ML12353A473

SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP

(* Denotes a Critical Step) EVAl (Required for UNSAT

NO. STANDARD S/U evaluation) 3.0 Steps identified with dollar signs ($) are Reads and initials step.

those items required to meet Technical Specification acceptance criteria. Such steps, if not satisfactorily completed, may have reportability requirements and shall be brought to the immediate attention of the SM/CRS.

5.1.1 COMPLETE Attachment 2 per the Completes Attachment 2 with the below data.

following:

RECORD Data .

RECORD Test Results by initialing SAT or UNSAT column using the stated Acceptance Criteria.

AU. 2 RWST Level Records RWST level with channel for which calibration data was obtained RWST levels are:

CH I: 41.4 CH II: 41.4 CH III: 41.4 CHIV: 41.5 Initials SAT for RWST Level and inserts date.

I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 40f9

OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Att.2 RWSTTemp Checks P-250 computer point T0650A and enters 70"F. Initials SAT for RWST Temp and inserts date.

Att.2 RWSTConc Refers to initial conditions for RWST boron concentration and enters 2350 ppm. Initials SAT for RWST boron concentration and inserts date.

Att. 2 21 BAST Vol AND/OR 22 BAST Vol Records 21 and 22 BAST level indicated on control console from 2L11 06 and 2L11 02 respectively as 2L1106 - 49.5%

2L1102 - 49.5%

Uses Tech Spec 3.1.2.6.a. 3.1.2.6.b, and Figure 3.1 and determines 21 BAST Vol AND/OR 22 BAST Vol is SAT. Initials SAT for BAST volume and inserts date.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ________________

SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

AU. 2 21 BAST Temp AND/OR 22 BAST Temp Records 21 and 22 BAST temp indicated on control console from 2TI107 and 2TI103 respectively as:

2TI107 - 98.2 2TI103 - 97.1 Initials SAT for 21 BAST Temp AND/OR 22 BAST Temp and inserts date.

Refers to initial conditions for BAST boron

Att. 2 21 BAST Conc AND/OR 22 BAST Cone concentrations and enters 6610 ppm for 21 BAST and 6610 ppm for 22 BAST.

Uses Tech Spec 3.1.2.6.a, 3.1.2.6.b, and Figure 3.1-2 and determines 21 and 22 BAST boron conc is SAT. Initials and inserts date.

--- -- --~

--- --- ---- ........... -.--~- ........ -.-~- ............- . -

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 9

OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation) 5.3.1 This surveillance is considered satisfactory when Attachments 2 and 3 Initials step 5.3.1 (as applicable) are complete with components listed meeting Acceptance Criteria stated in each Attachment.

OR 5.3.2 This surveillance is unsatisfactory. N/A's step 5.3.2 A. INITIATE Notification(s) to correct the unsatisfactory condition.

B. RECORD Notification number(s) and reason for unsatisfactory completion on Attachment 4 in the Comments Section.

5.4.1 COMPLETE Attachment 4, Sections 1.0 Completes Attachment 4, Sections 1.0 and and 2.0, AND FORWARD this procedure 2.0, and returns procedure to JPM Evaluator.

to the SM/CRS for review.

JPM is complete when procedure is returned to evaluator .

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 9

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 (KIA) 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 verifiBd 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/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ _. Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 9

INITIAL CONDITIONS:

Salem Unit 2 is at 100% power.

21 BAT pump developed a leak that went unnoticed until the cross-connected BASTs reached their low level alarm setpoint.

Chemistry reported current RWST and BAST boron concentrations last shift. No additions to those tanks have occurred since that report.

21 BAST - 6610 ppm

22 BAST - 6610 ppm

RWST - 2350 ppm

Off Normal and Off-Normal Tagged list review has been performed SAT.

INITIATING CUE:

You are the Reactor Operator. Perform S2.0P-ST.CVC-0010, Borated Water Sources Data.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE (ALARA)

TASK: Perform Stay Time Calculation for Emergency Condition.

TASK NUMBER: N1200100104 JPM NUMBER: 11-01 ILOT RO A3 ALTERNATE PATH: I I KIA NUMBER: 2.3.4

~

IMPORTANCE FACTOR: 3.2 APPLICABILITY: --=R::-::O::--- SRO EoD RO[Z] STAD SROD EVALUATION SETTING/METHOD: Classroom

REFERENCES:

Radiological Survey Maps, RP-AA-203, NC.EP-EP.ZZ-0304 TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-7-12 Instructor Date: 8-24-12 Validated By: Brennan / Mulford 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: D SAT D UNSAT REASON. IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 4

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:.

DATE:

SYSTEM: ADMINISTRATIVE (ALARA)

TASK: Perform Stay Time Calculation for Emergency Condition.

TASK NUMBER: N1200100104 INITIAL CONDITIONS:

1. Unit 1 experienced Rx trip with a small RCS leak from 100% power.

2. The Rx failed to automatically trip on a valid trip demand, and was tripped successfully with the Rx trip handle.

3. Salem is currently in an Alert.

4. Your TEDE dose for the year is 1925 mrem.

INITIATING CUE:

You have been directed to perform a detailed inspection of 22 RHR pump room prior to starting the pump. You will NOT be going into the 22 RHR HX area. Your job is estimated to take 2 hours0.0833 days 0.0119 weeks 0.00274 months to complete.

Using the correct survey map, and conservatively using the HIGHEST dose rate in the room for your ENTIRE exposure, determine:

1. Can you complete the job without exceeding your current dose authorization

2. What would be your new TEDE dose for the year after performing the job (or as much as possible) WITHOUT exceeding your current dose authorization?

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:

Determines:

1. YES job can be performed

2. Calculates new TEDE dose of 2025 mrem.

Page 2 of 4

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: ADMINISTRATIVE (ALARA)

TASK: Determine Radiological Conditions For Personnel Exposure STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD evaluation)

S/U Provide the attached survey maps of 11 RHR and 12 RHR, 21 and 22 RHR, and Selects the Survey Map S1 55 General area. Also have blank "S2 AUX 045' 22 RHR ROOMS" copies of RP-M-203, Exposure Control 1 Map # 21045Z2 and Authorization and NC.EP-EP.ZZ 0304, Operational Support Center (OSC)

Radiation Protection Response if asked for.

START TIME:

If asked, provide NC.EP-EPZZ-0304, Note: Contains guidance for automatic OSC Radiation Protection Response. increase in allowed dose to 4500 mrem.

(Section 5.0 Note.)

I Determines dose limit is automatically raised to 4500 mrem upon the declaration of an ALERT or higher Emergency.

2 Determine highest dose rate in room. Per the survey map, squares are dose

rates in mrem/hr, and circles are smear locations. The highest square is located under the words "Vertical Elbow" of the map and indicates 50 mrem/hr.

Page 3 of6

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: ADMINISTRATIVE (ALARA)

TASK: Determine Radiological Conditions For Personnel Exposure STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 3 Calculate TEDE dose for year Subtracts year to date TEDE dose from

Emergency Dose limit of 4,500 mrem, and gets 2575 mrem. Determines 2 hours0.0833 days 0.0119 weeks 0.00274 months of work will result in 100 mrem dose, and new TEDE dose is 2025 mrem, which does NOT exceed to 4,500 mrem authorized in an Emergency Terminate JPM when candidate has returned paperwork.

4 STOP TIME:

Page 4 of6

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 (KIA) 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/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

INITIAL CONDITIONS:

Page 50f6

1. Unit 1 experienced Rx trip with a small ReS leak from 100% power.

2. The Rx failed to automatically trip on a valid trip demand, and was tripped successfully with the Rx trip handle.

3. Salem is currently in an Alert.

4. Your TEDE dose for the year is 1925 mrem.

INITIATING CUE:

You have been directed to perform a detailed inspection of 22 RHR pump room prior to starting the pump. You will NOT be going into the 22 RHR HX area. Your job is estimated to take 2 hours0.0833 days 0.0119 weeks 0.00274 months to complete.

Using the correct survey map, and conservatively using the HIGHEST dose rate in the room for your ENTIRE exposure, determine:

1. Can you complete the job without exceeding your current dose authorization

2. What would be your new TEDE dose for the year after performing the job (or as much as possible) WITHOUT exceeding your current dose authorization?

1.

2.

Page 6 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance to demonstrate Operability of 21 CFCU TASK NUMBER: N1230300302 JPM NUMBER: 11-01 NRC SRO Admin A1-1 ALTERNATE PATH: I X I ~ANUMBER: ______-=2~.1~.2~5______~

IMPORTANCE FACTOR: 4.2

--=-::--

APPLICABILITY: RO SRO EOD ROO STAD SROm EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S2.0P-ST.CBV-0003, Rev. 17 (checked 8-14-12)

TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME: 12 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-14-12 Instructor Validated By: A Crampton Date: 9-10-12 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

{PRIVATE }SYSTEM: Administrative TASK: Review a completed surveillance to demonstrate Operability of 21 CFCU TASK NUMBER: N1230300302 INITIAL CONDITIONS: 21 CFCU was returned from corrective maintenance. S2.0P-ST.CBV-0003, Containment Systems - Containment Cooling was performed for the Operability Retest.

INITIATING CUE:

You have been directed to review the surveillance for completeness and accuracy lAW Step 5.3.4.

Document any discrepancies that you identify and/or actions that you would take on Attachment 8, Section 1.0, Comments.

{PRIVATE }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. Identify that the Minimum Flow Rate recorded on Attachment 1, page 1 of 1, Section 3.0, for 91 psid is incorrectly recorded as 1638. Identify the correct Minimum Flow Rate should be 1683.

2. Identify that the actual Cooling Water Flow Rate (1675) is below the Minimum Flow Rate required as shown on Attachment 1 and Exhibit 1, and the surveillance is UNSAT vs SAT.

Page 2 of5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:._ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Review a completed surveillance to demonstrate Operability of 21 CFCU

STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Provide completed S2.0P-ST.CBV-0003 surveillance.

Reviews procedure.

Identifies that the Minimum Flow Rate recorded

on Attachment 1, page 1 of 1, Section 3.0, for 91 psid is incorrectly recorded as 1638. (This was due to operator performing ST rounding down as opposed to rounding up lAW P&L 3.4.)

Identifies correct value for Minimum Flow Required as 1683.

Cue: IF candidate only determines flow is wrong, THEN ask candidate to determine

correct flow.

Identifies that the actual Cooling Water Flow Rate of 1675 gpm is below the Minimum Flow Rate of 1683 as shown on Exhibit 1 and the ST is UNSAT.

When candidate turns in JPM, ensure they have provided correct flow as per Cue above, then state JPM is complete.

---~- ---- ---

Page 3 of5 PSEG Restricted - Possession Requires Specific Pennission from Nuclear Training

. OPERATOR TRAINING PROGRAM{PRIVATE}

JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 4 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 (KIA) 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 ..IPM:

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 ..IPM cover page.

SME/lnstructor:_ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

Page 4 of5 PSEG Restricted Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

21 CFCU was returned from corrective maintenance. S2.0P-ST.CBV-0003, Containment Systems - Containment Cooling was performed for the Operability Retest.

INITIATING CUE:

You have been directed to review the surveillance for completeness and accuracy lAW Step 5.3.4.

Document any discrepancies that you identify and/or actions that you would take on , Section 1.0, Comments.

Page 5 of5 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Direct Actions for Spent Fuel Movement (Determine work which would require suspension of Fuel Movement)

TASK NUMBER: N1120760102 JPM NUMBER: 11-01 NRC SRO Admin A1-2 ALTERNATE PATH: KIA NUMBER: 2.1.42

~~------~

IMPORTANCE FACTOR: 3.4 APPLICABILITY:

RO SRO EOD ROO STAD SROm EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S2.0P-IO.ZZ-0010, Rev. 31 , S2.0P-SO.CH-0001 Rev 30, S2.0P-SO.SW-0005 Rev41, S2.0P-SO.DG-0005, Rev.6 (all checked 8-14-12) Salem Tech Specs TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8*14*12 Instructor Validated By: A Crampton Date: 9*10*12 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

I EVALUATOR'S SIGNATURE: DATE:

Page 1 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

{PRIVATE Administrative

}SYSTEM:

TASK: Direct Actions for Spent Fuel Movement (Determine work which would require suspension of Fuel Movement)

TASK NUMBER: N1120760102 INITIAL Salem Unit 2 is operating at 99% power, coasting down into a refueling outage CONDITIONS: which will start in 2 weeks.

Irradiated fuel movement is in progress in the Spent Fuel Pool lAW S2.0P-IO.ZZ 0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours0.333 days 0.0476 weeks 0.011 months , at which time it will terminate.

The unit has no active Tech Spec LCOs.

The current time is 0800.

INITIATING CUE:

You have been directed to review the upcoming Unit 2 work for the shift and determine which activities would require suspension of fuel movement before that activity could be performed.

Work scheduled for today and expected duration 0900- 22 SW pump packing replacement (48 hours2 days 0.286 weeks 0.0658 months ) 1000- 2A EDG Monthly surveillance run (2 hours0.0833 days 0.0119 weeks 0.00274 months ) 1300- 21 Chiller compressor oil change (8 hours0.333 days 0.0476 weeks 0.011 months ) 1400- Delivery of New Fuel into the Fuel Handling Building for upcoming refueling outage (6 hours0.25 days 0.0357 weeks 0.00822 months )

{PRIVATE }Successful Completion Criteria:

1. All critical steps completed

2. AU 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. Determination that 22 SW pump work, 2A EDG surveillance, and 21 Chiller work do NOT require suspension of fuel movment.

2. Determination that New Fuel delivery DOES required suspension of fuel movement.

Page 2 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine work which would require suspension of Fuel Movement)

STEP STEP STANDARD EVAL COMMENTS NO.

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

Provide marked up copy of S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations. All other procedures are located in the Salem LORT classroom, where this JPM should be administered one at a time.

Notes:

TSAS 3.8.1.2 applies during Modes 5 and 6 and during movement of irradiated fuel, and only requires one EDG.

Only one FHB exhaust fan is required to be backed by an operable EDG (IOP-10 page 15)

Operable SFP pumps only need one of them backed by operable EDG. (IOP-10 page 15)

Page 3 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine work which would require suspension of Fuel Movement)

STEP STEP STANDARD EVAL COMMENTS NO.

Denotes a Critical Step StU (Required for UNSAT evaluation)

Notes:

TSAS 3.7.10 allows a chiller to be taken out if movement of irradiated fuel is already on going, and gives 14 days to restore it. 3.0.4 does NOT apply.

Two SW pumps are required to be operable, one of which is EDG backed. (IOP-10 page 16.) Of the 5 remaining SW pumps, 4 are powered from Band C vital and their EDGs remain operable. Service Water Tech Specs will not be entered for a single SW pump being inoperable. !

Page 4 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine work which would require suspension of Fuel Movement)

STEP STEP STANDARD EVAL COMMENTS NO.

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

Determines that:

22 SW pump does NOT require suspension of

fuel movement.

2A EDG surveillance does NOT require

suspension of fuel movement.

21 Chiller oil replacement does NOT require suspension of fuel movement

New Fuel delivery DOES require suspension of fuel movement (based on requirement that the Truck Bay door to the Fuel Handling building must remain closed, page 17 of 33)

Evaluator ensure tear off sheet has candidates name and status for each of the four work activities.

Additional information: TSAS 3.7.10 requires 3 Operable Chillers. The ACTIONS associated with having one chiller inoperable are found on page 3/4 7-29 under Modes 5 and 6 or during movement of irradiated fuel assemblies. The ACTION requires you to do: a.1 and a.2 or take action 3, which is suspend core alts and movement of irradiated fuel. Action a.1 would be performed, and a.2 states the chiller has 14 days to be returned to operable before the action of a.3 is required. Step 3.10 of S2.0P-IO.ZZ-0010 Spent Fuel Pool Manipulations, says to refer to TSAS 3.7.10 for required actions if a chiller is inoperable.

Page 50f7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

Name:

OPERATOR TRAINING PROGRAM{PRIVATE}

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 bedow.

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

_______ 2. Knowledge and Abilities (KIA) 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 ~IPM.

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

SMEllnstructor:__________________ Date: _______

SMEllnstructor: Date: ----------

SMEllnstructor: Date: ____________

Page 6 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

Name:

INITIAL CONDITIONS:

Salem Unit 2 is operating at 99% power, coasting down into a refueling outage which will start in 2 weeks.

Irradiated fuel movement is in progress in the Spent Fuel Pool lAW S2.0P-IO.zZ-0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours0.333 days 0.0476 weeks 0.011 months , at which time it will terminate.

The unit has no active Tech Spec LCOs.

The current time is 0800.

INITIATING CUE:

You have been directed to review the upcoming Unit 2 work for the shift and determine which activities would require suspension of fuel movement before that activity could be performed.

Work scheduled for today and expected duration 0900- 22 SW pump packing replacement (48 hours2 days 0.286 weeks 0.0658 months ) 1000- 2A EDG Monthly surveillance run (2 hours0.0833 days 0.0119 weeks 0.00274 months ) 1300- 21 Chiller compressor oil change (8 hours0.333 days 0.0476 weeks 0.011 months ) 1400- Delivery of New Fuel into the Fuel Handling Building for upcoming refueling outage (6 hours0.25 days 0.0357 weeks 0.00822 months )

Page 7 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review an OTSC to an Implementing Procedure TASK NUMBER: N1230020302 JPM NUMBER: 11-01 NRC SRO Admin A2 ALTERNATE PATH: I X I KIA NUMBER: 2.2.6

~

IMPORTANCE FACTOR: 3.6 APPLICABILITY:

- -RO--- SRO EOD ROO STAD SROm EVALUATION SETTING/METHOD: Classroom AD-AA-101-101, Rev. 4, PSEG Implementing Procedure On The Spot Change

REFERENCES:

(OTSC) Process TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME: 15 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-14-12 Instructor Validated By: A Crampton Date: 9-10-12 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: D SAT D UNSAT REASON,IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted Possession Requires Specific Permission from Nuclear Training Page 1 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

{PRIVATE }SYSTEM: Administrative TASK: Review an OTSC to an Implementing Procedure TASK NUMBER: N1230020302 INITIAL CONDITIONS: Operators are performing S 1.OP-PT. SW -0101, Differential Pressure Test of Turbine Area SW Stop Valves 11SW20, 13SW20, and 1SW26. The operator in the field identified an incorrect connection point for installation of a pressure instrument.

An OTSC has been initiated to allow the performance test to continue with the proper pressure test connection identified.

The OTSC Initiator has verified the correct revision (Rev. 6), and determined there are no other OTSCs associated with this procedure.

INITIATING CUE: As the operators Supervisor, review the proposed OTSC change. Determine if an OTSC is warranted for the condition. If so, review OTSC for completeness and accuracy. Note any problems, deficiencies, or comments on the OTSC form. If an OTSC is not warranted for this condition, inform the evaluator of this.

{PRIVATE }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. Identify that the OTSC process applies to this situation.

2. Identify the incorrect OTSC # during review of the OTSC.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Review an OTSC to an Implementing Procedure

STEP STEP STANDARD EVAL COMMENTS I NO.

Denotes a Critical Step StU (Required for UNSAT evaluation) I j

NOTE TO EVALUATOR: IF the candidate asks for drawings or other procedures with the intent of technically verifying the Component 10's, THEN cue candidate that the technical verification of the component IDs has been performed and verified by 2 other SROs.

Candidate reviews OTSC Provide OTSC Form F1, and pages 6,10,15 for applicability, 16,18-20 of S1.0P-PT.SW-0101.

completeness, and When asked, provide a copy of AO-AA-101 accuracy. 101, PSEG Implementing Procedure On The Spot Change (OTSC) Process.

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OPERATOR TRAINING PROGRAM NAME:,_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Review an OTSC to an Implementing Procedure

STEP STEP STANDARD EVAL COMMENTS NO.

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

Candidate reviews Form-1 and OTSC process procedure.

The following should be noted:

- The OTSC process is appropriate for this situation. The procedure steps cannot be performed as written because the pressure test connection is incorrect.

The OTSC No. on Form F1 is incorrect. As per the OTSC procedure, the sequential number is the current revision number followed by the next available sequential letter, and should be 6A, not 7A.

Candidate identifies and When candidate records discrepancies, records discrepancies. terminate JPM.

I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 6

OPERATOR TRAINING PROGRAM{PRIVATE}

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 (KIA) 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/lnstructor:______________ Date: _ _ _ _ __

SME/lnstructor:______________ Date: _ _ _ _ __

SME/lnstructor:______________ Date: - - - - - -

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INITIAL CONDITIONS:

Operators are performing S1.0P-PT.SW-01 01, Differential Pressure Test of Turbine Area SW Stop Valves 11 SW20, 13SW20, and 1SW26. The operator in the field identified an incorrect connection point for installation of a pressure instrument.

An OTSe has been initiated to allow the performance test to continue with the proper pressure test connection identified.

The OTSe Initiator has verified the correct revision (Rev. 6), and determined there are no other OTSes associated with this procedure.

INITIATING CUE:

As the operators Supervisor, review the proposed OTSe change. Determine if an OTSe is warranted for the condition. If so, review OTSe for completeness and accuracy. Note any problems, deficiencies, or comments on the OTSe form. If an OTSe is not warranted for this condition, inform the evaluator of this.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Determine required actions upon Radioactive Effluent Monitor failure TASK NUMBER: N1200010301 JPM NUMBER: 11-01 NRC SRO Admin A3 ALTERNATE PATH: KIA NUMBER: 2.3.11

~

IMPORTANCE FACTOR: _ _ _ _ 4.3 APPLICABI LlTY: RO SRO EoD ROD STAD SROW EVALUATION SETTING/METHOD: Classroom Salem ODCM, Salem Tech Specs, S1.0P-SO.WL-0001, Release of 11 evcs Monitor Tank, S1.0P-SO.WG-0011, Release of 14 GOT, S1.0P-SO.CBV-0002

REFERENCES:

Containment Pressure-Vacuum Relief System TOOLS AND EQUIPMENT:

VALIDATED ..IPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-15-12 Instructor Validated By: A Crampton Date: 9-10-12 Approved By: i1J:;;;l~/;f.~J

.[.~ining Depa~~nt Date: C([{ ~"

Approved By: 1<."\fY.\M....!6'1 '1.1L.t4>.uc.J '\ Date: qf')~

dperatilms b~paP1:ment ~

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Ad ministrative TASK: Determine required actions upon Radioactive Effluent Monitor failure TASK NUMBER: N1200010301 INITIAL CONDITIONS: Unit 1 is operating at 100% power.

Radiation Monitor 1R1.2A- Containment Noble Gas, failed its Source Check when preparing to perform a normal Containment Pressure Relief lAW S1.0P-SO.CBV-000.2, Containment Pressure-Vacuum Relief System Operation.

11 CVCS Monitor Tank is ready for release.

14 Gas Decay Tank (GOT) is ready for release.

INITIATING CUE: Prior to initiating the Containment Pressure Relief, Rad Monitor 1R41 OJ Plant Vent Release Rate, indication fails high, and is confirmed as an instrument failure.

Determine the requirements, if any, which must be met to initiate:

Containment Pressure Relief

11 CVCS Monitor Tank release

14 GOT release List all compensatory actions, including times they must occur for each release to be initiated. If a release is prohibited from being initiated in this conditions then state ttlat. If no additional restrictions apply to any of the releases then state that.

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. Determines additional compensatory measures apply for the Waste Gas Release and the Containment Pressure Relief per key.

2. Determines no additional compensatory actions required for Liquid Release.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure

STEP STEP STANDARD EVAL COMMENTS NO.

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

Note: There is no controlled copy of the Salem aDCM in the classroom. Ensure the Simulator copy is placed in II classroom prior to starting JPM, or provide a copy to each candidate.

Evaluate the effect the combined failure of the 1R12A and the 1R41D have upon the initiation of Containment Pressure Relief, Waste Liquid Release, and Gaseous Releases.

r-------- -----

Waste Gas Release Determines aDCM 3.3.3.9 applies to Gaseous Effluent which directs actions per Table 3.3-13.

r---- ----------- ---- ------

Determines Table 3.3-1 Instrument #1, Waste Gas Holdup System is applicable, which requires (1) 1R41A ~ D. Action 31 applies.

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OPERATOR TRAINING PROGRAM NAME:,____________________

JOB PERFORMANCE MEASURE DATE:,____________________

System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure STEP STEP STANDARD EVAL COMMENTS NO.

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

Action 31 states that with less than the minimum required Operable channels, the contents of the tank may be released provided that prior to the initiating the release:

a. At least two independent samples of the tanks contents are analyzed; and

b. At least two technically qualified memebers of the facility Staff independently verify the release rate calculations and discharge valving lineup; otherwise suspend release of radioactive effluents via this pathway.

Additionally, S1.0P-SO. WG-0011, Discharge of 14 Gas Decay tank to Plant Vent, Section 3.0, Dose Estimates and Approval, Step

3.4.C (on page 18) states ... " Grab samples are being obtained at least once per 8 hours0.333 days 0.0476 weeks 0.011 months AND analyzed for gaseous principal gamma emitters within 24 hours1 days 0.143 weeks 0.0329 months

Determines that there is no restriction on performing Liquid Releases.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE::_______________

System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure

STEP STEP STANDARD EVAL COMMENTS NO.

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

Containment Pressure Relief Determines that Precaution and Limitation 2.3 of S1.0P-SO.CBV-0001 directs operator to notify Chemistry to comply with the contingency actions associated with the ODCM prior to performing a Containment Pressure I Relief.

Determines Table 3.3-13, Instrument #3, applies to the Containment Pressure Relief.

With both channels (1R41A~ 0 OR 1R12A) inoperable, Action 37 applies.

Action 37 states that with less than the minimum required Operable channels, Containment Pressure Reliefs may be performed provided that prior to initiating the release:

a. At least two independent samples of

the tanks contents are analyzed, and

b. At least two technically qualified

members of the facility Staff independently verify the release rate calculations, otherwise suspend release of radioactive effluents via this pathway.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Determine required actions upon Radioactive Effluent Monitor failure STEP STEP STANDARD EVAL COMMENTS NO.

Denotes a Critical Step StU (Required for UNSAT evaluation) ,

Terminate JPM when all paperwork is handed in.

Note to Evaluator: JPM modeled after Pilgrim Jan 2011 NRC Exam SRO Admin JPM RC.

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

~ 1. Task description and number, 'JPM description and number are identified.

_.!r:..A..---=-_2. Knowledge and Abilities (KIA) references are included.

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

_1- ___ 4. Initial setup conditions are identified.

_L- ___ 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 currert revision of that procedure: Procedure Rev. ~ Date "[(I ~/O c;...

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 ...IPM 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/lnstructor:~;.4;,..a~~--b-<~~~==-_ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

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INITIAL CONDITIONS:

Unit 1 is operating at 100% power, Radiation Monitor 1R12A- Containment Noble Gas, failed its Source Check when preparing to perform a normal Containment Pressure Relief lAW S1.0P-SO.CBV-0002, Containment Pressure-Vacuum Relief System Operation.

