Text

Draft Operating Test (Section a, Section B, Section C) (Folder 2)
	ML20296A430
Person / Time
Site:	Salem
Issue date:	10/22/2020
From:	Peter Ott; Operations Branch I
To:	; Public Service Enterprise Group
Shared Package
ML19105A168	List: ML19211C255; ML20176A296; ML20240A318; ML20240A322; ML20296A430; ML20296A432; ML20297A279; ML20297A306; ML20300A556; ML20301A632; ML21012A270;
References
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	Download: ML20296A430 (472)
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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Admin - Conduct of Operations TASK: Calculate Shutdown Margin IAW SC.RE-ST.ZZ-0002 TASK NUMBER: N1200030301 JPM NUMBER: 19-01 NRC RO-A1 ALTERNATE PATH: K/A NUMBER: 2.1.43 IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Classroom / Perform

REFERENCES:

SC.RE-ST.ZZ-0002(Q), Rev. 23 SHUTDOWN MARGIN CALCULATION S2.RE-RA.ZZ-0016(Q), Rev. 11 CURVE BOOK (both checked 1-14-20)

TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 60 minutes Developed By: R. Chan Date: 1-14-20 Instructor Validated By: Klein / Weidner Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 INITIAL CONDITIONS:

Unit 2 Reactor Power is 100%.

All Control Rod Group Demand Counters are at 225 steps.

Current boron concentration is 300 ppm.

Current core burnup is 10,000 EFPH.

Control Rod 1D5 was been declared INOPERABLE at 1000 today due to not moving out during a rod exercise test.

You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3 for a misaligned rod.

Control Rod 1D5 has been identified as trippable and is currently at 214 steps.

INITIATING CUE:

You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 Attachment 3 to satisfy the one (1) hour action requirement of TSAS 3.1.3.1 Action c.3 to verify Shutdown Margin requirements is satisfied.

When performing calculation, the CRS directs you to use only the tables as directed by SC.RE-ST.ZZ-0002, do not use Figures.

This is a Time Critical JPM.

Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Perform SDM calculation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and determines SDM of -2398 (+/- 5 pcm) is satisfactory.

Page 2 of 15

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Obtains copy of procedure SC.RE- Provide Rev. 23 of surveillance.

ST.ZZ-0002(Q).

Obtains copy of S2.RE-RA.ZZ-0016 Curve Book. Provide Rev. 11 of Curve Book.

CUE: When the operator acknowledges ready to start JPM RECORD START TIME.

START:________________

3.0 Reviews and signs off Precautions and Reviews Precautions & Limitations and Limitations Section 3.0 signs off Steps 3.1 - 3.7.

5.1 SELECT the applicable step below (e.g. Determines 5.1.1.C is the correct step 5.1.1.A): for the current conditions, which is to complete Attachment 3.

5.1.1.C IF SDM is to be verified (per T/S Refers to Attachment 3.

4.1.1.1.1.a) with reactor critical (Mode 1 or 2) and one or more control rods are inoperable, THEN COMPLETE Attachment 3.

Att. 3 The reactor is in Mode 1 or Mode 2 Determines Unit is in Mode 1.

with keff > 1.0 2.1 Page 3 of 15

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Att. 3 Precautions and Limitations: Section Reviews and signs steps 3.1-3.5.

3.0 3.0

Section Critical Conditions Determines the following data and

4.1 calculations

4.1.1 100%

4.1.2 300 ppm 4.1.3 D @ 225 steps 4.1.4 10,000 EFPH 4.1.5 0 4.1.6 1

Section Calculation of Rod Worth 4.2.1 -3697 4.2 4.2.2 -3581 4.2.3 920 4.2.4 0 4.2.5 500 4.2.6 0 4.2.7 -5858

Section Calculation of SDM 4.3.1 -5858 4.3 4.3.2 636 4.3.3 120 4.3.4 2704 4.3.5 -2398 Page 4 of 15

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation) 4.4 Acceptance Criteria Reviews required SDM in MODE 1 or 2 of -1300 pcm and initials 4.4.1.

4.4.1 IS THE SDM (Item 4.3.5) EQUAL TO OR MORE NEGATIVE THAN Determines calculated SDM is SAT

(-)1300 PCM? and initials SAT.

Evaluator Note: See Answer Key for completed Attachment 3 CUE MARK stop time of JPM when JPM is Complete when operator procedures are returned to proctor. submits Attachment to Evaluator.

STOP:___________________

Page 5 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 6 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 7 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 8 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 9 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 10 of 15

Page 11 of 15 Page 12 of 15 Page 13 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 14 of 15

INITIAL CONDITIONS:

Unit 2 Reactor Power is 100%.

All Control Rod Group Demand Counters are at 225 steps.

Current boron concentration is 300 ppm.

Current core burnup is 10,000 EFPH.

Control Rod 1D5 was been declared INOPERABLE at 1000 today due to not moving out during a rod exercise test.

You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3 for a misaligned rod.

Control Rod 1D5 has been identified as trippable and is currently at 214 steps.

INITIATING CUE:

You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 Attachment 3 to satisfy the one (1) hour action requirement of TSAS 3.1.3.1 Action c.3 to verify Shutdown Margin requirements is satisfied.

When performing calculation, the CRS directs you to use only the tables as directed by SC.RE-ST.ZZ-0002, do not use Figures.

This is a Time Critical JPM.

Page 15 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topic - Conduct of Operations TASK: Verification of Active License Status TASK NUMBER: N1200030301 JPM NUMBER: 19-01 NRC RO-A2 ALTERNATE PATH: K/A NUMBER: 2.1.4 IMPORTANCE FACTOR: 3.3 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Classroom / Perform OP-AA-105-101, Rev 16 & OP-AA-105-102, Rev 12 (checked 1-15-20)

REFERENCES:

RP-AA-440, Rev 10 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NA Developed By: R. Chan Date: 1-15-20 Instructor Validated By: Klein / Weidner Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Generic Administrative Topic - Conduct of Operations TASK: Verification of Active License Status TASK NUMBER: N1200030301 INITIAL CONDITIONS:

Both Units are operating at 100% power.

Today is January 1, 2020.

You are the on-shift RO on Unit 1.

You must leave the shift.

There are three replacement operators that are available on-site.

INITIATING CUE:

Using the provided information, determine which of the three operators, if any, are qualified to relieve you IAW OP-AA-105-102, NRC Active License Maintenance and OP-AA-105-101, Administrative Process For NRC License and Medical Requirements.

Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Operator determines that RO #3 can relieve him.

2. Operator determines that RO#1 is not qualified due to not meeting the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shift hour requirement and RO#2 is not qualified due to not meeting license restrictions for wearing corrective lenses.

Page 2 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Verification of Active License Status

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

CUE Provide copies of the following procedures:

1. OP-AA-105-101

2. OP-AA-105-102

3. RP-AA-440 CUE: When the operator acknowledges ready to start JPM RECORD START TIME.

START:________________

1 Reviews RO #1 data and determines Determines that RO #1 is not eligibility for relief qualified to relieve the RO due to not having the minimum five 12-hour shifts per calendar quarter IAW OP-AA-105-102 section 4.1.1.1 (page 4).

2 Reviews RO #2 data and determines Determines that RO #2 is not eligibility for relief qualified to relieve the RO due to not having the required corrective lenses IAW NRC Form 396 medical form restriction for corrective lenses.

Page 3 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Verification of Active License Status

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

3 Reviews RO #2 data and determines Determines that RO #3 is qualified to eligibility for relief relieve the RO on Unit 1.

CUE MARK stop time of JPM when JPM is Complete when operator procedures are returned to proctor. submits Attachment to Evaluator.

STOP:___________________

Page 4 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 5 of 11

Page 6 of 11 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE ANSWER KEY Qualified for State reason if not qualified for relief.

Relief?

(Yes / No)

Does not having the minimum five 12-hour shifts per calendar quarter IAW OP-AA-105-102 section RO #1 4.1.1.1 (page 4).

NO Does not have the required corrective lenses IAW NRC Form 396 medical form restriction for corrective lenses.

RO #2 NO Meets all requirements.

RO #3 YES ANSWER KEY Page 7 of 11

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 8 of 11

INITIAL CONDITIONS:

Both Units are operating at 100% power.

Today is January 1, 2020.

You are the on-shift RO on Unit 1.

You must leave the shift.

There are three replacement operators that are available on-site.

INITIATING CUE:

Using the provided information, determine which of the three operators, if any, are qualified to relieve you IAW OP-AA-105-102, NRC Active License Maintenance and OP-AA-105-101, Administrative Process For NRC License and Medical Requirements.

Qualified for State reason if not qualified for relief.

Relief?

(Yes / No)

RO #1 RO #2 RO #3 Page 9 of 11

Record of Shifts Performed During Fourth Quarter 2019:

Date Shift Position No. Hours Comments 11/2/19 Unit 2 RO 0600-1800 11/3/19 Unit 2 PO 0600-1800 11/4/19 Unit 2 RO 0600-1800 Attended All Hands meeting at Processing Center for RO#1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , then attended Unit 2 Outage planning meeting in B Bldg for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

11/5/19 Unit 2 PO 0600-1800 12/24/19 Unit 1 RO 0600-1800 10/7/19 Unit 1 RO 0600-1800 10/8/19 Unit 1 PO 0600-1800 RO #2 10/9/19 Unit 2 PO 0600-1800 10/10/19 Unit 2 PO 0600-1800 11/28/19 Unit 2 PO 0600-1800 10/18/19 Unit 1 RO 0600-1800 10/19/19 WCC NCO 0600-1800 10/20/19 Unit 2 PO 0600-1800 RO #3 11/28/19 Unit 2 RO 0600-1800 11/29/19 Unit 2 PO 0600-1800 12/25/19 Unit 1 PO 0600-1800 Page 10 of 11

Additional Information:

Status of Date of Date of Most Date of most Recent NRC Comments Requalification Training Last Recent Form 396 on File SCBA Respiratory Mask Fit Examination (Biennial Medical Exam)

Test on File All requirements of TQ-AA-106, Licensed RO #1 Operator Requal Training 11/18/19 11/18/19 10/10/19 Program, are up to date and satisfactorily Restrictions: None completed.

All requirements of TQ- RO stated that he left his AA-106, Licensed prescription eye glasses at Operator Requal Training home.

RO #2 Program, are up to date 7/1/19 7/1/19 7/1/19 and satisfactorily completed. Restrictions: Corrective lenses shall be worn when performing licensed duties.

All requirements of TQ- RO stated that he has his AA-106, Licensed blood pressure medication with RO #3 Operator Requal Training 4/9/19 4/9/19 9/15/19 him and has taken the Program, are up to date prescribed dosage for the day.

and satisfactorily Restrictions: Shall take completed. medication as prescribed to maintain medical qualifications.

Page 11 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topic - Equipment Control TASK: Identify Components to Isolate a Service Water System Leak Using Station Drawings TASK NUMBER: N1220050302 JPM NUMBER: 19-01 NRC RO-A3 ALTERNATE PATH: K/A NUMBER: 2.2.41 IMPORTANCE FACTOR: 3.5 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Classroom / Perform

REFERENCES:

205342 Sheets 1 thru 7 (checked 1-15-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-15-20 Instructor Validated By: Klein / Weidner Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC RO-A3 Rev # Date Description Validation Required 00 7-30-19 NEW JPM for 19-01 NRC ILOT Exam. Yes K/A 2.2.41: Ability to obtain and interpret station electrical and mechanical drawings. RO 3.5 / SRO 3.9 Page 2 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Generic Administrative Topic - Equipment Control TASK: Identify Components to Isolate a Service Water System Leak Using Station Drawings TASK NUMBER: N1220050302 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

1. PROVIDE clean copies of P&ID drawing 205342 sheets 1 thru 7.

2. PROVIDE highlighter or marker.

Page 3 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Generic Administrative Topic - Equipment Control TASK: Identify Components to Isolate a Service Water System Leak Using Station Drawings TASK NUMBER: N1220050302 INITIAL CONDITIONS:

Unit 2 is in a Refueling outage with the reactor defueled.

A Service Water leak has been identified by your field operator on a 2 inch drain valve (21SW268) near the 21SW76 valve inside the SW Valve Room, Auxiliary Building.

The 21SW76 is a manual isolation valve for the SW outlet of 21 CFCU.

The 21SW268, 21 NUC HDR FROM FCV DRAIN, is a 2 inch drain valve downstream of the 21SW76, 21 CFCU SW OUTLET VLV.

The field operator reports that the leak is at the body to bonnet location of the valve.

INITIATING CUE:

You are the Work Control NCO.

The Work Control SRO directs you to identify the minimum number of components needed to isolate the leak.

Drains and vents are NOT required to be identified at this point.

A complete work clearance (tagout) with all required blocking points will be performed in accordance with station procedures after leak isolation.

Assume check valves will function as designed with no leak-by.

Mark up (or circle components) on the provided P&ID drawings for the valves required to be closed and document your list of valves on this Cue Sheet:

SUCCESSFUL COMPLETION CRITERIA:

1. ALL critical steps completed

2. ALL sequential steps completed in order

3. ALL time-critical steps completed within the allotted time JPM completed within validated time.

Completion may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Page 4 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Task Standard for Successful Completion:

1. Operator identifies the following valves on drawing 205342 as a minimum to be closed to isolate leak:

21SW472 (sheet 3) 21SW355 (sheet 3) 21SW50 (sheet 3) 21SW414 (sheet 5) 21SW78 (sheet 6) 22SW76 (sheet 6) 21SW76 (sheet 6) 21SW646 (sheet 6) 22SW646 (sheet 6)

Optional Valves: These valves may be included but not necessary for leak isolation based on taking credit for check valve(s) preventing backflow:

- 21SW844 (sheet 3) check valves 21SW47 and 21SW79 upstream

- 21, 22, & 23SW45 (sheet 3) check valve 21SW79 downstream

2. Operator correctly marks up the required valves on the provided P&ID drawings (205342) IAW with the enclosed answer key within this JPM.

Page 5 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:_______________________

DATE:________________________

SYSTEM: Generic Administrative Topic - Equipment Control TASK: Identify Components to Isolate a Service Water System Leak Using Station Drawings STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for NO. (* Critical Step)

S/U UNSAT evaluation)

(# Sequential Critical Step)

- 1. Provide copy of drawing 205342 Sheets 1 thru 7.

2. Provide two (2) highlighters with different colors CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

Mark up (or circle components) the provided Using the P&IDs provided, the operator P&ID drawings for the valves required to be highlights or marks (e.g., circles valve) the closed. minimum valves to isolate (close) the leak.

Evaluators Note: Operator only needs to highlight the valves on the provided P&ID.

List the components needed to be closed to Operator identifies the following valves isolate the leak: needed to be closed:

21SW472 (sheet 3) 21SW355 (sheet 3) 21SW50 (sheet 3) 21SW414 (sheet 5) 21SW78 (sheet 6) 22SW76 (sheet 6) 21SW76 (sheet 6) 22SW646 (sheet 6) 21SW646 (sheet 6)

Page 6 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:_______________________

DATE:________________________

SYSTEM: Generic Administrative Topic - Equipment Control TASK: Identify Components to Isolate a Service Water System Leak Using Station Drawings STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for NO. (* Critical Step)

S/U UNSAT evaluation)

(# Sequential Critical Step)

CUE: WHEN operator informs you the task is Terminate JPM when operator submits the complete, OR the JPM has been terminated for Cue Sheet and P&ID drawings.

other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 7 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Valves on 205342 Sheet 3:

1. 21, 22, & 23SW45 (Note: optional)

2. 21SW50

3. 21SW844 (Note: Optional)

Page 8 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Valve on 205342 Sheet 5:

1. 21SW414 Page 9 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Valves on 205342 Sheet 6:

1. 21 & 22SW76

2. 21SW78

3. 21 & 22SW646 Page 10 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC RO-A3 NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

(205342 sheet 1 Rev 84, sheet 2 Rev 80, sheet 3 Rev 81, sheet 4 Rev 64, sheet 5 Rev 74, sheet 6 Rev 72, sheet 7 Rev 7)

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 11 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

INITIAL CONDITIONS:

Unit 2 is in a Refueling outage with the reactor defueled.

A Service Water leak has been identified by your field operator on a 2 inch drain valve (21SW268) near the 21SW76 valve inside the SW Valve Room, Auxiliary Building.

The 21SW76 is a manual isolation valve for the SW outlet of 21 CFCU.

The 21SW268, 21 NUC HDR FROM FCV DRAIN, is a 2 inch drain valve downstream of the 21SW76, 21 CFCU SW OUTLET VLV.

The field operator reports that the leak is at the body to bonnet location of the valve.

INITIATING CUE:

You are the Work Control NCO.

The Work Control SRO directs you to identify the minimum number of components needed to isolate the leak.

Drains and vents are NOT required to be identified at this point.

A complete work clearance (tagout) with all required blocking points will be performed in accordance with station procedures after leak isolation.

Assume check valves will function as designed with no leak-by.

Mark up (or circle components) on the provided P&ID drawings for the valves required to be closed and document your list of valves on this Cue Sheet:

Page 12 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE List valves here (valve description not required):

Page 13 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan - Administrative TASK: Activate ERDS During an ALERT IAW EP-SA-325-F8 TASK NUMBER: N1240110501 JPM NUMBER: 19-01 NRC RO-A4 ALTERNATE PATH: K/A NUMBER: G 2.4.43 IMPORTANCE FACTOR: 3.2 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

EP-SA-325-F8, Rev 0 (checked 8-5-19)

TOOLS AND EQUIPMENT: ERDS XXX LAN Computer in Simulator VALIDATED JPM COMPLETION TIME: 5 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 8-5-19 Instructor Validated By: Date:

SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JPM NUMBER: 19-01 NRC RO-A4 Rev # Date Description Validation Required 00 10-11-17 New JPM. Added revision history and simulator setup pages. Yes Editorial comments from IP 71111.11 FASA.

01 8-5-19 Editorial change to new procedure EP-AA-325-F8 now active Yes due to Rev 6 changes to EALs.

Page 2 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Emergency Plan - Administrative TASK: Activate ERDS During an ALERT IAW EP-SA-325-F8 TASK NUMBER: N1240110501 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

PRIOR to conducting this JPM; CONTACT the NRC ERDS Test monitor and NOTIFY ERDS being used for Training. (Day time: 301-287-9386, Night time: 240-888-2326, Day time cell: 301-731-2581, alternate number 301-873-6322, Erds.resource@nrc.gov)

OPEN the ERDS program using the SPDS computer terminal in the back computer room. Single click the ERDS program using the mouse, this will now enable the computer in the simulator to connect ERDS to NRC using EP-SA-325-F8.

Log onto the ERDS computer in simulator.

ENSURE the ERDS XXX computer is available and working.

Page 3 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Plan - Administrative TASK: Activate ERDS During an ALERT IAW EP-SA-325-F8 TASK NUMBER: N1240110501 INITIAL CONDITIONS:

Salem Unit 2 was manually tripped from 100% power due to an RCS leak.

Safety Injection was manually initiated and all ECCS pumps are running The Shift Manager has declared an ALERT.

INITIATING CUE:

You are the Work Control NCO and designated Secondary Communicator.

ACTIVATE ERDS IAW Step 1.2.b of EP-SA-325-F8, Secondary Communicator Log.

Notify the Shift Manager when ERDS is activated.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Activates ERDS by correctly performing steps 1.2.b.1 thru 1.2.b.6 IAW EP-SA-325-F8.

Page 4 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Emergency Plan - Administrative Task: Activate ERDS During an ALERT IAW EP-SA-325-F8 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

CUE: Simulator Operator:

NOTIFY NRC ERDS Test monitor of pending Training evolution.

OPEN ERDS program on SPDS computer.

LOG ON to ERDS computer.

CUE Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

1.2.b Within 60 minute, ACTIVATE ERDS from a LAN computer 1.2.b.1 PROCEED to a computer with its Operator proceeds to ERDS XXX monitor labeled ERDS XXX (XXX is computer located inside Salem

the computers asset tag number) in the Simulator horseshoe area.

Salem Control Room and START the program by SELECTING the Operator selects the ERDS_ Salem ERDS_Salem desktop icon. desktop icon.

Page 5 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Emergency Plan - Administrative Task: Activate ERDS During an ALERT IAW EP-SA-325-F8 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step) 1.2.b.2 On the Login For ERDS Display Operator enters the PASSWORD and popup window ENTER the selects Login to proceed.

PASSWORD (Password is the same as the Username) and SELECT Login to proceed.

1.2.b.3 SELECT the Action button labeled Operator selects the button labeled

<CONNECT> on the appropriate <CONNECT> for Salem 2 ERDS Link

Salem 1 or Salem 2 ERDS Link Control and Status Display Screen.

Control and Status Display Screen.

1.2.b.4 SELECT the <YES> button in the Operator selects <YES> button in the Current Link Control State is Current Link Control State is

Disconnect. Do You Want To Disconnect. Do You Want To Connect? box. Connect? box.

1.2.b.5 OBSERVE that Status changes to Operator checks that the Status Transmitting Data. changes to Transmitting Data 1.2.b.6 VERIFY successful communications Operator verifies that the Message status by observing that the Messages Sent value is increasing from zero

Sent value is increasing from zero 0 0 to some positive integer > 0.

to some positive integer > 0.

Page 6 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Emergency Plan - Administrative Task: Activate ERDS During an ALERT IAW EP-SA-325-F8 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step) 1.2.b.7 INFORM the CRS of successful ERDS Terminate JPM when CRS/SM is activation status notified ERDS is activated.

OR IF ERDS activation is not successful, THEN CONTACT IT Support: Network Operations (Ext. #7008), EOF IT Supervisor (NETS # 5009), or the IT Help Desk (Ext. 5555) for assistance.

CUE: JPM is Complete. Terminate JPM when operator notifies you that ERDS is activated.

RECORD the STOP TIME.

STOP TIME:________________

Page 7 of 11

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Emergency Plan - Administrative Task: Activate ERDS During an ALERT IAW EP-SA-325-F8 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

When all operators have completed N/A this JPM, THEN:

Simulator Operator:

NOTIFY NRC ERDS Test monitor of that Training evolution has ended.

CLOSE the ERDS program on the SPDS computer in back computer room.

Page 8 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JPM #: 19-01 NRC RO-A4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 9 of 11

INITIAL CONDITIONS:

Salem Unit 2 was manually tripped from 100% power due to an RCS leak.

Safety Injection was manually initiated and all ECCS pumps are running The Shift Manager has declared an ALERT.

INITIATING CUE:

You are the Work Control NCO and designated Secondary Communicator.

ACTIVATE ERDS IAW Step 1.2.b of EP-SA-111-F8, Secondary Communicator Log.

Notify the Shift Manager when ERDS is activated.

Page 10 of 11

Page 11 of 11 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Admin - Conduct of Operations TASK: Review Completed Shutdown Margin IAW SC.RE-ST.ZZ-0002 TASK NUMBER: N1200030301 JPM NUMBER: 19-01 NRC SRO-A1 ALTERNATE PATH: K/A NUMBER: 2.1.43 IMPORTANCE FACTOR: 4.3 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom / Perform

REFERENCES:

SC.RE-ST.ZZ-0002(Q), Rev. 24 SHUTDOWN MARGIN CALCULATION S2.RE-RA.ZZ-0016(Q), Rev. 12 CURVE BOOK (both checked 4-7-20)

TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 4-7-20 Instructor Validated By: Moore / Knock / Lantigua Date: 4-8-20 / 4-21-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 INITIAL CONDITIONS:

Unit 2 load reduction in preparation for Main Turbine valve testing was placed on hold at 90% Power due to two Control Rods (1D4 and 1D2) stopped moving.

Group Demand Counter for Control Bank D indicates 200 steps.

The CRS has declared both Control Rods INOPERABLE and entered TS LCO 3.1.3.1 Action c.3.

Current boron concentration is 1300 ppm.

Current core burnup is 4000 EFPH.

Subsequently, Reactor Engineering informs you that both Control Rods are UNTRIPPABLE.

The RO has completed a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

INITIATING CUE:

Review the completed Shutdown Margin Calculation for completeness and accuracy.

1. Identify any discrepancies and how to correct them on the CUE SHEET by recording the step number in error and what the correction should be OR you can MARK UP the provided procedure by one lining the error and record the correction.

2. Does the Shutdown Margin Calculation meet the surveillance requirement (Yes/No)? If no, briefly explain why?

List of Discrepancies (use this if NOT marking up procedure):

Step # in error What is the correction?

Page 2 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

Candidate identifies the following errors in Attachment 3:

1. Step 4.1.6 completed in error. Step 4.5 should be completed with a value of 2.

2. Step 4.2.5 completed in error. Step 4.2.4 should be completed with a value of 4330 pcm.

3. Step 4.2.7 completed in error. Trippable Rod Worth with Untrippable RCCA(s) should be used with a value of -2327.8 pcm (+/- 1 pcm)

4. Step 4.3.1 should be the same value as calculated in step 4.2.7 of -2327.8 pcm

5. Step 4.3.5 SDM should be -269.5 pcm (+/- 1 pcm)

6. Step 4.4.1 marked incorrectly as SAT. With SDM of -269.5 pcm this step should be marked as UNSAT.

7. Step 4.4.2.A marked incorrectly as N/A, should be 315.5 pcm (+/- 1 pcm)

8. Step 4.4..2.B marked incorrectly as N/A, should be 19 % RTP (+/ 20 % RTP)

Page 3 of 20

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Obtains copy of procedure SC.RE- Provide Rev. 24 of surveillance.

ST.ZZ-0002(Q).

Obtains copy of S2.RE-RA.ZZ-0016 Curve Book. Provide Rev. 12 of Curve Book.

CUE: When the operator acknowledges ready to start JPM RECORD START TIME.

START:________________

4.1.6 # OF DROPPED OR MISALIGNED Candidate determines step 4.1.6 is RCCA(s) incorrectly filled out. This step should not be completed since both Control Rods were deemed untrippable.

Candidate identifies that step 4.1.5 should have been completed with a value of:

2 untrippable RCCA(s).

Page 5 of 20

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

4.2.5 PENALTY FOR DROPPED OR Candidate determines that step 4.2.5 MISALIGNED RCCA(s) was not the correct step to complete based on rods being untrippable.

Candidate determines that step 4.2.4 PENALTY FOR UNTRIPPABLE RCCA(s) should be used.

Candidate performs step 4.2.4 and calculates a value of:

4330 pcm.

4.2.7 CHOOSE the appropriate calculation Candidate determines that the below. MARK the calculation not used TRIPPABLE ROD WORTH as N/A. calculation chosen was incorrect based on rods being untrippable.

Candidate determines that the TIPPABLE ROD WORTH WITH UNTRIPPABLE RCCA(s) calculation should be used.

Candidate determines the calculated TRIPPABLE ROD WORTH WITH UNTRIPABLE RCCA(s) is:

-2327.8 pcm.

Page 6 of 20

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

4.3.1 TRIPPABLE ROD WORTH Candidates corrects step to th same value is step 4.2.7:

-2327.8 pcm

4.3.5 SDM Candidate determines that the calculated SDM 0f -2815.5 pcm is 2.1 incorrect.

Candidate calculates the SDM value to be:

-269.5 pcm.

4.4.1 IS THE SDM EQUAL TO OR MORE Candidate determines that this step NEGATIVE THAN (-) 1300 PCM? was incorrectly marked as SAT.

Candidate determines that the step is UNSAT.

4.4.2 IF the SDM is UNDAT, THEN PERFORM the following:

4.4.2.A CALCULATE the power defect Candidate performs calculation and required to achieve required SDM determines required power defect is:

315.5 pcm Page 7 of 20

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation) 4.4.2.B DETERMINE Reactor Power Level Candidate refers to Figure 17A and based on power defect in 4.4.2.A and determines Reactor Power Level of:

boron concentration in 4.1.2 (Figure 17A/Table 2-1) 19 % RTP (acceptable band 15-20 % RTP)

CUE MARK stop time of JPM when JPM is Complete when Candidate procedures are returned to proctor. submits Attachment to Evaluator.

STOP:___________________

Page 8 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 9 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 10 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 11 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 12 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 13 of 20

Page 14 of 20 Page 15 of 20 Page 16 of 20 Page 17 of 20 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 18 of 20

INITIAL CONDITIONS:

Unit 2 load reduction in preparation for Main Turbine valve testing was placed on hold at 90% Power due to two Control Rods (1D4 and 1D2) stopped moving.

Group Demand Counter for Control Bank D indicates 200 steps.

The CRS has declared both Control Rods INOPERABLE and entered TS LCO 3.1.3.1 Action c.3.

Current boron concentration is 1300 ppm.

Current core burnup is 4000 EFPH.

Subsequently, Reactor Engineering informs you that both Control Rods are UNTRIPPABLE.

The RO has completed a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

Page 19 of 20

INITIATING CUE:

Review the completed Shutdown Margin Calculation for completeness and accuracy.

1. Identify any discrepancies and how to correct them on the CUE SHEET by recording the step number in error and what the correction should be OR you can MARK UP the provided procedure by one lining the error and record the correction.

2. Does the Shutdown Margin Calculation meet the surveillance requirement (Yes/No)? If no, briefly explain why?

List of Discrepancies (use this if NOT marking up procedure):

Step # in error What is the correction?

Page 20 of 20

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topic - Conduct of Operations TASK: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures TASK NUMBER: N1230040302 JPM NUMBER: 19-01 NRC SRO-A2 ALTERNATE PATH: K/A NUMBER: 2.1.5 IMPORTANCE FACTOR: 3.9 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom / Perform LS-AA-119-1003 , Rev 8 & SY-AA-102-201, Rev 11 (checked 1-16-20)

REFERENCES:

LS-AA-119, Rev 12 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 45 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NA Developed By: R. Chan Date: 1-16-20 Instructor Validated By: Moore Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 22

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Generic Administrative Topic - Conduct of Operations TASK: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures TASK NUMBER: N1230040302 INITIAL CONDITIONS:

Today is Thursday October 17, 2020.

Both Units are at 100% power.

You are the Shift Manager and your crew has just began its 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months night shift starting at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months .

The crew is at minimum staffing levels.

At 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , the Plant Operator on Unit 2 has become ill and has been sent home, which places the shift BELOW MINIMUM staffing levels.

There are NO qualified operators available on-site.

Five operators have been contacted at home.

This call-out is NOT for an emergency.

INITIATING CUE:

Based on Administrative requirements, determine the following from the given list of available operators and work schedules:

o How soon must relief be found?

o From the list provided, who is eligible to assume the shift duties (provided the individual called in works the remaining hours of the shift and they work the schedule provided in this JPM) o For those who are NOT eligible, state the reason why?

Page 2 of 22

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Determines two (2) hours to restore shift crew to minimum staffing levels.

2. Determines Operator #2 can be called in.

3. States why operators are not eligible to assume the shift:

a. Operator #1 violates LS-AA-119-1003 work hour rules (> 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period),

b. Operator #3 is not fit for duty IAW SY-AA-102-201 due to consuming alcohol during the past five hours,

c. Operator #4 will violate LS-AA-119-1003 work hour rule (> 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24-hour period) and/or break period (less than 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break), and

d. Operator #5 is not fit for duty IAW SY-AA-102-201 due to use of medication affecting his/her ability to perform work.

Page 3 of 22

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Page Left Intentionally Blank Page 4 of 22

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

CUE: Provide copies or make available the following procedures:

1. LS-AA-119

2. LS-AA-119-1003

3. SY-AA-102-201

4. Salem Technical Specification CUE: When the operator acknowledges ready to start JPM RECORD START TIME.

START:________________

1 How soon must relief be found? Determines IAW Technical Specification Administrative section that two (2) hours to restore shift staffing to minimum levels.

Page 5 of 22

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

2 Determines that Operator #2 is From the list provided, who is eligible eligible to be called in without to assume the shift duties (provided the violating the work hour rules and individual called in works the remaining fitness for duty program hours of the shift and they work the requirements.

schedule provided in this JPM)

Page 6 of 22

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

3 For those who are NOT eligible, state Operator #1 violates LS-AA-119-1003 the reason why? work hour rules (> 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period),

Operator #3 is not fit for duty IAW SY-AA-102-201 due to consuming alcohol during the past five hours, Operator #4 will violate LS-AA-119-1003 work hour rule (> 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24-hour period) and/or break period (less than 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break), and Operator #5 is not fit for duty IAW SY-AA-102-201 due to use of medication affecting his/her ability to perform work.

JPM is Complete when candidate submits cue sheet.

CUE MARK stop time of JPM when JPM is Complete when operator procedures are returned to proctor. submits Attachment to Evaluator.

STOP:___________________

Page 7 of 22

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topic - Conduct of Operations Task: Evaluate Shift Staffing Requirements and Take Corrective Actions IAW Administrative Procedures

STEP NO. STEP STANDARD EVAL COMMENTS

(* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Page 8 of 22

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE ANSWER KEY Fatigue Work Hour Evaluation Fitness for Duty (LS-AA-119-1003) (SY-AA-102-201)

Operator Worked > 16 Worked >26 Worked > 72 At least 10-hour At least 34-hour hours in 24- hours in a 48- hours in a break between break during the Fit for Duty?

hour period hour period rolling 7 day successive work last nine day period periods period 1 NO NO YES YES N/A YES 2 NO NO NO YES N/A YES 3 NO NO NO YES NO Consumed alcohol within the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 YES NO NO NO N/A YES 5 NO NO NO YES N/A NO Used medication that may impair operator performance. Stated not fit for duty.

ANSWER KEY Page 9 of 22

ANSWER KEY LS-AA-119-1003 ANSWER KEY Page 10 of 22

ANSWER KEY ANSWER KEY Page 11 of 22

ANSWER KEY ANSWER KEY Page 12 of 22

ANSWER KEY SY-AA-102-201 ANSWER KEY Page 13 of 22

ANSWER KEY Page 14 of 22

ANSWER KEY Salem Technical Specification ANSWER KEY Page 15 of 22

ANSWER KEY ANSWER KEY Page 16 of 22

ANSWER KEY Operator Wed Thurs Fri Sat Sun Mon Tues Wed Thurs Fri Sat Sun Mon Tues Wed 10/9 10/10 10/11 10/12 10/13 10/14 10/15 10/16 10/17 10/18 10/19 10/20 10/21 10/22 10/23

1 N N N N D D N N N N N N (6) (12) (12) (6) (12) (12) (6) (12) (12) (12) (12) (6)

2 D D D N N N N N N (12) (12) (12) (6) (12) (12) (12) (12) (6)

3 D D D N N N N N N (12) (12) (12) (6) (12) (12) (12) (12) (6)

4 T T T T T T T N D D D (10) (10) (10) (10) (10) (10) (10) (6) (12) (12) (12)

N (6)

5 N N N N N N N N N (6) (12) (12) (6) (6) (6) (6) (12) (12)

Operator Eligible to Assume Evaluation for Eligibility / Reason if Not Eligible the Shift?

1 NO On day 7 (10/21) the operator #1 would have worked 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months in a seven day period which is a violation of LS-AA-119-1003 (no more than 72 work hours in any 7-day period). This operator should not be called in.

2 YES Operator #2 works the schedule and finishes his/her shift on 10/22 the total hours worked would be 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months . Therefore, operator

2 would not violate any of LS-AA-119-1003 work hour rules and required rest periods.

3 NO Operator #3 works the schedule and finishes his/her shift on 10/22 the total hours worked would be 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months . Operator #3 would not violate any of LS-AA-119-1003 work hour rules and required rest periods. However, Operator #3 self-reported on the phone call that he/she consumed alcohol during the last five hours and believes to be not fit for duty. This operator should not be called in.

4 NO If Operator #4 works the night shift, he/she would have worked 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months in a 24-hour period and violate LS-AA-119-1003 in two areas; (1) no more than 16 work hours in any 24-hour period, and (2) at least a 10-hour break between successive work periods..).

This operator should not be called in.

5 NO If Operator #4 works the schedule and finishes his/her shift on 10/18 the total hours worked would be 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Operator #5 would not violate any of LS-AA-119-1003 work hour rules and required rest periods. However, Operator #5 self-reported on the phone call that he/she took medication that can cause impairment and believes to be not fit for duty. This operator should not be called in.

ANSWER KEY Page 17 of 22

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 18 of 22

INITIAL CONDITIONS:

Today is Thursday October 17, 2020.

Both Units are at 100% power.

You are the Shift Manager and your crew has just began its 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months night shift starting at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months .

The crew is at minimum staffing levels.

At 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , the Plant Operator on Unit 2 has become ill and has been sent home, which places the shift BELOW MINIMUM staffing levels.

