Text

Final Operating Test (Sections a, B, and C) (Folder 3)
	ML17031A347
Person / Time
Site:	Salem
Issue date:	12/12/2016
From:	; NRC Region 1
To:	; Public Service Enterprise Group
Shared Package
ML16076A441	List: IR 05000272/2017301; ML16193A633; ML17031A294; ML17031A302; ML17031A337; ML17031A347; ML17109A351; ML17109A352; ML17109A358; ML17109A360; ML17109A361; ML17109A363; ML17109A364; NTD-16-051, Draft Outlines (Facility Letter Dtd. - 9/12/2016 (Folder 2);
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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump TASK NUMBER: N0020080101 JPM NUMBER: 15-01 NRC RO A1-1 ALTERNATE PATH: D KIA NUMBER: ~~~~~~~~~~

2.1.25 IMPORTANCE FACTOR: 3.9 APPLICABILITY: RO SRO EOD RO[)) STAD SRoD EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S2.0P-AR.ZZ-0003, Overhead Annunciators Window C, Rev. 19 S2.0P-SO.RC-0004, Identifying and Measuring Leakage, Rev. 16 (Both Rev checked 8-9-16)

TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans I N Mulford Date: 9-22-16 I 9-29-16 SME or Instructor ~

Approved By:

Oper~ng ~a~r Approved By:

Ope~rtment 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 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~

SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump TASK NUMBER: N0020080101 SIMULATOR SETUP N/A INITIAL CONDITIONS:

Unit 2 is operating at 100% power, steady state, SOL.

At 0015, OHA C-2 CNTMT SUMP PMP START unexpectedly annunciates, along with OHA A-41.

The Aux typewriter shows 21 containment sump pump has started. 2 minutes later, OHA C-2 clears, OHA A-41 annunciates, and the Aux typewriter shows 21 containment sump pump has stopped. The plant remains stable, no indications of a RCS leak are apparent, and no operations have been performed which would cause containment sump level to rise.

INITIATING CUE:

You are the RO. Calculate the leak rate into the Containment Sump by performing Section 5.3 of S2.0P-SO.RC-0004, Identifying and Measuring Leakage.

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. Calculate leakage into Containment Sump of 0.85-1.0 gpm.

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

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~

SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

Provide blank copy of 82.0P-SO.RC-0004, and marked up copy of Attachment 1.

SO.RC-4 !E either Containment Sump Pump 5.3.1 AUTO starts, THEN RECORD the following on Attachment 1, Section 2.0:

Records 21 Cont Sump

...

Operating Containment Sump Pump Number

Time of pump start Records time of pump start as 0015 SO.RC-4 CALCULATE elapsed time in minutes Calculates elapsed time in minutes 5.3.2 between start time and previous between start time and previous Containment Sump Pump stop time Containment Sump Pump stop time and AND RECORD on Attachment 1, records on Attachment 1, Section 2.0 by Section 2.0. using previous stop time of 1855

yesterday, and with cue of 0015 today determines elapsed time is 320 minutes.

SO.RC-4 ENSURE no draining, sampling, or 5.3.3 liquid additions to Containment Sump Determines from initial conditions that have occurred during selected time no draining, sampling, or liquid additions frame. to Containment Sump have occurred during selected time frame.

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

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~-

SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

SO.RC-4 CALCULATE Containment Sump Calculates Containment Sump Leak 5.3.4 Leak Rate using Attachment 3. Rate using Attachment 3 (page 1 of 2),

and determines the 320 minute line crosses the 0.9 gpm leak rate line.

Note: Due to no increment between 300 and 350 minutes, extrapolation of data may result in leak rate slightly above or below 0.9 gpm. However, the leakrate MUST be determined to be within the bounding numbers for actions required

>0.85 gpm (to initiate Section 5.6) and

>1.0 gpm (to initiate S2.0P-ST.RC-0008)

SO.RC-4 RECORD Containment Sump Pump Records Containment Sump Pump stop 5.3.5 stop time and date on Attachment 1, time as 0017 and todays date on Section 2.0. Attachment 1, Section 2.0.

SO.RC-4 !E leakage to Containment Sump Determines leakage to Containment 5.3.6 exceeds 1.0 gpm AND Unit in Modes Sump does not exceed 1.0 gpm 1-4, THEN:

A. INITIATE S2.0P-ST.RC-0008(Q),

Reactor Coolant Water Inventory Balance.

B. REFER to Technical Specification 3.4.7.2.

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

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~-

SYSTEM: Reactor Coolant System TASK: Measure Leakage to the Containment Sump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

SO.RC-4 !E leakage to Containment Sump Determines leakage to Containment 5.3.7 exceeds 0.85 gpm, THEN INITIATE Sump does exceed 0.85 gpm, and Section 5.6 of this procedure. initiates Section 5.6 of procedure.

Terminate JPM when procedure is returned to evaluator.

Page 5 of 7 PSEG Restricted- Possession Requires Specific Permission From Nuclear Training

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 JPM usage, revalidate JPM using steps 8 and 11 below.

~ W\ ~ 1. Task description and number, JPM description and number are identified.

vv M ,,/ 2. Knowledge and Abilities (KIA) references are included.

\µ N'\ ~ 3. Performance location specified. (in-plant, control room, or simulator)

\y md 4. Initial setup conditions are identified.

Vv N'l A/ 5. Initiating and terminating Cues are properly identified.

\JV Md 6. Task standards identified and verified by SME review.

\f\ M / 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

~ N"\ d 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Jj_ Date t./* z. i. ' t IP

/C, N'\~ 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: ,,z. ~I.I SME/lnstructoro {)fLtj ~;l{Vcl J._q_hb_

Date: _ ' \.___{

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

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

INITIAL CONDITIONS:

Unit 2 is operating at 100% power, steady state, SOL.

At 0015, OHA C-2 CNTMT SUMP PMP START unexpectedly annunciates, along with OHA A-41.

The Aux typewriter shows 21 containment sump pump has started. 2 minutes later, OHA C-2 clears, OHA A-41 annunciates, and the Aux typewriter shows 21 containment sump pump has stopped. The plant remains stable, no indications of a RCS leak are apparent, and no operations have been performed which would cause containment sump level to rise.

INITIATING CUE:

You are the RO. Calculate the leak rate into the Containment Sump by performing Section 5.3 of S2.0P-SO.RC-0004, Identifying and Measuring Leakage.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 JPM NUMBER: 15-01 NRC RO A1-2 ALTERNATE PATH: D KIA NUMBER: ~~~~~~~~~~

2.1.43 IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EOCJ R0[8J STAL] SROCJ EVALUATION SETTING/METHOD: Classroom

REFERENCES:

SC.RE-ST.ZZ-0002(0), Rev. 23 SHUTDOWN MARGIN CALCULATION S2.RE-RA.ZZ-0016(Q), Rev. 8 CURVE BOOK (both checked 8-9-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 50 minutes Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans I N Mulford Date: 9-22-16 I 9-29-16 SME or lnstructo~l Approved By:

Tra~1ent Approved By:

Operbrtment 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 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~-

DATE:

SYSTEM: Conduct of Operations TASK: Calculate Shutdown Margin TASK NUMBER: N1200030301 INITIAL CONDITIONS: - Unit 2 Reactor Power is 100%.

- All Control Rod Group Demand Counters are at 227 steps.

- Current boron concentration is 300 ppm.

- Current core burn up is 10,000 EFPH.

- Control Rod 105 was been declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

- Control Rod 105 has been identified as trippable and is currently at 214 steps.

INITIATING CUE:

The current time is 1010.

This is a time critical JPM. Time will commence when you are provided with the applicable procedures.

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

Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

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

Task Standard for Successful Completion:

1. Perform SOM calculation and determine SOM is -2441 (+/- 5 pcm) and SAT.

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OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~~-

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(*Denotes a Critical Step) SIU (Required for UNSAT evaluation)

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

ST.ZZ-0002(0).

Obtains copy of 82.RE-RA.ZZ-0016 I Curve Book. Provide Rev. 8 of Curve Book.

I Evaluator: MARK start time of JPM:

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

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

5.1.1.C !E SOM is to be verified (per T/S Refers to Attachment 3.

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

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

with kett .:::. 1.0 2.1 Att. 3 Precautions and Limitations: Section Reviews and signs steps 3.1-3.5.

3.0 3.0 I

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

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

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

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

Att.3 Section 4 contains the data points Determines the following data and Section required and the calculations to calculations:

4.1 determine shutdown margin. 4.1.1 100%

4.1.2 300 ppm 4.1.3 D@ 227 steps 4.1.4 10,000 EFPH 4.1.5 0 I 4.1.6 1 Att. 3 4.2.1 -3841 Section 4.2.2 -3335 4.2 4.2.3 728 4.2.4 0 4.2.5 500 4.2.6 0 4.2.7 -5948 Att. 3 4.3.1 -5948 Section 4.3.2 645 4.3 4.3.3 120 4.3.4 2742 4.3.5 -2441 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 7

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

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

System: Conduct of Operations Task: Calculate Shutdown Margin

STEP NO. STEP STANDARD EVAL COMMENTS

(*Denotes a Critical Step) SIU (Required for UNSAT evaluation) 4.4 Att 4 Acceptance Criteria Reviews required SOM in MODE 1 or 2 of -1300 pcm and initials 4.4.1.

4.4.1 IS THE SOM (Item 4.3.5) EQUAL I

TO OR MORE NEGATIVE THAN Determines calculated SOM is SAT and I

(-)1300 PCM? initials SAT.

Evaluator: MARK stop time of JPM: when procedures are returned to proctor.

Total time from START to STOP is 50 minutes or less.

Terminating Cue: Once operator has returned procedures to proctor, terminate JPM.

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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 JPM usage, revalidate JPM using steps 8 and 11 below.

f\M. ~ 1. Task description and number, JPM description and number are identified.

f'M. -( 2. Knowledge and Abilities (KIA) references are included.

N"' / 3. Performance location specified. (in-plant, control room, or simulator)

N"\ / 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 7- z-z- 1 11>

13

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.

~ Date: )- 2 <: -t/,

~:_,.,(,

SME/lnstructor:

SME/lnstructor:C/ 1£,(A Date: _q~/~_q_/1b__

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

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

INITIAL CONDITIONS:

- Unit 2 Reactor Power is 100%.

- All Control Rod Group Demand Counters are at 227 steps.

- Current boron concentration is 300 ppm.

- Current core burnup is 10,000 EFPH.

- Control Rod 105 was been declared INOPERABLE at 1000 today due to

- -not moving out during a rod exercise test. You have been directed to perform a Shutdown Margin Calculation IAW SC.RE-ST.ZZ-0002 to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

- Control Rod 105 has been identified as trippable and is currently at 214 steps.

INITIATING CUE:

The current time is 1010.

This is a time critical JPM. Time will commence when you are provided with the applicable procedures.

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

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs TASK NUMBER: N0040420201 JPM NUMBER: 15-01 NRC RO Admin A2 ALTERNATE PATH: I....._ _.I KIA NUMBER: 2.2.37

~~~~-~--~~

IMPORTANCE FACTOR: 3.6 4.6 APPLICABILITY:

- -RO- - SRO EOLJ ROITJ STAD SROO]

EVALUATION SETTING/METHOD: ,~,~~*-

n/11:ihb Perform S2.0P-ST.CVC-0010, Rev. 10 (checked 9-28-16)

REFERENCES:

Salem Tech Specs TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 11 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: S Harris I J Pierce Date: 9-28-16 SME or lnstruc J\l, Approved By:

Training partme~

Date: 1*) ,/,

Approved By:

Operatic~! Date: /6jfl/1c, 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 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~

SYSTEM: Chemical and Volume Control TASK: Demonstrate the Operability of the RWST and/or the BASTs TASK NUMBER: N0040420201 SIMULATOR SETUP: N/A INITIAL CONDITIONS:

Salem Unit 2 is at 100% power.

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

21 BAT pump, and the leak, are isolated.

21 BAST level - 49.5%

22 BAST level - 49.5%

21 BAST temp - 98.2°F

22 BAST temp - 97.1°F

RWST temperature - 70°F

RWST levels are:

CHl-41.4'

CH II - 41.4'

CH 111-41.4'

CH IV-41.5'

Chemistry reports current RWST and BAST boron concentrations are:

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.

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 Attachment 2 of S2.0P-ST.CVC-0010 per key and determine the Surveillance is SAT PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8

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 S/U evaluation)

Provide marked up copy of S2.0P-ST.CVC-0010, Borated Water Sources and Tech Spec 3.1.2.6 (2 pa~es) 3.0 Precautions and Limitations Reads and initials steps.

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.

Att. 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 Ill: 41.4 CH IV: 41.5 Initials SAT for RWST Level and inserts date.

Att. 2 RWSTTemp Refers to initial conditions for RWST temperature 70°F. Initials SAT for RWST Temp and inserts date.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8

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 S/U evaluation)

Att. 2 RWST Cone 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 Refers to initial conditions for 21 and 22 BAST level and enters:

21 BAST vol- 49.5%

22 BAST vol - 49.5%

Uses Tech Spec 3.1.2.6.a, 3.1.2.6.b, and Figure 3.1-2 and determines 21 BAST Vol AND/OR 22 BAST Vol is SAT. Initials SAT for BAST volume and inserts date.

Att. 2 21 BAST Temp AND/OR 22 BAST Temp Refers to initial conditions for 21 and 22 BAST temp and records:

21 BAST temp - 98.2°F 22 BAST temp - 97.1°F Initials SAT for 21 BAST Temp AND/OR 22 BAST Temp and inserts date.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8

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 S/U evaluation)

Refers to initial conditions for BAST boron

Att. 2 21 BAST Cone 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 concentration is SAT. Initials and inserts date.

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 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 8

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 S/U evaluation)

JPM is complete when procedure is returned to evaluator.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 8

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.

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

\j-J Jl 2. Knowledge and Abilities (KIA) references are included.

\Y 7 h~ 3. Performance location specified. (in-plant, control room, or simulator)

\;J J 4. Initial setup conditions are identified.

\j'1 'A 5. Initiating and terminating Cues are properly identified.

~

\jJ 6. Task standards identified and verified by SME review.

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

~ /l 8. Verify the procedure referenced by this JPM matchys the most current revision of that procedure: Procedure Rev. _1_0_ Date 4-f IJ., l 13

\) ~ 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/lnstructo~JOL~ t.,, :J * "?,<'/<"'- Date: ~ [ 2-~ 1i <o SME/lnstructor;,A JJlJA,I.<% £1 S- il..6(n* ~ Date: - -c, /-i,g (l(.o SM Ell nstructor: Date: - - - - - -

~

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8

INITIAL CONDITIONS:

Salem Unit 2 is at 100% power.

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

21 BAT pump, and the leak, are isolated.

21 BAST level - 49.5%

22 BAST level - 49.5%

21 BAST temp - 98.2°F

22 BAST temp - 97.1°F

RWST temperature - 70°F

RWST levels are:

CH 1- 41.4'

CH 11 - 41 .4'

CH 111 - 41.4'

CH IV-41.5'

Chemistry reports current RWST and BAST boron concentrations are:

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 8 of 8

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

TASK: Perform Stay Time Calculation for Emergency Condition.

TASK NUMBER: N1200100104 JPM NUMBER: 15-01 NRC RO A3 ALTERNATE PATH: D KIA NUMBER:

i 2.3.4 IMPORTANCE FACTOR: - - 3.2 APPLICABILITY: RO SRO EoD Ro[K] STAD SROD EVALUATION SETTING/METHOD: Classroom

REFERENCES:

Radiological Survey Maps, RP-AA-203 Rev. 6, NC.EP-EP.ZZ-0304 Rev. 16 TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-9-16 Instructor Validated By: R Evans IN Mulford Date: 9-22-16 I 9-29-16 SME or lnst:t~~l Approved By:

T~ent Date: /0 )1/1 \_p Approved By:

O~rtment Date: !b/11//(~

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 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to complete.

Using the correct survey map, and conservatively using the HIGHEST dose rate anywhere in the pump 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:

YES job can be performed

2. Calculates new TEDE dose of 2005 mrem.

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

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)

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

Radiation Protection Response if asked for.

START TIME:

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

(Section 5.0 Note.)

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

Page 3 of 6

OPERATOR TRAINING PROGRAM NAME:

~---------

JOB PERFORMANCE MEASURE DATE: - - - - - - - - - -

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) 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 "22RH37" on the map and indicates 40 mrem/hr.

Note: The square with "250" inside it is in the RHR HX room, and is not in the area which the operator will go.

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of work will result in 80 mrem dose, and new TEDE dose is 2005 mrem, which does NOT exceed 4,500 mrem authorized in an Emergency.

Terminate JPM when candidate has returned paperwork.

4 STOP TIME:

Page 4 of 6

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.

Vv N'\ d 1. Task description and number, JPM description and number are identified.

\}-' N'\ ~ 2. Knowledge and Abilities (KIA) references are included.

vN'\-t 3. Performance location specified. (in-plant, control room, or simulator)

V M ~ 4. Initial setup conditions are identified.

v rt\ ~ 5. Initiating and terminating Cues are properly identified.

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

v- N1 / 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

\J N1 -( 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.-~-- Date S'~"Z"'-* '"'

N1 £ 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: 9- 2. ~ - '""

SME/lnstructor: ~lfw-J Date: q /q.ci/1b SME/lnstructor: Date:

Page 5 of 6

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to complete.

Using the correct survey map, and conservatively using the HIGHEST dose rate anywhere in the pump 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: 15-01 NRC SRO Admin A1-1 ALTERNATE PATH: ._I_ _.I KIA NUMBER: ~~~~~~~~~~

2.1.25 IMPORTANCE FACTOR: 4.2 APPLICABILITY: RO SRO EOCJ ROCJ STAL] SROCK]

EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S2.0P-ST.CBV-0003, Rev. 19 (checked 8-10-16)

TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME: 12 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-10-16 Instructor Validated By: R Boyer I P Williams Date: 9-28-16 / 10-4-16 SME or Instructor~

Approved By:

. Trammg rt;t.f<Vlt pa men Date: 1~//r0 Approved By:*

Op~artment Date:

10)/;1, 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

OPERATORTRAININGPROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~-

DATE:

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 IAW Step 5.3.4.

If any discrepancies are identified, note them and any actions that you would take on Attachment 8, Section 1.0, Comments.

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, Section 3.0, for 87 psid is incorrectly recorded as 1592. Identify the correct Minimum Flow Rate should be 1638.

2. Identify that the actual Cooling Water Flow Rate (1625) is below the Minimum Flow Rate required as shown on Attachment 1 and Exhibit 1, and the surveillance is UNSAT vs SAT.

Page 2 of 5 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, 21 CFCU Data Sheet,

Section 3.0, for 87 psid is incorrectly recorded as 1592. (This was due to operator performing ST rounding down as opposed to rounding up IAW P&L 3.4.)

Identifies correct value for Minimum Flow Required as 1638.

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

Identifies that the actual Cooling Water Flow Rate of 1625 gpm is below the Minimum Flow Rate of 1638 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 Permission from Nuclear Training

OPERATOR TRAINING 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.

V/ ~Task description and number, JPM description and number are identified.

IJ ./ £?2. Knowledge and Abilities (KIA) references are included.

\J / /J ~Performance location specified. (in-plant, control room, or simulator)

V. I tf/-V4. *Initial setup conditions are identified.

~ </!-A~nitiating and terminating Cues are properly identified.

U. 9 6. Task standards identified and verified by SME review.

\J I fj:) 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _j_!J_ Date s/u/1 L L~t 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.

._. =: . . !~

Date: -+--o/ a'--'----1/f,_

Date:_/~~.____*"4-~~{b=---

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 IAW Step 5.3.4.

If any discrepancies are identified, note them and any actions that you would take on , Section 1.0, Comments.

Page5of5 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 equipment allowed to be removed from service while SFP manipulations are in progress)

TASK NUMBER: N1120760102 JPM NUMBER: 15-01 NRC SRO A 1-2 ALTERNATE PATH: D KIA NUMBER:

~--------~

2.1.42 IMPORTANCE FACTOR: 3.4 APPLICABILITY: RO SRO EOCJ ROCJ STAL] SRO[TI EVALUATION SETTING/METHOD: Classroom or Simulator

REFERENCES:

S2.0P-IO.ZZ-0010, Rev. 33, S2.0P-SO.CH-0001 Rev 32, S2.0P-SO.SW-0005 Rev 42 S2.0P-SO.DG-0005, Rev. 6 (all rev checked 8-10-16) 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: 8-10-16 Instructor Validated By: R Boyer IP Williams Date: 9-28-16110-4-16 SME or Instructor Approved By: AA /J Date: 100~

Traini;~rtm~-,{(ft-t, Approved By: ~ Date: 10/1j1t, Op-;rations Depa"nt 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 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

~~~~~~~~~~~~~~~

DATE:

SYSTEM: Administrative TASK: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)

TASK NUMBER: N1120760102 INITIAL Salem Unit 2 is operating at199% 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 IAW S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , at which time it will terminate.