11 CVCS Monitor Tank is ready for release.

14 Gas Decay Tank (GOT) is ready for releaSE!.

INITIATING CUE:

Prior to initiating the Containment Pressure Relief, Rad Monitor 1R41 0, Plant Vent Release Rate, indication fails high, and is confirmed as an instrument failure.

Determine the requirements, if any, which must be met to initiate:

Containment Pressure Relief

11 CVCS Monitor Tank release

14 GOT release List all compensatory actions, including times they must occur for each release to be initiated.

If a release is prohibited from being initiated in this conditions then state that. If no additional restrictions apply to any of the releases then state that.

PSEG Restricted - Possession Requires Spedfic Permission from Nuclear Training Page 8 of 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

TASK NUMBER: 1240020502 JPM NUMBER: 11-01 NRC SRO Admin A4-1 (ESG-1)

ALTERNATE PATH: L-I_~I ~ANUMBER: ______-=2~.4~.4~1______~

IMPORTANCE FACTOR: 4.6 APPLICABILITY: ----=R"""O-- SRO EoD RoD STAD SROm EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 08-21-12 Instructor Validated By: Boos Date: 08-23-12 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1 )

TASK NUMBER: 1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event. complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

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. Complete the ICMF with the classification of ALERT under EAL RB2.L and provide it to the Primary Communicator within 15 minutes of Start Time.

2. Complete the ICMF with the classification of SAE under EAL RB2.L AND CBS.L and provide it to the Primary Communicator within 15 minutes of Start Time. This is the classification if the cavitating charging pump is not recognized and it fails.

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OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Note: This ECG call can either be an ALERT or a SAE based on whether or not the crew tripped the cavitating charging pump.

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

START TIME:

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.

duties I

Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG Classifies the event Determines the classification of the event and refers to ECG Attachment 2 (Alert)

OR refers to Att. 3 (SAE)

Att2 CALL communicators to the Control Pages communicators and initials as SM A.1 Room Cue: I am the Primary Communicator PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 10

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

'* NO. STANDARD S/U evaluation)

Att 2 IF a security Event is in progress, THEN Determines Security Event is not in A.2 IMPLEMENT the prompt actions of progress.

NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to the classification.

AU 2 As time allows, OBTAIN Classification Cue: No independent review will be A.3 Independent Verification (ensure verifier performed.

understands the EAL assessment clock is running);

STA or designee performs Independent Verification for SM.

SM or designee performs Independent Verification for EDO.

EDO or designee performs Independent Verification for ERM.

AU 2 While classification verification is in Begins filling out ICMF.

A.4 progress and if time allows, COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment)

Att 2 After classification verification and/or Before 15 minute assessment clock A.5 before 15 minute EAL assessment clock expires, declares ALERT (or SAE if expires, DECLARE and ALERT (or SAE appropriate based on ESG performance) if appropriate based on ESG at Salem Unit(s) performance) at Salem Unit(s)___

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stU evaluation)

Att 2 ACTIVATE "ERO Emergency Callout" Cue: Activation of ERO Emergency B.1 per posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (Commitment EP96-003)

Att 2 COMPLETE/APPROVE the (ICMF) (last B.2 page of this attachment).

Fills out Section II of ICMF:

EAL#(s): RB2.L (or RB2.L AND CB5.L)

Description of Event:

Loss of the Reactor Coolant System Barrier OR Loss of the Reactor Coolant System Barrier, Loss of the Containment Barrier.

Note: Description of Event is found in EAL Description Table Fills out Section III:

Checks for a Radiological Release is in progress.

Fills out Section IV:

Retrieves wind speed and direction data from SPDS Initials for am~roval to transmit

~--

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Att 2 IF time allows, OBTAIN an accuracy peer Cue: Peer check is not provided.

B.3 check of the completed ICMF.

Att 2 PROVIDE the ICMF to the Primary Provides ICMF to Primary Communicator B.4 Communicator and DIRECT the within 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME:

Attachment 6.

Terminate JPM when ICMF is given to the Evaluator.

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EP-SA-lll-F2 ATT2 Pg 3 of3 INITIAL CONTACT MESSAGE FORM

1. THIS IS _ ..._ _ _ _ _ _ _ _ _ _, COMMUNICATOR IN THE [(/ CONTROL ROOM (NAME) TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) NO. _.....________.

II.

[{/ THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT TIME ON _ _ _TODAYS DATE .

(Time-24 HR CLOCK) (DATE)

EAL #(s) RB2.L DESCRIPTION OF EVENT: Loss of the Reactor Coolant System Barrier III.

NOTE:

Radiological Release is defined as: Plant Effluent > F,~deral Limit of 2.42E+05 uCi/sec Noble Gas or 2.1E+Ol uCi/sec 1-131.

[{/ NO RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release o THERE A RADIOLOGICAL RELEASE IN PROGRESS definition IV. [{/ 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: _ _ _ _ _ __

(From MET Computer ISPDS) (DEGREES) (MPH)

V. [{/ NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME Candidates Initial EC Initials (Approval to Transmit ICMF)

SGS Rev. 00 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 10

EP~SA-l11~F3 ATT3 Pg 3 of3 INITIAL CONTACT MESSAGE FORM

1. THIS IS --

, COMMUNICATOR IN THE iii CONTROL ROOM (NAME) oTSC EOF AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) NO. _ . __- __.. ~_ _.

u.

iii THIS IS NOTIFICATION OF A SITE AREA EMERGENCY WHICH WAS DECLARED AT TIME ON _ _ _TODAYS DATE (Time-24 HR CLOCK) (DATE)

EAL #(s) RB2.L AND CBS.L DESCRIPTION OF EVENT: Loss of the Reactor Coolant System Barrier, Loss of the Containment III.

~-------------------------------------------------------------~

NOTE:

Radiological ReJease is defined as: Plant Effluent> Federal Limit of2.42E+05 uCi/sec Noble Gas or 2.1E+01 uCi/sec 1-131.

o NO RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release D THERE IS A RADIOLOGICAL RELEASE IN PROGRESS definition IV. iii 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: ._~_. . _______

(From MET Computer ISPDS) (DEGREES) (MPH)

V. iii NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME Candidates Initial EC Initials (Approval to Transmit ICMF)

SGS Rev. 01 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 10

TQ-AA-106-0303 Revision 4 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 (KIA) 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 ~IPM 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.

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEllnstructor: Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 10

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

TASK NUMBER: 1240020502 JPM NUMBER: 11-01 NRC SRO Admin A4-2 (ESG-2)

ALTERNATE PATH: 1

...._ .....1 KIA NUMBER: 2.4.41

~

IMPORTANCE FACTOR: 4.6 APPLICABILITY: ---=R=O-- SRO EoD ROO STAD SROm EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 08-21-12 Instructor Validated By: Wathey Date: 08-23-12 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 9

OPERATOR TR:AINING PROGRAM JOB PERFORMANCE MEASURE NAME: __________________________

DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

TASK NUMBER: 1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

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. Complete the ICMF with the classification of ALERT under EAL RB3.L and provide it to the Primary Communicator within 15 minutes of Start Time.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 9

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Note: This ECG call can either be an ALERT or a SAE based on whether or not the crew tripped the cavitating charging pump.

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

START TIME:

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started. I duties Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG Classifies the event Determines the classification of the event and refers to ECG Attachment 2 (Alert)

Att 2 CALL communicators to the Control Pages communicators and initials as SM A.1 Room Cue: I am the Primary Communicator PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of9

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

Att 2 IF a security Event is in progress, THEN Determines Security Event is not in A2 IMPLEMENT the prompt actions of progress.

NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to the classification.

Att 2 As time allows, OBTAIN Classification Cue: No independent review will be A3 Independent Verification (ensure verifier performed.

understands the EAL assessment clock is running);

STA or designee performs Independent I Verification for SM.

SM or designee performs Independent Verification for EDO.

EDO or designee performs Independent Verification for ERM. I Att 2 While classification verification is in Begins filling out ICMF.

A4 progress and if time allows, COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment)

Att 2 After classification verification and/or Before 15 minute assessment clock A5 before 15 minute EAL assessment clock expires, declares ALERT at Salem expires, DECLARE and ALERT at Salem Unit(s)

Unit(s)

AU 2 ACTIVATE "ERO Emergency Callout" Cue: Activation of ERO Emergency 8.1 per posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (Commitment EP96-003)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 40f9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Att 2 COMPLETE/APPROVE the (ICMF) (last Fills out Section II of ICMF:

8.2 page of this attachment).

EAL#(s): RB3.L Description of Event:

Loss of the Reactor Coolant System Barrier Note: Description of Event is found in EAL Description Table Fills out Section III:

Checks for a Radiological Release is in progress.

Fills out Section IV:

Retrieves wind speed and direction data from SPDS Initials for aQQroval to transmit Att 2 IF time allows, OBTAIN an accuracy peer Cue: Peer check is not provided.

B.3 check of the completed ICMF.

7 PROVIDE the ICMF to the Primary Provides ICMF to Primary Communicator

Communicator and DIRECT the within 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME:

Attachment 6.

Terminate JPM when ICMF is given to the Evaluator.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 50f9

EP-SA-1l1-F2 ATT2 Pg 3 of3 INITIAL CONTACT MESSAGE FORM

1. THIS IS _ _ _ _ _ _ _ _ _ _, COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) oTSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) NO ..____ ...._ _ __

II.

o THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT TIME ON _ _ _TODAYSDATE .

(Time-24 HR CLOCK) (DATE)

EAL #(s) RB3.L DESCRIPTION OF EVENT: Loss of the Reactor Coolant System Barrier III.,--_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _---,

NOTE:

Radiological Release is defined as: Plant Effluent> Federal Limit of 2.42E+05 uCi/sec Noble Gas or 2.lE+Ol uCi/sec 1-131.

o NO RADIOLGlCAL RELEASE IS IN PROGRESS. see NOTE for release o THERE A RADIOLOGlCAL RELEASE IN PROGRESS definition IV. 0 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: _ _ _ _ __

(From MET Computer ISPDS) (DEGREES) (MPH)

V. &:I NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME Candidates Initial EC Initials (Approval to Transmit ICl\IF)

SGS Rev. 00 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 9

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of9

TQ-AA-106-0303 Revision 4 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, ,IPM description and number are identified.

____ 2. Knowledge and Abilities (KIA) 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.

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SM Ell nstructor:- - - - - - - - - - - - - - - - - Date: _______

SMElinstructor:_ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of9

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

TASK NUMBER: 1240020502 JPM NUMBER: 11-01 NRC SRO Admin A4-3 (ESG-3)

ALTERNATE PATH: I I KIA NUMBER: 2.4.41

~

IMPORTANCE FACTOR: __________~----- 4.6 APPLICABILITY: RO SRO EOD RoD STAD SROm EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 08*21*12 Instructor Validated By: A Crampton Date: 9*10*12 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

TASK NUMBER: 1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical ..'PM.

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. Complete the ICMF with the classification of SAE under EAL FB2.P AND RB2.P and provide it to the Primary Communicator within 15 minutes of Start Time.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

START TIME:

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.

duties Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG Classifies the event Determines the classification of the event and refers to ECG Attachment 3 (SAE)

AU 3 CALL communicators to the Control Pages communicators and initials as SM A.1 Room Cue: I am the Primary Communicator AU 3 IF a security Event is in progress, THEN Determines Security Event is not in A.2 IMPLEMENT the prompt actions of progress.

NC.EP-EP.ZZ-0102, EC Response, Attachment 10, prior to the classification.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 30f9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Att 3 As time allows, OBTAIN Classification Cue: No independent review will be A.3 Independent Verification (ensure verifier performed.

understands the EAL assessment clock is running);

STA or designee performs Independent Verification for SM.

SM or designee performs Independent Verification for EDO.

EDO or designee performs Independent Verification for ERM.

Att 3 While classification verification is in Begins filling out ICMF.

A.4 progress and if time allows, COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment)

Att 3 After classification verification and/or Before 15 minute assessment clock A5 before 15 minute EAL assessment clock expires, declares SITE AREA expires, DECLARE SITE AREA EMERGENCY at Salem Unit(s)

EMERGENCY at Salem Unit(s)

Att 3 ACTIVATE "ERO Emergency Callout" Cue: Activation of ERO Emergency B.1 per posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (Commitment EP96-003)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of9

OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Att 3 COMPLETE/APPROVE the (ICMF) (last B.2 page of this attachment).

Fills out Section II of ICMF:

EAL#(s): FB2.P AND RB2.P Description of Event Potential Loss of the Fuel Clad Barrier, Potential Loss of the Reactor Coolant System Barrier Note: Description of Event is found in EAL Description Table Fills out Section III:

Checks for a Radiological Release is in progress.

Fills out Section IV:

Retrieves wind speed and direction data from SPDS Initials for a tm rovaI to transmit Att 3 IF time allows, OBTAIN an accuracy peer Cue: Peer check is not provided.

8.3 check of the completed ICMF.

Att 3 PROVIDE the ICMF to the Primary Provides ICMF to Primary Communicator BA Communicator and DIRECT the within 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME:

Attachment 6.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 50f9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

Terminate JPM when ICMF is given to the Evaluator.

'-~~~ ------

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 60f9

EP-SA-lll-F3 ATT3 Pg 3 of3 INITIAL CONTACT MESSAGE FORM

1. THIS IS _ _ _ _ _ _ _ _ _ _, COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) oTSC o EOF AT THE SALEM NUCLEAR GENERATING STATION, UNIT(s) NO. _________.

II.

o THIS IS NOTIFICATION OF A SITE AREA EMERGENCY WHICH WAS DECLARED AT TIME ON _ _ _TODAYS DATE_ _,

(Time-24 HR CLOCK) (DATE)

EAL #(8) FB2.P AND RB2.P DESCRIPTION OF EVENT Potential Loss of the Fuel Clad Barrier, Potential Loss of the Reactor Coolant System Barrier III.

~--------------------------------------------------------------------~

NOTE:

Radiological Release is defined as: Plant Effluent> Federal Limit of 2.42E+05 uCi/sec Noble Gas or 2.1E+Ol uCi/sec 1-131.

o NO RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release o THERE IS A RADIOLOGICAL RELEASE IN PROGRESS definition IV. 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: _ _ _ _ __

(From MET Computer ISPDS) (DEGREES) (MPH)

V. 0 NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME Candidates Initial EC Initials (Approval to Transmit ICMJ;')

SGS Rev. 01 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 70f9

TQ*AA*106*0303 Revision 4 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, .IPM description and number are identified.

____ 2. Knowledge and Abilities (KIA) 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/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - - -

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 9

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedurE9s or to look atthe control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of9

OPERATOR TRJ~INING PROGRA.M JOB PERFORMA:.~CE MEASlJRE STATION: SALEM SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N001 00701 01 JPM NUMBER: 11-01 NRC Sim a ALTERNATE PATH: I X I ~ANUMBER: _______0~0_1_A_4.~03~____~

IMPORTANCE FACTOR: ____ 4.~0--_ 3.7 APPLICABILITY: RO SRO EOD RO[IJ STAD SRO[IJ EVALUATION SETTING/METHOD: Simulator

REFERENCES:

S2.0P-ST.RCS-0001, Rev. 20 (checked 08-06-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08-04-2012 Instructor Validated By: Mulford Date: 08-24-2012 SM ~or Inst1uctor,

<f;l~"

)

Approved By: --\l.v;/ll¥1 Date:

aining epartmenf Approved By: -=is ~~\J~ /6-.'1 tt!.Jko'-J ~~ ') Date: C;/i.f ('A Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 SIMULATOR IC: IC-2S1 on NRC portable hard drive MALFUNCTIONS REQUIRED: RT-1 will trip 21 SGFP MALF: BF0105A, 21 STM GEN FEED PUMP TRIP, Final Value: 3 OVERRIDES REQUIRED: None SPECIAL INSTRUCTIONS: None

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ____________________________

DATE: _____________________________

SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 INITIAL CONDITIONS:

Unit 2 is operating at steady state, 100% power. Power has been at 100% for 30 days.

INITIATING CUE:

You are directed to perform S2.0P-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.

A Maintenance Technician is stationed at the Rod Control System Power Cabinets.

Communications are established via plant page between the Control Room and Jeff Stevens, NEO, at the Rod Control System Power CabinE3ts.

The CRS has directed that steps 5.1.2 through 5.1.9 are to be performed in order.

The CRS directs that 15 steps of rod insertion are to be performed for each bank to ensure that each rod moves at least 10 steps.

Initial Control Rod Positions are:

SOA SDB SOC SOD F-04 230 G-03 230 E-03 230 C-05 230 0-10 230 C-09 230 C-11 226 E-13 226 K-12 230 J-13 230 L-i3 227 N-11 227 M-06 230 N-07 230 N-05 227 L-03 230 B-04 230 J-02 225 0-14 227 C-06 226 P-12 230 G-13 230 M-02 230 N-09 230 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:

Operator trips the Rx when Shutdown Bank B is inserted in the core and a SGFP trips.

OP)i~RATOR TRAINING PROGRAM NAME: _____________________

Jon PERFORMANCE MEASURE DATE: ______________________

SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS

STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. (#Denotes a Sequential Step) STANDARD S/U Evaluation)

Provide marked up copy of ST.RCS-0001, with Reviews Prerequisites.

Prerequisite Section 2.0 filled out.

Reviews and signs Precautions and Limitations.

Cue: IF ASKED, state that no special contingency actions have been briefed other than what is in the P&L's.

5.1.1 IF this surveillance is to be performed .... N/As step based on steady state 100%

operation.

OPERATOR TRAINING PROGRAM N~E: _______________________

JOB PlmFORMANCE MEASUJU~

DATE:

SYSTEM: Rod Control TASK: Perfonn a Control Rod Operability Verification STEP COMMENTS

STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. (#Denotes a Sequential Step) STANDARD S/U Evaluation) 5.1.2 PERFORM Shutdown Bank A testing as follows:

A. IF the Rx is critical, THEN ENSURE Checks Tave/Tref recorder on 2RP4 and Tavg is within 1 degree of Tref. notes Tavg is within 1 0 of Tref..

B. PLACE Bank Selector Switch in the SBA Rotates Bank Selector Switch fully counter position. clockwise to the SBA position.

C. ENSURE GRP. SELECT "C" lights are Contacts NEO and directs him to verify illuminated on Rod Control System lights.

Power Cabinets 21 AC and 22AC. Cue: GRP SELECT "C" fights are illuminated at Rod Control System Power Cabinets 21AC and 22AC.

D. Maneuver Shutdown Bank A at least 10 Inserts SBA at least 10 steps.

steps in anyone direction.

E. ENSURE each rod in Shutdown Bank A Verifies rod movement by viewing rod indicated rod movement of at least 10 position on P-250 computer.

steps. Initials SAT for Groups 1 and 2 for SBA on F. RECORD Shutdown Bank A "Test AU 1.

Results" by initialing in attachment 1. Withdraws SBA to ARO position.

G. RESTORE Shutdown Bank A to pre-test Continuous rod withdrawal is acceptable.

condition. Cue: GRP SELECT "C" lights are H. ENSURE GRP. SELECT "C" lights are illuminated at Rod Control System Power illuminated on Rod Control System Cabinets 21 AC and 22AC.

Power Cabinets 21AC and 22AC. ----_ _._

OPERATOR TRAINING PROGRAM NAME: ______________________

JOB PERFORMANCE MEASURE DATE: _______________________

SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification STEP COMMENTS

STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. (#Denotes a Sequential Step) STANDARD S/U Evaluation) 5.1.3 PERFORM Shutdown Bank B testing as follows:

A. IF the Rx is critical, THEN ENSURE Checks Tave/Tref recorder on 2RP4 and Tavg is within 1 degree of Tref. notes Tavg is within 1° of Tref..

B. PLACE Bank Selector Switch in the SBB Rotates Bank Selector Switch clockwise position. to the SBB position.

n C. ENSURE GRP. SELECT "C lights are Contacts NEO and directs him to verify illuminated on Rod Control System lights.

Power Cabinets 21 BO and 22BO. Cue: GRP SELECT "C" lights are illuminated at Rod Control System Power Cabinets 21 BO and 22BO.

D. Maneuver Shutdown Bank B at least 10 Inserts S88 at least 10 steps.

steps in anyone direction. I E. ENSURE each rod in Shutdown Bank B SIMULATOR OPERATOR:

indicated rod movement of at least 10 INSERT RT-1 when the o~erator is steps. checking rod ~osition after insertion.

This will tri~ 21 SGFP.

Responds to 21 SGFP trip by tripping the Rx lAW P&L 3.13.

Movement of the Rod Bank Selector Switch to MAN or AUTO under these conditions is incorrect.

I~~~~~~~~

When the operator has either tripped the Rx or initiated rod insertion in MAN or AUTO, state JPM is complete.

OPERATOR TRA1NL~G PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 4 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.

---lM:...L......,_1. Task description and number, JPM description and number are identified.

--LN'1-=-_- 2. Knowledge and Abilities (KIA) references are included.

---<M'-!.-..J........._ 3. Performance location specified. (in-plant, control room, or simulator)

__NJ--o_ 4. Initial setup conditions are identified.

--f.N"\-=-.lo.....-_ 5. Initiating and terminating Cues are properly identified.

--..IN'1L'-+I_ 6. Task standards identified and verified by SME review.

-+I\",..M-',r-- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

-..LN"\.J!.-~_ 8. Verify the procedure referenced by this JPM matc~es t~e most current revision of that procedure: Procedure Rev. ~ Date S.J.a1.f ~a

=--f\M~\-9. Pilot test the JPM:

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

b. ensure performance time is accurate.

~ 10.@)he 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.

SMElinstructor:I;C--#-+---'---_I--_--<.~__>...:::.~..!.!lw_=_cA SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMElinstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is operating at steady state, 100% power. Power has been at 100% for 30 days.

INITIATING CUE:

You are directed to perform S2.0P-ST.RCS-0001, Reactivity Control System Rod Control Assemblies.

A Maintenance Technician is stationed at the Rod Control System Power Cabinets.

Communications are established via plant page between the Control Room and Jeff Stevens, NEO, at the Rod Control System Power Cabin,ets.

The CRS has directed that steps 5.1.2 through 5.1.9 are to be performed in order.

The CRS directs that 15 steps of rod insertion are to be performed for each bank to ensure that each rod moves at least 10 steps.

Initial Control Rod Positions are:

SOA SOB SOC SOD F-04 230 G-03 230 E-03 230 C-05 230 0-10 230 C-09230 C-11 226 E-13 226 K-12 230 J-13 230 L-13 227 N-11 227 M-06 230 N-07 230 N-05 227 L-03 230 B-04 230 J-02 225 0-14 227 C-06 226 P-12 230 G-13 230 M-02 230 N-09 230

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

STATION: SALEM SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves TASK NUMBER: N0060160201 JPM NUMBER: 11-01 ILOT Sim b ALTERNATE PATH: m KIA NUMBER: _ _ _0'-'-0-'-6_A_4._02_ _- i IMPORTANCE FACTOR: 4.0 3.8 APPLICABILITY: RO SRO EOL] RO[ZJ STA [~ SRO [ZJ EVALUATION SETTING/METHOD: Simulator I Perform S2.0P-ST.SJ-0006, Inservice Testing Safety Injection Valves Mode 6,

REFERENCES:

Re~13 TOOLS AND EQUIPMENT: Stopwatch VALIDATED JPM COMPLETION TIME: 15 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-04-12 Instructor Validated By: Mulford Date: 08-23-12 Approved By:

~ Training Department Date: ?!l3/J1 Approved By: .'1< ~L(61~NC'~) Date: ~;,~~~

Op;\1tions D,epartment ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

. EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves TASK NUMBER: N0060160201 SIMULATOR SETUP IC-242 This IC was developed by: Simulating Mode 6 conditions. Depressurizing RCS with RHR remaining in service. Opening both PORVs. Simulating cavity level 126' by filling PZR full.

Remote: SJ01D 21SJ54 breaker 2AY2EP2D Remote: SJ02D 22SJ54 breaker 2BY2EP2D ET*1 ka103anl 22SJ54 open PB. Tied to:

22 Accumulator Channel I pressure (1/0 A105) Final Value 33 with a ramp time of 38 seconds.

22 Accumulator Channel II pressure (1/0 A106) Final Value 33 with a ramp time of 37 seconds.

INITIAL CONDITIONS:

Unit 2 is in MODE 6 with the Rx vessel head removed.

The control room is preparing to perform ECCS Accumulator Check Valve testing.

A second control room operator is available.

A NEO is stationed in the field for any operations required.

Reactor cavity level is 126'.

Refueling Transfer Tube Gate Valve is shut.

INITIATING CUE: Perform forward flow testing of 21-24 ECCS Accumulators Check Valves lAW S2.0P ST.SJ-0006. nlis is the normally scheduled surveillance.

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. C()mpletion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Perform forward flow test of 21 ECCS Accumulator and determine it is SAT.

2. Perform forward flow test of 22 ECCS Accumulator and determine it is UNSAT.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD SJU evaluation)

Provide copy of S2.0P-ST.SJ-0006 with prerequisites complete and calibration data Cue if required: If asked during JPM filled in. performance about cavity level, evaluator will respond that the normal control room staff is monitoring level, and it remains stable at 126'.

3.0 PRECAUTIONS AND LIMITATIONS. Reviews Precautions and Limitations 5.1.1 RECORD 21 Accumulator Initial Data in Records 21 Accumulator Initial Data Attachment 2, Section 1.0. in Attachment 2, Section 1.0. as 69.2 psig and 96.6 %.

5.1.2 CLOSE 2AY2EP2D, 21 SJ54 Contacts NEO and directs them to ACCUMULATOR OUTLET VALVE. shut2AY2EP2D,21SJ54 ACCUMULATOR OUTLET VALVE.

Simulator Operator: Modify Remote SJ01 D from tagged to untagged to shut 2AY2EP2D and report back to control room.

5.1.3 At Panel 2RP4, ENSURE 21 SJ54 in the At Panel 2RP4, checks 21 SJ54 is in VALVE OPERABLE position. the VALVE OPERABLE position.

5.1.4 IF Scheduled Surveillance testing is to be performed (Refer to P&L Step 3.6),

THEN:

5.1.4.A A. Simultaneously PERFORM the following:

OPEN 21SJ54, 21 ACCUM OUT

START the Stopwatch Simultaneously depresses the open

'---- ~ -~ ~--

PB for 21 SJ54 and starts stopwatch.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation) 5.1.4.8 B. When 21 Accumulator pressure is observed to be 35 psig,

Simultaneously PERFORM the following: Simultaneously depresses the

STOP the Stopwatch 21 SJ54 close P8 and stops the

CLOSE 21 SJ54 stopwatch when 21 Accumulator pressure indicates 35 psig.