There are NO qualified operators available on-site.

Five operators have been contacted at home.

This call-out is NOT for an emergency.

INITIATING CUE:

Based on Administrative requirements, determine the following from the given list of available operators and work schedules:

o How soon must relief be found?

o From the list provided, who is eligible to assume the shift duties (provided the individual called in works the remaining hours of the shift and they work the schedule provided in this JPM) o For those who are NOT eligible, state the reason why?

Page 19 of 22

Operator Response to Call-In phone call:

Operator Call-Out Phone Responses 1 I dont mind working another night. I need the extra money to save for my new boat. I can be there in 30 minutes. I have not consumed alcohol during the past five hours and I am fit for duty.

2 I would rather not work tonight, my son has a baseball game, but if you guys are in a jam I can be there in 45 minutes. I have not consumed alcohol during the past five hours and I am fit for duty.

3 Im home right now with some friends visiting from out of town. Ive had a couple of beers with the guys. I can come in if you want me to. I can be there in 50 minutes. I have consumed alcohol during the past five hours and I dont really think Im fit for duty.

4 I just got home from training at 1730. This was my last day of training and dont take the watch until Monday day shift. I live nearby and can be there in 30 minutes. I have not consumed alcohol during the past five hours and I am fit for duty.

5 I just finished working nights on Wednesday morning. I think a caught a cold from one of the operators. Im fighting a really nasty cold and just took a dose of Nyquil Liquid Nighttime Cold Medicine an hour ago so I could get some rest. I know I dont want to infect the other guys on shift, but I know the situation youre in and willing to help out. I could take a hot shower to help wake me up and I could be there in an hour. I have not consumed alcohol during the past five hours and Im not sure if Im fit for duty but willing to come in.

Page 20 of 22

Operators Schedule:

Operator Wed Thurs Fri Sat Sun Mon Tues Wed Thurs Fri Sat Sun Mon Tues Wed 10/9 10/10 10/11 10/12 10/13 10/14 10/15 10/16 10/17 10/18 10/19 10/20 10/21 10/22 10/23

1 N N N N D D N N N N N (6) (12) (12) (6) (12) (12) (6) (12) (12) (12) (6)

2 D D D N N N N N (12) (12) (12) (6) (12) (12) (12) (6)

3 D D D N N N N N (12) (12) (12) (6) (12) (12) (12) (6)

4 T T T T T T T D D D (10) (10) (10) (10) (10) (10) (10) (12) (12) (12)

5 N N N N N N N (6) (12) (12) (6) (6) (12) (12)

N (12) = 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Night shift (1800-0600)

N (6) = 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months on the first Night shift starting at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months or 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months on the last morning of Night Shift ending at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months D (12) = 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Day Shift (0600-1800)

T (10) = 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of Training (0700-1700)

BLANK SPACE = Scheduled day off Page 21 of 22

Operator Eligible to Assume Watch State Reason if not eligible (Yes / No)

1

2

3

4

5 Page 22 of 22

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topics - Equipment Control TASK: Determine Component Operability and Technical Specification Action Statement(s)

TASK NUMBER: 112670302 JPM NUMBER: 19-01 NRC SRO-A3 ALTERNATE PATH: K/A NUMBER: G 2.2.37 IMPORTANCE FACTOR: 4.6 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom / Simulate S1.OP-SO.DG-0005, Rev. 10 (checked 1-16-20)

REFERENCES:

Salem Unit 1 Tech Specs 3.8.1.1 & S1.OP-SO.SW-0005 Rev 47 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 15 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-16-20 Instructor Validated By: Moore Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC SRO-A3 Rev # Date Description Validation Required 00 9-4-18 This is a NEW JPM. Added revision history and simulator Yes setup pages. Editorial comments from IP 71111.11 FASA.

01 12-4-18 Incorporated NRC Prep week comments. Comment is No enhancements to clarify a question and re-validation is not required.

02 8-6-19 MODIFIED JPM to use SW component failure. Yes

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Generic Administrative Topics - Equipment Control TASK: Determine Component Operability and Technical Specification Action Statement(s)

TASK NUMBER: 112670302 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

ENSURE copy of S1.OP-SO.DG-0005 and Unit 1 Technical Specifications are available per candidate.

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Generic Administrative Topics - Equipment Control TASK: Determine Component Operability and Technical Specification Action Statement(s)

TASK NUMBER: 112670302 INITIAL CONDITIONS:

Salem 1 is at 100% power.

13 SW Pump is C/T for motor replacement. Tagged at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months today.

1A EDG fails its Surveillance Test and was declared INOPERABLE today at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months .

INITIATING CUE:

You are the Unit 1 CRS.

(Part 1) What Technical Specification Action statement(s) are applicable and why?

EVALUATORs CUE: When candidate submits response to Part1, THEN CUE Part 2 task.

(Part 2-CUE after Part 1 is complete) Subsequently, 12 SW Pump Strainer shear pin key breaks (motor spinning without strainer basket) due to strainer being clogged / DP.

What Technical Specification Action statement(s) are applicable now and why?

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Determines T/S 3.8.1.1 actions b1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), b3 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), b4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) is applicable. The candidate provides correct supporting information to T/S action and IAW attached answer key.

2. Determines T/S 3.8.1.1 action b2 (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) and 3.7.4.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) are now applicable. The candidate provides correct supporting information to T/S action and IAW attached answer key.

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Admin - Emergency Plan TASK: Classify the Emergency and complete the ICMF STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

CUE: EVALUATORS CUE: Evaluators Note: Provide copies of these procedures when requested.

IF Requested, THEN PROVIDE copies of:

S1.OP-SO.DG-0005 S1.OP-SO.SW-0005 CUE EVALUATORS CUE: ONLY PROVIDE PART 2 AFTER CANDIDATE SUBMITS RESPONSE TO PART 1.

CUE: PROVIDE the operator the initiating cue AND ENTER START TIME AFTER operator repeats back the Initiating Cue.

START TIME:___________________

Page 5 of 19

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Admin - Emergency Plan TASK: Classify the Emergency and complete the ICMF STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

PART 1 (Part 1) What Technical Specification Candidate determines the following Action statement(s) are applicable and Tech Spec action statement(s) are why? applicable:

3.8.1.1 Action b.1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), b.3 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), and b.4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) for 1A EDG Inoperable.

Evaluators Note: TS 3.7.4.1 is not applicable at this time with 13 SW Pump Inoperable since you still meet the requirements for having two Operable SW Loops Operable (one pump per bus and two pumps per bay Operable). Therefore, TS 3.8..1.1.b2 is not applicable at this time.

CUE EVALUATORs CUE: When candidate submits response to Part 1, THEN CUE Part 2 task.

Page 6 of 19

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Admin - Emergency Plan TASK: Classify the Emergency and complete the ICMF STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

PART 2 (Part 2-CUE after Part 1 is complete) Candidate determines the following Tech Spec action statement(s) are EVALUATORS CUE: Subsequently, 12 applicable (in addition to the Part 1 TS SW Pump Strainer shear pin key breaks actions that are still active):

(motor spinning without strainer basket) due to strainer being clogged with high 3.8.1.1 Action b.2 (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) for not DP. having a Two SW Loops Operable.

You now have 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to restore 1A What Technical Specification Action EDG or be in Hot Standby within the statement(s) are applicable now and next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

why?

3.7.4.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) for only ONE SW Loop Operable.

Evaluators Note: TS 3.7.4.1 is applicable at this time with 12 & 13 SW Pump Inoperable since you only have one SW Loop Operable. With only one SW Loop Operable, TS 3.8.1.1.b.2 is now applicable and you have 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to restore 1A EDG or be in Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

JPM is complete Page 7 of 19

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Admin - Emergency Plan TASK: Classify the Emergency and complete the ICMF STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

CUE: WHEN operator informs you the task is Terminate JPM after Candidate submits complete, OR the JPM has been the response to you.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:____________________

Page 8 of 19

ANSWER KEY Page 9 of 19

ANSWER KEY Case Studies from S1.OP-SO.DG-0005, Exhibit 1:

Page 10 of 19

ANSWER KEY Page 11 of 19

ANSWER KEY Page 12 of 19

PART 1 ANSWER KEY What Technical Specification Action statement(s) are applicable and why?

T/S 3.8.1.1, Actions b.1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), b.3 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), and b.4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

Why?

Two (2) SW Loops remain Operable.

Enter TS LCO for 1A EDG Inoperable only; redundant SW Loops are operable.

Supporting Bases:

With 13 SW Pump Inoperable; TWO SW Loops remain Operable based on meeting the requirements for one SW Pump powered from each vital bus and two SW Pumps Operable per Bay as defined in S1.OP-SO.DG-0005, Attachment 2, page 102.

C C B B A A Bus Bus Bus Bus Bus Bus 11 12 13 14 15 16 C/T

1 SW Bay Pumps #3 SW Bay Pumps IAW S1.OP-SO.SW-0005, Attachment 2, in order to have two independent OPERABLE Service Water loops, the following SW pumps are required as a minimum:

(1) One OPERABLE SW pump powered from the A vital bus, AND YES - 15 & 16 SW Pumps are Operable (2) One OPERABLE SW pump powered from the B vital bus, AND YES - 14 SW Pump is Operable (3) One OPERABLE SW pump powered from the C vital bus, AND YES - 11 & 12 SW Pumps are Operable (4) Two OPERABLE SW pumps per Bay.

1 SW Bay - YES -11 & 12 SW Pumps are Operable

3 SW Bay - YES - 15 & 16 SW Pumps are Operable Page 13 of 19

Part 1 - Continued

Since 1A EDG is declared INOPERABLE and ALL other components are Operable (i.e., TWO SW Loops remain Operable), THEN T/S 3.8.1.1, Actions b.1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), b.3 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), and b.4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) are applicable.

With TWO SW Loops OPERABLE, the required redundant system or component remains Operable and T/S 3.8.1.1, Action b.2 is not applicable.

This condition is Special Case D - Service Water or Case #1 from S1.OP-SO.DG-0005, Exhibit 1. 1A EDG must be restored to Operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months IAW T/S 3.8.1.1, Action b.4.

Page 14 of 19

PART 2 ANSWER KEY Subsequently, 12 SW Pump Strainer shear pin key breaks (motor spinning without strainer basket) due to strainer being clogged / DP.

What Technical Specification Action statement(s) are applicable now and why?

T/S 3.8.1.1, Actions b.2 (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) and 3.7.4.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

Why?

Only one SW Loop is Operable and now youve lost your redundant SW Loop. TS 3.7.4.1 now applies for one SW Loop operable.

With a redundant SW Loop Inoperable, then TS 3.8.1.1. Action b2 now applies.

Supporting Bases:

With 13 and 12 SW Pumps Inoperable; TWO SW Loops are not Operable based on not meeting two SW Pumps Operable in each Bay (i.e., Bay #1 doesnt have two Operable SW Pumps). However, ONE SW Loop is Operable based on meeting the requirements for one SW Pump powered from B vital bus and one SW Pump powered from C vital bus as defined in S1.OP-SO.DG-0005, Attachment 2, page 102.

C C B B A A Bus Bus Bus Bus Bus Bus 11 12 13 14 15 16 Shear Pin C/T breaks

1 SW Bay Pumps #3 SW Bay Pumps IAW S1.OP-SO.SW-0005, Attachment 2, in order to have two independent OPERABLE Service Water loops, the following SW pumps are required as a minimum:

(1) One OPERABLE SW pump powered from the A vital bus, AND YES - 15 & 16 SW Pumps are Operable (2) One OPERABLE SW pump powered from the B vital bus, AND YES - 14 SW Pump is Operable (3) One OPERABLE SW pump powered from the C vital bus, AND YES - 11 SW Pumps are Operable Page 15 of 19

(4) Two OPERABLE SW pumps per Bay. - NO

1 SW Bay - NO - ONLY 11 SW Pumps is Operable

3 SW Bay - YES - 15 & 16 SW Pumps are Operable

Since only ONE SW Loops is Operable, THEN T/S 3.7.4.1 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) is applicable, AND IAW S1.OP-SO.SW-0005, Attachment 2, in order to have one OPERABLE SW loop, the following SW pumps are required as a minimum:

(1) One OPERABLE SW pump powered from the A vital bus AND one OPERABLE SW pump powered from the B vital bus, YES - 15 & 16 SW Pumps (A bus) and 14 SW Pump (B bus)

OR (2) One OPERABLE SW pump powered from the A vital bus AND one OPERABLE SW pump powered from the C vital bus, YES - 15 & 16 SW Pumps (A bus) and 11 SW Pump (C bus)

OR (3) One OPERABLE SW pump powered from the B vital bus, AND one OPERABLE SW pump powered from the C vital bus YES - 14 SW Pump (B bus) and 11 SW Pump (C bus)

With 1A EDG Inoperable and only ONE SW Loop Operable, the required redundant system or component is INOPERABLE, THEN T/S 3.8.1.1, Action b.2 (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) is applicable and 15 & 16 SW Pumps must be declared Inoperable in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 1A EDG must be restored to Operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or a unit shutdown is required (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to Mode 3, following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months to Mode 5).

This condition is Special Case E - Service Water from S1.OP-SO.DG-0005, Exhibit 1. 1A EDG must be restored to Operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months IAW T/S 3.8.1.1, Action b.4. In addition, T/S 3.8.1.1, Action b.2 now applicable and 1A EDG must be restored to Operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or a unit shutdown is required (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to Mode 3, following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months to Mode 5).

Page 16 of 19

TQ-AA-106-0303 Revision 5 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC SRO-A3 NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 17 of 19

PART 2 (Give to Candidate after Part 1 is submitted):

Subsequently, 12 SW Pump Strainer shear pin key breaks (motor spinning without strainer basket) due to strainer being clogged / DP.

What Technical Specification Action statement(s) are applicable now and why?

Page 18 of 19

INITIAL CONDITIONS:

Salem 1 is at 100% power.

13 SW Pump is C/T for motor replacement. Tagged at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months today.

1A EDG fails its Surveillance Test and was declared INOPERABLE today at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months .

INITIATING CUE:

You are the Unit 1 CRS.

What Technical Specification Action statement(s) are applicable and why?

Page 19 of 19

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topics - Radiation Control TASK: Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002 TASK NUMBER: N0680070302 JPM NUMBER: 19-01 NRC SRO-A4 ALTERNATE PATH: K/A NUMBER: G 2.3.6 IMPORTANCE FACTOR: 3.8 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S1.OP-SO.WL-0002, Rev 31 (checked 1-16-20)

TOOLS AND EQUIPMENT: Highlighters (Pens)

VALIDATED JPM COMPLETION TIME: 30 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-16-20 Instructor Validated By: Moore Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC SRO-A4 Rev # Date Description Validation Required 00 8-5-19 K/A 2.3.6, SRO 3.8, Ability to approve release permits. Yes

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Generic Administrative Topics - Radiation Control TASK: Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002 TASK NUMBER: N0680070302 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS: None

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Generic Administrative Topics - Radiation Control TASK: Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002 TASK NUMBER: N0680070302 INITIAL CONDITIONS:

Unit 2 is in a refueling outage.

ALL Unit 2 Circulators are out of service.

21 CCHX is in service at 1500 gpm and 22 CCHX is removed from service and drained.

Salem Unit 1 is operating at 75% power.

There are no active Tech Specs on Unit 1.

12A Circulator is C/T for waterbox cleaning.

11 and 12 CCHXs are in service.

12 CVCS Monitor Tank is in recirculation using 11 CVCS Monitor Tank Pump.

Chemistry has granted permission to release the tank with a minimum dilution flow rate of 100,000 gpm.

INITIATING CUE:

You are the Unit 1 CRS.

DETERMINE which CCHX will be selected for the release of 12 CVCS Monitor Tank IAW S1.OP-SO.WL-0002, Attachment 2, Section 2.2 Release Verification.

MARK UP the provided drawings using a highlighter to IDENTIFY the flow path from 12 CVCS Monitor Tank to the discharge to the river.

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Selects 21 CCHX to 12A AND/OR 12B CW Pumps in service as release path.

2. Correctly identifies the release flow path on the provided drawings and IAW with the attached answer key.

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Administrative Topics - Radiation Control TASK: Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

CUE: Provide copies of the following materials:

S1.OP-SO.WL-0002 205230 205239 Sht. 1 205229 Sht. 2 205242 Sht. 4 205339 Sht. 1 205342 Shts. 3 thru 6 205209 Sht. 2 CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:________________

1 DETERMINE which CCHX will be Selects 21 CCHX to 12A AND/OR 12B CW selected for the release of 12 CVCS Pumps in service as release flow path.

Monitor Tank IAW S1.OP-SO.WL-0002, Attachment 2, Section 2.2 Release Verification.

Page 6 of 18

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Generic Administrative Topics - Radiation Control TASK: Select Release Path for Radioactive Liquid Waste Release IAW S1.OP-SO.WL-0002 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

2 MARK UP the provided drawings using a Correctly identifies the release flow path on highlighter to IDENTIFY the flow path the provided drawings and IAW with from 12 CVCS Monitor Tank to the attached answer key.

discharge to the river.

CUE: JPM is Complete Terminate JPM when SRO submits the completed Cue Sheet to the Evaluator.

RECORD the STOP TIME:

STOP TIME:_________________

Page 7 of 18

ANSWER KEY Drawing 205230:

Page 8 of 18

Drawing 205239 Sheet 1:

Page 9 of 18

Drawing 205339 Sheet 1:

Page 10 of 18

Drawing 205342 Sheet 3:

Page 11 of 18

Drawing 205342 Sheet 3:

Page 12 of 18

Drawing 205342 Sheet 4:

Page 13 of 18

Drawing 205342 Sheet 6:

Page 14 of 18

Drawing 205209 Sheet 2:

Page 15 of 18

ANSWER KEY DETERMINE which CCHX will be selected for the release of 12 CVCS Monitor Tank IAW S1.OP-SO.WL-0002, Attachment 2, Section 2.2 Release Verification.

21 CCHX AND 12A AND/OR 12B CW Pumps In Service MARK UP the provided drawings using a highlighter to IDENTIFY the flow path from 12 CVCS Monitor Tank to the discharge to the river.

See enclosed drawing excerpts for correct highlighted flow path.

ANSWER KEY Page 16 of 18

TQ-AA-106-0303 Revision 5 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM #: 19-01 NRC SRO-A1 NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk

(*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 17 of 18

INITIAL CONDITIONS:

Unit 2 is in a refueling outage.

ALL Unit 2 Circulators are out of service.

21 CCHX is in service at 1500 gpm and 22 CCHX is removed from service and drained.

Salem Unit 1 is operating at 75% power.

There are no active Tech Specs on Unit 1.

12A Circulator is C/T for waterbox cleaning.

11 and 12 CCHXs are in service.

12 CVCS Monitor Tank is in recirculation using 11 CVCS Monitor Tank Pump.

Chemistry has granted permission to release the tank with a minimum dilution flow rate of 100,000 gpm.

INITIATING CUE:

You are the Unit 1 CRS.

DETERMINE which CCHX will be selected for the release of 12 CVCS Monitor Tank IAW S1.OP-SO.WL-0002, Attachment 2, Section 2.2 Release Verification.

MARK UP the provided drawings using a highlighter to IDENTIFY the flow path from 12 CVCS Monitor Tank to the discharge to the river.

Page 18 of 18

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Generic Administrative Topics - Emergency Plan TASK: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 TASK NUMBER: 1240020502 JPM NUMBER: 19-01 NRC SRO-A5 ALTERNATE PATH: K/A NUMBER: G 2.4.41 IMPORTANCE FACTOR: 4.6 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom EP-SA-325-101, Rev. 01 (checked 1-16-20)

EP-SA-325-123, Rev 00

REFERENCES:

EP-SA-325-F4, Rev 00 TOOLS AND EQUIPMENT: Salem ECG Books Rev 6 VALIDATED JPM COMPLETION TIME: 8 mins TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 mins / 10 mins Developed By: R. Chan Date: 1-16-20 Instructor Validated By: Moore Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JPM NUMBER: 19-01 NRC SRO-A5 Rev # Date Description Validation Required 00 8-6-19 NEW JPM for 19-01 ILOT NRC Exam. Yes Page 2 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Generic Administrative Topics - Emergency Plan TASK: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 TASK NUMBER: 1240020502 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

ENSURE sufficient BLANK copies of EP-SA-325 Attachments 1 thru 4.

ENSURE sufficient copies of ECG books and/or wall charts.

Page 3 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Generic Administrative Topics - Emergency Plan TASK: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 TASK NUMBER: 1240020502 INITIAL CONDITIONS:

Unit 2 experienced a Large Break LOCA and an Automatic Safety Injection (SI).

All available equipment started following SI signal.

An ALERT was declared based on EAL# RB1.L, Loss of the Reactor Coolant System Barrier.

The Emergency Core Cooling System (ECCS) is currently aligned for Cold Leg Recirculation IAW EOP-LOCA-3.

The crew is responding to the following alarms and indications:

o OHA C-26, 21 RHR SUMP OVRFLO o Auxiliary Typewriter alarm point; 21 RHR Sump Pump start.

o 2R41D, Plant Vent Radiation Monitor, indicating 3.18E+05 µCi/sec and rising The crew responded to the alarms/indications by closing the 21SJ44, Containment Sump Suction Valve, to isolate the leak but the valve failed to close.

The OCC is briefing a field team to investigate the breaker associated for the 21SJ44 valve.

The 2R44A and 2R44B, Containment High range Radiation Monitors, are currently reading 305 R/Hr.

The 2R41D, Plant Vent Radiation Monitor, is currently reading 5.12E+6 µCi/sec and rising.

Met Tower data indicates wind from 180 degrees at 5 mph.

INITIATING CUE:

You are the Emergency Coordinator (EC).

CLASSIFY the event AND COMPLETE / APPROVE the ICMF IAW the applicable procedure.

The JPM will stop when you have submitted the ICMF to your evaluator.

THIS IS A TIME CRITICAL JPM.

Page 4 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Classifies the event as a General Emergency (GE) 13 points based on RB1.L or RB2.L (5 pts), FB2.L (5 pts) and CB2.L (3 pts) or CB3.L (3 pts) within 15 minutes

2. Correctly completes sections I thru V of the ICMF IAW with attached answer key for the classified event within 10 minutes from event declaration.

Page 5 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE This page left intentionally blank Page 6 of 12

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topics - Emergency Plan Task: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

CUE: PROVIDE the following materials:

Salem ECG books (Rev 6) and/or wall charts Blank copies of Attachments 1 thru 4 (EP-SA-325-F1/F2/F3/F4)

CUE: READ to the Operator: Operator reviews initial conditions and acknowledges the initiating cue.

THIS IS A TIME CRITICAL JPM.

You will be giving time to REVIEW the Initial Conditions on the Cue Sheet. The JPM will START once you have completed your review and acknowledge the Initiating Cue. The time will stop when you have classified the event and submitted the ICMF to the Lead Evaluator.

Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:________________

Page 7 of 12

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topics - Emergency Plan Task: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

Operator classifies the event as a

CLASSIFY the event.

General Emergency (GE) 13 points based on EAL#s: RB1.L or RB2.L (5 pts),

FB2.L (5 pts) and CB2.L (3 pts) or CB3.L (3 pts) within 15 minutes from when the JPM started.

COMPLETE / APPROVE the ICMF Evaluators Note: Attachments 1 thru 4 will be made available. The operator will have to select the correct Attachment based on the classification.

Operator correctly fills out Sections I thru V of the ICMF for General Emergency (GE) IAW EP-SA-325-F4, Attachment 4. Completing the ICMF within 10 minutes from when he event was declared on the ICMF form Note: A release is in progress due to the event.

Note: See attached ANSWER KEY for complete and accurate ICMF.

Page 8 of 12

OPERATOR TRAINING PROGRAM NAME:___________________________

JOB PERFORMANCE MEASURE DATE:___________________________

System: Generic Administrative Topics - Emergency Plan Task: Classify the Event and Complete / Approve the ICMF IAW EP-SA-325-101 STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

CUE: JPM is Complete.

Terminate JPM when operator submits the ICMF form.

RECORD the STOP TIME.

STOP TIME:________________

Page 9 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE ANSWER KEY ANSWER KEY Page 10 of 12

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM #: 19-01 NRC SRO-A5 NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 11 of 12

INITIAL CONDITIONS:

Unit 2 experienced a Large Break LOCA and an Automatic Safety Injection (SI).

All available equipment started following SI signal.

An ALERT was declared based on EAL# RB1.L, Loss of the Reactor Coolant System Barrier.

The Emergency Core Cooling System (ECCS) is currently aligned for Cold Leg Recirculation IAW EOP-LOCA-3.

The crew is responding to the following alarms and indications:

o OHA C-26, 21 RHR SUMP OVRFLO o Auxiliary Typewriter alarm point; 21 RHR Sump Pump start.

o 2R41D, Plant Vent Radiation Monitor, indicating 3.18E+05 µCi/sec and rising The crew responded to the alarms/indications by closing the 21SJ44, Containment Sump Suction Valve, to isolate the leak but the valve failed to close.

The OCC is briefing a field team to investigate the breaker associated for the 21SJ44 valve.

The 2R44A and 2R44B, Containment High range Radiation Monitors, are currently reading 305 R/Hr.

The 2R41D, Plant Vent Radiation Monitor, is currently reading 5.12E+6 µCi/sec and rising.

Met Tower data indicates wind from 180 degrees at 5 mph.

INITIATING CUE:

You are the Emergency Coordinator (EC).

CLASSIFY the event AND COMPLETE / APPROVE the ICMF IAW the applicable procedure.

The JPM will stop when you have submitted the ICMF to your evaluator.

THIS IS A TIME CRITICAL JPM.

Page 12 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed Open Pressurizer Spray Valve IAW S2.OP-AB.PZR-0001 TASK NUMBER: 1140240401 JPM NUMBER: 19-01 NRC Sim-a ALTERNATE PATH: X K/A NUMBER: 010 A4.01 IMPORTANCE FACTOR: 3.7 3.5 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.OP-AB.PZR-0001, Rev. 18 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Weidner Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: N/A Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-a Rev # Date Description Validation Required 00 3-12-18 Added revision history and simulator setup pages. Editorial Yes comments from IP 71111.11 FASA. Incorporated changes to 2-EOP-APPX-1 Rev. 25.

01 7-19-18 Added step 3.33 if CAS action is taken first. Identified a No alternate step at which the JPM can be terminated. These changes do not require re-validation since they do not change the course of actions previously validated that the operator is required to perform to meet the task standard.

See Rev. 0 for validator approvals.

02 9-17-19 MODIFIED JPM that initial failure is with PZR pressure Yes channel failing high then the Alternate Path is one of the spray valves fails to fully close requiring a reactor trip and stopping RCPs.

010 K/A A4.01: Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PZR spray valve Page 2 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 TASK NUMBER: 1140240401 SIMULATOR IC: IC-201 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 PR0016A, PZR Press Channel 1 fails high N/A N/A N/A RT-1 2500 02 VL0444, 2PS1 fails to position 00:00:15 N/A N/A ET-3 35

3. These malfunctions will simulate a PZR Pressure channel failing high causing both spray valves to fully open. RCS pressure will rapidly lower. [Alternate Path] When the operator uses either the Master Pressure Controller or 2PS1 bezel to close the spray valve, the operator will recognize that 2PS1 will not fully close requiring the operator to take the action in AB.PZR-1 to trip reactor and stop 21 and 23 RCPs.

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 EVENT TRIGGERS:

ET# Description Command 1 KB210DMI, MPC Manual PB 2 KB210PRI, MPC Increase PB 3 et_array(01) AND et_array(02) 4 KB214TWI, 2PS1 Decrease PB IMF VL0444 SPECIAL INSTRUCTIONS:

Additional instructor to assist in silencing alarms following reactor trip.

Page 3 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 TASK 1140240401 NUMBER:

INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

INITIATING CUE:

You are the Reactor Operator.

Respond to all indications and alarms.

Your evaluator will respond to all alarms not related to your task.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Trips the Reactor

2. Stops 21 and 23 RCPs Page 4 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

CUE:

Simulator Operator: Insert RT-1 on direction from Lead Examiner.

PR0016A , PZR Pressure Channel 1 fails high CUE: The following alarms will come after RT-1 is Operator scans the control board and inserted: recognizes that PZR Pressure Channel 1 is failed high.

OHA D-8, RC PRESS HI

OHA E-42, 2PR1 1/2 TRIP Page 5 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

Operator takes manual control of Master Operator takes manual control of the Pressure Controller. Master Pressure Controller (MPC) and adjust demand to increase RCS pressure (close spray valves).

Examiners Note: Operator may enter AB.PZR-0001 first, then wait for the step to take manual control of the MPC.

Enters S2.OP-AB.PZR-0001, Pressurizer Enters S2.OP-AB.PZR-0001 directly or Pressure Malfunction via OHA D-8 OR E-42 ARP.

Simulator Operator: IF operator attempts Examiners Note: It is acceptable to to CLOSE 2PS1 here, THEN ENSURE ET- attempt closing 2PS1 prior to entering 4 is TRUE. This will insert malfunction on S2.OP-AB.PZR-001.

2PS1.

Page 6 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.1 INITIATE Attachment 1 Continuous Action Initiates Attachment 1 Continuous Action Summary. Summary.

IF AT ANY TIME RCS pressure drops to IF the operator at this points determines to 2000 psig and continues to drop, THEN: implement the CAS action, THEN provide the following CUE:

1. TRIP the Reactor

2. GO TO 2-EOP-TRIP-1, Reactor CUE: Your evaluator will implement Trip or Safety Injection, AND the actions of EOP-TRIP-1. The CRS CONTINUE with this procedure. directs you to TRIP the Reactor AND CONTINUE implementing S2.OP-AB.PZR-0001.

Examiners Note: IF the operator

[***see Examiners Note***] initiates the CAS here, THEN Tripping the Reactor is a CRITICAL STEP.

3.2 Is POPS in service? No - Determines POPS is not in service by initial conditions or console indications.

3.3 Is the controlling Pressurizer Pressure YES - Determines Pressurizer Pressure Control Channel (I or III) failed? Control Channel I is failed.

3.5 PLACE the Master Pressure Controller in PLACES MPC in MANUAL (if not MANUAL previously performed).

Page 7 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

3.6 ADJUST MPC demand signal to be Operator ADJUSTS MPC demand using consistent with Attachment 2, to restore Attachment 2.

pressure to program value.

Examiners Note: MPC demand should Simulator Operator: ENSURE ET-3 is eventually be adjusted to 0% to close TRUE when operator places MPC in spray valves and turn on PZR heaters.

Manual and depresses the Increase Pressure pushbutton on MPC.

This will insert the malfunction for 2PS1 failing partially closed, 3.6 SELECT the other Pressure Control Operator selects Channel 3.

Channel 3.7 RETURN the MPC to AUTO Operator places MPC in AUTO ALTERNATE PATH STARTS HERE: 2PS1 Spray Valve will not fully close 2PS1 Spray Valve not fully closed Operator recognizes 2PS1 is not fully closed based on dual bezel indication (indeterminate position) and RCS pressure continues to SLOWLY lower (if MPC demand was adjusted to 0).

Examiners Note: Operator can go back to beginning of procedure or go directly to Step 3.17.

Page 8 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.17 Is a Spray Valve(s) failed? (Refer to Yes - Determines 2PS1 is NOT fully Attachment 2 for guidance) closed.

3.18 PLACE the Spray Valve(s) in MANUAL Depresses MANUAL PB for 2PS1.

Simulator Operator: ENSURE ET-4 is TRUE if operator depresses CLOSED pushbutton for 2PS1.

This will insert the malfunction for 2PS1 failing partially closed, 3.19 OPERATE the Spray Valves to control Depresses the CLOSE PB for 2PS1 and pressure consistent with Attachment 2. recognizes that 2PS1 will not fully close.

3.20 PLACE all Pressurizer heaters in MANUAL Determines all PZR heaters are in and ON MANUAL and ON.

3.21 Has pressure control been regained? No - Determines pressure control has not been regained since 2PS1 remains open AND RCS pressure is rapidly lowering.

3.22 Is RCS pressure dropping rapidly? NO, operator determines that RCS pressure is slowly lowering.

IF Yes - Operator GOES TO STEP 3.23 (Step 3.23 starts on page 11).

Examiners Note: The operator may choose to take the No or Yes path here.

Page 9 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.25 IF the Unit is on line, THEN COMMENCE a CUE: CRS will brief the crew on power power reduction in anticipation of tripping reduction, CONTINUE on with procedure.

the Reactor and stopping RCPs.

3.26 ATTEMPT to identify the leaking Spray Operator recognizes 2PS1 is not fully Valve by monitoring the following: closed based on dual bezel indication

Valve demand indication (indeterminate position).

Valve position indication

Spray line temperature, increasing OR elevated spray line temperature indicates spray valve leakage or failure.

3.27 Is a Containment entry possible? CUE: Shift Manager states Containment entry NOT possible at this time. Continue on with procedure.

3.29 WAIT at this point until one of the following CUE: CRS determines a Reactor Trip is occurs OR is required, THEN CONTINUE: required. Continue on with procedure.

A. The leaking spray valve is manually isolated. OR B. The SM/CRS determines a Reactor Trip is required. OR C. The SM/CRS determines stopping a RCP(s) is required 3.30 Is the leaking Spray Valve manually NO, since containment entry is not isolated? possible at this time.

3.31 Are Reactor Trip Breakers CLOSED? YES Page 10 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

3.32 PERFORM the following:

A. TRIP the Reactor Operator trips the Reactor.

B. Is Reactor Trip Confirmed? Operator confirms Rx is tripped.

Operator STOPs 21 and 23 RCPs C. STOP 21 and 23 RCPs D. IF Pressurizer Pressure continues CUE: JPM is Complete to drop, THEN STOP all but one RCP.

E. GO TO 2-EOP-TRIP-1 From Step 3.22, if Operator determines RCS pressure is dropping rapidly.

3.22 Is RCS pressure dropping rapidly? YES 3.23 Are Reactor Trip Breakers CLOSED? YES Page 11 of 15

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure Control System TASK: Respond to Failed open Pressurizer Spray Valve IAW AB.PZR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.24 PERFORM the following:

A. TRIP the Reactor Operator trips the Reactor.

B. Is Reactor Trip Confirmed? Operator confirms Rx is tripped.

Operator STOPs 21 and 23 RCPs C. STOP 21 and 23 RCPs D. IF Pressurizer Pressure continues CUE: JPM is Complete to drop, THEN STOP all but one RCP.

E. GO TO 2-EOP-TRIP-1 From Step 3.23 IF operator initiates CAS to Trip Rx prior to reaching Step 3.23.

3.23 Are Reactor Trip Breakers CLOSED? NO, based on taking CAS action to trip the reactor.

GO TO STEP 3.33

3.33 STOP 21 AND 23 RCPs: Depresses STOP PBs for 21 and 23 RCP and verifies start lights extinguish and stop lights illuminates.

CUE: JPM is complete when 21 & 23 RCPs are stopped.

Page 12 of 15

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE S2.OP-AB.PZR-0001:

Page 13 of 15

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 14 of 15

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

INITIATING CUE:

You are the Reactor Operator.

Respond to all indications and alarms.

Your evaluator will respond to all alarms not related to your task.

Page 15 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented TASK NUMBER: 1140730402 JPM NUMBER: 19-01 NRC Sim-b ALTERNATE PATH: X K/A NUMBER: 005 A2.03 IMPORTANCE FACTOR: 2.9 3.1 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.OP-AB.RHR-0001, Rev. 21 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Klein Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 24

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-b Rev # Date Description Validation Required 00 9-17-19 MODIFIED JPM for a loss of both RHR pumps. Yes 005 K/A A2.03: Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR pump/motor malfunction Page 2 of 24

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented TASK NUMBER: 1140730402 SIMULATOR IC: IC-202 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 21 RHR Pump trips N/A N/A N/A 02 22 RHR pump trips 00:00:03 N/A N/A ET-1

3. These malfunctions will simulate 21 RHR Pump tripping on electrical fault. 22 RHR pump will start then trip for unknown reasons. (Alternate Path) With the RCS depressurized and vented, the Operator will perform Attachment 8 COLD LEG Injection by transferring Charging Pump suction to RWST, opening the BIT Isolation valves, and closing the charging discharge valves (2CV68 or 2CV69).

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 EVENT TRIGGERS:

ET# Description Command 1 QAA03PRN, 22 RHR start bezel light 2

3 4

SPECIAL INSTRUCTIONS:

Ensure RHR process diagram on P250

Ensure bezel tags for 21 & 22 SI Pumps and 22 CV Pump being C/T

Additional instructor to assist in silencing alarms following reactor trip.