The unit has no active Tech Spec LCOs.

21 SW pump is CIT for emergent strainer work.

The current time is 0800.

INITIATING CUE:

You have been directed to review the upcoming work for the shift and determine which activities may proceed as scheduled while continuing the fuel movement in the Spent Fuel Pool uninterrupted.

Work scheduled for today Circle whether each activity may or may not be performed lE any of the activities cannot proceed, explain your reason(s) 0900- 22 SW pump packing replacement MAY MAY NOT 1000- 2A EOG tagout for maintenance MAY MAY NOT 1300- 21 Chiller compressor oil change MAY MAY NOT 1400- Delivery of New Fuel into the Fuel MAY MAY NOT Handling Building for upcoming refueling outage.

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 that 22 SW pp work, 2A EOG surveillance, and 21 Chiller work MAY be performed.

2. Determines that New Fuel delivery may NOT be performed.

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

'.'ii OPERATOR TRAINING PROGRAM NAME: _ _ _ _ _ _ _ _ _ __

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

System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)

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

Provide blank copies of:

S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations.

S2.0P-SO.DG-0005, Preparation for Removing a Diesel Generator from Service.

S2.0P-SO.SW-0005, Service Water System Operation.

S2.0P-SO.CH-0001, Chilled Water System Operation.

Provide copies of Tech Specs.

Page 3 of7 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 equipment allowed to be removed from service while SFP manipulations are in progress)

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

Notes:

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

Only one FHB exhaust fan is required to be backed by an operable EOG (IOP-10 P&L 3. 7 and page 17)

Operable SFP pumps only need one of them backed by operable EOG. (IOP-10 P&L 3.4 and page 17)

TSAS 3. 7 .10 allows a chiller to be taken out of service if movement of irradiated fuel is already on-going, and gives 14 days to restore it.

Two SW pumps are required to be operable, one of which is EOG backed.

(IOP-10 page 18.) The four remaining SW pumps are powered from Band C vital and their EDGs remain operable.

TSAS 3.7.4 will be entered for less than two operable SW loops, but is a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action.

Page 4 of7 PSEG Restricted - Possession Requires Specific Pennission from Nuclear Training

~

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 0 ATE: _ _ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Direct Actions for Spent Fuel Movement (Determine equipment allowed to be removed from service while SFP manipulations are in progress)

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

Notes: (cont)

FHB Truck Bay Door is required to be closed. (IOP-10 paqe 19)

Determines that:

22 SW pump work MAY be performed.

2A EOG surveillance MAY be performed.

21 Chiller oil replacement MAY be performed.

New Fuel delivery may NOT be performed because FHB Truck Bay door is required to be closed per IOP-10, page 19.

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

Page 5 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

Name:

OPERATOR TRAINING 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 .

.Id' 01. Task description and number, JPM description and number are identified.

~Knowledge and Abilities (KIA) references are included.

,/._ d ~Performance location specified. (in-plant, control room, or simulator) 1.d<f:Z--4. Initial setup conditions are identified.

/ A~. Initiating and terminating Cues are properly identified.

j ff ~-Task standards identified and verified by SME review.

I a~ Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~erify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. ilei,y1J'.,S Date 1h.!J I<,

~at 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: - - - - - -

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

Page 6 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

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 IAW S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations, and will continue without interruption for the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , at which time it will terminate.

The unit has no active Tech Spec LCOs.

21 SW pump is C/T for emergent strainer work.

The current time is 0800.

INITIATING CUE:

You have been directed to review the upcoming work for the shift and determine which activities may proceed as scheduled while continuing the fuel movement in the Spent Fuel Pool uninterrupted.

Work scheduled for today Circle whether each activity may or may not be performed lE any of the activities cannot proceed, explain your reason(s) 0900- 22 SW pump packing replacement MAY MAY NOT 1000- 2A EOG tag out for maintenance MAY MAY NOT 1300- 21 Chiller compressor oil change MAY MAY NOT 1400- Delivery of New Fuel into the Fuel MAY MAY NOT Handling Building for upcoming refueling outage.

Page 7 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance to calculate Shutdown Margin TASK NUMBER: 1200030301 JPM NUMBER: 15-01 NRC SRO A2 ALTERNATE PATH: D KIA NUMBER: ~~~~~~~~~~

2.2.12 IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EoD ROD STAD sRo[KJ EVALUATION SETTING/METHOD: Classroom

REFERENCES:

SC.RE-ST.ZZ-0002, Rev. 23 Shutdown Margin Calculation S2.RE-RA.ZZ-0016, Rev. 8 Figures Salem Unit 2 Technical Specifications TSAS 3.1.3.1 Movable Control Assemblies TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 20 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 30 minutes Developed By: G Gauding Date: 8-10-16 Instructor Validated: R Boyer I P Williams Date: 9-28-16 / 10-4-16 Approved By: s~:~f;( Date: 10//rl.

Tra/1:~nment Approved By: Date: 1oj1~r.,

Operations Repr entative 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:

SYSTEM: Administrative TASK: Review a completed surveillance to calculate Shutdown Margin TASK 1200030301 NUMBER:

INITIAL CONDITIONS:

- Unit 2 Reactor Power is 100%.

- All Control Rod Group Demand Counters are at 227 steps.

- Current boron concentration is 300 ppm.

- Current core burnup is 10,000 EFPH.

- Control Rod 105 was declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. A Shutdown Margin Calculation has been performed IAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

- Control Rod 105 has been identified as trippable and is currently at 214 steps.

- The current time is 1030.

INITIATING CUE:

1. Review the attached SOM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.

2. Note any discrepancies found by the review on Attachment 7.

3. Determine if SOM is SAT.

This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are returned to proctor.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

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

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made Task Standard for Successful Completion:

1. Determines the incorrect value for Control Bank Worth and Shutdown Bank Worth have been used.

2. Determines SOM with correct values used is SAT.

3. Completes review within 30 minutes.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 6

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

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

System: ADMINISTRATIVE Task: Review a completed surveillance to calculate Shutdown Margin STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

NO. SIU Evaluation)

Note to Evaluator: The time critical aspect refers to the time required when the Shutdown Margin requirement of TSAS 3.1.3.1.c must be met.

1 Provide the marked up copy of SC.RE- Ensures Sections 3 and 4 are completed.

ST.ZZ-0002 and copy of S2.RE-RA.ZZ-0016, Curve Book.

Time Start:

2 Review Section 5 to ensure the correct Reviews Section 5 and determines the correct Attachment was performed. Attachment (3) was performed.

3 Review the completed Shutdown Reviews SOM and determines:

Margin Calculation: 1. An incorrect value for Total Control Bank Worth (Step 4.2.1) has been used (0 EFPH value vs current

10,000 EFPH value)

2. An incorrect value for Total Shutdown Bank Worth (Step 4.2.2)has been used (0 EFPH value vs current 10,000 EFPH value)

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 6

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

JOB PERFORMANCE MEASURE DATE:- - - - - - - - - - -

System: ADMINISTRATIVE Task: Review a completed surveillance to calculate Shutdown Margin STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

NO. S/U Evaluation)

3 3. Determines Trippable Rod Worth is can't incorrect based on incorrect steps 4.2.1 and 4.2.2)

4. Determines Ten Percent Rod Worth Penalty (step 4.3.2) is incorrect based on incorrect steps 4.2.1 and 4.2.2)

5. Determines SOM is incorrect based on incorrect steps 4.2.1 and 4.2.2 and 4.3.2)

Correct Values are:

4.2.1 -3841 4.3.1 -5948 4.2.2 -3335 4.3.2 645 4.2.3 728 4.3.4 2742 4.2.4 0 4.3.5 -2441 4.2.5 500 4.2.6 0 4.2.7 -5948

4 Acceptance Criteria Determines Acceptance Criteria are still met with correct values used.

Turns in procedures within 30 minutes of start time.

Time Stop:

- - - Total time to complete JPM MUST be 30 minutes or less.****

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

I 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 JPM usage, revalidate JPM using steps 8 and 11 below.

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

v / }t; 2. Knowledge and Abilities (KIA) references are included.

"'- / ; ~3. Performance location specified. (in-plant, control room, or simulator) v ~4. Initial setup conditions are identified.

\r I J~ 5. Initiating and terminating Cues are properly identified.

v- / P/ 9--6. Task standards identified and verified by SME review.

\]'-

~Critical steps meet the criteria for critical steps and are identified with an asterisk (').

~Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev.~ Date _1:;~/"'~l'_'*-_ __

J D9. 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.

Date: r6yj,£_

Date: --./9f---<Tm~~--

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

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

- Unit 2 Reactor Power is 100%.

- All Control Rod Group Demand Counters are at 227 steps.

- Current boron concentration is 300 ppm.

- Current core burnup is 10,000 EFPH.

- Control Rod 105 was declared INOPERABLE at 1000 today due to not moving out during a rod exercise test. A Shutdown Margin Calculation has been performed IAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, to satisfy the action requirement of TSAS 3.1.3.1 Action c.3.

- Control Rod 105 has been identified as trippable and is currently at 214 steps.

- The current time is 1030.

INITIATING CUE:

1. Review the attached SOM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.

2. Note any discrepancies found by the review on Attachment 7.

3. Determine if SOM is SAT.

This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are returned to proctor.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Determine required actions upon Radioactive Effluent Monitor failure TASK NUMBER: N1200010301 JPM NUMBER: 15-01 NRC SRO Admin A3 ALTERNATE PATH: CJ KIA NUMBER: _________ 2.3.11 _,

IMPORTANCE FACTOR: 4.3

- -RO- - SRO APPLICABILITY:

EOCJ ROCJ STAL] SRO[ZJ EVALUATION SETTING/METHOD: Classroom Salem ODCM, Salem Tech Specs, S1 .OP-SO.WL-0001, Rev. 27, S1 .OP-SO.WG-

REFERENCES:

0011, Rev. 31, S1 .OP-SO.CBV-0002, Rev. 21 (All checked 8-10-16)

TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME: 25 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-10-16 Instructor Validated By: Date: 9-28-16 / 10-4-16 Approved By:

Approved By:

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

CONDITIONS:

Radiation Monitor 1R12A, Containment Noble Gas, failed its Source Check when preparing to perform a normal Containment Pressure Relief IAW S1 .OP-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 Prior to initiating the Containment Pressure Relief, Rad Monitor 1R41 D, Plant Vent CUE: Release Rate, indication fails high, and is confirmed as an instrument failure.

For the following radiological releases, determine:

1) Can the release be performed with the failed monitors described above, and,

2) If the release can be performed, what compensatory actions are required, if any.

Assume each release will be performed individually.

RELEASES CAN BE RELEASED? COMP ACTION REQ

14 GOT release YES I NO

Containment Pressure Relief YES I NO

11 CVCS Monitor Tank release YES I NO 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 ALL the releases may be performed.

2. Determines additional compensatory measures apply for the Waste Gas Release and the Containment Pressure Relief per key, and no additional compensatory actions are required for Liquid Release.

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)

Provide blank copies of:

S1 .OP-SO.WG-0011 S1 .OP-SO.CBV-0002 S1 .OP-SO.WL-0001 Salem ODCM Waste Gas Release Determines ODCM 3.3.3.9 applies to S1 .OP-SO.WG-0011 Gaseous Effluent which directs actions per Table 3.3-13.

Determines Table 3.3-13, Instrument #1, Waste Gas Holdup System is applicable, which requires (1) 1R41A~ D. Action 31 applies.

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OPERATOR TRAINING PROGRAM NAME:

DATE: _ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE 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 members 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, Attachment 2, 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND analyzed for gaseous principal

~amma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8

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)

Containment Pressure Relief Determines that Precaution and Limitation S1 .OP-SO.CBV-0002 2.3 of S1 .OP-SO.CBV-0001 directs operator to notify Chemistry to comply with the contingency actions associated with the ODCM prior to performing a Containment Pressure Relief.

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

With both channels (1 R41A ~DOR 1R12A) inoperable, Action 37 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 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.

Note: Applicant may identify compensatory actions per P&L 3.11

Waste Liquid Release Determines no compensatory actions are S1 .OP-SO.WL-0001 required to initiate the Liquid Release.

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 JPM usage, revalidate JPM using steps 8 and 11 below.

\}v / ~ 1f1*. Task description and number, JPM description and number are identified.

\j- / ~~- Knowledge and Abilities (KIA) references are included.

Vv / ~<{Ji;j. Performance location specified. (in-plant, control room, or simulator)

~ I ~ ~- Initial setup conditions are identified.

'-J ./- r- ~- Initiating and terminating Cues are properly identified.

/r P6. Task standards identified and verified by SME review.

l""'-[;?7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

,eA-- ~*Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _ _ Date----..,----

/)_.,,- A\\ N-v:t.:JJ'~ ~w ~fz.<1;ltio

~ 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

r-Jft/8;;-(i_Dthe JPM cannot be performed as written with proper responses, then revise the JPM .

. . w'fT11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SM81nstructo~-~(t;_ Date: ci /2$} lb SME/lnstructor: ~/ fv; ~J--L Date: l~C 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 IAW S1 .OP-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 D, Plant Vent Release Rate, indication fails high, and is confirmed as an instrument failure.

For the following radiological releases, determine:

1) Can the release be performed with the failed monitors described above, and,

2) If the release can be performed, what compensatory actions are required, if any.

Assume each release will be performed individually.

RELEASES CAN BE RELEASED? COMP ACTION REQ

14 GOT release YES I NO

Containment Pressure Relief YES/ NO

11 CVCS Monitor Tank release YES I NO PSEG Restricted - Possession Requires Specific 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: 15-01 NRC SRO Admin A4-1 (ESG-1)

ALTERNATE PATH: _ I_ _I KIA NUMBER: ~~~~~~~~~~

2.4.41 IMPORTANCE FACTOR: 4.6 APPLICABILITY: RO SRO EoD ROD STAD SRO[K]

EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

EP-SA-111-F2 Rev. 2 (ALERT)

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: 9-19-15 Instructor Validated By: C Davis IP Williams Date: 9-21-16110-4-16 SME or Ins ruct~

Approved By:

Traini epaUent Date: 1ff u Approved By: Date: 1oj;j1r, obepartment 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. Declare an ALERT under EAL RB3.P within 15 minutes of start time, and provide ICMF to the Primary Communicator within the next 15 minutes.

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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)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT S/U evaluation)

Provide candidate with 'Tear-off sheet" Reviews initial conditions and EOP's (as and Blank Copies of EP-SA-111-F1 necessary - 5 minute limit prior to starting) through F4 (UE, ALERT, SAE, GE)

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 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 of 8

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)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT 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.

If time allows, DIRECT Classification Att 2 Cue: No independent verification will be A.3 Independent Verification to be performed.

performed.

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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)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT S/U evaluation)

Att 2 After Classification Independent Declares an ALERT under RB3.P within A.4 Verification is obtained: 15 minutes of Start Time:

DECLARE the ALERT (enter time and date on ICMF)

Completes and Approves the ICMF as

*COMPLETE I APPROVE the ICMF follows:

EAL#(s): RB3.P Description of Event: Potential Loss of the Reactor Coolant System Boundary Note: Description of Event is found in EAL Description Table Fills out Section Ill:

Checks IS NOT for a Radiological Release in progress.

Fills out Section IV:

Retrieves wind speed (10)and direction (160) data from SPDS Initials for a1212roval to transmit Att 2 ' I i A.5 If time allows OBTAIN accuracy peer check of the completed ICMF Cue: No peer check will be performed.

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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)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD forUNSAT S/U evaluation)

Att 2 A.6 Continue with NOTIFICATION AND ACTIVATION as follows:

If not previously performed, ACTIVATE I DIRECT ACTIVATION of ERO Cue: Activation of ERO Emergency Callout is not required for this JPM.

Emergency Callout (EP 96-003)

DIRECT the Primary Communicator to Provides ICMF to Primary Communicator implement ECG Attachment 6 within 15 minutes of event declaration Terminate JPM when ICMF is given to the Evaluator.

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TQ-AA-106-0303 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.

\,tJ /~~Task description and number, JPM description and number are identified.

/ 1),-.._~- Knowledge and Abilities (KJA) references are included.

/ ~ Performance location specified. (in-plant, control room, or simulator)

/ ~- Initial setup conditions are identified.

/ ~4--s. Initiating and terminating Cues are properly identified.

~-Task standards identified and verified by SME review.

l-.... <fh. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

t,_tfi> 8. Verify the procedure referenced by this JPM matches the most current revision of

~hat procedure: Procedure Rev. __1_ Date '\ -'lf. { 6 f/\..,, 9. Pilot test the JPM:

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

b. ensure performance time is accurate.

~-~. If the JPM cannot be performed as written with proper responses, then revise the JPM.

(,,,.._ ~When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor~Af° Date:~

SME/lnstructor: /~~J Date:~

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

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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."-lf 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.

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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: 15-01 NRC SRO Admin A4-1 (ESG-2)

ALTERNATE PATH: KIA NUMBER: ~~~~~~~~~~

2.4.41 IMPORTANCE FACTOR: 4.6 APPLICABILITY: RO SRO EOCJ ROCJ STAC] SRO[IJ EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

EP-SA-111-F2 Rev. 2 (ALERT)

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: 9-19-15 Instructor Validated By: Date: 9-21-16110-4-16 Approved By:

Approved By:

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-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. Declare an ALERT under EAL RB3.L within 15 minutes of start time, and provide ICMF to the Primary Communicator within the next 15 minutes.

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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-2)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT S/U evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as and Blank Copies of EP-SA-111-F1 necessary - 5 minute limit prior to starting) through F4 (UE, ALERT, SAE, GE)

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 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 of 8

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)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT 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.

If time allows, DIRECT Classification Att 2 Cue: No independent verification will be A.3 Independent Verification to be performed.

performed.

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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-2)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT S/U evaluation)

Att 2 After Classification Independent Declares an ALERT under RB3.L within A.4 Verification is obtained: 15 minutes of Start Time:

DECLARE the ALERT (enter time and date on ICMF)

Completes and Approves the ICMF as

*COMPLETE I APPROVE the ICMF follows:

EAL#(s): RB3.L Description of Event: Loss of the Reactor Coolant System Boundary Note: Description of Event is found in EAL Description Table Fills out Section Ill:

Checks IS for a Radiological Release in progress.

Fills out Section IV:

Retrieves wind speed (10)and direction (160) data from SPDS Initials for aggroval to transmit Att 2 A.5 lftime allows OBTAIN accuracy peer check of the completed ICMF Cue: No peer check will be performed.

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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-2)

COMMENTS STEP STEP (Required

(*Denotes a Critical Step) EVAL

NO. STANDARD for UNSAT S/U evaluation)

Att 2 A.6 Continue with NOTIFICATION AND ACTIVATION as follows:

If not previously performed, ACTIVATE I DIRECT ACTIVATION of ERO Cue: Activation of ERO Emergency Callout is not required for this JPM.

Emergency Callout (EP 96-003)

DIRECT the Primary Communicator to Provides ICMF to Primary Communicator implement ECG Attachment 6 within 15 minutes of event declaration Terminate JPM when ICMF is given to the Evaluator.

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TQ-AA-106-0303 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.

l-... ~Task description and number, JPM description and number are identified.

~Q.*Knowledge and Abilities (KIA) references are included.

0 U°3:'Performance location specified. (in-plant, control room, or simulator)

&-t& Initial setup conditions are identified.

V\ Qs.-lnitiating and terminating Cues are properly identified.

0, ~Task standards identified and verified by SME review.

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

~ {/)s. Verify the procedure referenced by this JPM matches the m2st current revision of

that procedure: Procedure Rev.~ Date fl, it.[(.,,_

~BPilot test the JPM:

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

b. ensure performance time is accurate.

{/\_ ~- If the JPM cannot be performed as written with proper responses, then revise the JPM.