5.1.4.C PERFORM the following lAW Attachment 2, Section 2.0:

RECORD Stopwatch Number and

Reading (A) in Attachment 2, Section Records stopwatch number and 2.0. reading (A) in Attachment 2 Section

CALCULATE Accumulator Slowdown 2.0

Time (C) by subtracting Disk Calculates Accumulator Slowdown Movement Time (8) from Stopwatch Time (C) by subtracting Disk Reading (A) AND RECORD in Movement Time (S-1.15 seconds)

Attachment 2, Section 2.0. from Stopwatch Reading (A) AND

DIRECT a second Operator to records in Attachment 2, Section 2.0.

perform Independent Verification of the calculation performed lAW Directs a second Operator to perform Attachment 2, Section 2.0. Independent Verification of the calculation performed lAW Attachment 2, Section 2.0.

Cue: IV is complete SAT.

5.1.4.0 RECORD 21SJ55 and 21SJ56 OPEN "Test Records 21SJ55 and 21SJ56 OPEN

Results" by initialing the SAT or UNSAT "Test Results" by initialing the SAT column using the Acceptance Criteria in column using the Acceptance Criteria Attachment 2, Section 2.0. in Attachment 2, Section 2.0.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves STEP COMMENTS STEP (Required for UNSAT

(*Denotes a Critical Step) EVAL

NO. STANDARD S/U evaluation) 5.1.5 IF Post-Maintenance Operability (Valve Exercise) testing is to be performed

Determines Post Maintenance (Refer to P&L Step 3.6),

Operability testing is N/A.

THEN:

A. OPEN 21 SJ54, 21 ACCUM OUT.

B. When 21 Accumulator level has decreased by at least 20%, CLOSE 21SJ54, 21 ACCUM OUT.

C. RECORD 21SJ55 and 21SJ56 VALVE EXERCISE "Test Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment 2, Section 3.0.

5.1.6 OPEN 2AY2EP2D, 21SJ54 ACCUMULATOR Contacts NEO and directs them to OUTLET VALVE. open 2AY2EP2D, 21SJ54 ACCUMULATOR OUTLET VALVE.

Simulator Operator: Modify REMOTE SJ01 D to tagged to open 2AY2EP2D.

5.1.7 DIRECT a second Operator to perform Restoration Independent Verification Cue: Restoration Independent of the components identified in Attachment 6, Verification of the components Section 1.0. identified in Attachment 6, Section 1.0. is complete SAT.

5.2.1 RECORD 22 Accumulator Initial Data in Records 22 Accumulator Initial Data Attachment 3, Section 1.0. in Attachment 3, Section 1.0. as 67.4 psig and 97.6 %.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

JOB PERFORMANCE MEASURE SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

5.2.2 CLOSE 2BY2EP2D, 22SJ54 Contacts NEO and directs them to ACCUMULATOR OUTLET VALVE. shut2BY2EP2D, 22SJ54 ACCUMULATOR OUTLET VALVE.

Simulator Operator: Modify Remote SJ02D from tagged to untagged to shut 2BY2EP2D.

5.2.3 At Panel 2RP4, ENSURE 22SJ54 in the At Panel 2RP4. checks 22SJ54 is in VALVE OPERABLE position. the VALVE OPERABLE position.

5.2.4 IF Scheduled Surveillance testing is to be performed (Refer to P&L Step 3.6).

THEN:

5.2.4.A A. Simultaneously PERFORM the following:

OPEN 22SJ54. 22 ACCUM OUT

START the Stopwatch Simultaneously depresses the open PB for 22SJ54 and starts stopwatch.

Simulator Operator: Ensure ET-1 is TRUE when 22SJ54 Open PB is depressed.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ECCS TASK: Perform forward Flow 1ST of ECCS Accumulator Check Valves STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 5.2.4.B B. When 22 Accumulator pressure is observed to be 35 psig.

Simultaneously PERFORM the following: Simultaneously depresses the

STOP the Stopwatch 22SJ54 close PB and stops the

CLOSE 22SJ54 stopwatch when 22 Accumulator pressure indicates 35 psig.

Simulator Operator: If 22SJ54 close PB is not depressed, DELETE overrides A 105 and 106 when they reach their full ramp in time.

5.2AC PERFORM the following IAVV Attachment 3, Section 2.0:

RECORD Stopwatch Number and

Reading (A) in Attachment 3, Section Records stopwatch number and 2.0. reading (A) in Attachment 3 Section

CALCULATE Accumulator Blowdown 2.0

Time (C) by subtracting Disk Calculates Accumulator Blowdown Movement Time (B) from Stopwatch Time (C) by subtracting Disk Reading (A) AND RECORD in Movement Time (B-1.15 seconds)

Attachment 3, Section 2.0. from Stopwatch Reading (A) AND

DIRECT a second Operator to records in Attachment 3, Section 2.0.

perform Independent Verification of the calculation performed lAW Directs a second Operator to perform Attachment 3, Section 2.0. Independent Verification of the calculation performed lAW Attachment 3, Section 2.0.

Cue: IV is complete SAT.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

SYSTEM: ECCS

.. -- ... '_1,_,,111_' ** ___ I ._1r .. _. _, __.__ ""' ___ "'_J_ ......,. _ .. __ ..... _ .* __

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 5.2.4.0 RECORD 22SJ55 and 22SJ56 OPEN "Test Records 22SJ55 and 22SJ56 OPEN

Results" by initialing the SAT or UNSAT "Test Results" by initialing the column using the Acceptance Criteria in UNSAT column using the Acceptance Attachment 3, Section 2.0. Criteria in Attachment 3, Section 2.0.

based on blowdown time >27.79 seconds.

5.2.5 IF Post-Maintenance Operability (Valve Exercise) testing is to be performed

Determines Post Maintenance (Refer to P&L Step 3.6),

Operability testing is N/A.

THEN:

A. OPEN 22SJ54, 21 ACCUM OUT.

B. When 22 Accumulator level has decreased by at least 20%, CLOSE 22SJ54, 22 ACCUM OUT.

C. RECORD 22SJ55 and 22SJ56 VALVE EXERCISE liTest Results" by initialing the SAT or UNSAT column using the Acceptance Criteria in Attachment 3, Section 3.0.

5.2.6 OPEN 2BY2EP2D, 22SJ54 ACCUMULATOR Contacts NEO and directs them to OUTLET VALVE. open 2BY2EP2D, 22SJ54 ACCUMULATOR OUTLET VALVE.

Simulator Operator: Modify REMOTE SJ02D to tagged to open 2BY2EP2D.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

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

_N'\L....:...-'.>-_1. Task description and number, JPM description and number are identified.

_f'.M<...:.-+-._2. Knowledge and Abilities (KIA) refemnces are included.

~Mt.....:....+j_ 3.. Performance location specified. (in-plant, control room, or simulator)

'f'J1:.........Jf--- 4. Initial setup conditions are identified.

---'..N'j....:........l,_ _ 5. Initiating and terminating Cues are properly identified.

--<f\n-,--,__ 6. Task standards identified and verified by SME review.

"Nj~.f-_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

- . .N"l....L..t-

. 8. Verify the procedure referenced by this JPM matches the most current revision of I that procedure: Procedure Rev. 1'3_ Date g {~1/1'}...

---,-f\!=\---\.__ 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

tJ1A 1O.(fr)he JPM cannot be performed as written with proper responses, then revise the ...IPM.

____ 11. When ...IPM is revalidated, SME or Instructor sign and date ...IPM cover page.

SME/lnstructor:r:!L-SMEll nstructor: - - - - - - - - - - - - -

f!{;--;.I. M.vt/J Date: _-='a'.J...,:<1~. . .: .)-'-'/1. :. :.2_ _

Date: - - - - - -

SME/lnstructor: Date: - - - - - -

PSEG Restricted-Possession Requires Specific Permissio~ from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: EGCS TASK: Perform forward Flow 1ST of EGGS Accumulator Gheck Valves STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 5.2.7 DIRECT a second Operator to perform Restoration Independent Verification Cue: Restoration Independent of the components identified in Attachment 6, Verification of the components Section 2.0. identified in Attachment 6, Section 2.0. is complete SAT.

Cue: JPM is complete. --~-

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is in MODE 6 with the Rx vessel head removed.

The control room is preparing to perform ECCS Accumulator Check Valve testing.

A second control room operator is available.

A NED is stationed in the field for any operations required.

Reactor cavity level is 126'.

Refueling Transfer Tube Gate Valve is shut.

INITIATING CUE:

Perform forward flow testing of 21-24 ECCS Accumulators Check Valves lAW S2.0P-ST.SJ-0006.

This is the normally scheduled surveillance.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

TASK NUMBER: 1140240401 JPM NUMBER: 11-01 ILOT NRC Sim c ALTERNATE PATH: I X I KIA NUMBER: 010 A4,01

~

IMPORTANCE FACTOR: 3,7 3,5

---':'-R;"';"O--

APPLICABILITY: SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: Simulator

REFERENCES:

S2.0P-AB.PZR-0001, Rev. 18 (Rev, checked 08-21-12-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 4min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 04-12-12 Instructor Validated By: Mulford 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: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

NAME:

PSEG Restricted* Possession Requires Specific Permission from Nuclear Training Page 1 of9

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE DATE:

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

TASK 1140240401 NUMBER:

SIMULATOR SETUP: IC-253 4% power, BOL.

I/O 8304 OVLO Pressurizer Relief Valve Outlet Temperature- Value: 98.6 MALF: PR018A PZR PORV 2PR1 develops leak - Value:40000 Tied to ET-1 RT-1 PR0019A PZR Spray Valve 2PS1 fails open ET-1 kal06tph 23 RCP Stop INITIAL CONDITIONS:

Reactor power is stable at 4.0% power. The power ascension is on hold temporarily.

INITIATING CUE:

You are the Reactor Operator. Respond to all indications and alarms.

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. Trip Rx.

2. Stops 21 and 23 RCP.

3. Stops 22 OR 24 RCP.

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OPERATIONS TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAl (Required for UNSAT NO. STANDARD S/U Evaluation)

Simulator Operator: Note: The time between the 2PS 1 failing open and RCS pressure Insert RT-1 on direction of evaluator. reaching 2,000 psig is - 4 minutes and 15 seconds.

MALF: PR0019A, 2PS1 fails open Recognizes lowering PZR Pressure and/or alarm and/or change in 2PS1 position.

Acknowledges OHA E-28 PZR HTR ON PRESS LO. Recognizes 22 PZR BtU heaters energized. If operator refers to ARP for OHA E-28, it directs entry into S2.0P-AB.PZR-0001.

Pressurizer Pressure Malfunction.

Enters S2.0P-AB.PZR-0001 directly or via OHA E-28 ARP.

Note: It is acceptable to attempt closing 2PS1 prior to entering S2.0P AB.PZR-001.

I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of9

OPERATIONS TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) 3.1 INITIATE Attachment 1 Continuous Initiates Attachment 1 Continuous Action Summary. Action Summary.

Note: There is a CAS action to trip the Rx if RCS pressure lowers to 2,000 psig and continues to drop. IF the operator were to trip the Rx during this JPM based on that CAS action and not at step 3.24.A on page 6 as expected, THEN AFTER the operator has tripped the Rx, verified the Main Turbine is tripped, verified SI not actuated or required and all 4KV vital buses energized, the following cue must be given:

Cue: The immediate actions of TRIP"1 have been verified by the CRS and RO. The CRS directs you to continue actions of S2.0P*

AB.PZR"0001, while the remaining crew members will continue to perform TRIP-1.

3.2 Is POPS in service? Determines POPS is not in service by initial conditions or console indications.

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OPERATIONS TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) 3.3 Is the controlling Pressurizer Pressure Determines Pressurizer Pressure Control Channel (lor III) failed? Control Channel (lor III) is not failed and GOES TO Step 3.11 3.11 Is the Master Pressure Controller Determines Master Pressure failed? (Refer to Attachment 2 for Controller is not failed and GOES TO guidance) Step 3.17 (may not refer to Attachment 2 if 2PS1 has been noted open with pressure below closing setpoint.)

3.17 Is a Spray Valve(s) failed? (Refer to Determines 2PS1 is failed open.

Attachment 2 for guidance) 3.18 PLACE the Spray Valve(s) in MANUAL Depresses MANUAL PB for 2PS1 and verifies AUTO light extinguished and MANUAL light illuminates. I 3.19 OPERATE the Spray Valves to control Depresses the CLOSE PB for 2PS1 pressure consistent with Attachment 2. and recognizes that 2PS1 remains open.

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

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 50f9

OPERATIONS TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) 3.21 Has pressure control been regained? Determines pressure control has not been regained since 2PS 1 remains open.

3.22 Is RCS pressure dropping rapidly? Determines RCS pressure is dropping rapidly from console indication.

3.23 Are Reactor Trip Breakers CLOSED? Determines Reactor Trip Breakers are closed by initial conditions or console indication.

3.24 PERFORM the following:

A

A TRIP the Reactor. Initiates a Reactor Trip using either MANUAL TRIP handle.

3.24 B. Is Reactor Trip Confirmed? Determines Reactor Trip is confirmed B after identifying PRNI reading < 5%

and IR NI indication dropping.

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

Simulator Operator: Ensure ET-1 is TRUE when 23 RCP stop PB is depressed.

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OPERATIONS TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Pressurizer Pressure and Level TASK: TeAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS I STEP (* Denotes a Critical Step) EVAL (Required for UNSAT i

NO. STANDARD Stu Evaluation)

3.24 IF Pressurizer Pressure continues to Determines Pressurizer Pressure D drop, THEN STOP all but one Rep. continues to drop, and depresses STOP PB on 22 OR 24 Rep and verifies start light extinguishes and stop light illuminates.

3.24 E GO TO 2-EOP-TRIP-1, Reactor Trip or Begins performing Immediate Actions Safety Injection, AND CONTINUE with of 2-EOP-TRIP-1, Reactor Trip or this procedure. Safety Injection.

Cue: When operator begins performing Immediate Actions of 2 EOP-TRIP-1, Reactor Trip or Safety Injection, state JPM is complete.

---~- ---- -- ---- -----

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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 (KIA) 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 propE~rly 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 .)PM 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 ..IPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SME/lnstructor: Date: _ _ _ _ __

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 80f9

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Reactor power is stable at 4.0% power. The power ascension is on hold temporarily.

INITIATING CUE: You are the Reactor Operator. Respond to all indications and alarms.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Residual Heat Removal TASK: TCAF a Loss of RHR TASK NUMBER: I\J 1140300401 JPM NUMBER: 11-01 NRC Sim d ALTERNATE PATH: D KIA NUMBER: APE 025 AA1.09

~

IMPORTANCE FACTOR: 3.2 3.1 APPLICABILITY: RO SRO EoD ROITJ STAD SROITJ EVALUATION SETTING/METHOD: Simulator

REFERENCES:

S2.0P-AB.RHR-0001, Rev. 17 (Rev checked 8-6-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08-18-12 Instructor Validated By:

SL Brennan Instructor .

Date: 08-24-12 Approved By:

T aining Departm~II¥~

Approved By: D~- ~L (is v~V-~.,J e~.) Date: '1/4/::t.

Op~~tionsbefi\ahment ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Residual Heat Removal TASK: TCAF a Loss of RHR TASK N1140300401 NUMBER:

SIMULATOR SETUP: IC-254 MALF VL0626 22RH18 fails to position (0-100%) Final Value 100% (This is to mimic the 22RH 18-A/S being CIT in the SHUT position).

RT-1 MALF RH0026A 21 RHR pump trip RT-3 REM RH02A 22RH12 Initial-O Final 100 Ramp 60 sec RT-3 REM RH06A 22RH17 Initial -0 Final 100 Ramp 120 sec INITIAL CONDITIONS:

Unit 2 is in MODE 4.

RCS pressure is 315 psig and stable.

RHR HX inlet temp is 289 degrees with a 1O°F/hr cooldown in progress.

21 RHR loop is in service in shutdown cooling mode.

22 RHR loop is aligned for ECCS.

INITIATING CUE:

You are the Reactor Operator. Monitor the cooldown and report when 21 RHR HX inlet temp reaches 285°F.

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. Place 22 RHR loop in service in Shutdown Cooling (SOC) mode by:

A. Aligning RHR valves to SOC line!up. (Step 3.52 & Att. 2)

B. Starting 22 RHR pump. (Step 3.S2 & Att. 2)

C. Establishing stable RHR flow of 1800-3000 gpm (Step 3.68)

D. Establishing RCS temperature stable or lowering (Step 3.68)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Pago 2 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) S/U (Required for UNSAT NO. STANDARD Evaluation)

Simulator Operator insert RT-1 on Evaluators direction.

MALF: RH0026A 21 RHR Pump Trip Responds to trip of 21 RHR pump by depressing the STOP PB.

r---

Note to Evaluator: The PZR Hi Ivl alarm on 2CC2 will annunciate shortly after the RHR pump is tripped. IF the candidate begins actions to respond to this alarm, THEN CUE that a second operator will refer to the Alarm Response Procedure for the PZR Hi level alarm.

Recognizes there is no RHR cooling, and enters S2.0P-AB.RHR-0001, Loss of RHR.

3.1 INITIATE Attachment 1. Continuous Initiates Attachment 1, Continuous Action Action Summary. Summary.

f-3.2 IF the RCS is vented to the Recognizes the RCS is not vented to the Containment... containment and N/A's step.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: ' TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) stu (Required for UNSAT NO. STANDARD Evaluation) 3.3 Is RCS aligned for operation <101 ft. Determines RCS is not aligned for elevation (Reduced Inventory)? operation <101 ft. elevation (Reduced Inventory) and goes to step 3.5.

3.5 Is the loss of RHR due to a mechanical Determines the loss of RHR is due to a failure or loss of electrical power to the in- mechanical failure or loss of electrical service RHR pump? power to the in-service RHR pump and goes to step 3.50.

Note: If operator answers NO here, then they will perform steps which are designed for system, rather than pump, problems, and is incorrect.

3.6 GO TO Step 3.50 Goes to Step 3.50 3.50 Is a heat sink available for Residual Heat Determines a heat sink available for Removal? Residual Heat Removal since SW and

Component Cooling to RHR CCW are unaffected.

System

Service Water to Component Cooling System PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) StU (Required for UNSAT NO. STANDARD Evaluation) 3.51 Is an RHR Loop available? Determines a RHR Loop is available since 22 RHR loop is available (lined up in ECCS Mode).

3.52 PLACE the alternate RHR Loop in service:

IE alternate loop is aligned for Performance steps on next page ECCS, THEN PERFORM Attachment 2, Aligning RHR Loop From ECCS To Shutdown Cooling.

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

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

" Page 5 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) StU (Required for UNSAT NO. STANDARD Evaluationl Att. 2 2.0 IF placing RHR Loop 22 in service, THEN:

A. ENSURE RHR Loop 22 is aligned Determines 22 RHR loop is aligned for for ECCS injection. ECCS injection from initial conditions.

B. PLACE 22RH29 RHR PUMP Determines 22RH29, RHR PUMP MINIMUM MINIMUM FLOW VALVE in FLOW VALVE is in AUTO.

AUTO.

C. Locally:

OPEN 22RH12 RHR HX Directs a local operator to open 22RH 12 This step to open 3 local BYPASS ISOLATION VALVE RHR HX BYPASS ISOLATION VALVE, valves is considered a

OPEN 22RH17 RHR open 22RH 17 RHR LETDOWN critical task because LETDOWN ISOLATION ISOLATION VALVE, and open 22RH18 failure to have these local VALVE NS RHR LETDOWN ISOLATION VALVE valves opened will prevent

OPEN 22RH 18-NS RHR AIR SUPPLY placing 22 RHR loop in LETDOWN ISOLATION service in SDC.(No bypass VALVE AIR SUPPLY CUE: Time compression will be used to or 22RH18 flow control) perform field actions.

(Note: Time compression will be utilized for operato'rs performing actions in the Simulator Operator: When directed to field.) ,open 22RH 18-NS, delete MALF VL0626 22RH18 fails to position (0*100) (This allows valve to move when control console PBs are depressed.)

Then insert RT-3 to open the 22RH12 and 22RH17. Report to operator when they are open. Also report that you have released the Red Blocking Tag and opened 22RH18-A/S, RHR LETDOWN

... ~. . .- ..

ISOLATION VALVE AIR SUPPLY PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) S/U (Required for UNSAT NO. STANDARD Evaluation)

Simulator ORerator Cue: IF requested for WCC to release tag, state that the NEO has the release for 22RH 18- A/S LOCAL A/S TO 22RH18.

D. In the Control Room:

Depresses CLOSE PB's for:

CLOSE 22RH18, RHR PUMP

22RH 18 RHR PUMP FLOW FLOW CONTROL VALVE CONTROL VALVE

CLOSE 21RH18, RHR PUMP

21RH18 RHR PUMP FLOW FLOW CONTROL VALVE CONTROL VALVE

CLOSE 2RH20, RHR HX

2RH20 RHR HX BYPASS BYPASS

21CC16 RHR HX COMPONENT

CLOSE 21CC16, RHR HX COOL OUT VALVE COMPONENT COOL OUT And verifies valves stroke closed.

VALVE

Depresses OPEN PB for 22CC16 and

OPEN 22CC16, RHR HX COMPONENT COOL OUT verifies it strokes open.

VALVE

START 22 RHR PUMP Depresses the START PB for 22 RHR pump and verifies the pump started.

PSEG Restricted ~ Possession Requires Specific Permission from Nuclear Training Page 7 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) S/U (Required for UNSAT NO. STANDARD Evaluation \

F. OPERATE 22RH18 and 2RH20, to Adjusts 22RH18 RHR PUMP FLOW maintain stable RHR flow to the CONTROL VALVE and 2RH20 RHR HX Reactor Coolant System. BYPASS to establish stable RHR pump flow.

RETURN to procedure step in effect. Returns to step 3.52 and initials step as complete.

3.53 Is RHR in service? Determines RHR is in service by previous step performance.

3.54 Is a heat sink available for Residual Heat Removal?

Component Cooling to RHR Determines a heat sink available for System Residual Heat Removal since SW and

Service Water to Component CCW are unaffected.

Cooling System PSEG Restricted ~ Possession Requires Specific Permission from Nuclear Training Page 8 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) S/U (Required for UNSAT NO. STANDARD Evaluation) 3.55 Is RHR flow stable? Checks RHR flow and determines flow is stable, and goes to Step 3.68 Note: Operator may adjust 22RH18 RHR PUMP FLOW CONTROL VALVE and 2RH20 RHR HX BYPASS if flow is not stable, or not 1800-3000 gpm per step 3.56.

If this is the case, RHR system verification is performed at step 3.59. (It is the same as step 3.68).

L PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 12

OPERATOR TRAINING PROGRAM NAME:

SYSTEM Residual Heat Removal TASK: TCAF Loss of RHR STEP COMMENTS STEP (* Denotes a Critical Step) S/U (Required for UNSAT NO. STANDARD Evaluation) 3.68 Is RHR System normal as indicated by ALL of the following?

RHR Pumps - at least one Verifies 22 RHR pump lIS running

RCS level- >97.5 ft. elevation Determines ReS is full (PZR level)

AND stable OR rising consistent with current RCS makeup AND no excessive indication of RCS Leakage.

RHR flow - stable between 1800 Adds 21SJ49 RHR DISCH TO COLD and 3000 gpm LEGS flow and 22SJ49 RHR DISCH TO

RCS temperature - stable or COLD LEGS flow to get 1800-3000 gpm.

lowering Uses P-250 computer to verify RCS temperature is stable or lowering. IF temperature is NOT stable or lowering.

raises flow through HX by opening 22RH 18 RHR PUMP FLOW CONTROL VALVE while lowering bypass flow by closing 2RH20 RHR HX BYPASS to turn RCS temperature.

Note: It is acceptable to use either RCS temperature indication(s) OR RHR HX inlet temperature to determine if RCS temperature is stable or lowering. CETs will respond the quickest.

After determining RCS temp is stable or lowering and goes to Step 4.0, state: "JPM is complete."

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASIURE 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.

J:3 1. Task description and number, JPM description and number are identified.

_ - 1 t -_ _ 2. Knowledge and Abilities (KIA) references are included.

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

_.........1."'--_ 4. Initial setup conditions are identified.

11 5. Initiating and terminating Cues are properly identified.

1'- 6. Task standards identified and verified by SME review.

_--,-",--_7. Critical steps meet the criteria for critic:al 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 :2 '(. /1...

_-L-_ 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 ..IPM.

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

SME/lnstructor:_--.l-:JL:.....-_~ _ _...:t5_I"_8?1~~

_ _ __ Date: __'?_'_~_'f_.I_'L-SME/lnstructor: Date: - - - - - -

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ ___ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 11 of 12

OPERATOR TRAiNING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is in MODE 4.

RCS pressure is 315 psig and stable.

RHR HX inlet temp is 289 degrees with a 1QOF/hr cooldown in progress.

21 RHR loop is in service in shutdown cooling mode.

22 RHR loop is aligned for ECCS.

INITIATING CUE:

You are the Reactor Operator. Monitor the cooldown and report when 21 RHR HX inlet temp reaches 285°F.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 12 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Main Turb ASO trip)

TASK NUMBER: N1140420401 JPM NUMBER: 11-01 NRC Sim e ALTERNATE PATH: I X I KIA NUMBER: 2.4.31 IMPORTANCE FACTOR: 4.2 4.1 APPLICABILITY: RO SRO EO RO I X I STA SRO EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AR.ZZ-0007, Rev. 48, Overhead Window G

REFERENCES:

S2.0P-AB.TRB-0001, Rev. 14, Turbine Trip <P-9 (Both rev checked 8-6-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-6-12 Instructor Validated By: Mulford Date: 8-23-12 sMyr In~:r, ~

Approved By: /~

Tr'3ining Depa ct ..

AJi~!t~

nt Date: 11/(l.

Approved By: ~ 11 (~"'V\V~Ne~ ) Date: ~/s;/1~

o,;;rat'o'ns Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Pa!ae 1 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE: __________________________

SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

TASK NUMBER: N1140420401 SIMULATOR SETUP IC-255 MALF TU0118A 21 MS28 Turb Stop Valve Fails Open RT-2 1/0 4505 OVLO Low Oil Pressure - I MALF AN0244 SE.R 244Fails- :G4 Turbine Auto Stop Oil Pressure Low RT-3 MALF AN0605 SER 605 Fails - : F32 DEHC Trip I/O 4506 OVLO Low Oil Pressure - II 110 4507 OVLO Low Oil Pressure-III I

INITIAL CONDITIONS:

40% power, BOL.

A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE: You are the Reactor Operator. Respond to all alarms and indications.

I 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. Trip the Main Turbine.

2. Trip the Rx.

Page 2 of 10 PSEG Restricted - Possession Requin~s Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Main Turbine TASK" TCAF Main Turbine Trip < P-9 (Low ASO pressure)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) i SIMULATOR OPERATOR:

Insert RT-2 after candidate assumes the Announces unexpected OHA G-4 TURB watch. AUTO STOP OIL PRESS LO Refers to S2.0P-AR.ZZ-0007, Overhead Window G.