Page 3 of 24

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented TASK 1140730402 NUMBER:

INITIAL CONDITIONS:

Unit 2 is in Mode 5 following a 30 day refueling outage.

The RCS is depressurized AND vented using 2PS59 as the approved vent path.

The crew is performing S2.OP-IO.ZZ-0002, Cold Shutdown to Hot Standby.

Plant conditions are as follows:

PZR level is 25%

21 Charging Pump in service

21 and 22 SI Pumps are C/T

22 Charging Pump is C/T

RHR Letdown Booster Pump in service with 2CV8 throttled

RCS temperature is 154 °F.

22 RHR Pump is aligned for Shutdown Cooling INITIATING CUE:

You are the Reactor Operator.

The in-service RHR pump (21 RHR Pump) providing shutdown cooling has just tripped due to an electrical fault on the motor.

INITIATE S2.OP-AB.RHR-0001, Loss of RHR.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Initiates COLD LEG Injection by transferring Charging Pump suction to RWST, opening BIT Isolation valves and closing Charging discharge valve IAW S2.OP-AB.RHR-0001, Attachment 8.

Page 4 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: Fill in the JPM Start Time when the Note:

student acknowledges the Initiating

21 and 22 SI Pumps are C/T Cue.

22 Charging Pump is C/T

21 Charging Pump in service START TIME:___________________

CET 160 °F 3.1 INITIATE Attachment 1, Continuous CUE: CRS will initiate the CAS, Action Summary CONTINUE on with procedure.

3.2 IF the RCS is vented to the CUE: Equipment hatch is CLOSED.

Containment atmosphere with the Containment Equipment hatch OPEN AND at least two RCS loops are filled with associated SGs available, THEN CLOSE the vent path prior to Core Boil. (Refer to ORAM report or Attachment 4)

NOTE 0% Pressurizer Level Cold Cal.

indication corresponds to 108.92 ft.

elevation, when the RCS is filled and vented.

3.3 Is RCS aligned for operation <101 ft. No elevation (Reduced Inventory)?

Page 5 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.5 Is the loss of RHR due to a Yes mechanical failure or loss of electrical power to the in-service RHR Pump?

3.6 GO TO Step 3.50 3.50 Is a heat sink available for Residual Yes Heat Removal?

___ Component Cooling to RHR System

___ Service Water to Component Cooling System 3.51 Is an RHR Loop available? Yes (22 RHR is available aligned for shutdown cooling)

Page 6 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.52 PLACE the alternate RHR Loop in Performs Attachment 3 to start 22 service: RHR Pump.

___IF alternate RHR Loop is aligned for ECCS, THEN PERFORM Operator performs the following Attachment 2, Aligning RHR Loop actions in Attachment 3:

From ECCS To Shutdown Cooling.

Closes 21RH18 OR

Closes 21CC16

___IF alternate RHR Loop is aligned

Opens 22CC16 for Shutdown Cooling, THEN

Starts 22 RHR Pump PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling.

ALTERNATE PATH STARTS HERE: 22 RHR Pump Trips Examiners Note:

The Operator may return to the procedure step in effect (Step 3.52)

OR can re-enter the AB procedure.

Page 7 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

RE- IF Operator re-enters the procedure, Operator performs the following steps:

ENTER THEN the following steps will be AB performed: 3.1 - CUE: Attachment 1 is being performed by extra operator.

3.2 - N/A 3.3 - No 3.5 - Yes 3.6 - GO TO Step 3.50 3.50 - Yes 3.51 - Return to Step 3.31 3.31 - Continue 3.32 - Initiate Attachment 8, Cold Leg Injection 3.53 Is RHR in service? No. 22 RHR Pump tripped.

RETURNS to STEP 3.7 3.7 CHECK RHR cooling availability as follows:

A. Is any RHR pump running? No Page 8 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.9 PERFORM the following: Performs actions as follows

___ STOP 2 RHR Letdown Booster Depresses stop PB for L/D Booster Pump Pump

___ ISOLATE Sampling activities CUE: No sampling is in progress

___ ISOLATE Normal Letdown to Verifies Normal L/D not in service CVCS

___ ISOLATE Excess Letdown Verifies Excess Letdown not in service

___ ISOLATE RHR Letdown to Depresses CLOSED PB for 2CV8 CVCS

___ TERMINATE any known CUE: CRS will terminate any maintenance or testing in progress maintenance or testing in progress.

Page 9 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

3.10 DETERMINE time to core boiling Determines time to core boiling using Attachment 4, Time To Reach (dependent on CET):

Boiling After Loss of RHR or Attachment 5, Heatup Rate For Loss Using Attachment 4 page 15, Time Of RHR Cooling, as applicable, if not to Saturation After Core Offload At already done in the daily ORAM Water Elev. 10% PZR Level and T-report. Hot between 170 - 180 F:

RCS at 170 F: Time to Boil = 40 mins RCS at 180 F: Time to Boil = 30 mins Using Attachment 5 page 2, Heatup Rate curve After Offload:

1 F per minute using heatup curve

[Acceptable Band = 30 - 40 mins]

3.11 Is RCS level >97.5 ft elevation and Yes stable or rising consistent with current RCS makeup (Charging, SI) and no excessive indication of RCS Leakage?

Page 10 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.12 Does the time to core boiling allow No adequate time for normal restoration AND local venting of CUE: CRS has determined RHR System? insufficient time is available to restore RHR system. Continue on with procedure.

3.20 CONTINUE Operator continues on with procedure 3.21 IS RCS level >101 ft.? Yes 3.22 SEND an Operator to locally monitor Operator recognizes no RHR pumps RHR Pump while starting. available and continues on.

CUE: If asked about status of RHR Pumps state the following: both RHR Pumps are being investigated.

Page 11 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.23 START one RHR Pump at full flow as Operator recognizes No RHR Pumps follows: available and continues on with

___IF alternate RHR Loop is aligned procedure.

for ECCS, THEN PERFORM Attachment 2, Aligning RHR Loop From ECCS To Shutdown Cooling.

OR

___IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling.

3.24 NOTIFY local Operator to perform Operator determines this step is Not observation at RHR Pumps: Applicable and continues on with

___ No abnormal noise procedure

___ No seal damage

___ No RHR suction pressure oscillations Page 12 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 3.25 Is RHR System normal as indicated No, no RHR Pumps are running.

by ALL of the following?

___ RHR Pumps - at least one running

___ RCS Level - >101 ft. elevation and stable or rising

___ RHR Flow - stabilized >1500 gpm

___ RCS Temperature - stable or lowering

___ No local indication of RHR Pump damage 3.30 STOP any running RHR Pumps. Operator recognizes no RHR Pumps are running and continues on with procedure.

3.31 CONTINUE Page 13 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

3.32 INITIATE one of the alternate Operator performs Attachment 8, methods of decay heat removal: Cold Leg Injection based on Core Exit TCS less than 200 F.

___ Attachment 7, Hot Leg Injection (Feed & Bleed - Preferred method if RCS not intact or Loops not filled and core exit TCs > 200°F)

___ Attachment 8, Cold Leg Injection (Feed & Bleed - Preferred Method if Core Exit TCs < 200°F)

___ Attachment 9, Steam Generator Reflux Cooling (RCS depressurized and no other means of decay heat removal is available)

___ Attachment 10, Forced Flow Or Natural Circulation Cooldown (RCS intact and filled to greater than 0% in the Pressurizer with Loops filled)

___ Attachment 11, Cooling the RCS with Spent Fuel Pool (Reactor Vessel Head Removed)

Page 14 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

ATT Attachment 8 COLD LEG 8 INJECTION (preferred method if RCS < 200 F) 1.0 MAKEUP to the RCS as follows:

1.A IF the BIT flowpath AND a Charging YES Pump is available, THEN ALIGN feed path to the RCS as follows:

1.A.1 1. OPEN RWST outlet to Charging Operator depresses the OPEN Pumps: pushbuttons for 2SJ1 or 2SJ2.

___ 2SJ1

___ 2SJ2

1.A.2 2. CLOSE VCT outlet to Charging Operator depresses the CLOSED Pumps: pushbuttons for 2CV40 or 2CV41.

___ 2CV40

___ 2CV41 1.A.3 IF both Centrifugal Charging Pumps N/A. 21 Charging Pump is in service.

are tagged out, THEN SEND Operator to release breaker for one Centrifugal Charging Pump.

Page 15 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

NOTE CAUTION Operator reads Caution and continues on with procedure.

When the PS26 is the vent path, maximum flow of < 300 gpm is CUE: IF asked about the nozzle required when steam generator dams, then state: nozzle dams are nozzle dams are installed. This may not installed.

be controller by throttling the pump discharge valve.

1.A.4 START the designated available Charging Pump AND FEED at 21 Charging Pump already running.

maximum rate by aligning the following valves in the Cold Leg Injection flow path:

___ OPEN BIT INLET: 2SJ4 or 2SJ5 Operator depresses the OPEN pushbutton for BIT valves 2SJ4 or

___ OPEN BIT OUTLET: 2SJ12 or 2SJ5 AND 2SJ12 or 2SJ13.

2SJ13 Operator CLOSES 2CV68 or 2CV69

___ CLOSE Charging Discharge by depressing the associated Isolation Valves: 2CV68 or 2CV69 CLOSED pushbutton.

JPM is Complete Page 16 of 24

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heal Removal System TASK: Respond to a Loss of Both RHR Pumps IAW S2.OP-AB.RHR-0001 in Mode 5 with RCS Depressurized and Vented STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: WHEN operator informs you the task Terminate JPM when 2CV68 or is complete, OR the JPM has been 2CV69 is closed.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 17 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE S2.OP-AB.PZR-0001:

Page 18 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 19 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 20 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 21 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 22 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 23 of 24

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is in Mode 5 following a 30 day refueling outage.

The RCS is depressurized AND vented using 2PS59 as the approved vent path.

The crew is performing S2.OP-IO.ZZ-0002, Cold Shutdown to Hot Standby.

Plant conditions are as follows:

PZR level is 25%

21 Charging Pump in service

21 and 22 SI Pumps are C/T

22 Charging Pump is C/T

RHR Letdown Booster Pump in service with 2CV8 throttled

RCS temperature is 154 °F.

22 RHR Pump is aligned for Shutdown Cooling INITIATING CUE:

You are the Reactor Operator.

The in-service RHR pump (21 RHR Pump) providing shutdown cooling has just tripped due to an electrical fault on the motor.

INITIATE S2.OP-AB.RHR-0001, Loss of RHR.

Page 24 of 24

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

TASK: Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK NUMBER: N0010070101 JPM NUMBER: 19-01 NRC Sim-c ALTERNATE PATH: X K/A NUMBER: 001 A2.11 IMPORTANCE FACTOR: 4.4 4.7 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.OP-ST.RCS-0001 Rev. 23 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Weidner Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-c Rev # Date Description Validation Required 00 8-13-19 Modified JPM. Added Alternate Path for continuous rod Yes motion when rod bank selected to Auto or Manual requiring operator to Manually trip the reactor.

001 K/A A2.11: Ability to (a) predict the impacts of the following malfunction or operation on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: situations requiring a reactor trip Page 2 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

TASK: Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK NUMBER: 1150070501 SIMULATOR IC: IC-203 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 RD0045, Uncontrolled Rod Insert in Auto N/A N/A N/A ET-1 TRUE 02

3. These malfunctions will simulate failure of rod control system when rods are selected to Auto or Manual (Alt Path) resulting in continuous rod insertion. The operator will mitigate the event by manually tripping the reactor.

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 KB433W1D, Rod Bank Selector Sw in Auto ET-1 ON 02 03 04 EVENT TRIGGERS:

ET# Description Command 1 KB433W1D, Rod bank Selector SW to Auto SPECIAL INSTRUCTIONS:

Rod bank selector switch selected to CBC position

Ensure ARPI screen is up on P-250.

For efficiency, provide the procedures to the operators up front to allow time to read and review.

Page 3 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

TASK: Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK NUMBER: 1150070501 INITIAL CONDITIONS:

Unit 2 is at 100% power BOL.

No major equipment is out of service and no Tech Specs are active.

The rod control system surveillance is in progress with the only remaining rod bank to test is Control Bank D.

INITIATING CUE:

You are the Reactor Operator.

The CRS directs you to complete the rod control system surveillance IAW S2.OP-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.

A Maintenance Technician is stationed at the Rod Control Power Cabinets (Relay Room)

CRS directs that 15 steps of rod insertion will be performed to ensure each rod moves at least 10 steps.

Pre-Test D bank rod positions were recorded and attached with your Cue Sheet.

Notify the CRS when the testing is complete.

Your evaluator will take care of all alarms not related to your task.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Correctly performs rod control surveillance using approved procedure

2. Responds to continuous rod movement by manually tripping the reactor.

Page 4 of 12

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step) S/U evaluation)

(# Sequential Critical Step)

ENSURE marked up copy of S2.OP-ST.RCS-0001 is open and marked up on console.

Provide copy of OP-AP-300-1001, PWR Control Rod Movement Requirements.

Operator reads and reviews procedures prior Operator reads P&Ls and reviews OP-AP-300-to start. 1001 prior to start CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

5.1.10 Operator checks Tave/Tref recorder on 2RP4 A. IF the reactor is critical, THEN ENSURE and determines Tavg is within +/-1 F of Tref.

TAVG is within +/-1°F of TREF.

5.1.10.B Operator rotates selector switch clockwise B. PLACE Bank Selector Switch in the "CBD" to the CBD position position.

Page 5 of 12

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step) S/U evaluation)

(# Sequential Critical Step) 5.1.10.C Contacts Maint Technician at Power Cabinets.

C. ENSURE GRP. SELECT "B" lights are illuminated on Rod Control System Power CUE: Technician reports GRP SELECT B Cabinets 21BD and 22BD. lights are illuminated on Cabinets 21 BD and 22BD.

5.1.10.D Operator inserts Control Bank D 15 steps.

D. MANEUVER Control Bank D at least 10 steps in any one direction.

5.1.10.E Evaluators Note: Operator may request to E. ENSURE each rod in Control Bank D insert rods additional steps, IF so, just restate indicated rod movement of at least 10 steps.

the request.

Operator monitors rod position on P-250 and determines D bank rods all moved at least 10 steps.

Optional CUE: Reactor Engineer reports rods indicate 10 step movement.

5.1.10.F Operator records test results as SAT.

F. RECORD CONTROL BANK D "Test Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment 1, Rod Control Assembly Data.

Page 6 of 12

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step) S/U evaluation)

(# Sequential Critical Step) 5.1.10.G G. RESTORE Control Bank D to the pre-test Operator withdraws Bank D to previous position. position (ARO) 5.1.11 ALIGN the Rod Control System as follows:

ALTERNATE PATH STARTS HERE: Continuous rod movement when rod bank is selected to Auto or Manual 5.1.11.A Operator checks Tave/Tref recorder on 2RP4 A. IF the reactor is critical, THEN ENSURE and determines Tavg is within 1 F of Tref.

TAVG is within +/-1°F of TREF.

5.1.11.B N/A B. IF Turbine Power is 15%, THEN PLACE Bank Selector Switch in the "MAN" position.

Simulator Operator: ENSURE ET-1 is TRUE when rods selected to Auto. This will insert MALF: RD0045, Uncontrolled Rod Insertion in AUTO AND MANUAL.

Page 7 of 12

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step) S/U evaluation)

(# Sequential Critical Step)

5.1.11.C CUE: IF asked, CRS directs rod bank selected C. IF Turbine Power is >15%, THEN PLACE to AUTO.

Bank Selector Switch in the "AUTO" OR "MAN" position as directed by the SM/CRS. Operator determines that Rx power is > 15%

and rotates selector switch counterclockwise to the AUTO position.

Operator announces that rods are stepping in and no runback in progress.

CUE: IF operator recommends to CRS to place rods in Manual, THEN state; understand placing rods to manual.

Operator places rod bank switch to Manual and reports rod motion has NOT stopped.

Operator Manually trips the Reactor.

JPM Complete once Reactor is Tripped.

Examiners Note:

The operator may refer to S2.OP-AB.ROD-0003, Continuous Rod Motion and take the actions in the AB to manually trip the reactor.

Page 8 of 12

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactivity Control (SF-1) - Control Rod Drive System (CRDS)

Perform Control Rod System Surveillance IAW S2.OP-ST.RCS-0001 TASK:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step) S/U evaluation)

(# Sequential Critical Step)

CUE: JPM is Complete Terminate the JPM when Reactor is tripped.

RECORD the STOP TIME.

STOP TIME:________________

Page 9 of 12

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC Sim-c NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 10 of 12

INITIAL CONDITIONS:

Unit 2 is at 100% power BOL.

No major equipment is out of service and no Tech Specs are active.

The rod control system surveillance is in progress with the only remaining rod bank to test is Control Bank D.

INITIATING CUE:

You are the Reactor Operator.

The CRS directs you to complete the rod control system surveillance IAW S2.OP-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.

A Maintenance Technician is stationed at the Rod Control Power Cabinets (Relay Room)

CRS directs that 15 steps of rod insertion will be performed to ensure each rod moves at least 10 steps.

Pre-Test D bank rod positions were recorded and attached with your Cue Sheet.

Notify the CRS when the testing is complete.

Your evaluator will take care of all alarms not related to your task.

Page 11 of 12

P-250 ARPI for Control Bank D (Pre-Test):

Page 12 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 TASK NUMBER: N0060040101 JPM NUMBER: 19-01 NRC Sim-d ALTERNATE PATH: K/A NUMBER: 006 A4.07 IMPORTANCE FACTOR: 4.4 4.4 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.OP-SO.SJ-0002, Rev. 24 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Klein Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: N/A Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-d Rev # Date Description Validation Required 00 8-15-19 006 K/A A4.07: Ability to manually operate and/or monitor in Yes the control room: ECCS pumps and valves Page 2 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 TASK NUMBER: N0060040101 SIMULATOR IC: IC-203 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01

3. No malfunctions are required for this JPM. Setup IC with 21 SI Accumulator level approx. 56%.

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 EVENT TRIGGERS:

ET# Description Command 1

2 3

4 SPECIAL INSTRUCTIONS:

Additional instructor to assist in silencing alarms following reactor trip.

Page 3 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 TASK N0060040101 NUMBER:

INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

INITIATING CUE:

You are the Reactor Operator.

RAISE level in 21 SI Accumulator Tank to at least 60% IAW IAW Section 5.2 of S2.OP-SO.SJ-0002, Accumulator Operations, using 21 SI pump.

Your evaluator will respond to all alarms not related to your task.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Raises level in 21 SI Accumulator to at least 60% or as directed IAW S2.OP-SO.SJ-0002.

Page 4 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

5.2 Accumulator Make-up using 21 Safety Injection Pump with RCS Temperature

>312°F OR the Reactor Vessel Head is Removed 5.2.1 ENSURE either of the following Operator determines RCS Cold Leg conditions exist: temperatures are > 312 F and

ALL RCS Cold Leg Temperatures continues on.

>312°F OR

The Reactor Vessel Head is Removed.

CAUTION Operator reads note and continues on.

NOTE Closing 21SJ134 may require entry into TSAS 3.5.2.

Page 5 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 5.2.2 IF RCS pressure is <2000 psig, Operators determines RCS is > 2000 THEN ENSURE CLOSED 21SJ134, psig and marks step as N/A.

COLD LEG DISCHARGE NOTE CAUTION Operator reads note and continues on.

A maximum of one Safety Injection Pump OR one Centrifugal Charging Pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is #312°F. This restriction also applies in Modes 5-6 when the head is on the reactor vessel.

5.2.3 START 21 Safety Injection Pump. Operator depresses the START pushbutton for 21 SI Pump.

5.2.4 OPEN 2SJ53, 21 SI PUMP Operator depresses the OPEN DISCHARGE TEST LINE VALVE. pushbutton for 2SJ53.

5.2.5 OPEN 2SJ123, TEST LINE TO CVCS Operator depresses the OPEN HUT. pushbutton for 2SJ123.

Page 6 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

NOTE CAUTION Operator reads note and continues on.

Do NOT cross-tie Accumulators at any time OPERABILITY is required (e.g.; filling, draining, venting or pressurizing more than one Accumulator at a time).

5.2.6 OPEN associated Accumulator fill Operator depresses the OPEN valve: pushbutton for 21SJ20.

___ 21SJ20, ACCUM FILL

___ 22SJ20, ACCUM FILL

___ 23SJ20, ACCUM FILL

___ 24SJ20, ACCUM FILL

5.2.7 When desired level is reached, CLOSE Operator depresses the CLOSE the associated Accumulator fill valve: pushbutton for 21SJ20 WHEN level

___ 21SJ20, ACCUM FILL is at least 60% or greater.

___ 22SJ20, ACCUM FILL

___ 23SJ20, ACCUM FILL Optional CUE: Level is 60%

___ 24SJ20, ACCUM FILL.

5.2.8 If required, REPEAT Steps 5.2.6 and Operator marks as N/A 5.2.7 to fill additional Accumulators.

Page 7 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Core Cooling System TASK: Raise Level in 21 SI Accumulator IAW S2.OP-SO.SJ-0002 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 5.2.9 CLOSE 2SJ53 Operator depresses CLOSE pushbutton for 2SJ53 5.2.10 CLOSE 2SJ123 Operator depresses CLOSE pushbutton for 2SJ123.

5.2.11 STOP 21 Safety Injection Pump. Operator depresses STOP pushbutton for 21 SI Pump.

CUE: JPM is Complete CUE: WHEN operator informs you the task is Terminate JPM when operator complete, OR the JPM has been stops 21 SI Pump.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 8 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE S2.OP-SO.SJ-0002:

Page 9 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 10 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 11 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

INITIATING CUE:

You are the Reactor Operator.

RAISE level in 21 SI Accumulator Tank to at least 60% IAW IAW Section 5.2 of S2.OP-SO.SJ-0002, Accumulator Operations, using 21 SI pump.

Your evaluator will respond to all alarms not related to your task.

Page 12 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA TASK NUMBER: N1150500502 JPM NUMBER: 19-01 NRC Sim-e ALTERNATE PATH: X K/A NUMBER: 026 A4.01 IMPORTANCE FACTOR: 4.5 4.3 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

2-EOP-TRIP-1, Rev. 33 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Klein Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Representative ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-e Rev # Date Description Validation Required 00 5-30-17 Added revision history and simulator setup pages. Editorial No comments from IP 71111.11 FASA.

01 4-16-18 Corrected minor editorial errors and added Figure 1 to Yes provide snapshot of EOP section used during JPM and added improved malfunctions table.

02 9-17-19 MODIFIED JPM to add 2CS16 and 2CS17 NaOH valves fail Yes to open.

Page 2 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 TASK NUMBER: N1150500502 SIMULATOR IC: IC-204 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 RC0001A, RCS Rupture of RC Loop 21 N/A N/A N/A N/A N/A 02 VL0087, 2CC131 Fails to Position N/A N/A N/A N/A 100 03 VL0056, 2CC190 Fails to Position N/A N/A N/A N/A 100 04 RP0277A, Auto CS fails to actuate N/A N/A N/A N/A N/A 05 RP0277B, Auto CS fails to actuate N/A N/A N/A N/A N/A 06 RP0276A, Auto Phase B fails to actuate N/A N/A N/A N/A N/A 07 RP0276B, Auto Phase B fails to actuate N/A N/A N/A N/A N/A 08 VL0013, 2CS16 fails to position N/A N/A N/A N/A 0 09 VL0014, 2CS17 fails to position N/A N/A N/A N/A 0

3. These malfunctions will simulate failure of CS to actuate. The operator will be required to manually actuate Phase B and CS using key switches. [Alternate Path] The operator will recognize that not all Phase B/CS valves are in their safeguards positions. The operator will manually reposition the valves to their safeguards position (closes 2CC131 and 2CC190, opens 2CS16 and 2CS17).

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity EVENT TRIGGERS:

ET# Description Command 1 KA617TCM, 2CC131 Closed PB DMF VL0087 2 KA618TCM. 2CC190 Closed PB DMF VL0056 3 KA404PNT, 2CS16 Open PB DMF VL0013 4 KA406PNT, 2CS17 Open PB DMF VL0014 SPECIAL INSTRUCTIONS: None Page 3 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 TASK NUMBER: N1150500502 INITIAL CONDITIONS:

A Large Break LOCA on Reactor Coolant Loop 22 has occurred.

The Reactor Automatically Tripped and SI was actuated

The crew has completed Steps 1 through 10 of 2-EOP-TRIP-1, Rx Trip or Safety Injection.

INITIATING CUE:

You are the Reactor Operator.

The CRS directs you to continue on with EOP-TRIP-1 starting at STEP 11.

Your evaluator will respond to any alarms not associated with your task.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Manually initiates Containment Spray using key switches.

3. Closes 2CC131 OR 2CC190 Phase B valves.

4. Opens 2CS16 OR 2CS17 NaOH Discharge Valves Page 4 of 10

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task Standard) EVAL (Required for UNSAT

(* Critical Step) S/U Evaluation)

(# Sequential Critical Step)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

The following steps are from 2-EOP-TRIP- Evaluators Note: The following EOP 1, Major Action for Containment Spray CAS actions were already implemented:

Actuation Verification, Step 11.

STOP RCPs Examiners Note: Figure 1 is a snapshot CLOSE charging pump mini flows that shows the exact EOP steps to follow along.

Step Has Containment Pressure remained less NO, Operator determines containment pressure 11 than 15 psig has NOT remained less than 15 psig.

Step Initiate Phase B and Spray Actuation Operator uses both Safeguards Keys and 11 simultaneously rotates both keys on 2CC1 to actuate Phase B and Spray Actuation on at least one Safeguards train.

Examiners Note: Operator can use one key at a time so long as the key switch is not rotated back to the initial position prior to removing the key.

Step Did any available CNMT Spray pump fail to No, Operator determines that both CS pumps 11.2 start are running.

Page 5 of 10

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task Standard) EVAL (Required for UNSAT

(* Critical Step) S/U Evaluation)

(# Sequential Critical Step)

Step Initiate Loop 21 thru 24 Main Steam Isolation Determines Loops 21 thru 24 Main Steam 11.3 Isolation previously actuated. (From hi-hi containment pressure signal)

Operator reports 21-24 RCPs are stopped.

Step Stop 21 thru 24 RCPs 11.3 ALTERNATE PATH STARTS HERE: 2CC131 and 2CC190 failed to close on Phase B AND 2CS16 and 2CS17 fail to open on CS signal.

Step Are valve groups in Table D in Safeguards NO, operator identifies that 2CC131 and 11.4 positions 2CC190 remain OPEN AND 2CS16 and 2CS17 remain CLOSED.

Step Place Valves in Safeguards position Operator depresses CLOSED pushbutton 11.4 for 2CC131 and 2CC190 and verifies Simulator Operator: ENSURE the following CLOSED bezel are illuminated.

Event Triggers are TRUE, this will delete the following malfunctions to enable the valves to Operator depresses the OPEN pushbutton reposition: for 2CS16 and 2CS17 and verifies OPEN bezel are illuminated.

ET-1: VL0013 for 2CS16 ET-2: VL0014 for 2CS17 CUE: JPM is Complete ET-3: VL0087 for 2CC131 ET-4: VL0056 for 2CC190 Examiners Note: Selecting Manual for 2CC131 is NOT required to close the valve.

Page 6 of 10

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Spray System TASK: Manually Initiate Containment Spray and Open Phase B Valves in EOP-TRIP-1 During a LOCA STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task Standard) EVAL (Required for UNSAT

(* Critical Step) S/U Evaluation)

(# Sequential Critical Step)

CUE: WHEN operator informs you the task is Terminate JPM when operator repositions complete, OR the JPM has been terminated Phase B/CS valves of EOP-TRIP-1.

for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 7 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Figure 1 (EOP-TRIP-1, Sheet 2):

Page 8 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC Sim-e NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 9 of 10

INITIAL CONDITIONS:

A Large Break LOCA on Reactor Coolant Loop 22 has occurred.

The Reactor Automatically Tripped and SI was actuated

The crew has completed Steps 1 through 10 of 2-EOP-TRIP-1, Rx Trip or Safety Injection.

INITIATING CUE:

You are the Reactor Operator.

The CRS directs you to continue on with EOP-TRIP-1 starting at STEP 11.

Your evaluator will respond to any alarms not associated with your task.

Page 10 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 TASK NUMBER: N1140230401 JPM NUMBER: 19-01 NRC Sim-f ALTERNATE PATH: K/A NUMBER: 015 A4.03 IMPORTANCE FACTOR: 3.8 3.9 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.OP-SO.RPS-0001, Rev. 6 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Klein Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: N/A Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-f Rev # Date Description Validation Required 00 9-17-19 015 K/A A4.03: Ability to manually operate and/or monitor in Yes the control room: Trip bypasses Page 2 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 TASK NUMBER: N1140230401 SIMULATOR IC: IC-205 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 NI0193A, PR CH N41 Fails H/L N/A N/A N/A N/A 200

3. This malfunction will simulate a power range NIS channel failing high. The JPM will require the operator to remove the channel from service IAW S2.OP-SO.RPS-0001.

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 EVENT TRIGGERS:

ET# Description Command 1

2 3

4 SPECIAL INSTRUCTIONS:

None.

Page 3 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 TASK N1140230401 NUMBER:

INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

Power Range NIS Channel 2N41 has failed high.

The crew has placed rod control in Manual and performed all the required actions in S2.OP-AB.NIS-0001, Nuclear Instrumentation System Malfunction.

The following OHA Alarms are lit:

o E-15, PR HI RNG FLUX HI o E-31, PR OVRPWR ROD STOP o E-39, PR CH DEV o E-47, PR NEUT FLUX RATE HI INITIATING CUE:

You are the Plant Operator.

REMOVE the failed 2N41 Channel from service IAW S2.OP-SO.RPS-0001, Nuclear Instrumentation Channel Trip/Restoration (see attached pages).

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Removes 2N41 Channel from service by performing Steps 5.1.5.A thru 5.1.5.E correctly IAW S2.OP-SO.RPS-0001.

Page 4 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

5.1 Placing 2N41 Power Range NI in Tripped Condition IAW S2.OP-SO.RPS-0001 5.1.1 ENSURE that tripping of associated Operator checks 2RP4 panel and bistable(s) will NOT result in an ESF ensures tripping bistable will not result OR RPS actuation in Rx Trip.

5.1.2 ENSURE 2N41 Channel is NOT Operator checks 2N41 recorder and selected on NIS Recorder 2NR45 ensures not selected on 2N41 recorder.

5.1.3 ENSURE Rod Control is in Manual Operator verifies rod control is in Manual.

5.1.4 ENTER T/S 3.3.1.1, Reactor Trip CUE: CRS will enter Tech Spec System Instrumentation for 2N41. 3.3.1.1 for 2N41.

NOTE Operator reads note and continues on Steps 5.1.5 through 5.1.7 may be with procedure.

performed in any order 5.1.5 At NI Rack No. 81, PERFORM the Operator goes to back of control room following: (simulator).

Page 5 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

5.1.5. PLACE DETECTOR CURRENT Operator places DETECTOR A COMPARATOR, UPPER SECTION, CURRENT COMPARATOR, UPPER switch in PRN41 position AND SECTION switch to the PRN41 ENSURE the following: position.

___ CHANNEL DEFEAT lamp Operator verifies CHANNEL illuminates. DEFEAT lamp is lit.

___ OHA E-38, UPPER SECT DEV Note: OHA E-38 was NOT in prior to ABV 50% PWR, clears. tripping channel.

5.1.5. PLACE DETECTOR CURRENT Operator places DETECTOR B COMPARATOR, LOWER SECTION, CURRENT COMPARATOR, LOWER switch in PRN41 position AND SECTION switch to the PRN41 ENSURE the following: position.

___ CHANNEL DEFEAT lamp Operator verifies CHANNEL illuminates. DEFEAT lamp is lit.

___ OHA E-46, LOWER SECT DEV Note: OHA E-46 was NOT in prior to ABV 50% PWR, clears. tripping channel.

5.1.5. PLACE POWER MISMATCH BYPASS Operator places POWER C switch in BYPASS PR N41. (Defeats MISMATCH BYPASS switch in input to Rod Control) BYPASS PR N41 position.

Page 6 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

5.1.5. PLACE ROD STOP BYPASS switch in Operator places ROD STOP D BYPASS PR N41 AND ENSURE the BYPASS switch to BYPASS PR N41 following: position.

___ 2RP4 - OVER POWER ROD Operator verifies 2RP4 OVER STOP MANUAL BYPASS, CH I is POWER ROD STOP MANUAL illuminated. BYPASS, CH I is lit.

___ OHA E-31, PR OVERPWR ROD Operator verifies OHA E-31 is STOP, is clear. cleared.

5.1.5. PLACE COMPARATOR CHANNEL Operator places COMPARATOR E DEFEAT switch in N41 AND ENSURE CHANNEL DEFEAT switch in N41 the following: position.

___ COMPARATOR DEFEAT lamp is Operator verifies COMPARATOR illuminated. DEFEAT lamp is lit.

___ OHA E-39, PR CH DEV, is clear. Operator verifies OHA E-39 is cleared.

CUE: JPM is Complete Page 7 of 12

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Instrumentation TASK: Remove a Power Range Channel from Service IAW S2.OP-SO.RPS-0001 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: WHEN operator informs you the task is Terminate JPM when operator complete, OR the JPM has been completes Step 5.1.5.E.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 8 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 9 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The Unit 2 is operating at 100% power with no major equipment out of service.

Power Range NIS Channel 2N41 has failed high.

The crew has placed rod control in Manual and performed all the required actions in S2.OP-AB.NIS-0001, Nuclear Instrumentation System Malfunction.

The following OHA Alarms are lit:

o E-15, PR HI RNG FLUX HI o E-31, PR OVRPWR ROD STOP o E-39, PR CH DEV o E-47, PR NEUT FLUX RATE HI INITIATING CUE:

You are the Plant Operator.

REMOVE the failed 2N41 Channel from service IAW S2.OP-SO.RPS-0001, Nuclear Instrumentation Channel Trip/Restoration (see attached pages).

Page 10 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 11 of 12

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE Page 12 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 TASK NUMBER: N1150190501 JPM NUMBER: 19-01 NRC Sim-g ALTERNATE PATH: K/A NUMBER: 039 A4.07 IMPORTANCE FACTOR: 2.8* 2.9 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

2-EOP-SGTR-1, Rev. 32 (checked 1-13-20)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 15 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-13-20 Instructor Validated By: Moore / Klein Date:

SME or Instructor Approved By: Date:

Training Department Approved By: N/A Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC Sim-g Rev # Date Description Validation Required 00 9-18-19 039 K/A A4.03: Ability to manually operate and/or monitor in Yes the control room: Steam dump valves Page 2 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 TASK NUMBER: N1150190501 SIMULATOR IC: IC-206 MALFUNCTIONS:

1. Reset the simulator to the above IC #.

2. Verify the following events on the Summary/ET Trigger Lists:

MALF Description Delay Initial Ramp Trigger Severity ID # Time Value Time 01 SG0078D, 24 SG Tube Rupture N/A N/A N/A N/A 650

3. This malfunction will simulate a steam generator tube rupture on 24 SG. The JPM will require the operator to perform RCS cooldown using steam dumps IAW Step 10 of EOP-SGTR-1.

OVERRIDES / REMOTES:

ID # Description Delay Initial Ramp Trigger Condition/

Time Value Time Severity 01 EVENT TRIGGERS:

ET# Description Command 1

2 3

4 SPECIAL INSTRUCTIONS:

None.

Page 3 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 TASK N1150190501 NUMBER:

INITIAL CONDITIONS:

The Unit 2 Reactor was manually tripped and Safety Injection was actuated due to a verified Steam Generator Tube Rupture on 24 Steam Generator.

All required actions in EOP-TRIP-1 are complete.

The crew is currently implementing EOP-SGTR-1, Steam Generator Tube Rupture, and all steps up to Step 9 are complete.

INITIATING CUE:

You are the Plant Operator.

The CRS DIRECTS you to PERFORM an RCS Cooldown starting at Step 10 of 2-EOP-SGTR-1.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Correctly implements the steps of EOP-SGTR-1 to cooldown the RCS using steam dumps to the required temperature of 503 F.

Page 4 of 11

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

2-EOP-SGTR-1 Sheet 2, STEP 10

10 DETERMINE REQUIRED RCS TEMP Operator uses Table B and USING TABLE B determines required RCS temperature based on current ruptured 24 SG pressure (approx.

