

RVI08B, Reference Line Break Wide Range Level - 100%

RVI09A, Reference Line Break Narrow Range Level - 100%

RVI09A, Reference Line Break Narrow Range Level - 100%

RVI10, Reference Line Break Refuel Range Level - 100%

If directed to perform T-247, wait 4 minutes and insert Remote Function T247 TERMINATION The scenario may be terminated when RPV water level is being raised to the Main Steam Lines.

7 SHIFT TURNOVER PLANT CONDITIONS:

A Unit 2 is operating at 95% power.

B APRM is bypassed due to a failed circuit.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

APRM Scram Margin Check per SO 60A.7.C-2.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

None GENERAL INFORMATION:

None

8 CRITICAL TASK LIST

1.

Initiate ARI to shut down the reactor within 5 minutes of ATWS conditions.

a. Safety Significance - Failure to initiate ARI will result in localized power peaking and damage to the fuel cladding.

b. Cue - Reactor scram initiated and control rods not fully inserted.

c. Measurable Performance Indicators - Arms and depresses the ARI pushbuttons.

d. Performance Feedback - Scram air header depressurizing and control rods inserting.

2.

Commence flooding the RPV within 10 minutes of normal indications of RPV water level are lost.

a. Safety Significance - Failure to flood the RPV will result in a loss of adequate core cooling and possible damage to the fuel cladding.

b. Cue - Loss of all level indications.

c. Measurable Performance Indicators - Performing an RPV blowdown and maximizing injection into the RPV.

d. Performance Feedback - RPV pressure rising and SRV tailpipe temperatures lowering.

9 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 1 Event

Description:

APRM Scram Margin Check Cause:

N/A Effects:

N/A Time Position Applicant's Actions or Behavior CRS

1. Direct the PRO to perform SO 60A.7.C, APRM Scram Margin Check.

PRO

1. At each APRM NUMAC Display:

a. Depresses the ETC softkey. (Step 4.1.1)

b. Depress the Show Parameters softkey. (Step 4.1.2)

c. Records the values of STP Upscale Trip on Data Sheet

1. (Step 4.1.3)

d. Depresses Exit softkey. (Step 4.1.4)

e. Records STP (%) value on Data Sheet 1. (Step 4.1.5)

f. Repeat the above steps for the remaining APRM channels. (Step 4.1.6)

g. Subtract the current APRM STP from the STP Upscale Trip value and record on Data Sheet 1 under Scram Margin. (Step 4.3)

10 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.:

2 Event

Description:

Raise Reactor Power to 100%

Cause:

N/A Effects:

N/A Time Position Applicant's Actions or Behavior CRS

1. Directs URO to raise reactor power to 100% per the Standing ReMA.

URO

1. Depresses the Raise pushbuttons for the A and B Recirc Pumps to raise reactor power.

PRO

1. Provides peer checks for power manipulation.

11 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.:

3 Event

Description:

CRD Accumulator 46-35 Low Pressure Cause:

Nitrogen leak from the accumulator.

Effects:

Slower scram time for the associated control rod.

Time Position Applicant's Actions or Behavior URO

1. Recognize and report alarm 211 E-2, CRD Accumulator Lo-Press Hi Level, is in.

2. Reports control rod 46-35 accumulator alarm is lit.

TS CRS

1. Acknowledges report.

2. Determines an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months LCO is required per T.S. 3.1.5, Condition A.

PRO

1. Dispatches EO to investigate accumulator 46-35.

12 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.:

4 Event

Description:

High Vibrations on the A RFP.

Cause:

Misalignment of the Turbine/Pump Flex coupling.

Effects:

Rising feedwater pump/turbine vibrations.

Time Position Applicant's Actions or Behavior PRO

1. Recognize and report alarm 202 E-1, A RFP/T Vibration High, is in.

2. Checks feedwater pump vibrations on the PPC.

3. Reports A Feedwater Pump vibrations are rising.

4. Dispatches EO to investigate high vibrations on the A RFPT.

5. Reports vibrations have exceeded 5 mils. (Step 5)

CRS

1. Directs URO to perform GP-9 to lower reactor power to attempt to lower vibrations. (Step 4)

2. Directs URO to rapidly shutdown the A RFP per SO 6D.2.A, Reactor Feedwater Pump Shutdown. (Step 5 of ARC 202 E-1 and Step 4.2 of SO 6D.2.A-2)