ARP Reviews causes and determines one of 1.0/2.0 three Auto Stop Oil Pressure channels reading ~50 psig causes the alarm, and 2 of 3 channels in alarm will trip the Main Turbine.

IF alarm is due to testing OR alarm is Determines no testing in progress and ARP expected for current plant conditions, alarm is not expected.

3.1 THEN no further action is required.

ARP CONFIRM alarm by verifying 2RP4 AST Checks 2RP4 AST Oil Press Low status 3.2 Oil Press Low status light indications. light is illuminated for Channel I.

Page 3 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Main Turbine TASK TeAF Main Turbine Trip < P-9 (Low ASO pressure)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

ARP IF a Turbine Trip occurs, 3.3 THEN:

A. IF ~P-9 (49% power),

THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

B. <P-9 (49% power),

THEN GO TO S2.0P-AB.TRB-0001 (0),

Turbine Trip Below P-9.

ARP IF instrument failure is suspected, v'::'! . ..,.

A THEN: There is no justification for suspecting A. REFER TO Technical Specifications. instrument failure without having technician B. REMOVE affected channel from investigate.

service lAW S2.0P-SO.RPS-0006(0),

Main Turbine Channel Trip/Restoration. May dispatch operator to check turbine or C. INITIATE a NOTF to determine and call for assistance from WCC or correct the cause of the alarm. maintenance. I Note: Allow sufficient time for candidate to try and initiate action to investigate.

Simulator Operator: Insert RT-3 on direction from Evaluator.

This simulates the remaining 2 channels see a low Auto Stop Oil signal and actuates OHA F-32, which indicates a demand for a Turbine Trip, which does not occur.

Page 4 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK TCAF Main Turbine Trip < P-9 (Low ASO pressure)

STEP COMMENTS i STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) i Candidate recognizes a demand for a turbine trip has occurred, but the turbine has not tripped.

Initiates a turbine trip from trip handle and verifies turbine is tripped. Recognizes step 3.3 states ...

"IF <P-9 (49% power),

THEN GO TO S2.0P-AB.TRB-DOO1(Q),

Turbine Trip Below P-9." And goes to S2.0P-AB.TRB-0001.

AB.TRB INITIATE Attachment 1, Continuous Initiates Attachment 1, Continuous Action 1 Action Summary. Summary.

Page 5 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Low ASO pressure)

STEP COMMENTS STEP EVAL (Required for UNSAT

(*Denotes a Critical Step)

NO. STANDARD S/U evaluation)

AB.TRB VERIFY the Turbine is tripped. Note: IF the candidate observes the 3.2 21 MS28 remaining open at this point, THEN they may determine the turbine is not tripped, and perform a MSLI by depressing all 4 MSLI PBs on either Safeguards bezel. Initiating a MSLI before the Rx is tripped is an incorrect action which may challenge SG safeties if they lift.

Initiating a MSLI renders the Main Steam Dumps inoperable and prematurely isolates the SGFPs. With Rx power >P-10 (10%)

and steam dumps not available, a Rx trip is required lAW CAS actions 1.0 and 2.0.

See page 8 for complete discussion.

See next page for required actions in EOP TRIP-1 IF a Rx trip is performed here.

AB.TRB Are all Turbine Stop Valves closed? Determines all Turbine Stop Valves are 3.3 NOT closed from 2RP4.

Goes to Step 3.7.

AB.TRB TRIP the Reactor, GO TO 2-EOP-TRIP- Trips the Reactor using either of the 3.7 1, Reactor Trip or Safety Injection. Reactor Trip handles.

Page 6 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Low ASO pressure)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD SJU evaluation)

IF candidate initiates a Rx trip prior to initiating a MSLI based on CAS actions 1.0 and 2.0 which would occur if they initiated a MSLI, then successful performance of TRIP-1 immediate actions must be performed as follows:

EOP

TRIP-1 TRIP REACTOR Trips the Rx using either Trip handle.

... ~ ,

1 EOP TRIP-1 IS REACTOR TRIP CONFIRMED Confirms Rx trip 1 - - .. 2 -----~=-

EOP- TRIP TURBINE Attempts to trip the Main Turbine using the TRIP-1 Trip handle.

3 Determines the Trip handle did not close all Main Turbine Stop Valves.

Depresses Turbine Trip bezel.

Determines the Trip handle did not close all Main Turbine Stop Valves.

EOP

TRIP-1 TRIP TURBINE (MSLI step) Initiates a MSLl.

3 Terminate JPM after MSLI has been performed.

Page 7 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

Turbine Trip requirements- During performance of this JPM, the candidate will receive direction from the Alarm Response Procedure S2.0P-AR.ZZ 0007, Overhead Window G, OHA G-4, page 9, which states "TRIP the Turbine and GO TO S2.0P-AB.TRB-0001, Turbine Trip <P-9."

When outside the EOP network, initiating a MSLI to perform a Turbine Trip is NOT an appropriate action, since in TRIP-1 the steps for tripping the Rx precede the steps for tripping the Turbine, and the MSLI would only be performed AFTER all attempts to trip the Rx from the control room have already been performed. IF the Rx trip were NOT confirmed, then the Turbine trip steps would include the MSLI since the overriding concern at that point would be reduction of Rx power by removing the Main Turbine from service.

After entering the EOP Network, actions for tripping the Reactor and tripping the Turbine have special definitions as described in OP-AA-101-111-1003, Use of Procedures, which ONLY apply while in the EOP network. When defining turbine trip while in EOP-TRIP-1, it states on page 13,

" Steps 2.2 and 3, TRIP TURBINE, are defined as, "Operate the turbine trip switch" IF turbine trip NOT confirmed, THEN trip the turbine using the Turbine Trip bezel.

IF turbine trip NOT confirmed, THEN initiate main steam isolation.""

For these reasons, initiating a MSLI during this JPM prior to initiating a Rx trip will be considered failure criteria due to the possible challenge to SG safeties which may occur due to this action, and which otherwise would not occur in the JPM.

Page 8 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

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.

~N:\--l..__ 1. Task description and number, ..IPM description and number are identified.

--I.tf\----\,,--_ 2. Knowledge and Abilities (KIA) references are included.

.f\M-"-\,__ 3. Performance location specified. (in-plant, control room, or simulator)

'-1't\----\,,--_ 4. Initial setup conditions are identified.

--::.M-"-lf--- 5. Initiating and terminating Cues are properly identified.

--I.f\M~I--_ 6. Task standards identified and verified by SME review.

,N"\'--->r-'_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

N\ 8. Verify the proced u re referenced~b(1~i s J PM matcher. thf most cu rre nt revision of that procedure: Procedure Rev. ~ Date '3£13(11

,N'\!...--+-,_ 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

-.!..!N"+/..::...JAL--_1 O. QVhe 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.

SMEJlnstructor@

f4:---'/J,fLl~~

SMElinstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - -

Date: -----

Page 9 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

40% power, BOl.

A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE:

You are the Reactor Operator. Respond to all alarms and indications.

Page 10 of 10 PSEG Restricted - Possession RE~quires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRA)1 JOB PERFORlV[ANCE MEASURE STATION: SALEM SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0100110101 JPM NUMBER: 11-01 NRC Sim f ALTERNATE PATH: KIA NUMBER: _ _ _ _ OO_7_A_4_._04_

IMPORTANCE FACTOR: ____ 2.~6--_

APPLICABILITY: RO SRO EOD ROm STAD SROm EVALUATION SETIING/METHOD: Simulator / Perform

REFERENCES:

S2.0P-SO.PZR-0003, Rev. 15 (checked 08-22-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08-22-12 Instructor Validated By: Br nnan Date: 08-24-12 SM or ~nstructo . .)

Approved By:

Training Departme t

'IJ./f"frvJ Date: 1/t{rL Approved By: B l A ( i3'-:1'"1 lLKoN e.. N \

o e~~partm~nt )

Date: 1/5) :l.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted-Possession Requires Specific Penrussion from Nuclear Training 10f7

OPERATOR TR.uNING PROGRAl'Vl JOB PERFOAAIANCE MEASURE NAME: ____________________________

DATE:

SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0450040101 SIMULATOR SETUP: IC- 256, PRT level 55.9% (or low enough for the PRT Hi-Lo Lvi alarm to be locked in) with PRT pressure 9.8 psig. Paper copies of procedure needed.

INITIAL CONDITIONS:

Unit 2 is at 100% power.

2PR1 is leaking and 2PR6 is shut with power applied. Operators have been attempting to determine the leak rate through 2PR1.

Console alarm PRT Level Hi-Lo is in alarm (10) with PRT level at 55.9%.

INITIATING CUE:

You are directed to raise PRT level to 60% lAW S2.0P-SO.PZR-0003, Pressurizer Relief Tank Operation, Section 5.1 .

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. Raise PRT level to > 57% while maintaining PRT pressure o pSig.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 2 of7

OPERATOR TRAINING PROGRAM NAME: ______________________

JOB PERIfORMANCli~ MEASURE DATE: _ _ _ _ _ _ _ _ _ __

SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure I

STEP NO.

STEP

(*Denotes a Critical Step) STANDARD EVAL stu COMMENTS (Required for UNSAT Evaluation)

I Provide marked up paper copy of S2.0P-SO.PZR-0003.

Reviews Precautions and Limitations. I 5.1.1 IF PRT level is low, THEN PERFORM the following:

Note: The step for reducing PRT pressure may be performed prior to raising level, II since pressure is close to the maximum allowed. (See Step 5.1.1.0)

I IF PRT pressure reduction is performed first, THEN Cue if PRT pressure is lowered past 7 psig ... " CRS states that the pressure reduction is sufficient to allow filling of the PRT now."

5.1.1.A IF required, THEN START 21 or 22 Primary Depresses start pushbutton for 22 Primary Water Pump. Water Pump. (aligned for manual start)

OR Places 21 Primary Water Pump in manual and depresses start pushbutton for 21 Primary Water Pump.

IF operator does not start a Primary Water Pump and will gravity feed to makeup to the PRT, THEN Cue: The CRS directs you to use a Primary Water pump to makeup to the PRT.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 3 of?

OPERATOR TRAINING PROGRAM NAME: _______________________

Jon PlmFORMANCE MEASURE DATE: _ _ _ _ _ _ _ _ _ _ _ __

SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure STEP STEP EVAL COMMENTS

NO. (*Denotes a Critical Step) STANDARD SJU (Required for UNSAT Evaluation)

5.1.1.8 OPEN 2WR80, CaNT PRI WATER STOP. Depresses open pushbutton for 2WR80 CaNT PRI WATER STOP and verifies open light lit.

5.1.1.C OPEN 2WR82, PRT WATER SUPPLY. Depresses open pushbutton for 2WR82, PRT WATER SUPPL Y and verifies open light lit.

5.1.1.0 IF PRT pressure approaches 10 psig, THEN Depresses open pushbutton for 2PR15, OPEN 2PR15, VENT, as necessary, to maintain VENT Qrior to PRT Qressure rising PRT pressure at >3 psig and ~10 psig. above 10.0 Qsig, and depresses close pushbutton prior to PRT pressure lowering below 3.1 psig.

Note: IF PRT Hi Pressure alarm is received, it prevents the 2PR15 from opening, and pressure cannot be reduced.

When candidate has demonstrated that they can raise level without exceeding 10 psig, then Cue: PRT level is now 60%

PSEG Restricted-Possession Requires Specific Pennission from Nuclear Training Page 4 of?

OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE: ____________________

SYSTEM: PZR and PRT TASK: Adjust PRT level and pressure STEP STEP EVAL COMMENTS

NO. (*Denotes a Critical Step) STANDARD S/U (Required for UNSAT Evaluation) 5.1.1.E When PRT level increases to between 59% and When PRT level rises to 60%:

86%:

Closes 2WR80, CONT PRI WATER

1. CLOSE 2WR80, CONT PRI WATER STOP.

STOP.

2. CLOSE 2WR82, PRT WATER SUPPLY Closes 2WR82, PRT WATER SUPPLY. . ,

3. ENSURE 2PR15, VENT is closed. Ensures 2PR15, VENT is closed.

4. IE Primary Water Pump is in service Depresses stop pushbutton for running lAW Step 5.1.1.A, AND is NOT required Primary Water Pump. IF 21 Primary to be in service for any other reason, Water pump 'v',fas used to fill PRT, THEN places 21 or 22 Primary Water pump in THEN STOP running Primary Water auto.

Pump.

5.1.1.F DIRECT a second Operator to perform an Independent Verification of component position in Attachment 1, Section 1.0 TERMINATING CUE: After candidate reads Step 5.1.1 state JPM is complete.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 5 of7

OPERATOR TRAINING PROGRAl"VI JOB PERFORi:VIA.L~CE 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.

Ij'J 1. Task description and number, JPM description and number are identified.

11 2. Knowledge and Abilities (KIA) references are included.

(j1. 3. Performance location specified. (in-plant, control room, or simulator)

-21_ 4. Initial setup conditions are identified,

_--1-_ _ 5. Initiating and terminating Cues are properly identified,

-+1>-><-- 6. Task standards identified and verified by SME review.

_...J.1?,--_7, Critical steps meet the criteria for critical steps and are identified with an asterisk (*),

_ . .9. 1,--_ 8, Verify the procedure referenced by this ,IPM matches the most current revision of that procedure: Procedure Rev, ~ Date f- 2. '1, 1 t

-'11--.- 9, Pilot test the JPM:

a. verify C'.J8S both verbal and visual are free of conflict, and

b. ens'JrE! perfurmance time is accurate.

4L-- 10@he ,!PM 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, Date: _--'-_:;.._<{_,_I"'-

Date: _ _ _ _ __

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 6 of7

OPERATOR TRAINING PROGRAM JOB PERFORl\lANCE MEASlJRE INITIAL CONDITIONS:

Unit 2 is at 100% power.

2PR1 is leaking and 2PR6 is shut with power applied. Operators have been attempting to determine the leak rate through 2PR1.

Console alarm PRT Level Hi-Lo is in alarm (10) with PRT level at 55.9%.

INITIATING CUE:

You are directed to raise PRT level to 60% lAW S2.0P-SO.PZR-0003, Pressurizer Relief Tank Operation, Section 5.1.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 7 of7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air TASK NUMBER: N 1140070401 JPM NUMBER: 11-01 ILOT Sim g ALTERNATE PATH: I X I KJA NUMBER: APE 065 AA2.06

~

IMPORTANCE FACTOR: 3.6 4.2 APPLICABILITY: RO SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AB.CA-0001, Rev. 17 Loss of Control Air

REFERENCES:

S2.0P-AR.ZZ-0011, Rev. 58, pages 118-128 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

Developed By: G Gauding Date: 8-4-12 Instructor Validated By: Brennan Date: 8-24-12 lU ln uctor Approved By: JI4~J Date: 1t~/r,-

Tr ' 109 D rtment V Approved By: ::t> t 1 ~~t /A!<JG,;Ju.J)

Ope~~'ns ~"pir1ment Date: r/s/t2 ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: __________________________

DATE: _____________________

SYSTEM: Loss of Control air TASK: TCAF Loss of Control Air TASK NUMBER: N1140070401 SIMULATOR SETUP:

IC-252 RT-1 MALF: CA0221 #2 STATION AIR CMPRSSR TRIP REM: CA13D LOCKOUT #1 STATION AIR CMPRSR, Delay 1:30 I/O : A001 OVLO COMP 1 TROUBLE ALARM, Fin Val: ON, Delay 1:30 Other setup:

REM: CA15D LOCKOUT #3 STATION AIR CMPRSR CA11 D #1 EMERGENCY AIR COMPRSR IN AUTO Fin Val: MANUAL 1/0 : A001 OVLO COMP 3 TROUBLE ALARM, Fin Val: ON INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

A WG release is in progress from 21 GDT.

#3 SAC is CIT for scheduled maintenance.

Unit 1 is operating at 100% power.

INITIATING CUE:

You are the Unit 2 Reactor Operator. Respond to all indications and alarms.

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. Isolate Letdown

2. Terminate Gaseous Release

3. Trip the Rx prior to auto trip on 10 10 SG NR level.

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OPERATOR TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air I

STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) I Note: The #1 and #3 Compressor Trouble alarms on 2CC1 do NOT have audible or flash capabilities (S2.0P-AR.ZZ-0011 page 120).

Simulator Operator: Insert RT-1 after operator assumes watch.

Determines #2 Station Air Compressor (SAC) has tripped, and the Unit 2 Emergency Control Air Compressor (ECAC) has automatically started.

Note: All 3 SAC supply breakers open is an auto start signal for both ECAC's. The Unit 2 ECAC will auto start, (Unit 1 will not). By design, the ECAC will not load until its control air header pressure lowers to 85 psig. 2A control air header is supplied from #2 ECAC, 2B control air header is supplied from #1 ECAC.

Note: The next-to-Ioad SAC (follow) will not immediately start. It requires Station Air header pressure to drop to 5 psig below the follow setpoint (105 psig) for - 5 seconds.

Refers to the S2.0P-AR.ZZ-0011, Control Console 2CC1, ARP for COMPR 2 TROUBLE.

--~

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OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

ARP 3.1 IF SAC 2 trips, THEN:

A. COORDINATE (as necessary) Coordinates with Unit 1 to start at least one with Unit 1 SAC lAW SC.OP-SO.SA-0001(Z), Station Air B. ENSURE operating OR START at System Operation.

least one SAC lAW SC.OP SO.SA-0001(Z), Station Air Cue when contacted as Unit 1: Unit 1 will System Operation. ensure #1 SAC is placed in service.

ARP 3.2 IF AT ANY TIME Station Air pressure GOES TO S2.0P-AB.CA-0001(Q), Loss of cannot be maintained ~100 psig, THEN Control Air, when Station Air pressure lowers GO TO S2. OP-AB.CA-OOO 1(Q), Loss of to 100 psig if AB not entered previously.

Control Air.

Simulator Operator: Ensure #1 SAC locks out 1:30 after insertion of RT-1, then announce twice on plant page: "#1 I

I Station Air Compressor Trip."

Recognizes that no SAC's are running, and enters S2.0P-AB.CA-0001 if not entered I

previously.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 13

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Note: Approximate event times are listed below from insertion of RT-1.

1 min - 1 SAC auto starts.

1 min 30 sec - 1 SAC trips.

3 min 50 sec 2 ECAC begins loading.

4 min 10 sec - 2B Control Air header pressure reaches 80 PSIG, and SA low pressure alarm.

4 min 25 sec - CA low pressure alarm.

6.5 min 24BF19 Feed Reg Valves begin closing.

7 min 10 sec - G-15 OHA ADFCS TRBL.

AB.CA INITIATE Attachment 1, Continuous Initiates Attachment 1, Continuous Action 3.1 Action Summary. Summary.

Cue IF Required: If CAS Step 8.0 action is being taken to refer to Attachment 2 for valve fail positions and for further action to be taken, then:

Cue: The CRS will refer to Attachment 2 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 13

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Loss of Control Air TASK" TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation) 3.2 Do either of the following conditions Determines all SAC's are stopped or exist? determines Station Air Header pressure is

All Station Air Compressors <100 psig.

stopped OR

Either Station Air Header <100 psig 3.3 IF a loss of 1F Group Bus has occurred, Determines a loss of 1F Group Bus has not AND 1H Group Bus is available, THEN occurred.

SEND an Operator to restore power to #1 SAC Auxiiiary Oil pump by transferring 1 i Cue if required: Unit 1 reports 1F Group Bus Turbine West 230V Control Center lAW is energized.

Attachment 14, Section 1.0.

I 3.4 IF a loss of 2F Group Bus has occurred, Determines a loss of 2F Group Bus has not AND 2H Group Bus is available, occurred.

THEN SEND an Operator to restore power to #2 SAC Auxiliary Oil pump by transferring 21 Turbine West 230V Control Center lAW Attachment 14, Section 2.0.

---- ---~ ------- ...... _ . _ - - ----- ----~

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 13

OPERATOR TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP EVAL (Required for UNSAT

(* Denotes a Critical Step)

NO. STANDARD S/U evaluation) 3.5 IF a loss of 1H Group Bus has occurred, Determines a loss of 1H Group Bus has not AND 1F Group Bus is available, occurred.

THEN SEND an Operator to restore power to #3 SAC Auxiliary Oil pump by Cue if required: Unit 1 reports 1H Group transferring 11 Turbine East 230V Bus is energized.

Control Center lAW Attachment 14, Section 3.0.

3.6 START or have Unit One Control Room Determines no SAC's are available.

START the Next to Load Station Air Compressor. Cue if required: If Unit 1 is contacted, report that #3 Station Air Compressor is tagged out and #1 Station Air Compressor has tripped, and that an operator has been dispatched to the Station Air Compressors.

3.7 Is either Station Air Header <100 psig? Determines both Station Air Headers are

<100 psig.

3.8 Attempt to START, or have Unit One Determines no SAC's can be started.

Control Room START, the remaining Station Air Compressor.

3.9 NOTIFY the SM/CRS to evaluate use of Cue: CRS will evaluate use of temporary air temporary air compressors. compressors.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 13

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 3.10 Is 2A Control Aii Header S88 psig? Determines 2A control air header pressure is:

3.11 S88 psig and determines #2 ECAC is in service OR

>88 psig.

3.12 Is 2B Control Air Header S88 psig? Determines 2B control air header pressure is:

3.13 S88 psig and contacts Unit 1 to place #1 ECAC in service OR

>88 psig.

Cue: When Unit 1 is contacted to start #1 ECAC, state: .. # 1 ECAC has tripped. "

3.14 SEND operators as necessary to: Dispatches operators to:

LOCATE AND ISOLATE any air

LOCATE AND ISOLATE any air system leaks. system leaks.

INVESTIGATE cause of air

INVESTIGATE cause of air compressor trip/trouble. compressor trip/trouble.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 13

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: -----------------

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 3.15 IF Station Air is lost, AND either of the Determines Station Air is lost, and neither of following are in service: the following are in service:

Spent Fuel Pool Transfer Pool

Spent Fuel Pool Transfer Pool Weir Weir Gate Seals Gate Seals

SG Nozzle Dams

SG Nozzle Dams THEN:

A. EVACUATE personnel from the areas subject to leakage/flooding.

B. INITIATE monitoring of Fuel Pool and/or Reactor Vessel levels for the need to makeup due to leakage.

3.16 IF cooling water to the Station or Determines cooling water to the Station or Emergency Air Compressors is lost, Emergency Air Compressors is not lost.

THEN INITIATE the applicable portion of Attachment 6, Abnormal Cooling Water Lineups.

3.17 Are both 2A and 2B Control Air Headers Determines both 2A and 2B Control Air

<80 psig? Headers are not <80 psig.

3.18 Is 2B Control Air Header <80 psig? Determines 28 Control Air Header is <80 psig.

3.55 CONTINUE PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 13

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Loss of Control Air TASK TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stu evaluation)

3.56 ISOLATE Letdown by closing the Isolates Letdown by closing the following following valves: valves:

A 2CV3, 45 GPM ORIFICE A 2CV3, 45 GPM ORIFICE B. 2CV4, 75 GPM ORIFICE B. 2CV4, 75 GPM ORIFICE C. 2CV5, 75 GPM ORIFICE C. 2CV5, 75 GPM ORIFICE D. 2CV2 D. 2CV2 2CV277 E. 2CV277 F. 2CV7 F. 2CV7 3.57 VERIFY any Liquid or Gaseous release is Determines 2WG41 , GAS DECAY TK TO

STOPPED by ensuring the following PLANT VENT is open, and shuts 2WG41 ,

valves are dosed: GAS DECAY TK TO PLANT VENT.

2WL51 , TO CIRC WTR DISCHARGE Verifies 2WL51 is shut.

2WG41 , GAS DECAY TK TO PLANT VENT CAS IF AT ANY TIME Station Air is lost, THEN:

INITIATE monitoring of 21 Identifies all BF19 valves closing.

24BF19 operation.

IF any BF19 goes CLOSED, Trips the Reactor.

AND the applicable SG water level cannot be maintained, THEN 'cUE IF REQUIRED: IE reactor is tripped TRIP the Reactor, CONTINUE prior to completion of steps 3.56 AND 3.57, with this procedure AND GO TO then allow immediate actions for the Rx trip 2-EOP-TRIP-1, Reactor Trip Or to be performed. THEN CUE: The CRS and Safety Injection. another RO will continue performing TRIP-i.

You are to continue performing AB.CA.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10 of 13

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ------------------

SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Terminate JPM once Rx has been tripped, Letdown isolated, and the WG release I I terminated.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 11 of 13

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.

--;:::it.-- 2. Knowledge and Abilities (KIA) refe!rences are included.

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

_..!l.;;,t.._ _ 4. Initial setup conditions are identified.

_ - L -_ _ 5. Initiating and terminating Cues are properly identified.

-.I.,}--- 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. ,7 Date ,8'.;2 y./ 'l,...

__rr' __ 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

_--,f-JL..!...-_10. If the .JPM cannot be performed as written with proper responses, then revise the JPM.

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

SME/lnstructor:_~;Jfr--"'-=-_?-. _ _A-,-,-/"_~:. .:.:~,- , - _ __ Date: __ 0_-_2._y_._/_l..---_

SMEllnstructor:~_ _~_ _ _ _ _ _ _ __ Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 12 of 13

INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

A WG release is in progress from 21 GOT.

#3 SAC is err for scheduled maintenance.

Unit 1 is operating at 100% power.

INITIATING CUE:

You are the Unit 2 Reactor Operator. Respond to all indications and alarms.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Pa~Je 13 of 13

OPERATOR TRAIN1NG PROGRAlVI JOB PERFORMANCE MEASURE STATION: Salem Generating Station SYSTEM: Radioactive Waste Liquid TASK: Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation with failure of 2WL51 to automatically shut.)