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

SME/lnstructor: ~

SME/lnstructor~/lt~

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

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 8

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 8 of 8

OPERATOR TRArnING PROGRAM JOB PERFORlVIAl~CE MEASURE STATION: SALEM SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 JPM NUMBER: 15-01 NRC Sim a ALTERNATE PATH: I x I K/A NUMBER: 001 A4.03

~~~~~~~~~~~

IMPORTANCE FACTOR: 4.0 3.7 APPLICABILITY: RO SRO EoO ROCK] STAD SROCK]

EVALUATION SETTING/METHOD: Simulator

REFERENCES:

S2.0P-ST.RCS-0001, Rev. 22 (checked 8-3-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-3-16 Instructor Validated By: M Lutek I W Russell Date: 8-22-16 SME or Instructor Approved By: tv'\ ~ Ffl'-\

Train in partment Approved By:

Ope~ment 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 PROGRAlVI JOB PERFORMAl~CE MEASURE JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS SYSTEM: Rod Control TASK: Perform a Control Rod Operability Verification TASK NUMBER: N0010070101 SIMULATOR IC: IC-251 in 15-01 NRC JPMs 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 Note to Evaluator: OP-AP-300-1001 required a peer check for all non-emergency manual rod motion.

Do NOT correct operator if a mistake is made when performing a peer check. For all required peer checks simply state "Peer check SAT".

OPERATOR TRAINING PROGRANI 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 Cabinets.

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:

SDA SOB SOC SOD F-04 229 G-03 229 E-03 229 C-05 229 D-10 228 C-09 227 C-11 223 E-13 223 K-12 227 J-13 227 L-13 224 N-11 224 M-06 227 N-07 229 N-05 224 L-03 227 B-04 230 J-02 223 D-14 224 C-06 223 P-12 229 G-13 227 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 NRG 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.

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. STANDARD S/U Evaluation)

Provide marked up copy of S2.0P-ST.RCS- Reviews Prerequisites.

0001, Rev. 22, with Prerequisite Sections 2.1-2.8 filled out.

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

Reviews and signs Precautions and Limitations.

Cue: lE 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 .... Determines step is N/A based on steady state 100% operation.

5.1.2 PERFORM Attachment 2, Rod Control System Performs Attachment 2 Rod Control Voltage Checks as follows: System Voltage Checks by:

A. PLACE Rod Bank Selector Switch to A. Places Rod Bank Selector Switch "MANUAL". to manual.

- B. Direct Maintenance to COMPLETE B. Directs Direct Maintenance to Attachment 2, Rod Control System complete Attachment 2, Rod Voltage Checks. Control System Voltage Checks.

Cue: Maintenance reports Attachment 2 Rod Control System Voltage Checks are complete SAT.

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. STANDARD SIU Evaluation)

Note _The Shutdown Rod Insertion Limit (TS Initials both notes.

3.1.3.4) is not applicable during the performance of this test for rods actually undergoing testing.

_Steps 5.1.3 through 5.1.10 may be performed in anv order.

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. STANDARD S/U Evaluation) 5.1.3 PERFORM Shutdown Bank A testing as follows:

A. lE the Rx is critical, THEN ENSURE T avg Checks Tave/Tref recorder on 2RP4 and is within +/-1°F of Tret* notes Tavg is within 1°F of Tref ..

B. PLACE Bank Selector Switch in the Rotates Bank Selector Switch fully counter

"SBA" 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 GRP. SELECT "C" lights are illuminated Power Cabinets 21AC and 22AC. on Rod Control System Power Cabinets 21 AC and 22AC.

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

D. Maneuver Shutdown Bank A at least 10 IAW OP-AA-300-1001, prior to rod

steps in any one direction. movement, operator states initial Shutdown Bank A position, target control rod position, and direction of rod movement, then inserts SBA at least 10 steps to stated target position.

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.

F. RECORD Shutdown Bank A "Test Initials SAT for Groups 1 and 2 for SBA on Results" by initialing in Attachment 1. Att 1.

G. RESTORE Shutdown Bank A to pre-test Operator states initial Shutdown Bank A

condition. position, target control rod position, and direction of rod movement, then withdraws SBA to stated target ARO position.

Continuous rod withdrawal is acceptable.

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. STANDARD S/U Evaluation) 5.1.4 PERFORM Shutdown Bank B testing as follows:

A. lE the Rx is critical, THEN ENSURE Tavg Checks Tave/Tref recorder on 2RP4 and is within +/-1°F of Tref* notes Tavg is within 1°F of Tref.

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

"SBB" position. the SBB position.

C. ENSURE GRP. SELECT "C" lights are Contacts NEO and directs him to verify illuminated on Rod Control System GRP. SELECT "C" lights are illuminated Power Cabinets 21 BD and 22BD. on Rod Control System Power Cabinets 21 BD and 22BD.

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

D. MANUEVER Shutdown Bank B at least Operator states initial Shutdown Bank B

10 steps in any one direction. position, target control rod position, and direction of rod movement, then inserts SBB at least 10 steps to stated target position.

E. ENSURE each rod in Shutdown Bank B SIMULATOR OPERATOR: INSERT RT-1 indicated rod movement of at least 1O when the operator is checking rod position steps. after insertion. This will trip 21 SGFP.

Responds to 21 SGFP trip by tripping the

Rx IAW P&L 3.13. (This is Alternate Path)

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

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

OPERATOR TRAINING PROGRAM JOB PERFORlVIAl~CE 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.

V / 'd-lJ'll1. Task description and number, JPM description and number are identified.

(,A I rlfll 2. Knowledge and Abilities (KIA) references are included.

V ./ ~ ltQl3. Performance location specified. (in-plant, control room, or simulator)

V I '?r-lft. Initial setup conditions are identified.

V I (;- L£1. Initiating and terminating Cues are properly identified.

(/"' I (r- ~.Task standards identified and verified by SME review.

v I §-~. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

(, I ~ ~. Verify the procedure referenced by th is J PM matches thepost current revision of iJ1 that procedure: Procedure Rev. _21_ Date ~/ 1 :e, ti ~

~ 9. Pilot test the JPM:

/{/\ a. verify Cues both verbal and visual are free of conflict, and 1

wu \ b. ensure performance time is accurate.

0 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: _ _ f_V\_L_v_t_-t..-_L_____ Date: ~f ,_,_)If::,

SM E/I nstructor:~f/i~* -'~IL4(~-"--+--~£~.=f.=~*=e1/"'-'-

. __ Date: _ _ f" /~-z:i--+L_,__d~o*_

r '

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

OPERATOR TRAINING PROGRA1"VI 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 Cabinets.

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:

SDA SOB SOC SOD F-04 229 G-03 229 E-03 229 C-05 229 D-10 228 C-09 227 C-11 223 E-13 223 K-12 227 J-13 227 L-13 224 N-11 224 M-06 227 N-07 229 N-05 224 L-03 227 8-04 230 J-02 223 D-14 224 C-06 223 P-12 229 G-13 227 M-02 230 N-09 230

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

STATION: SALEM SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sump blockage TASK NUMBER: N 1150900501 JPM NUMBER: 15-01 NRC Sim b ALTERNATE PATH: I x I KIA NUMBER:

!2.4.4 IMPORTANCE FACTOR: 4.5 4.7 APPLICABILITY: RO SRO EOr=J RO[KJ STAD SRO[KJ EVALUATION SETTING/METHOD: Simulator I Perform 2-EOP-LOCA-1, REV. 30, 2-EOP-LOCA-3, Rev. 30, 2-EOP-APPX-7, Rev. 0, OP-

REFERENCES:

AA-101-111-1003, Rev. 6 (All rev checked 5/9/16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Developed By: G Gauding Date: 5-9-16 Instructor Validated By: D Cox I M Lutek Date: 8-22-16 SME or Instructor Approved By:

Tra~~~j{'t Date: lo lo/"

Approved By:

Oper~ent Date: /o /1Dj;r.,

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: Emergency Operating Procedures TASK: Perform Actions for Containment Sump blockage TASK NUMBER: N1150900501 SIMULATOR SETUP: RT-1 MALFS: VL0120 21SJ44 fails to position (0-100%) Severity 1.0 VL0121 22SJ44 fails to position (0-100%) Severity 2.0 I/O's: AA04 B LO 21SJ44 SIS SUMP VALVE OPEN: ON AAOS B LO 21SJ44 SIS SUMP VALVE OPEN: ON AAOS CLO 22SJ44 SIS SUMP VALVE CLOSED: OFF AA04 CLO 21SJ44 SIS SUMP VALVE CLOSED: OFF ET-1 KAA01TPN 21 RHR pump STOP PB, tied to delete VL0120 ET-3 KAA01TPN 21 RHR pump STOP PB, tied to delete VL0121

- - Check SJ44 OPEN lights are lit.***

Mark up LOCA-3 up to step 21.

INITIAL CONDITIONS:

A LBLOCA has occurred.

The crew has responded by performing TRIP-1 and LOCA-1.

The crew is performing LOCA-3 with all AC buses energized from off-site power, and is waiting at step 21 for RWST lo-lo level alarm.

All ECCS pumps are operating except 22 CS pump which was stopped at step 8.

INITIATING CUE:

You are the Reactor Operator. Continue performing LOCA-3.

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. Secure all ECCS pumps.

2. Reestablish recirculation flow with ONE RHR pump and ONE charging OR SI pump.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation)

Simulator Operator: Insert RT-1 to cause cavitation of both RHR pumps.

Determines ECCS pumps are exhibiting signs of cavitation and recognizes entry into APPX-7 is warranted from Continuous Action Summary.

Evaluator: IF the intention to stop the cavitating RHR pumps is voiced, THEN FOR RO APPLICANT ONL Y1 IMMEDIATELY CUE:

The CRS directs you to implement Appendix-7. (This is to prevent activation of Event Trigger when 21 RHR pump is stopped.

CUE IF REQUIRED: The CRS directs you to implement Appendix-?.

Note: Operator may go to EOP-LOCA-5, but first step of LOCA-5 will direct performance of APPX-7. Use above cue if required in LOCA-5.

Evaluator: Provide paper copy of 2-EOP-APPX-7.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block -*- -

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation}

APPX-7 CAUTION

Any pump receiving suction from Evaluator: Stopping RHR pumps here an RHR pump should be stopped WITHOUT first stopping any SI or Charging before stopping the RHR pump. pumps receiving suction from RHR pump

If any Charging Pump, SI Pump, discharge is failure criteria.

or Containment Spray Pump loses suction or shows indication of cavitation, the pump should be stopped.

1 (CAS) MONITOR RHR Pump suction conditions:

a. CHECK NO indications of Determines BOTH RHR pumps exhibit signs cavitation. of cavitation, as well as ALL ECCS pumps

Pump Amps - stable and normal being supplied from RHR pumps.

for discharge pressure and flow.

Flow - stable and normal for discharge pressure.

Discharge Pressure - stable and normal for flow

Oscillations - none indicated PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: Emergency Operating Procedures TASK Perform Actions

-- for Containment

--- --- --- S -- - - - block STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation) 1.a a. PERFORM the following:

RNO 1. ENSURE 21 RH29 AND 22RH29 Places 21 RH29 and 22RH29 in AUTO.

in AUTO.

2. STOP ANY Charging Pump or SI Stops 21 and 22 Charging pumps and 21 and Pump taking suction from 22 SI pumps.

affected RHR Pump(s)

3. IF indications of cavitation Determines pump cavitation is continuing, continue, THEN CLOSE 21 CS36 verifies 21 CS36 and 22CS36 are shut.

AND 22CS36, RHR TO CS VALVE.

4. lE indications of cavitation continue AND radiological conditions permit, THEN PERFORM the following: CUE: Radiation Protection has determined

a. SEND an operator to release both RHR pump rooms to be unavailable for tags and restore CA to access due to high radiation levels.

RH18(s).

b. CLOSE affected RH18(s).

5. lE indications of cavitation Determines RHR pump cavitation is continue, THEN REMOVE continuing, and removes lockout from 21 SJ49 LOCKOUT(s) AND CLOSE and 22SJ49 RHR TO COLD LEG and shuts affected SJ49(s), RHR TO COLD 21 SJ49 and 22SJ49.

LEG.

6. lE indications of cavitation Determines indications of cavitation continue, continue, THEN STOP affected and stops 21 and 22 RHR pump.

RHR Pump(s). Simulator Operator: Ensure ET-1 and ET-3 are TRUE when 21 and 22 RHR pump STOP PBs are depressed. This removes the SJ44 failures.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation) 2 CHECK ALL AVAILABLE CFCUs Determines all CFCUs are running in Low running in Low Speed. Speed.

3. SECURE Containment Spray flow path:

a. STOP ALL Containment Spray Stops 21 CS pump.

Pumps.

b. CHECK 21CS36 AND 22CS36 Determines 21 CS36 and 22CS36 are shut.

CLOSED.

4. (CAS) CHECK RWST level >1.2 feet. Determines RWST level is >1.2 feet.

5. ATTEMPT to establish RHR Pump suction:

a. CHECK 21 SJ44 AND 22SJ44 Determines 21 SJ44 AND 22SJ44 are open.

OPEN.

b. CHECK AT LEAST ONE RHR Determines NEITHER RHR Pumps is running Pump running, with suction with suction aligned to Containment Sump.

aligned to Containment Sump.

5.b b. PERFORM the following:

RNO 5.b 1. REMOVE LOCKOUT(s) AND Determines 21 SJ49 and 22SJ49 previously RNO CLOSE affected SJ49(s) RHR shut.

DISCH TO COLD LEG.

5.b 2. ENSURE 21 RH29 AND 22RH29 Determines 21 RH29 and 22RH29 are in RNO in AUTO AUTO.

5.b 3. START ONE RHR Pump. Starts 21 OR 22 RHR pump.

RNO PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: Emergency Operating Procedures TASK Perform Actions for Containment

- - S block STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD SIU UNSAT evaluation) 5.b 4. !E indications of cavitation occur, Determines cavitation is NOT occurring.

RNO THEN STOP the running RHR pump, AND START the other RHR pump.

5.b 5. !E NO RHR Pumps can be run Determines RHR pump can be run without RNO without cavitation, THEN STOP cavitation.

any running RHR Pumps AND GO TO Step 8.

5. c) CHECK 21 RH29 AND 22RH29 Determines 21 RH29 and 22RH29 are in in AUTO. AUTO.

d) REMOVE LOCKOUT(s) AND Determines BOTH SJ49's are shut.

CLOSE affected SJ49(s) RHR DISCH TO COLD LEG.

e) CHECK ONLY ONE RHR Pump Determines only one RHR pumps is running.

running with suction from Containment Sump.

6. ATTEMPT to establish Charging Pump or SI Pump flow in recirculation mode: Checks Charging Pump and SI Pump suction

a. CHECK Charging Pump and SI aligned to running RHR pump by:

Pump suction aligned to running a.1. Checks 2SJ67 and 2SJ68 SHUT RHR pump. a.2 Checks 22SJ45 OPEN a.3 Checks 21 SJ45 OPEN a.4 Checks 21 SJ113 and 22SJ113 OPEN a.5 Checks 2SJ1 and 2SJ2 OPEN a.6 Checks 2SJ30 SHUT

b. CHECK ONLY ONE Charging Determine NO Charging or SI pumps are Pump OR SI Pump running. running.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for Containment Sumo block --

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT evaluation)

6.b START OR STOP, Charging and SI Starts ONLY ONE Charging or SI pump.

RNO Pumps, as required, to obtain ONLY ONE pump running in recirculation Note: Per the NOTE at top of page 3, the alignment. intent of Step 6 is to start only a single pump (Charging or SI), and it is preferable to start a Charging pump. SAT performance of Step 6 does not require starting a Charging pump, just one of the 4 available charqinq or SI pumps.

6 c. CHECK Charging Pump or SI Determines Charging or SI pump is running in Pump running in recirculation recirculation alignment.

alignment.

d. GO TO Step 9 Terminate JPM when operator goes to Step 9.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE TQ-AA-106-0303 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 J I ~/ 1. Task description and number, JPM description and number are identified.

V !~I r /2.

1 Knowledge and Abilities (KIA) references are included.

CA /~ 0 J 3. Performance location specified. (in-plant, control room, or simulator) lll ~4. Initial setup conditions are identified.

1.rv ~5. Initiating and terminating Cues are properly identified.

\. 7},

'\.. ~6. Task standards identified and verified by SME review.

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

~8. Verify the procedure referenced by this JPM mat£hes the n;iost current revision of

~/ that procedure: Procedure Rev. _i2__ Date 8

2'2-- I t.,.

- - - - 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/lnstructore}:>

SME/lnstructor:

C, .*

( /

tff' N\1..,.. v:n[.U--

Date:

8-22-lb 6-/ 7, ,_,I 110 SME/lnstructor: Date:

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

A LBLOCA has occurred.

The crew has responded by performing TRIP-1 and LOCA-1.

The crew is performing LOCA-3 with all AC buses energized from off-site power, and is waiting at step 21 for RWST lo-lo level alarm.

All ECCS pumps are operating except 22 CS pump which was stopped at step 8.

INITIATING CUE:

You are the Reactor Operator. Continue performing LOCA-3.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 TASK NUMBER: 1150070501 JPM NUMBER: 15-01 NRC Sim c ALTERNATE PATH: I x I KIA NUMBER: ~~~~~~~~~~~

E09 EA1 .1 IMPORTANCE FACTOR: 3.5 3.5 APPLICABILITY: RO SRO EoD RO[]:] STAL] SROITJ EVALUATION SETTING/METHOD: Simulator I Perform

REFERENCES:

2-EOP-TRIP-6 Rev. 30 (Rev checked 8-3-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-3-16 Instructor Validated By: W Russell / D Cox SME or Instructor i Date: 8-22-16 Approved By:

Train~~('-;; Date: 10/;/v Approved By:

Op rations De rtment Date: /D;/1f r, 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:

SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 TASK NUMBER: 1150070501 SIMULATOR SETUP:

1. Trip RCP's

2. Perform EOP's to TRIP-6, Step 12 - SI ACCUM ISOLATION

3. Override 24SJ54, Acc. Isolation Valve, close PB in the OFF position.

4. Place SPDS on Press/Temp Display

5. Put RCS Tcolds on trend on console.

6. Provide marked up copy of TRIP-6 INITIAL CONDITIONS:

A reactor trip occurred when a 500KV grid perturbation occurred, which also caused all RCPs to trip. The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS. The RCPs will NOT be restarted.

INITIATING CUE:

Begin performing 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS at step 12.

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. Shut 21, 22, and 23 SJ54's.

2. Vent 24 Accumulator to atmospheric pressure.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 2 of 6

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation)

Reviews conditions and the marked up EOP-TRIP-6 Natural Circ Cooldown With RVLIS 12 IS RCS PRESSURE <1000 PSIG Verifies RCS pressure <1000 psig.

12.1 REMOVE LOCKOUT FROM 21-24SJ54 At 2RP4 Panel, selects VALVE OPERABLE on (ACCUMULATOR OUTLET VALVES) 21-24SJ54 ACCUMULATOR OUTLET VALVES LOCKOUT switches.

12.1 CLOSE 21-24SJ54 Depresses CLOSE PB on 21-24SJ54, noting that 21, 22, and 23SJ54 begin to stroke closed.

12.1 ARE 21-24SJ54 CLOSED Determines 24SJ54 is OPEN.

Alternate path actions start here.

VENT ANY AFFECTED ACCUMULATORS:

12.2

MAINTAIN RCS PRESSURE Verifies RCS Pressure >24 Accumulator GREATER THAN ACCUMULATOR Pressure NITROGEN PRESSURE

OPEN 2NT35 (N2 HOR VALVE) Opens 2NT35 (N2 HOR VALVE)

OPEN AFFECTED SJ93 (N2 Opens 24SJ93 (N2 SUPPLY VAL VE) and SUPPLY VALVE) observes 24 Accumulator pressure lowering PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 3 of 6

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ECCS TASK: Isolate the ECCS Accumulators IAW TRIP-6 STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation) 12.3 WHEN ACCUMULATOR VENTING IS Cue: 24 Accumulator has been completely COMPLETE THEN CLOSE: vented and 24 Accumulator pressure is now reading ZERO.

2NT35 Closes 2NT35 N2 HOR VALVE

21 THRU 24 SJ93 Closes 24SJ93 N2 SUPPLY VALVE Cue: JPM is complete PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 4 of 6

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

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

(; / 5. Initiating and terminating cues are properly identified.

V / ~ 6. Task standards identified and verified by SME review.

(/ ~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk n

. Verify the procedure referenced by this JPM mate es the most current revision of that procedure: Procedure Rev. ~Date 8" t2 lo

. 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:. (J/ ~

SME/lnstructor: ~, { i>/'

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

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 5 of 6

INITIAL CONDITIONS:

A reactor trip occurred when a 500KV grid perturbation occurred, which also caused all RCPs to trip. The operating crew has progressed through the EOP's and is now in 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS. The RCPs will NOT be restarted.

INITIATING CUE:

Begin performing 2-EOP-TRIP-6, NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS at step 12.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

TASK NUMBER: N 1150290501 JPM NUMBER: 15-01 NRC Sim d ALTERNATE PATH: I x I KIA NUMBER: EPE E05 EA 1.1

---~---~-~

IMPORTANCE FACTOR:

- -4.1- - 4.0 APPLICABILITY: RO SRO EOCJ RO[KJ STACJ SRO[KJ EVALUATION SETTING/METHOD: Simulator - Perform

REFERENCES:

2-EOP-FRHS-1, Loss of Secondary Heat Sink, Rev.~ 61 At- 1-:Jf',~,<c TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 6 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-2-16 Instructor Validated By: S Harris I J Pierce Date: 9-28-16 Approved By:

~ru~~{l Traini~Department 1o)j1t,,

Approved By:

Ope~ment Date:

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 8

.. OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~

SYSTEM: Emerqencv Operatinq Procedures TASK: TCAF a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

TASK NUMBER: N1150290501 SIMULATOR SETUP: RX HEAD VENT KEYS ARE LOCATED IN SIM BOOTH IC-254 developed by: MSL rupture (1 Oo/o)downstream of MS IVs. Fail all MSIVs open. All AFW pumps failed. Fail 2PR2 shut. Performed TRIP-1 through Step 20. SG WR levels <32%.

INITIAL CONDITIONS:

Unit 2 initiated a Rx trip from 100% power in response to a Main Steam line break at the mixing bottle.

An automatic Safety Injection initiated.

The Main Turbine failed to trip automatically, and was manually tripped from the control console.

MSLI failed, and all MSIV's remain open.

All AFW flow has been lost. --- - - - - ----- --*** - ---- -

EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.1 INITIATING CUE:

You are the Reactor Operator. Perform FRHS-1 starting at Step 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.

Task Standard for Successful Completion:

1. Stop ALL RCPs.

2. Open 2PR1.

3. Open Rx Head Vent Valves 2RC40-2RC43.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 8

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation) 1 IS TOTAL AFW FLOW LESS THAN Determines it was not operator action which 22E04 LB/HR DUE TO OPERATOR caused total AFW flow to be less than 22E04 ACTIONS lb/hr.

2 !E AT LEAST ONE INTACT OR Recognizes ALL SGs are faulted.

RUPTURED SG IS AVAILABLE, THEN DO NOT FEED A FAULTED SG 3 IS RCS PRESSURE GREATER THAN Checks RCS pressure on control console ANY INTACT OR RUPTURED SG and determines it is greater than all SG PRESSURE pressures checked on control console.

3.1 ARE RCS T-HOTS GREATER THAN Checks RCS Thot indication on control 350°F console and determines that RCS Thots are greater than 350°F.

4 !E WR LEVELS IN AT LEAST TWO SG's Determines at least 2 SG WR levels < 32%

ARE LESS THAN 32% (37% ADVERSE), and goes to Step 21.

THEN IMMEDIATELY GO TO STEP 21 TO INITIATE RCS BLEED AND FEED PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 8

OPERATOR TRAINING PROGRAM NAME: - - - - - - - - -

JOB PERFORMANCE MEASURE DATE: - - - - - - - - -

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation) 21 CAUTION TO ESTABLISH RCS HEAT REMOVAL Reads Step.

BY RCS BLEED AND FEED, STEPS 24 THRU 29 MUST BE PERFORMED QUICKLY AND WITHOUT INTERRUPTION

23 STOP ALL RCPS Depresses STOP PB for 21-24 RCPs and verifies green stop light illuminates and red start light extinguishes.

22 INITIATE SI Uses Safeguards key and initiates SI on at least one train of Safeguards initiation.

23 ARE SI VALVES IN SAFEGUARDS Checks 2RP4 and/or console indication to POSITION determine that all valves listed in Table B are in Safeguards position.

Table B valves are:

2SJ4 OPEN BIT INLET 2SJ5 OPEN BIT INLET 2SJ12 OPEN BIT OUTLET 2SJ13 OPEN BIT OUTLET 2CV68 CLOSED CHARGING DISCHARGE 2CV69 CLOSED CHARGING DISCHARGE (continued next paqe)

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OPERATOR TRAINING PROGRAM NAME: - - - - - - - - -

JOB PERFORMANCE MEASURE DATE: - - - - - - - - -

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation)

Table B Valves (can't):

21-24SJ54 OPEN ACCUMULATOR OUTLET 2SJ1 OPEN RWST TO CHARGING 2SJ2 OPEN RWST TO CHARGING 2CV40 CLOSED DISCHARGE STOP 2CV41 CLOSED DISCHARGE STOP 23.1 IS 21 OR 22 CHARGING PUMP Checks control console and determines 21 RUNNING and 22 charging pump are running.

IS BIT FLOW ESTABLISHED Checks console and determines BIT flow is established.

23.2 IS ANY SI PUMP RUNNING Checks control console and determines 21 and 22 SI pumps are running.

ARE VALVES IN TABLE COPEN FOR Checks control console indication for valves AT LEAST ONE RUNNING SI PUMP listed in Table C and determines the valves are open for at least one running SI pump.

Table C valves are:

21 /22 SI PUMPS 2SJ30 (FROM RWST) 21/22SJ33 (SI PUMP SUCTION) 2SJ135 (COLD LEG DISCHARGE) 21/22SJ134 (COLD LEG DISCHARGE)

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OPERATOR TRAINING PROGRAM NAME: - - - - - - - - -

JOB PERFORMANCE MEASURE DATE: - - - - - - - - -

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation)

ARE ALL CHARGING AND SI PUMPS Determines all charging and SI pumps are RUNNING AND ALIGNED TO DELIVER running and aligned to deliver flow.

FLOW 24 OPEN BOTH PZR PORV STOP VALVES Checks control console and determines BOTH 2PR6 and 2PR7 PORV STOP VALVES are open.

OPEN BOTH PZR PORVS Places 2PR1 in manual and depresses 2PR1 PZR PORV open PB and verifies green closed light extinguishes and red open light illuminates.

Places 2PR2 in manual and depresses 2PR2 PZR PORV open PB and reports that 2PR2 will not open.

24.1 ARE BOTH PZR PORV STOP VALVES Checks control console and determines BOTH OPEN 2PR6 and 2PR7 PORV STOP VALVES are open.

AREBOTHPZRPORVSOPEN Determines 2PR2 PZR PORV is not open.

Alternate path actions start here.

24.2 OPEN 2RC40 THRU 2RC43 (REACTOR Inserts key into each 2RC40 THRU 2RC43 HEAD VENTS) (REACTOR HEAD VENTS) switch on 2RP3, turns to open, and verifies each valve opens.

Terminate JPM when operator has opened 2RC40 thru 2RC43 Reactor Head Vents.

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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.

V / ,Y ~ 1. Task description and number, JPM description and number are identified.

If: ~ 2. Knowledge and Abilities (KIA) references are included.

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

Ir' I ,!Jr ~ 4. Initial setup conditions are identified.

I 1-= "1 s. Initiating and terminating Cues are properly identified.

/

/ 7\ 6. Task standards identified and verified by SME review.

v I -t' ~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

I

!1.,, \ 8. Verify the procedure referenced by this JPM matches the most current revision of I *v' that procedure: Procedure Rev. 20 Date .,12t/1-'

V \ 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:

~.~\~a-r~ Date: 7)9)£ SME/lnstructor: 5 . Linn'~ 'Jvjk Date: ;, /~s */1~

SME/lnstructor: Date:

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INITIAL CONDITIONS:

Unit 2 initiated a Rx trip from 100% power in response to a Main Steamline break at the mixing bottle.

An automatic Safety Injection initiated.

The Main Turbine failed to trip automatically, and was manually tripped from the control console.

MSLI failed, and all MSIV's remain open.

All AFW flow has been lost.

EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.1 INITIATING CUE:

You are the Reactor Operator. Perform FRHS-1 starting at Step 1.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: Salem Generating Station SYSTEM: Emergency Operating Procedures TASK: TCAF Total Loss of All Service Water TASK NUMBER: N1140380401 JPM NUMBER: 15-01 NRC Sim e ALTERNATE PATH: CJ KIA NUMBER:

- - - -076 A2.01

-- ----l IMPORTANCE FACTOR: 3.5 3.7 APPLICABILITY: RO SRO EOCJ RO((] STAC] SRO((]

EVALUATION SETTING/METHOD: Simulator I Perform S2.0P-AB.SW-0001, Loss of SW Header Pressure, Rev. 16 S2.0P-AB.SW-0005, Loss of All Service Water Rev. 4 S2.0P-AR.ZZ-0002, Overhead Annunciator Window B Rev. 36

REFERENCES:

(All rev checked 8-3-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 3-23-16 Instructor Validated By: W Russell I D Cox Date: 8-22-16 SME or Instructor Approved By: Date:

Approved By: Date:

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~

DATE:

SYSTEM: Abnormal Operating Procedures TASK: TCAF a Total Loss of All Service Water TASK: N1140380401 Simulator Setup: IC-255 100% power. 21 charging pump in service 2 SW bay removed from service IAW S2.0P-AB.SW-003, Service Water Bay Leak. All 4 bay pumps in service.

S2.0P-AB.SW-003 out and marked up.

MALFS: Tied to RT-1 24 SW pump trip 25 SW pump trip 26 SW pump trip INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

21 charging pump is in service.

23 charging pump is aligned for Normal operation IAW Section 4.1 of S2.0P-SO.CVC-0002, Charging Pump Operation.

2 SW Bay has been removed from service to isolate a leak in the bay IAW S2.0P-AB.SW-0003, Service Water Bay Leak.

All #4 Service Water Bay pumps are in service.

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 Task Standard for Successful Completion:

1. Trip the Rx

2. Stop all RCPs prior to or within 3 minutes of any RCP bearing temperature reaching 175°F or any other RCP trip criteria being met in S2.0P-AB.RCP-001.

3. Place 23 Charging pump in service.

4. Reduce operating CCW pumps to one.

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Abnormal Operating Procedures TASK: TCAF a Loss of all Service Water STEP STEP STANDARD EVAL COMMENTS

No. S/U Simulator Operator: Insert RT-1 after operator assumes watch. This trips all 4 Bay SW pumps.

Recognizes that all SW pumps have tripped.

Enters S2.0P-AB.SW-0005, Loss of All Service Water directly, or responds IAW ARP for [ow service water header pressures. ARP steps are after AB.SW-5 steps here in JPM.

AB.SW-1 steps are after ARP steps here in JPM.

AB.SW-5 TRIP the reactor, AND CONFIRM the Trips the Rx using either trip handle, and 3.1 Reactor Trip. confirms the Rx trip.

AB.SW-5 STOP all RCPs. Depresses stop PBs for all RCPs.

3.2 GO TO 2-EOP-TRIP-1, Reactor Trip or Cue: You are to continue with S2.0P-AB.SW-Safety Injection, AND CONTINUE with this 0005 while other operators perform TRIP-1.

procedure. Evaluator: Silence OHA's as not associated with loss of SW.

AB.SW-5 CLOSE the following valves to isolate

3.4 letdown

2CV3, 45 GPM ORIFACE Shuts the open orifice isolation valve and PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STEP STEP STANDARD EVAL COMMENTS

No. S/U

2CV4, 75 GPM ORIFICE ensures the remaining orifice isolation valves

2CV5, 75 GPM ORIFICE are shut.

AB.SW-5 INITIATE Attachment 1, Continuous Action Initiates Attachment 1, Continuous Action 3.5 Summary. Summary.

AB.SW-5 3.6 IF a Centrifugal Charging Pump is in Determines a centrifugal charging pump is in service AND the 23 Charging Pump is service and 23 charging pump is immediately IMMEDIATELY available to be placed in available to be placed in service.

service, THEN PERFORM the following:

A VERIFY ALL 21-24 RCP Seal Inlet Temperatures <225°F as indicated on 2CC1 or the Plant Computer B. ENSURE 23 Charging Pump is aligned for Normal Operation IAW S2.0P-SO.CVC-0002(Q) Charging Pump Operation.

C. PLACE 23 Charging Pump in MANUAL.

D. PLACE Charging Master Flow Controller in MANUAL.

E. SET 23 Charging Pump Speed Demand to 10-12%.

F. START 23 Charging Pump AND immediately INCREASE Speed Demand to approximately 20% to couple pump.

G. ADJUST 23 Charging Pump Speed Demand to obtain desired flow.

H. ENSURE Seal Injection Flow 6-12 gpm to each Reactor Coolant Pump not to exceed 40 gpm total Seal PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STEP STEP STANDARD EVAL COMMENTS

No. S/U Injection Flow.

I. STOP 21 and 22 Centrifugal Charging Pumps.

J. DISPATCH an Operator to monitor operation of 23 Charging Pump due to the potential for rising Component Cooling Water System temperature.

AB.SW-5 !E a Centrifugal Charging Pump is in Determines a Centrifugal Charging Pump is not 3.7 service AND the 23 Charging Pump is NOT in service IMMEDIATELY available to be placed in service, THEN STOP 21 and 22 Centrifugal Charging Pumps.

AB.SW-5 PLACE 2CC131, RCP THERMAL Places 2CC131, RCP THERMAL BARRIER, in 3.8 BARRIER, in MANUAL. MANUAL.

AB.SW-5 PLACE Component Cooling Pumps in Places all Component Cooling Pumps in

3.9 MANUAL AND REDUCE the number of MANUAL AND stops all but one Component operating Component Cooling Water Cooling Water Pumps.

Pumps to one.

Terminate JPM.

ARP 3.1 VERIFY header low pressure using Determines header pressure is low.

OHA's 2PA5373 on 2CC1.

B-13,14 3.2 !E low pressure conditions exists due to Determines loss of SW system pressure does known system configuration, THEN GO TO not conditions exists due to known system S2.0P-SO.SW-0001 (Q) Service water configuration.

Pump operation, to adjust system pressure.

3.3 IF a valid low pressure condition exists, Determines valid low pressure condition exists, THEN GO TO 82.0P-AB.SW-0001 (Q), and goes to $2.0P-AB.SW-0001, Loss of PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STEP STEP STANDARD EVAL COMMENTS

No. S/U Loss of Service Water Header Pressure. Service Water Header Pressure.

AB.SW-1 INITIATE Attachment 1, Continuous Action Initiates Attachment 1, Continuous Action 3.1 Summary. Summary.

AB.SW-1 Is there indication of a leak in a Service Determines there is no unisolated leak (SW 3.2 Water Bay per the following? Bay 2 has been isolated)

Visual indication

OHA B-29, 21-23 SW PMP SMP AREA LVL HI

OHA B-30, 24-26 SW PMP SMP AREA LVL HI AB.SW-1 START Service Water pumps to maintain Determines no SW pumps are available to be 3.4 header pressure between 95 and 105 psig. started.

AB.SW-1 Is there a leak or valve malfunction on the Determines the cause of low SW header 3.5 turbine header as indicated by any of the pressure is from loss of all SW pumps.

following?

AB.SW-1 Are both nuclear Service Water headers in Determines neither nuclear SW header is in 3.6 service? service.

AB.SW-1 IF the Unit is in a Service Water Header Determines the Unit is not in a Service Water 3.7 Outage ... Header Outage.

AB.SW-1 lE the Unit is NOT in a Service Water Determines the Unit is not in a Service Water 3.8 Header Outage, THEN GO TO S2.0P- Header Outage, and goes to S2.0P-AB,SW-AB.SW-0005 (Q), Loss of All Service Water 0005.

TERMINATING CUE: After reduction of CCW pumps to one, terminate JPM.

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE TQ-AA-106-0303 Revision 5 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.

\,l 1.11111 ~ 1. Task description and number, J PM description and number a re identified.

It /WI\ / 2. Knowledge and Abilities (KIA) references are included.

\}. ,/~* 3. Performance location specified. (in-plant, control room, or simulator)

V/ 4. Initial setup conditions are identified.

l

\f ( 5. Initiating and terminating Cues are. properly identified.

\.r / ~6. Task standards 1dent1f1ed and venfled by SME review.

/JA {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. _'i_*_Date 8'}I i.Z-bro I

W't\ J9. 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: --=-g+-=/i;,'-=zji'l--'-1-=~

I SME/lnstructor: Date: ~ -z_z ~;L SME/lnstructor: Date: ------

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is operating at 100% power.

21 charging pump is in service.

23 charging pump is aligned for Normal operation IAW Section 4.1 of S2.0P-SO.CVC-0002, Charging Pump Operation.

2 SW Bay has been removed from service to isolate a leak in the bay IAW S2.0P-AB.SW-0003, Service Water Bay Leak.

All #4 Service Water Bay pumps are in service.

INITIATING CUE:

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

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAlVI JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0100110101 JPM NUMBER: 15-01 NRC Sim f ALTERNATE PATH: K/ANUMBER: 007 A4.04

~

IMPORTANCE FACTOR: 2.6

- - 2.6---

APPLICABILITY: RO SRO EoO RO[ZJ STAD SRO[Z]

EVALUATION SETTING/METHOD: Simulator I Perform

REFERENCES:

S2.0P-SO.PZR-0003, Rev. 15 (checked 8-5-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: M Lutek I W Russell SME or Instructor i, Date: 8-22-16 Approved By:

Tra~CrJ* 4 Date:

Approved By:

obartment 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 of7

OPERATOR TRAINING PROGRAM JOB PERFORMAL~CE MEASURE NAME: ~~~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~~~

SYSTEM: Pressurizer and PRT TASK: Adjust PRT level and pressure TASK NUMBER: N0450040101 SIMULATOR SETUP: 15-01 NRC IC-256 PRT level 56.2% (or low enough for the PRT Hi-Lo Lvl 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 (lo) with PRT level at 56.2%.

INITIATING CUE:

You are directed to raise PRT level to 60% IAW 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 > 60% while maintaining PRT pressure ~10 psig.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 2 of7

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)

Provide marked up paper copy of S2.0P- Reviews Precautions and Limitations.

SO.PZR-0003.

5.1.1 IF PRT level is low, THEN PERFORM the Note: The step for reducing PRT pressure following: may be performed prior to raising level, since pressure is close to the maximum allowed. (See Step 5.1.1.D)

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 !E required, THEN ST ART 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 Pem1ission from Nuclear Training Page 3 of7

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.B OPEN 2WR80, CONT PRI WATER STOP. Depresses open pushbutton for 2WR80 CONT PRI WATER STOP and verifies open light lit.

5.1.1.C OPEN 2WR82, PRT WATER SUPPLY. Depresses open pushbutton for 2WR82, PRT WATER SUPPLY and verifies open light lit.

5.1.1.D !E PRT pressure approaches 10 psig, THEN Depresses open pushbutton for 2PR15, OPEN 2PR15, VENT, as necessary, to maintain VENT prior to PRT pressure rising PRT pressure at >3 psig and _:::10 psig. above 10.0 psig, 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 operator has demonstrated that they can raise level without exceeding 10 psig, then Cue: PRT level is now 60%

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 4 of7

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. lE Primary Water Pump is in service Depresses stop pushbutton for running Primary Water Pump. lE 21 Primary IAW Step 5.1.1.A, AND is NOT required Water pump was used to fill PRT, THEN to be in service for any other reason, 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 operator reads Step 5.1.1.F, state JPM is complete.

PSEG Restricted-Possession Requires Specific Permission from Nuclear Training Page 5 of7

OPERATOR TRAINING PROGRA1"\1 JOB PERFORMAl~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.

\A I (r ldh1. Task description and number, JPM description and number are identified.

"' / wt~ 2. Knowledge and Abilities (KIA) references are included.

II- / d"- l#fl 3. Performance location specified. (in-plant, control room, or simulator)

\,. / d-- l6'?1 4. Initial setup conditions are identified.

~ / (f"" VJ/15. Initiating and terminating Cues are properly identified.

(J.i / ~ l}JI\, 6. Task standards identified and verified by SME review.

v )'- ~ 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. IS Date 3/2;i./11,;

f \Ml 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: 4Lv~1t---/ ~ Date:

'-'lUJr-=--"'--=---'-----'-R-'-u-'-~-s SMEii nstructor:__.h/......._,_' ~=---~*

'--- Date:

SME/lnstructor: Date: _ _ _ _ __

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

OPERATOR TRAINll'IG PROGRAM JOB PERFOR.L\IIANCE MEASURE 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 (lo) with PRT level at 56.2%.

INITIATING CUE:

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

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: Salem Generating Station SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer)

TASK NUMBER: 1150140501 JPM NUMBER: 15-01 NRC Sim g ALTERNATE PATH: D KIA NUMBER: EPE 055 EA 1.07

~~~~~~~~--1 IMPORTANCE FACTOR: 4.3 4.5 APPLICABILITY: RO SRO EoD RO[ZJ STAD SRO[Z]

EVALUATION SETTING/METHOD: Simulator I Perform

REFERENCES:

S2.0P-SO.DG-0001, Rev. 39, S2.0P-S0.4KV-0001, Rev. 32 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Developed By: G Gauding Date: 4-18-16 Instructor Validated By: Hancock I Russell Date: 8-16-16 SME or Instructor Approved By:

Tra~ment Approved By:

Operbsentative ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 1 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: ~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer)

TASK 1150140501 NUMBER:

Simulator Setup: IC-256 (with 24ASO racked down and control power off)

INITIAL CONDITIONS:

1. Unit 2 is recovering from a loss of all AC Power.

2. The crew is performing step 16 of 2-EOP-LOPA-1.

3. 23 AFW pump is supplying all required AFW flow.