URO

1. Lowers recirc pump speed until feedwater flow is less than 14 Mlbm/hr. (Step 4)

2. Opens AO2139A, Feed Pump A Recirc. (Step 4.3.1)

3. Closes AO-2147A, Feed Pump A Check. (Step 4.3.2)

4. Places the A RFP M/A station in Manual. (Step 4.3.3)

5. Closes MO-2149A, Feed Pump A Disch. (Step 4.3.4)

6. Verifies M/A station output is set to 2600-2900 RPM. (Step 4.7.1)

7. Emergency stops the A RFP. (Step 4.7.2)

8. Trips the A RFP when speed is at minimum. (Step 4.7.3)

9. Reports completion to the CRS.

13 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 5 Event

Description:

Earthquake/Core Spray A Loop Rupture Cause:

Seismic Activity Effects:

Lowering Torus water level and rising water level in CS A pump room.

Time Position Applicant's Actions or Behavior PRO

1. Recognize and report alarms 319 F-2, SMS System Triggered, and 319 G-2, Operating Basis Earthquake Exceeded, are in.

2. Dispatches EO to investigate alarms in the Cable Spread Room.

CRS

1. Updates and enters SE-5, Earthquake.

2. Directs PRO to dispatch operators to walk down plant equipment.

PRO

1. Dispatches EOs to walk down plant equipment.

2. Recognize and reports alarm 224 A-4, A Core Spray Line Vent Accumulator Low Level, is in

3. Recognize and reports alarm 224 A-5, C Core Spray Pump Room Flood, is in.

4. Updates and enters T-103, Secondary Containment Control.

5. Dispatches EO to investigate high water level in the C Core Spray Pump Room.

TS CRS

1. Acknowledge the report.

2. Directs PRO to isolate the A Core Spray Loop.

3. Directs PRO to remove UT fuses for the A and C Core Spray Pumps.

4. Determines a 7 day LCO is required per T.S. 3.5.1, Condition A.

PRO

1. Obtains keys for Core Spray suction valves.

2. Closes MO-2-14-007A and C.

3. Dispatches EO to remove A and C Core Spray UT fuses.

14 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 6 Event

Description:

A Service Water Pump Trip Cause:

Overcurrent trip Effects:

Rising RBCCW and TBCCW temperatures Time Position Applicant's Actions or Behavior PRO

1. Recognize and reports alarms 216 F-1, Service Water Header Lo Press, 216 G-1, A Service Water Pump Trip, and 216 G-2, A Service Water Pump Ovld, are in.

2. Updates and enters ON-127, Loss of Service Water.

CRS

1. Acknowledges the report.

2. Directs PRO to start the C Service Water Pump per SO 30.1.A, Unit 2 Service Water System Normal Operations.

PRO

1. Directs EO to perform steps 4.2.3 and 4.2.4 for the C Service Water Pump.

2. Starts the C Service Water Pump. (Step 4.2.5)

3. Verifies current is between 23 and 28 amps. (Step 4.2.5)

4. Verifies discharge pressure is between 65 and 95 psig. (Step 4.2.6)

5. Directs an EO to verify discharge pressure is between 65 and 95 psig. (Step 4.2.7)

6. Reports completion to the CRS.

15 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 7/8 Event

Description:

Loss of Feedwater Heating/Thermal Hydraulic Instabilities Cause: Air line break in extraction steam valves Effects: Lowering feedwater temperature and oscillating reactor power.

Time Position Applicant's Actions or Behavior PRO

1. Recognize and reports loss of the A5 feedwater heater.

2. Updates and enters OT-104, Positive Reactivity Addition.

CRS

1. Directs URO to maintain reactor power below pre-transient level. (Step 2.1)

2. Plots position on the Power/Flow map.

3. If operating in the MELLLA+ region, then directs insertion of GP-9 control rods as necessary to exit the MELLLA+ region.

4. If operating outside the analyzed region, then directs insertion of GP-9 control rods as necessary to maintain power within the analyzed region.

URO

1. Reduces Recirc Flow as necessary to main reactor power below pre-transient level.

2. Inserts GP-9 control rods as directed.

3. Recognizes and reports indications of THI.

4. Reports THI is getting worse and rod insertion has no effect.

CRS

1. Acknowledges report.

2. Directs ROs to perform a GP-4 Shutdown.

16 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 9 Event

Description:

ATWS Cause: Failure of the Auto and Manual scram circuit Effects: Control rods do not insert.