TASK NUMBER: N0685140104 JPM NUMBER: 11-01 NRC Sim h ALTERNATE PATH: I X I KIA NUMBER: 068 A4.03

~~~~----~

IMPORTANCE FACTOR: 3.9 3.8

::R=-c=---

APPLICABILITY: O SRO EOO ROm STAO SRO [KJ EVALUATION SETTING/METHOD: Simulator / Perform S2.0P-AB.RAO-0001, Rev. :29 (Rev checked 08-06-12) Abnormal Radiation S2.0P-SO.WL-0001, Rev. 25, (Rev checked 08-06-12) Release of Radioactive Liquid

REFERENCES:

Waster from 21 CVCS Monitor Tank TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Instructor Validated By:

Approved By: Date: 1 ! l-;f 'G Approved By: Date: q/511~

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

I EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Radioactive Waste Liquid TASK: Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System (and respond to High Radiation wi failure of WL51 to automatically shut.)

TASK NUMBER: N0685140104 SIMULATOR SETUP IC-258 Have S2.0P-SO.wL-0001 open on U desk.

MALF: RM0235C Process Rad Mon 2R18 fails anywhere (1 E5) tied to ET-3 with 30 second delay .

MALF: VL0305 2WL51 Fails to position (0-100%) tied to ET-3 with 5 second ramp.

ET-3 kao07pnu 2WL51 open PB ET-5 kao07tcu 2WL51 close PB (OMF VL0305)

INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

An authorized radioactive liquid release from 21 CVCS Monitor Tank through 21 CCHX to Unit 1 Circ Water is being aligned in the field. The RWO performing the release is currently beginning Step 5.5, Release of 21 CVCS MT via SW System to CW System.

INITIATING CUE:

You are the Unit 2 Reactor Operator. Respond to all indications and alarms.

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 opens 2WL51 to commence the Liquid Release.

2. Operator shuts 2WL51 after receipt of Hi Radiation Alarm on 2R18.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of9

OPERATOR TRAINING PROGRAM NAME:

DATE: _________________

JOB PERFORMANCE MEASURE SYSTEM: Waste Liquid STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation)

Note to Evaluator: The RWO has the official copy of the procedure in the field.

Evaluator: Initiate JPM by giving the following CUE:

Cue: This is the RWO. Open 2WL51 ,

Liquid Release Stop Valve lAW step 5.5.2 of S2.0P-SOWL-0001.

5.5.2 Direct Unit 2 NCO to OPEN 2WL51, LIQUID RELEASE STOP VALVE.

Depresses open pushbutton for 2WL51

LIQUID RELEASE STOP VALVE and verifies red open light illuminates.

Simulator Operator: Ensure ET-3 is TRUE when the operator depresses 2WL51 open PB. This inserts the 2R18 High Radiation condition after a 30 second delay.

Announces OHA A-6, RMS HI RAD OR TRBL, as unexpected, and refers to S2.0P AR.zZ-0001, Overhead Annunciators-Window A.

OR Checks CRT and reports CRT point 725,

(* If it RMS Hi Rad or Trbl-Liq Waste Disposal CH applies 2R18 in alarm, and after observing 2WL51 here) open, shuts 2WL51 using Step 5.5.9 of S2.0P-SO.WL-0001 or S2.0P-AR.ZZ-0001 for guidance.

L _____ ----_. -- ---_.- ---

PSEG Restricted Possession Requires Specific Permission from Nuclear Page 3 of9

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Waste Liquid TASK' Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System STEP COMMENTS STEP EVAL (Required for

(*Denotes a Critical Step) STANDARD

NO. StU UNSAT evaluation)

Evaluator Note: The 2WL51 status control should be maintained by the release procedure. Once the 2WL51 is shut, the Control Room operator must contact the RWO to inform them of the 2WL51 status.

!EJhe operator calls the RWO to report 2R18 status (on Panel 104) OR states that they would go to rack area of Control Room to verify 2R18 reading, THEN cue as follows as required:

Cue: The RWO reports 2R18 reading 1x105 cps.

Cue: The 2R18 in the rack area reads 5

1x10 cps.

Evaluator Note: lE the operator shuts the 2WL51 based on the Hi Radiation signal, without reporting which procedure directs the action, THEN allow the operator to continue until they justify their action based on procedure direction. Once the 2WL51 is shut, its status communicated to the RWO, and procedure direction for shutting the 2WL51 identified, terminate the JPM.

Evaluator Note: Steps for AB.RAD continue on next page.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of9

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Waste Liquid TASK' Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD stu UNSAT evaluation)

Checks CRT and reports CRT point 725, RMS Hi Rad or Trbl-Liq Waste Disposal CH 2R18 in alarm.

ARP IF 2R18 indicates Hi Radiation or trouble, Enters S2.0P-AB.RAD-0001, Abnormal 3.18 THEN GO TO S2,OP-AB.RAD-0001, Radiation.

Abnormal Radiation.

AB.RAD DETERMINE affected Radiation Monitor. Verifies 2R18 is the affected rad monitor.

3.1 ---

AB.RAD Is the alarm, warning, or rising indication valid? Determines alarm must be considered valid 3.2 (EVALUATE the following): since a radioactive liquid release has just

Chemistry Sampling commenced and the 2R18 is sampling that

Rising activity on related monitors release, and the monitor has been proven

Maintenance activities in vicinity of operable during performance of Attachment radiation detector 2, Section 2.3, which performed a source check on 2R18.

Transfer of radioactive resins or other materials in affected area

No indication of failure or fault on affected Radiation Monitor

Radioactive release from Salem or Hope Creek PSEG Restricted Possession Requires Specific Permission from Nuclear Training Page 5 of9

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Waste Liquid

" .. w .....

STEP COMMENTS STEP

("'Denotes a Critical Step) EVAL (Required for

NO. STANDARD stu UNSAT evaluation)

AB.RAD Announce the following on Plant PA system: Announces "Radiation Monitor 2R18 Liquid 3.6

Affected Radiation Monitor number Waste Disposal is in alarm, Auxiliary and name Building 84 elevation"

Location of Radiation Monitor area Note: Operator may also include 64' with elevated indication elevation.

AB.RAD IE a release to the environment is in progress, If the operator has NOT shut the 2WL51 ,

3.7 THEN DIRECT Shift Radiation Protection THEN the operator directs the Shift Technician (SRPT) to complete and provide Rndiation Protection Technician (SRPT) to Page 2 of the Station Status Checklist (SSCL) complete and provide Page 2 of the Station for release rate determination. Status Checklist (SSCL) for release rate determination.

Cue if required: IF required, state the CRS will contact the SRPT to complete page 2 of SSCL.

Note: This step may not be performed based on the operators knowledge of the ECG and that the SSCL looks at Gaseous Releases.

AB.RAD NOTIFY SM/CRS to REFER to Event Directs SM/CRS to refer to Event 3.8 Classification Guide, ODCM, and Technical Classification Guide, ODCM, and Technical Specifications. Specifications

-~~~~-~

i AB.RAD INITIATE the applicable attachment for Initiates Attachment 1 of S2.0P-AB.RAD 3.9 affected Radiation Monitor: 0001, Abnormal Radiation.

~~~~ ~ ~~~

---- ~-~

PSEG Restricted Possession Requires Specific Pennissiol1 from Nuclear Training Page 6 of9

OPERATOR TRAINING PROGRAM NAME:

SYSTEM: Waste liquid TASK" Perform an Authorized Release of Radioactive Liquid Waste to the Circulating Water System STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation)

AB.RAD IE 2R18, Liquid Waste Disposal, is the affected AU. 1 monitor, THEN:

5.0 5.1 ENSURE 2WL51 , TO CIRC WTR Shuts (or checks shut) 2WL51 , TO CIRC

(* If it DISCHARGE, is CLOSED to stop all WTR DISCHARGE applies Liquid Waste releases.

here) 5.2 TERMINATE Liquid Waste Release procedure in effect. Contacts RWO and directs them to terminate release procedure in effect.

Once the 2WL51 is shut, its status communicated to the RWO, and procedure direction for shutting the 2WL51 identified, terminate the JPM.

Terminating Cue: None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training 70f9

OPERATORTRAfrITNGPROGRAM JOB PERFORMAl'JCE 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.

--!.N1....:....Jl---_1. Task description and number, JPM description and number are identified.

--,-M~__ 2. Knowledge and Abilities (KIA) references are included.

--.!-.N'\...::..-l.f-_ 3. Performance location specified. (in-plant, control room, or simulator)

--!.M---:I----_4. Initial setup conditions are identified.

--,-N'\~-- 5. Initiating and terminating Cues are properly identified.

---J.~...!.....l,\--_6. Task standards identified and verified by 8ME review.

---iIt\,--+-._7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

---LN1-'-'r__ 8. Verify the procedure referenced by this JPM matcbes e most current revision of

, that procedure: Procedure Rev. ~ Date ~ cf3 I~

--<..m--\,,--_ 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

~ 10@:he .JPM cannot be performed as written with proper responses, then revise the JPM.

_ _ _ _ 11. When JPM is revalidated, 8ME or Instructor sign and date JPM cover page.

SM Ellnstructor:/!Ji .~ ...----N.}t,if!,{J.

8M E/lnstructor: Date: _ _ _ _ __

Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Pennission from Nuclear Training Page 80f9

OPERATOR TR.A.INING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

An authorized radioactive liquid release from 21 CVCS Monitor Tank through 21 CCHX to Unit 1 Circ Water is being aligned in the field. The RWO performing the release is currently beginning Step 5.5, Release of 21 cves MT via SW System to ew System.

INITIATING CUE:

You are the Unit 2 Reactor Operator. Respond to all indications and alarms.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

STATION: SALEM SYSTEM: CVCS TASK: Locally Borate the RCS TASK NUMBER: N1130140504 JPM NUMBER: 11-01 NRC IP-i ALTERNATE PATH: D KIA NU MBER: __A_P..............

EO .......6_8_AA_1........_____

08 --t IMPORTANCE FACTOR: 4.2 4.2 APPLICABILITY: RO SRO EOD RO((] STA C] SRO [ [ ]

EVALUATION SETTING/METHOD: Inplant Simulate

REFERENCES:

S1.0P-AB.CR-0001, Control Room Evacuation Rev. 17 (checked 8-6-12)

TOOLS AND EQUIPMENT: JAM key VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08-06*12 Instructor Validated By: Tait Date: 08-23-12 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: D SAT D UNSAT REASON. IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: CVCS TASK: Locally Borate the RCS TASK NUMBER: N1130140504 INITIAL CONDITIONS:

Unit 1control room was evacuated due to a security event.

The immediate actions of S1.0P-AB.CR-0001, Control Room Evacuation were completed successfully_

3 control rods remain withdrawn following the Rx trip.

1CV55 is in local manual controlling charging flow at 90 gpm.

Total RCP seal injection flow is 30 gpm.

INITIATING CUE:

You are the Reactor Operator.

Perform emergency boration for the stuck control rods lAW Attachment 5, Step 10, of S1.0P-AB.CR 0001.

Steps 1-9 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.

Task Standard for Successful Completion:

1. Locate panels 701-1A and 701-1 B for 11 and 12CV160.

2. Simulate establishing boration through 1CV175.

3. Simulate adjusting charging flow to 105 gpm.

Page 2 of 6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: CVCS TASK: locallv borate the RCS STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Provide copy of S1.0P-AB.CR-0001, Attachment 5.

10.0 WHEN directed by the CRS, THEN:

10.1 PROCEED to Unit 1 Cont Air Redundant Air locates Unit 1 Cont Air Redundant Supply Wall Mntd Pnl 701-1A, EI Air Supply Wall Mntd Pn1701-1A 122', near the Boric Acid Storage Tanks.

10.2 CLOSE the Air Supply Isolation Valve, locates and simulates closing the 11CV160 AlS, IR SUPPLY FOR 11CV160. Supply Isolation Valve, 11 CV160 AlS, IR SUPPLY FOR 11CV160.

10.3 OPEN draincock for control air regulator for Simulates opening draincock for 11 CV160. control air regulator for 11 CV160.

10.4 PROCEED to Unit 1 Cont Air Redundant Air locates Unit 1 Cont Air Redundant Supply Wall Mntd PnI701-1B, EI Air Supply Wall Mntd Pnl 701-1 B 122", near the Boric Acid Storage Tanks.

10.5 CLOSE the Air Supply Isolation Valve, locates and simulates closing the 12CV160 AlS, AIR SUPPLY FOR 12CV160. Supply Isolation Valve, 12CV160 AlS, IR SUPPLY FOR 12CV160.

10.6 OPEN draincock for control air regulator for locates and simulates closing the Air 12CV160. Supply Isolation Valve, 12CV160 AlS Page 30f6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: _________________

JOB PERFORMANCE MEASURE DATE: _________________

SYSTEM: CVCS TASK Locallv borate the RCS STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

10.7 OPEN 1CV175, Rapid Borate Stop Valve. Locates and discusses opening 1CV175, Rapid Borate Stop Valve by disengaging clutch and rorating handwheel.

10.8 PROCEED to 1CV55 and ADJUST the flow Locates Unit 1 CVC Chg for 75 gpm above existing total flow for all Pmps FL & PR Inst Pnl, Panel 216-1.

RCP seal flows.

Determines charging flow must be raised to 105 gpm.

Adjusts 1CV55 air signal to raise

.. charging flow .

i 11.0 REQUEST NEO#1 to adjust 1CV73 to maintain flow to RCP seals between 6 and 10 gpm.

12.0 NOTIFY the CRS that rapid Boration has Cue if Required: If charging flow is commenced. raised to 165 gpm (75 gpm above total charging flow), then when CRS is notified, state PZR level is rising quicker than it should be, and to ensure charging flow is adjusted to 75 gpm > Seal Injection flow.)

Adjusts charging flow to 105 gpm.

Terminate JPM. I Page 4 of6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

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 (KIA) 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/lnstructor:_ _ _ _ _ _ _ _ _ _ __ Date: - - - - - -

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ __ Date:

SMEllnstructor: Date: _ _ _ _ __

Page 5 of 6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 1 control room was evacuated due to a security event.

The immediate actions of S1.0P-AB.CR-0001, Control Room Evacuation were completed successfully.

3 control rods remain withdrawn following the Rx trip.

1CV55 is in local manual controlling char'ging flow at 90 gpm.

Total RCP seal injection flow is 30 gpm.

INITIATING CUE:

You are the Reactor Operator.

Perform emergency boration for the stuck control rods lAW Attachment 5, Step 10, of S1.0P-AB.CR 0001.

Steps 1-9 are complete.

Page 6 of 6 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Diesel Generator TASK: Start and synchronize an Em 43rgency Diesel Generator TASK NUMBER: 113001 0501 JPM NUMBER: 11-01 NRC IP-j ALTERNATE PATH: I I KIA NUMBER: _ _ _. .; .0. .; ,.64..;. . ;,.A.,; ; 2;,;. ;.0. .; ,9_ _ _-i IMPORTANCE FACTOR: 3.1 3.3 APPLICABILITY: RO SRO EOD ROm STAD SROm EVALUATION SETTING/METHOD: In Plant I Simulate

REFERENCES:

2A Diesel Generator Operation, S2.0P-SO.DG-0001(Q)Rev. 37 (checked 08-13-12)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 20 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08*13*12 Instructor Validated By: Rydell Date: 8*23*12 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 REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: EDG TASK: Start and synchronize an Emergency Diesel Generator TASK 113001 0501 NUMBER:

INITIAL Unit 2 is operating at 100% power, with no equipment OOS. Engineering has CONDITIONS:

requested a loaded run of 2A EDG.

INITIATING CUE:

The Unit 2 CRS has directed you to locally start and load 2A DIG lAW S2.0P-SO.DG-0001(Q),

Section 5.2. & 5.4 Prerequisites, Precautions and Limitations, and Section 5.1, Diesel Generator Startup Checks have been performed.

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:

Perform S2.0P-SO.DG-0001 Sections 5.2 and 5.4 in correct order and to completion.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _______________________

TASK: Locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT I

(*Denotes a Critical Step) S/U

NO. Evaluation)

Provide marked up copy of S2.0P SO.DG-0001 2A Diesel Generator Operation 5.2.1 NOTIFY NCO that 2A Diesel Generator is Locates nearest page.

to be locally started.

Cue: NCO acknowledges.

5.2.2 CHECK voltage permissive indicator light Points out voltage permissive indicator 2DAE4-LT2, EDG VOLTAGE, on light 2DAE4-LT2, EDG VOLTAGE, on Generator Control Panel is OFF Generator Control Panel.

r-----~~ -----

Cue: Light is off 5.2.3 CHECK speed permissive indicator light Points out speed permissive indicator 2DAE4-LT3, EDG SPEED, on Generator light 2DAE4-LT3, EDG SPEED, on Control Panel is OFF. Generator Control Panel.

Cue: Light is off

5.2.4 PLACE 2A-DF-GCP-1, 2A DIESEL GEN Points out 2A-DF-GCP-1, 2A DIESEL LOADING SW in MANUAL (DROOP). GEN LOADING SW., and simulates rotating to DROOP position.

Cue: Annunciator 8-9, Generator loading in Droop Mode annunciates.

5.2.5 ENSURE 8-9, GENERATOR LOADING Acknowledges alarm 8-9, Generator IN DROOP MODE, is in alarm. Loading in Droop Mode, and simulates depressing Silence PB.

Cue: Alarm 8-9, Generator Loading in Droop Mode has silenced.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: _________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) S/U

NO. Evaluation)

5.2.6 PLACE 2A-DF-SS, 2A DG STOP/ST ART Points out 2A-DF-SS, 2A DG SWITCH in START. STOP/START SWITCH, and simulates placing in START.

Cue: 2A Diesel is accelerating.

5.2.7 IF Diesel Generator Speed is NOT 900 rpm, THEN SET speed to 900 rpm using Cue when Speed indicator is the SPEED CONTROL SWITCH (GS). checked: Speed is 880 rpm.

Points out SPEED CONTROL SWITCH (GS) and simulates turning in RAISE direction.

Cue: 2A Diesel Speed is 900 rpm.

5.2.8 IF 2AD1AX6D*, 2A Diesel Generator 125VDC breaker is closed, THEN:

CHECK voltage permissive Points out voltage permissive indicator indicator light 2DAE4-LT2, EDG light 2DAE4-LT2, EDG VOLTAGE.

VOL T AGE, on Generator Control Panel is ON. Cue: Voltage permissive indicator light

CHECK speed permissive indicator 2DAE4-LT2, EDG VOLTAGE Light is on light 2DAE4-LT3, EDG SPEED, on Generator Control Panel is ON. Points out speed permissive indicator light 2DAE4-LT3, EDG SPEED Cue: Speed permissive indicator light 2DAE4-LT3, EDG SPEED light is on PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: ________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) StU

NO. Evaluation) 5.2.9 IF Field Ground Relay 64/G white indicating light is OFF, AND C-6, Points out Field Ground Relay 64/G GENERATOR FIELD GROUND, is clear, white indicating light.

THEN:

A. RESET 64/G relay Cue: Field Ground Relay 64/G white B. ENSURE 64/G white indicating indicating light is illuminated.

light is illuminated.

5.2.10 ENSURE 2A Diesel Generator K1C Field Points out 2A Diesel Generator K1C Flashing Relay Supervisory Light is OFF. Field Flashing Relay Supervisory Light Cue: 2A Diesel Generator K1C Field Flashing Relay Supervisory Light is off.

5.2.11 RECORD the following Diesel Generator Points out gages and switches to Start Readings: determine readings.

Cue when proper gauge is pointed out:

2VM189 Gen. Volts - 4160 Volts on all 3 phases 2FM 186 Gen. Frequency - 60 Hz 2PL6429 LO Hdr. Press - 80 psig 2PL6449 JW Hdr. Press - 45 psig 2PL7209 Air Manifold Press - 0 psig 2TA16524 Gen. Stator Temp - 187" PSEG Restricted Possession Requires Specific Permission from Nuclear Training Page 5 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) S/U

NO. Evaluation) 5.2.12 IF 2A Diesel Generator is to be operated Cue: Diesel will be parallel loaded.

unloaded for an extended period of time(>30 minutes), THEN INITIATE Section 5.7, Diesel Generator Running Checks.

5.2.13 IE Diesel Generator is to be parallel loaded, THEN INITIATE Section 5.4, Diesel Generator Parallel Loading.

5.4.1 IF Section 5.1 Diesel Generator Startup Verifies Section 5.1 is complete.

Checks, was NOT performed, THEN at 2A DG 4KV cabinet cubicle breaker 2AD1AX6D, PLACE selector switch 2A DG SYNC ENABLE in ENABLE.

5.4.2 NOTIFY NCO that 2A EDG is to be Cue: NCO acknowledges 2A DG is to synchronized and loaded locally. be synchronized and loaded locally.

i 5.4.3 ENSURE 2A-DF-GCP-1, 2A DIESEL GEN Verifies 2A-DF-GCP-1, 2A DIESEL LOADING SW, in MANUAL (DROOP) GEN LOADING SW, is in MANUAL (DROOP)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) Stu

NO. Evaluation)

5.4.4 ADJUST 2A EDG output voltage, as indicated on VOLTMETER-GEN (2VM189) When operator points out 2VM189 to 50 - 100 Volts higher than that of 2A and 2VM190, then Cue: 2VM189 reads 4KV Vital Bus voltage, as indicated by 4150, and 2VM190 reads 4150.

VOLTMETER-BUS (2VM190), using the VOL TAGE CONTROL SWITCH (VCS). Points out VOL TAGE CONTROL SWITCH (VCS) and simulates going to RAISE.

Cue: 2VM189 reads 4210, and 2VM190 reads 4150.

5.4.5 ENSURE generator terminal voltage is Points out VOLTMETER SWITCH -

present on all 3 phases by rotating GEN (VS-G), simulates rotating through VOL TMETER SWITCH - GEN (VS-G) each position, while observing 2VM189 through each position AND OBSERVING voltmeter 2VM189. Cue: Voltage is present on all three phases.

5.4.6 ENSURE 2A 4KV Vital Bus voltage is Points out VOLTMETER SWITCH -

present on all 3 phases by rotating BUS (VS-B), simulates rotating through VOLTMETER SWITCH - BUS (VS-B) each position, while observing 2VM190 through each position AND OBSERVING voltmeter 2VM190. Cue: Voltage is present on all three phases.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _________________________

TASK: locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) S/U

NO. Evaluation) 5.4.7 PLACE the following switches in "1-2": Points out VOL TMETER SWITCH GEN (VS-G) and VOLTMETER

VOLTMETER SWITCH - GEN (VS- SWITCH - BUS (VS-B)

G)

VOLTMETER SWITCH - BUS (VS B) Cue: Switches are in 1-2.

5.4.8 ENSURE 2DAE4-LT2. EDG Voltage Points out 2DAE4-LT2. EDG Voltage indication light is ON. indication light.

Cue: 2DAE4-LT2. EDG Voltage indication light is on.

5.4.9 ENSURE 2DAE4-L T3. EDG Speed Points out 2DAE4-LT3. EDG Speed indication light is ON. indication light.

Cue: 2DAE4-lT2. EDG Voltage indication light is on.

5.4.10 SYNCHRONIZE 2A Diesel Generator to 2A 4KV Vital Bus as follows:

A. PLACE 2A-DF-SYNCH, 2A DG SYNC SWITCH (SS) to ON. Points out 2A-DF-SYNCH, 2A DG SYNC SWITCH (SS), and simulates placing in ON position.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 8 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: ________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: _________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) StU

NO. Evaluation)

F COORDINATE the following when the synchroscope is at "12 o'clock" (+zero, -2 minutes):

1. CLOSE 2A-DF-GCP-3 Points out 2A-DF-GCP-3 GENERATOR GENERATOR CIRCUIT CIRCUIT BREAKER SWITCH (BCS)

BREAKER SWITCH (BCS) and simulates taking to the CLOSE position when the synch scope is at 12

2. RAISE 2A Diesel Generator load to o'clock.

=: 500KW using SPEED CONTROL SWITCH (GS) to prevent tripping Cue 2A Diesel Generator Breaker has the Diesel Generator Breaker on closed.

reverse power.

Points out SPEED CONTROL SWITCH (GS) simulates going to RAISE while observing KW meter.

Cue Load is 500 KW.

G PLACE 2A-DF-SYNCH, 2A DG SYNCH Points out 2A-DF-SYNCH, 2A DG SWITCH (SS) to OFF. SYNCH SWITCH (SS). and simulates placing it in OFF position.

Cue: JPM is complete.

PSEG Restricted - Possession Requires SpeCific Permission from Nuclear Training Page 10 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME: _________________________

TASK: Locally start and load an Emergency Diesel Generator DATE: ________________________

COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) S/U

NO. Evaluation)

8. ADJUST Diesel speed using the SPEED When operator points out CONTROL SWITCH (GS) such that synchroscope, then Cue: Scope is Synchroscope pointer rotates slowly in the going in the slow direction.

FAST (clockwise) direction.

Points out SPEED CONTROL SWITCH (GS)and simulates going to RAISE.

Cue Synchroscope pointer rotating slowly in the FAST direction.

C. ENSURE the following four SYNC CHECK Points out four SYNC CHECK RELAY RELAY 25 UPPER AND LOWER 25 UPPER AND LOWER VOLTAGE VOLTAGE LIMIT LEOS are ON. LIMIT LEOS.

"Upper Voltage Limit" "L OK" "8 OK" "Lower Voltage Limit" "L OK" "8 OK" Cue as each LED is located: Light is on.

D. IE the SYNC CHK RELAY 25 ~F OK LED Points out SYNC CHK RELAY 25 ~F is OFF, THEN ADJUST 2A Diesel OK LED.

Generator speed using the SPEED CONTROL SWITCH (GS) until the ~F OK Cue Light is on.

LED is ON.

E. ENSURE DG SYNC PERMISSIVE green indicating light is ON each time the Cue DG SYNC PERMISSIVE green synchroscope indicator is near 12 o'clock indicating light is ON each time the position (+/- approximately 3 minutes), synchroscope indicator is near 12 AND is OFF in any other position of the o'clock position (+/- approximately 3 synchroscope. minutes), AND is OFF in any other position of the synchroscope.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 12

OPERATORTRA~GPROGRAM 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 (KIA) 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 ~IPM.

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

SMEllnstructor: Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ _ _. Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 11 of 12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is operating at 100% power, with no equipment OOS. Engineering has requested a loaded run of 2A EDG.