4. 2A EOG was started first and is providing power to 2A Vital Bus

5. 2B EOG was just started and is powering 2B 4KV vital bus.

6. 2C 4KV Vital Bus remains deenergized and unavailable.

7. 24 Station Power Transformer (SPT) has just been energized.

8. With 24 SPT now available, the CRS has directed that S2.0P-SO.DG-0001 Section 5.8 and S2.0P-S0.4KV-0001 Section 5.3.6 be utilized to swap 2A Vital Bus from 2A EOG to 24 SPT.

INITIATING CUE:

You are the Control Board Operator. Complete Section 5.8 of S2.0P-SO.OG-0001, and then utilize Section 5.3.6 of S2.0P-S0.4KV-0001 to restore power to 2A Vital Bus from 24 SPT. Prerequisites and Precautions and Limitations have been reviewed and signed.

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:

- Energize 2A 4KV vital bus using 24 SPT PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 2 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Operating Procedures TASK: Perform Actions for a Loss of All AC Power (Energize a 4KV Vital Bus from a Station Power Transformer)

STEP STEP STANDARD EVAL COMMENTS No. (* denotes critical task) S/U Provide marked up copies of S2.0P-SO.DG-0001 and S2.0P-S0.4KV-0001.

SO.DG-1 !E 2A EOG is paralleled on 2A 4KV Vital Determines 2A Diesel Generator is not 5.8.1 Bus .... paralleled on 2A 4KV Vital Bus.

5.8.2 !E 2A Vital Bus is isolated and energized from 2A EOG, THEN: Places redundant equipment in service as

PLACE redundant equipment in needed:

service as necessary to support deenergizing 2A Vital Bus

22 CCW pump Note: 1 SW pump with the TGA isolated is

STOP all 2A Vital Bus loads using sufficient for maintaining SW header pressure Attachment 1 Stops the following equipment (if running):

21 CCW pump

21 SW pump

21 CFCU

21 Aux Building Exhaust Fan

21 SWGR Room Supply Fan

21 SWGR Room Exhaust Fan

21 BAT pump

21 FHB Exhaust Fan

21 AFW pump

21 SI I 21 CS pumps PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 3 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STEP STEP EVAL STANDARD COMMENTS No. (* denotes critical task) S/U 5.8.3 OPEN 2A DIESEL GENERATOR BREAKER Opens 2A DIESEL GENERATOR BREAKER by performing one of the following: by performing one of the following:

OPEN 2AD1AX6D, 2A DIESEL

Directs opening of 2AD1AX6D, 2A GENERATOR BREAKER (64' Swgr DIESEL GENERATOR BREAKER (64' Rm), or Swgr Rm), or

PRESS 2A BREAKER OPEN

Presses 2A BREAKER OPEN pushbutton (2CC3), or pushbutton (2CC3), or

PLACE 2A-DF-GCP-3, GENERATOR

Directs placing 2A-DF-GCP-3, CIRCUIT (BCS), to TRIP (2A DIG GENERATOR CIRCUIT (BCS), to Control Panel). TRIP (2A DIG Control Panel).

5.8.4 ALLOW Diesel to run unloaded for~ 3 Cue: 2A EOG will be shutdown by local minutes prior to stopping the EOG. operator.

5.8.5 If diesel unloading ... Determines step is NIA S0.4KV-1 IF 2A 4KV Vital Bus is to be energized from 5.3.6 24 SPT,THEN:

5.3.6.A Direct NEO to RACK UP 2AD1AX24ASD, Contacts NEO and directs them to rack up 24 STATION POWER TRANSFORMER 2AD1AX24ASD, 24 STATION POWER INFEED BREAKER (64' Swgr Rm). TRANSFORMER INFEED BREAKER.

Simulator Operator: MODIFY REMOTE ED21D to ON, then report 2AD1AX24ASD, 24 STATION POWER TRANSFORMER INFEED BREAKER is racked up.

5.3.6.B PRESS Mimic Bus 2A VITAL INFEED 24ASD Depresses Mimic Bus 2A VITAL INFEED pushbutton AND ENSURE Console Bezel 24ASD pushbutton AND determines the 24ASD MIMIC BUS INTLK CLOSE Console Bezel 24ASD MIMIC BUS INTLK SELECTION illuminates. CLOSE SELECTION illuminates.

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 4 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE 5.3.6.C PERFORM the following:

1. PRESS AND HOLD control console Presses and Holds control console 24ASD 24ASD CLOSE pushbutton. CLOSE pushbutton, then releases pushbutton

2. RELEASE pushbutton when 24ASD when 24ASD indicates closed.

indicates CLOSED.

3. ENSURE the following: Checks Console bezel 24ASD MIMIC BUS

a. Console bezel 24ASD MIMIC BUS INTLK INTLK CLOSE SELECTION is extinguished.

CLOSE SELECTION is extinguished.

b. 2A 4KV Vital Bus voltage is 4.275 -

4.336KV (normal)

OR 4.330 - 4.417KV (single source of off-site Determines 2A Vital Bus voltage is 4.275 -

power). 4.385KV (single source of off-site power.

c. OHA J-17, 2A 4KV VTL BUS Determines OHA J-17 2A 4KV VTL BUS UNDRVOLT, is clear. UNDRVOLT is clear.

Terminate JPM.

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 5 of 7

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 JPM usage, revalidate JPM using steps 8 and 11 below.

I! / ;:J- 1. Task description and number, JPM description and number are identified.

" ./ (), 2. Knowledge and Abilities (KJA) references are included.

v I~

~ 3. Performance location specified. (in-plant, control room, or simulator) v ~ 4. Initial setup conditions are identified.

v ~ 5. Initiating and terminating Cues are properly identified.

v ~ 6. Task standards identified and verified by SME review .

.v --9-- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

V ___Q_ 8. Verify the procedure referenced bl_ this JPM matchei the most current revision of

~ that procedure: Procedure Rev. 2j_ Date <3/Jvlllo fJ 9. Pilot test the JPM: . ] z_

-C- 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.

~nstructo?!IL~"""'k_.- Date: $> J(L /1~

's-M(;lnstructor,.~ ~l( Date: S I/ i G /J I

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

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

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 6 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Unit 2 is recovering from a loss of all AC Power.

2. The crew is performing step 16 of 2-EOP-LOPA-1.

3. 23 AFW pump is supplying all required AFW flow.

4. 2A EOG was started first and is providing power to 2A Vital Bus

5. 2B EOG was just started and is powering 2B 4KV vital bus.

6. 2C 4KV Vital Bus remains deenergized and unavailable.

7. 24 Station Power Transformer (SPT) has just been energized.

8. With 24 SPT now available, the CRS has directed that S2.0P-SO.DG-0001 Section 5.8 and S2.0P-S0.4KV-0001 Section 5.3.6 be utilized to swap 2A Vital Bus from 2A EOG to 24 SPT.

INITIATING CUE:

You are the Control Board Operator. Complete Section 5.8 of S2.0P-SO.OG-0001, and then utilize Section 5.3.6 of S2.0P-S0.4KV-0001 to restore power to 2A Vital Bus from 24 SPT. Prerequisites and Precautions and Limitations have been reviewed and signed.

PSEG Confidential- Possession Requires Specific Approval from Nuclear Training Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Loss of Control Air TASK: TCAF a Loss of Control Air TASK NUMBER: N1140070401 JPM NUMBER: 15-01 NRC Sim h ALTERNATE PATH: I x I KIA NUMBER: APE 065 AA2.06

~~~~~~~~~~

IMPORTANCE FACTOR: 3.6 4.2 APPLICABILITY: RO SRO EOCJ RO[KJ STACJ SRO[KJ EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AB.CA-0001, Rev. 21 Loss of Control Air (both rev checked 8-5-16)

REFERENCES:

S2.0P-AR.ZZ-0011, Rev. 60, pages 118-128 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: M Lutek I W Russell Date: 8-22-16 SME or Instructor fJL_

Approved By:

Trai~:n;v Date:

Approved By: Date:

Operbrtment 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: Check 2WG41 is open 15-01 NRC IC-258 RT-1 MALF: CA0221 #2 STATION AIR CMPRSSR TRIP REM: CA13D LOCKOUT #1 STATION AIR CMPRSR, Delay 1:30 1/0 : AQ01 OVLO COMP 1 TROUBLE ALARM, Fin Val: ON, Delay 1:30 Other setup:

REM: CA15D LOCKOUT #3 STATION AIR CMPRSR CA11D #1 EMERGENCY AIR COMPRSR IN AUTO Fin Val: MANUAL CA 12M #1 EMRGENCY AIR CMPRSR SWITCH Fin Val: Stop 1/0 : AQ01 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 GOT.

#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 lo lo SG NR level.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2of13

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 SIU evaluation)

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-load 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 13

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 0 ATE:

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 lE SAC 2 trips, THEN:

A. COORDINATE (as necessary) Coordinates with Unit 1 to start at least one with Unit 1 SAC IAW SC.OP-SO.SA-0001{Z), Station Air B. ENSURE operating OR START at System Operation.

least one SAC IAW 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 S2.0P-AB.CA-0001(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 Station Air Compressor Trip."

Recognizes that no SAC's are running, and enters S2.0P-AB.CA-0001 if not entered previously.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4of13

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)

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 - 28 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 3.2 EITHER of the following conditions exist? Determines all SAC's are stopped or

ALL Station Air Compressors determines Station Air Header pressure is stopped <100 psig.

EITHER Station Air Header <100 psig PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5of13

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) 3.3 lE a loss of 1 F 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 Auxiliary Oil pump by transferring 11 Turbine West 230V Control Center IAW Attachment 14, Section 1.0.

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 i transferring 21 Turbine West 230V Control Center IAW Attachment 14, Section 2.0.

3.5 lE 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 transferring 11 Turbine East 230V Control Center IAW Attachment 14, Section 3.0.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6of13

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 evaluation)

S/U 3.6 START or have Unit One Control Room Determines no SAC's are available.

START 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 Either Station Air Header indicating less Determines both Station Air Headers are than100 psig? indicating less than 100 psig.

3.8 Attempt to START, or have Unit One Determines no SAC's can be started.

Control Room START, remaining Station Air Compressor.

3.9 NOTIFY the CRS/SM to evaluate use of Cue: CRS will evaluate use of temporary air temporary air compressors. compressors.

3.10/3.11 2A Control Air Header less than or equal Determines 2A control air header pressure is:

to 88 psig? less than or equal to 88 psig and determines

2 ECAC is in service OR

>88 psig.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 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 (Required for UNSAT

(*Denotes a Critical Step) EVAL

NO. STANDARD S/U evaluation) 3.12/3.13 2B Control Air Header less than or equal Determines 2B control air header pressure is:

to 88 psig?

less than or equal to 88 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 to: Dispatches operators to:

LOCATE AND ISOLATE ANY air

LOCATE AND ISOLATE any air system leaks. system leaks.

INVESTIGATE cause of ANY air

INVESTIGATE cause of air compressor trip/trouble. compressor trip/trouble.

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 areas subject to leakage/flooding.

B. INITIATE monitoring of Fuel Pool or Reactor Vessel levels for the need to makeup due to leakage.

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) 3.16 !E 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.

3.17 BOTH 2A and 2B Control Air Headers Determines both 2A and 2B Control Air less than 80 psig? Headers are not <80 psig.

3.18 ANY Excess Flow Check Valve closed as indicated by at least one of the following?

(Attachment 5, Excess Flow Check Valve Determines NO Excess Flow Check Valve Table) [INPO IER L2 15-16] closed.

Groups of valves repositioning with normal air pressure indicated in Control Room

Local observation of low pressure downstream of an Excess Flow Check Valve 3.19 2B Control Air Header less than 80 psig? Determines 28 Control Air Header is <80 psig.

Alternate Path actions start here.

3.57 CONTINUE

3.58 CLOSE the following valves: Closes the following valves:

A. 2CV3, LTDWN ORIFICE !SOL VALVE A. 2CV3, LTOWN ORIFICE !SOL VALVE B. 2CV4, LTDWN ORIFICE !SOL VALVE B. 2CV4, LTDWN ORIFICE !SOL VALVE C. 2CV5, LTDWN ORIFICE ISOL VALVE C. 2CV5, LTDWN ORIFICE !SOL VALVE D. 2CV2 LETDOWN LINE !SOL VALVE D. 2CV2 LETDOWN LINE !SOL VALVE E. 2CV277 LTDWN LINE !SOL VALVE E. 2CV277 LTDWN LINE ISOL VALVE F. 2CV7 LTDWN HX INLET VALVE F. 2CV7 LTDWN HX INLET VALVE PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9of13

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) 3.57 VERIFY ANY Liquid or Gaseous release Determines 2WG41, GAS DECAY TK TO

is stopped by ensuring the following PLANT VENT is open, and shuts 2WG41, valves CLOSED: 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, 6.0 THEN:

INITIATE monitoring of 21- Identifies all BF19 valves closing.

24BF19 SG FW CONT VALVE,

operation. Trips the Reactor.

!E ANY BF19 SG FW CONT VALVE closes AND Applicable SG water level CANNOT be maintained, THEN:

A. TRIP the Reactor B. CONTINUE with this procedure C. GO TO 2-EOP-TRIP-1, Reactor Trip Or Safety Injection.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 10of13

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: - - - - - - - - -

SYSTEM: Loss of Control Air TASK TCAF a Loss of Control Air STEP COMMENTS STEP (Required for UNSAT

(* Denotes a Critical Step) EVAL

NO. STANDARD S/U evaluation)

TRIP-1 Performs Immediate Actions of EOP-TRIP-1:

Confirms the Rx trip Trips the Main turbine Checks at least 1 4KV vital bus energized Determines SI is not initiated or required.

Cue after Immediate Actions have been performed: The CRS and another operator will continue performing the EOPs. You are to continue in current procedure.

Terminate JPM once Rx has been tripped, letdown isolated, and the WG release 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.

/ ~tut] Task description and number, JPM description and number are identified.

/ )-- ~-Knowledge and Abilities (KIA) references are included.

I ~- Performance location specified. (in-plant, control room, or simulator)

/ G~. Initial setup conditions are identified.

I . Initiating and terminating Cues are properly identified.

/ M. Task standards identified and verified by SME review.

0 ~- Critical steps meet the criteria for critical steps and are identified with an asterisk(*).

}-Lil. 8. Verify the procedure referenced 2rs JPM mate es th most current revision of that procedure: Procedure Rev. Date "'l--, _

'(s:\J./!'g_ 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: __~_~L....,.......,_v_~~.r~~~----'P.+--=-,.cAr----

SME/lnstructor:~A~~-"'-~~~-~-~_u_ss-_*_t_l_ _

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 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.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 13 of 13

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer/Pressure Relief TASK: Transfer Pressurizer 22 Backup Heaters to Emergency Power Supply TASK NUMBER: 115 043 05 01 JPM NUMBER: 15-01 NRC Annual IP-i ALTERNATE PATH: D KIA NUMBER: 010 A4.02

~~~~~~~~---!

IMPORTANCE FACTOR: 3.6 3.4 APPLICABILITY: RO SRO EOCJ RO[D STAC] SRO[D EVALUATION SETTING/METHOD: In Plant, Simulate

REFERENCES:

S2.0P-SO.PZR-0010 Rev. 10 (Rev. checked 8-5-16)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 20 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor Validated By: S Bickhart I J Hancock Date: 9-30-16 SME or lnstruc~:{~

10~0~<..,

Tr~rtment Approved By: Date:

Jo/10/1t.~

Approved By:

Ope~ons Dep~1ent Date:

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1of6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Pressurizer/Pressure Relief TASK: Transfer Pressurizer 22 Backup Heaters to Emergency Power Supply TASK 1150430501 NUMBER:

INITIAL CONDITIONS:

Due to a loss of power to the group buses it is necessary to energize the PZR Backup Heaters from their emergency power supply.

INITIATING CUE:

The CRS directs you to perform S2.0P-SO.PZR-0010(Q), Section 5.3, Transferring Pzr Htr 22 BU Group To The Emergency Power Supply.

All prerequisites and Precautions and Limitations have been reviewed and completed.

2A EOG is carrying 2A Vital Bus and is loaded to 2400 KW.

You have a JAM key.

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. Simulate opening all but three PZR heater disconnects.

2. Simulate aligning emergency power to PZR heater bus from 2A vital bus.

Page 2of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:~~~~~~~~~~

SYSTEM: Pressurizer/Pressure Relief DATE:~~~~~~~~~~

TASK: Transfer 22 Backup Heaters to Emergency Power Supply STEP COMMENTS

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

Operator obtains procedure S2.0P- Provide marked up copy of S2.0P-SO.PZR-0010, Pressurizer Backup Heaters SO.PZR-0010, Pressurizer Backup Power Supply Transfer. Heaters Power Supply Transfer 5.3.1 ENSURE 2AX1AX14X, 2EP Locates breaker 2AX1AX14X 2EP PRESSURIZER HEATER BUS FEED PRESSURIZER HEATER BUS FEED (EMERGENCY) is OPEN (84' Swgr Rm). (EMERGENCY) on 2A 460V Vital Bus, Elev. 84' Swgr Rm and determines current breaker position.

Cue: 2AX1AX14X Breaker indicates OPEN.

5.3.2 Request NCO to PERFORM the following:

Locates nearest means of A. PLACE 22 Backup Group in communications and requests NCO to MANUAL. place 22 B/U Htrs in MANUAL and B. PRESS the 22 BACKUP OFF press the 22 BACKUP OFF pushbutton pushbutton.

Cue: NCO reports 22 B/U Htrs are in MANUAL and 22 BACKUP OFF pushbutton has been depressed.

5.3.3 ENSURE 2EX1 EP2EPX, 2EP 480V Locates 2EX1 EP2EPX, 2EP 480V PRESSURIZER HEATER BUS MAIN PRESSURIZER HEATER BUS MAIN BREAKER is OPEN (78' Electrical BREAKER on El. 78 Electrical Pen.

Penetration). Cue: 2EX1EP2EPX, 2EP 480V PRESSURIZER HEATER BUS MAIN BREAKER is OPEN.

Page 3of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: _ _ _ _ _ _ _ _ _~

SYSTEM: Pressurizer/Pressure Relief DATE:

TASK: Transfer 22 Backup Heaters to Emergency Power Supply STEP COMMENTS

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

5.3.4 REMOVE interlock key from breaker Describes turning key and removing 2EX1 EP2EPX. interlock key from breaker 2EX1 EP2EPX.

Note: Tab must be pushed in to rotate key to allow its removal.

5.3.5 PLACE any eleven of the following Operator locates individual heater disconnects in OFF (only three disconnects disconnects, places all but three are to remain ON) AND MARK the disconnects in OFF and notes remaining disconnects as N/A: disconnects left ON as N/A in procedure.

5.3.6 PLACE, 2AX1AX14X-1, 2EP PZR HTR Operator locates 2AX1AX14X-1, 2EP BUS EMERGENCY FEED DISCONNECT PZR HTR BUS EMERGENCY FEED SWITCH, in the ON position (Elev 78' DISCONNECT SWITCH, and places it Electrical Penetration). in the ON position (Elev 78' Electrical Penetration).

5.3.7 INSERT interlock key, AND UNLOCK Locates Corry Key Interlock on breaker 2AX1AX14X. 2AX1AX14X breaker, inserts and turns key.