Time Position Applicant's Actions or Behavior URO

1. Depresses the Scram pushbuttons and places the Mode Switch in Shutdown.

2. Reports the following:

a. Mode Switch is in SHUTDOWN.

b. Control rods are NOT inserting.

c. APRMS are NOT downscale.

CRS

1. Updates and enters T-101, RPV Control, and T-117, ATWS RPV Control.

2. Directs ROs to perform ATWS Rapid Response Cards.

CT1 URO

1. Arms and depresses ARI pushbuttons. (Step 3)

2. Recognize and report lowering scram air header pressure.

3. Reports control rods are inserting and APRMs are downscale.

CRS

1. Updates and exits T-117, and re-enters T-101.

2. Directs ROs to perform normal scram actions.

3. Directs URO to maintain +5-+35 RPV water level with feedwater and 800-1000 psig reactor pressure with EHC.

URO

1. Performs Reactor Operator Scram Actions RRC as follows:

a. Emergency stops all feedwater pumps. (Step 5)

b. Closes all feedwater pump discharge valves. (Step 6)

c. Opens C RFP discharge bypass valve. (Step 7)

d. Verifies all control rods are inserted. (Step 10)

e. Verifies Scram Discharge Volume vents and drains are closed. (Step 11)

f. Operates feedwater to maintain RPV water level.

17 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 9 Event

Description:

ATWS cont.

Time Position Applicant's Actions or Behavior PRO

1. Performs PRO Scram Actions RRC as follows:

a. Transfers house loads to offsite power. (Step 1)

b. Trips the Main Turbine when loading is < 50MW. (Step 2)

c. Verify Main Generator is locked out. (Step 3)

d. Starts all Main Turbine Bearing Lift Pumps. (Step 4)

e. Verifies Group II/III isolations. (Step 5)

f. Verifies HWC has tripped. (Step 6)

URO

1. Reports the Scram Report as follows:

a. RPV water level, trend, and status of feedwater.

b. RPV pressure, trend, and the status of EHC.

c. All control rods are inserted.

d. Scram Discharge Volume Vents and Drains are closed.

e. Mode Switch is in Shutdown.

PRO

1. Reports the Scram Report as follows:

a. House Loads are transferred.

b. Main Turbine is tripped.

c. Main Generator is locked out.

d. Group I, II, and III isolations are complete and SBGTS is initiated.

e. Hydrogen Water Chemistry is isolated.

f. Recirc Pump speed is 30%.

g. Instrument Air Header pressure is greater than drywell pressure.

2. Bypasses and restores Drywell Instrument Nitrogen as follows:

a. Places AO-2969A and B control switches to CLOSE.

b. Places D/W Inst. N2 Bypass switches in BYPASS.

c. Places AO-2969A and B control switches to Auto/Open.

CRS

1. Acknowledges the scram reports.

2. Directs PRO to bypass and restore Drywell Instrument Nitrogen.

18 Operator Actions Form 3.3-2 Op Test No.:

1 Scenario No.:

4 Event No.: 10 Event

Description:

Aftershock/Loss of Level Indication Cause: Aftershock Effects: Loss of all level indication Time Position Applicant's Actions or Behavior PRO

1. Recognize and report alarms 319 F-2, SMS System Triggered, and 319 G-2, Operating Basis Earthquake Exceeded, are in.

URO

1. Recognize and report loss of all level indication.

CRS

1. Updates and enters T-116, RPV Flooding.

2. Verifies Torus water level is above 7.

3. Directs URO to open all ADS valves.

4. Directs URO to inject with low pressure systems to flood the RPV.

5. Directs PRO to close the following valves:

a. MSIVs

b. HPCI and RCIC Steam Isolation Valves

c. Main Steam Line drains.

PRO

1. Closes the MSIVs and Main Steam Line drains.

2. Closes the HPCI and RCIC Steam Isolation Valves.

CT2 URO

1. Opens all ADS valves.

2. Injects with RHR/Core Spray/Condensate to flood the RPV.

3. Verifies the RPV is flooded by the following:

a. SRV tailpipe temperatures lowering

b. Torus water level stabilizing TERMINATION CRITERIA:

The scenario may be terminated when RPV water level is being raised to the Main Steam Lines.

Form 3.2-1 Administrative Topics Outline Facility: PBAPS Date of Examination: May 2022 Examination Level:

RO X

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

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations G2.1.20 (4.6), Perform Daily Jet Pump Operability Surveillance (PLOR-264C)

R/M Conduct of Operations G2.1.18 (3.8), SBGT JPM (PLOR-NEW)

R/N Equipment Control G2.2.22 (4.0), Review Reactor Vessel Temperatures during a Cooldown (PLOR-NEW)

R/N Radiation Control N/A Emergency Plan G2.4.39 (3.9), Perform State/Local Event Notification (PLOR-NEW)

S/N

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

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)

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).