1045 psi) is 503 F.

10.1 IS INTACT SG AVAILABLE FOR Yes, Operator determines 3 intact COOLDOWN SGs are available for cooldown.

10.2 ARE CONDENSER STEAM DUMPS Yes, Operator determines steam AVAILABLE dumps are available.

Examiners Note: The operator will need to determine if steam dumps are available or not.

PLACE STEAM DUMPS IN MANUAL Operator depresses the MANUAL pushbutton on Pressure Mode bezel.

Page 5 of 11

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

ADJUST STEAM PRESSURE VALVE Operator adjusts demand by DEMAND TO 0% depressing the DECREASE DEMAND pushbutton on the Pressure Mode bezel.

Examiners Note: The valve demand will be already indicating 0% so no operation action is required.

PLACE STEAM DUMPS IN MS Operator depresses the MS PRESS PRESS CONTROL CONTROL pushbutton on the Control Mode bezel.

10.3 Operator depresses the BYPASS When RCS Tavg Low-Low is reached, TAVG pushbutton WHEN Tavg Low-THEN depress BYPASS TAVG Low is reached.

pushbutton.

Operator continues on with procedure.

Examiners Note: Operator needs to monitor CETs, Tavg and steam dump valves in order to determine when this step should be performed, otherwise the steam dump valves will close and the cooldown will stop.

Page 6 of 11

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

Operator adjust steam pressure ADJUST STEAM PRESSURE VALVE valve demand to 25% by DEMAND TO 25%. depressing the INCREASE DEMAND pushbutton on the Pressure Mode bezel.

10.5 IS HOTTEST CET LESS THAN RCS No.

COOLDOWN TEMP Page 7 of 11

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation) 10.8 CUE: The crew will continue on with WHEN HOTTEST CET LESS THAN SGTR-1, CRS directs you to monitor REQUIRED RCS COOLDOWN TEMP the RCS cooldown.

THEN DO STEPS 10.6 AND 10.7 Operator WAITs until required CET temperature is reached.

Examiners Note: It will take approx.

5-6 minutes to reach target CET temperature.

Examiners Note: The operator may adjust AFW flows to intact SGs prior to or during the cooldown as necessary.

Optional CUE: At Lead Examiners discretion, the following cue may be used: hottest CETs are now indicating less than your target temperature.

Page 8 of 11

OPERATIONS TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Secondary System TASK: Perform RCS Cooldown using Steam Dumps IAW EOP-SGTR-1 STEP STEP STANDARD COMMENTS

No. (Shaded area denotes Critical Step) (Bolded area identifies Task EVAL (Required for UNSAT

(* Critical Step) Standard) S/U Evaluation)

10.6 Operator places steam dump STOP COOLDOWN pressure control in Auto by depressing the AUTO pushbutton on the Pressure Mode bezel OR manually lowers demand to close steam dumps to maintain temperature.

CUE: JPM is Complete 10.7 DUMP STEAM TO MAINTAIN RCS TEMP LESS THAN REQUIRED CUE: WHEN operator informs you the task is Terminate JPM when operator complete, OR the JPM has been completes Step 10.6.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 9 of 11

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 10 of 11

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The Unit 2 Reactor was manually tripped and Safety Injection was actuated due to a verified Steam Generator Tube Rupture on 24 Steam Generator.

All required actions in EOP-TRIP-1 are complete.

The crew is currently implementing EOP-SGTR-1, Steam Generator Tube Rupture, and all steps up to Step 9 are complete.

INITIATING CUE:

You are the Plant Operator.

The CRS DIRECTS you to PERFORM an RCS Cooldown starting at Step 10 of 2-EOP-SGTR-1.

Page 11 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

TASK NUMBER: N0620110101 JPM NUMBER: 19-01 NRC Sim-h ALTERNATE PATH: X K/A NUMBER: 062 A2.04 IMPORTANCE FACTOR: 3.1 3.4 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator / Perform S2.OP-SO.4KV-0008, Rev. 13 (checked 1-13-20

REFERENCES:

S2.OP-AR.ZZ-0009, Rev 28 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R Chan Date: 1-13-20 Instructor Validated By: Moore / Weidner Date: 1-13-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 14

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 16-01 NRC Sim-h Rev # Date Description Validation Required 00 9-29-17 Added revision history and simulator setup pages. Editorial Yes comments from IP 71111.11 FASA.

01 12-15-17 Updated to reflect procedure change to S2.OP-SO.4KV- No 0008, Rev. 13 that corrected a typographical error on P&L 3.3 that could confuse the operator in response to the malfunction.

Page 2 of 14

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

TASK NUMBER: N0620110101 SIMULATOR IC: IC-207 MALFUNCTIONS / REMOTES:

1. Reset the simulator to IC-208.

2. Verify the following actions in the Summary/ET Trigger Lists:

a. ET-1: KC509PC0 - 2BGGD 2G Group Bus Feeder Close, INSERT MALF: EL0142 -

Loss of 2G 4160 V Group Bus.

3. This malfunction will simulate a loss of the 2G Group Bus only and result in the loss of one (1)

RCP (24 RCP). Based on S2.OP-SO.4KV-0008, Precautions and Limitations 3.3, the crew should respond to OHA J-39 when it does NOT clear following bus transfer. The OHA ARP will direct you to J-38 to TRIP the Reactor and GO TO EOP-TRIP-1.

4. Check APT voltage the same as the Group bus voltage pre-req 2.3.3

5. This completes the setup for this JPM.

OVERRIDES: None SPECIAL INSTRUCTIONS:

Provide marked up hard copy of S2.OP-SO.4KV-0008.

Setup to only deenergize one (1) Group Bus, THEN the operator will receive OHA J-39, 4KV GRP BUS XFER FAIL.

The OHA ARP for J-39 will direct operator to J-38 for response.

The OHA ARP for J-8 will direct operator to D-31 for response.

OHA J-38 states: IF ANY RCP Trips THEN:

o TRIP Reactor o GO TO EOP-TRIP-1 Page 3 of 14

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

TASK NUMBER: N0620110101 INITIAL CONDITIONS:

Unit 2 power ascension is in progress following refueling outage.

Reactor power is at 20%.

The Main Generator is connect to the grid with 190 MWe output.

Steam Dumps are in Tavg Mode -Auto

Rod Control is in Manual (D-104) until Group Buses are transferred

Group Buses are currently powered from the Station Power Transformers (SPT).

INITIATING CUE:

You are the Plant Operator.

The CRS directs you to TRANSFER all 4KV Group Buses from their respective Station Power Transformers (SPT) to the Aux Power Transformers (APT) IAW S2.OP-SO.4KV-0008, 4KV Group Buses Power Supply Transfer in the following order:

1. 2F IAW section 5.2

2. 2G IAW section 5.3

3. 2H IAW section 5.4

4. 2E IAW section 5.1

All pre-requisites are completed SAT.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Correctly performs the transfer of 2F 4KV Group bus from SPT to APT IAW S2.OP-SO.4KV-0008.

2. Manually trips the Reactor IAW Alarm Response Procedure following the loss of one RCP (24 RCP).

Page 4 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

PROVIDE a copy of S2.OP-SO.4KV-0008 to the operator.

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

Operator reviews Precautions and P&L Examiners Note: The operator may Limitations.

also review the OHA ARPs prior to starting the JPM.

Examiners Note: P&L 3.3 will be applicable when the 2G 4KV Bus de-energizes:

When transferring a group Bus from SPT to APT, OHA J-39, GROUP BUS XFER FAIL, will illuminate then clear on bus transfer (expected response). OHA J-39 annunciator response is applicable when the alarm does NOT clear following bus transfer.

5.2 Transferring 2F 4KV Group Bus from 22 SPT to 2 APT 5.2.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are clear.

Page 5 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step) 5.2.2 ENSURE 2A APT voltage is 4.22 - Checks 2A APT reading on 2CC3 and 4.36KV. ensures 2A APT voltage is 4.22 - 4.36KV.

5.2.3 IF Auxiliary Power Unit Isolation Transfer Determines Auxiliary Power Unit Isolation is tripped, Transfer is not tripped from control console THEN RESET Auxiliary Power Unit indication.

Isolation Transfer (UIT).

5.2.4 PRESS the Mimic Bus 2F GROUP BUS Depresses Mimic Bus 2F GROUP BUS INFEED 2BFGD BREAKER pushbutton, INFEED 2BFGD BREAKER pushbutton AND ENSURE console bezel 2BFGD and verifies console bezel 2BFGD MIMIC MIMIC BUS INTLK CLOSE SELECTION BUS INTLK CLOSE SELECTION is illuminates. Illuminated.

Page 6 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

5.2.5 *PRESS control console 2BFGD CLOSE Depresses control console 2BFGD pushbutton, CLOSE pushbutton and verifies the AND ENSURE the following: following:

A. *22FSD is OPEN. A. 22FSD OPEN bezel is illuminated.

B. *2BFGD is CLOSED. B. 2BFGD CLOSED bezel is illuminated.

C. *2F 4KV Group Bus voltage is 4.22 - C. 2F 4KV Group Bus voltage is 4.22 -

4.36KV. 4.36KV.

D. Console bezel 2BFGD MIMIC BUS D. Console bezel 2BFGD MIMIC BUS INTLK CLOSE SELECTION is INTLK CLOSE SELECTION is extinguished. extinguished.

5.3 Transferring 2G 4KV Group Bus from 22 SPT to 2 APT 5.3.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are clear.

5.3.2 ENSURE 2A APT voltage is 4.22 - Checks 2A APT reading on 2CC3 and 4.36KV. ensures 2A APT voltage is 4.22 - 4.36KV.

5.3.3 IF Auxiliary Power Unit Isolation Transfer Determines Auxiliary Power Unit Isolation is tripped, THEN RESET Auxiliary Power Transfer is not tripped from control console Unit Isolation Transfer (UIT). indication.

Page 7 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

5.3.4 PRESS Mimic Bus 2G GROUP BUS Depresses Mimic Bus 2G GROUP BUS INFEED 2BGGD BREAKER pushbutton, INFEED 2BGGD BREAKER pushbutton, AND ENSURE console bezel 2BGGD AND verifies console bezel 2BGGD MIMIC BUS INTLK CLOSE SELECTION MIMIC BUS INTLK CLOSE SELECTION illuminates. is illuminated.

ALTERNATE PATH STARTS HERE: 2G Bus fails to transfer resulting in de-energized bus and loss of 24 RCP.

Page 8 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

5.3.5 *PRESS control console 2BGGD CLOSE Operator determines 2G 4KV Group bus pushbutton, AND ENSURE the following: did not transfer and announces several unexpected OHA alarms.

A. *22GSD is OPEN. The following OHA alarms are applicable to B. *2BGGD is CLOSED. the loss of 2G 4KV bus and will provide the C. *2G 4KV Group Bus voltage is 4.22 - operator with the required actions:

4.36KV.

J-8 (2G 4KV GRP BUS DIFF/OVRLD),

D. Console bezel 2BGGD MIMIC BUS J-38 (4KV GRP BUS UNDRVOLT),

INTLK CLOSE SELECTION is J-39 (4KV GRP BUS XFER FAIL), and extinguished. D-31 (24 RCP BKR OPEN/FLO LO).

CUE: If requested to dispatch an operator to inspect the 4KV group Bus, state; the CRS will send an operator to investigate.

Operator identifies that OHA ARPs for J-38 or D-31 requires tripping the Reactor and going to EOP-TRIP-1 (OHA response are provided in next steps).

CUE: If operator informs CRS of action to trip the reactor, state; take actions per the alarm response procedure.

Operator TRIPs the Reactor .

Page 9 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

OHA 2G 4KV GRP BUS DIFF/OVRLD IF the operator refers to this ARP, THEN ARP the operator determines that Step 3.3 is J-8 applicable and performs the following:

3.3 RESPOND to OHA D-31 for loss of 24 RCP, AND OHA D-30 for loss of 23 Operators responds IAW OHA D-31 (see RCP (if in alarm) page 11)

OHA 4KV GRP BUS XFER FAIL IF the operator refers to this ARP, THEN is ARP directed to:

J-39 3.0 OPERATOR ACTIONS GOES TO ARP for J-38 for response.

GO TO OHA J-38 response OHA 4KV GRP BUS UNDRVOLT IF the operator refers to this ARP, THEN

ARP the operator determines that Step 3.5 is J-38 applicable and performs the following:

3.0 OPERATOR ACTIONS:

Operator TRIPs the Reactor.

3.5 IF ANY RCP trips, THEN:

CUE: JPM is Complete A. TRIP Reactor B. GO TO 2-EOP-TRIP-1 Page 10 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

OHA 24 RCP BKR OPEN/FLO LO IF the operator refers to this ARP, THEN

ARP the operator determines that Step 3.5 is D-31 applicable and performs the following:

3.0 OPERATOR ACTIONS:

Operator TRIPs the Reactor.

3.5 IF Reactor Coolant System flow degradation exists, THEN:

CUE: JPM is Complete A. TRIP the Reactor Note: Stopping 24 RCP is not required due B. STOP 24 RCP to the bus de-energizing.

C. IF RCP shutdown was due to RCP Seal Leakoff 6 gpm, THEN simultaneously PERFORM the following:

Between 3-5 minutes after stopping 24 RCP, CLOSE 24CV104, SEAL LEAKOFF.

GO TO 2-EOP-TRIP-1 D. GO TO 2-EOP-TRIP-1 Page 11 of 14

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: A.C. Electrical Distribution TASK: Transfer 4KV Group Buses To The Alternate Power Supply (SPT to APT)

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step)

(Bolded area identifies Task Standard) EVAL (Required for UNSAT NO. (* Critical Step)

S/U evaluation)

(# Sequential Critical Step)

CUE: JPM is Complete Terminate the JPM when the Rx trip has been initiated.

RECORD the STOP TIME.

STOP TIME:________________

Page 12 of 14

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM #: 19-01 NRC Sim-h NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 13 of 14

INITIAL CONDITIONS:

Unit 2 power ascension is in progress following refueling outage.

Reactor power is at 20%.

The Main Generator is connect to the grid with 190 MWe output.

Steam Dumps are in Tavg Mode -Auto

Rod Control is in Manual (D-104) until Group Buses are transferred

Group Buses are currently powered from the Station Power Transformers (SPT).

INITIATING CUE:

You are the Plant Operator.

The CRS directs you to TRANSFER all 4KV Group Buses from their respective Station Power Transformers (SPT) to the Aux Power Transformers (APT) IAW S2.OP-SO.4KV-0008, 4KV Group Buses Power Supply Transfer in the following order:

1. 2F IAW section 5.2

2. 2G IAW section 5.3

3. 2H IAW section 5.4

4. 2E IAW section 5.1

All pre-requisites are completed SAT.

Page 14 of 14

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001.

TASK NUMBER: 1130070501 JPM NUMBER: 19-01 NRC IP-i ALTERNATE PATH: K/A NUMBER: APE 068 AA1.22 IMPORTANCE FACTOR: 4.0 4.3 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: In Plant / Simulate

REFERENCES:

S2.OP-AB.CR-0001, Rev. 23 (checked 1-15-20)

TOOLS AND EQUIPMENT: JAM Key VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-15-20 Instructor Validated By: Moore / Klein Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC IP-i Rev # Date Description Validation Required 00 6-20-17 Added revision history and simulator setup pages. Editorial No comments from IP 71111.11 FASA. Incorporated comments from validation.

01 9-18-19 APE 068 AA1.22: Ability to operate and/or monitor the Yes following as they apply to the Control Room Evacuation:

Flow control valve for RCS charging header Deleted actions to locally trip the reactor. Added photo of Panel 216 to assist evaluator.

Page 2 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001.

TASK NUMBER: 1130070501 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

This JPM is located inside the Unit 2 RCA.

NOTE: Evaluator must have a JAM key to give to operator at start of JPM. Operators do not have individual JAM keys!

Notification to control room will be required when opening panel door in charging alley.

Page 3 of 11

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001.

TASK NUMBER: 1130070501 INITIAL CONDITIONS:

The Unit 2 Control Room has been evacuated in accordance with S2.OP-AB.CR-0001, Control Room Evacuation.

A reactor trip from 100% was initiated prior to evacuating the Control Room.

INITIATING CUE:

You are directed to take local control of charging flow IAW S2.OP-AB.CR-0001, Control Room Evacuation, Attachment 5, starting at Step 8.0 (see attached page).

Steps 1.0-7.0 of Attachment 5 have been completed.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Locally controls Charging flow using hand air operator IAW S2.OP.AB.CR-0001

2. Correctly adjusts air operator to change charging flow to the desired flow of 70 gpm.

Page 4 of 11

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

Evaluator provide blank copy of Attachment 5, a JAM Key, and state: You have a radio and all required keys.

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

Proceeds to Unit 2 Panel 216-1, Chg Pmps FL & PR Inst Pnl.

Examiners Note: Panel 216-1 will cause an alarm in the Control Room when opened. The Control Room must be notified prior to opening this panel, and when it is secured.

8.0 TAKE control of 2CV55, Cent Chg Pmp Flow Cont Valve, by performing the following:

8.1 RECORD the charging flow as indicated on Records charging flow from 2FI-128A, 2FI-128A. Charging Pump Flow Indication.

_____ gpm indicated on 2FI-128A (Typically around 90 gpm)

Locates local E/P Bypass Selector

8.2 PLACE local E/P Bypass Line Selector Valve Valve and simulates rotating valve in Manual.

(clockwise) to MAN position.

Page 5 of 11

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation) 8.3 Using the MANUAL hand air operator, Reads flowrate from 2FI-128A (Note:

ENSURE that the flow rate as noted in Step field labeled as 2FT-128A), Charging 8.1 is being maintained with 2CV55. Pump Flow Indication to ensure the flow rate is maintained with 2CV55.

CUE #1: The flow rate is the same as recorded in Step 8.1. The CRS directs you to adjust charging flow to 70 gpm.

(OR a value not currently indicating on 2FI-128A).

Examiners Note: the task here is to see if the operator understands how to operate the hand sender to adjust charging flow.

Page 6 of 11

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Abnormal Plant Evolutions TASK: Locally Control Charging Flow IAW S2.OP-AB.CR-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

Adjust charging flow using hand air operator. Simulates rotating hand air operator in the clockwise direction to RAISE air

pressure to lower charging flow to 70 gpm.

CUE #1: Charging flow is 70 gpm.

CUE #2: IF hand sender is rotated counter-clockwise,THEN state the following:

charging flow has increased to 100 gpm.

Examiners Note: Raising air pressure lowers flow, Decreasing air pressure raise flow. (2CV55 fails open on loss of air)

CUE #3: JPM is Complete when flow is adjusted to the desired value.

CUE: WHEN operator informs you the task is Terminate JPM when operator complete, OR the JPM has been terminated completes adjusting charging flow.

for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 7 of 11

Inside Charging Panel 216:

Page 8 of 11 Rev. 0

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC IP-i NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 9 of 11 Rev. 0

INITIAL CONDITIONS:

The Unit 2 Control Room has been evacuated in accordance with S2.OP-AB.CR-0001, Control Room Evacuation.

A reactor trip from 100% was initiated prior to evacuating the Control Room INITIATING CUE:

You are directed to take local control of charging flow IAW S2.OP-AB.CR-0001, Control Room Evacuation, Attachment 5, starting at Step 8.0 (see attached page).

Steps 1.0-7.0 of Attachment 5 have been completed.

Page 10 of 11 Rev. 0

Page 11 of 11 Rev. 0 Operations Training Program Job Performance Measure STATION: SALEM SYSTEM: Generic Administrative - Conduct of Operations TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 TASK NUMBER: N1150140501 JPM NUMBER: 19-01 NRC IP-j ALTERNATE PATH: K/A NUMBER: G2.1.23 IMPORTANCE FACTOR: 4.3 4.4 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: In Plant / Simulate SC.OP-SO.CA-0001, Rev. 14 (checked 1-15-20)

REFERENCES:

DWG 604495, Rev. 2 and 205347 Sht. 2 Rev. 43 (H-6)

TOOLS AND EQUIPMENT: SBO Compressor Building is normally unlocked (L-3 key if locked)

VALIDATED JPM COMPLETION TIME: 20 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-15-20 Instructor Validated By: Moore / Weidner Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 18

Operations Training Program Job Performance Measure REVISION HISTORY JPM NUMBER: 19-01 NRC IP-j Rev # Date Description Validation Required 00 6-16-17 Added revision history and simulator setup pages. Editorial No comments from IP 71111.11 FASA.

01 9-18-19 G2.1.23: Ability to perform specific system and integrated Yes plant procedures during all modes of operation.

Page 2 of 18

Operations Training Program Job Performance Measure SIMULATOR SETUP INSTRUCTIONS SYSTEM: Generic Administrative - Conduct of Operations TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 TASK NUMBER: N1150140501 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

This JPM is NOT located inside the RCA.

Need L-3 key to unlock SBO Compressor Building Page 3 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 TASK N1150140501 NUMBER:

INITIAL CONDITIONS:

Both Salem Units have tripped due to a loss of off-site power.

Equipment problems have resulted in NO Emergency Control Air Compressors (ECACs) running.

INITIATING CUE:

The Unit 2 CRS has directed you to start the Station Blackout Compressor (SBO) IAW SC.OP-SO.CA-0001, SBO Diesel Control Air Compressor, starting with Step 5.1.3 (see attached).

Steps 5.1.1 and 5.1.2 are complete.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Operator performs Steps 5.1.3 thru 5.1.16 of SC.OP-SO.CA-0001 correctly and in proper sequence to start the SBO Diesel Control Air Compressor.

Page 4 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

Provide marked up copy of the SC.OP- Operator reviews and signs Precautions SO.CA-0001, SBO Diesel Control Air and Limitations.

Compressor with Prerequisites signed off.

Additionally, Step 5.1.1 for removing Operator must address obtaining Inspection Covers will be previously hearing protection per P&L 3.1 completed, as will Step 5.1.2 to re-install inspection covers. All other P&Ls require no action other than reading and initialing with the exception of P&L 3.10 is verified at the SBO.

CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

5.1.3 OPEN both Engine intake louvers (located CUE: After locating and describing how outside building on west wall.) to open Engine intake louvers, state that the Engine intake louvers are open.

Page 5 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step) 5.1.4 OPEN 1CA1920, BLACKOUT AIR Operator simulates opening 1CA1920 COMPRESSOR DRAIN VALVE, to drain by turning counterclockwise direction.

any water accumulation, then CLOSE 1CA1920. CUE: After locating 1CA1920, BLACKOUT AIR COMPRESSOR DRAIN VALVE, and describing how to open, including that the drain cap must be removed, state: 1CA1920, BLACKOUT AIR COMPRESSOR DRAIN VALVE, has been cycled and no water came out of pipe.

Since the cue would be the same whether or not the drain cap was removed (nothing came out the end of pipe) only comment here for review if pipe cap was not removed.

5.1.5 OPEN 2FZSBO10, BATTERY CHARGER, Locates 2FZSBO10, BATTERY breaker. CHARGER, breaker in Panel 2FZSBO, SBO Compressor Bldg Distribution Panel, and simulates opening.

CUE: breaker is open.

Page 6 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step) 5.1.6 PLACE SBO Control Air Dryer switch in Locates SBO Control Air Dryer switch ON position. and simulates turning switch to ON position.

CUE: SBO Control Air Dryer switch is ON and Control Air On light is illuminated.

5.1.7 RECORD Engine Hourmeter reading on Locates Engine Hourmeter, 1XA16993, Attachment 1, Section 1.0, and in log book Tachometer/Hourmeter, inside engine at SBO compressor. control panel labeled Compressor Noise Emission Control Information, and records current reading in Section 1.0 of Att. 1. Locates logbook hanging from side of panel 2FZSBO, SBO Compressor Bldg Distribution Panel, and identifies where Engine Hourmeter should be logged.

Page 7 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step) 5.1.8 PLACE UNLOADER VALVE selector Locates UNLOADER VALVE selector switch in START position. switch, and ensures switch in START position.

Examiners Note: UNLOADER VALVE selector switch is normally in START position when engine is shutdown.

NOTE Operator reads note and continues on If engine fails to start after thirty seconds of with procedure.

cranking, allow starter to cool 5 minutes before attempting restart.

5.1.9 PRESS AND HOLD BY-PASS VALVE Locates BY-PASS VALVE pushbutton. pushbutton in control panel, and simulates depressing AND holding depressed.

Page 8 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

5.1.10 PLACE SBO-IGN-SWT, ENGINE While keeping the BY-PASS VALVE IGNITION SWITCH in START position until pushbutton depressed, operator engine starts, then RELEASE to RUN simulates placing the SBO-IGN-SWT, position. ENGINE IGNITION switch in the START position.

CUE: Engine has started.

After CUE is given, operator releases SBO-IGN-SWT switch to RUN.

Examiners Note: IF operator releases the BY-PASS VALVE pushbutton at this point without checking oil pressure >15 psig, THEN:

CUE: engine has stopped.

Examiners Note: see step 5.1.11 for actions to re-perform engine start.

Page 9 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

5.1.11 When engine oil pressure is >15 psig, Identifies oil pressure reading on RELEASE BY-PASS VALVE pushbutton. gauge labeled oil pressure gauge inside control panel.

CUE: Oil pressure is 40 psig.

Operator releases BY-PASS VALVE pushbutton.

Examiners Note: IF operator releases this pushbutton before verifying oil pressure and was cued that the engine stopped, then the operator will need to re-perform steps 5.1.9 thru 5..1.11.

IF operator reads NOTE and waits 5 minutes to cool engine, THEN use:

CUE: 5 minutes has elapsed.

5.1.12 ALLOW engine to run for 5 minutes to CUE: 5 minutes has elapsed.

warm up.

Page 10 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

5.1.13 OPEN 1CA1913 SBO COMPRESSOR Locates and simulates opening in DISCHARGE VALVE, to pressurize Control the counter-clockwise direction Air header. 1CA1913 SBO COMPRESSOR DISCHARGE VALVE.

CUE: valve is open.

5.1.14 OPEN 1CA1886, BLACKOUT AIR Locates and simulates opening in COMPRESSOR ISOLATION. the counter-clockwise direction 1CA1886, BLACKOUT AIR COMPRESSOR ISOLATION.

CUE: valve is open.

Examiners Note: 1CA1886 is located near the entrance to Service Building on right side past the U2 mixing bottle Page 11 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

5.1.15 OPEN 2CA584, YARD CONTROL AIR Locates and simulates opening in SUPPLY VALVE, to pressurize Aux. the counter-clockwise direction Building 1A and 2A Control Air headers. 2CA584, YARD CONTROL AIR SUPPLY VALVE.

CUE: valve is open Examiners Note: 2CA584 is located near the entrance to Service Building on right side past the U2 mixing bottle.

5.1.16 PLACE UNLOADER VALVE selector Operator returns to the SBO switch in RUN position. Compressor Building and points out UNLOADER VALVE selector switch and simulates placing it in RUN position.

CUE: switch is in RUN JPM is Complete Page 12 of 18

Operations Training Program Job Performance Measure SYSTEM: Generic Administrative - Conduct of Operations NAME: __________________________

TASK: Start the SBO Air Compressor IAW SC.OP-SO.CA-0001 DATE:

STEP STANDARD COMMENTS STEP (Shaded area denotes Critical Step) (Bolded area identifies Task

EVAL (Required for UNSAT NO. (* Critical Step) Standard)

S/U evaluation)

(# Sequential Critical Step)

CUE: WHEN operator informs you the task is Terminate JPM when operator complete, OR the JPM has been completes step 5.1.16.

terminated for other reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 13 of 18

JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC IP-j NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 14 of 18

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Both Salem Units have tripped due to a loss of off-site power.

Equipment problems have resulted in NO Emergency Control Air Compressors (ECACs) running.

INITIATING CUE:

The Unit 2 CRS has directed you to start the Station Blackout Compressor (SBO) IAW SC.OP-SO.CA-0001, SBO Diesel Control Air Compressor, starting with Step 5.1.3 (see attached).

Steps 5.1.1 and 5.1.2 are complete.

Page 15 of 18

JOB PERFORMANCE MEASURE Page 16 of 18

JOB PERFORMANCE MEASURE Page 17 of 18

JOB PERFORMANCE MEASURE Page 18 of 18

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001.

TASK NUMBER: N0680010101 JPM NUMBER: 19-01 NRC IP-k ALTERNATE PATH: K/A NUMBER: 068 A2.02 IMPORTANCE FACTOR: 2.7* 2.8*

APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: In Plant / Simulate S1.OP-SO.WL-0001, Rev. 28 (checked 1-15-20)

REFERENCES:

S1.OP-TM.ZZ-0002, Rev.8 TOOLS AND EQUIPMENT: Calculator, Tank Capacity Book VALIDATED JPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: R. Chan Date: 1-15-20 Instructor Validated By: Moore / Klein Date: 1-16-20 SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 1 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 19-01 NRC IP-k Rev # Date Description Validation Required 00 9-18-19 NEW JPM Yes 068 A2.02: Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release Page 2 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001.

TASK NUMBER: N0680010101 SIMULATOR IC: N/A MALFUNCTIONS / REMOTES: N/A OVERRIDES: N/A SPECIAL INSTRUCTIONS:

This JPM is located inside the Unit 1 RCA.

Page 3 of 15

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001.

TASK NUMBER: N0680010101 INITIAL CONDITIONS:

The 11 CVCS Monitor Tank is at 90% and processing for release is being performed.

INITIATING CUE:

You are the extra NCO.

The CRS directs you to place 11 CVCS Monitor Tank in recirculation using section 5.1 of S1.OP-SO.WL-0001, Release of Radioactive Liquid Waste from 11 CVCS Monitor Tank.

11 Monitor Tank Pump will be placed in service.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Correctly performs recirculation valve lineup using Attachment 1 IAW S1.OP.SO.WL-0001

2. Correctly determines minimum recirculation time of 6 Hrs 30 Mins (band 6 Hrs 20 Mins to 6 Hrs 40 Mins)

Page 4 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

Provide operator the following:

1. Provide filled out copy of S1.OP-SO.WL-0001

2. S1.OP-TM.ZZ-0002, Tank Capacity Data

3. Calculator CUE: Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

START TIME:___________________

NOTE Operator reads note and continues on Any additions made to Monitor Tank that is with procedure.

isolated and placed on recirculation for sampling will invalidate sample analysis, requiring further recirculation time and additional sampling.

5.1 11 CVCS MT Release Preparation Page 5 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

PLACE valves in "Recirc Position" IAW

Operator correctly locates the valves 5.1.1 Attachment 1, Section 1.0 listed on Attachment 1 AND simulates re-positioning each valve to the correct position IAW Attachment 1.

CUE: Report the position of each valve as listed in Attachment 1 (see attached list on page 11).

Examiners Note: The following valves listed in Attachment 1 Section 1.0 are to be in the following positions with 11 MT Tank Pump in service:

11WR27 MT PMP SUCT V - OPEN 11WR31 MT PMP DISCH V - OPEN 12WR27 MT PMP SUCT V - CLOSED 12WR31 MT PMP DISCH V - CLOSED DIRECT second Operator to PERFORM 5.1.2 Independent Verification IAW Attachment 1, CUE: IVs are complete.

Section 1.0 PLACE LO-LEVEL CUT-OFF switch in TANK 11 Operator places LO-LEVEL CUT-OFF switch 5.1.3 position in the TANK 11 position.

CUE: switch is on TANK 11 position Page 6 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

IF recirculating 11 CVCS MT with 11 MT Pump, CUE: recirculate using 11 MT Pump

THEN START 11 MT Pump 5.1.4 Operator starts 11 MT Pump by depressing start pushbutton.

CUE: Pump is running Page 7 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

IF recirculating 11 CVCS MT with 12 MT Pump, 5.1.5 Operator marks step as N/A THEN START 12 MT Pump 5.1.6 THROTTLE 11WR53, MT RECIRC V, to maintain

80 psig on discharge of operating MT Pump CUE #1: discharge pressure is 40 psig.

Operator throttles 11WR53 in the closed (clockwise) direction to raise discharge pressure.

CUE #2: discharge pressure is 80 psig.

CUE #3: IF throttled in open direction THEN state: discharge pressure is 20 psig.

5.1.7 COMPLETE Attachment 1, Section 2.0

Operator correctly completes Attachment 1 Section 2.0 (see steps below)

Examiners Note: Ability to interpret tank curves will be important to determine tank volume and proper minimum recirculation time.

ATT 1 Time Recirculated Started (A)

Records current time ATT 1 CVCS Monitor Tank 11 Level Records 90%

Page 8 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

ATT 1 Volume *

Refers to S1.OP-TM.ZZ-0002 and selects

obtained from tank volume S1.OP-TM.ZZ-0002, CVCS Monitor Tank curve Page 8.

Tank Capacity Data Using curve and tank level of 90%operator determines tank volume of 19,500 gallons (acceptable band 19,000 to 20,000 gallons)

ATT 1 Minimum Time required to recirculate tank (B)

[(Volume) X 3 / 150 gpm]

Operator calculates minimum recirculation time of 6 Hrs 30 Min based on 19,500 gallons.

Acceptable band:

19,000 gallons = 6 Hrs 20 Mins, to 20,000 gallons = 6 Hrs 40 Mins Time Minimum Recirculation Completed Operator adds time (B) to start time (A)

(A + B) 5.1.8 DIRECT second Operator to PERFORM CUE: IV is complete Independent Verification of calculations performed in Attachment 1, Section 2.0 CUE: JPM is Complete Page 9 of 15

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Liquid Radwaste Release TASK: Place 11 CVCS Monitor Tank in Recirculation IAW S1.OP-SO.WL-0001 STEP COMMENTS STANDARD STEP (Shaded area denotes Critical Step) (Required for

(Bolded area identifies Task Standard) EVAL NO. (* Critical Step) UNSAT

S/U

(# Sequential Critical Step) evaluation)

CUE: WHEN operator informs you the task is complete, Terminate JPM when operator completes OR the JPM has been terminated for other Attachment 1 Section 2.0.

reasons, THEN RECORD the STOP TIME.

STOP TIME:________________

Page 10 of 15 Valves Page 11 of 15 Rev. 0

S1.OP-TM.ZZ-0002 Tank Capacity Data, Page 8:

Page 12 of 15 Rev. 0 Page 13 of 15 Rev. 0

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM#: 19-01 NRC IP-k NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

________ 1. Task description and number, JPM description and number are identified.

________ 2. Knowledge and Abilities (K/A) references are included.

________ 3. Performance location specified. (in-plant, control room, or simulator)

________ 4. Initial setup conditions are identified.

________ 5. Initiating and terminating Cues are properly identified.

________ 6. Task standards identified and verified by SME review.

________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

________ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _____ Date _____________

________ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

________ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

________ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:______________________________ Date: ______________

Page 14 of 15 Rev. 0

INITIAL CONDITIONS:

The 11 CVCS Monitor Tank is at 90% and processing for release is being performed INITIATING CUE:

You are the extra NCO.

The CRS directs you to place 11 CVCS Monitor Tank in recirculation using section 5.1 of S1.OP-SO.WL-0001, Release of Radioactive Liquid Waste from 11 CVCS Monitor Tank.

11 Monitor Tank Pump will be placed in service.

Page 15 of 15 Rev. 0

TQ-AA-106-0204 Page 1 of 36 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: NRC-1 [AR.ZZ-2, AB.CVC-1, AB.CW-1, AB.LOOP-3, AB.LOAD-1, LOPA-1 w/2C EDG recovery]

SCENARIO NUMBER: 19-01 NRC-1 EFFECTIVE DATE: See Approval Date EXPECTED DURATION: 60 minutes REVISION NUMBER: 07 PROGRAM: L.O. REQUAL X INITIAL LICENSE STA OTHER Revision Summary:

See ESG-1806 for previous revision summaries.

Rev. 06 (3-19-19) (formerly ESG-1806) Modified for 2019 Annual exam. Deleted malfunction for 2R1B and 2LT112 failures. Added PZR level alarm channel fails low, 22 SGFP trip, and one SW pump trips following starting an EDG in LOPA-1.

Rev. 07 (last used on ESG-1905 2019 LORT Annual Exam). Modified for 19-01 ILOT exam. Used ESG-1905 for EOP-LOPA major actions and modified all other events.