5.3.8 NOTIFY NCO that PZR Htr 22 B/U Group Candidate makes report to the Control has been transferred to the emergency Room.

power supply (2A 460V Vital Bus). Repeat back notification and state:

JPM is comolete.

Page 4 of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

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.

W 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.

J 16. Task standards identified and verified by SME review.

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

J..--4

< 8. Verify the procedure referenced by this JPM mat9hEis the most current revision of that procedure: Procedure Rev. __J.._ Date H L'11 S

_); } 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: ~&..II ... ~ Date: '/Jo/1" SME/lnstruct~ __..-1$fdt~~ Date: 'lf3v,h6 SME/lnstructor: Date: - - - - - -

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Due to a loss of power to the group buses it is necessary to energize the PZR Backup Heaters from their emergency power supply.

INITIATING CUE:

The CRS directs you to perform S2.0P-SO.PZR-0010(Q), Section 5.3, Transferring Pzr Htr 22 BU Group To The Emergency Power Supply.

All prerequisites and Precautions and Limitations have been reviewed and completed.

2A EOG is carrying 2A Vital Bus and is loaded to 2400 KW.

You have a JAM key.

Page 6of6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

STATION: SALEM SYSTEM: Auxiliary Feedwater TASK:

Perform Auxiliary Feedwater Back Leakage Test TASK NUMBER: N0610160204 JPM NUMBER: 15-01 NRC IP-j ALTERNATE PATH: I I KIA NUMBER: 061 K1 .02

~----------.,

IMPORTANCE FACTOR:

- -3.4-- 3.7 APPLICABILITY: RO SRO EOLJ RO[KJ STALJ SRO[KJ EVALUATION SETTING/METHOD: lnplant- Simulate

REFERENCES:

S1 .OP-PT.AF-0002, Rev. 7, Auxiliary Feedwater Backleakage (checked 8-5-16)

TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NIA Developed By: G Gauding Date: 8-5-16 Instructor Validated By: S Bickhart I J Hancock Date: 9-30-16 SME or Instructor Approved By: ~ Mvff(W\ Date: tojof 0 Training~partment Approved By: Date: /ofcf~

Opebrtment 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 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME: ~~~~~~~~~~~~~~

DATE: ~~~~~~~~~~~~~~

SYSTEM: Auxiliary Feedwater System TASK: Perform Auxiliary Feedwater Back Leakage Test TASK NUMBER: N0610160204 INITIAL CONDITIONS:

Unit 1 is operating at 100% power. 11 AFW pump was secured 30 minutes ago after its normally scheduled quarterly surveillance run.

INITIATING CUE:

You are directed to perform S1 .OP-PT.AF-0002, Auxiliary Feedwater Backleakage.

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. Determine 11 AFW pump and piping requires venting.

2. Vents 11 AFW pump and piping.

Page 2 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: AFW TASK Perform Auxiliary Feedwater Back Leakaae Test STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation)

Provide operator with blank copy of S1 .OP- Reviews and initial all Prerequisites PT.AF-0002, Rev. 7, and a calculator. and Precautions and Limitations.

5.1.1 RECORD following on Attachment 1, Section 1.0: After locating 1TA165551, provide

AFW Line Temperatures (1TA165551) the following AFW line

Highest line temperature temperatures:

11-104

Average line temperature 12- 106

Temperature difference 13- 161 14- 108 On Attachment 1, records AFW temperatures, calculates total of 479, divides that by 4 and determines

highest line temp is 161 and average line temp is 119. 75.

Determines Temp Diff 161- 119.75 =

41.25.

5.1.2 IF temperature in each line is <120°F, AND temperature difference between highest Determines highest temp is >120°F and average line temp is .:::_10°F, THEN RECORD Test Results in Attachment 1, Section 5.0.

Page 3 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: AFW TASK Perform Auxiliarv Feedwater Back Leakaae Test STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation) 5.1.3 IF temperature in any line is .'.:'._120°F AND <160°F, THEN: Determines highest temp is >160°F A. RECORD Auxiliary Feedwater System piping temperatures every hour in Control Room Narrative Log.

B. RECORD Test Results in Attachment 1, Section 5.0.

5.1.4 IF temperature difference between highest and average line temp is >10°F, THEN Determines temperature difference RECORD Test Results in Attachment 1, between highest and average line

Section 5.0. temp is >10°F, and records Test Results in Attachment 1, Section 5.0.,

as UNSAT for all three categories.

5.1.6 I IF temperature in any line is .'.::160°F THEN:

A. RECORD findings in Control Room Narrative Log.

B. VENT Auxiliary Feedwater pumps/piping IAW Section 5.2.

Page 4 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ~~~~~~~~~-

JOB PERFORMANCE MEASURE DATE: ~~~~~~~~~-

SYSTEM: AFW TASK: Perform Auxiliarv Feedwater B --

- --- - T STEP COMMENTS STEP

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

NO. STANDARD S/U evaluation)

5.2.1 IF 11 Auxiliary Feedwater Pump and piping is affected, THEN:

A. SLOWLY THROTTLE OPEN 11AF83, AF Locates and opens 11 AF83, AF PUMP VENT, until a solid stream of water is PUMP VENT, until a solid stream of observed. water is observed.

Cue: A solid stream of water is observed.

B. CLOSE 11 AF83. Closes 11 AF83 Locates and opens 11 AF114, AF C. SLOWLY THROTTLE OPEN 11AF114, PUMP DISCH VENT, until a solid AF PUMP DISCH VENT, until a solid stream stream of water is observed.

of water is observed. Cue: A solid stream of water is observed.

D. CLOSE 11AF114. Closes 11AF114.

Terminate JPM I

Page 5 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

This page intentionally blank.

Page 6 of 8

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.

U~ 2. Knowledge and Abilities (KIA) references are included.

V ;I- ')I 3. Performance location specified. (in-plant, control room, or simulator)

V/ 'S / 4_ Initial setup conditions are identified.

\/ erL2L5. Initiating and terminating Cues are properly identified.

\J'~/6. Task standards identified and verified by SME review.

I> /7. Critical steps meet the criteria for critical steps and are identified with an asterisk n

\!'- d 18. Verify the procedure referenced by this JPM maJchfs the most current rev1s1on of that procedure: Procedure Rev. :f- Date /,ffJ{-fJ.

~ 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: 9/.Jo//h SME/lnstructo~cft!Mll t- Date: 9/~ ~JI co.

SME/lnstructor: Date:

Page 7 of 8 PSEG Restricted-Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 1 is operating at 100% power. 11 AFW pump was secured 30 minutes ago after its normally scheduled quarterly surveillance run.

INITIATING CUE:

You are directed to perform S1 .OP-PT.AF-0002, Auxiliary Feedwater Backleakage.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Diesel Generator Start and synchronize an Emergency Diesel Generator ASK NUMBER: 113 0010501 PM NUMBER: 15-01 NRC IP-k L TERNATE PATH: D KIA NUMBER:

IMPORTANCE FACTOR:

064 A2.09

~----------!

3.1 3.3 PPLICABILITY: RO SRO EoD ROW STAD sRoW EVALUATION SETTING/METHOD: In Plant I Simulate

REFERENCES:

2A Diesel Generator Operation, S2.0P-SO.DG-0001 (Q)Rev. 39 (checked 8-5-16)

OOLS AND EQUIPMENT: None ALIDATED JPM COMPLETION TIME: 20 min IME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 8-5-16 Instructor alidated By: S Bickhart I J Hancock Date: 9-30-16 pproved By: Date: 10/o/c...

pproved By:

CTUAL JPM COMPLETION TIME:

CTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: DsAT OuNSAT 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: EOG TASK: Start and synchronize an Emergency Diesel Generator TASK 113 0010501 NUMBER:

INITIAL Unit 2 is operating at 100% power, with no equipment OOS. Engineering has CONDITIONS: requested a loaded run of 2A EOG.

INITIATING CUE:

The Unit 2 CRS has directed you to locally start and parallel load 2A DIG IAW 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

(*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 acknowledqes.

5.2.2 CHECK voltage permissive indicator light Points out voltage permissive indicator 2DAE4-LT2, EDG VOLT AGE, on light 2DAE4-LT2, EOG VOLTAGE, on Generator Control Panel is OFF Generator Control Panel.

Cue: Liqht is off 5.2.3 CHECK speed permissive indicator light Points out speed permissive indicator 2DAE4-LT3, EOG SPEED, on Generator light 2DAE4-LT3, EOG SPEED, on Control Panel is OFF. Generator Control Panel.

Cue: Liqht is off

5.2.4 !E 2A 4KV Vital Bus is currently energized, (Diesel Generator is to be parallel loaded),

THEN: Points out 2A-DF-GCP-1, 2A DIESEL A. PLACE 2A-DF-GCP-1, 2A DIESEL GEN LOADING SW., and simulates GEN LOADING SW in MANUAL rotating to DROOP position.

(DROOP).

B. ENSURE B-9, GENERATOR LOADING Cue: Annunciator B-9, Generator IN DROOP MODE, is in alarm. loading in Droop Mode annunciates.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3of12

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)

5.2.5 PLACE 2A-DF-SS, 2A DG STOP/START Points out 2A-DF-SS, 2A DG SWITCH in START. STOP/START SWITCH, and simulates placing in START.

Cue: 2A Diesel is acceleratinq.

5.2.6 !E 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.

5.2.7 !E 2AD1AX6D*, 2A Diesel Generator 125VDC breaker is closed, THEN:

CHECK voltage permissive Points out voltage permissive indicator indicator light 2DAE4-LT2, EOG light 2DAE4-LT2, EOG VOLTAGE.

VOLTAGE, on Generator Control Cue: Voltage permissive indicator light Panel is ON. 2DAE4-LT2, EOG VOLTAGE Light is on

CHECK speed permissive indicator Points out speed permissive indicator light 2DAE4-LT3, EOG SPEED, on light 2DAE4-LT3, EOG SPEED Generator Control Panel is ON. Cue: Speed permissive indicator light 2DAE4-LT3, EOG SPEED light is on I

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4of12

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM: Emergency Diesel Generator NAME:

DATE:~~~~~~~~~~~~~

TASK: Locally start and load an Emergency Diesel Generator COMMENTS STEP EVAL STEP STANDARD (Required for UNSAT

(*Denotes a Critical Step) S/U

NO. Evaluation) 5.2.8 IF Field Ground Relay 64/G white indicating light is OFF, AND C-6, GENERATOR FIELD GROUND, is clear, Points out Field Ground Relay 64/G THEN: white indicating light.

A. RESET 64/G relay B. ENSURE 64/G white indicating Cue: Field Ground Relay 64/G white light is illuminated. indicating light is illuminated.

5.2.9 ENSURE 2A Diesel Generator K1 C Field Points out 2A Diesel Generator K1 C Flashing Relay Supervisory Light is OFF. Field Flashing Relay Supervisory Light Cue: 2A Diesel Generator K1 C Field Flashing Relay Supervisory Light is off.

5.2.10 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 2FM186 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 5of12

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) 5.2.11 lE 2A Diesel Generator is to be operated Determines from initiating cue that 2A unloaded for an extended period of EOG is to be parallel loaded.

time(>30 minutes), THEN INITIATE Section 5.7, Diesel Generator Running Checks.

5.2.12 lE Diesel Generator is to be parallel Initiates Section 5.4, Diesel Generator loaded, THEN INITIATE Section 5.4, Parallel Loading.

Diesel Generator Parallel Loading.

5.4.1 lE Section 5.1 Diesel Generator Startup Verifies Section 5.1 is complete.

Checks, was NOT performed, THEN at 2A DG 4KV cabinet cubicle breaker 2AD1AX60, PLACE selector switch 2A DG SYNC ENABLE in ENABLE.

5.4.2 NOTIFY NCO that 2A EOG is to be Cue: NCO acknowledges 2A DG is to synchronized and loaded locally. be synchronized and loaded locally.

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 6of12

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)

5.4.4 ADJUST 2A EOG 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 VOLTAGE CONTROL SWITCH (VCS). Points out VOLTAGE 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 VOLTMETER 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 7of12

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 VOLTMETER SWITCH -

GEN (VS-G) and VOLTMETER

VOLTMETER SWITCH - GEN SWITCH - BUS (VS-B)

(VS-G)

VOLTMETER SWITCH - BUS (VS-B) Cue: Switches are in 1-2.

5.4.8 ENSURE 2DAE4-LT2, EOG Voltage Points out 2DAE4-LT2, EOG Voltage indication light is ON. indication light.

Cue: 2DAE4-LT2, EOG Voltage indication liqht is on.

5.4.9 ENSURE 2DAE4-LT3, EOG Speed Points out 2DAE4-LT3, EOG Speed indication light is ON. indication light.

Cue: 2DAE4-LT2, EOG Voltage indication liaht is on.

5.4.10 SYNCHRONIZE 2A Diesel Generator to 2A 4KV Vital Bus as follows:

5.4.10 PLACE 2A-DF-SYNCH, 2A DG SYNC A. 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 8of12

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)

5.4.10 ADJUST Diesel speed using the SPEED When operator points out B. 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.

5.4.10 ENSURE the following four SYNC CHECK Points out four SYNC CHECK RELAY C. RELAY 25 UPPER AND LOWER 25 UPPER AND LOWER VOLTAGE VOLTAGE LIMIT LEDS are ON. LIMIT LEDS.

"Upper Voltage Limit" "L OK" "B OK" "Lower Voltage Limit" "LOK" "B OK" Cue as each LED is located: Light is on.

5.4.10 IF the SYNC CHK RELAY 25 i'.1F OK LED Points out SYNC CHK RELAY 25 i'.1F D. is OFF, THEN ADJUST 2A Diesel OK LED.

Generator speed using the SPEED CONTROL SWITCH (GS) until the i'.1F OK Cue Light is on.

LED is ON.

5.4.10 ENSURE DG SYNC PERMISSIVE green E. 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 svnchroscope.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9of12

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)

5.4.10 COORDINATE the following when the F 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 Cue 2A Diesel Generator Breaker has prevent tripping the Diesel closed.

Generator Breaker on reverse power. Points out SPEED CONTROL SWITCH (GS) simulates going to RAISE while observing KW meter.

Cue Load is 500 KW.

5.4.10 PLACE 2A-DF-SYNCH, 2A DG SYNCH Points out 2A-DF-SYNCH, 2A DG G 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 10of12

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 JPM usage, revalidate JPM using steps 8 and 11 below.

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

e.. ~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 .

~

.J ) /6. Task standards identified and verified by SME review.

/

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

c-r-r") ) 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. _n_ Date !i/3ohlo

_ci____f9. 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/lnstruc~~ c,l..., Date: 1 /Jo U'2 SME/lnstruc . Pt :t- Date: q~//6 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 EOG.

INITIATING CUE:

The Unit 2 CRS has directed you to locally start and parallel load 2A DIG IAW 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 12of12

TQ-AA-106-0204 Page 1of27 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-1 SCENARIO NUMBER: 15-01 NRC ESG-1 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: .___ _.I LO. REQUAL X j INITIAL LICENSE

.___ _.I STA

~-~'OTHER Revision Summary New issue for 15-01 !LOT NRC exam PREPARED BY: G Gauding 7-18-16 Lead Regulatory Exam Author Date

-;ri . .

APPROVED BY:

(~

Oat APPROVED BY:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 2 of 27 A. Given the order or indications of a charging system malfunction, perform actions as the nuclear control operator to RESPOND to the loss or malfunction of the charging system in accordance with S2.0P-AB.CVC-0001.

B. Given indication of a loss or malfunction of the Charging system DIRECT corrective action for a Charging System malfunction in accordance with S2. OP-AB. CVC-0001.

C. Given the indications of a reactor coolant system (RCS) malfunction or leak, perform actions as the nuclear control operator to RESPOND to the malfunctioning accordance with S2.0P-AB.RC-0001.

D. Given the indications of a reactor coolant system (RCS) malfunction or leak, DIRECT the response to the malfunction in accordance with S2.0P-AB.RC-0001.

E. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

F. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

G. 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.

H. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

I. Given a safety injection has occurred and inadequate ECCS flow exists, ALIGN equipment to obtain required ECCS flow in accordance with station procedures.

J. Given the order or indications of a loss of coolant accident (LOCA), complete actions as the nuclear control operator to PERFORM the immediate response to the LOCA in accordance with the approved station procedures.

K. Given indication of a loss of coolant accident (LOCA), DIRECT the immediate response to the LOCA in accordance with the approved station procedures.

L. Given conditions that allow SI termination, perform actions as the nuclear control operator to TERMINATE safety injection in accordance with the approved station procedures.

M. Given conditions that allow SI termination, DIRECT the response to the safety injection termination in accordance with the approved station procedures.

MAJb .::i,E:N

.....".... *v"* ~:. '.\ ..'..

A. Controlling PZR Level Channel fails low B. 20 gpm RCS leak C. 150 gpm SBLOCA D. SBLOCA escalation during SI termination PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 3 of 27 A. The crew will take the watch with the unit at 100% power, MOL. PZR Pressure Channel Ill is selected for Control.

B. After the crew assumes the watch, the controlling PZR level channel will fail low. eves Letdown will isolate, and the Master Flow Controller will raise charging flow. The crew will enter S2.0P-AB.CVC-0001, Loss of Charging. The crew will take manual control of charging flow and return PZR level to program. The crew will remove the failed channel from service.

The crew will restore normal letdown. The CRS will identify Tech Specs.

C. After the PZR level channel failure has been addressed, a 20 gpm RCS leak will occur. The crew will diagnose the leak. The crew will swap to a centrifugal charging pump and a 45 gpm orifice, and estimate the leak rate. The CRS will identify Tech Specs.

D. The CRS will determine a unit shutdown is required based on the RCS leak. The crew ill initiate a controlled shutdown.

E. After the downpower has commenced, the RCS leak rate will rise to 150 gpm. The crew will diagnose deteriorating primary conditions. When it is determined that PZR level will be unable to be maintained >11 %, the crew will take the CAS action to trip the reactor and initiate Safety Injection.

F. The crew will perform plant stabilization and diagnostics in EOP-TRIP-1, Reactor Trip or Safety Injection. The crew will identify no AFW flow. 2A SEC will not reset, and will require deenergization to start 21 AFW pump. The crew will establish at least 22E4 lbm/hr AFW flow.

(CT#1)

G. The crew will determine there is no High Head ECCS flow, and open the BIT Isolation Valves to establish High Head ECCS Injection (CT#2).

H. The crew will transition to EOP-LOCA-1, Loss of Reactor Coolant when directed in TRIP-1.

I. The crew will reset Safeguards in LOCA-1, and determine SI termination criteria are met to transition to EOP-TRIP-3, SI Termination.

J. The crew will stop all but one Charging pump and align CVCS for normal charging. When evaluating the leak, the SBLOCA will get significantly larger. The crew will diagnose degrading conditions and take the CAS action to start ECCS pumps as necessary, and go to EOP-LOCA-2.

K. The scenario will terminate when the transition to LOCA-2 has been made.

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TQ-AA-106-0204 Page 4 of 27 IC-231 PREP FOR TRAINING (i.e.,computerset~oints, 1 procedures',be~el ~gver~';te1gged equipment)

Initial I Description 1 VC1 and VC4 CIT 2 RCPs (SELF CHECK)

_ 3 RTBs (SELF CHECK)

_ 4 MS167s (SELF CHECK)

_ 5 500 KV SWYD (SELF CHECK)

_ 6 SGFP Trip (SELF CHECK)

_ 7 23 CV PP (SELF CHECK) 8 PZR Pressure Channel Ill selected for Control.

g 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 Permission from Nuclear Training

TQ-AA-106-0204 Page 5 of 27 ET# Description 1 1 EVENT-ACTION: I COMMAND:

PURPOSE:

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time 01 PR0017A PZR LEVEL CH I LT459 FAILS H/L NIA N/A RT-1 0 RC0002 RCS LEAK INTO CONTAINMENT (equiv to 0-02 N/A N/A ~J/A RT-3 20 4 inches 03 RP0342 2SJ12 FAILS TO AUTO OPEN ON SEC N/A N/A N/A N/A 04 RP0343 2SJ13 FAILS TO AUTO OPEN ON SEC NIA NIA N/A N/A 05 RP318E1 Aux Feed Pum 21 Fails to Start on SEC NIA NIA NIA N/A 06 RP318E2 Aux Feed Pump 22 Fails to Start on SEC NIA NIA NIA N/A AF0353A 21 AFP FAILURE TO AUTO START ON ANY 07 NIA NIA NIA N/A (ALL SIGNALS AF0353B 22 AFP FAILURE TO AUTO START ON ANY 08 N/A NIA NIA NIA ALL SIGNALS SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time 01 DG01 D DE ENERGIZE "A" SEC CABINET N/A N/A NIA RT-9 YES 02 SP01A1 Prevailin Wind S eed N/A N/A NIA N/A 10 03 SP01A2 Prevailin Wind Direction NIA N/A N/A NIA 160 04 MS05A 21 MS45 21 STM GEN STM SUP-23 AFP NIA NIA N/A NIA 0 05 MS06A 23MS45 23 STM GEN STM SUP-23 AFP NIA N/;\ N/A NIA 0 SELF-CHECK 01 Description CB09 A DI KCB09ASE 2A SFGD EMER OPR-EMERG Delay Time NIA Initial Value N/A Ramp Time i'JIA Trigger i'J/A Condition/

Sem;ty j OFF LOADING RESET PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 6 of 27 Description 1.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 7 of 27 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 8 of 27 Jfv~fUatpW1nstr:dctqr Activily ,@: ... ' ;if:'ex{.tlctecJ'~,ia{lt/Sfodel)t:Rlsponse; J::SBT

1. Controlling PZR Level Channel Fails LOW

,simulafor Oper:at~r: Insert RT*1

- - on direction from L.ead Evaluator.