Form 3.2-1 Administrative Topics Outline Facility: PBAPS Date of Examination: May 2022 Examination Level:

RO SRO X

Operating Test Number: 1 Administrative Topic (Step 1)

Activity and Associated K/A (Step 2)

Type Code (Step 3)

Conduct of Operations G2.1.19 (3.8), Compensatory Actions for an Inoperable Fire Door (PLOR-273C)

R/M Conduct of Operations G2.1.5 (3.9), Evaluate Overtime Work Request (PLOR-279C)

R/D Equipment Control G2.2.23 (4.6), Complete Tech Spec Log Entries (PLOR-206C)

R/M Radiation Control G2.3.6 (3.8), Evaluate Liquid Radwaste Discharge Paperwork (PLOR-265C)

R/D Emergency Plan G2.4.41 (4.6), EAL Classification and State/Local Notifications (PLOR-XXXC)

R/N

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

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)

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).

Form 3.2-2 Control Room/In-Plant Systems Outline Facility: PBAPS Date of Examination: May 2022 Operating Test Number: 1 Exam Level: X RO X SRO-I X SRO-U System/JPM Title Type Code Safety Function Control Room Systems

a. 211000 A3.06 (4.1), Inject Boron into the RPV (Alt Path - RWCU Fails to Isolate) (PLOR-301CA)

A/D/EN/S 1

b. 295001 A4.02 (4.0), S/D the A RFP Turbine (Alt Path -

Min Flow Valve Fails Closed) (PLOR-303CA)

A/D/S 2

c. 295025 EA1.04 (3.6), S/U HPCI in the CST-CST Mode (Alt Path - High Oil Temp) (PLOR-NEW)

A/D/EN/L/S 3

d. 203000 A4.02 (4.2/4.2), Place the 2B RHR HX Cross-Tie in Service (Alt Path - B/U Power Supply Reqd)

A/D/EN/L/S 4

e. (RO ONLY) 223001 A4.10 (3.5), CAD System N2 Addition to PC during Normal Operations (PLOR-034C)

D/S 5

f. 295003 AA1.02 (4.5), Diesel Generator Lockout from the Control Room (PLOR-113C)

D/EN/L/S 6

g. 201006 A4.07 (3.3), Inputting an INOP Control Rod in the RWM (PLOR-NEW)

N/S 7

h. 271000 A4.09 (3.0), Restore SJAE Supply Pressure to Normal (Alt Path - Control Valve Fails) (PLOR-NEW)

A/N/S 9

In-Plant Systems

i. 201001 A2.07 (4.0/3.6), Place the Alternate CRD Flow Control Valve in Service (PLOR-NEW)

E/N/R 1

j. 295031 EA 1.08 (3.9), Defeating HPCI and RCIC High Level Trip Signals (T-229-3) (PLOR-238P)

D/E/R 2

k. 295018 AA1.01 (3.3), Loss of RBCCW (Plant Actions for the Inst N2 System) (PLOR-096P)

D/E/R 8

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.

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

Code License Level Criteria RO SRO-I SRO-U (A)lternate path (RO/SRO-I 5) (SRO-U 3) 4-6 4-6 2-3 (C)ontrol room (D)irect from bank (RO/SRO-I 8) (SRO-U 4) 9 8

4 (E)mergency or abnormal in-plant (RO/SRO-I

3) (SRO-U 2) 1 1

1 (EN)gineered safety feature (for control room system) (RO/SRO-I 4) (SRO-U 2) 1 1

1 (L)ow power/shutdown (RO/SRO-I 3) (SRO-U

1) 1 1

1 (N)ew or (M)odified from bank (must apply to at least one alternate path JPM) (RO/SRO-I

3) (SRO-U 1) 2 2

1 (P)revious two exams (randomly selected) (0) 3 3

2 (R)adiologically controlled area (3) 1 1

1 (S)imulator (8)

v t e Letter Sequence Other
EPID:L-2022-OLL-0004, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML22206A258, ML22206A264, ML22206A269, ML22235A720, ML22242A260, ML22243A107, ML22243A229, ML22250A683, ML22299A010, ML22299A100
MONTHYEAR2022-05-16 [Table View]

ML22243A229

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