INITIATING CUE:

The Unit 2 CRS has directed you to locally start and load 2A DIG lAW S2.0P-SO.DG-0001(Q), Section 5.2. & 5.4 Prerequisites, Precautions and Limitations, and Section 5.1, Diesel Generator Startup Checks have been performed.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 12 of 12

Operations Training Program Job Performance Measure STATION: SALEM SYSTEM: Control Air TASK: Perform Actions for a Loss of All AC Power (Start the SBO Compressor)

TASK NUMBER: N1150140501 JPM NUMBER: 11-01 NRC IP-j ALTERNATE PATH: KIA NUMBER: 2.1.23

~~~------~

IMPORTANCE FACTOR: 4.3 4.4

~PPLICABILlTY:

---::R=-O=--- SRO EOD ROW STAD SROW EVALUATION SETTING/METHOD: In Plant SC.OP-SO.CA-0001, SBO Diesel Control Air Compressor, Rev. 14 2-EOP-LOPA-1, Loss of All AC Power, Rev. 27

REFERENCES:

S2.0P-AB.LOOP-1, Loss of Off-Slite Power, Rev. 27 S2.0P-AB.CA-0001, Loss of Control Air, Rev. 17 DWG 604495 (Rev. 2) and 205347-2 Rev. 40 (H-6)

TOOLS AND EQUIPMENT: SBO Compressor Building is normally unlocked (L-3 key if locked)

VALIDATED ..IPM COMPLETION TIME: 12 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 08-13-12 Instructor Validated By: Date:

SME or Instructor Approved By: Date:

Training Department Approved By: Date:

Operations Department

~CTUAL ..IPM COMPLETION TIME:

~CTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: DAT [JJNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Perfc)rmance Measure SYSTEM: Control Air TASK: Perform Actions for a Loss of All AC Power (Start the SBO Compressor)

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) lAW SC.OP-SO.CA-0001. SBO Diesel Control Air Compressor. starting with Step 5.1.3.

The Component Off Normal and Off Normal Tagged review has been performed SAT.

It is NOT the summer operating period.

The inspection covers have already been removed. Step 5.1.1 was performed SAT. and the inspection covers replaced lAW Step 5.1.2 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 SC.OP-SO.CA-0001. SBO Diesel Control Air Compressor, SECTION 5.1 in the correct sequence which would result in SBO Compressor running supplying air through 1CA1913 SBO COMPRESSOR DISCHARGE VALVE, and 1CA1886 BLACKOUT AIR COMPRESSOR ISOLATION. and 2CA584 YARD CONTROL AIR SUPPLY VALVE to Aux Building headers 1A and 2A.

Page 2 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ____________________

TAS ... . _.. _...... _.. _.. - ._. - ---- _....... - . _.. _. ,_._..... -- - - ** '1"'" - - - - . I ...

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

Provide marked up copy of the SC.OP- Operator has and uses standard SO. CA-OOO 1, SBO Diesel Control Air personnel safety equipment. Dons Compressor with Prerequisites signed off. hardhat, safety glasses. Uses hearing Additionally, Step 5.1.1 for removing protection when entering high noise Inspection Covers will be previously areas that are posted as hearing completed, as will Step 5.1.2 to re-install protection required. Uses gloves when inspection covers. operating equipment or climbing.

Operator reviews and signs Precautions and Limitations, and performs P&L 3.10 as described in next step.

Operator must obtain hearing protection per P&L 3.1 All other P&Ls require no action other than reading and initialing with the exception of P&L 3.10 which will be performed at the SSO as identified below.

Operator proceeds to SBO Compressor Building.

Page 3 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ____________________

TAS ... & _ ** _ *** , ..._ ... _ . , _ I_I ______ *** ~ .... _. _ ... _ *._~_, ...... _ _

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU Evaluation)

P&L Ensure the Battery Tender has power by Operator observes the battery Tender 3.10 observing the Red and Green lamps on the GREEN light is illuminated, and the front. The placard next to the Battery RED light is not illuminated in the SBO Tender explains the Red and Green lamps building. (Green is a float charge on the and their significance. battery, Red (full charging current) would only be present after a discharge) 5.1.3 OPEN both Engine intake louvers (located Cue: After operator locates and outside building on west wall.) describes how to open Engine intake louvers, state that the Engine intake louvers are open.

5.1.4 OPEN 1CA 1920, BLACKOUT AIR Cue: After operator locates 1CA1920, COMPRESSOR DRAIN VALVE, to drain BLACKOUT AIR COMPRESSOR any water accumulation, then CLOSE DRAIN VALVE, and describes how to 1CA1920. open, including that the drain cap must be removed, state 1CA 1920, 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.

Page 4 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ____________________

TAS ... . .. ...... .. ..

~ ~ ~ ~ ~ .~. - -~~~ ~ ....... - . .. \_._ .....

~ ~. ~ --- -~ ... ,....~~~~ . .. .. -

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU Evaluation) 5.1.5 OPEN 2FZSB010, BATTERY CHARGER, Operator locates 2FZSB01 0, breaker. BATTERY CHARGER, breaker in Panel 2FZSBO, SBO Compressor Bldg Distribution Panel, and simulates opening.

Cue:2FZSB010,BATTERY CHARGER, breaker, is open.

5.1.6 PLACE SBO Control Air Dryer switch in Operator locates SBO Control Air Dryer ON position. switch 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 Operator locates Engine Hourmeter, Attachment 1, Section 1.0, and in log book 1XA16993, Tachometer/Hourmeter, at SBO compressor. inside engine control panel labeled Compressor Noise Emission Control Information, and records current reading in Section 1.0 of Att. 1.

Operator locates logbook hanging from side of panel 2FZSBO, SBO Compressor Bldg Distribution Panel, and identifies where Engine Hourmeter should be logged.

Page 5 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ____________________

TAS . -. ............ _.... -- .. - ._. ..... . . . . . . . . ._ ** u *** _

__ ..... ,_~ ...... _ _ ......._._ ...*. _._--'/ - - ..

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU Evaluation) 5.1.8 PLACE UNLOADER VALVE selector Operator locates UNLOADER VALVE switch in START position. selector switch, and ensures switch in START position.

Note: UNLOADER VALVE selector switch is normally in Start when engine is shutdown.

5.1.9 PRESS AND HOLD BY-PASS VALVE Operators locates BY-PASS VALVE pushbutton. pushbutton in control panel, and simulates depressing AND holding depressed.

I I I I Page 6 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ___________________

TAS ... I _11_.tll I '_"'_It_ ,_, ______ ~, "I I ,._. _-"_1 -,,-, " "'1 _ _ _ _ _ _ "11 ...... ____

_.... _

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

5.1.10 PLACE SBO-IGN-SWT, ENGINE While keeping the Bypass Valve IGNITION SWITCH in START position until pushbutton depressed, operator engine starts, then RELEASE to RUN simulates placing the SBO-IGN-SWT position. SBO Air Comp Inst Pnl Engine Ignition Switch in START.

Cue: Engine has started.

After cue is given, operator releases SBO-IGN-SWT SBO Air Comp Inst Pnl Engine Ignition Switch to RUN.

Note: If operator also releases the BYPASS VALVE pushbutton at this point, without checking oil pressure

>15 psig, then CUE that the engine has stopped.

5.1.11 When engine oil pressure is >15 psig. Operator identifies oil pressure reading RELEASE BY-PASS VALVE pushbutton. on gauge labeled oil pressure gauge inside control panel.

Cue: Oil pressure is 40 psig.

Operator releases BY-PASS VALVE pushbutton.

Page 7 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ___________________

TAS - --

_. ,._ **** ~ _ _ .... _ .............. -" ____ ** u ***

~ ._ ... _. _................ - - - - .. 'r""----. ........

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation) 5.1.12 ALLOW engine to run for 5 minutes to Cue: 5 minutes has elapsed.

warm up.

5.1.13 OPEN 1CA1913 SBO COMPRESSOR Operator locates and describes opening DISCHARGE VALVE, to pressurize Control 1CA 1913 SBO COMPRESSOR Air header. DISCHARGE VALVE Cue: 1CA 1913 SBO COMPRESSOR DISCHARGE VALVE, is open.

5.1.14 OPEN 1CA 1886, BLACKOUT AIR Operator locates and describes opening COMPRESSOR ISOLATION. 1CA1886, BLACKOUT AIR COMPRESSOR ISOLATION.

Note: 1CA 1886 is located near the entrance to Service Building on right side past the U2 mixing bottle Cue: 1CA 1886, BLACKOUT AIR COMPRESSOR ISOLATION is open_

L~~~~ --- ~-~

Page 8 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Operations Training Program Job Performance Measure SYSTEM: Control Air NAME: ____________________

TAS -.- . -' ._ ..... '-"-"- ._. - --- _...... '- . ----' ,_._ .. - --- -"'r-" ----. _..... .

STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

5.1.15 OPEN 2CA584, YARD CONTROL AIR Operator locates and describes opening SUPPLY VALVE, to pressurize Aux. 2CA584, YARD CONTROL AIR Building 1A and 2A Control Air headers. SUPPLY VALVE.

Note: 2CA584 is located near the entrance to Service Building on right side past the U2 mixing bottle.

Cue: 2CA584, YARD CONTROL AIR SUPPLY VALVE is open.

5.1.16 PLACE UNLOADER VALVE selector Operator returns to S80 Compressor switch in RUN position. Building and points out UNLOADER VALVE selector switch describes placing it in RUN position.

Cue: JPM is complete.

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JOB PERFOR"IANCE 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 (KIA) 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/lnstructor: Date:

SME/lnstructor: Date: _______

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _________

INITIAL CONDITIONS:

Page 10 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE 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) lAW SC.OP SO.CA-0001, SBO Diesel Control Air Compressor, starting with Step 5.1.3.

The Component Off Normal and Off Normal Tagged review has been performed SAT.

It is NOT the summer operating period.

The inspection covers have already been removed, Step 5.1.1 was performed SAT, and the inspection covers replaced lAW Step 5.1.2 Page 11 of 11 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 11-01 NRC Examiners: Operators:

Initial Conditions: 100% power, EOL. PZR Pressure channel II is O/S for calibration.

Turnover: Maintain current power. Perform 1ST Room Cooler Valves Modes 1-6 lAW S2.0P-ST.SW 0014.

Event Malf. No. Event No.

Event Type*

Description I

1 I N CRS/PO Safety Related Room cooler surveillance (TS) 2 SGOO95A I SG NR Ch failure (TS)

TA0314 R,C 3

RD0061 ALL Stator Water runback wi subsequent auto rod control failure I

C 4 O/R CF12 MS10 failure in automatic CRS/PO I RP0176A 5 M Inadvertent SI, 2C 4KV vital bus UV following Rx trip, C812!C809 ALL LBLOCA RCOOO1 6 C RP318A1,2 Lo Head ECCS fails to actuate ALL 7 C RP0277A,B CS fails to actuate CRS RO i

C 8 CV62B Chargin!~ pump cavitation RO CT's: Init Cont Spray, initiate Lo head ECCS, xfer to CLR, trip cavitatin~ charging pp.

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)ajor Appendix 0, Page 38 of 39

TQ-AA-106-0204 Page 1 of 37 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 11-01 NRC ESG-1 SCENARIO NUMBER: 11-01 NRC ESG-1 EFFECTIVE DATE: See Approval Dates below EXPECTED DURATION: 70 minutes REVISION NUMBER: 01 PROGRAM: ' - - _........

L.O. REQUAL X : INITIAL LICENSE

'--_.. . . .I STA OTHER Revision Summary New issue for 09-01 NRC Exam (Spare Scenario not used)

Rev. 01 - Modified to SBT format.

PREPARED BY: G Gauding 08-4-12 ulatory EX/,Author Date APPROVED BY: bJ~(L~J}

perations Training-Manager 7 qltL/r Date o

APPROVED BY:

~ ~~'FacnT~~u;t~"-~AJ'j e r~sentative r/c,!t~

odie PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 2 of 37 A. Given the unit with a condition requiring a stator water runback, the crew will take action to verify or perform the actions needed for the runback, lAW approved station procedures.

B. Given a situation requiring rapid boration, the crew will initiate a rapid boration and terminate when required lAW approved station procedures.

C. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

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 safety injection DIRECT the response to the safety injection 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 a safety injection has occurred and equipment has failed to START equipment that has failed to automatically start in accordance with the approved station procedures.

H. Given indication of a loss of coolant accident (LOCA) DIRECT the immediate response to the LOCA in accordance with the approved station procedures.

I. 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 procedufi8s.

J. Given a loss of coolant accident (LOCA) and plant conditions to support cold leg recirculation DI RECT actions to transfer to cold leg recirculation DIRECT actions to transfer to cold leg recirculation.

K. Given the order or a loss of coolant accident (LOCA) and plant conditions to support cold leg recirculation perform actions as the nuclear control operator to TRANSFER to cold leg recirculation in accordance with the approved station procedures.

L. Given indication of excessive contelinment pressure DIRECT the response to the excessive pressure in accordance with the approved station procedures.

R. Given the order or indications of excessive containment pressure perform actions as the nuclear control operator to RESPOND to the excessive pressure in accordance with the approved station procedures.

S. Given the unit in the EOPs and an excessive containment pressure the crew will reduce containment pressure lAW approve station procedures.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 P e 3 of 37 A. Room cooler surveillance unsat B. 21 SG Ch II NR level fails high.

C. Automatic Stator Water Runback D. MS10 failure E. lBlOCA A. The crew will take the turnover at 100% power, EOl. I&C is performing a channel calibration of PZR Pressure Channel II. 2PR7 is shut with power removed to comply with TSAS 3.4.5.b. All bistables associated with PZR Pressure Channel" are tripped lAW S2.IC.

CC.RCP-0018, 2PT-456 Pressurizer Pressure Protection Channel II. Orders for the shift are to complete 1ST of Room Cooler valves (RHR pump room coolers) lAW S2.0P-ST.SW 0014, Inservice Testing Room CoolE)r Valves Modes 1-6 for the RHR pump room coole"rs.

Maintain 100% power.

S. After assuming the watch, the crew will test the RHR pump room coolers. The 21SW153 room cooler SW valve stroke time will be in the Required Evaluation Range. The CRS will either declare the valve inoperable, or retest the valve as called for in the procedure. If a second test is performed, the stroke time will fall in the Required Action Range, and the CRS will declare the valve inoperable. lAW S2.0P-SO.SW-0005, Service Water System Operation, the RHR pump must be declared inoperable when its room cooler is inoperable.

(page 104). The CRS enters TS 3.5.2 for only 1 train of ECCS.

C. After completing the surveillance, 21 SG NR level Ch. II fails high. The crew will verify no ADFCS malfunction and the CRS will enter the appropriate Tech Spec.

D. A Stator Water Main Turbine runback will initiate and the runback wi" terminate at -900 Mwe when the initiating condition clears. Control Rod speed fails to minimum, and operators will place Rod control in manual to insert rods. Operators will ensure positive control of the Main Turbine and borate the RCS in conjunction with rod insertion to restore Tavg and AFD.

E. Once the plant has been stabilized, 21 MS1 0 fails - 33% open in auto. The PO will take manual control and shut 21MS10.

F. A false Safety Injection signal is generated, and the Rx automatically trips. Operators will backup the Rx trip and Safety Injection actuation.

G. 2C 4KV Vital bus will deenergize upon the Rx trip, and the SEC will load 2C vital bus on its EDG. 21 CCW pump will trip, and 23 CCW pump control wi" transfer and remain in manual.

22 charging pump will not start on SEC initiation, and operators will block the SEC and start 22 charging pump. A lBlOCA occurs 5 minutes after the Rx trips. Automatic Phase Band Containment Spray will not occur, and operators will manually initiate Cont Spray and manually start Containment Spray pumps. Operators will perform diagnostics in TRIP-1 and transition to lOCA-1. 21 charging pump will trip 15 minutes after the Rx trip.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 4 of 37 H. The crew will transition to LOCA-3 when RWST level reaches 15.2 ft. The crew will perform the transfer to CL Recirc with all 4KV vital busses energized and 2C bus energized from its EDG. During the transfer, 22 charging pump will cavitate when 2SJ1 and 2SJ2 are shut, and operators will stop the pump. If the pump is not stopped, it will fail, and a LOCA outside containment will occur.

I. The scenario will terminate when 22 charging pump is tripped, or after indications of CVCS system piping failure have occurred if the pump was not secured.

IC-3 or Pre-snapped IC-241 Initial I Description 1 RH 1 and RH2 CIT 2 RH18s CIT 3 VC1 and VC4 CIT 4 RCPs (SELF CHECK)

_ 5 RTBs (SELF CHECK)

_ 6 MS167s (SELF CHECK)

_ 7 500 KV SWYD (SELF CHECK)

_ 8 SGFP Trip (SELF CHECK)

_ 9 23 CV PP (SELF CHECK) 10 OHA G-20 in alarm.

_ 11 2PR7 shut and deenergized.

12 S2.1C-CC-RCP-0018, 2PT-456 Pressurizer Pressure Protection Channell!, Exhibit 1 signed and on NCO desk or provided to crew for turnover.

13 Marked up S2.0P-ST.SW-0014, Inservice Testing Room Cooler Valves Modes 1-6 and S2.RA-ST.SW-0014 Rev. 29, Acceptance Criteria, provided to crew with turnover.

_14 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 5 of 37 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group MONP254 <10 /1 CONT ROD BANK C < 10 (RX TRIP) 1 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: gbc18axd < 0.851 II (205) CONTROL ROD POSITION 3 COMMAND: DMF TA0314 PURPOSE: <update as needed>

EVENT ACTION: kb117lck II 2SJ2 RWST TO CHG PUMP CLOSE 5 COMMAND:

PURPOSE: <update as needed>,

EVENT ACTION: MONP254 <10 CONT ROD BANK C < 10 ( RX TRIP) 7 COMMAND:

PURPOSE: <update as needed>

~---~----~----~~~.

EVENT ACTION: 1 > 0.2//21 MS1 0 11 COMMAND: DOR KCF12LW1 PURPOSE: <update as needed>

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TQ-AA-106-0204 Page 6 of 37 SERPOINT AN0302 SER 302 FAILS - :E35 2PR2 PROTECTION 01 NJA NiA NfA FAllSfOVRD CH II LOOP UNSAFEflN TEST TO ON SERPOINT 02 Nil" NfA N/A FAIlSfOVRD TO ON 03 N/A 04 21 SG lVlXMTR CH II FAll NiA 120 05 06 07 08 09 10 N!A 550 N!A SERPOINT AN0289 SER 289 FAILS -:H45 GENERATOR 12 NJA N!A RT-11 FAllS/OVRD STATOR COOLING SYSTEM TROUBLE TO OFF RM0210B1 AREA RAD MONITOR 2R4 FAilS 13 00:00:30 RT-9 15 ANYWHERE SERPOINT RMS HI RAD OR TRBl 14 00:00:30 N/A N/A RT-9 FAIlSfOVRD 15 16 17 SERPOINT 18 NfA N1A N/A FAllSfOVRD TO ON 19 N!A N!A 8 20 NIA N/A N!A RT-7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 Page 7 of 37 SELF CHECK 01 PR02D PZR HI PR RX TRP CH 2PC456A BS N!A 02 PR13D PZR LO PR BLKSI CH 2 PC4568 BS NfA 03 NlA 04 NiA 05 N/A 06 N/A N/A TRIP 07 Nil\' NjA TAGGED 08 N!A ET*5 .000045 Value 01 Nj,A, ET*7 02 N/A NiA N/A ET-7 03 NiA N1A N!A 04 Nil, ~j!A

~j?",\ ET-7 05 N/A N!A ET-7 06 N/A N!A RT-5

1. PZR Pressure Channel IV selected for Alarm PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 8 of 37 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 9 of 37

1. Valve surveillance with Unsat result CRS directs PO to commence testing of 21 RHR plJmp room cooler.

I PO records asfound position (auto

. cooler on Attachment 2.

PO contacts field operators for performance of valve stroke time monitoring.

PO and field ooerators test 21SW153.

Role Play: Report after the room cooler is started that the 21SW153 stroke time was 5.2 seconds.

PO reports stroke time is in the Required Evaluation Ranae.

! CRS either directs valve to be retested, or

~Iares valve _-'-_ __

Role Play: If PO retests 21SW153, report stroke time is 5.7 seconds After the second stroke time test is performed, CRS declares the 2SW153 inoperable if not already done.

CRS declares 21 RHR pump inoperable, and enters TSAS 3.5.2 for less than 2 full ECCS trains.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 10 of 37 Note: S2.0P-SO.SW-0001, Service Water System Operation, , SW System Operability Guidelines, page 104 discusses RHR Pump Room Cooler and RHR pump operability.

Proceed to next event on direction from Lead Evaluator.

2. 21 SG NR level Channel II fails high PO announces OHA G-15 ADFCS Trouble, and 21 SG Isolation Level Hi-Hi console alarf!ls as unexpected.

PO identifies 21 SG NR level CH 11 has failed h.

PO verifies all ADFCS parameters are normal and still beinq controlled in automatic.

CRS contacts I&C or WCC and informs them of channel failure.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 11 of 37 CRS enters TSAS 3.3.1.1 Action 6, and 3.3.2.1 action b 19.

Proceed to next event after Tech Spec call at direction of Lead Evaluator.

3. Stator Water Runback PO announces OHA's H-38 GEN STAT RUNBACK, and H-45 GEN STAT CLG SYS TRBL as u RO monitors primary plant and ensures control rods start stepping inward in auto when demanded due to power mismatch and Tref Tava deviation OR inserts rods if in Manual.

Note: The was Initiated at PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 12 of 37 30% per minute, but the Main Turbine Governor valves respond slower than that. When the load reduction signal clears, the DEHC reference will stop changing. but the turbine governor valves will still be closing, and Mwe will lower another -100 before reference equals actual.

RO reports control rod speed is not consistent with temperature and power deviation, and receives permission from CRS to place control rods in RO inserts control rods in manual to maintain Tavg-Tref mismatch in the band given by CRS.

PO starts standby Stator Cooling Water pump IAWARP.

CRS dispatches an operator to the Stator Water Panel 968 to investigate and determine nel alarm status lAW Role Play: 5 minutes after being dispatched, insert RT-11 which will clear OHA H-45. Then call control room as NEO and report:

Panel 968 alarm A-1 L, Inlet Flow Low was flashing, but cleared when I acknowledged it. Inlet flow is PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ~AA~1 06-0204 13 of 37 reading 600 gpm. There are currently NO alarms on the panel.

PO verifies that when OHA H-38 clears, the DEHC ref}rence stops loweri IF OHA E-16 ROD INSERT LMT LO-LO annunciates, THEN RO/PO initiates Emergency Boration lAW S2.0P-SO.CVC 0008 as directed by ARP by:

Determining that there is no set time duration for the boration per step 5.1.1.

Starts at least one Boric Acid Transfer pump in FAST speed.

Ensures charging flow is > 75 gpm.

Opens 2CV175 Rapid Borate Stop Valve Closes 21 and 22CV160. Recirc Vlvs Ensures boric acid flow is >36 gpm on 2FI-113A.

- Ensures charging flow is >75 gpm on 2FI-128B

- Starts at least one Boric Acid Transfer pump in FAST speed.

- Ensures the 2CV179 and 2CV181 shut.

- Manually open 2CV172.

- Open 2CV185.

- Close 2CV160 and 2CV161.

- Ensure Boric Acid flow >36gpm on 2FI 110A.

Note: Emergency Boration is to continue until control rods are at least 2 steps higher than the RIL, PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 14 of 37 CRS enters S2.0P-AB.LOAO-0001, Rapid Load Reduction.

emergency boration was initiated, THEN WHEN OHA E-16 clears, RO stops the emergency boration by:

Stopping the Boric Acid Transfer pump started above Closing the 2CV175 Throttling open 21 and 22CV160 as required.

- Place the running Boric ,f..,cid pump in Slow Speed.

Close the 2CV172 and 2CV185.

Return the CVCS Makeup system to AUTO.

Throttle open 2CV160 and 2CV161.

CRS enters. .. . ... _.. _.. _u_ --- -.. ------1 Proceed to next event on direction from Lead Evaluator.

4. MS10 failure PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 15 of 37 PO either places 21 MS10 in manual and shuts valve or raises steam pressure setpoint so that valve resoonds and shuts.

CRS enters S2.0P-AB.STM-0001, Excessive Steam Flow.

Proceed to next event once 21 MS 10 is shut OR if crew trips Rx.

5. LBLOCA PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 16 of 37 RO performs TRIP-1 immediate actions from memory:

- Verifies Rx tripped Verifies Rx trip confirmed

- Trips the Main Turbine

- Verifies at least one 4KV vital bus energized.

- Reports Safety Injection actuated and backs up SI.

CRS reads immediate action steps to RO and RO verifies performance.

RO/PO reports 2C 4KV vital bus is energized from 2C EDG.

RO reports 22 charging pump, 21 and 22 RHR pumps failed to start.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 17 of 37 Crew blocks ALL SECs on 2RP1. --------------

Crew resets Emergency loading on ALL S ___:::::.~_ _ _--I

6. Lo Head ECCS fails to actuate RO starts 22 Charging 21 RHR pump, and 22 RHR 2 Rx PO reports all AFW pumps running, and requests permission to throttle AFW flow while maintaining 22E4 Ibm/hr or 9% level in at least one SG NR level.

PO lowers 23 AFW pump speed to minimum, and throttles 21-24AF21's to maintain AFW flow - 22E4 Ibm/hr.

RO/PO identifies that a LBLOCA has occurred control board indications.

7. Containment Spray fails to actuate.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 18 of 37 RO reports control console indication of Containment Spray and Phase B actuation, no Containment Spray system components have actuated.

CRS refers/returns to Step 11 and directs RO initiate Containment Spray by:

Initiate phase B and Spray actuation.

- RO inserts BOTH keys into CS actuation and turns at same time.

- RO reports spray valve realignment.

Start 21 and 22 CS pumps

- RO inserts key and turns for 21 and 22 CS pumps and reports both CS pumps are running.

- Initiate MSLI RO reports MSLI initiated,

- Stop 21-24 RCPs

- RO depresses stop PB for all RCPs.

- Ensure valve groups in Table 0 in safeguards position.

PO reports all Table D valves in safeguards position.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA*106*0204 19 of 37 PO reports all 3 4KV vital busses are energized with 2C 4KV vital bus energized from 2C EDG.

RO reports control room ventilation is in Accident Pressurized mode.

RO reports 2 swgr supply and 1 swgr exhaust fans are runnill9-=-._ _ _ _ _ _ _ _ _ _----"

PO reports only 22 CCW pump is running.

Note: The PO should NOT attempt to start 23 CCW pump here, since 2C vital 4kv bus is powered from the EDG and there is no direction in TRIP-1 to start the second CCW pump. IF the PO attempts to start 23 CCW pump, it will neither start nor backflash due to scenario setup override.

CRS dispatches an operator to shut 2CC37 and 2CC48.

CREW performs ECCS flow evaluation and determines all ECCS pumps are injecting to RCS Eis expected for LBLOCA and cont prE!!)!)-"--l m PO reports AFW status and is maintaining 22E4 Ibm/hr or 15% (adverse cont numbers in effect) level in at least one SG NR level, then maintainina 15-33%.

RQE~ports all RCPs are PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 20 of 37 RO ensures seal injection flow is maintained to all RCPs.

PO reports there are no faulted or ruptured SGs.

Note: All SG pressures will be dropping due to the LBLOCA with 21 SG pressure lower than the

_ 3 SGs due to the RCS rupture being on that loop.

CRS transitions to LOCA-1 on containment radiation levels.

Note: STA will report to the control room 10 minutes after being paged and begin monitoring CFSTs.

Note: 21 charging pump trip 15 after the Rx

?1<:;~Clming Note: Upon the transition out of TRIP-1, CFST monitoring becomes PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 21 of 37 active.

STA identifies that a PURPLE path exists on both the Thermal Shock and Containment Environment Critical Function Status Trees.

CRS transitions to FRTS-1 based on RCS cool down rate and Table A conditions.

STA identifies a PURPLE path still exists for Containment Environment (if containment ressure remains above 15 Note: Depending on scenario timing) the FRCE Purple path may have cleared, and will clear

-15 minutes of LBLOCA initi<>tin CRS transitions to FRCE-1 based on PURPLE PCltbJQrcontCliQment Environment. ... _ _ _--j-RO verifies actions previously performed:

CFCUs running in low speed with properSW RCPs stopped Both CS pumps running.

Containment isolations MSLI No faulted SGs.

S transitions back~~~~------

to LOCA-1.

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TQ-AA-106*0204 22 of 37 PO reports AFW status and is maintaining 22E41bm/hr or 15% (adverse cont numbers in effect) level in at least one SG NR level. then 15-33%.

RO resets SGBD Sample Isolation Bypass and ODens21-24SS94s, CRS directs chemistry to sample SGs for boroni31J9c-a'--c'-'tl_'v-..:.ity'-,_ _ _ _ _ _ _ _ _ _-+

RO reports both PORVs shut with 2PR6 open and 2ER7 shut with power reITJ()ve_d_,- - - - I -

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TQ-AA-106-0204 Paae 23 of 37 CRS requests assistance from TSC to restore off-site Dower to 2C 4KV vital bus.

RO reports both RHR pumps and both SJ44s are available.

RO/PO reports no rad monitors in Table Care in warnina or alarm.

CRS directs chemistry to sample the RCS and analyze for failed fuel and boron. -----l---~

CRS consults TSC about equipment availabilitv to assist in lona term recove CRS verifies operators were dispatched in TRIP-1 to shut 2CC37 and 2CC48.

If the crew arrives at Step 18.2 prior to RWST level of 15.2', they will enter a "do loop" with return to step 16. When RWST 10 level alarm actuates, continue below.

RO reports RWST 10 level alarm as expected alarm.

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TQ-AA-106-0204 Paae 24 of 37 Log time of RWST LO-LO level alarm for CT#2 evaluation.

RO reports both Cont Sump Level >62% are lit.

RO depresses Sump Auto Armed PBs for 21 and 22SJ44.

PO removes lockouts for 2SJ67, 2SJ68 and RO reports both RHR pumps are running and shuts LOG TIME 2SJ69 Close is initiated:

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TQ-AA-106-0204 Paae 25 of 37 LOG TIME Containment Spray pump stopped:

230V load centers are re CS pumps are operating and PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 26 of 37 CRS selects step 11 as the correct flowpath transition.

PO reports C bus is energized from its EDG.

LOG TIME ECCS Pumps verified running:

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TQ*AA*106*0204 Paae 27 of 37

8. Charging pump caviatation RO/PO recognizes 22 charging pump is cavitating by amperage indication, discharge flow and BIT flow, and discharge pressure oscillations.

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TQ-AA-106-0204 Paae 28 of 37 TERMINATE the scenario when 22 charging pump has been secured, whether by operator action or when it trips 7 minutes after cavitating starts.

RO places 21 and 22RH29 controllers in Manual and ensures valves are shut.

Note: Some of the following steps may be performed depending on when, or if, the crew recognizes the 22 charging pump cavitation, and should be evaluated accordingly.

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TQ-AA-106-0204 29 of 37 CRS dispatches operator to tag SJ44 breakers PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 30 of 37 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-LOCA-1 Loss of Coolant Accident G. 2-EOP-LOCA-3 Transfer to Cold Leg Recirculation H. S2.0P-AB.LOAD-0001 Rapid Load Reduction I. S2.0P-AB.RC-0001 Reactor Coolant System Leak J. S2.0P-ST.SW-0014, 1ST Room Cooler Valves Modes 1-6 K. S2.RA-ST.SW-0014, 1ST Room Cooler Valves Modes 1-6 Acceptance Criteria L. S2.0P-SO.SW-0005, Service Water System Operation PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204

- - /,iATTAcHMENT1'*

C L1Nlf TWO PL.ANT STATUS> .

TODAY MODE: 1 POWER: 100 RCS BORON: 100 MWe 1200 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS Core Burnup: 12,600 EFPH MOST LIMITING LCO AND DATEITIME OF EXPIRATION:

3.4.5 action b for PZR Pressure Channel II calibration. 70 hours2.917 days 0.417 weeks 0.0959 months left in action time.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

S2.IC-CC-RCP-0018, 2PT-456 Pressurizer Pressure Protection Channel II.

S2.0P-ST.SW-0014, Inservice Testin\~ Room Cooler Valves Modes 1-6. 21 RHR pump room cooler is to be tested upon assuming the watch. All other room coolers have been tested SAT. 2 NEOs are stationed at 21 RHR pump room to allow coordination of testing via the plant page system.

ABNORMAL PLANT CONFIGURATIONS:

2PR7 shut and power removed to comply with TSAS 3.4.5.b for PZR Pressure Channel II being out of service for channel calibration.

PZR Pressure Channel IV selected for Alarm.

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

3.3.1.1 action 6 and 3.3.2.1 action 19 for PZR Pressure Channell! PT-456.

SECONDARY:

OHA G-20 SEAL CVL HTG STM SYS TRBL is in alarm due to Gland Sealing Steam high pressure. NEO is investigating.

Heating steam is aligned to Unit 1.

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

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 aHA lamps operating (aHA 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 ReS 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.

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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 individual's 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.

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TQ-AA-106-0204 SCENARIO IDENTIFIER: 11-01 NRC-ESG-1 REVIEWER: E Gallagher Initials Qualitative Attributes EG 1. The scenario has clearly stated objectives in the scenario.

EG 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.

EG 3. The scenario consists mostly of related events.

EG 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 EG 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.

EG 6. The events are valid with regard to physics and thermodynamics.

EG 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

EG B. The simulator modeling is not altered.

EG 9. All crew competencies can be evaluated.

EG 10. The scenario has been validated.

EG 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.

EG 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

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TQaAA-106-0204 Note: The quantitative attribute target ranges that are specified on the form are not absolute limitations; some scenarios may be an excellent evaluation tool, but may not fit within the ranges. A scenario that does not fit into these ranges shall be evaluated to ensure that the level of difficulty is appropriate. (ES-301 Section D.5.d)

Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section D.5.d)

GG 8 Total malfunctions inserted: 5-8 GG 4 Ma Ifunctions that occur after EOP entry: 1-2 GG 2 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 2 EOPs entered/requiring sUbstantive actions: 1-2 GG 1 EOP contingencies requiring substantive actions: 0-2 GG 4 Crew Critical Tasks: 2-3 COMMENTS:

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TQ-AA-106-0204 11-01 NRC ESG-1 CT#1 (E-O-H) Manually start at least one RHR pump prior to transition out of EOP-TRIP-1.

Basis- Failure to manually start at least one low-head ECCS pump under the postulated conditions constitutes "mis-operation or incorrect crew performance which leads to degraded ... capacity."

This is a critical task because of the LBLOCA which occurs, and 10 head ECCS is required.

CT#2 (E-O--E) Manually actuate at least the minimum required complement of containment cooling equipment before exiting TRIP-1.

Basis- Failure to manually actuate the minimum required complement of containment cooling equipment under the postulated conditions constitutes a "demonstrated inability by the crew to recognize a failurelincorrect auto actuation of an ESF system or component." Failure to manually actuate containment spray represents a "demonstrated inability of the crew to effectively direct/manipulate ESF controls that would lead to a violation of the facility license condition ."

CT# 3: (ES-1.3-A) Transfer to Cold Leg Recirculation such that at least one train of ECCS is in operation in the recirculation mode within the following time frames:

1. From RWST 10 level alarm to initiating closed on 2SJ69 - ~3.7 minutes.

2. From RWST 10 level alarm to one containment spray pump stop- ~5.5 minutes.

3. From RWST 10 level alarm to switchover completion (includes restarting ECCS pumps if stopped on RWST 10-10 level) - ~ 11.2 minutes.

Basis: Failure to establish cold leg recirculation within the time frame specified in the FSAR is a "demonstrated inability of the crew to effectively direct/manipulate ESF controls that would lead to a violation of the facility license condition."

CT#4: Trip the cavitating Charging Pump prio1r to pump/system piping damage.

Basis: Failure to trip a cavitating charging pump during the transfer to cold leg recirculation when indications of cavitation are present, leads to the possibility of system damage and the advent of a loss of coolant outside the containment building. (As is the case in this scenario.)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

EVENTS LEADING TO CORE DAMAGE YIN Event YIN N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Slack Out Y LOCA COMPONENTITRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN COMPONENT, SYSTEM, OR TRAIN YIN COMPONENT, SYSTEM. OR TRAIN N Containment Sump Strainers N Gas Turbine I\J 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 SSO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION N Restore AC power during SSO N Connect to gas turbine N Trip Reactor and RCPs after loss of component Gooling system Y Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the cves 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 ESG.

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Appendix D Scenario Outline Form ES-D-1 Facility: SALEM <1 &2 Scenario No.: ESG-2 Op-TestNo.: 11-011\JRC Examiners: Operators:

Initial Conditions: 75% power, MOL. Power was reduced 30 minutes ago due to a short duration oscillation on 21 SGFP speed. PZR PORV 2PR1 was declared inoperable 3 hours0.125 days 0.0179 weeks 0.00411 months ago due to control circuit problems, and its motor operated block valve 2PR6 is shut and power is removed from its breaker to comply with TSAS 3.4.5 action b.