.MALF~PR0017APZRtVLCH I

,(LT459)FAH.:5H/L **' .

Severity: 0 .

RO reports unexpected OHA E-36, PZR HTR OFF LVL LO.

RO diagnoses controlling PZR level channel failure.

RO may request permission to place the Master Flow Controller in manual prior to direction in AB.eve to do so.

CRS enters 82.0P-AB.CVC-0001, Loss of Charging.

CRS directs initiation of Attachment 1 CAS.

RO reports charging pumps are running, and no indication of cavitation.

RO reports PZR level channel I has failed low.

If not previously performed, RO takes manual control of charging and maintains PZR level within band assigned by CRS.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 9 of 27

.* ',ri<e;ta1uator/lnstfucli

,' '1i-;'. )~J' ;+/-}*.':. I .?:.:'.,~* -. '

exriected, i>1ant/s~lltl~nt:R~spO,ose,&:, . .SBTi

~.

RO selects operable channel for Control, Alarm, and Recorders.

RO restores PZR heaters to pre-event condition.

RO announces OHA E-20 PZR HTR ON LVL HI as expected when it annunciates due to no letdown with charging flow established.

PO restores letdown by:

- Ensuring open 2CV7

- Placing 2CV18 in manual and closing, then opening until close PB extinguishes.

- Opening 2CV2 and 2CV277, then placing both in auto.

- Ensuring charging flow is 90 gpm.

- Opening a 75 gpm orifice isolation valve while adjusting 2CV18 to control letdown pressure -300 psig.

- Placing 2CV18 in auto.

RO returns Master Flow Controller to auto when PZR level returns to proqram.

CRS contacts IC for assistance in removing channel from service.

CRS enter LCO 3.3.1.1 action 6.

Proceed to next event after Tech Spec call at direction from Lead evaluator.

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TQ-AA-106-0204 Page 10 of 27 eva1u*at0rlfrndruclor Activity ~.,*'

~?Jf"': ,,.,! ~:,~.?'-- '.*~,f,;;\ !~;,~'**+_ ~~-:;::( ,~?;~fe:'~,. ;{('f,(<<:e i:r""'~*

'F!xpeq~ed:(P~~nt/Student.Re'ipdnse

, ;~:c~~

1

. ,,,,,, **____,. *"*---- *--, ;,*.*.*' *'"t ,_, '""""'""

~ssf,'.

LOG't

&c~,M~"t:>~;r' . 11t"

3. 20 gpm RCS leak Simulator Operator: Insert RT-3 orfdirection from Lead Evaluator

MALF: RC0002 ,.;.. ~cs Le~k into containment..

Final Value: 20 gpm*

RO reports that charging flow is rising (if MFC has been returned to auto) and PZR level is lowering slowly.

Crew reports reading on 2R11A containment radiation monitor is rising.

RO reports unexpected OHA C-2 CNTMT SUMP PMP START when it occurs.

CRS enters S2. OP-AB. RC-0001, Reactor Coolant System Leak.

CRS directs initiation of Attachment 1 CAS.

RO reports RCS temperature > 350°F in Mode 1.

RO reports PZR level is lowering.

Note: PZR level is above program, and charging flow will be lower than normal to reduce PZR level. If charging flow is raised here to stabilize level, then step to place a centrifugal charging pump in PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 11of27

.EvaluatofJl~itrii(;tf>riActivitY * * . '.l:xJ)~ctiJ.~f J'lafntJStuderlt Rispori~~ ,,,-,c

.li'SBT <fomment:.;~¥<1,

~kr "'~~( /~~/

,.'A,*, )~ '- C), i'.' ,} /"!~, *,,0/?f',, ~)/'. >~>j/ t ,* '- )7 ,;;# , 4 ',, .**~' "'"'- " ' '.<<*'*

,,"J,,

service may not be performed.

CRS enters S2.0P-AB.RAD-0001, Abnormal Radiation after OHA A-6 unexpected annunciation.

RO swaps to a centrifugal charging pump IAW Step 3.14, and raises charging flow to stabilize PZR level.

PO reduces letdown flow to minimum by opening 2CV3, maintaining letdown pressure

-300 psig with 2CV18 in manual, then closing the open 75 gpm orifice and returning 2CV18 to auto.

RO stabilizes PZR level and estimates leak rate.

CRS initiates S2.0P-ST.RC-0008, Reactor Coolant System Water Inventory Balance.

CRS contacts Rad Pro for recommendation on CFCU operation.

Role Play: If contacted state Rad Pro recommends placing 2 CFCU's in Low Speed and 2 CFCU's in High Speed.

PO places 2 CFCU's in Low Speed and 2 CFCU's in High Speed.

CRS initiates actions to locate and isolate the leak IAW Attachment 2.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 12 of 27

.*.;~~E'laluc:ilor/lh$ltuetoJ;~£Act1VitY

,v~. A~" ~ .. i :._,.-~, ~ ~, ~,1tr:* J' , ,'§' . "~,AL

.;'lt,

' ~ ,, ' ;.~;*

~ Exi>&cted*Ptant1stuaenl

~;J, .; wj. iJt ResPtlnse*

, __A[.!*, : >~t<*'

.,,,"s***a**Tc * * * *

.*. *a_,51( !rco'l)r~J"lr:;:* ***

CRS enters TSAS 3.4.7.2.b action b for RCS leakage, and 3.6.1.4 for containment pressure if it has reached 0.3 psiq.

Role Play: After RCS leakage Tech Spec has been identified, if CRS does not initiate a power reduction to bring the unit offline, call Control Room as Operations Director and instruct the CRS to initiate a 30% per hour load reduction to 20% in preparation for taking Unit 2 offline to investigate and repair the RCS leak.

CRS briefs power reduction.

RO initiates boration.

PO initiates turbine load reduction at 30% per hour.

CRS may enter S2.0P-AB.LOAD-0001 Rapid Load Reduction to perform the power reduction.

Proceed to next event on direction from Lead Evaluator.

3. SBLOCA Simulator Operator: .MODIFY MALF RC0002 from 20 to 150 on direction from Lead Evaluator.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 13 of 27 eval,uatb.rtlnstructor ActivitY;'* . Expict~CI PlantlsfodeijfRespoJ\sef"" '/\'$'81 Commeilf *

.. . *7*. .."t*

. .* i'. ... ****, F ',.\.,~ J > 37' * ;1* LOG* *i RO reports PZR level trending down and adjusts charging flow to maintain PZR level.

RO reports PZR level will not be able to be maintained >17%.

CRS directs Rx trip and Safety Injection RO trips the reactor and confirms the reactor trip.

RO initiates Safety Injection.

RO continues Immediate Actions of TRIP-1

- Trips the Main Turbine

- Reports at least one 4KV vital bus energized.

- Reports SI initiated.

CRS and RO verify performance of immediate actions.

4. AFW fails to initiate PO reports SEC loading is not complete for 2A and 28 vital buses, 21 and 22 AFW pumps have failed to start. Reports 23 AFW pump started but is not providinq any AFW flow.

RO blocks 2A and 28 SECs.

PO resets 2A and 28 SECs.

PO reports 2A SEC will not reset.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 14 of 27

<r .. evafo~lotll~stru~o~.A,ctijitf' 5~:';expected.:P1a11tf5tudent Resp<>n$e,,

'"Y" . ,,., '*" ,, . ' .

.,;,sBT1;:S

corl)ment,~:,

,;',- :' .*. .. *. ... ... :~

CRS dispatches operator to deenergize 2A SEC.

Simulator Operator: 2 minutes

~fter being dispatched, jnsert RT-9 to deenergize 2A SEC:

RO starts 22 AFW pump.

CT#1 (cr.:s) Establish atleast

22E4 lbl11/hr AFWflowto the *

SG's prior to a transition to FRHS*1 being required. *

'>\'

SAT UNSAT PO reports AFW pump status, and starts 21 AFW pump when 2A SEC is deenergized.

PO reports not all valve groups in Table B are in safequards position.

PO reports 2SJ 12 and 2SJ 13 BIT isolation valves have not opened.

RO opens 2SJ12 and 2SJ13 and reports BIT flow is established.

CT#2 {CT*6) Establish flow from

'atleastone charging pump prior to transition out ofTRIP-1.

SAT UNSAT PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 15 of 27

~- ~ 7 Commenf" *

..,, ", ~

JS;.. iJ! ~t~fii y;:: .* ,cklJ:ii, ft :fd;. ;~~jt r* ... **** <*

) t: cf<' t** Y,'.;Jw .:0:. LOGt I

RO reports 21 and 22CA330s are shut.

RO reports containment pressure has remained <15 psig.

PO reports no high steam flow condition.

CRS directs implementation of the ECG.

PO reports all 4KV vital buses enerqized.

RO reports CAV in AP mode.

RO reports 2 switchgear supply and one exhaust fan are running.

RO reports 2 or more CCW pumps running.

RO reports RCS not aligned for Cold Leg Recirc.

RO reports charging flow is at least 100 gpm on SI systems charc::iinq flow meter.

RO reports RCS pressure is not <1540 psiq.

PO reports total AFW flow is 22E4 lbm/hr or 9% level in at least one SG NR level, then maintains 19-33% level.

RO reports all RCPs running, and RCS temperature is stable at or trending to 547°F.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 16 of 27

'f,Evaluator!lnst~ctor Acdvlfy " 7~:~ Expebted, Plaht/Student RespoHse ** SBT . r Comment .\.Bn* ....

i~;,:cr~ :>}".\~*~(,,.c ,,.,,

RO reports both RTBs are open.

RO reports both PZR PORVs are shut with their Block Valves open.

RO reports all RCPs in service and PZR spray operating as expected for current plant conditions.

RO reports RCS pressure >1350 psig and maintains seal injection flow to all RCPs.

PO reports no indication of faulted SGs.

PO/RO report no indications of a steam generator tube rupture.

RO reports radiation monitor channel status in Table F.

PO reports 2 or more channels rising or in warninq or alarm.

CRS transitions to EOP-LOCA-1, Loss of Reactor Coolant.

Note: CFST monitoring will commence after the transition out of TRI P-1. STA will report to the control room 10 minutes after being paged.

PO reports no faulted SGs.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 17 of 27

.,.~e:valuatCff!(~~tructorAcUvify 1

'Sxpd~ted 'f>1aflt/StuBent Respo*nse ".ii'*IV' ;.,sat ,,vi "Cofumerii.'7 r,, *

'{7~>

'h AT~:!'~ ,~,**'!~J:JF;~;~;,,,

PO reports total AFW flow is 22E4 lbm/hr or 9% level in at least one SG NR level, then maintains 19-33% level.

PO reports no ruptured SGs.

RO resets SI, Phase A, and Phase B isolations.

RO opens 21 and 22CA330s.

PO resets 2C SEC, and reports 230V control centers reset.

RO resets SGBD Sample Isolation Bypass and opens21-24SS94s.

CRS directs chemistry to sample SGs for activity and boron.

RO reports PORVs are shut with Block valves open.

RO reports subcoolinq > 0°F.

PO reports AFW flow >22E4 lbm/hr or SG NR level >9%.

RO reports RCS pressure is stable or risinq.

RO reports PZR level >11 %.

CRS transitions to EOP-TRIP-3, SI Termination.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 18 of 27 Evaiuator/lnstfocfor A'ctivitY . . E;xp~Cfe(ltPlant/StuCle*nt Resp(mse~"": SBT comment *,*M*\

5

£ *, *

'1 .il'0'lft , ,, ';~ ~;* i2t*'*5 ' v";>'..*; ' .~J'.'.)RQ{)t/"'- "'

LOG RO resets SI, Phase A, and Phase B isolations if not previously reset.

RO opens 21 and 22CA330s if not previously performed.

RO reports spray valves are not failed open.

PO resets 2C SEC and reports 230V control centers reset if not previously performed.

RO stops all but one charqinq pump.

RO reports RCS pressure is stable or risinq.

RO reports charging pump suction is aligned to the RWST.

RO opens 2CV139 and 2CV140 if shut.

RO shuts BIT isolation valves 2SJ4, 2SJ5, 2SJ12, 2SJ13.

RO shuts 2CV55 Charqinq Flow Control valve.

RO opens 2CV68 and 2CV69 Charging Discharqe valves.

Simulator Operator: MODIFY MALF RC0002 from . 150 to 2000 when 2CV68 and 2CV69 are ooen.

RO adjusts 2CV55 to maintain PZR level PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 19 of 27

Evaluatortl'nstruct.6r

',; /,, :. .

~: )~{' ,}:>*:**

Activity::'

~:*.;',

"!1ft1c.pected* Plant/Student' Response ..

A". ~

T:3*;.

SB ,.~§~~'.. > Commen'f *)J&:J1!:~r *.

.,,,:;; 1n~*7 '* .s >d'.>: '*

'.~* fr,: . :t' : .*. L;\;l\.;J .. .j

>25%.

RO reports PZR level is not stable or risinq.

PO reports no faulted SGs.

RO opens BIT isolation valves 2SJ4,5, 12, 13, and shuts normal charging line isolation valves 2CV68 and 69.

CRS goes to EOP-LOCA-2, Post LOCA Cooldown and Depressurization.

Terminate scenario on direction from Lead Evaluator after the transition to LOCA-2 is made.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 20 of 27 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-10.ZZ-0004, Power Operation F. S2.0P-AB.CVC-0001, Loss of Charging G. S2.0P-AB.RC-0001, Reactor Coolant System Leak H. 2-EOP-TRIP-1, Reactor Trip or Safety Injection I. 2-EOP-TRIP-3, Safety Injection Termination J. 2-EOP-LOCA-1, Loss of Reactor Coolant K. 2-EOP-LOCA-2, Post LOCA Cooldown and Depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 21of27 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 100% RCS BORON: 857 MWe 1220 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS MOST LIMITING LCO AND DATEfflME OF EXPIRATION:

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

ABNORMAL PLANT CONFIGURATIONS:

PZR Pressure Channel Ill is selected for Control CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

SECONDARY:

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 22 of 27 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked "Training Use Only" and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 23 of 27 ATTACHMENT 3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an 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 24 of 27 SCENARIO IDENTIFIER: 15-01 ILOT NRC ESG-1 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario.

CR 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.

CR 3. The scenario consists mostly of related events.

CR 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 CR 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.

CR 6. The events are valid with regard to physics and thermodynamics.

CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

CR 8. The simulator modeling is not altered.

CR 9. All crew competencies can be evaluated.

CR 10. The scenario has been validated.

CR 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.

CR 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 Page 25 of 27 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section 0.5.d)

GG 3 Malfunctions 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 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 26 of 27 15-01 NRC ESG-1 CT#1 (CT-4) Establish the minimum required feed flow prior to a transition to FRHS-1 being required.

Basis: Failure to establish the required minimum feed flow rate under the postulated plant conditions, results in "adverse consequence(s) or significant degradation in the mitigative capability of the plant."

Failure to perform the critical task represents a "demonstrated inability of the crew to:

Take an action or combination of actions that would prevent a challenge to plant safety Recognize a failure I incorrect auto actuation of an ESF system or component."

CT#2 (CT-6) Establish flow from at least one high-head ECCS pump before transition out of TRIP-1.

Basis: Failure to manually start at least one Charging pump under the postulated conditions constitutes misoperation or incorrect crew performance in which the crew does not prevent "degraded emergency core cooling system (ECCS) ... capacity." In this case, at least one Charging/SI pump (high-head SI pump for LP plants) can be manually started from the control room. Therefore, failure to manually start a Charging/SI pump (high-head SI pump for LP plants) also represents a failure by the crew to "demonstrate the following abilities:

Effectively direct or manipulate engineered safety feature (ESF) controls that would prevent a significant reduction of safety margin beyond that irreparably introduced by the scenario Recognize a failure or an incorrect automatic actuation of an ESF system or component" Additionally, under the postulated plant conditions, failure to manually start a Charging/SI pump (high-head SI pump for LP plants) (when it is possible to do so) is a "violation of the facility license condition."

Note to Evaluators: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Task procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 27 of 27 ATTACHMENT6:

ESG-PRA ~ELATIONSHIP: E~A~UATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out y LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TO~lll.I N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.

TQ-AA-106-0204 Page 1 of 32 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-2 SCENARIO NUMBER: 15-01 NRC ESG-2 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: ,____ ___,\ LO. REQUAL X \ INITIAL LICENSE

..________,\ STA

~-~'OTHER Revision Summary New issue for 15-01 !LOT NRC exam PREPARED BY: G Gauding 8-3-16 Lead Regulatory Exam Author Date APPROVED BY: JVivFl raining Manager

("~?late 4

APPROVED BY:

~ aClHty Repre ~ .i.f/LA.ifij atlve

{J)/,, IL~

'Tdate 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 loss of a heater drain pump or condensate pump, take corrective action IAW S2.0P-AB.CN-0001.

B. 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 S2.0P-AB.CN-0001.

C. Given indication of a feedwater or condensate system malfunction, DIRECT the response to the malfunction in accordance with S2.0P-AB.CN-0001.

D. Given a steam generator tube leak, take corrective action, IAW S2.0P-AB.SG-0001.

E. 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 S1/S2.0P-AB.SG-0001.

F. Given the order or indications of a steam generator tube leak (SGTL), DIRECT the response to the tube leak, in accordance with S2.0P-AB.SG-0001.

G. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

I. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

J. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

K. Given the order or indications of a steam generator tube rupture (SGTR), perform actions as the nuclear control operator to RESPOND to the tube rupture in accordance with the approved station procedures.

L. Given indication of a steam generator tube rupture (SGTR), DIRECT the response to the SGTR in accordance with the approved station procedures.

A. 2C EDG Pre-lube pump failure (TS)

B. 23 Condensate pump trip /Power Reduction C. 21 SGTL I 21 SGTR D. Loss of Spray during RCS depressurization E. Stuck open PZR PORV during RCS depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 4 of 32 A. The crew will take the watch with the unit at 89.4% power, BOL. Power was reduced last shift in preparation for performing Main Turbine Valve testing later this shift. 2C EOG Jacket Water heater failed last shift. Condensate Polisher is in service.

B. After the crew assumes the watch, the 2C EOG Pre-lube pump will fail. The CRS will identify 2C EOG is now inoperable, and enter the appropriate LCO. The CRS will initiate actions to ensure S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alignment is performed within one hour.

C. After the EOG failure has been addressed, 23 Condensate pump will trip. The crew will enter S2.0P-AB.CN-0001, Main Feedwater I Condensate System Abnormality, and perform actions to bypass the polisher and feedwater heaters strings as required to maintain SGFP suction pressure.

D. The crew will perform a power reduction to~ 85% power and ensure SGFP suction pressure remains above 320 psig.

E. During the power reduction, a SGTL will occur on 21 SG. The crew will enter S2.0P-AB.SG-0001, Steam Generator Tube Leak. The crew will perform actions to minimize the spread of secondary contamination and minimize the potential for steam release from the affected SG.

The crew will isolate the steam supply to 23 AFW pump from 21 SG, and the CRS will identify 23 AFW is inoperable and enter the appropriate LCO.

F. After the AFW pump LCO is identified, the SG tube will rupture. The crew will identify the SGTR, and initiate a Rx trip and Safety Injection based on the uncontrolled rise in 21 SG NR or WR level.