PREPARED BY: R. Chan 8-20-19 Lead Regulatory Exam Author Date APPROVED BY:

Operations Training Manager Date APPROVED BY:

Facility Representative Date Last Updated: 2/11/2021 7:54 AM

TQ-AA-106-0204 Page 2 of 36 SCAN OF SIGNED SCENARIO COVER SHEET

TQ-AA-106-0204 Page 3 of 36 I. OBJECTIVES

1. Using station procedures perform a reactor power ascension IAW S2.OP-IO.ZZ-0004.

2. Given a malfunction with SW Accumulator, direct/perform actions to respond to the malfunction in accordance with Alarm Response Procedures.

3. Given a malfunction with a PZR level channel, direct/perform actions to respond to the malfunction in accordance with S2.OP-AB.CVC-0001.

4. Given a loss of the #4 SPT direct/perform actions to respond to the loss of #4 SPT in accordance with S2.OP-AB.LOOP-0003.

5. Given a loss of the 23 CW Bus direct/perform actions to respond to the loss of three circulators in accordance with S2.OP-AB.CW-0001.

6. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

7. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

8. Given the order or indications of a loss of all AC power, complete actions as the nuclear control operator to PERFORM the immediate response in accordance with the approved station procedures.

9. Given the order with the immediate response to a loss of all AC accident completed and no safety injection actuated or required, perform actions as the nuclear control operator to RECOVER from the loss of AC in accordance with the approved station procedures.

10. Given indication of a loss of all AC power, DIRECT the immediate response in accordance with the approved station procedures.

11. Given the plant with the immediate response completed for a loss of all AC power which did not result in a required safety injection, DIRECT the recovery of the loss of AC in accordance with the approved station procedures.

12. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

TQ-AA-106-0204 Page 4 of 36 II. MAJOR EVENTS

1. Power Ascension to 100% at 10%/hour

2. SW Accumulator Tank Low Pressure Alarm (TS)

3. PZR Level Channel 1 fails low (TS)

4. Loss of #4 SPT and Loss of 23 CW Bus (power reduction) (TS)

5. Loss of Offsite Power

6. Loss of 2A Vital Bus and 2B EDG Trips on Overpseed.

III. SCENARIO

SUMMARY

1. The crew takes the watch with the unit at 90% power, MOL. 2C EDG is C/T for governor oil replacement and fuel rack lube with 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months remaining in the TSAS.

2. The crew will be briefed prior to taking the watch to perform power ascension to 100% at 10%/hour. The crew will directed to use control rods and turbine load control for raising reactor power.

3. After the power ascension has commenced, the crew will receive OHA alarm B-47 for SW Accumulator Tank #21 Trouble. The crew will dispatch an operator to the field to determine the cause of the alarm. Field operator will report that 21 SW Accumulator Tank alarm is for low tank pressure. The crew will determine that 21 SW Accumualtor is Inoperable due to low pressure and IAW the Alarm Response Procedure take action to stop and isolate 21 and 22 CFCUs from service. The CRS will enter TS 3.6.1.1 and 3.6.2.3.

4. Following actions for the 21 SW Accumulator, Pressurizer Level Channel 1 will fail low and result in the loss of letdown flow. The crew will take action IAW S2.OP-AB.CVC-0001, Loss of Charging, to take manual control of charging flow, swap to operable channel, and restore pressurizer heaters and letdown flow. The CRS will enter TS 3.3.1.1

5. Once the crew has addressed the failed pressurizer level channel, a loss of #4 Station Power Transformer (SPT) and 23 CW Bus will occur. The crew will take the following actions; enter S2.OP-AB.CW-0001 for a loss 21A-23A circulators and S2.OP-AB.LOOP-0003, Partial Loss of Offiste Power. As a result of the loss of 23 CW Bus, condenser differential temperatures (DT) will exceed the limits of 27 F and require a turbine load reduction (to less than 80% power) to reduce DTs. The crew may re-energize 23 CW Bus IAW AB.LOOP-0003 Attachment 4 by closing the cross-tie breaker from 24 CW Bus. The CRS will enter TS 3.8.1.1 Action c (one off-site source and one EDG inoperable).

6. After the crew has initiated a turbine load reduction, a loss of offsite power will occur. The reactor will automatically trip and the crew will enter 2-EOP-TRIP-1, Reactor Trop or Safety Injection. While in EOP-TRIP-1, a loss of 2A 4kV Vital Bus on Bus Differential protection and the 2B EDG will trip on overpseed resulting in a loss of all 4KV Vital Busses. The crew will transition to 2-EOP-LOPA-1, Loss of All AC Power, based on all three vital busses de-energized.

7. While in EOP-LOPA-1, the crew will recognize that the 2C EDG is running with no service water pumps and will need to be stopped. Maintenance will return 2C EDG to available status

TQ-AA-106-0204 Page 5 of 36 after Step 26 of EOP-LOPA-1 is performed. Following the report of the release of 2C EDG from the work control supervisor, the crew will start 2C EDG, close its output breaker and re-energize the 2C 4KV Vital Bus [Critical Task #1]. Once the bus is re-energized, the crew will start one service water pump to provide EDG cooling [Critical Task #2].

8. The scenario will terminate when 2C 4KV vital bus is re-energized and the crew starts one SW Pump to provide EDG cooling.

TQ-AA-106-0204 Page 6 of 36 IV. INITIAL CONDITIONS

____ IC-201 PREP FOR TRAINING (i.e. computer setpoints, procedures, bezel covers ,tagged equipment)

Initial Description

____ 1 VC1and VC4 C/T

____ 2 RCPs (SELF CHECK)

____ 3 RTBs (SELF CHECK)

____ 4 MS167s (SELF CHECK)

____ 5 500 KV SWYD (SELF CHECK)

____ 6 SGFP Trip (SELF CHECK)

____ 7 23 CV PP (SELF CHECK)

____ 8 2C EDG C/T

____ 9 Jet C/T Suggested Protected Equipment:

___ 10 2A and 2B EDGs

___ 11 Complete Attachment 2 Simulator Ready-for-Training/Examination Checklist.

TQ-AA-106-0204 Page 7 of 36 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: MONP254 < 10. //CONT ROD BANK C < 10 ( RX TRIP )

1 COMMAND:

PURPOSE: <update as needed>

MALFUNCTIONS:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time SER POINT AN0025 SER 025 FAILS - :B47 SW ACCUM TANK #21

______ 01 N/A N/A N/A RT-1 FAILS/OVRD TROUBLE TO ON

______ 02 VL0569 21SW223 Fails to Position ( 0-100% ) N/A N/A N/A RT-11 0

______ 03 VL0570 22SW223 Fails to Position ( 0-100% ) N/A N/A N/A RT-11 0

______ 04 PR0017A PZR LEVEL CH I (LT459) FAILS H/L N/A N/A N/A RT-2 0

______ 05 EL0048 LOSS OF #4 STAT POWER XFMR-DIFF N/A N/A N/A RT-3

______ 06 EL0134 LOSS OF ALL 500KV OFF-SITE POWE N/A N/A N/A RT-4

______ 07 EL0144 LOSS OF 2A 4160V VITAL BUS 00:00:30 N/A N/A ET-1

______ 08 EL0162 2B EMERG DIESEL GENERATOR TRIP 00:00:30 N/A N/A ET-1

______ 09 VL0083 2SJ1 Fails to Position ( 0-100% ) N/A 0 00:01:00 RT-14 100

______ 10 VL0085 2CV40 Fails to Position ( 0-100% ) N/A 0 00:01:00 RT-15 0

______ 11 VL0053 2SW26 Fails to Position ( 0-100% ) N/A 0 00:02:00 RT-15 0

______ 12 VL0045 2CV116 Fails to Position ( 0-100% ) N/A 0 00:02:00 RT-13 0

______ 13 VL0087 2CC131 Fails to Position ( 0-100% ) N/A 0 00:01:00 RT-7 0

______ 14 VL0580 21MC31 Fails to Position ( 0-100% ) N/A N/A N/A RT-8 5

______ 15 VL0581 22MC31 Fails to Position ( 0-100% ) N/A N/A N/A RT-8 5

______ 16 VL0582 23MC31 Fails to Position ( 0-100% ) N/A N/A N/A RT-8 5 REMOTES:

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

______ 01 CT191-1D 21 CFCU BKR #1 High Speed 125VDC N/A N/A N/A RT-10 OFF

______ 02 CT191-2D 21 CFCU BKR #2 High Speed 125VDC 00:00:05 N/A N/A RT-10 OFF

______ 03 CT191-3D 21 CFCU BKR #3 Low Speed 125VDC 00:00:10 N/A N/A RT-10 OFF

______ 04 CT192-1D 22 CFCU BKR #1 High Speed 125VDC 00:00:15 N/A N/A RT-10 OFF

______ 05 CT192-2D 22 CFCU BKR #2 High Speed 125VDC 00:00:20 N/A N/A RT-10 OFF

______ 06 CT192-3D 22 CFCU BKR #3 Low Speed 125VDC 00:00:25 N/A N/A RT-10 OFF

______ 07 DG01D DEENERGIZE "A" SEC CABINET N/A N/A N/A RT-12 YES

TQ-AA-106-0204 Page 8 of 36

______ 08 DG02D DEENERGIZE "B" SEC CABINET 00:00:05 N/A N/A RT-12 YES

______ 09 DG03D DEENERGIZE "C" SEC CABINET 00:00:10 N/A N/A RT-12 YES

______ 10 DG28D 2C DIESEL GEN LOCKED OUT N/A N/A N/A N/A YES

______ 11 DG29D 2C DG BKR CONTROL POWER N/A N/A N/A N/A OFF

______ 12 DG30D 2C DG BKR RACK OUT N/A N/A N/A N/A TAGGED

______ 13 CV28A 21CV98 RCP SEAL INJ MAN ISOL 00:02:00 7500 00:01:00 RT-9 0

______ 14 CV29A 22CV98 RCP SEAL INJ MAN ISOL 00:03:00 7500 00:01:00 RT-9 0

______ 15 CV30A 23CV98 RCP SEAL INJ MAN ISOL 00:04:00 7500 00:01:00 RT-9 0

______ 16 CV31A 24CV98 RCP SEAL INJ MAN ISOL 00:05:00 7500 00:01:00 RT-9 0

______ 17 AF20D 21 AFW PUMP BKR CONTROL POWER 00:01:00 N/A N/A RT-6 OFF

______ 18 AF25D 22 AFW PUMP BKR CONTROL POWER 00:01:30 N/A N/A RT-6 OFF OVERRIDES:

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity OTHER CONDITIONS:

Description

____ 1.

TQ-AA-106-0204 Page 9 of 36 V. SEQUENCE OF EVENTS

1. State shift job assignments.

2. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

3. Inform the crew The simulator is running. You may commence panel walkdowns at this time.

SM please inform me when your crew is ready to assume the shift.

4. Allow sufficient time for panel walk-downs. When informed by the SM that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

TQ-AA-106-0204 Page 10 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment

1. 21 SW Accumulator Tank Low Pressure Simulator Operator: Insert RT-1 on direction from Lead Examiner. This will insert the following malfunction:

AN0025, OHA B-47, 21 SW Accum Tank Trouble Crew reports unexpected OHA Alarm B-47, 21 SW Accumulator Tank Trouble.

Crew dispatches field operator to investigate cause of alarm.

Role Play: After 1-2 minutes, report as the field operator the following: the alarm is for low tank pressure and its reading just below 55%. I dont see or hear any signs of system leakage. I checked my logs and the tank pressure has been at the low end of the log readings for several days.

Note: SW Tank is Inoperable when pressure is outside of the band of 138-157 psig (55.2 -

62.8% local)

The crew declares 21 SW Accumulator Inoperable and IAW the Alarm Response Procedure and/or S2.OP-SO.SW-0005, take actions to stop 21 and 22 CFCUs and then isolate them from the field by closing valves in the field.

TQ-AA-106-0204 Page 11 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment PO stops 21 and 22 CFCUs.

The CRS directs WCC supervisor to CLOSE the following field valves:

21 & 22 SW76, CFCU Outlet Valves

21 & 22 SW54, CFCU Inlet Valves Simlator Operator: When notified, Insert RT-11 to simulate closing of the SW76 and SW54 valves in the field for affected CFCUs:

VL0569, 21SW223 fails to position VL0570, 22SW223 fails to position Value = 0 Wait 3-5 minutes, THEN Notify the CRS the SW valves are closed.

The crew evaluates Tech Specs due to the low tank pressure.

TS evaluation #1:

The CRS enters TS 3.6.1.1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) for Containment Integrity and 3.6.2.3 (14 days) for two CFCUs Inoperable.

Proceed to next event after Tech Specs has been evaluated or by direction from Lead Examiner.

The crew may direct field operator to perform make-up to restore SW Accumulator pressure to within specification for Operability IAW S2.OP-SO.SW-00006, SW Accumulator Operation.

TQ-AA-106-0204 Page 12 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Role Play: IF required, acknowledge the direction to make-up to SW Accumualtor Tank using the OP-SW-6 procoedure to restore pressure to within the specified pressure band.

2. PZR Level Channel 1 Fails Low Simulator Operator: Insert RT-2 on direction from Lead Examiner. This will insert the following malfunction:

PR0017A PZR level CH 1 Fails Low Value = 0 RO reports unexpected OHA E-36, PZR HTR OFF LVL LO and diagnoses failure of PZR level channel.

RO reports letdown isolated Examiners Note: Crew may place Master Flow Controller in Manual prior to entering AB procedure.

CRS enters S2.OP-AB.CVC-0001, Loss of Charging.

PO initiates of Attachment 1 CAS.

RO reports 23 charging pump is running.

RO reports there is no indication of cavitation.

RO reports PZR level channel 1 has failed Low.

RO takes manual control of charging flow, if not

TQ-AA-106-0204 Page 13 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment previously done, and lowers charging flow to minimize level rise in PZR.

RO selects operable channel for Control, Alarm and Recorder.

RO energizes PZR heaters to normal alignment Examiners Note: An auto CVCS makeup to the VCT may occur at some point based on no letdown flow.

Restoration of Letdown:

RO ensures open 2CV7 RO places 2CV18 in Manual and opens until close PB extinguishes RO opens 2CV2 and 2CV277 and place in Auto RO ensures charging flow 85-90 gpm RO opens one letdown orifice (2CV3, 4, 5) and adjusts 2CV18 to maintain letdown pressure 300 psig RO places 2CV18 in Auto CRS directs charging placed in Auto when PZR level returns to program CRS directs Maintenance assistance to remove failed channel from service IAW S2.OP-SO.RPS-0003.

TS evaluation #2:

TQ-AA-106-0204 Page 14 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CRS enters TS 3.3.1.1 Action 6 (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ). Note: T/S 3.3.3.5 and 3.3.3.7 do not apply.

Proceed to next event after Tech Specs evaluated or at direction of Lead Examiner

3. Loss of #4 SPT Simulator Operator: Insert RT-3 on direction from Lead Examiner. This will insert the following malfunction:

EL0048, Loss of #4 SPT PO reports several OHA alarms for B and K window and investigates the cause.

PO reports one or more of the following:

500 KV Bus Section 1 is de-energized,

Loss of #4 SPT

All the Vital Busses are energized from 23 SPT (single source of off-site power).

PO reports that 23 CW Bus is de-energized and 21A thru 23A CW pumps have tripped.

Examiners Note: The crew will need to enter 2 AB procedures. Following the trip of the 21A-23A circulators, the crew should recognize that the condenser DTs have exceeded the procedural limit of 27 F and initiate a turbine load reduction to less than 80% IAW S2.OP-AB.CW-0001 as the first priority.

TQ-AA-106-0204 Page 15 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment S2.OP-AB.CW-0001 starts here:

Crew enters S2.OP-AB.CW-0001, CW System Malfunction.

PO initiates Attachment 1 CAS.

PO reports no pipe ruptures in the circulating system.

PO reports 3 circulators are out of service.

PO reports condenser hotwells are being maintained.

PO reports at least once circulator pump in operation on each condenser.

CRS dispatches field operators to OPEN the 21-23MC62, TURB HOD SPRAY NYPASS VLV on affected condenser.

Simulator Operator: Insert RT-8 to simulate opening of 21-23MC62 Hood Spray Bypass valve.

VL0580, 21MC31 fails to position VL0581, 22MC31 fails to position VL0582, 23MC31 fails to position Value = 5%

(Monitor hood spary temps on P250 to maintain 100 F)

CRS directs PO to monitor condenser hotwell and condensate pump suction piping for signs of flashing.

CRS directs event response team to investigate cause of

TQ-AA-106-0204 Page 16 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment loss of 23 CW Bus.

PO reports that condensate pump suction temperature temp is less than 120 F.

CRS contacts Chemistry to maintain chlorination parmaters within limits and monitor condensate polisher resin.

Condenser DTs exceed 27 F (load reduction):

PO reports that Attachment 1 CAS Step 5 Condenser DTs is greater than 27 F and that a load reduction is required.

Crew briefs reactivity plan for turbine load reduction IAW S2.OP-AB.LOAD-0001, Rapid Load Reduction.

Examiners Note: During validation, the crew needed to lower turbine load to less than 80%

power to lower DTs to less than 27 F. The crew may perform load reductions is small power increments until the desired DT is reached.

RO initiates boration IAW S2.OP-SO.CVC-0006 PO initiates turbine load reduction as directed by CRS IAW AB.LOAD-0001 and S2.OP-SO.TRB-0001.

RO reports when control rods are inserting to maintain Tavg on program.

RO energizes all PZR heaters.

S2.OP-AB.LOOP-0003, Partial Loss of Off-

TQ-AA-106-0204 Page 17 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment site Power, starts here:

PO initiates Attachment 1 CAS CRS notifies SM to refer to ECGs PO reports no 4KV Vital Bus powered by EDGs PO reports both 500 KV Bus Sections 1 and 2 are not energized.

PO reports 500 KV Bus Section 1 is de-energized.

CRS request Unit 1 to OPEN the following breakers:

500 KV BS 1-5 breaker (12X)

500 KV BS 1-8 breaker (20X)

[Note: already open as part of the event, indication is on 2CC3]

Role Play: Respond as Unit 1 Operator that both the 500 KV BS 1-5 and 1-8 breakers are OPEN.

PO OPENS 500 KV BS1-9 breaker (32X)

[Note: already open as part of the event]

CRS initiates action to determine the cause of loss of 500 KV BS 1 PO OPENS 500 KV Circuit Switchers:

2T60, 13 KV Ring Bus

4T60, 13 KB South Bus Re-energizing 23 CW Bus:

TQ-AA-106-0204 Page 18 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CRS directs PO to energize 2CW Bus Section 23 from Bus Section 24 IAW Attachment 4.

Examiners Note: The crew at this time may determine not to re-energize 23 CW Bus until the cause of the event is determined.

PO reports that OHAs K-2 and K-10 are clear.

PO reports that the breakers listed in Attachment 4 Step 1.2 are OPEN.

PO reports 2CW Bus Section 24 voltage is within the band of 4.22-4.36KV PO PRESSES 2CW2BD AUTO SWAP OFF pushbutton and ensures pushbutton is illuminated.

PO PRESSES Mimic Bus 2CW SWGR BUS-TIE BREAKER 2CW2BD pushbutton and ensures bezel is illuminated.

PO PRESSES 2CW2BD CLOSE pushbutton and ensures the breaker goes CLOSED, Bus Section 23 votlage is within the band of 4.22-4.36KV, and 2CW2BD Mimic bezel is extinguished.

TS evaluation #3:

CRS enters TS 3.8.1.1 Action C (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) for one source of off-site power and one EDG Inoperable.

Examiners Note: Tech Spec evaluation could be delayed until end of scenario by Lead Examiners discretion.

TQ-AA-106-0204 Page 19 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Proceed to next event by direction from Lead Examiner.

4. Loss of Offsite Power Simulator Operator: Insert RT-4 on direction from Lead Examiner. This will insert malfunction:

EL0134, Loss of Offiste Power RO reports reactor automatically tripped and performs immediate actions of 2-EOP-TRIP-1.

Trips the reactor

Confirms the reactor tripped

Trips the main turbine

5. Loss of 2A Vital Bus and 2B EDG Emergency Trips on Overspeed:

Simulator Operator: Ensure ET-1 is TRUE following Rx Trip. This will insert the following malfunctions:

EL0144, Loss of 2A Vital Bus (Bus Diff Protection)

EL0162, 2B EDG Emerg Trips on Overspeed Time Delay = 30 seconds

TQ-AA-106-0204 Page 20 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO reports that all 4KV Vital Busses are de-energized.

EOP-LOPA-1 starts here:

Crew transitions to 2-EOP-LOPA-1, Loss of All AC Power.

PO throttles AFW flow to no less than 22E4 lbm/hr.

RO performs immediate actions of LOPA-1:

Trip the Reactor Trip the Turbine CRS and RO verify performance of immediate actions.

RO closes 2CV2 and 2CV277 RO reports 2CV278 and 2CV131 are closed.

RO reports that both PZR PORVs are closed.

PO reports total AFW pump is > 22E4 lbm/hr.

RO makes page announcement.

CRS dispatches operator to deenergize all SECs.

De-energize SECs:

Simulator Operator: After being contacted, Insert RT-12 to deenergize all SECs with a time delay.

REMOTES:

TQ-AA-106-0204 Page 21 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment DG01D Deenergize A SEC DG02D Deenergize B SEC DG03D Deenergize C SEC NOTIFY CRS when complete.

Examiners Note: Around this point the crew should be discussing strategy to recover a vital bus. 2B EDG tripped on overspeed and will take some time to troubleshoot. 2C EDG is C/T for minor maintenance. 2A vital bus is deenergized on Bus Differential protection and therefore not expected back soon. Crew should determine that success path is to restore 2C EDG from maintenance and start the diesel.

CRS directs performance of blackout coping actions of S2.OP-AB.LOOP-1, Att 2, Part A.

Role Play (AB.LOOP-1, Attachment 2 Part A):

After 10-15 minutes report back that Blackout Coping actions in Attachment 2 Section 1.A and 1.B have been completed within 30 minutes.

PO reports 23 AFW supplying feed flow to SGs.

Crew waits until all SECs are deenergized.

CRS receives report that all SECs are deenergized.

Stop running EDGs:

TQ-AA-106-0204 Page 22 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment PO stops 2A EDG based on no service water pump running IAW CAS of LOPA-1.

RO depresses stop pushbutton for all loads in Table A of LOPA-1.

Examiners Note: PO may report the following to the crew regarding vital bus status:

2A Bus - Bus deenergized, EDG is running with No Service Water pumps in service, OHA for Bus Differential.

2B Bus - Bus deenergized, EDG started but emergency tripped 2C Bus - Bus deenergized, EDG is C/T PO reports status of 4 KV Vital Busses and priority should be placed on restoring 2B EDG from maintenance.

Role Play (2B EDG): IF dispatched, report that BC EDG tripped on overspeed and the fuel rack linkage looks bent.

Role Play (Maintenance on 2C EDG): When contacted about status of 2C EDG maintenance, state that you will go to the field to get a status from maintenance.

PO reports that no 4 KV Vital Bus are energized RO reports that SI has not actuated or required.

Examiners Note: There will be no console indications to verify valve positions during

TQ-AA-106-0204 Page 23 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment LOPA-1 only local field reports.

CRS directs WCC to Open 2SJ1 or 2SJ2 Simulator Operator: Insert RT-14 to open 2SJ1.

VL0083 2SJ1 fails to position Final = 100 Ramp: 01:00 mins CRS directs WCC to Close 2CV40 or 2CV41.

Simulator Operator: Insert RT-15 to close 2CV40.

VL0085 2CV40 fails to position Final = 0 Ramp: 01:00 mins CRS directs WCC to Close 2SW26.

Simulator Operator: Insert RT-15 to close 2SW26.

VL0053 2SW26 fails to position Final = 0 Ramp: 02:00 mins RO reports SI has not actuated and initiates SI.

Crew verifies closure of Phase A and CVI valves.

Note: 2CV116 closed later.

TQ-AA-106-0204 Page 24 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO resets SI.

RO resets Phase A signal.

RO opens 21 and 22 CA330s.

CRS directs WCC to remove control power for 21 and 22 AFW pumps.

Simulator Operator: Insert RT-6 to remove control power to 21 and 22 AFW pumps.

Remote:

AF20D, 21 AFW Control Power AF25D, 22 AFW Control Power Value = OFF CRS request assistance to restore power IAW S2.OP-AB.LOOP-0001, Loss of Offsite Power, while continuing with LOPA-1.

EOP-LOPA-1, Step 26 starts here:

CRS reads Step 26, When at least one 4kV vital bus is energized, THEN go to step 43.

Proceed to Role Play for releasing tags on 2C EDG after CRS read Step 26.

CRS informs crew to not start any Charging pumps until directed.

Release of 2C EDG:

Role Play: Notify CRS that the 2C EDG is

TQ-AA-106-0204 Page 25 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment being returned from Maintenance in the next 5 minutes and will notify you when the tag release is in the field.

CRS directs WCC to close 2CV83, 2CV89 and 2CV95 and 2CV116 Simulator Operator: Insert RT-9 to close 21-24 CV98. This will simulate closure for 2CV83, 2CV89 and 2CV95 to isolate seal injection filters.

Remotes:

CV28A, 21CV98 fails to position CV29A, 22CV98 fails to position CV30A, 23CV98 fails to position CV31A, 24CV98 fails to position Final = 0 Ramp: 1 min Delay = 0-5 mins Simulator Operator: Insert RT-13 to close the 2CV116 valve.

VL0045 2CV116 fails to position Final = 0 Ramp = 2 min CRS directs WCC to close 2CC131.

Simulator Operator: Insert RT-7 to close 2CC131.

VL0087 2CC131 fails to position Final = 0 Ramp: 01:00 min

TQ-AA-106-0204 Page 26 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment 2C EDG tag release:

Role Play: Notify CRS that 2C EDG tag release is in the field.

Simulator Operator: After 1-2 minutes, MODIFY the following Remotes to simulate releasing tags on 2C EDG:

DG20D, Output Bkr control power to ON DG21D, Output Bkr Racked Out to UNTAGGED DG19D, 2B Lockout Switch to NO Role Play: Notify CRS that 2C EDG tags are released and IVs complete.

Starting 2C EDG:

Critical Task-1 (CT-24): Energize one vital bus before transition out of LOPA-1.

SAT_______ UNSAT______

CRS returns to CAS Step 14 after notification that 2C EDG tags are released.

PO depresses start PB for 2C EDG and observes voltage increasing to 4KV.

PO depresses 2C EDG output breaker mimic PB and ensures mimic PB backlight illuminates.

TQ-AA-106-0204 Page 27 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment PO depresses 2C EDG output breaker closed PB bezel and verifies closed PB illumiinates. [Critical Task #1 complete]

Critical Task-2 (CT-25): Start one SW pump on running EDG before engine temperature limits are exceeded.

SAT________ UNSAT_______

PO starts 25 or 26 SW pump. [Critical Task #2 complete]

Terminate scenario when crew starts one SW Pump on 2C Bus or as direct by Lead Examiner.

TQ-AA-106-0204 Page 28 of 36 VI. SCENARIO REFERENCES

1. Alarm Response Procedures (Various)

2. Technical Specifications

3. Emergency Plan (ECG)

4. OP-AA-101-111-1003, Use of Procedures

5. S2.OP-IO.ZZ-0004, Power Operation

6. S2.OP-AB.CVC-0001, Loss of Charging

7. S2.OP-AB.LOOP-0001, Loss of Off-site Power

8. S2.OP-AB.LOOP-0003, Partial Loss of Offsite Power

9. S2.OP-AB.CW-0001, Circulating Water System Malfunction

10. S2.OP-AB.LOAD-0001, Rapid Load Reduction

11. 2-EOP-TRIP-1, Rx Trip or Safety Injection

12. 2-EOP-LOPA-1, Loss of All AC Power

TQ-AA-106-0204 Page 29 of 36 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 90% RCS BORON: 837 MWe 1090 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

3.8.1.1.b Action b (72 hrs), 2C EDG, 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months remain.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

S2.OP-ST.500-0001 was just completed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

ABNORMAL PLANT CONFIGURATIONS:

Jet is C/T due to emergent troubleshooting of output breaker failing to close.

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

2C EDG C/T for governor oil replacement and fuel rack lube.

SECONDARY:

Polisher in service Blowdown 35K per loop to 23 Condenser / Flashtank RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

None

TQ-AA-106-0204 Page 30 of 36 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in TRAIN Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify ECG paperwork is marked Training Use Only and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

TQ-AA-106-0204 Page 31 of 36 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individuals incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

TQ-AA-106-0204 Page 32 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST SCENARIO IDENTIFIER: 19-01 NRC Scenario 1 REVIEWER:

Initials Qualitative Attributes

1. The scenario has clearly stated objectives in the scenario.

2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

3. The scenario consists mostly of related events.

4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point

5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

6. The events are valid with regard to physics and thermodynamics.

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

8. The simulator modeling is not altered.

9. All crew competencies can be evaluated.

10. The scenario has been validated.

11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

TQ-AA-106-0204 Page 33 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 1 Target Quantitative Attributes per Scenario (NRC Form ES-D-1)

Initial Conditions: IC-201: 90% power, MOL; 23 Charging Pump is in service. The following equipment is out of service: 2C EDG C/T for governor oil replacement and fuel rack lube.

Turnover: The crew is directed to continue power ascension to 100% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using control rods and turbine load control.

Critical Tasks:

1. Energize at least one AC Emergency Bus (see WOG CT-24)

2. Manually start SW Pump for EDG Cooling (see WOG CT-25)

Event Malf. No. Event Type* Event No. Description 1 N/A ALL (R) Power ascension to 100% at 10% per hour IAW IOP-4 BOP (C) 2 AN0025 21 SW Accumulator Tank Low Pressure CRS (TS)

ATC (I) 3 PR0017A PZR Level Channel 1 Fails Low CRS (I,TS)

BOP (C) 4 EL0048 Loss of #4 SPT and 23 CW Bus CRS (C, TS) 5 EL0134 ALL (M) Loss of Offsite Power Loss of 2A 4KV Vital Bus EL0146 6 ALL (C) 2B EDG Trips on Overpseed EL0162 (time delayed)

ABs AR.ZZ-2 AB.CVC-1 AB.LOOP-3 AB.CW-1 AB.LOAD-1 EOPs TRIP-1 LOPA-1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Notes: None

TQ-AA-106-0204 Page 34 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 1 Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 6 2-6

2. Malfunctions after EOP entry (1-2) 2 6

3. Abnormal events (2-4) 3 2,3,4

4. Major transients (1-2) 1 5

5. EOPs entered/requiring substantive actions (1-2) 1 LOPA-1

6. Entry into a contingency EOP with substantive actions ( 1 per 0 N/A scenario set)

7. Preidentified critical tasks (2) 2 CT-24, CT-25

8. Tech Specs exercised ( 2) 3 2,3,4

TQ-AA-106-0204 Page 35 of 36 ATTACHMENT 5 ESG CRITICAL TASKS 19-01 NRC Scenario 1 CT-1 (CT-24):

Critical Task: Energize at least one AC emergency bus prior to end of scenario.

BASIS: See WOG Rev. 2 CT-2 (CT-25):

Critical Task: Manually start one SW pump for EDG cooling before engine temperatures are exceeded.

BASIS: See WOG Rev. 2

TQ-AA-106-0204 Revision 2 Page 36 of 36 ATTACHMENT 6 ESG-PRA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW Y Loss of Offsite Power N Loss of Control Air Y Loss of Switchgear and Pen Area Ventilation Y Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area Y Any Diesel Generator N RHR Suction Line valves from Hot Leg Y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed

TQ-AA-106-0204 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: NRC-21 [ARP, AB.COND-1, AB.ROD-3, AB.RC-1, TRIP-1, LOCA-1, LOCA-5]

SCENARIO NUMBER: 19-01 NRC ESG-21 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 04 PROGRAM: L.O. REQUAL X INITIAL LICENSE STA OTHER Revision Summary:

See ESG-1807 for previous revisions.

Rev. 03 (last used 2019 Annual ESG-1913) Modified for 19-01 ILOT NRC exam.

Modified abnormal events. Incorporated comments from validation; added 22 vacuum pump trip.

Rev 04 Incorporated comments from NRC working mtg on 2-14-20 to reduce the scenario duration. Deleted Loss of Off-site Power and Loss of 2A 4KV Vital Bus.

Added 21 RHR Pump is C/T for maintenance to support LOCA-5 conditions.

PREPARED BY: R. Chan 2-25-20 Lead Regulatory Exam Author Date APPROVED BY:

Operations Training Manager or Date designee APPROVED BY:

Operations Director or designee Date Last Updated: 2/10/2021 4:15 PM SCAN OF SIGNED SCENARIO COVER SHEET Page 1 of 40

Page 2 of 40 I. OBJECTIVES A. Given the order, perform a turbine load reduction in accordance with station procedures.

B. Given indications of a Steam Generator instrumentation malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures.

C. Given indication of a Steam Generator instrumentation malfunction, DIRECT the response to the malfunction in accordance with the approved station procedures.

D. Given indications of a loss of vacuum, perform actions as the nuclear control operator to RESPOND to the malfunction, IAW approved station procedures.

E. Given indications of a loss of vacuum, DIRECT the response to the malfunction IAW approved station procedures.

F. Given indications of a RCS RTD instrument failure, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with approved station procedures.

G. Given indications of a RCS RTD instrument failure, DIRECT the response to the malfunction in accordance with approved station procedures.

H. Given an RCS leak at power, respond to the event IAW approved station procedures.

I. Given the indications of a reactor coolant system (RCS) malfunction or leak, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures.

J. Given the indications of a reactor coolant system (RCS) malfunction or leak, DIRECT the response to the malfunction in accordance with the approved station procedures.

K. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

L. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

Page 3 of 40 M. Given the order or indications of a reactor trip, perform actions as the shift technical advisor to RESPOND to the reactor trip in accordance with the approved station procedures.

N. Given the order or indications of a safety injection perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

O. Given indication of a safety injection DIRECT the response to the safety injection in accordance with the approved station procedures.

P. Given the order or indications of a safety injection, perform actions as the shift technical advisor to RESPOND to the safety injection in accordance with the approved station procedures.

Q. Given a safety injection has occurred and equipment has failed to start, START equipment that has failed to automatically start in accordance with station procedures.

R. Given the order or indications of a loss of coolant accident (LOCA), complete actions as the nuclear control operator to PERFORM the immediate response to the LOCA in accordance with the approved station procedures.

S. Given indication of a loss of coolant accident (LOCA), DIRECT the immediate response to the LOCA in accordance with the approved station procedures.

T. Given the order or a loss of coolant accident (LOCA) with indication of a loss of emergency recirculation, perform actions as the nuclear control operator to RESPOND to the loss of emergency recirculation in accordance with the approved station procedures.

U. Given a loss of coolant accident (LOCA) and a loss of emergency recirculation, DIRECT actions to respond to the emergency recirculation loss in accordance with the approved station procedures.

V. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

Page 4 of 40 II. MAJOR EVENTS

1. Planned Load Reduction to 89% at 10%/hour

2. 23 SG Pressure Channel 3 Fails Low (TS only)

3. 24 Vacuum Pump trips

4. RC Loop 24 Cold Leg RTD Fails High (TS)

5. RCS Leak

6. 22 RHR Pump Fails to Start on SEC Signal

7. Loss of Emergency Recirculation capability (22 RHR Pump Trips)

III. SCENARIO

SUMMARY

1. The crew assumes the watch at 100% power, EOL. 23 Charging Pump is C/T for pulsation damper repairs with 21 Charging Pump in service.

2. After assuming the watch, the crew will brief a planned load reduction to 89% at 10%/hour IAW S2.OP-IO.ZZ-0004, Power Operation, in preparation for Main Turbine Valve testing next shift.

3. After the power reduction has commenced, 23 SG Pressure Channel 3 will fail low. The crew will respond IAW Alarm Response Procedure and determine that the event has no impact to plant operations. The CRS will enter TS 3.3.2.1.b Action 19.

4. After the 23 SG Pressure Channel has been addressed, 24 condenser vacuum pump will trip.

The crew will recognize that condenser backpressure is slowly rising and enter S2.OP-AB.COND-0001, Loss of Condenser Vacuum. The crew will start all available vacuum pumps and stabilize condenser back pressure.

5. After the crew addresses vacuum pump trip, 24 Loop Cold Leg RTD will fail high causing control rods to continuously insert. The crew will verify no turbine runback in progress and place rods in manual. The crew will enter S2.OP-AB.ROD-0003, Continuous Rod Motion, and place rods to manual, defeat the failed channel, place Charging Flow in manual, then restore rods to Auto. The CRS will enter TS 3.3.1.1, Action 6 and 3.3.2.1.b Action 19.