Turnover: Maintain current power.

Event Malf. No. Event Event Type" No. Description I

1 RC0014B C2 RC Loop Tavg Channel failure (TS)

C 2 SG0078C 500 gpd SGTL on 23 SG. (TS)

ALL R

3 Power reduction ALL M

4 SGOO78C SGTRon 23 SG ALL Loss of Off Site power during SGTR RCS cooldown 5 C EL0134 (ROfCRS restart safeguards loads, PO re-establish RCS ALL cooldown via SG atmospheric reliefs) 6 C Only available PZR PORV 2PR2 fails to open results in VL0298 CRS RO SGTR without RCS pressure control CTs: 1. Isolate feedwater into and steam flow out of 23 SG,

2. Cooldown and maintain CET Target temperature.

.. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39

TQ-AA-106-0204 Page 1 of 33 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: SGTL 1 SGTR w no pressure control SCENARIO NUMBER: 11-01 NRC ESG-2 EFFECTIVE DATE: See Below EXPECTED DURATION: 80 minutes REVISION NUMBER: 02 PROGRAM: '---'------'

L.O. REQUAL INITIAL LICENSE OTHER Revision Summary New Issue for 2010 LORT Annual Exam Rev. 1- Added TAC pp trip to beginning of scenario concurrent with SGTL.

Rev. 2 - 6/2012 Modified SGTL size from 90 to 500 gpd. Modified format to ILOT exam.

Removed TAC pump trip. Added Tavg channel failure. Modified temp at which loss of off site power occurs (from 535 to 510) Removed 21 SGFP at idle, both SGFP's are in service PREPARED BY: G Gauding 08-04-2012 ulatory Exam Author Date APPROVED BY: rle~t:~

Date APPROVED BY: ¥ ~

~3",-dcNe.)

FaclY Re~r~sentative ~ D e PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 Page 2 of 32

TQ-AA-106-0204 Page 3 of 32 A. Given a steam generator tube leak, take corrective action, lAW S2.0P-AB.SG-0001.

B. Given the order or indications of a steam generator tube leak (SGTL), perform actions as the nuclear control operator to RESPOND to the tube leak in accordance with the approved station procedures.

C. Given the order or indications of a steam generator tube leak (SGTL), DIRECT the response to the tube leak, in accordance with the approved station procedures.

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 steam generator tube rupture (SGTR), perform actions as the nuclear control operator to RESPOI\JD to the tube rupture in accordance with the approved station procedures.

I. Given indication of a steam generator tube rupture (SGTR). DIRECT the response to the SGTR in accordance with the approved station procedures.

J. Given the order or indications of a steam generator tube rupture (SGTR) without pressurizer pressure control, perform actions as the nuclear control operator to RESPOND to the SGTR in accordance with the approved station procedures.

K. Given the indication of a steam generator tube rupture (SGTR) without pressurizer pressure control, DIRECT the response to the SGTR in accordance with the approved station procedures.

L. During performance of emergency opel"ating procedures, monitor the critical safety function status trees in accordance the EOP in 13ffect.

A. 22 RCS Loop Th fails high B. 500 gpd SGTL C. SGTR D. Loss of Both SI pumps E. Loss of Off site power PSEG Restricted - Possession Requims Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 4 of 32 A. The crew will take the watch at 75% power, middle of life. Power was reduced 30 minutes ago as a precaution due to a short duration speed oscillation on 21 SGFP. Both SGFPs remain in service. PZR PORV 2PR1 was declared inoperable 3 hours0.125 days 0.0179 weeks 0.00411 months ago due to intermittent control circuit anomalies, and the PORV Block valve 2PR6 was shutand deenergized to comply with TSAS 3.4.5 action b.

B. Shortly after the crew takes the watch, 22 loop Tavg channel fails high. The RO will place rod control in manual after determining stable Main Turbine load. The CRS will enter S2.0P AB.ROD-0003, Continuous Rod Motion, remove the failed channel from service, and identify appropriate Tech Specs.

C. A small (500 gpd) SGTL will ramp in on 23 SG. The CRS will enter S2.OP-AB.SG-0001, Steam Generator Tube Leak, and take actions to quantify the leak and minimize the spread of contamination in the secondary plant.

D. The Crew identifies that the SGTL meets the criteria for Action Level 3 in S2.0P-AB.SG-0001, requiring the unit to be <50% power within one hour, and that Tech Spec 3.4.7.2 applies once the leak is >150 gpd.

E. The CRS will direct a power reduction to be initiated. The RO will use boration and manual rod control while the PO reduces Main Turbine load.

F. After the power reduction is initiated, the affected tube on 23 SG will rupture. Operators will identify the rising leak rate, and initiate a Rx trip and Safety Injection lAW CAS when conditions warrant.

G. The crew will perform diagnostics in 2-EOP-TRIP-1, Reactor Trip or Safety Injection. 22 AFW pump pressure override protection fails and cannot be defeated. Operators will isolate AFW to 23 SG.

H. The crew Will transition to 2-EOP-SGTR-1, Steam Generator Tube Rupture. With the 23MS45 steam supply from 23 SG to 23 AFW pump still open, the CRS will secure 23 AFW pump if not performed previously, leaving 24 SG as the only generator receiving AFW flow. Once secured and with 23MS45 shut, the crew will reset 23MS52 and start 23 AFW pump.

I. During the RCS cooldown in SGTR-1, a loss of off-site power will occur when the hottest CET reaches 510 degrees. The crew will perform the actions of Table C to restart safeguards loads, and re-establish the cooldown using the MS10s. 21 SI pump will not start if the crew attempts to start it, and 22 SI pump will trip if started.

J. Once the target temperature has been reached, the crew will attempt to perform the RCS depressurization with the only available PORV since RCPs lost off site power and 2PR1 is unavailable. 2PR2 will not open. With no SI pumps running, the CRS will transition to SGTR-5.

K. The scenario will terminate after the transition to SGTR-5 has been made.

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TQ*AA*106*0204 Page 5 of 32 IC- 242 1 RH 1 and RH2 CIT 2 RH18s CIT 3 VC1 and VC4 CIT 4 RCPs (SELF CHECK)

_ 5 RTBs (SELF CHECK) 6 MS167s (SELF CHECK)

_ 7 500 KV SWYD (SELF CHECK)

_ 8 SGFP Trip (SELF CHECK)

_ 9 23 CV PP (SELF CHECK)

_ 10 2PR6 CIT with power removed 11 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

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TQ-AA-106-0204 Page 6 of 32 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group i MONP254<1 0 II CONT BANK C GROUP POS 2 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: monp1 INCORE TIC TEMP.O 3 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: kbm06tcy II 23BF19 FW CONTROL VALVE-CLOSE 4 COMMAND: DMFVL0448 PURPOSE: <update as needed>

EVENT ACTION: kbm12tcy II 23BF13 FW INLET STOP CLOSE 6 COMMAND: DMF VLOO25 PURPOSE: <update as needed>

03 04 05 06 AN3735 AAS 735 FAILS - :21 TGA SUMP LEVEL HIGH 07 AN3736 AAS 736 FAILS-.:22 TGA SUMP LEVEL HIGH 00:03:10 NiA NfA RT-2 AASPOINT 08 NfA NfA RT-2 FAILS/OVRD AAS POINT 09 AN3738 AAS 738 FAILS- :24 TGA SUMP LEVEL HIGH NiA . RT-2 FAILSfOVRD TOON 10 AN3739 AAS 739 FAILS - :25 TGA SUMP LEVEL HIGH 11 12 NJA 13 N!A RTc13 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 7 of 32 SELF CHECK 01 NfA 02 NfA NfA 03

AF010 23 AUX :F_P~T.:R

. .::.I,-P.:...:R=ES=E'-'-T_ _ _ _ _ _ _----'I .......=00::..:..:1:..::0=:0,,-0_---'-=-=-_'---.:...:.:Ni.:...::'A----'-_L_--'-'-'---=-_L-......c=:..: :='----'

SELF CHECK 01 00:00:05 NJA ET-3 ON 1 A 01 22 AUX FEED PUMP-PRESS OVERRIDE 02 N/A NfA N/A N!A OFF DEFEAT

1. RH1 and RH2 (CIT)

2. VC 1 and 4 (CIT)

3. RH 18's (CIT)

4. RCPs (SELF CHECK)

5. RT (SELF CHECK)

6. MS 167s (SELF CHECK)

7. 500 KV SWYD (SELF CHECK)

8. 2PR6 shut with power removed.

9. SGFP TRIP (SELF CHECK)

1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 8 of 32 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.

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TQ*AA*106*0204 Page 9 of 32

1. 22 ReS Loop Th Fails High RO reports control rods inserting at 72 spm, verifies no runback in progress, gains concurrence from CRS and places control rods in manual.

CRS enters S2.0P-AB-ROD-3, Continuous Rod Motion.

RO reports rod motion stopped.

RO adjusts Rods in manual to control Tavg 0

within 1.5 of program using Att. 1.

RO reports rod motion was inward.

RO reports no NI failures.

RO reports 22 loop Tavg failed high and no dilution in progress.

RO places Master Flow Controller to manual and adjusts charging flow to return PZR level PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 10 of 32 C()mmEsht '.'

L' *F~:~l~~iiu~~~~~~~~t~~~r~~~~'~;t~/:~;d::%i;;:,:~;:;f;~.~;~;.~~~~:1!!(f~.!:!:~t/~!Ud~?t. R.es'F)oh~i~;.~.~:,"*'

to program using AU. 2.

RO selects Deviation Defeat for Loop 22 ~ T and Tave.

RO selects recorders to channel other than 22 loop.

RO returns Master Flow Controller to auto when PZR level is on program.

RO reports control rods are above the RIL.

RO withdraws control rods to ARO or to establish Tave within 1.5°F of program.

RO verifies Tave within 1.5 0 program and restores the Rods to Auto.

CRS initiates removing 22 loop RCS temperature channel from service lAW SO. RPS-0002.

CRS enters TSAS(s) 3.3.1.1 Action 6, and 3.3.2.1 Action 19*.

Proceed to next event after Tech Spec call is made at Lead Evaluators direction.

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TQ-AA-106-0204 Paae 11 of 32

2. SGTL RO announces OHA A-6 RMS HI RAD OR TRBL as unexpected.

RO reports CRT shows 2R53C in alarm.

RO reports 2R53C reading and slowly rising.

CRS contacts Radiation Protection to perform SC.RP-TI.RM-0607(Q), Primary To Secondary Leak Rate Response lAW ARP.

CRS enters S2.0P-AB.SG-001 Steam Generator Tube Leak directly or enters S2.0P AB.RAD-001, Abnormal Radiation.

Note: Go to downpower actions when Action Level 3 is identified.

CRS directs performance of S2.0P-AB.SG 001 CAS.

PO initiates trending of 2R19C and 2R53C.

Crew contacts Chemistry to:

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TQ-AA-106-0204 12 of 32

- Initiate sampling of 23 SG to confirm and quantify actual leak rate.

- Provide algorithm correlation factor required)

- Provide a rate-ot-change for 23 SG primary to secondary leakage.

Role Play: When contacted, respond as Chemistry that a technician will be dispatched to the Control Room, and that sampling of 23 SG will be performed.

CRS dispatches an operator to deenergize TGA sumps.

Note: PZR level may be lowering if rods were not resored to ARO. (Programmed level lower due to lower Tavg.)

RO reports PZR level is stable. IF RO reports PZR level is lowering, RO will swap to a PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 13 of 32 centrifugal charging pump.

RO reports unit is in Mode 1.

Crew identifies 2R53C, 2R19C and 2R15 rising.

PO reports affected SG is 23.

PO raises 23MS10 setpoint to 1045 psig.

PO closes or checks closed 23GB4, 23MS7, and 23MS18.

CRS dispatches an operator to shut 23MS45, and enters TSAS 3.7.1.3 for 23 AFW pump.

CRS dispatches an operator to re-align SGBD and MS sampling to Waste System.

CAS Action Level 3 required actions start here.

CRS determines that the CAS indicates that Action Level 3 is present lAW Step 6.2.A based on:

- Leak rate is .:::. 75 gpd AND

- The rate of change of the leakrate is .:::. 30 gpd/hr.

CRS determines a power reduction to :::50 %

must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and a PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 14 of 32 shutdown to Mode 3 (Hot Standby) within the next 2 hours0.0833 days 0.0119 weeks 0.00274 months .

CRS enters TSAS 3.4.7.2.c Note: If time does not permit Tech Spec identification, post scenario follow up question will be required.

RO calculates boron addition required for power reduction to 50%.

CRS orders a power reduction at a rate which ensure power is <50% within one hour.

CRS enters S2.0P-AB.LOAD-0001, Rapid Load Reduction to perform the power reduction.

RO reports reflash of OHA A-6, and CRT indicates 2R15 in alarm.

RO reports indications of worsening tube leak on 23 SG.

OHA A-6 will reflash several more times as 2R15, 2R19C, and 2R41D alarm.

CRS determines CAS actions for rising SG NR PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 15 of 32 level lAW CAS 1.0 are true.

CRS directs the RO to trip the Rx, confirm and initiate a Safety RO trips the Rx, confirms the trip, and initiates a Safety Injection.

Evaluators log time of Rx Trip here:

RO performs immediate actions of TRIP-1:

Verifies Rx tripped.

Verifies Rx trip confirmation Trips the Main Turbine.

Verifies off site power available to vital busses Verifies SI initiation.

CRS reads immediate action steps to RO who confirms their performance.

Crew commences monitoring TRIP-1 CAS.

RO reports SEC loading is not complete busses, but all available started.

PO reports all AFW pumps are running, but 22 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 16 of 32 AFW pump is not supplying flow even though its discharge pressure is high enough.

PO requests, and receives, permission to depress Pressure Override Defeat for 22 AFW pump, which has no effect on AFW PO reports 23 AFW pump is running, and that an unmonitored release is occurring from the TDAFW pump steam discharge with 23MS45 not shut yet.

AFW flow control is complicated by the fact that a SGTR is present on 23 SG, but the 23MS45 has not been shut yet.

Additionally, 22 AFW pump is not supplying flow to 21 and 22 SGs because its Pressure Override circuit has failed. Shortly after the Rx is tripped, SG level will recover in at least one SG so that AFW flow can be lowered < 22E4.

TRIP-1 does not direct tripping 23 AFW pump unless 2 MDAFW pps are running, which in this case is not true, since a running pump would be supplying flow.

Detailed observation of the crew during AFW flow decisions should be made by the evaluators.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 17 of 32 PO requests to throttle AFW flow, and isolates AFW flow to 23 SG by closing 23AF11 and 23AF21.

CRS directs PO to maintain total AFW flow

>22E4 Ibm/hr while throttling AFW flow.

RO reports 23BF19 and 23BF13 are NOT shut when performing Safeguards Valve Alignment.

CRS directs PO to shut 23BF19 and 23BF13 from the control console.

PO shuts 23BF19 and 23BF13.

RO reports normal containment pressure.

CRS determines no MSLI is required.

CRS directs SM to refer to the ECG.

PO reports all 4KV vital busses energized from PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106*0204 18 of 32 off site power.

RO reports control room ventilation in accident pressurized mode.

RO reports 2 CCW pumps are running.

RO reports ECCS is injecting as expected for current RCS pressure.

PO reports AFW flow and SG NR level status.

RO reports all RCPs are in operation.

RO reports MSLI is not required.

RO rerorts RTBs are open, PORVs shut, PORV block valve 2PR7 open, 2PR6 shut and CIT, and PZR spray valves operating as expected for current RCS pressure.

RO reports RCS pressure> 1350 psig.

RO maintains seal injection flow to all RCPs.

PO reports no faulted SGs.

PO reports 23 SG is ruptured based on NR level.

CRS transitions to SGTR-1.

Crew commences monitoring of CFSTs.

RO maintains seal injection flow to all Reps.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 19 of 32 PO reports 23 SG is ruptured, and 23MS10 is set at 1045 psig.

PO reports 23MS10 operating as expected for current pressure.

PO shuts 23MS167 and ensures 23MS7, 23MS18, and 23G84 are shut.

PO reports 23 SG is ruptured.

PO reports 23 AFW pump is NOT only source of AFW.

PO lowers 23 AFW pump speed to minimum and trips 23 AFW pump.

PO stops 23 AFW pump.

CRS sends an operator to reset 23MS52 when all SG NR levels are> 15%.

SlmUlator,Operatorr~;jii1serf RT..8

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to iE:,'

-",'::.,:;,,1<:,\

reset:ZMS5Z.' '"RIqncludes'a*10;mlnute*

'-2.>?

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 20 of 32 CRS checks on status of MS sampling valves which were directed to be shut in AB.SG, or if not previously directed to be closed, directs closure of 2SS333.

If previously dispatched to shut 2SS333, then when contacted by crew report 2SS333 is shut.

PO reports 23 SG is isolated from intact SGs, 23 SG NR level is >9%, and feed flow is isolated to 23 SG.

RO reports power is CfT to 2PR6, and CRS orders power restored.

Note: Do NOT restore power to 2PR6 during scenario. If asked later in scenario, state the breaker appears to be mechanically bound in the open position.

RO reports 2PR2 is operating correctly in response to PZR pressure.

PO reports no faulted SGs.

RO resets SI and Phase A isolations, and opens CA330's.

PO resets all SECs.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 21 of 32 RO stops both RHR pumps.

PO reports 23 SG is isolated and >375 psig.

CRS dispatches an operator to shift Gland Sealing steam to Unit 1.

CRS determines target temperature for RCS cooldown is 503 degrees.

PO commences RCS cooldown by using Steam Dumps in MS Pressure Control-Manual at 25% demand.

PO Bypasses Tavg on steam dump control when Tavg reaches 543°F.

CRS recognized loss of off-site power and returns to Step 10 CAS to perform actions of Table C.

PO verifies all available equipment started for each SEC.

PO resets all SECs.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 22 of 32 CRS directs starting of Safeguards loads.

CRS directs the cooldown to be re-established using intact SGs 21,22 and 24MS10's fully open.

RO shuts charging pump mini flows when RCS pressure lowers to 1500 psig.

CJ;#~;(~

~~;: ~j'~,:::~~\~ijlr~H(l~marhta.iri;i:i

%~s;RC$JenjperatU:retorri~i~talri,;, *. *.' *.*.*;\

riminirriJ~!l',;r~.CI~ired . subcooling~j,.J,

":~t c' ,< >>i '~;L' SAT'"

PO stabilizes hottest CET temperature less than 503 degrees.

PO reports 23 SG pressure is stable or rising or at least 250 psig above intact SG pressure.

RO reports adequate subcooling.

RO reports Reps are stopped and normal PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 e 23 of 32 RO reports 2PR2 PZR PORV is available.

Note: If asked about restoring power to 2PR6, report that there has been no progress in determining what is keeping the breaker from being closed.

RO reports 2PR2 will not open.

CRS returns to step 18 and answers NO to if a PORV is available.

RO reports no SI pumps are running.

RO reports no SI pumps running if start attempt is made.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ~AA-106~0204 24 of 32 CRS transitions to SGTR-5.

PO reports 23 SG NR level.

RO reports no RCPs are due to loss of off-site power.

RO reports no PZR PORV available since 2PR6 is shut and deenergized to comply with TS 3.4.5.b RO reports neither SI pump will run.

PO maintains AFW flow 9-33% with any SG N R level >9%.

RO reports PZR level >11 % and RCS subcooling >0°.

PO reports >22E4 Ibm/hr AFW flow is available.

RO reports RVLlS level >57% Full Range.

PO reports 23 SG ruptured.

RO stops all but 21 OR 22 charging pumps.

Terminate scenario after reduction to single charging pump has been performed at Lead Evaluators direction.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 25 of 32 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-1 01-*111-1 003, Use of Procedures E. S2.0P-AB.RAD-0001, Abnormal Radiation F. S2.0P-AB.SG-0001, Steam Generator Tube Leak G. 2-EOP-TRIP-1, Rx Trip or Safety Injection H. 2-EOP-CFST-1, Critical Safety Function Status Trees I. 2-EOP-SGTR-1, Steam Generator Tube Rupture J. 2-EOP-SGTR-5, Steam Generator Tube Rupture wlo Pressure Control PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 26 of 32

........ ****ATTAcHMEN"{*1*

UNlr,.w6p'(ANTtSJATUS*

TODAY MODE: 1 POWER: 75 RCS BORON: 915 MWe 890 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS Core Burnup is 5000 EFPH Control Bank D rods are in auto at 154 steps Power was reduced 30 minutes ago as a precaution due to a short duration speed oscillation on 21 SGFP Xenon building in at 80 pcm I hr MOST LIMITING LCO AND DATEITIME OF EXPIRATION:

3.4.5. Action b" 2PR1 expires 69 hours2.875 days 0.411 weeks 0.0945 months from now EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

None ABNORMAL PLANT CONFIGURATIONS:

2PR6 shut and power CIT.

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

PZR PORV 2PR1 was declared inoperable 3 hours0.125 days 0.0179 weeks 0.00411 months ago due to intermittent control circuit anomalies.

SECONDARY:

21 SGFP speed problem has not been investigated.

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

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 aHA lamps operating (aHA 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 Worksh43et 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Revision 2 Page 28 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 cl licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automaticcilly actuated plant system would have been required to mitigate the consequences of an individual's 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 Page 29 of 32 ATTACHMENT 4 SIMULATOR SCENARIO REVIEW CHECKLIST Note: Attach a separate copy of this form to each scenario reviewed. This form is used as guidance for the examination team as they conduct their review for the proposed scenarios.

SCENARIO IDENTIFIER: 11*01 NRC ESG*2 REVIEWER: E Gallagher Initials Qualitative Attributes EG 1. The scenario has clearly stated objectives in the scenario.

EG 2. The initial conditions are realistic, in tl1at some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

EG 3. The scenario consists mostly of related events.

EG 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 EG 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.

EG 6. The events are valid with regard to physics and thermodynamics.

EG 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

EG 8. The simulator modeling is not altered.

EG 9. All crew competencies can be evaluated.

EG 10. The scenario has been validated.

EG 11. If the sampling plan indicates that thE! scenario was used for training during the requalification cycle, evaluate the neE~d to modify or replace the scenario.

EG 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 P~ge 30 of 32 ATTACHMENT 4(cont)

SIMULATOR SCENARIO REVIEW CHECKLIST Note: The quantitative attribute target ranges that are specified on the form are not absolute limitations; some scenarios may be an excellent evaluation tool, but may not fit within the ranges. A scenario that does not fit into these ranges shall be evaluated to ensure that the level of difficulty is appropriate. (ES-301 Section D.5.d)

Quantitative Attributes GG 7 Total malfunctions inserted: e;-8 GG 3 Malfunctions that occur after EOP entry: 1-2 GG 2 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 2 EOPs entered/requiring substantive actions: 1-2 GG 1 EOP contingencies requiring substantive actions: 0-2 GG 2 Crew Critical Tasks: 2-3 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 31 of 32 11*01 NRC ESG*2 CT #1: (E-3-A) Isolate AFW to the ruptured SG within 10 minutes of entry into TRIP-1 and subsequently close 23MS167, 23MS18, 23MS7 and 23GB4 in SGTR-1.

BASIS: Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that u . . . necessitates the crew taking compensating actions which complicates the event mitigation strategy ... "

CT #2: (E-3-B) Establish/Maintain RCS temperature so a transition from SGTR-1 does not occur because Tave is too high to maintain minimum subcooling, OR below the RCS temperature that caUSE~S an extreme challenge (Red) or severe (Purple) challenge to the subcriticality and/or the integrity CSF.

BASIS: Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency procedure, which constitutes an incorrect performance that " ... necessitates the crew taking compensating actions which complicates the event mitigation strategy ... "

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 32 of 32 11-01 NRC ESG-2 SALEM ESG - PRA RELATIONSHIPS EVALUATION FORM EVENTS LEADING TO CORE DAMAGE YIN YIN Event N TRANSIENTS with pes Unavailable N Loss of Service Water Y Steam Generator Tube Rupture N Loss ofCCW Y Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENTITRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN COMPONENT, SYSTEM, OR TRAIN YIN 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 YIN 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 Cool down 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 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

Appendix 0 Scenario Outline Form ES-O-1 Facility: SALEIV11 & 2 Scenario No.: ESG-3 Op-Test l\lo.: 11-01 NRC Examiners: Operators:

Initial Conditions: 47%, BOL , Rod control is in manual for insertion of new NI currents, currently performing SC.IC-OC.NIS-0021 for 2N41. 21 Charging pump is CIT due to bio-fouling. 22 charging pump is in service. 23 charging pump is inoperable but available. 21 SGFP O/S for speed control troubleshooting, HOPs O/S, calorimetric just performed SAT lAW requirement of S2.0P-10.ZZ-0004, Power Operations. 21 and 22 condensate pumps in service. 23A Circulator CIT for corrective maintenance. Minor CW grassing has been occurring.

Turnover: Raise power to 51 %@ 10% per hour, place all HOP liS, continue power ascension to 60%

at 10% per hour, all lAW IOP-4.

Event Malf. No. Event Event Type*

No. Description I

N 1 Raise power ALL AN3855 2 ANOO23 CRS 2A 1 12ENOC batter charger trip (TS)

OA0030 I

3 PROO16A PZR Press Inst fails hi (during first 1% power up) (TS)

CRS RO C325 C Loss of Circ Water Bus Section 23 causes loss of 2 more 4

CN0086B CRS PO "A" circulators, degrading Condenser Vacuum R

5 Power reduction.

ALL M 21 Condensate pump trip causes loss of only operating 6 CN0117A ALL SGFP -..,. Manual Rx trip AF018'IB 7 C AF0181A Sequential loss of all AFW-....FRHS Red Path CRSPO B606 C FRHS Bleed and Feed initiation (no centrifugal charging 8 CV0208B ALL pumps available) Cond pump recovery.

CT#1 Establish AFW flow CT#2 Establilsh RCS Bleed and Feed

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Pal~e 38 of 39

TQ-AA-106-0204 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Loss of vacuum, loss of feed, FRHS Cond Pump recovery SCENARIO NUMBER: 11-01 NRC ESG-3 EFFECTIVE DATE: See Approval Dates below EXPECTED DURATION: 80 minutes REVISION NUMBER: 01 PROGRAM: '---"-----'

L.O. REQUAL f . X I INITIAL LICENSE STA OTHER Revision Summary New Issue for 09-01 ILOT CERT Exam Rev 01 6/2012 Replaced CFCU trip with 125VDC Battery charger trip. Added 22 charging pump liS and subsequent trip to caus.e immediate Bleed and Feed requirement in FRHS-1.

PREPARED BY: G Gauding 8-4-12 gulatory Exam Author Date APPROVED BY: fjZ-IL Date APPROVED BY: .P~~ 6StiarJ"J f!acility ~presentative

) q III!~

Date PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

-1

TQ-AA-106-0204 A. Given a situation with an OHA alarm, the crew will perform action(s) to investigate and correct the cause of the alarm, lAW approved station procedures.

B. Given the unit at power with the generator synchronized to the grid, the crew will perform a power increase at 10%/hr, lAW S2.0P-IO.ZZ-0004.

C. Given the unit at power with a failurE~ of the pressurizer pressure channel, take corrective action lAW S2.0P-AB.PZR-0001.

D. Given indication of a pressurizer control system malfunction, DIRECT the response to the malfunction in accordance with the clpproved station procedures.

E. Given the order or indications of a pressurizer control system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures F. Given the order or indications of a feedwater or condensate system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures.

G. Given indication of a feedwater or condensate system malfunction, DIRECT the response to the malfunction in accordance with 1:1e approved station procedures H. Given a loss of a heater drain pump or condensate pump, take corrective action lAW S2.0P-AB.CN-0001.

L 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.

J. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

K. 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.

L. Given indication of a loss of secondary heat sink, DIRECT the response to the heat sink loss in accordance with the approved station procedures.

M. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect A. PZR Pressure controlling channel fails high B. Loss of 2 additional circulators/vacuum degradation.

C. Loss of only operating SGFP >P-10.

D. FRHS with no charging pumps.

E. FRHS Cond pump recovery.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

-2

TQ*AA*106*0204 A. The crew will take the watch with Rx power at 48%, BOL. Power was reduced yesterday during CW grassing. 21 SGFP developed speed oscillations during the downpower and was removed from service for troubIE~shooting. 23A Circulator is CIT for Traveling Screen corrective maintenance. Rod control is in manual for insertion of new NI currents, currently performing SC.IC-DC.NIS-0021 for 2N41, which is the last of the 4 channels to be updated.

The adjustment is complete, and technicians are finishing the paperwork. All Heater Drain Pumps are O/S. 21 and 22 condensate pumps in service. Orders for the shift are to raise power to 51 % at 10% per hour, place HOPs in service, then continue power ascension to 60%. The Rx fuel is conditioned to 90% power.

B. Shortly after the crew assumes the watch, the 2A1 125VOC Battery Charger will trip. The CRS will enter the appropriate Tech Spec, and dispatch an operator to investigate.

C. After initiating the power ascension to 51 %, the controlling PZR pressure channel will fail high. Operators will enter S2.0P-AB.PZR-0001, Pressurizer Pressure Control Malfunction, stabilize the plant, place a redundant channel in control, and return the Master Pressure Controller to automatic. The CRS will enter the appropriate Tech Spec.

D. After power has been raised, a loss of 2CW 4KV bus section 23 occurs, and the 2 remaining "A" circulators trip. The CRS will enter S2.0P-AB.CW-0001, Circulating Water System Malfunction. Condenser vacuum wil! begin to degrade, and the crew will commence a power reduction.

During the power reduction as vacuum continues to degrade, 21 condensate pump will trip.

The remaining condensate pump will be unable to supply sufficient flow, and as 22 SGFP speed rises, its suction pressure will lower rapidly to the SGFP trip setpoint. The crew will manually trip the Reactor upon the loss of the only operating SGFP.

F. The CRS will transition to TRIP-2, Rx Trip Response, after the immediate actions of TRIP-1 are performed and SI is not required. No AFW flow will be present following the Rx trip. 22 AFW pump trips after starting, 21 AFW pump pressure override circuit fails, and 23 AFW pump does not auto start. The crew starts 23 AFW pump, and 21 AFW pump trips after its pressure override circuit is defeated.

G. 5 minutes after the Rx trip, the operating centrifugal charging pump (22) will trip, and letdown will automatically isolate. After establishing AFW flow, the last remaining AFW pump (23) develops a speed control problem which causes its speed demand to lower speed to zero. With FRPs in effect, the CRS will transition to FRHS-1, Loss of Secondary Heat Sink with AFW flow < 22E4 Ibm/hr and Steam Generator Narrow Range levels all <9%.

H. The crew will establish RCS Bleed and Feed based on having no centrifugal charging pumps. The crew will depressurize a steam generator and establish Condensate flow to the depressurized steam generator.

I. The scenario will terminate when feed flow has been established to at least one SG, and SG WR level(s) are rising.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

<1

__ Pre-snapped IC-243 2 RH18s CIT 3 VC1 and VC4 CIT 4 RCPs (SELF CHECK) 5 RTBs (SELF CHECK)

_ 6 MS167s (SELF CHECK)

_ 7 500 KV SWYD (SELF CHECK) 8 SGFP Trip (SELF CHECK) 9 23 CV PP (SELF CHECK)

_10 23A Circulator CIT

_ 11 21 SGFP OIS 12 Place copy of SC.lC-DC.NIS-0021, Exhibit 1 on NCO desk.

_ 13 22 charging pump in service

_14 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 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

-4

TQ-AA-106-0204 EVENT ACTION: MONP254 <10 II CONT ROD BANK C < 10 ( RX TRIP) 1 COMMAND: DMF CNOO86B PURPOSE: <update as needed>

.~--------~

-~

EVENT ACTION: kb507azp /I 21 AUX FEED PUMP-PRESSURE OVERRI 5 COMMAND:

PURPOSE: <update as needed> .......... _ .............. __

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 5

TQ-AA-106-0204 01 PR0016A PZR PRESS CH ! FAILS H/L NfA 2500 02 CN0117A 21 PUMPTRJP NfA 03 AF0181 B 22 AUX FEEDWATER PUMP TRIP 00:00:29 N/A SERPOINT AN0304 SER 304 FAILS -:A4 REACTOR 04 N/A NfA N/A N/A FAILS/OVRD PROTECTION SYS CH I INSTRUMENT LOOP IN TEST TOON 05 0.9 06 0.6 07 0 08 0 09 10 11 100 12 0 AAS POINT AN3855AAS 855 FAILS - :2A1/2A2125VDC BATIERY 13 N/A N!A N!A RT-1 FAILS/OVRD CHARGERS TROUBLE" TO ON SERPOINT AN0023 SER 023 FAILS - :B2 2A 125VDC CONTROL 14 00:00:03 N/A RT-1 FAfLSfOVRD BUS VOLTAGE LOW TO ON CN0086S Loss of 22 main condenser vacuum 15 00:01:00 17 00:07:00 20 16 AF018.1A 21 AUX FEEDWATER PUMP TRIP 00:00:05 N!A NfA ET-S 17 CV0208B 22 CHARGING PUMP TRIP 00:05:00 N/A NtA ET-1 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 6

TQ-AA-106-0204 SELF Description Delay Initial Ramp Trigger Conditionl CHECK Time Value Time Severity 01 8526 L AO 21 STM GEN FEED PUMP SPEED N!A N!A NiA N/A 02 B524 A1 LO 21 SGFP TURNING GEAR ENGAGE N/A N/A NiA N/A ON 03 8524 A2 LO 21 SGFP TURNING GEAR DISENGAGE: NfA N/A NiA N/A OFF 04 C325 F Dr 23CW1AD OPEN N/A NiA N/A RT-5 ON 05 B606 F 01 23 AUX FEED PUMP-SPEED DECREASE NfA N!A NiA RT-9 ON 06 07 08 09 1.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- j7 _

TQ*AA*106*0204 A State shift job assignments. I 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.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- l3

1. Power Ascension CRS direct RO to maintain TavelTref in a designated band using controlrQ9 s ______ in m'-'-a__n-'-u__

a'---l.-----t----

CRS directs RO and PO to coordinate actions while rais Note: Digital EHC is set up initially for 1% per minute. PO must set it correctly for 10% per hour.

r hour.

T~~~:~;;! ... _.......... ___ ' y " ___ _ .. _. ---------j Proceed to next event after a noticeable change in turbine and Rx power has occurred.

2. 2A1125 VDC Battery Charger Trip PSEG Restricted - Possession Requires Specific Approval Nuclear Training

- 9

~':**2>:;:~~'~gd,~;:~i <~:~1rt~f":

'125VDC CONTROL BUS ... .... '

i V(:)hJJ\.Gg*E9\tY*3;)~j~r.j: *....*. ?~ . * <.. .*** c{\*.

T Remote!DA003DfBATTERy'*tii.;((*>***.*.

'CHAR-GERA1STATlJS:}OFFUNE.

RO reports OHA A-41 AUX ALM SYS PRINTER and OHA B-2 2A 125VDC CNTRL BUS VOLT LO as unexoected.

PO reports point in alarm is for 2A 112A2 125 VDC Batterv Charaer Trouble.

PO refers to ARP for OHA B-2 and reports low bus voltage alarm setpoint is <128 VDC, and current readina is 127 VDC.

CRS disoatches an ooerator to investiaate.

Role Play: 2 minutes after being dispatched, report as NEO that the supply breaker on the 2A 1 125 VDC Battery Charger is tripped.

Report there is no apparent reason for the breaker trip.

CRS contacts WCC I Maintenance to investiaate.

CRS enters TSAS 3.8.2.3 action b.

CRS determines that the 2A2 125 VDC Battery Charger must be placed in service within the next 2 hours0.0833 days 0.0119 weeks 0.00274 months if 2A1 Battery Charger cannot be restored to ooerable status.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 10

TQ-AA-106-0204 Continue to next event after Tech Spec determination is made or at direction of Lead Evaluator.

3. Controlling PZR Pressure Channell (PT-455) fails high RO announces RC PRESS DEVIATION HI console alarm, OHA 0-8 RC PRESS HI and OHA E-42 2PR1/2 TRIP as un RO diagnoses PZR Pressure channel I failed high, and requests permission to place MPC in manual.

CRS directs RO to place MPC in manual and raise PZR RO places MPC in manual and lowers demand to minimum, and announces that control has been established over MPC

()~tpu~~~t.=~,---___

RO reports RC PRESS DEVIATION HI and OHA E-28 cleared as expected when reducing MPC and 22 BU PZR nO<:lTOrC

~------~

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 11

TQ-AA-106-0204 CRS enters S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction.

PO reports controlling PZR Pressure channel I is failed hiah.

PO reports PZR Master Pressure Controller is in manual with demand signal consistent with Attachment 2 and is restoring PZR pressure to program value.

PO selects PZR pressure channel III for control.----------------

PO returns Master CRS direct removal of failed channel service lAW S2.0P-SO.RPS-0003, Pressurizer Channel in

_______________ __________ A-C'--_ _ __

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 12

TQ-AA-106-0204 CRS dispatches an operator to remove power from Note: Do NOT remove power from 2PR6 during scenario. If asked later in scenario why the power has not been removed, reply that the breaker would not open and electrical has been dispatched to investigate.

CRS directs RO and PO to proceed with r ascension.

Proceed to next event after power ascension has re-started or on direction from Lead Evaluator. If CRS takes no action to perform the power ascension, then call as Rob DeNight (SOS) and direct the CRS to perform the power ascension.

r hour.

RO/PO announces when Below P-9 light extinguishes.

PSEG Restricted Possession Requires Specific Approval from Nuclear Training

- 13

TQ-AA-106-0204 PO announces OHAs K-27 23 STA XFMR TRBL and K-34 4KV CW BUS UNDRVOLT as lnAvnActed.

PO diagnoses loss of 2CW 4KV bus section 23.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 14

TQ-AA-106-0204 CRS enters S2.0P-AB.CW-0001, Circulating Water System Malfunction based on 2 or more circulators out of service.

PO refers to ARPs for the K overhead windows.