6. Once actions for 24 Loop RTD failure is addressed, a RCS leak wil occur resulting in rapidly lowering PZR level and pressure. The crew will take CAS actions in S2.OP-AB.RC-0001 and manually trip the reactor. Immediately following the Rx Trip the RCS leak will escalate into a Large Break LOCA and a malfunction will prevent Auto Safety Injection to actuate. The crew will respond by manually initiating SI [Critical Task #1]. The crew will enter EOP-TRIP-1, Reactor Trip or Safety Injection.

7. While in EOP-TRIP-1, the crew will recognize that 22 RHR Pump failed to start on SEC signal.

The crew will block and reset 2B SEC, then manually start 22 RHR Pump [Critical Task #2].

8. The crew will perform diagnostics in EOP-TRIP-1 and eventually transition to EOP-LOCA-1, Loss of Coolant, based on containment pressure > 4 psig. While in EOP-LOCA-1, the 22 RHR Pump will trip and the crew will determine a loss of emergency recirculation capability and transition to EOP-LOCA-5, Loss of Emergency Recirculation. The crew will perform the

Page 5 of 40 following actions in LOCA-5; make-up to RWST, stop Containment Spray Pumps, and then reduce ECCS to a single train [Critical Task #3].

9. The scenario can be terminated when the crew stops one Charging pump or by direction from Lead Examiner.

Page 6 of 40 IV. INITIAL CONDITIONS

____ IC-211 PREP FOR TRAINING (i.e. computer setpoints, procedures, bezel covers ,tagged equipment)

Initial Description

____ 1 2VC1and 2VC4 C/T

____ 2 RCPs (SELF CHECK)

____ 3 RTBs (SELF CHECK)

____ 4 21-24MS167s (SELF CHECK)

____ 5 500 KV SWYD (SELF CHECK)

____ 6 21 and 22 SGFP Trip (SELF CHECK)

____ 7 21 CV Pump (SELF CHECK)

____ 8 21 RHR Pump C/T

____ 9 23 Charging pump C/T Suggested Protected Equipment:

___ 10 22 RHR Pump

___ 11 Complete Attachment 2 Simulator Ready-for-Training/Examination Checklist.

Page 7 of 40 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: MONP254 < 10. //CONT ROD BANK C < 10 ( RX TRIP )

1 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KCK02PBZ //22 VACUUM PUMP-START 2 COMMAND:

PURPOSE: <update as needed>

MALFUNCTIONS:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time

______ 01 SG0100C 23 SG PR XMTR (536) PROT CH III FAIL N/A N/A N/A RT-1 0

______ 02 RC0015D LOOP 24 COLD LEG RTD FAILS HI/L N/A N/A N/A RT-3 630 RC0002 RCS LEAK INTO CONTAINMENT ( equiv to 0-

______ 03 N/A 0 00:01:00 RT-4 18000 4 inches )

______ 04 RP0108 FAILURE OF AUTOMATIC SI N/A N/A N/A N/A

______ 05 RP318A2 RHR PUMP 22 Fails to Start on SEC N/A N/A N/A N/A

______ 06 VC0087C TRIP OF VACUUM PUMP 24 N/A N/A N/A RT-2

______ 07 RH0026B 22 RHR PUMP TRIP N/A N/A N/A RT-5

______ 08 RC0001A RCS RUPTURE OF RC LOOP 21 N/A N/A N/A ET-1

______ 09 VC0087A TRIP OF VACUUM PUMP 22 00:00:02 N/A N/A ET-2 REMOTES:

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

______ 01 CV20A 2CV182 BLENDER ISO VLV N/A N/A N/A RT-10 100

______ 02 CV21A 2CV184 BLENDER DISC TO RWST N/A N/A N/A RT-10 100

______ 03 RH26D 21 RHR PUMP BKR CONTROL POWER N/A N/A N/A N/A OFF

______ 04 RH27D 21 RHR PUMP RACK OUT N/A N/A N/A N/A TAGGED OVERRIDES:

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity AH03 C1 LO QAH03HRK RWST HEATER PUMP

______ 01 00:00:02 N/A N/A RT-11 ON START

______ 02 AH03 C2 LO QAH03KGK RWST HEATER PUMP STOP N/A N/A N/A RT-11 OFF

Page 8 of 40 OTHER CONDITIONS:

Description

____ 1. None

Page 9 of 40 V. SEQUENCE OF EVENTS A. State shift job assignments.

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet)

C. Inform the crew The simulator is running. You may commence panel walkdowns at this time. SM please inform me when your crew is ready to assume the shift.

D. Allow sufficient time for panel walk-downs. When informed by the SM that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

Page 10 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG

1. Power Reduction to 89%

CRS briefs crew on power reduction to 89% at 10%/hour IAW S2.OP-IO.ZZ-0004, Section 4.3 Power Reduction.

RO briefs boration plan for load reduction.

PO briefs turbine load control plan.

RO initiates boration IAW S2.OP-SO.CVC-0006.

PO initiates turbine load reduction IAW S2.OP-SO.TRB-0002, Turbine Generator Shutdown Operation.

RO monitors Tavg and control rods for proper response.

Proceed to next event by direction from Lead Examiner.

Examiners Note: The crew may at any time stop the load reduction to respond to the next events.

2. 23 SG Pressure Channel 3 Fails Low Simulator Operator: Insert RT-1 on direction from Lead Examiner.

SG0100C, 23 SG PRESS CH 3 FAILS

Page 11 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG H/L Value: 0 PO reports unexpected OHA alarms for G-17 LOOP 23 STM LN DP LO and G-33 STM LN PRESS LO, and console alarm for PRESS LO.

PO reports the following bistables are lit on 2RP4 for STM LINE DIFFERENTIAL LOOP 23 and LOW STEAMLINE PRESSURE LOOP 23.

PO reports 23 SG Pressure Channel 3 has failed low.

Crew reviews ARP and determines no operator is required and no impact to plant operation due to failed channel.

CRS directs support for removing failed channel from service IAW S2.OP-SO.RPS-0004, Placing SG Channel in Trip Condition.

TS evaluation #1:

CRS enters TS 3.3.2.1.b, Action 19 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

Proceed to next event when Tech Spec has been evaluated or at Lead Examiners direction.

3. 24 Vacuum Pump Trips:

Page 12 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG Simulator Operator: At direction from Lead Evalautor insert RT-2. This will trip 24 vacuum pump:

VC0087C, Trip of Vacuum Pump 24 PO reports unexpected trip of 24 Vacuum Pump.

CRS enters S2.OP-AB.COND-0001, Loss of Condenser Vacuum.

PO initiates Attachment 1 CAS.

CRS dispatches operator to perform Attachment 2, Loss of Vacuum Local Checks.

Role Play: When dispatched to perform , THEN after 2-5 minutes report the following: Ive completed and have found no abnormal conditions except for the breaker being tripped open.

PO reports 24 Vacuum pump is stopped and the 24AR25 is closed.

PO reports condenser backpressure is rising rapidly.

PO reports rising backpressure is not attributed to CW System malfunctions.

PO starts all available vacuum pumps.

Page 13 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG 22 Vacuum Pump trips following start:

Simulator Operator: Ensure ET-2 is TRUE IF 22 Vacuum pump is started.

This will cause the pump to trip following start.

IF 22 Vacuum Pump is started, the PO reports that the pump started then tripped seconds later.

25AR25 fails to open following start of 25 Vacuum Pump:

PO reports that 25 Vacuum Pump started but the 25AR25 failed to open.

Role Play: IF requested to check local indications at the Vacuum Pump, THEN report that the local gauge reading is SAT and all other parameters are in the SAT range.

PO manually opens 25AR25.

PO reports that condenser back pressure is improving.

Proceed to next event at direction from Lead Examiner.

4. 24 Loop Cold Leg RTD Fails High

Page 14 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG Simulator Operator: Insert RT-3 on direction from Lead Examiner.

RC0015D, 24 Cold Leg RTD Fails H/L Value = 630 RO reports unexpected continuous rod insertion with no turbine runback in progress.

Examiners Note: RO may request to take manual control of Master Flow Controller prior to direction provided in S2.OP-AB.ROD-0003.

RO places rod control in Manual.

RO reports rod motion has stopped.

CRS enters S2.OP-AB.ROD-0003, Continuous Rod Motion.

RO reports that 24 RC Loop Tavg Channel has failed high. (may also report DT is reading zero indicating failed high Cold Leg input)

Examiners Note: RO could place MFC in Manual at anytime or wait until directed in AB.ROD-0003.

RO places Master Fow Controller (MFC) to Manual

Page 15 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO reports various 2CC2 console alarms in for: RC Loop Tavg Deviation, Tavg-Tref Deviation, RC Tavg Hi or Lo-Lo, RC Loops DT Dev.

CRS confirms control rods are in manual and rod motion has stopped.

CRS directs RO to adjust rods in manual to maintain Tavg within 1.5 deg of T program. Any rod manipulation is pre-announced, and the RO monitors control board indications for plant response to rod motion.

RO reports rod motion was in the inward direction and a NIS channel has NOT failed.

CRS directs RO to stop any dilution in progress.

RO reports 24 loop Tavg channel has failed High.

CRS directs RO to return PZR level to program.

RO places Charging System Master Flow Controller in manual (if not previously performed).

RO adjusts charging flow to restore PZR level to program IAW Attachment 2.

RO defeats 24 loop Reactor Coolant Differential Temperature and 24 loop Reactor Coolant Average Temperatures on 2CC2.

Page 16 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO selects channel other than 24 loop for Reactor Coolant Differential Temperature and Reactor Coolant Average Temperature.

When PZR level has been restored to program, RO places Charging System Master Flow Controller in auto.

RO reports control rods are above the rod insertion limit.

RO restores control rods to previous position at time of load reduction.

RO places rod control in Auto after ensuring Tavg is within 1.5 degrees of Tref.

TS evaluation #2:

CRS enters TS: 3.3.1.1 Action 6 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) and 3.3.2.1.b Action 19* (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

Examiners Note: Operator actions already performed in AB.ROD-0003, no additional actions in control room, I&C Maintenance is required to complete S2.OP-SO.RPS-0002.

CRS initiates S2.OP-SO.RPS-0002 to place 24 loop Tavg in tripped condition.

Proceed to next event after Tech Specs has been evaluated or by direction from Lead Examiner.

5. RCS Leak

Page 17 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG Simulator Operator: Insert RT-4 by direction from Lead Examiner.

RC0002, RCS Leakage Value = 18000 Ramp = 1 minute RO reports unexpected OHA E-28 PZR HTR ON PRESS LO and Console Alarms for PZR LEVEL LO and CONT PRESS HI.

RO reports rapidly lowering PZR level and RCS Pressure.

RO reports 2R11A is rising.

CRS enters S2.OP-AB.RC-0001, RCS Leakage.

CRS initiates Attachment 1 CAS and directs RO to:

Trip the Rx

Confirm the Rx is tripped

Initiate Safety Injection

6. Large Break LOCA Simulator Operator: Ensure ET-1 is TRUE following Rx Trip. This will insert LBLOCA malfunction.

RC0001A, RCS rupture on RC loop 21 Auto SI fails to actuate on both trains:

Page 18 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO may report SI failed to Auto actuate (depending on where RCS pressure is at during time SI is manually actuated)

Critical Task-1 (CT-2): Manually actuate SI before transition out of EOP-TRIP-1.

SAT________ UNSAT________

RO manually actuates SI on one Train and verifies the other train actuated. [Critical Task #1]

RO continues Immediate Actions of TRIP-1:

Reports the Main Turbine is tripped and backs up Main Turbine trip.

Reports all 4KV vital busses energized.

Reports SI has been initiated.

CRS and RO verify Immediate Actions complete.

CRS directs initiation of the following EOP-TRIP-1 CAS actions when RCS pressure meets the criteria:

Stops RCPs (1350 psig)

Close Chagring Mini-flows (1500 psig)

RO announces Rx Trip and Safety Injection on the station PA.

PO reports ALL Vital Buses are energized.

PO reports SEC loading for 2B vital bus is NOT complete.

Page 19 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG

7. 22 RHR Pump fails to start on SEC signal (21 RHR Pump is C/T):

PO reports 22 RHR pump failed to start.

PO blocks and resets 2B SEC.

RO starts 22 RHR pump. [Critical Task-2]

Critical Task-2 (CT-5): Manually start one low head ECCS pump before transition out of EOP-TRIP-1.

SAT________ UNSAT________

PO throttles AFW flow to no less than 22E4lbm/hr while SG NR levels remain <9%. (15% adverse)

PO reports all valve groups in Table B are in their safeguards positions.

RO reports containment pressure has NOT remained <15 psig.

RO reports Phase B and Spray actuation Auto initiated.

RO reports 22 CS pumps is running.

RO reports MSLI Auto initiated.

Page 20 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO reports all valves groups in Table D are in the safeguards positions.

PO reports no indication of High Steam flow on 2RP4.

PO reports All vital busses are energized.

RO reports control room ventilation is in Accident Pressurized Mode.

RO reports proper switchgear room ventilation.

RO reports 2 CCW pumps are running.

RO reports both CCW HXs are in Auto.

RO reports RCS pressure is less than 300 psig (420 psig Adverse)

RO reports BIT flow >100 gpm, and expected SI pump and RHR pump flows consistent with RCS pressure.

PO maintains total AFW flow >22E4 lbm/hr until at least one SG NR level is > 9% (15% adverse), then maintains SG NR levels between 19% and 33%.

Examiners Note: Based on the pace of the crew, they may perform the following CAS steps sooner or later in EOP-TRIP-1.

Page 21 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO closes charging pump mini flows IAW TRIP-1 CAS when RCS pressure is < 1500 psig with BIT flow established. [TRIP-1 CAS]

RO stops RCPs IAW TRIP-1 CAS when RCS pressure is <1350 psig with ECCS flow established. [TRIP-1 CAS]

RO reports RCP status, and CRS determines whether a MSLI for temperature control is required.

RO reports both RTBs are open.

RO reports both PZR PORVs are closed and their block valves are open.

Crew identifies when containment pressure rises to 4 psig and adverse numbers are to be used.

RO reports RCP status and PZR spray consistent with number of operating RCPs.

RO reports RCS pressure < 1350 psig and ECCS flow established.

RO trips all RCPs IAW EOP CAS.

RO maintains seal injection to all RCPs.

Examiners Note: SG pressure could lowering slowly based on the break flow from the LBLOCA.

Page 22 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG PO reports normal expected SG pressures for current conditions and CRS determines no faulted SGs exist.

PO reports no indications of a SGTR exist.

RO reports two or more channels in Table F are NOT warning or alarm using P250 computer OR reports Containment Pressure > 4 psig.

EOP-LOCA-1 steps here:

CRS transitions to 2-EOP-LOCA-1, Loss of Reactor Coolant.

PO reports no indications of faulted SGs.

PO maintains total AFW flow >22E4 lbm/hr until at least one SG NR level is > 9% (15% adverse), then maintains SG NR levels between 19% and 33%.

PO reports no indications of a SGTR exist.

RO resets SI and Phase A isolation.

RO resets Phase B isolation.

RO opens 21 and 22CA330s.

PO resets all SECs.

PO reports 230V control centers reset.

Page 23 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG RO resets SGBD Sample Isolation Bypass and opens 21-24 SS94s.

CRS directs chemistry to sample 21-24 SGs for boron and activity.

RO reports both PZR PORVs are Closed and Block valves are Open.

RO reports subcooling is NOT greater than 0 F.

RO reports RHR is not aligned for Cold Leg Recirculation.

RO reports RHR flow is > 300 gpm.

Proceed to next event following status of 4KV Vital Buses RO reports All 4KV vital buses are energized from off site power.

PO stops all unloaded EDGs.

Role Play: IF requested to verify EDG is reset to Auto, THEN state the following:

EDG is reset for Auto start IAW EOP-APPX-9.

Verify OHA J-4, J-12 and J-20 for associated EDG is cleared.

Simulator Operator: No Actions.

Page 24 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG

8. Trip of 22 RHR Pump (Loss of Emergency Recirculation Capability):

Simulator Operator: Insert RT-5 at direction from Lead Examiner to trip the last running RHR Pump.

This malfunction will result in the crew entering EOP-LOCA-5.

RH0026B, 22 RHR Pump Trip Value = TRUE RO reports that 22 RHR Pump tripped.

RO reports NO RHR pumps are available.

Role Play: IF an operator is dispatched to investigate why 22 RHR pump trip, THEN report the following: the breaker tripped on overcurrent (relay flag is dropped).

CRS determines that no RHR Pumps are available and transitions from Step 16 to EOP-LOCA-5, Loss of Emergency Recirculation RO depresses close pushbuttons for 21 and 22 CC16s (CCW to RHR HX outlet valves).

EOP-LOCA-5 steps here:

Page 25 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG Examiners Note: IF crew transitions to EOP-LOCA-3 at this point, THEN LOCA-3 CAS will direct them to EOP-LOCA-5.

CRS transitions to 2-EOP-LOCA-5, Loss of Emergency Coolant Recirculation.

CRS verifies safeguards reset and all unloaded EDGs stopped.

RO reports containment sump level >62% light are illuminated.

RO reports NO train of Emergency Recirculation is available due to no RHR Pumps available.

CRS directs investigation into both RHR pump trips.

RO reports all available CFCUs are running in low speed.

Examiners Note: Critical Task-3 is broken down into a series of three (3) actions to conserve RWST inventory.

Part 1 is stopping CS Pumps Part 2 is RWST makeup.

Part 3 is reducing SI to one train.

Examiners Note: During validations, RWST level was 14.2 ft., Cntmt Pressure was 17 psig, and 4 CFCUs were running.

Page 26 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG CRS determines NO CS pumps are required to be running at Step 9 IAW Table C.

Critical Task-3 (CT-29): Makeup to RWST and minimize RWST outflow before ECCS pumps cavitate.

SAT_______ UNSAT_______

Part 1 is stopping CS Pumps Steps shaded are required to complete the CT.

Part 1 - Stopping CS pumps:

RO resets Spray actuation.

RO stops 21 AND 22 CS pump. [Critical Task-2, Part 1 complete]

RO closes 21 and 22 CS2s.

Part 2 - Make-up to RWST:

RO initiates makeup to the RWST IAW S2.OP-SO.CVC-0006.

S2.OP-SO.CVC-0006 Section 5.8 steps start here:

GO TO Page 29 to continue on with LOCA-5 steps.

Page 27 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG PO directs field operator to start RWST Heater Pump Simulator Operator: Insert RT-11 to simulate RWST Heater Recirc Pump in service bezel illuminated:

AH03 C2: RWST Heater Pump Stop Final = Override OFF AH03 C1: RWST Heater Pump Start Final = Override ON Delay = 2 seconds NOTIFY control room when RWST heater recirc pump is in service.

PO ensures VCT level is adequate.

PO obtains Boric Acid flow setpoint from REM Figure 100B or 100D. (at least 20 gpm)

PO resets COUNT A on makeup flow register to zero IAW Exhibit 1.

PO places makeup control mode select in stop PO places 2CV179 in Manual (goes full open)

PO places 2CV172 in Manual.

PO dispatches field operator to locally check 2BR170 is closed.

Page 28 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG Role Play: After 1-2 minutes report 2BR170 is CLOSED. No action needed by Simulator Operator.

PO notifies CRS to evaluate TS for applicability.

PO starts 22 Primary Water pump.

PO dispatches field operator to locally open 2CV182 and 2CV184.

Simulator Operator: Insert RT-10 when crew requests 2CV182 and 2CV184 to be locally opened in support of RWST makeup.

CV20A, 2CV182 Blender Isol Valve (ramp 30 secs)

CV21A, 2CV184 Blender Isol Valve (time delay 30 secs, ramp 30 secs)

Value = 100 NOTIFY control room when valves are open.

Examiners Note: When the 2CV182 and 2CV184 are opened the Primary Water flow counter will start.

PO places 22 Boric Acid Pump in Manual/Fast start PO adjusts 2CV172 flow to the value recorded previously. (at least 20 gpm)

Page 29 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG PO closes 21 and 22 CV160 if flow not achieved.

PO adjusts 2CV179 to 50 gpm using open/close pushbuttons. [Critical Task-3, Part 2 complete]

PO reports makeup to RWST has been initiated.

Critical Task-3 (CT-29): Makeup to RWST and minimize RWST outflow before ECCS pumps cavitate.

SAT_______ UNSAT_______

Part 2 is RWST makeup.

Steps shaded are required to complete the CT.

LOCA-5 continued here:

PO maintains total AFW flow >22E4 lbm/hr until at least one SG NR level is > 9% (15% adverse), then maintains SG NR levels between 19% and 33%.

CRS directs performance of SDM.

RCS cooldown at 100 F/hr:

PO plots RCS cooldown.

PO reports intact SGs available for cooldown

Page 30 of 40 SBT Evaluator/Instructor Activity Expected Plant/Student Response Comments LOG PO reports steam dumps NOT available due to MSLI.

PO dumps steam using intact available MS10s Part 3 - SI flow reduction to one train:

RO reports BIT flow is established.

RO stops all but one charging pump. [Critical Task-3, Part 3 complete]

Critical Task-3 (CT-29): Makeup to RWST and minimize RWST outflow before ECCS pumps cavitate.

SAT_______ UNSAT_______

Part 3 is reducing SI to one train.

Steps shaded are required to complete the CT.

RO runs only one SI pump.

RO reports No flow on 21 or 22 SJ49 flow meters.

RO reports no RHR pumps are running.

Terminate the scenario when the crew stops all but one Charging Pump or at Lead Examiners direction.

Page 31 of 40 VI. SCENARIO REFERENCES A. Alarm Response Procedures (various)

B. Technical Specifications C. Emergency Plan (ECG)

D. S2.OP-AB.COND-0001, Loss of Condenser Vacuum E. S2.OP-AB.ROD-0003, Continuous Rod Motion F. S2.OP-AB.RC-0001, RCS Leak G. 2-EOP-TRIP-1, Reactor Trip or Safety Injection H. 2-EOP-LOCA-1, Loss of Reactor Coolant I. 2-EOP-LOCA-5, Loss of Emergency Recirculation

TQ-AA-106-0204 Page 32 of 40 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 100% RCS BORON: 27 ppm MWe 1220 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS:

Reactor Engineering directs the use of control rods, boration and turbine load control during the load reduction.

MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

None EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

Load reduction to 89% at 10%/hour in preparation for Main Turbine valve testing.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Hope Creek and Salem 1 are at 100% power.

PRIMARY:

23 Charging Pump C/T for pulsation damper replacement.

21 RHR Pump C/T for motor bearing inspection.

SECONDARY:

Heating Steam is aligned to Unit 1 Polisher is in service Blowdown is 35K per loop to 23 Condenser / Flashtank RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

TQ-AA-106-0204 Page 33 of 40 ATTACHMENT 2 SIMULATOR READY-FOR-TRAINING CHECKLIST

1. Verify simulator is in TRAIN Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter With Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked Training Use Only and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

TQ-AA-106-0204 Page 34 of 40 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individuals incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

TQ-AA-106-0204 Revision 2 Page 35 of 40 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST SCENARIO IDENTIFIER: 19-01 NRC Scenario #2 REVIEWER: R. Chan Initials Qualitative Attributes RC 1. The scenario has clearly stated objectives in the scenario.

RC 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

RC 3. The scenario consists mostly of related events.

RC 4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point RC 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

RC 6. The events are valid with regard to physics and thermodynamics.

RC 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

RC 8. The simulator modeling is not altered.

RC 9. All crew competencies can be evaluated.

RC 10. The scenario has been validated.

NA 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

RC 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

TQ-AA-106-0204 Revision 2 Page 36 of 40 ATTACHMENT 4 (Cont)

SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 2 Target Quantitative Attributes per Scenario (NRC Form ES-D-1)

Initial Conditions: IC-211: 100% power, EOL; 21 Charging Pump I/S. The following equipment is out of service:

23 Charging Pump and 21 RHR Pump C/T for maintenance.

Turnover: The crew is directed to reduce power to 89% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using boration, control rods and turbine load control in preparation for Main Turbine valve testing.

Critical Tasks:

1. Manually actuate SI (see WOG CT-2)

2. Manually start low head ECCS pump (see WOG CT-5)

3. Make-up to RWST and minimize RWST outflow (see WOG CT-29)

Event Malf. No. Event Type* Event No. Description 1 N/A ALL (R) Load reduction to 89% at 10% per hour IAW IOP-4 2 SG0100C CRS (TS) 23 SG Pressure Channel 3 fails low BOP (C) 3 VC0087C 24 vacuum pump trips CRS (C)

ATC (I) 4 RC0015D 24 Loop Cold Ledg RTD fails high CRS (I, TS)

RC0002 -RCS Leak (18000 gpm, ramped) 5 ALL (M)

RP0108 -Auto Safety Injection fails to actuate 6 RC0001A ALL (C) Large Break LOCA BOP (I) 7 RP318A2 22 RHR Pump fails to start on SEC signal CRS (I)

ATC (C) 8 RH0026B 22 RHR Pump trips CRS (C)

ABs IOP-4 AR.ZZ-2 AB.COND-1 AB.ROD-3 AB.RC-1 EOPs TRIP-1 LOCA-1 LOCA-5

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Notes: None

TQ-AA-106-0204 Revision 2 Page 37 of 40 Scenario No.: 2 Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 7 2-8

2. Malfunctions after EOP entry (1-2) 3 6,7,8

3. Abnormal events (2-4) 3 2,3,4

4. Major transients (1-2) 1 5

5. EOPs entered/requiring substantive actions (1-2) 1 LOCA-1

6. Entry into a contingency EOP with substantive actions ( 1 per 1 LOCA-5 scenario set)

CT-2, CT-5,

7. Preidentified critical tasks (2) 3 CT-29

8. Tech Specs exercised ( 2) 2 2,4

TQ-AA-106-0204 Revision 2 Page 38 of 40 ATTACHMENT 5 ESG CRITICAL TASKS 19-01 NRC Scenario #2 CT #1 (CT-2):

Critical Task: Manually actuate SI before transition out of EOP-TRIP-1.

Basis: See WOG Rev. 2.

CT #2 (CT-5):

Critical Task: Manually start one low head ECCS pump before transition out of EOP-TRIP-1.

Basis: See WOG Rev. 2.

CT #3 (CT-29):

Critical Task: Makeup to the RWST and minimize RWST outflow to the RWST before ECCS pumps cavitate.

This CT is satisfied when the following series of actions are completed to conserve RWST inventory:

1. Stopping Containment Spray (CS) Pumps

2. Initiating RWST make up,

3. Reducing SI to one train BASIS: See WOG Rev. 2

TQ-AA-106-0204 Revision 2 Page 39 of 40 ATTACHMENT 6 ESG - PSA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out Y LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY COMPONENT, SYSTEM, OR Y/N COMPONENT, SYSTEM, OR TRAIN Y/N TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed

TQ-AA-106-0204 Page 1 of 32 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: NRC-3 [AB.CVC, AR.ZZ-4, AB.SW-1, AB.CN-1, AB.LOAD-1, TRIP-1, LOSC-1, TRIP-3]

SCENARIO NUMBER: 19-01 NRC-3 EFFECTIVE DATE: See Approval Below EXPECTED DURATION: 75 minutes REVISION NUMBER: 01 PROGRAM: L.O. REQUAL X INITIAL LICENSE STA OTHER Revision Summary:

New issue for 16-01 ILOT NRC exam. Incoporated comments from validation. Added 2SW191 unsat valve stroke time (21 charging pump) and 21 ABV Exhaust Fan trip to allow CRS to exercise Tech Specs. Note: Based on the minor changes to the scenario and no expected impact to the major event flowpaths and critical tasks, a full re-validation and SBT was not deemed necessary. A partial re-validation was performed on only the added Tech Spec changes on 11-8-17.

Rev. 01: Modified for 19-01 ILOT NRC Exam.

PREPARED BY: R. Chan 1-3-20 Lead Regulatory Exam Author Date APPROVED BY:

Operations Training Manager Date APPROVED BY:

Operations Department Date

TQ-AA-106-0204 Page 2 of 32 SCAN OF SIGNED SCENARIO COVER SHEET

Page 3 of 32 I. OBJECTIVES A. Given the order or indications of a charging system malfunction, PERFORM actions as the nuclear control operator to RESPOND to the loss or malfunction of the charging system in accordance with the approved station procedures.

B. Given indication of a loss or malfunction of the Charging system DIRECT corrective action for a Charging System malfunction in accordance with the approved station procedures.

C. Given indication of a loss of a SW Pump, PERFORM actions as the nuclear control operator to RESPOND to the malfunction in accordance with approved station procedures.

D. Given indication of a loss of a SW Pump, DIRECT corrective action for a SW System malfunction in accordance with the approved station procedures.

E. Given indication of a loss of a Condensate Pump, PERFORM actions as the nuclear control operator to RESPOND to the malfunction in accordance with approved station procedures F. Given indication of a loss or malfunction of the Condensate system DIRECT corrective action for a Condesate System malfunction in accordance with the approved station procedures G. Given the order or indications of a reactor trip, PERFORM actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures I. Given the order or indications of a safety injection PERFORM actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

J. Given indication of a safety injection DIRECT the response to the safety injection in accordance with the approved station procedures.

K. Given the order or indications of a safety injection PERFORM actions as the shift technical advisor to RESPOND to the safety injection in accordance with the approved station procedures.

L. Given the order or indications of a loss of secondary heat sink, perform actions as the nuclear control operator to RESPOND to the loss of heat sink in accordance with the approved station procedures.

M. Given indication of a loss of secondary heat sink, DIRECT the response to the heat sink loss in accordance with the approved station procedures.

N. Given the order or indications of a loss of secondary heat sink, PERFORM actions as the shift technical advisor for a loss of heat sink IAW approved station procedures.

O. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

Page 4 of 32 II. MAJOR EVENTS

1. VCT Level channel fails high (2LT-114)

2. RCS Wide Range Pressure transmitter fails low (2PT-405)

3. 23 SW Pump trips and 26 SW Pump fails to auto start

4. 23 Condensate Pump trips

5. 21 Feedwater Line break (inside containment)

6. ATWS

7. 21BF13 fails to close on SI signal

8. Terminate SI III. SCENARIO

SUMMARY

Page 5 of 32 A. The crew will receive the unit at 100% power MOL. 21 SW Pump is C/T for pump repack.

B. Once the crew takes the watch, VCT level channel 2LT-114 will fail high. This will result in the VCT diverting to the CVCS HUT and lowering VCT level. The crew will either recognize lowering VCT level or 2CV35 diverting to the HUT or unexpected Auto make-up (4 minutes later). The CRS will enter S2.OP-AB.CVC-0001, Loss of Charging, and will take action to manually align 2CV35 back to VCT.

C. After the VCT level is addressed, the the RCS Wide range Pressure Channel 2PT-405 will fail low. The crew will recognize the failed channel by OHA alarm and 2RP4 indication on SUbcooling Marging Monitor. The crew will take action IAW S2.OP-AR.ZZ-0004 and determine an invalid indication. The CRS will enter TS 3.3.3.7 Action a.1.

D. Following the VCT level issue, 23 SW Pump will trip and the standby 26 SW Pump will fail to Auto start on lowering pressure. The crew will respond by manually starting 26 SW Pump.

The CRS may enter S2.OP-AB.SW-0001, Loss of SW Header Pressure. The CRS will enter TS 3.7.4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

E. After 23 SW Pump trip is addressed, 23 Condensate Pump will trip. The crew will enter S2.OP-AB.CN-0001, Main Feedwater/Condensate System Abnormality, and bypass the condensate polisher system and determine a load reduction to 85% is required. The crew performs load reduction IAW S2.OP-AB.LOAD-0001, Rapid Load Reduction.

F. Once the crew has completed the load reduction, 21 SG feed line will break inside containment. A demand for Auto Reactor Trip will occur but the reactor will fail to trip (ATWS). The crew will trip the reactor by opening both rod drive M-G set breakers [Critical Task #1] and enter 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

G. Following entry into 2-EOP-TRIP-1, the crew will observe that 21 SG feed flow is oscillating with the other SGs indicating approx. 11% steam flow. The crew will initiate MSLI for faulted SGs. Following the MSLI, the crew will recognize that 21 SG is the faulted SG and isolate AFW flow by closing 21AF21 and 21AF11 [Critical Task #2]. During TRIP-1, the crew will also recognize that 21BF13 failed to close and take action to manually close. The crew will eventually transition to 2-EOP-LOSC-1, Loss of Secondary Coolant.

H. While in EOP-LOSC-1, the crew will isolate feed and steam flow to 21 SG [Critical Task

2]. The crew will transition to EOP-TRIP-3, SI Termination, to terminate SI by stopping ECCS pumps, isolating BIT flow and placing normal letdown in service.

I. The scenario may be terminated when the crew places normal letdown in service or at directon by Lead Examiner.

Page 6 of 32 J. INITIAL CONDITIONS

____ IC-203 PREP FOR TRAINING (i.e. computer setpoints, procedures, bezel covers ,tagged equipment)

Initial Description VC1and VC4 C/T RCPs (SELF CHECK)

RTBs (SELF CHECK)

MS167s (SELF CHECK) 500 KV SWYD (SELF CHECK)

SGFP Trip (SELF CHECK) 23 CV PP (SELF CHECK) 21 SW Pump C/T Complete Attachment 2 Simulator Ready-for-Training/Examination Checklist.

Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group

Page 7 of 32 EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: KBD12TCY //21BF13 FW INLET STOP VALVE CLOSE 1 COMMAND: DMF VL0023 PURPOSE: <update as needed>

MALFUNCTIONS:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time

______ 01 RC0022A RCS PRESS (PT405) FAILS HI/L N/A N/A N/A RT-2 0

______ 02 SW0215C 23 SERVICE WATER PUMP TRIP N/A N/A N/A RT-3 PRESS SW

______ 03 SW0339F 26 SW PUMP- Press SW Fails H/L N/A N/A N/A N/A FAIL HI

______ 04 CN0117C 23 CONDENSATE PUMP TRIP N/A N/A N/A RT-4

______ 05 CV0036 VCT LEVEL XMTR LT114 FAILS H/L N/A N/A N/A RT-1 100

______ 06 BF0111A 21 FW LINE BREAK INSIDE CNTMT N/A N/A N/A RT-5 10000

______ 07 RP0058 FAILURE OF AUTOMATIC RX TRIP N/A N/A N/A N/A

______ 08 RP0059A FAILURE OF MANUAL RX TRIP N/A N/A N/A N/A

______ 09 RP0059B FAILURE OF MANUAL SI/RX TRIP N/A N/A N/A N/A RP0060A FAILURE OF TRAIN "A" RX TRIP BREAKER

______ 10 N/A N/A N/A N/A TO TRIP RP0060B FAILURE OF TRAIN "B" RX TRIP BREAKER

______ 11 N/A N/A N/A N/A TO TRIP

______ 12 VL0446 21BF19 Fails to Position ( 0-100% ) N/A N/A N/A RT-5 50

______ 13 VL0023 21BF13 Fails to Position ( 0-100% ) N/A N/A N/A N/A 100 REMOTES:

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

______ 01 SW23D 21 SW PUMP BKR CONTROL POWER N/A N/A N/A N/A OFF

______ 02 SW24D 21 SW PUMP RACK OUT N/A N/A N/A N/A TAGGED

______ 03 CV41A VCT PRESSURE CONTROLLER SETPOINT N/A N/A N/A N/A 25

______ 04 RP18D Open MAIN RX TRIP BKR A N/A N/A N/A RT-10 TRIP OPEN

______ 05 RP19D Open MAIN RX TRIP BKR B 00:00:03 N/A N/A RT-10 TRIP OPEN

______ 06 MS05A 21MS45 21 STM GEN STM SUP-23 AFP N/A 10000 00:01:00 RT-11 0

______ 07 AF01D 23 AUX FP TRIP RESET N/A N/A N/A RT-12 RESET OVERRIDES:

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity

Page 8 of 32 OTHER CONDITIONS:

Description

Page 9 of 32 SEQUENCE OF EVENTS

a. State shift job assignments.

b. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

c. Inform the crew The simulator is running. You may commence panel walkdowns at this time.

SM please inform me when your crew is ready to assume the shift.

d. Allow sufficient time for panel walk-downs. When informed by the SM that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

Page 10 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment

1. 2LT-114 VCT Level fails high:

Simulator Operator: Insert RT-1 at direction from Lead Examiner.

CV0036, 2LT-114 fails H/L Value = 100 Examiners Note: This malfunction will not result in any alarms except if Auto make-up is initiated. The Lead Examiner may continue to next event at anytime.

Crew recognizes either VCT level is lowering or 2CV35 is diverted to CVCS HUT.

CRS enters S2.OP-AB.CVC-0001, Loss of Charging PO initiates Attachment 1 CAS RO reports 23 Charging pump is running.

RO reports no cavitation of Charging Pumps.

RO reports no PZR level failure RO reports 2LT-114 has failed high as indicated on the P-250 plant computer.

Examiners Note: If operator does not recognize lowering VCT level it will take approx. 4 minutes until you get Auto Make-up (11%). Auto make-up will NOT maintain VCT

Page 11 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment level and eventually the crew will receive console alarm for VCT Level Hi-Lo.

RO takes manual control of 2CV35 and positions to VCT.

RO reports letdown has not isolated.

CRS directs RO to maintain VCT level by either:

Cycling 2CV35, or

Initiating manual make-up IAW S2.OP-SO.CVC-0006 RO reports Charging Pump is supplying adequate charging flow.

CRS directs RO to place 2CV35 in Auto when cause has been corrected.

Proceed to next event at Lead Examiners direction

2. RCS Wide Range Pressure Channel fails low (2PT-405):

Simulator Operator: Insert RT-2 on direction from Lead Examiner.

RC0022A, 2PT-405 fails H/L Value = 0 RO reports unexpected OHA alarms for D-40 SUBCLG CH A MARGIN LO.

RO reports Subcooling Channel A is lost to monitor on

Page 12 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment 2RP4 and recorder on 2CC2.

Crew refers to OHA D-40 ARP.

RO reports 2PT-405 has failed low.

ARP refers CRS to review Tech Specs.

TS evaluation #1:

CRS enters TS 3.3.3.7 Action a.1 (30 days)

Proceed to next event at Lead Examiners direction

3. 23 SW Pump trips and 26 SW fails to Auto start:

Simulator Operator: Enter RT-3 on direction from Lead Examiner.

SW0215C, 23 SW pump trips SW0339F, 26 SW pressure switch fails high RO reports unexpected OHA alarms for:

B-13, 21 SW HDR PRESS LO

B-14, 22 SW HDR PRESS LO

B-15, TURB AREA SW HDR PRESS LO RO reports 23 SW Pump tripped and 26 SW Pump in Auto failed to start.

RO starts 26 SW pump.

RO reports low SW pressure alarms are cleared.

Page 13 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Examiners Note: Crew does not have to enter S2.OP-AB.SW-0001 since the only action that the AB requires is to start standby SW Pump.

CRS enters S2.OP-AB.SW-0001, Loss of SW Header Pressure PO initiates Attachment 1 CAS PO reports no indication of SW Bay leak.

PO starts SW Pumps to maintain header pressure between 95-150 psi.

PO reports all SW OHA alarms are cleared.

PO reports no indication of leak or valve malfunction on the turbine header.

TS evaluation #2:

CRS enters TS 3.7.4 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ). This is due to having 21 and 23 SW Pumps inoperable in one bay resulting in only one operable SW loop (refer to S2.OP-SO.SW-0005 Attachment 2)

Proceed to next event at Lead Examiner direction.

4. 23 Condensate Pump trips:

Simulator Operator: Insert RT-4 by direction from Lead Examiner.

Page 14 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CN0117C, 23 condensate pump trips PO reports 23 Condensate Pump tripped.

CRS enters S2.OP-AB.CN-0001, Main Feedwater/Condesnate Abnormality.

PO initiates Attachment 1 CAS PO reports SGFP did not trip PO reports 23 Condensate Pump tripped.

Role Play: After 1-2 minutes report the following; 23 Condensate Pump breaker is open and the overcurrent relay flag is up.

PO reports SGFP suction pressure is less than 320 psig.

PO opens 21-23 CN108s (Polisher Bypass valves)

PO reports 2CN47 is not open.

CRS evaluates plant conditons IAW Attachment 2 section 4.0 CRS determines that a load reduction to 85% Rx power at 5%/min is required.

CRS brief load reduction and Reactivity plan.

RO initiates boration IAW S2.OP-SO.CVC-0006,

Page 15 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Boration Concentration Control.

PO initiates load reduction using turbine load control IAW S2.OP-SO.TRB-0001, Turbine-Generator Startup Operations CRS enters S2.OP-AB.LOAD-0001, Rapid Load Reduction.

PO initiates Attachment 1 CAS RO maintains Tavg on program IAW Attachment 3 RO energizes all PZR heaters.

CRS directs WCC to transfer heating steam to Unit 1 IAW SC.OP-SO.HS-0001.

Proceed to next event after the load reduction is complete or at Lead Examiners direction.

5. 21 SG Feed Line Break (inside containment):

Simulator Operator: Insert RT-5 by direction from Lead Examiner.

BF0111A, 21 SG feedline break inside containment Value = 10000 ATWS:

RO reports demand for First-Out OHA for F-3, 21 SG LVL LO-LO but the Rx failed to Auto trip

Page 16 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO Trips the Rx by opening both M-G set breakers: 2E6D and 2G6D Critical Task #1 (CT-1): Manually trip the reactor before transition to FRSM-1 is required.

SAT _______ UNSAT ________

RO performs immediate actions of EOP-TRIP-1 RO reports large oscillating feed flow on 21 SG with no steam flow. All other SGs are indicating approx.

11% steam flow with no feed flow.

RO manually initiates MSLI.

RO reports Auto SI actuated on CNTMT PRESS HI RO backs up SI signal.

RO reports steam (feed) leak is on 21 SG.

PO receives permission to throttle AFW flow to no less than 22E4 lbm/hr.

PO closes 21AF21 and 21AF11 to isolate faulted 21 SG. [Critical Task #2, Part 1]

Page 17 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Critical Task # 2 (CT-17): Isolate the faulted SG before transition out of EOP-LOSC-1.

SAT_____ UNSAT_______

This CT is comprised of 2 parts; isolate feed flow and then steam flow later in EOP-LOSC-1.

RO reports SEC loading is not complete for B vital bus, but that all available equipment started.

PO reports 21 and 22 AFW pumps are operating.

21BF13 fails to close:

RO reports safeguards valve alignment status:

21BF13 is open Simulator Operator: Ensure ET-1 is TRUE when the 21BF13 closed pushbutton is depressed. This will delete malfunction VL0023.

PO manually closes 21BF13.

RO reports 21 and 22 CA330s are closed.

RO reports containment pressure has remained less than 15 psig.

PO reports main steam line isolation requirements were met and MSLI previously initiated.

Page 18 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment PO reports all 4KV vital busses are energized.

RO reports CAV is in Accident Pressurized mode.

RO reports correct switchgear room ventilation operation.

RO reports 2 CCW pumps are running.

RO reports both CCW HXs are in Auto.

RO reports correct ECCS pump alignment and expected flows for RCS conditions.

Examiners Note: PO should have lowered AFW flow to as close to 22E4 lbm/hr as possible.

PO reports AFW flow is >22E4 lbm/hr.

RO reports all RCPs are running.

RO reports Tavg is not stable and is rising.

RO reports Tavg is greater than 547 F.

PO controls Tavg by dumping steam using MS10s.

RO reports both reactor trip breakers are NOT open.

Examiners Note: If the crew does not dispatch an operator to locally open the RTBs, then they will not be able to reset SI and SEC to take control of the ECCS pumps in EOP-LOSC-1, unless they chose to block each SEC signal.

Page 19 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CRS directs WCC to locally open both Reactor Trip Breakers.

Simulator Operator: Insert RT-10 to locally open both RTBs.

RP18D, Open RTB A RP19D, Open RTB B RO reports both PZR PORVs are closed and block valves are open.

PO reports 21 SG pressure is lowering in an uncontrolled manner or completely depressurized.

RO reports that MSLI was previously initiated.

CRS transitions to 2-EOP-LOSC-1, Loss of Secondary Coolant.

RO reports MSLI has been initiated.

PO reports all valves in Table A are closed.

PO reports 21 SG pressure is dropping in an uncontrolled manner.

PO reports that all SGs pressures are NOT dropping in an uncontrolled manner OR completely depressurized.

PO reports the following valves are closed; 21BF19, 21BF40, 21BF13; 21AF21, 21AF11, 21MS10, 21MS7, 21MS18, 21MS167; 21GB4.

[Critical Task #2, Part 2]

Page 20 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Critical Task # 2 (CT-17): Isolate the faulted SG before transition out of EOP-LOSC-1.

SAT_____ UNSAT_______

PO reports that 21 SG is faulted.

PO reports that 23 AFW pump is not needed to maintain SG levels.

PO lowers 23 AFW pump speed to minimum.

PO Trips and then Stops 23 AFW pump.

Simulator Operator: IF requested, Insert RT-12 to reset 23 AFW pump 2MS52 trip valve.

AF01D 23 AUX FP TRIP RESET CRS dispatches operator to close 21MS45.

Simulator Operator: Insert RT-11 to close 21MS45.

MS05A 21 STM GEN SUP-23 AFP Final = 0 Ramp = 1 min RO resets Phase A.

RO resets SG sample isolation bypass.

Page 21 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO opens 21 thru 24 SS94s.

CRS directs Chemistry to sample all SGs for boron and activity.

RO reports that RCS temperature is rising.

PO adjusts MS10s to current intact SG pressure to stabilize RCS temperature.

RO reports no NR or WR SG levels are rising in an uncontrolled manner.

PO reports that 2R15, 2R19s and 2R46s are not in warning or alarm.

RO reports RCS subcooling is > 0 F.

PO reports that total AFW flow is NOT > 22E4 lbm/hr (about 3E4 lbm/hr during validations due to NR levels at 9% (15% adverse)).

RO reports that RCS pressure is stable or rising.

RO reports that PZR level is > 11% (19% adverse).

CRS transitions to EOP-TRIP-3, SI Termination.

Examiners Note: Need RTBs locally opened to reset SI.

RO resets SI, Phase A, and Phase B.

RO reports both CA330s are open.

RO reports that no spray valves are failed open.

Page 22 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO reports all SECs and control centers are reset.

RO stops all but 21 or 22 Charging Pump. (this should also include 23 Charging Pump if running)

RO reports RCS pressure is stable or rising.

Normal Charging Alignment:

RO reports that charging pump suction is aligned to the RWST.

RO opens 2CV139 and 2CV140.

RO closes 2SJ4, 2SJ5, 2SJ12, and 2SJ13.

RO closes 2CV55.

RO opens 2CV68 and 2CV69.

RO adjusts 2CV55 to maintain PZR level > 25%

(33% adverse)

RO reports PZR level is stable or rising.

RO reports RCS pressure is stable or rising.

RO reports that RCS pressure is > 1540 psig (1660 psig adverse).

RO stops 21 and 22 SI pumps.

RO reports that both RHR pumps are running and suction aligned to RWST.

RO stops 21 and 22 RHR pumps.

Page 23 of 32 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO reports RCS subcooling is > 0 F.

RO reports PZR level is > 11% (19% adverse).

RO reports no CS spray pumps are running.

Establish Normal Letdown:

RO reports PZR level is > 25% (33% adverse)

RO opens 2CV2 and 2CV277.

RO opens 2CV7.

RO adjusts 2CV55 to maintain > 87 gpm.

RO simultaneoulsy places one letdown orifice valve in service while adjusting the 2CV18 to maintain letdown pressure at 300 psig.

RO places 2CV18 in Auto.

RO reports normal letdown in service.

Scenarion may be terminated when letdown is restored or by direction from Lead Examiner.

Page 24 of 32 K. SCENARIO REFERENCES A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. 2-EOP-TRIP-1, Rx Trip or Safety Injection F. 2-EOP-LOSC-1, Loss of Secondary Coolant G. 2-EOP-TRIP-3, SI Termination H. S2.OP-AB.SW-0001, Loss of SW Header Pressure I. S2.OP-AB.CVC-0001, Loss of Charging J. S2.OP-SO.CN-0001, Main Feedwater/Condensate System Abnormality K. S2.OP-AB.LOAD-0001, Rapid Load Reduction L. S2.OP-IO.ZZ-0004, Power Operation

TQ-AA-106-0204 Page 25 of 32 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 100% RCS BORON: 802 MWe 1220 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

SECONDARY:

Polisher in service Blowdown 35K per loop to 23 Condenser RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

21 SW Pump C/T for pump repack.

TQ-AA-106-0204 Page 26 of 32 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in TRAIN Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. All printers have adequate paper AND functional ribbon

12. Required procedures clean

13. Multiple color procedure pens available

14. Required keys available

15. Simulator cleared of unauthorized material/personnel

16. All charts advanced to clean traces and chart recorders are on.

17. Rod step counters correct (channel check) and reset as necessary

18. Exam security set for simulator

19. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

20. Recording Media available (if applicable)

21. Ensure ECG classification is correct

22. Reference verification performed with required documents available

23. Verify phones disconnected from plant after drill.

24. Ensure ECG related paperwork is marked For Training Use Only.

TQ-AA-106-0204 Revision 2 Page 27 of 32 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individuals incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

TQ-AA-106-0204 Revision 2 Page 28 of 32 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST SCENARIO IDENTIFIER: 19-01 NRC Scenario 3 REVIEWER:

Initials Qualitative Attributes

1. The scenario has clearly stated objectives in the scenario.

2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

3. The scenario consists mostly of related events.

4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point

5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

6. The events are valid with regard to physics and thermodynamics.

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

8. The simulator modeling is not altered.

9. All crew competencies can be evaluated.

10. The scenario has been validated.

11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

TQ-AA-106-0204 Revision 2 Page 29 of 32 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 3 Target Quantitative Attributes per Scenario (NRC Form ES-D-1)

Initial Conditions: IC-203: 100% power, MOL; 21 SW Pump is C/T.

Turnover: Maintain current power level.

Critical Tasks:

1. Manually trip the reactor before transition to EOP-FRSM-1 is required (see WOG CT-1)

2. Isolate feed and stem flow to faulted SG (see WOG CT-17)

Event Malf. No. Event Type* Event No. Description RO (I) 1 CV0036 VCT Level Channel 2LT-114 fails high CRS (I) 2 RC0022A CRS (TS) RCS Wide Range Pressure Channel 2PT-405 fails low SW0215C RO (C) 3 23 SW Pump trips and 26 SW Pump fails to start in Auto SW0339F CRS (C,TS) 4 CN0117C ALL (C) 23 Condensate Pump trips 5 BF0111A ALL (M) 21 SG Feed Line Break inside containment RP0058 RP0059A RO (I) 6 RP0059B ATWS CRS (I)

RP0060A RP0060B VL0446 7 ALL (C) 21 BF19 and 21BF13 fails to close VL0023 ABs AB.CVC-1 AR.ZZ-4 AB.SW-1 AB.CN-1 AB.LOAD-1 EOPs TRIP-1 LOSC-1 TRIP-3

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

TQ-AA-106-0204 Revision 2 Page 30 of 32 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 3 Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 6 1, 2-7

2. Malfunctions after EOP entry (1-2) 2 6,7

3. Abnormal events (2-4) 3 1,3,4

4. Major transients (1-2) 1 5 TRIP-1

5. EOPs entered/requiring substantive actions (1-2) 3 LOSC-1 TRIP-3

6. Entry into a contingency EOP with substantive actions ( 1 per 0 NA scenario set)

7. Preidentified critical tasks (2) 2 5,6

8. Tech Specs exercised ( 2) 2 2,3 Comments:

Q-AA-106-0204 Page 31 of 32 ATTACHMENT 5 ESG CRITICAL TASKS 19-01 NRC Scenario 3 Critical Task #1 (CT-1): Manually initiate Rx Trip before transition to EOP-FRSM-1 is required.

Bases: See WOG Rev. 2 Critical Task #2 (CT-17): Isolate feed and steam flow to faulted SG before transition out of EOP-LOSC-1.

Bases: See WOG Rev. 2

TQ-AA-106-0204 Revision 2 Page 32 of 32 ATTACHMENT 6 ESG-PSA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each

TQ-AA-106-0204 Page 1 of 36 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: NRC-41 [AB.RAD-1, AB.CN-1, AB.RCP-1, TRIP-1, TRIP-2, SGTR-1]

SCENARIO NUMBER: 19-01 NRC ESG-41 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 70 minutes REVISION NUMBER: 03 PROGRAM: L.O. REQUAL X INITIAL LICENSE STA OTHER Revision Summary:

New issue for 16-01 ILOT NRC exam.

Rev. 01: Incorporated NRC comments from Prep week. Added Tech Spec LCO times.

Added clarification that CT#2 is broken down into two parts.

Rev. 02: Modified for 19-01 ILOT NRC exam.

Rev. 03 Incorporated NRC comments from working mtg on 2-14-20. Deleted Loss of Off-site Power to reduce coOldown time in SGTR-1 using steam dumps.

PREPARED BY: R. Chan 2-25-20 Lead Regulatory Exam Author Date APPROVED BY:

Operations Training Manager Date APPROVED BY:

Facility Representative Date

TQ-AA-106-0204 Page 2 of 36 SCAN OF SIGNED SCENARIO COVER SHEET

TQ-AA-106-0204 Page 3 of 36 I. OBJECTIVES A. Given the order, perform actions to raise reactor power IAW S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load.

B. Given indication of a radiation monitor system malfunction, DIRECT the response to the malfunction in accordance with approved station procedures.

C. Given the order or indications of a CFCU tripping, perform actions as the nuclear control operator to RESPOND to the malfunction, IAW approved station procedures.

D. Given the order or indications of a CFCU tripping, DIRECT the response to the malfunction IAW approved station procedures.

E. Given the failure of SGFP, perform actions as the nuclear control operator to RESPOND to the failure IAW S2.OP-AB.CN-0001.

F. Given the failure of SGFP, perform actions as the nuclear control operator to DIRECT the response to the malfunction IAW S2.OP-AB.CN-0001 G. Given the failure of affecting a Reactor Coolant Pump, DIRECT the response to the failure IAW S2.OP-AB.RCP-0001.

H. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

I. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

J. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

K. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

L. Given the order or indications of a steam generator tube rupture, perform actions as the nuclear control operator to RESPOND to the tube rupture in accordance with the approved station procedures.

M. Given the order or indications of a steam generator tube rupture, DIRECT the response to the tube rupture in accordance with the approved station procedures.

N. Given the order or indications of a ECCS pump failing to start, DIRECT the response to the malfunction in accordance with approved station procedures O. Given the order or indications of a PZR PORV malfunction, DIRECT the response to the malfunction in accordance with approved station procedures.

TQ-AA-106-0204 Page 4 of 36 II. MAJOR EVENTS A. Power Ascension B. 2R1B Control Room Radiation Monitor Channel 1 fails high C. 25 CFCU trips D. 21 SGFP trips and failure of Auto AFW start signal E. 23 RCP high vibration F. 21 SG Tube Rupture G. 21 SI Pump fails to start on SEC signal H. PZR PORV fails to close during RCS depressurization III. SCENARIO

SUMMARY

A. The crew will take the watch with the unit stable at 2% reactor power during a plant startup, BOL. 21 SGFP is in service and 22 SGFP is standby. Steam dumps are in Main Steam Pressure Control, Automatic, set at 1000 psig. The crew will be instructed to raise power to 10% and enter Mode 1.

B. The crew will initiate power ascension to 10%, and enter Mode 1, using Main Steam Dumps and control rods IAW S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load and S2.OP-SO.MS-0002, Steam Dump System Operation, Attachments 3 or 4.

C. After the crew enters Mode 1 (about 6% Rx power), the 2R1B Channel 1 Control Room Radiation Monitor will fail high. This will result in Control Room Ventilation actuating in Accident Pressurized Mode of operation. The crew will enter S2.OP-AB.RAD-0001, Abnomral Radaition. The crew will recognize that the 2R1B channel has failed high and is invalid. The CRS will enter TS 3.3.3.1 Action 28.

D. After the 2R1B channel failure has been addressed, 25 CFCU will trip on overcurrent protrection. The crew will respond by starting the standby CFCU in high speed. The crew will remove control power to the CFCU breakers to comply with Tech Spec containment integrity requirements. The CRS will enter TS 3.6.1.1 and 3.6.2.3 Action a.

E. After the 25 CFCU is addressed, 21 SGFP will trip on high thrust bearing oil pressure. The crew will respond IAW S2.OP-AB.CN-0001, Main Feedwater/Condensate System Abnormality.

The crew will reduce Rx power to less than 4%. The AFW pumps will fail to Auto start on low SG levels and the crew will respond by manually starting both motor driven AFW pumps or 23 AFW pump. The crew will throttle AFW flow as necessary to maintain SG narrow range levels between 19-33%. Note: the crew may take a conservative action to trip the Rx at this point due to lowering SG narrow range levels. If so, then the next event will occur during EOP-TRIP-2.

F. After the crew addresses the loss of 21 SGFP, 23 RCP will experience elevated shaft vibrations. The CRS wil enter S2.OP-AB.RCP-0001, RCP Abnomrality, and initate Attachment 2 for stopping 23 RCP due to exceeding shaft vibrations. The crew will trip the Rx, confirm the Rx is tripped, and stop 23 RCP.

TQ-AA-106-0204 Page 5 of 36 G. The crew will perform immediate actions in EOP-TRIP-1, Reactor Trip or Safety Injection, and then transition to EOP-TRIP-2, Reactor Trip Response, based on no SI required.

H. Shortly after transition to EOP-TRIP-2, 21 SG will rupture (650 gpm ramped over 5 minutes) and the crew will manually initiate SI and return to EOP-TRIP-1. While in EOP-TRIP-1, the crew will identify that 21 SI Pump failed to start. The crew will block and reset 2A SEC and manually start 21 SI Pump.

I. The crew will identify that 21 SG has a tube rupture based on SG narrow range levels rising, and 2R15, Condenser Offgas radiation montor in alarm, and transition to EOP-SGTR-1, Steam Generator Tube Rupture.

J. While in EOP-SGTR-1, the crew will isolate feed and steam flow to the ruptured 21 SG [Critical Task #1] and initiate a RCS cooldown [Critical Task #2] using steam dumps to the RCS target temperature. The crew will stop the cooldown when the hottest CETs are less than the required RCS cooldown temperature.

K. Following the RCS cooldown to target temperature, the crew will commence depressurization of the RCS using PZR PORVs due to normal spray unavailable (23 RCP stopped). After the crew reaches the depressurization stop criteria, they will close the PZR PORV and recognize that the PORV will not close. The crew will respond by closing the associated PZR PORV block valve [Critical Task #3].

L. The scenario may be terminated when the PZR PORV block valve is closed or by direction from the Lead Examiner.

TQ-AA-106-0204 Page 6 of 36 IV. INITIAL CONDITIONS

____ IC-204 PREP FOR TRAINING (i.e. computer setpoints, procedures, bezel covers ,tagged equipment)

Initial Description

____ 1 VC1and VC4 C/T

____ 2 RCPs (SELF CHECK)

____ 3 RTBs (SELF CHECK)

____ 4 MS167s (SELF CHECK)

____ 5 500 KV SWYD (SELF CHECK)

____ 6 SGFP Trip (SELF CHECK)

____ 7 23 CV PP (SELF CHECK)

____ 8 21 SGFP is in service

____ 9 IOP-3 open and complete up to step 4.3.18, Power Operation. Attachment 4 is marked up.

Steam Dumps are in MS Pressure Mode and Auto, and S2.OP-SO.MS-0002 is open and

___ 10 marked up to step 5.4.1

___ 11 Rod control in manual.

___ 12 Complete Attachment 2 Simulator Ready-for-Training/Examination Checklist.

Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group

TQ-AA-106-0204 Page 7 of 36 EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: KA501DOA //TRAIN "A" - SI OPERATE KEYSWITCH 1 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KA701DOA //TRAIN B - SI OPERATE KEYSWITCH 2 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KB201PNI //2PR1 RELIEF VALVE-OPEN 3 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KB202PNI //2PR2 RELIEF VALVE-OPEN 4 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: ET_array(1) .OR. ET_array(2) 5 COMMAND: DMF AF0353A PURPOSE: <update as needed>

EVENT ACTION: ET_array(1) .OR. ET_array(2) 6 COMMAND: DMF AF0353B PURPOSE: <update as needed>

MALFUNCTIONS:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time

______ 01 RM0207A PROCESS RAD MON 2R1B FAILS HIGH N/A N/A N/A RT-1

______ 02 VC0173E 25 CNTMT FAN COIL UNIT TRIP N/A N/A N/A RT-2 THRUST BEARING

______ 03 BF0105A 21 STM GEN FEED PUMP TRIP N/A N/A N/A RT-3 PRESSURE HIGH

______ 04 SG0078A 21 STEAM GENERATOR TUBE RUPTURE N/A 50 00:05:00 RT-5 650

______ 05 VL0297 2PR1 Fails to Position ( 0-100% ) 00:00:05 N/A N/A ET-3 100

______ 06 VL0298 2PR2 Fails to Position ( 0-100% ) 00:00:05 N/A N/A ET-4 100

______ 07 RP318R1 21 SI PMP FAILS TO START ON SEC N/A N/A N/A N/A AF0353A 21 AFP FAILURE TO AUTO START ON ANY

______ 08 N/A N/A N/A N/A (ALL) SIGNALS AF0353B 22 AFP FAILURE TO AUTO START ON ANY

______ 09 N/A N/A N/A N/A (ALL) SIGNALS

TQ-AA-106-0204 Page 8 of 36 REMOTES:

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

______ 01 CT195-1D 25 CFCU BKR #1 High Speed 125VDC N/A N/A N/A RT-10 OFF

______ 02 CT195-2D 25 CFCU BKR #2 High Speed 125VDC 00:00:05 N/A N/A RT-10 OFF

______ 03 CT195-3D 25 CFCU BKR #3 Low Speed 125VDC 00:00:10 N/A N/A RT-10 OFF

______ 04 RC42CX 23 RCP NOMINAL SHAFT x Vibration Reading N/A 13 00:04:00 RT-4 25

______ 05 RC42CY 23 RCP NOMINAL SHAFT y Vibration Reading N/A 5 00:10:00 RT-4 12 RC43CX 23 RCP NOMINAL MOTOR x Vibration

______ 06 N/A .5 00:04:00 RT-4 2.5 Reading RC43CY 23 RCP NOMINAL MOTOR y Vibration

______ 07 N/A .5 00:10:00 RT-4 2 Reading OVERRIDES:

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity OTHER CONDITIONS:

Description

____ 1. None

TQ-AA-106-0204 Page 9 of 36 V. SEQUENCE OF EVENTS A. State shift job assignments.

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew The simulator is running. You may commence panel walkdowns at this time.

CRS please inform me when your crew is ready to assume the shift.

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

TQ-AA-106-0204 Page 10 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment

1. Power Ascension Examiners Note: The crew will be using S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load, to perform the power ascension.

Step 4.3.16 provides guidance on raising reactor power using Steam Dumps IAW S2.OP-SO.MS-0002. The crew can use Attachments 3 or 4 of S2.OP-SO.MS-0002 to operate Steam Dumps.

The intent is for the crew to enter Mode 1, 6% Rx power, THEN; proceed to next event.

Examiners Note: Console alarm RC LOOPS Tavg - Tref DEVIATION will be in at the time the crew takes the watch.

The crew will be provided instructions during turnover that verification of Tavg is 541 F once per 30 minutes until alarm is reset in Control Room Narrative Log is being performed by the extra NCO.

This alarm will clear during the power ascension into Mode 1.

CRS directs power ascension using Main Steam Dumps in MS Pressure Control and control rods.

Examiners Note: The CRS will direct the

TQ-AA-106-0204 Page 11 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment crew in the order in which to raise Rx power by withdrawing control rods or raising steam dump demand first.

PO raises steam dump demand IAW S2.OP-SO.MS-0002, section 5.4 using Attachments 3 or 4.

RO withdraws control rods at the specified increments to maintain Tave on program.

Examiners Note: Program Tavg at 10%

Rx power is about 549 F.

During simulator runs, Steam Dump pressure setting was about 982 psig for a Rx Power of 5.4%.

RO announces when NIS indicates 5% Reactor Power and RECORDs time of Mode 1 entry in Control Room Narrative Log.

Proceed on to next event when Reactor Power is 6% or by direction from Lead Examiiner.

2. 2R1B Channel 1 Control Room Intake Radiation Monitor fails high:

Simulator Operator: Insert RT-1 on direction from Lead Examiner.

RM0207A, 2R1B fails H/L Value = high RO announces unexpected OHA alarm for A-6 RMS HI RAD OR TRBL.

TQ-AA-106-0204 Page 12 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CRS places power ascension on hold.

RO reports control room ventilation is in Accident Pressurized mode.

CRS enters S2.OP-AB.RAD-0001, Abnormal Radiation.

RO reports 2R1B Channel 1 is failed high.

RO reports alarm is invalid.

PO calls Unit 1 operator to check 1R1B Channel 2 reading.

Role Play: As the Unit 1 PO report the following: both 1R1B Channel 1 and 2 are reading normal.

CRS reviews Tech Specs.

TS evaluation #1:

CRS enters TS 3.3.3.1.b Action 28 (immediately place in Accident Pressurized mode or Recirculation mode of operation)

CRS requests assistance in troubleshooting failed RMS channel.

Proceed to next event after CRS evaluates Tech Specs or by direction from Lead Examiner.

TQ-AA-106-0204 Page 13 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment

3. 25 CFCU trips:

Simulator Operator: Insert RT-2 on direction from Lead Examiner.

VC0173E, 25 CFCU trips RO reports 25 CFCU tripped.

Role Play: If requested to why the CFCU tripped then report after 1 minute: both high speed breakers are open and the overcurrent flag is up.

Location: 84 ft. switchgear room CRS may direct starting 23 CFCU in high speed, if necessary.

CRS reviews S2.OP-SO.SW-0005, Attachemtn 5 for operability guidance.

TS evaluation #2:

CRS enters TS 3.6.2.3 Action a (14 days) and 3.6.1.1 (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months containment integrity until control power is removed)

CRS directs WCC to open control power for 25 CFCU high and low speed breakers.

Simulator Operator: Insert RT-10 when directed by CRS to open control power to high and low speed 460 V breakers.

TQ-AA-106-0204 Page 14 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CT195-1D, 25 CFCU breaker # 1high speed 125 VDC CT195-2D, 25 CFCU breaker #2 high speed 125 VDC CT195-3D, 25 CFCU breaker #3 low speed 125 VDC Proceed on to next event after control power is removed or by direction from Lead Examiner.

4. 21 SGFP Trips:

Simulator Operator: Insert RT-3 on direction from Lead Examiner.

BF0105A, 21 SGFP trips on thrust bearing oil pressure high.

RO reports console alarm for 21 SGFP thrust bearing oil bearing oil pressure high.

RO reports 21 SGFP tripped.

Role Play: If requested to why feedpump tripped then report after 1 minute: first out annunciator has thrust bearing oil pressue high trip locked in and will not clear.

CRS enters S2.OP-AB.CN-0001, Main Feedwater/Condensate System Abnormality CRS determines immediate actions of AB.CN-0001 is

TQ-AA-106-0204 Page 15 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment not met.

PO initiates Attachment 1 CAS.

PO reports 21 SGFP tripped.

RO reports Reactor Power is 6% or less than P-10 (10%).

RO reduces Reactor Power to less than 4% by inserting control rods.

CRS continues on with procedure.

PO reports Aux Feedwater is not in operation.

PO sets 21-24 AF21 demands to 0%.

PO starts 21 and 22 AFW Pumps.

PO adjusts 21-24 AF21s as necessary to maintain SG levels between +/- 5% of program.

Examiners Note: Depending how the crew feeds the SGs using AFW flow, the CRS may direct to trip the reactor based on SG NR levels approach the Auto Rx Trip setpoint (13%).

Simulator Operator: IF the crew trips the reactor here, THEN insert RT- 4 for the RCP High Vibration malfunction in EOP-TRIP-2.

TQ-AA-106-0204 Page 16 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Proceed to next event after AFW flow is established or by direction from Lead Examiner.

5. 23 RCP High Vibration (Major Transient):

Simulator Operator: Insert RT-4 on direction from Lead Examiner.

RC42CX, 23 RCP shaft x vibration Value = 5-25 RC42CY, 23 RCP shaft y vibration Value = 5-12 RC43CX, 23 RCP motor x vibration Value = 0.5-2.5 RC43CY, 23 RCP motor y vibration Value = 0.5-2.0 RO reports unexpected OHA alarm D-35 for RCP VIB HI.

RO reports 23 RCP vibration is elevated on 2RP3 monitor.

CRS enters S2.OP-AB.RCP-0001, RCP Abnormality RO reports 23 RCP shaft vibration exceeds 20 mils.

CRS implements the CAS action.

RO Trips the Rx.

RO Confirms the Rx Trip.

TQ-AA-106-0204 Page 17 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO stops 23 RCP.

CRS enters 2-EOP-TRIP-1, Reactor Trip of Safety Injection.

RO continues on with immediate actions of TRIP-1.

CRS and RO review immediate actions.

CRS and RO perform immediate action steps of EOP-TRIP-1 and confirm no Safety Injection is required.

PO throttles AFW flow to no less than 22E4 lbm/hr.

CRS transitions to 2-EOP-TRIP-2, Reactor Trip Response.

Examiners Note: CFSTs are in effect when transition out of EOP-TRIP-1 occurs. STA will report to control room 10 minutes after being summoned via page to monitor CFSTs.

CRS directs RO and PO to implement the CAS of EOP-TRIP-2.

Proceed on to next event when crew transitions to EOP-TRIP-2 or by direction from Lead Examiner.

6. SG Tube Rutpure (ramped):

TQ-AA-106-0204 Page 18 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Simulator Operator: Insert RT-5 on direction from Lead Examiner. This will insert a SG Tube Leak starting at 50 gpm then escalating to 650 gpm over a 5 minute period.

SG0078A, 21 SGTR Value = 50-650 gpm Ramp = 5 minutes Record Time SGTR is inserted:

RO reports RCS pressure and PZR level are lowering.

RO reports unexpected OHA alarm A-6 RMS HI RAD OR TRBL.

RO reports 2R15 is in Alarm.

Examiners Note: Crew can initiate SI without going to AB.SG-1.

CRS enters S2.OP-AB.SG-0001, Steam Generator Tube leak CRS implements the CAS action of AB.SG-0001 RO initiates Safety Injection.

CRS returns to EOP-TRIP-1.

TQ-AA-106-0204 Page 19 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO initiates SI and performs immediate actions of EOP-TRIP-1 CRS re-enters EOP-TRIP-1.

CRS performs immediate actions of EOP-TRIP-1.

CRS directs RO and PO to implement the CAS.

PO reports that SEC loading is NOT complete for energized ALL Vital Buses.

21 SI Pump fails to start on SEC signal:

PO reports 21 SI Pump failed to start.

PO blocks 2A SEC.

PO resets 2A SEC.

RO starts 21 SI Pump.

PO reports that 21 and 22 AFW pumps are running.

PO reports 21 SG NR levels are rising.

PO closes 21AF21 and 21AF11 valves. [Critical Task #1]

TQ-AA-106-0204 Page 20 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment Critical Task #1 (CT-18): Isolate feed flow to ruptured SG within 10 minutes.

SAT ________ UNSAT ________

Record Time AFW flow isolated:

If the ruptured SG is known at this point, the PO may request to close the 21AF21 and 21AF11 to isolate feed flow to the ruptured SG.

RO reports all valve groups are in safeguards positions.

RO reports that containment pressure has remained less than 15 psig.

PO reports that 2RP4 does NOT indicate high steam flow coincident with low steam pressure or low-low Tavg.

PO reports all 4KV vital buses are energized.

RO reports control room ventilation is in Accident Pressurized mode.

RO reports 2 switchgear supply and 1 exhaust fan are running.

RO reports 2 CCW pumps running.

RO reports ECCS flow as expected for current RCS pressure.

TQ-AA-106-0204 Page 21 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment PO maintains total AFW flow greater than 22E4 lbm/hr until at least one SG NR level is >9%, then maintains SG NR level 19-33%.

RO reports 21, 22, 24 RCPs are running.

RO reports RCS Tcolds are stable or tending to 547 F.

RO reports both RTBs are open.

RO reports both PZR PORVs are closed.

RO reports PZR PORV block valves are open.

RO reports 21, 22, 24 RCPs are running (23 RCP stopped previously).