~~~~--

CRS directs initiation of Attachment 1 CAS of S2.0P-AB.CW-0001.

PO reports there is no indication of a pipe PO reports at least one circulator is operating on each condenser.

CRS dispatches operators to open hood spray bypass valves and monitor condensate pump suction L.PIip..:.cin.....g,-,-._ _ _ _ _ _ _ _ _ _~.

Note: Main Condenser back pressure is limited to 5.0" with Main Generator load <560 MWe.

PO reports condenser backpressure is rising PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 15

TQ-AA-106-0204 CRS determines power reduction is necessary with backpressure rising and Main Generator output -500 MWe.

5. Power Reduction CRS enters S2.0P-AB.LOAO-0001, Rapid

~oaclnReduction, to perform power reduction.

CRS initiates Attachment 1 CAS of S2.0P AB.LOAO-0001.

CRS direct PO to initiate load reduction between 1~~~~~~--'--'-'-----

RO uses control rods in manual and boration as necessary to maintain Tavg on program lAW Attachment 3.

RO initiates boration as required to maintain control rods above the RIL.

PO reports when Below P-9 if power initially >49%.

Proceed to next event when the load reduction is underway.

6. Loss of 21 condensate pump PSEG Restricted - Possession Requires Specific Approval Nuclear Training

- 16

TQ-AA-106-0204 CRS enters S2.0P-AB.CN-0001, Main Feedwater/Condensate System Abno Note: If crew attempts to start the idle condensate pump it will not start.

PO reports SGFP Condensate Suction Pressure Lo Console alarms.

l~~-----------------------\

Note: SGFP Condensate Suction Pressure Lo Console alarms at 275 psig.

PO reports 22 SGFP speed is increasing and SGFP suction oressure continues to lower.

Note: SGFP trip on low suction pressure will occur at

<215 psig sustained for 10 seconds or 190 psig with no time delay and will auto start both MDAFW PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 17

TQ-AA-106-0204 Manual Rx trip is based on action of AB.CN with no SGFPs running and Rx power >10%.

RO performs Immediate Actions for TRIP-1, Reactor Trip or Safety Injection:

- Trip reactor

- Confirms reactor trip

- Trips turbine

- Verifies 4KV vital buses energized R"'n.....rtc SI not demanded or reauired CRS and RO verify performance of immediate actions.

CRS transitions to TRIP-2, Reactor Trip Response, based on no SI actuated or ired.

PSEG Restricted Possession Requires Specific Approval from Nuclear Training

- 18

TQ-AA-106-0204 PO reports no AFW flow, and the status of AFW:

- 21 AFW pump running with no flow and adequate discharge pressure

- 22 AFW pump is tripped

- 23 AFW DumD has not started CRS directs PO to start 23 AFW pump, and defeat PrE!~sLJCE! Override for 21 AFW pu PO starts 23 AFW pump and reports it is starting. Depresses 21 AFW pump pressure override defeat and reports 21 AFW pump after AFW flow initiated.

PO adjusts 23 AFW pump speed or 21-24 AF11 s to lower total AFW flow to no less than 22E4.,-.-.,.-.-_c_c_c_,_______________ ________J PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 19

7. Loss of all AFW flow PO reports 23 AFW pump speed lowering and no AFWflow.

Note: The STA will not arrive in the control room until 10 minutes after being paged. The crew is responsible for identifying the Heat Sink RED path.

The crew identifies when a Heat Sink RED path exists when all SG NR levels are <9%

and no feed flow exists.

Depending on scenario flow, SGNR levels may not be <9% when the last AFW pump is lost. The crew should continue actions in TRIP-2 entry conditions for FRHS-1 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 20

TQ-AA-106-0204 are met. (AFW flow <:22E4 Ibm/hr and all SG NR levels <9%.)

CRS transitions to FRHS-1, Loss of Secondary Heat Sink.

PO reports it was not operator action which caused total AFW flow to lower <: 22E4 Ibm/hr.

RO reports RCS pressure is > all SGs, and RCS Thots are> 350°F.

RO reports no centrifugal charging pumps are CRS goes to Step 23 Bleed and Feed initiation.

8. ReS Bleed and Feed PO reports SI valves in safeguards position r Table B.

RO reports 21 and 22 charging pumps are not PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 21

TQ-AA-106-0204 RO reports both PZR PORV Stop Valves and both PZR PORVs are 0 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 22

TQ-AA-106-0204 Crew selects only one SG deoressurization.

CRS reviews depressurization termination criteria.

Note: Steam dump availability is based on having condenser vacuum, at least one circulator in service on a waterbox and no MSLI initiated.

Note: IF CRS determines steam dumps are not available due to previous vacuum problem, then the PO will initiate MSLI on ALL loops and fully open the selected SG MS10 to depressurize selected SG.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 23

TQ-AA-106-0204 PO adjusts valve demand to 25%, and when Tava lowers to 543°F.

CRS dispatches operator to open selected SG BF40.

PO releases or verifies released selected BF22.

--- - - - - - - - : - - - - - - - - - - - t -

PO opens 21 and 22 CN48s and closes 21 and 22 CN32s.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 24

TQ-AA-106-0204 Depressurization of selected SG should not be stopped until WR level is rising in selected SG.

PO reports indication of feed flow to selected SG and WR level ..

The Scenario can be terminated at the Lead Evaluator's discretion, after SG WR level is observed to be rising.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 25

TQ-AA-106*0204 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction F. S2.0P-AB.CW-0001, Circulating Water System Abnormality G. S2.0P-AB.COND-0001, Loss of Condenser Vacuum H. S2.0P-AB.LOAD-0001, Rapid Load Reduction I. S2.0P-AB.CN-0001, Main Feedwater/Condensate System Abnormality J. S2-EOP-TRIP-1, Rx Trip or Safety Injection K. 2-EOP-TRIP-2, Rx Trip Response L 2-EOP-FRHS-1, Loss of Secondary Heat Sink PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 26

.>i.,;{Al!J\.q.~~Er.J,. . . . . . ..

>ji§VNITTVV()e~ANT~TATUS "TODAY MODE: 1 POWER: 47% RCS BORON: 1365 MWe 500 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS Xenon building in at 2 pcm per hour.

Reactivity plan for power ascension is control rods only for ascension to 60%.

MOST LIMITING LCO AND DATEfTlME OF EXPIRATION:

21 charging pump CfT for biofouling. TSAS 3.5.2.a and 3.1.2.4 (23 charging pump also inoperable) both 70 hours2.917 days 0.417 weeks 0.0959 months remaining.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

Raise power to 51% at 10% per hour, place HDPs in service, then continue power ascension to 60% lAW S2.0P-IO.zZ-0004, Power Operation.

Currently performing SC.IC-DC.NIS-0021 for 2N41, which is last NI channel to be updated. New data is installed, two bistables (411 C and 411 D) have not been restored yet, and procedure should be finished within next 15 minutes.

ABNORMAL PLANT CONFIGURATIONS:

Power was reduced yesterday during CW grassing. Rod control is in manual for insertion of new NI currents. 22 charging pump is in service to allow troubleshooting of 23 charging pump speed changer problem.

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

23 charging pump is O/S and available.

Power Range channel 2N41 , 3.3.1.1 Action 2.

SECONDARY:

21 SGFP developed speed oscillations during the down power and was removed from service for troubleshooting. Currently on turning gear.

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

23A Circulator is CfT for emergent Traveling Screen repair PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

- 27