RO reports both PZR spray valves are closed.

RO reports that RCS pressure is > 1350 psig.

RO maintains seal injection flow to all RCPs.

PO reports NO SG pressures are dropping in an uncontrolled manner or completely depressurized.

Examiners Note: After stopping 23 RCP, NR levels in 23 SG may be also rising. The crew should recognize that this is due to loss of forced circulation in that RC loop and reduced steaming effect in that SG.

TQ-AA-106-0204 Page 22 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO reports that NR level in 21 SG is rising in an uncontrolled manner.

CRS transitions to EOP-SGTR-1, Steam Generator Tube Rupture.

PO reports NR levels rising in 21 SG.

PO sets 21MS10 to 1045 psig.

PO closes 21MS167, 21MS18, 21MS7, and 21GB4.

PO reports 21MS167, 21MS18, and 21MS7 are closed.

PO reports that 21 SG is ruptured.

PO reports 23 AFW Pump is not the only source of feed flow.

PO lowers 23 AFW speed to minimum.

PO Trips 23 AFW Pump.

CRS directs WCC to close 21MS45.

Simulator Operator: Use Remote MS05A to simulate closing 21MS45.

Notify CRS when valve is closed.

CRS directs WCC to close 2SS321.

CRS dispatches operator to shift gland sealing steam to alternate source IAW S2.OP-SO.GS-0001.

TQ-AA-106-0204 Page 23 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CRS determines RCS target temperature using Table B (SG press at >1000 psig = 503 F CETs).

Examiner Note: Depending on the pace of the crew during EOP-TRIP-2, the crew may have determined that RCS temperature was not being controlled and initiated MSLI. IF this was peformed, THEN, the crew will report that NO steam dumps are available and cooldown with intact MS10s.

During validation using MS10s it took about 6 mins to reach CET of 503 F.

PO reports steam dumps are available.

PO places steam dumps in Manual.

PO places steam pressure valve demand to 0%.

PO places steam dumps in MS PRESS CONTROL.

PO adjusts steam pressure valve demand to 25%.

When Tavg low-low is reached, PO depresses Bypass Tavg pushbuttons.

PO dumps steam using steam dumps on intact SGs. [Critical Task #2, Part 1]

TQ-AA-106-0204 Page 24 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment CT#2 (CT-19): Control initial RCS cooldown so that transition from EOP-SGTR-1 does not occur.

This CT is broken down into two (2)

Parts; establishing RCS cooldown and then maintaining RCS temperature.

SAT_____ UNSAT_____

CRS continues on in EOP-SGTR-1.

RO reports hottest CETs are not less than RCS cooldown target temp.

PO maintains AFW flow > 22E4 lbm/hr until one SG NR level is > 9%, then maintain between 19% and 33%.

RO reports power is available to both PZR PORV stop valves.

RO reports both PZR PORVs are closed.

RO resets SI, Phase A, and Phase B isolation.

RO opens 21 and 22 CA330s.

PO resets each SEC and associated control centers.

RO reports RHR suction is aligned to the RWST.

RO stops both RHR pumps.

TQ-AA-106-0204 Page 25 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO reports hottest CETs are not less than RCS target temp.

Crew waits until hottest CETs are less than RCS target cooldown temp.

RO reports hottest CETs less than RCS target cooldown temp.

Examiners Note: It will take approx. 5 mins to reach the RCS target temperature.

PO stops the cooldown by placing MS Pressure Control in Auto. [Critical Task #2 - Part 2]

CRS directs PO to dump steam to maintain CET temp.

less than required.

PO reports ruptured SG pressure is stable or rising.

RO reports RCS subcooling is greater than 20 F.

RO reports normal PZR spray is NOT available (23 RCP stopped)

RCS depressurization using PZR PORVs:

RO reports PZR PORV are available.

CRS reviews depressurization termination criteria IAW Table E.

TQ-AA-106-0204 Page 26 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment RO opens ONLY one PZR PORV.

RO reports RCS pressure islowering.

RO reports when depressurization termination criteria is met IAW Table E.

PZR PORV fails to close:

RO closes PZR PORV.

Simulator Operator: Ensure ET-3 or ET-4 is TRUE for the PZR PORV opened.

This will insert malfunction to prevent PORV from closing.

ET-3, 2PR1 fails open ET-4, 2PR2 fails open RO reports opened PZR PORV failed to close.

RO closes the associated PZR PORV block valve for the open PORV. [Critical task #3]

Critical Task # (CT-10): Close PZR PORV block valve.

SAT _________ UNSAT ______

RO reports RCS pressure rising.

The scenario maybe terminated when the PZR PORV block valve is closed or

TQ-AA-106-0204 Page 27 of 36 Evaluator/Instructor Activity Expected Plant/Student Response SBT LOG Comment as directed by the Lead Examiner.

TQ-AA-106-0204 Page 28 of 36 VI. SCENARIO REFERENCES A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load F. S2.OP-AB.RAD-0001, Radiation System Abnormality G. S2.OP-SO.MS-0002, Steam Dump System Operation H. S2.OP-AB.CN-0001, Main Feedwater/Condensate System Abnormality I. S2.OP-AB.RCP-0001, Reactor Coolant Pump Abnormality J. 2-EOP-TRIP-1, Reactor Trip or Safety Injection K. 2-EOP-TRIP-2, Reactor Trip Response L. 2-EOP-SGTR-1, Steam Generator Tube Rupture

TQ-AA-106-0204 Page 29 of 36 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 2 POWER: 2% RCS BORON: 1584 MWe 0 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

N/A REACTIVITY PARAMETERS

Control Bank D at 114 steps.

Reactor Engineering directs use of control rods and steam dumps to raise power to 10%. No Fuel Conditioning Limits are imposed until 50%.

MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

None EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

S2.OP-IO.ZZ-0003, Hot Standby to Minimum Load complete up to Section 4.3, step 4.3.18.

S2.OP-SO.MS-0002, Steam Dump System Operation (5.4.1)

Monitoring Tavg > 541 F once per 30 minutes due to RC Loop Tavg - Tref Deviaton console alarm in (extra NCO to log).

Power ascension to 10% using control rods and steam dumps, and enter Mode 1.

Reactor Engineering is standing by to support power ascension.

Mode 1 entry is authorized.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

PRIMARY:

SECONDARY:

On main feedwater using 21 SGFP; 22 SGFP O/S in standby RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

TQ-AA-106-0204 Page 30 of 36 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in TRAIN Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked Training Use Only and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

TQ-AA-106-0204 Page 31 of 36 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individuals incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

TQ-AA-106-0204 Page 32 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST SCENARIO IDENTIFIER: 19-01 NRC Scenario #4 REVIEWER: R. Chan Initials Qualitative Attributes RC 1. The scenario has clearly stated objectives in the scenario.

RC 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

RC 3. The scenario consists mostly of related events.

RC 4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point RC 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

RC 6. The events are valid with regard to physics and thermodynamics.

RC 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

RC 8. The simulator modeling is not altered.

RC 9. All crew competencies can be evaluated.

RC 10. The scenario has been validated.

NA 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

RC 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

TQ-AA-106-0204 Page 33 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 4 Target Quantitative Attributes per Scenario (NRC Form ES-D-1)

Initial Conditions: IC-204: 2% power, BOL; 21 SGFP I/S.

Turnover: The crew is directed to continue power ascension to 10% reactor power IAW S2.OP-IO.ZZ-0003 using control rods, steam dumps, and turbine load control.

Critical Tasks:

1. Isolate feed and stem flow to ruptured SG (see WOG CT-18)

2. Cooldown RCS to target temperature (see WOG CT-19)

3. Close PZR PORV block valve on open PORV (see WOG CT-10)

Event Malf. No. Event Type* Event No. Description 1 N/A ALL (R) Continue power ascension to 10% IAW IOP-3 2 RM0207A CRS (TS) 2R1B Control Room Radiation monitor fails high RO (C) 3 TU0056 25 CFCU trips CRS (TS) 4 BF0105A ALL (C) 21 SGFP trips RC42CX RC42CY 5 ALL (M) 23 RCP high shaft vibrations RC43CX RC43CY 6 SG0078A ALL (C) 21 SGTR (650 gpm ramped over 5 minutes)

BOP (I) 7 SJ0184A 21 SI Pump fails to start on SEC signal CRS (I)

VL0297 8 ALL (C) PZR PORV fails to close during RCS depressurization VL0298 ABs IOP-3 AB.CN-1 AB.RCP-1 AB.SG-1 EOPs TRIP-1 TRIP-2 TRIP-1 SGTR-1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

TQ-AA-106-0204 Page 34 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 4 Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 7 2-8

2. Malfunctions after EOP entry (1-2) 3 6,7,8

3. Abnormal events (2-4) 3 2,3,4

4. Major transients (1-2) 1 5

5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-1

6. Entry into a contingency EOP with substantive actions ( 1 per 0 NA scenario set)

CT-18,CT-19,

7. Preidentified critical tasks (2) 3 CT-10

8. Tech Specs exercised ( 2) 2 2,3

TQ-AA-106-0204 Page 35 of 36 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST 19-01 NRC Scenario #4

1. Critical Task #1 (CT-18): Isolate feed and steam flow to ruptured SG before a transition to SGTR-3 occurs.

Bases: See WOG Rev 2

2. Critical Task #2 (CT-19): Control initial RCS cooldown so that transition from EOP-SGTR-1 does not occur due to low subcooling, o rsevere challenge on CFST Thernal Shock or Shutdown Margin.

Note: This CT is broken down into two (2) parts that include establishing RCS cooldown and then maintaining RCS temperature.

Bases: See WOG Rev 2

3. Critical Task #3 (CT-10): Close PZR PORV block valve of stuck open PZR PORV by completion of MCA step in SGTR-1 that directs closing PZR PORV block valve.

Note: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP

TQ-AA-106-0204 Revision 2 Page 36 of 36 ATTACHMENT 6 ESG-PRA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water Y Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST Y Cooldown the RCS and depressurize the system Y Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG

TQ-AA-106-0204 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: NRC-51 [IOP-4, AB.ROD-3, AR.ZZ-11, TRIP-1, FRHS-1 w/Condensate Recovery using S/Ds]

SCENARIO NUMBER: 19-01 NRC ESG-51 EFFECTIVE DATE: See Approval Below EXPECTED DURATION: 60 minutes REVISION NUMBER: 12 PROGRAM: L.O. REQUAL X INITIAL LICENSE STA OTHER Revision Summary:

For previous revision summaries see ESG-1512 Rev. 10 (5-1-19) (formerly ESG-1811) Modified for 2019 Annual Exam. Deleted Containment pressure malfunction and 2B SEC failure. Added 23 charging pump trip and PZR spray valve failure. Changed initial condition for 21 charging pump C/T to support TS call on 23 charging pump trip.

Rev. 11 (last used on 2019 Annual ESG-1908). Modified for 19-01 NRC exam.

Rev. 12 Incorporateed NRC comments from 2-14-20 working mtg to reduce the scenario duration. Removed starting 23 CN Pump, 24MS29 failing closed (note: 5%/min ramp rate no longer applicable), 2PT-506 failure, failure of Phase A to actuate, and moved Loss of 2B 4KV bus following Rx Trip. Added 22 ABV Exhaust fan damper failure and 2PT-505 failure.

Changed CT-12 to CT-13 MT failure to Auto Trip no MSLI required.

PREPARED BY: R. Chan 2-25-20 Lead Regulatory Exam Author Date APPROVED BY:

Operations Training Manager or Date designee APPROVED BY:

Operations Department Date

TQ-AA-106-0204 Page 2 of 33 SCAN OF SIGNED SCENARIO COVER SHEET

TQ-AA-106-0204 Page 3 of 33 I. OBJECTIVES A. Given the order, the crew will commence a power ascension IAW S2.OP-IO.ZZ-0004.

B. Given an instrument failure of 2PT-505, the crew will take actions IAW S2.OP-AB.ROD-0003 and place rods to manual and place steam dumps to MS Pressure Mode. CRS will exercise Tech Specs.

C. Given an indication of loss of air flow for 22 ABV Exhuast fan, the crew will take corrective actions IAW S2.OP-AR.ZZ-0011 and place the standby ABV Exhaust fan in service. CRS will exercise Tech Specs.

D. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

E. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

F. Given the order or indications of a safety injection perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

G. Given indication of a safety injection DIRECT the response to the safety injection in accordance with the approved station procedures.

H. Given the order or indications of a loss of secondary heat sink, perform actions as the nuclear control operator to RESPOND to the loss of heat sink in accordance with the approved station procedures.

I. Given indication of a loss of secondary heat sink, DIRECT the response to the heat sink loss in accordance with the approved station procedures.

J. Given the order or indications of a loss of secondary heat sink, PERFORM actions as the shift technical advisor for a loss of heat sink IAW approved station procedures.

K. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

TQ-AA-106-0204 Page 4 of 33 II. MAJOR EVENTS

1. Power ascension to 100% at 10%/hour.

2. 2PT-505 Turbine Inlet Pressure Channel fails low

3. 22 ABV Exhaust Fan damper fails closed

4. 23BF19 Feedwater Reg Valve fails closed (MT)

5. Main Turbine fails to trip and Auto MSLI fails to actuate.

6. Loss of 2B 4KV Vital Bus (loss of 22 MDAFW Pump).

7. Loss of all AFW flow and recovery by initiating Condensate flow.

III. SCENARIO

SUMMARY

A. The crew takes the watch at 84% power, MOL. 23 Condensate Pump has just been placed in service following maintenance. 21 Charging Pump is in service.

B. After the crew takes the watch, the crew commence a power ascension to 100% at 10%/hour. The crew will control RCS temperature by using dilution, control rods and turbine load control.

C. Once the power ascension has commenced, 2PT-505 turbine inlet pressure channel will fail low causing control rods to continoulsy inert. The crew will respond as directed IAW S2.OP-AB.ROD-0003, Continuous Rod Motion, by placing control rods in manual. The crew will also place steam dumps in MS Pressure Mode and CRS will enter TS 3.3.2.1 Act 19.

D. Following the 2PT-505 failure, 22 ABV Exhaust Fan damper will fail closed causing low air flow console alarm. The crew will recognize the low air flow and take corrective actions IAW S2.OP-AR.ZZ-0011, 2CC1 ARP to stop 22ABV Exhaust Fan and start the standby ABV Exhaust Fan.

The CRS will enter TS 3.7.7 Action a.

E. Once the crew addresses the low air flow for 22 ABV Exhaust Fan, 23BF19 will fail closed (ramped). The crew will receive console alarms for level deviation and recognize that the 23BF19 is closing. Attempts to take manual control will be unsuccessful and the crew will manually trip the reactor.

F. Following the Rx Trip, the Main Turbine fails to Auto trip. The crew responds by manually tripping the main turbine using the bezel trip pushbutton as part of immediate actions of 2-EOP-TRIP-1

[Critical Task #1]. Automatic Safety Injection will occur following Rx Trip based on the main turbine failing to trip and high steam flow.

G. Following reactor trip, the crew will recognize that the 2B 4KV Vital Bus is de-energized due to Bus Differential protection (results in loss of 22 MDAFW Pump). At the completion of ECCS flow verification, 23 AFW pump will trip on overspeed resulting in no AFW flow. The crew will transition to 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink, when directed in EOP-TRIP-1.

H. While in FRHS-1, the crew will continue to attempts to restore an alternate source of feedwater using Condensate Recovery path (SGFPs are not available due to SI signal). The crew will

TQ-AA-106-0204 Page 5 of 33 depressurize one steam generator using steam dumps. The crew will establish feed flow to one SG and verify that SG Wide Range levels are rising prior to exiting FRHS-1 [Critical Task #2].

I. The Lead Examiner may terminate the scenario after condensate flow has been established and/or WG level is rising.

TQ-AA-106-0204 Page 6 of 33 A. INITIAL CONDITIONS

____ IC-210 PREP FOR TRAINING (i.e. computer setpoints, procedures, bezel covers ,tagged equipment)

Initial Description

VC1and VC4 C/T

RCPs (SELF CHECK)

RTBs (SELF CHECK)

MS167s (SELF CHECK)

500 KV SWYD (SELF CHECK)

SGFP Trip (SELF CHECK)

23 CV PP (SELF CHECK)

Suggested Protected Equipment:

None

Complete Attachment 2 Simulator Ready-for-Training/Examination Checklist.

TQ-AA-106-0204 Page 7 of 33 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: MONP254 < 10. //CONT ROD BANK C < 10 ( RX TRIP )

1 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KCB02TY6 //TRIP TURBINE 2 COMMAND: DMF RP0073 PURPOSE: <update as needed>

MALFUNCTIONS:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time

______ 01 VL0448 23BF19 Fails to Position ( 0-100% ) N/A 40 00:01:00 RT-3 0 ALL ABOVE (20/AST,20-

______ 02 RP0073 MN TURB. TRIP FAILURES (VARIOUS ) N/A N/A N/A N/A 2/AST,20-ET) FAIL

______ 03 RP0279A AUTO MSLIS FAILS TO ACT, TRN A N/A N/A N/A N/A

______ 04 RP0279B AUTO MSLIS FAILS TO ACT, TRN B N/A N/A N/A N/A

______ 05 AF0181A 21 AUX FEEDWATER PUMP TRIP N/A N/A N/A ET-1

______ 06 AF0183 23 AUX FW PMP OVERSPEED TRIP N/A N/A N/A RT-4

______ 07 TU0055 TURBINE INLET PRESS XMTR 505 FAILS H/ N/A N/A N/A RT-1 0

______ 08 EL0145 LOSS OF 2B 4160V VITAL BUS N/A N/A N/A ET-1 REMOTES:

SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time

______ 01 AF20D 21 AFW PUMP BKR CONTROL POWER N/A N/A N/A RT-10 OFF ANCGA072 CGA OVRD 22 AUX BLDG EXH FAN LOW

______ 02 N/A N/A N/A RT-2 OVRD ON AIR FLOW ALARM OVERRIDES:

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity

TQ-AA-106-0204 Page 8 of 33 OTHER CONDITIONS:

Description

TQ-AA-106-0204 Page 9 of 33 SEQUENCE OF EVENTS

a. State shift job assignments.

b. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

c. Inform the crew The simulator is running. You may commence panel walkdowns at this time.

SM please inform me when your crew is ready to assume the shift.

d. Allow sufficient time for panel walk-downs. When informed by the SM that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

TQ-AA-106-0204 Page 10 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG

1. Power Ascension to 100%

CRS briefs crew on power ascension to 100% at 10%/hour IAW S2.OP-IO.ZZ-0004, Power Operation.

RO briefs reactivity plan for power ascension.

PO briefs turbine load control plan.

RO initiates dilution IAW S2.OP-SO.CVC-0006 or uses control rods.

PO initates turbine load control IAW S2.OP-SO.TRB-0001, Turbine Generator Startup Operation.

RO monitors Tavg and control rods for proper response.

Proceed to next event by direction from Lead Examiner.

2. 2PT-505 Turbine Inlet Steam Pressure Channel fails low:

Simulator Operator: Insert RT-1 by direction from Lead Evaluator.

TU0055, 2PT-505 fails low Value = 0 RO announces rods stepping in at 72 steps per minute, no load reject in progress, and requests to place rod control in manual.

TQ-AA-106-0204 Page 11 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG CRS directs RO to place rods in manual.

RO places rod control in manual and reports rod motion has stopped.

CRS enters S2.OP-AB.ROD-0003, Continuous Rod Motion.

CRS directs RO to maintain Tavg within 1.5°F of Tref, and RO uses manual rod control to control Tavg within that band.

RO reports Tavg and NIS channels NOT failed.

RO reports rods above the RIL.

PO reports PT-505 failed low.

PO places Main Steam dumps in MS Pressure Control-Auto.

TS evaluation #1:

CRS enters TSAS 3.3.2.1.b, Action 19 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ).

CRS initiates S2.OP-SO.RPS-0006, Main Turbine Channel Trip / Restoration.

RO withdraws control rods to ARO position.

Examiners Note: Rods will be left in Manual. This should not have any impact to the outcome of the scenario.

TQ-AA-106-0204 Page 12 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Proceed to next event at Lead Examiners direction.

3. 22 ABV Exhaust Fan damper fails closed:

Simulator Operator: Insert RT-2 on direction from Lead Evaluator.

ANCGA072, 22 ABV Exhaust Fan Low Air Flow Console Alarm Value = OVRD ON RO reports unexpected console alarm for 22 ABV Exhaust Fan AIR FLOW LOW PO refers to 2CC1 ARP RO reports 22 ABV Exhaust Fan is running.

PO dispatches operator to locally check the status of the breaker.

Role Play: When directed to check the status of the breaker, THEN state the following after 1 minute: the breaker for 22 ABV Exhaust Fan is closed.

RO reports that the Exhaust Filter lineup 21 HEPA (EMERG) and 23 HEPA (NORMAL) is in the proper lineup IAW S2.OP-SO.ABV-0001.

PO dispatches operator to locally check the Exhaust Fan Inlet Vanes.

TQ-AA-106-0204 Page 13 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Role Play: When directed to locally inspect 22 ABV Exhaust Fan Inlet Vanes, THEN report the following after 1-2 minutes: 2ABV14 inlet vane damper for 22 ABV Exhaust Fan is closed.

CRS determines that Exhaust flow can NOT be restored and directs starting standby fan IAW S2.OP-SO.ABV-0001.

PO starts standby 23 ABV Exhaust Fan IAW S2.OP-SO.ABV-0001.

TS evaluation #2:

CRS enters TSAS 3.7.7 Action a (14 day LCO).

Proceed to next event after Tech Specs has been evaluated or by direction from Lead Examiner.

4. 23BF19 Fails Closed (Major Transient):

Simulator Operator: Insert RT-3 at direction from Lead Examiner.

VL0448, 23BF19 fails to position.

Value = 0 Ramp = 1 min PO reports unexpected OHA alarms for:

G-15 ADFCS TRBL

TQ-AA-106-0204 Page 14 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG

G-23 21/22 SGFP SPEED DEVIATION

Console Alarm for 23 SG Program Setpoint Deviation PO reports 23BF19 is closing.

PO attempts to regain control by placing 23BF19 in Manual.

PO reports manual control of 23BF19 unsuccessful.

PO reports 23 SG NR levels are lowering and recommends Reactor Trip.

RO manualy trips the Reactor and performs immediate actions of EOP-TRIP-1.

5. Main Turbine Fails to Auto Trip AND MSLI fails to Auto actuate:

RO reports that Main Turbine failed to Auto trip.

RO reports Main Turbine failed to manually trip using Pistol Grip switch.

Simulator Operator: Ensure ET-2 is TRUE when operator depress the Turbine Trip Bezel. This will delete malfunction RP0073 and allow the turbine to trip.

RO manually trips the main turbine by depressing turbine trip bezel pushbutton. [Critical Task #1]

TQ-AA-106-0204 Page 15 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Critical Task #1 (CT-13): Manually trip the turbine before severe challenge develops to either subcriticality or integrity CFST, or transition to LOSC-1.

SAT _________ UNSAT _______

RO reports SI Auto actuated and manually backs up SI signal.

CRS enters 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

6 & 7. 21 AFW Pump Trips and Loss of 2B 4KV Vital Bus:

Simulator Operator: Ensure ET-1 is TRUE following Rx Trip. This will insert malfunction to trip 21 AFW Pump and Loss of 2B 4KV Vital Bus.

AF0181A, 21 AFW Pump trip EL0145, Loss of 2B 4KV Vital Bus CRS directs PO to throttle AFW flow to no less than 22E4 lbm/hr.

Simulator Operator: MONITOR SG NR levels. IF any SG NR levels recovers to 6-7 %, THEN insert RT-5 to trip 23 AFW Pump. This will ensure that a valid Heat Sink Red path exists prior to Step 20 in EOP-TRIP-1.

TQ-AA-106-0204 Page 16 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG PO reports 21 AFW Pump tripped and only 23 AFW Pump is running.

Simulator Operator: If directed to remove control power for 21 AFW Pump breaker then insert RT-10.

AF20D, 21 AFW breaker control power.

Location: 64 ft. Switchgear A Bus Role Play: IF directed to determine why 21 AFW Pump tripped, then after 2-3 minutes report the following: the overcurrent relay flag is up for 21 AFW Pump.

CRS and RO review immediate actions.

PO reports 2A and 2C Vital Buses are energized.

PO reports SEC loading not complete for 2A and 2B bus.

PO reports that 21 AFW Pump tripped following Rx Trip.

PO reports all available equipment started.

PO reports only 23 AFW Pumps is running.

PO reports that NOT all valves groups in Table B are in the safeguards position.

TQ-AA-106-0204 Page 17 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Examiners Note: Several SI and Feedwater Isolation valves will not be in the safeguards position due to the loss of 2B 460/230 VAC buses. All back-up valves will be in the safeguards position.

PO reports several Safety Injection and Feedwater Islolation valves not in position; but there redundant valves are in the safeguards position.

PO reports all Phase A valves are in the safeguards position.

CRS directs WCC to locally position valves to their safeguards position.

PO reports all Phase A valves are in the safeguards positions with the exception of 2CV284, but its backup valve 2CV116 is closed.

RO reports 21 and 22 CA330s are closed.

RO reports that containment pressure has remained less than 15 psig.

PO reports 2RP4 does not indicate high steam flow with low steam pressure or low-low Tavg.

PO reports MSLI was previously manually initiated.

PO reports 2B 4KV Vital bus is NOT energized.

CRS directs assistance in restoring 2B 4KV Vital Bus IAW S2.OP-AB.4KV-0002 while continuing with EOP.

TQ-AA-106-0204 Page 18 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Role Play: IF directed to restore 2B 4KV Vital Bus then state the following: the event response team will commence troubleshooting to restore 2B bus.

RO reports control room in Accident Pressurize mode.

PO reports two switchgear supply fans and one exhaust fan are running.

RO reports two CCW pumps are running and both CCW HX are in Auto.

Proceed to next event when ECCS Flow Evaluation is in progress:

RO reports expected ECCS flow for plant conditions.

8. 23 AFW Pump trips (loss of all AFW flow):

Simulator Operator: Insert RT-4 during ECCS flow evaluation steps in TRIP-1.

AF0183, 23 AFW Pump trips PO reports that 23 AFW Pump tripped.

Role Play: If requested to why 23 AFW Pump trip, then report that investigation is underway and no obvious signs why it tripped, but the trip linakge looks bent.

TQ-AA-106-0204 Page 19 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Note: RCS pressure will be low due to the MT failure to trip.

PO reports NO AFW flow PO reports no SG NR levels are > 9% (15% adverse)

PO reports total AFW flow is less than 22E4 lbm/hr.

CRS transitions to 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink.

Examiners Note: During scenario construction lowest SG WR levels was at

~28% which was sufficient to allow the crew to establish feed using main condensate.

PO reports operator action was not cause of AFW flow

<22E4 lbm/hr.

RO reports RCS pressure is > SG pressure.

RO reports RCS Thots > 350°.

CRS reads Bleed and Feed criteria. (3 WR levels < 20%

(25% Adverse))

PO closes all GB4s.

TQ-AA-106-0204 Page 20 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG RO closes all SS94s.

RO stops all RCPs.

CRS directs starting MSPI AFW pump.

Role Play: When directed to start MSPI AFW pump then after 1-2 minutes report the following: the MSPI AFW pump started but tripped on overspeed.

PO reports Condensate System is in service.

Evaluators Note: Both SGFPs tripped due to Auto SI actuation following MT failure to trip.

PO reports NO SGFPs are available (SI actuation) and MSPI pump failed to start.

RO reports SI has actuated (Auto initiated following Rx Trip)

Examiners Note: Due to the loss of 2B 460/230 VAC bus, several SI valves will not be in the safeguards position, but the back-up valves will.

PO verifies SI valve alignment IAW 2-EOP-APPX-3, SI Verification.

RO resets SI, Phase A, and Phase B isolation RO opens both CA330s

TQ-AA-106-0204 Page 21 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG RO resets all SECs and 230V control centers.

Examiners Note: FRHS-1 Step 18, Caution Note states: 21 and 23 SG should be steamed last to maximize availability of a steam supply for 23 AFW pump.

During simulator runs, 23 SG WRs levels was reading low due to 23BF19 failing closed prior to Rx trip, therefore the crew should select 22 or 24 SG to steam first.

EOP-FRHS-1 Condensate Recovery steps start here:

Crew selects only one SG for depressurization to < 575 psig.

PO reports steam dumps are available.

PO initiates MSLI on all loops except the selected SG.

PO places steam dumps in Manual.

PO adjusts steam pressure valve demand to zero.

PO places steam dumps in MS PRESS CONTROL PO adjusts steam pressure valve demand to 25%.

When RCS Tavg Low-Low is reached, then the PO depresses Bypass Tavg Pushbuttons.

TQ-AA-106-0204 Page 22 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG CRS dispatches operator to open the selected SG BF40 or BF19 valve (120 ft. elev. TGA).

Simulator Operator: Use the following REMOTES to operate the 22 or 24 SG BF40 or BF19s.

22 BF19: BF02A 24 BF19: BF04A 22 BF40: BF06A 24 BF40: BF08A Set Ramp Time = 03:00 mins Set Desired Value = 100 for Fully Open or see below:

Notify control room when selected valve is OPEN.

Examiners Note: During scenario validation using MS10s to lower SG pressures to inject with main condensate took considerable time (approx. 10 mins).

Condensate flow was established when SG pressure is around 600 psi.

PO opens the selected SG BF13.

Examiners Note: 21BF13 valve position indication will be lost due to loss of 2B 460/230 VAC bus. This valve is open.

The crew may choose 24BF13 since it has power to indication.

TQ-AA-106-0204 Page 23 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG PO reports that Release selected for selected BF22 PO opens 21 and 22 CN48 (SGFP Bypass valves).

PO closes 21 and 22 CN32 (SGFP suction valves).

Examiners Note: At this point the crew may wait at Step 18.5 of EOP-FRHS-1 until feedflow is achieved or continue on until the EOP directs you back to beginning of EOP until feed flow is achieved.

Critical Task-2 (CT-43):

Establish feedwater flow into at least one SG before Bleed and Feed is required.

SAT:_______ UNSAT:_______

Steps that are bolded and shaded are necessary to complete the critical task.

Examiners Note: The crew should verify indication of condensate flow AND SG WR level is rising when determining if Condensate Flow is established.

During validation it took approx. 6 mins to see WR rising when condensate flow was established at 5-6 %.

TQ-AA-106-0204 Page 24 of 33 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG Examiners Note: As the crew is waiting for feed flow to be established, you can expect the PZR PORVs to be cycling as the RCS heats up.

PO reports that Condensate flow is established to selected SG or CETs are lowering. [Critical Task #2]

CRS directs PO to maintain selected SG pressure to <

575 psig.

Crew reports that Bleed and Feed has NOT been initiated and transitions to procedure in effect (2-EOP-TRIP-1)

The scenario may be terminated after the crew has established condensate flow or by direction from Lead Examiner.

TQ-AA-106-0204 Page 25 of 33 B. SCENARIO REFERENCES A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.OP-IO.ZZ-0004, Power Operation F. S2.OP-AB.ROD-0003, Continuous Rod Motion G. S2.OP-AR.ZZ-0011, 2CC1 Alarm Response Procedure H. 2-EOP-TRIP-1, Reactor Trip or Safety Injection I. 2-EOP-FRHS-1, Response to Loss of Secondary Heat Sink

TQ-AA-106-0204 Page 26 of 33 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 84% RCS BORON: 843 MWe 1020 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS

Reactor Engineering directs performing power ascensrion to 100% using control rods, main turbine load control, and/or dilution.

MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

Commence power ascension to 100% at 10%/hour IAW S2.OP-IO.ZZ-0004, Power Operation following return to service of 23 Condensate Pump.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

SECONDARY:

23 Condensate Pump returned from maintenance

Blowdown 35K per loop to 23 condenser / flashtank

Polisher in service RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

None

TQ-AA-106-0204 Page 27 of 33 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in TRAIN Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked Training Use Only and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

TQ-AA-106-0204 Revision 2 Page 28 of 33 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individuals incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

TQ-AA-106-0204 Revision 2 Page 29 of 33 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST SCENARIO IDENTIFIER: 19-01 NRC Scenario #5 REVIEWER: R. Chan Initials Qualitative Attributes RC 1. The scenario has clearly stated objectives in the scenario.

RC 2. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

RC 3. The scenario consists mostly of related events.

RC 4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point RC 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

RC 6. The events are valid with regard to physics and thermodynamics.

RC 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

RC 8. The simulator modeling is not altered.

RC 9. All crew competencies can be evaluated.

RC 10. The scenario has been validated.

NA 11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

RC 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

TQ-AA-106-0204 Revision 2 Page 30 of 33 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 5 Target Quantitative Attributes per Scenario (NRC Form ES-D-1)

Initial Conditions: IC-210: 85% power, EOL; 21 Charging Pump I/S. The following equipment is out of service:

23 Charging Pump C/T for maintenance.

Turnover: 23 Condensate Pump just placed in service following maintenance and commence power ascension to 100% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using dilution, control rods and turbine load control.

Critical Tasks:

1. Manually trip the turbine (see WOG CT-13)

2. Establish condensate feed flow to SGs (see WOG CT-43)

Event Malf. No. Event Type* Event No. Description 1 N/A ALL (R) Commence power ascension to 100% at 10% per hour IAW IOP-4 2 TU0055 ALL (C, TS) 2PT-505 turbine inlet pressure channel fails low.

BOP (C) 3 ANCGA072 22 ABV Exhaust Fan discharge damper fails close (low air flow)

CRS (C,TS) 4 VL0448 ALL (M) 23BF19 fails closed RP0073 ATC (I)

Main Turbine fails to Auto trip 5 RP0279A CRS (I)

Auto MSLI fails to actuate RP0279B ATC (I) 2B 4KV Vital Bus de-energizes on bus differential protection (loss of 6 EL0145 CRS (I) 22 MDAFW Pump)

BOP (C) 7 AF0181A 21 AFW Pump trips following Rx Trip CRS (C) 23 AFW Pump trips on overspeed (loss of all AFW flow) during EOP-8 AF0183 ALL (C)

TRIP-1 ABs IOP-4 AB.ROD-3 AR.ZZ-11 EOPs TRIP-1 FRHS-1 w/condensate recovery

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

TQ-AA-106-0204 Revision 2 Page 31 of 33 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Scenario No.: 5 Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes Event No.

1. Total malfunctions (5-8) 7 2-8

2. Malfunctions after EOP entry (1-2) 4 5,6,7,8

3. Abnormal events (2-4) 2 2,3

4. Major transients (1-2) 1 4

5. EOPs entered/requiring substantive actions (1-2) 1 TRIP-1

6. Entry into a contingency EOP with substantive actions ( 1 per 1 FRHS-1 scenario set)

7. Preidentified critical tasks (2) 2 CT-13, CT-43

8. Tech Specs exercised ( 2) 2 2,3

TQ-AA-106-0204 Page 32 of 33 ATTACHMENT 5 ESG CRITICAL TASKS 19-01 NRC Scenario 5 CT-1 (CT-13):

Critical Task: Manually trip the turbine before a severe challenge develops to either subcriticality or integrity CSF or transition to LOSC-1.

Basis: See WOG Rev. 2 CT-2 (CT-43):

Critical Task: Establish feedwater flow into at least one SG before Bleed and Feed is required.

Basis: See WOG Rev. 2

TQ-AA-106-0204 Revision 2 Page 33 of 33 ATTACHMENT 6 ESG-PSA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg Y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed

v t e Letter Sequence Draft Other
CAC:000500, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML20055D883, ML20055E009, ML20057E559, ML20057E560, ML20087G852, ML20087H514, ML20184A247, ML20184A248, ML20240A318, ML20240A322, ML20254A128, ML20254A272, ML20268A322, ML20268B437, ML20268C197, ML20274A136, ML20279A331, ML20297A306, ML20300A556, ML20301A632, ML20302A234, ML20302A235, ML20303A011, ML20303A016, ML20307A010, ML20307A019, ML20321A279, ML20322A350, ML20323A018, ML20325A031, ML20328A162, ML20329A432, ML20329A442, ML20350B716, ML20350B723, ML20350B739, ML20350B785, ML21012A270, ML21025A073, ML21025A143, ML21025A403, ML21025A405, ML21025A414, ML21040A471, ML21040A483, ML21043A207, ML21050A084, ML21050A119, ML21050A227, ML21056A220... further results
MONTHYEAR2020-03-12 [Table View]

ML20296A430

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SUMMARY

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