G. The crew will perform plant stabilization and diagnostics in EOP-TRIP-1, Reactor Trip or Safety Injection. 21 AFW pump will trip shortly after starting. The crew will isolate AFW flow to and steam flow from 21 SG. (CT-1 ).

H. The crew will transition to EOP-SGTR-1, Steam Generator Tube Rupture to address the tube rupture. The crew will perform a cooldown to target temperature and demonstrate the ability to maintain RCS temperature< Target temperature (CT-2). The crew will initiate a RCS depressurization. During the depressurization the RCP providing driving head for Spray flow will trip. The crew will open a PZR PORV to continue the depressurization. If 2PR1 is the selected PORV, it will not open, and 2PR2 will be used.

I. The PZR PORV opened to depressurize the RCS will fail to shut when demanded after the depressurization is complete. The crew will attempt to terminate the depressurization by closing the PORV Block valve, which will not shut.

J. The scenario will be terminated after the CRS transitions to EOP-SGTR-3, SGTR with LOCA -

Subcooled Recovery, to address the loss of RCS pressure with the stuck open PORV.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 5 of 32 IC-232 PREP FOR<TRAINl~G (i.e,~ computer setpoint~~,proc~dure!), l:>~zel C()V~~s ,tagged equipment)

Initial I Description 1 VC1 and VC4 CIT 2 RCPs (SELF CHECK)

_ 3 RTBs (SELF CHECK)

_ 4 MS167s (SELF CHECK)

_ 5 500 KV SWYD (SELF CHECK)

_ 6 SGFP Trip (SELF CHECK)

_ 7 23 CV PP (SELF CHECK) 8 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 Permission from Nuclear Training

TQ-AA-106-0204 Page.6 of 32 Description

- -~* - - - --

EVENT ACTION: MONP254 <10. //CONTROL BANK C GROUP POSITION 1 COMMAND:

PURPOSE: <update as needed>

EVENT ACTION: KB202LCI //2PR7 RELIEF VALVE-22 STOP VALVE 3 COMMAND:

PURPOSE: <update as needed>

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time SER POINT AN0266 SER 266 FAILS - :J20 2C DIESEL 01 N/A N/A N/A RT-1 FAILS/OVRD GENERATOR URGENT TROUBLE TOON 02 CN0117C 23 CONDENSATE PUMP TRIP N/A NIA NIA RT-3 03 SG0078A 21 STEAM GENERATOR TUBE RUPTURE N/A NIA N/A RT-5 5 AAS POINT 04 AN3735 AAS 735 FAILS - :21 TGA SUMP LEVEL HIGH 00:03:00 N/A N/A RT-11 FAILS/OVRD TOON AAS POINT 05 AN3736 AAS 736 FAILS - :22 TGA SUMP LEVEL HIGH 00:03:10 N/A NIA RT-11 FAILS/OVRD TOON AAS POINT 06 AN3737 AAS 737 FAILS - :23 TGA SUMP LEVEL HIGH 00:03:20 N/A N/A RT-11 FAILS/OVRD TOON AAS POINT 07 AN3738 AAS 738 FAILS - :24 TGA SUMP LEVEL HIGH 00:03:30 N/A N/A RT-11 FAILS/OVRD TOON AAS POINT 08 AN3739 AAS 739 FAILS - :25 TGA SUMP LEVEL HIGH 00:03:50 N/A NIA RT-11 FAILS/OVRD TOON 09 AF0181A 21 AUX FEEDWATER PUMP TRIP 00:04:00 NIA N/A ET-1 10 VL0297 2PR1 Fails to Position 0-100%) NIA N/A N/A N/A 0 11 VL0298 2PR2 Fails to Position 0-100% NIA N/A N/A RT-13 100 12 RC0003C 23 RC PUMP ELECTRICAL TRIP N/A NIA NIA RT-7 13 RC0003A 21 RC PUMP ELECTRICAL TRIP NIA NIA N/A RT-9 14 VL0123 2PR7 Fails to Position ( 0-100%) NIA NIA NIA ET-3 90 15 CV0035 CHRG MASTER FLO CNTRLR FAILS H/L N/A NIA t'11A RT-15 26 SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time 01 SP01A1 Prevailing Wind Speed NIA NIA NIA NIA 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 7 of 32 02 GP01A2 Prevailing Wind Direction NIA N/A NIA SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity C201 A LO QC201AY3 2C DIESEL GEN-TROUBLE 01 NIA NIA NIA ON ALARM Description

1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 8 of 32

\j\1,i '"'--

-*<gq 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 32

,.lEva'u~tptr11il'structor Activ'lty ... {~:~'Exp,~te~"'plawnt/Stu~1enf R~!e#fise

comment****

.,Y':, *, )~i j c:~,f,~4 > ~', ~?:/,'>;*~, ;',:;,~L,~, ~= ~, . , ", d, ,_.~,

! ;. ;,HJ 7,r,. i1# 1. . ;tt .> . ; ;;,1lN: *.. . *.

1. 2C EOG Pre-Lube pump failure Simulator Operator: Insert RT-1 oh direction from Lead.Evaluator.

.MALF: lAN0266 SER,266 Fails;...

J20 2C~DlESEL GENERATOR::

URGENT TROUBLE PO announces unexpected OHA J-20, 2C DG URGENT TRBL.

The crew refers to the ARP and dispatches an operator to investiaate.

Role play: 2 minutes after being dispatched call control room and report 2C EOG Alarm Window A-7 PRE-LUBE PUMP FAILURE is in alarm. You have checked the Pre-lube pump and it is NOT running.

The Pre-lube pump breaker remains shut.

CRS refers to S2.0P-SO.DG-0003, 2C Diesel Generator Operation and recognizes 2C EOG is now inoperable with the Jacket Water Heater and Pre-lube pump inoperable, and enters LCO 3.8.1.1.b, action b.

CRS determines that S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alianment must be oerformed within one hour PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 10 of 32

~.* E\(alii'atofl:ln:stiuctor ActivltY,; . .ExReCted PlanflStudent,Response c" .* ;J 1?s'er Commeot1t 1

, , '. *:~~i~ ~r;;* *~.*rt ! iJ.:;,:.li> ;<ii~; , -~,-k . t ~>>~gJ~~i\1f _*. , .:i1~:'** .';**?:- *,P~*~;;;: 1<:?; - :J~~~ zf LoG. ,,;~t~k ~,:~~TI:-; -~

to demonstrate the operability of the independent AC Sources (action b.1)

Proceed to next event on direction from Lead Evaluator.

2. 23 Condensate pump trip I down power Simulator Operator: Insert RT-3 on dfrection from Lead Evaluator.

1 MALF:CN0117C 23 Condensate pump trip*

PO announces 23 Condensate pump trip.

CRS enters S2.0P-AB.CN-0001, Main Feedwater I Condensate System Abnormality.

PO reports no SGFP tripped.

PO reports 23 Condensate pump tripped.

PO bypasses condensate polisher by opening 21 thru 23 CN108 if SGFP suction pressure is

<320 psiQ.

Role Play: If dispatched, after 3 minutes report as NEO that you can't see anything wrong with 21 condensate pump. If dispatched to 4KV breaker, report after 2 minutes that there is an overcurrent relay flag dropped.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 11 of 32

. J;yaluat0rl1fistr4c(orActivity ~

Expec!id;~1ant1~tudent Response .

Comment1f!t:

,; J\t~t, , , '. ':::Y~~>ilZ,r *: ,'~ ,',

7~~ , , ,'*ltc;;,;hf1t~ ,;'~*

, i~l~'., ,c '~~~,' +1~,*:~g~;

PO reports SGFP suction pressure.

Note: Crew should discuss power increase expected when the CN47 is opened. (Note in AB.CN-1 ).

CRS directs 2CN47 opened if suction pressure remains< 320 psig.

PO isolates letdown by closing 21-24BG4 and 21-24GB185 if 2CN47 is open.

CRS directs power reduction to 85% at

~5%/min with 2 Condensate pumps and 3 Heater Drain pumps in service IAW Attachment 4.

CRS enters S2.0P-AB.LOAD-0001, Rapid Load Reduction, to perform the load reduction.

CRS directs initiation of AB.LOAD CAS.

RO calculates boron addition and rate for power reduction.

RO initiates boration.

PO initiates turbine load reduction to 85% at rate directed by CRS.

3. Master Flow Controller failure I Simulator Operator: Once the PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 12 of 32

.~.~~?~tivi,,f *

Expe'eted~planOStudent Res~onse'.*

mment . f;w

,': tr r~' ' :t' ,, ~,{]~~;'.' , !;:( ' ;;,!~' / , ;,, )',

power reduction is underway, insert RT-15 to fail the. Master F.low Controller.

MALF: CV0035' CHRG Master Flow Controller fails H/L . .

Severitv: 26 **

RO reports unexpected low seal injection flow alarms on all RCP's.

RO reports Master Flow Controller is failed based on lower than expected Charging flow 75 apm vs 87 aom CRS enters S2.0P-AB.CVC-0001, Loss of Charaina.

RO may use Alarm Response Procedure initially in response to Low Seal Injection Flow to adjust 2CV71 to restore seal injection flow to above the alarm setpoint, but this will not restore normal charaina flow.

RO reports:

- A charging pump is running with no indication of cavitation RO reports neither a PZR level nor a VCT level channel has failed.

No indication of charaina svstem leak RO reports the Charging Master Flow Controller has failed.

RO takes manual control of 23 charain PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 13 of 32 ccfmme'nf * *

s \j .* !* *.di?/ ::/ r:r, .~0* ff .:.I *; ;xtfi.ffil,&.§'LUl:i ';r~l\1".*

J/}., ,,f; pump, and adjusts speed to maintain PZR level on proqram IAW Att. 2.

RO reports PZR level can be maintained stable or rising.

RO announces auto rod motion when it occurs.

Proceed to next event on direction from Lead Evaluator.

4. 21 SG Tube Leak Simulator Operator; Insert RT-5 on direction from Lead evaluator.

.* MALF: SG00078A 21 STEAM

.GENERATOR TUBE RUPTURE Severity: 5 ;

RO reports unexpected OHA A-6 and identifies 2R53A 21 Main Steamline N2 monitor from CRT indication in alarm.

RO reports 2R53A level >1000 qpd.

CRS enters S2.0P-AB.SG-0001, Steam Generator Tube Leak, and S2.0P-AB.RAD-0001, Abnormal Radiation.

RO reports OHA A-6 reflash is 2R15 Condenser Air Ejector monitor in alarm.

CRS directs initiation of AB.SG CAS.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 14 of 32

- 1i;Evalqator/1nstructor

<' n J(ct1v1fy:i!f!!!J;. *ExnecteCl,fr>..~*.

. 0 fant/student Rijspo1lae'.l11:*.~~*.***

, N.r:~:: * , :,~~~>>' ,,

sar:

,,,, ' if~-~

b,f';;~*:J ';f.:d.i', ~.,.Zd .. , .~~.c0 ,, .... * ,; , "l c

t *.. ,.~ ...* ~*** ,;'c ,.* **~ . ** -*- ._.,,c, *:W '

RO reports when 2R 19A is in warning and alarm.

PO reports when SGBD isolation occurs on hiqh radiation.

CRS dispatches operator to isolate TGA and Condensate Polisher area sump pumps.

Simulator Operator:. When dispatched to.* isolatetfGA and polisher building sum'ps, insert RT-

,11. This deenergizes 21 :25 TGA sump pumps after a 3 minute time delay.

RO reports PZR level being maintained stable by risinq charqinq flow.

Note: Initial charging flow with stable PZR level is -89 gpm. 23 charging pump will deliver -99 gpm at full flow and seal injection of -26 gpm. IF RO reports PZR level is lowering (due to lag in Master Flow control response,) then RO will swap to a centrifugal charging pump at Step 3.6.

RO reports PZR level can be maintained stable or risinq.

Note: SGBD will isolate -2.5 minutes after 2R53D alarms. This PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 15 of 32

E\/alUator11nstn.ictor ActNitY comment:"'* *

,I <~~rj~'f *;;~: -, ,j,J;;, ,~.J~~t~,- ,"~

~wr -,

will cause RCS temp and PZR level to rise.

PO reports when load reduction is complete.

RO reports unit 2 is in MODE 1.

RO reports 21 SG is affected SG.

PO sets 21MS10 to 1045 psig, and ensures 21GB4, 21MS18, and 21MS7 are shut.

CRS dispatches an operator to shut 21 MS45 steam supply to 23 AFW pump.

Note: Do NOT report the 21 MS45 is shut until AFTER 23 AFW pump has been tripped at step 4. 7 of SGTR-1.

CRS enters LCO 3. 7 .1.2 for less than 3 operable AFW pumps, and LCO 3.4.7.2.c for

>150 gpd primary to secondary leakage though 21 SG.

CRS determines (Action Level 3) the unit must be less than 50% in less than one hour, the unit placed in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

CRS dispatches an operator to realign SGBD and Samplinq.

Proceed to next event on direction from Lead Evaluator after Tech Specs have been addressed.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 16 of 32

'eva1 ;Jr Ai ... e** d1]>1ant1Student R, SBT *;;~rc~:0,1m~~~,;~r**

5. SGTR Simulator Operator: MODIFY

. MALF SG00078A from 5 to 650 on direction from Lead Evaluator.

RO reports indications of worsening tube leak/rupture, with lowering PZR level and pressure.

CRS directs RO to trip the Rx, confirm the Rx trip, and initiate a Safety Injection, then enter TRIP-1.

RO trips the Rx, confirms the Rx trip, and initiates Safety Injection.

Simulator Operator: Ensure ET*1 is true when the* rx is tripped., This trips 21 AFW pump after a 4 minute delay.

RO backs up the Main Turbine trip, reports 4KV vital buses energized, and reports SI manually initiated.

CRS and RO verify TRIP-1 immediate actions.

PO receives CRS concurrence and isolates AFW to 21 SG by closing 21AF11 and 21AF21.

CT#1 (CT-18) Isolate feed flow into (oart 1) and steam flow from PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 17 of 32

. E~pected Pliint/s~µaenf Res~onse **

<' :7,£}: '~' , ;, _'*' . ~t00,,', ' ;~f~:~;- '

.Co~;;",~:!~~if!I ~:: iiw,*1"'**

(part 2) 21SG prior to a transition to SGTR-3 being required ..(steamflow isolation will be perform~~ on page 19)

Part*1 UNSAT_ _

SAT PO receives CRS concurrence and reduces total AFW flow to no less than 22E04 lbm/hr until at least one SG NR level is> 9%, then maintains NR levels 19-33%.

6. 21 AFW pump trip PO reports when 21 AFW pump trips, and adjusts flow from 22 and 23 AFW pumps as reauired based on current SG NR levels.

Note:

21 AFW pp supplies 23/24 SGs 22 AFW pp supplies 21/22 SGs 23 AFW pump supplies all SGs Simulator Operator: Use

REMOTE AF20 to OFF 2 minutes after being dispatched to remove **

control power from 21 AFW pump breaker.

PO reports all available equipment started on SEC loadina.

PO reoorts which AFW oumps are runnin PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 18 of 32

' *Evaluator/fnsln1ctor Acti~ityw*

- '.-:~?f~~- ~rr ~ _,,,,>AL , ;;v~:, ,,,,, , 'l~','

i~1Expe~te& Pla'nt/Studenf Response $BT . ' . Comment , . ~' *~tt PO reports correct safeguards valve alignment.

RO reports 21 and 22CA330s are shut.

RO reports containment pressure remains less than 15 psig.

PO reports no indication of hi steam flow.

PO reports all 4KV vital buses enerqized.

RO reports ventilation systems lineups correct for current plant conditions.

RO reports at least 2 CCW pumps are running.

RO reports proper ECCS flow indicated for current plant conditions.

PO reports AFW status, and maintains at least 22E4 lbm/hr flow until at least one SG NR level is >9%, then maintains SG NR levels 19-33%.

RO reports RCP status, and RCS temperature stable at or trendinq to 547°.

RO reports both RTBs are open.

RO reports PZR PORVs are shut with Block valves open.

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TQ-AA-106-0204 Page 19 of 32

e,,~ruator/rr;1str~Pf6r,e.ctivi~x~.. Expecte'tl .Plant/StuClenr Respons~,f" * **~.e'f* : ir*gomJQPnF

.118

~l r,,;. _ ,,,,,,;'Jt* *;:(f~f( ,,'.l"< ~c,j~),, ' "'* !;;/:;~* ~\f~~* ~ff;* f~~f-~t 1 ';;. ,~'.~~P' *,;,:~i?f' 1 J.'./,, ., J.r:OG; ..,.

RO reports PZR spray status for current plant conditions.

RO reports RCS pressure is >1350 psig.

RO maintains seal injection flow to RCPs.

PO reports no SGs are faulted.

PO reports NR or WR level is risinq in 21 SG.

CRS transitions to EOP-SGTR-1, Steam Generator Tube Rupture.

Note: STA will report to Control Room 10 minutes after being paged to report, and initiate monitoring of CFSTs.

RO maintains seal injection flow to all RCPs.

PO reports 21 SG is ruptured, and ensures 21MS10 is set at 1045 psiq.

PO reports 21 MS10 operating as expected for current pressure.

PO shuts 21MS167, and verifies 21MS7, 21MS18, and 21GB4 are shut.

Note: These steps complete CT#1 CT#1 (CT-18) Isolate feed flow into and steam flow from 21 SG prior to a transition to SGTR-3 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 20 of 32 1:). Eipedted' Plant/Student Re$poose' * *set

, ~f ,,'~j;f,'._ , *:1; 1

,*:J <("",_ , : *, >f:/:\., : ,.,/\:iL t '

bOG being required.

SAT UNSAT PO reoorts 21 SG is ruotured.

PO reports 23 AFW pump is not the only source of AFW.

PO ensures 23 AFW pump speed at minimum and trios 23 AFW oumo.

CRS dispatches operator to shut 21 MS45 if not oreviouslv oerformed.

CRS dispatches operator to shut 2SS321 sample valve.

PO reports 21 SG is isolated from all intact SGs.

PO controls AFW flow if required to maintain 21 SG NR level >9%.

PO reports when 21MS10 opens for pressure control av 1045 osia.

PO reoorts 21 SG oressure is >375 osi CRS determines target temperature from Table D. (503°F for ruptured SG pressure

~1000 osia.

PO reports intact SGs are available for cooldown.

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TQ-AA-106-0204 Page 21of32 "r :At';E'181uator1tnstrucJq( Activity;{...

of/Student Response ***

{- ???-;

c~nnment * ~'. **

-:-1 F~rn: :':", >, ;; *c~ ,* -),:; ~; -, ;l9fi:,'":~,'.' *' , J 1:~'., t -,~dat~_.:._...:.=..--'-"-"--=-~

'ij~~:r c'.Y

PO reports steam dumps are available, and places in MS Pressure Control-Manual at 25%

to perform cooldown.

PO bypasses Tavg when Tavg Low-Low is reached.

Crew monitors hottest CET temperature while continuina in procedure.

Note: When hottest CET is <503°F, crew will stop cooldown with steps on next page.

RO reports power is available to both PZR PORV Stop valves, both PZR PORVs are shut, and both PZR PORV Stop valves are ooen.

RO resets SI and Phase A isolation, and reoorts Phase B isolation reset.

RO ooens 21 and 22CA330.

PO resets each SEC and reports 230V control centers are reset.

RO reports RHR suction is aligned to the RWST and no RHR oumo discharae flow.

RO stoos both RHR s.

PO reports 21 SG is ruptured and 21MS167 is shut.

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TQ-AA-106-0204 Page 22 of 32 c<>mmr'nt"' . . ?qlf ~*

', *lloG*z

'. cf+rJ?+ ,,,,

RO shuts charging pump mini flows when RCS ressure is < 1500 si .

RO reports when hottest CET is less than RCS cooldown tar et tern .

CT#2 (CT-19) Establish and maintain an RCS temperature so that transition from SGTR-1 does**

not qccur because temperature is too high to maintain minimum suocooling,. or: so lowJt causes transition to FRTS or FRSM. *

SAT UNSAT PO re orts 21 SG ressure is stable or risin RO re RO re orts normal PZR s ra is available.

RO full o ens both PZR S ra Valves.

RO reports PZR Spray is reducing RCS ressure.

Crew continues de ressurization.

7. 23 RCP trip PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 23 of 32

'*i TEipectea'Pla'nt/S$dent Resji'onsef , '!; SBtW' ,1J~Pl>>1if;Qenl" '?]*,~ .

(\~<,_,L, cT ;~:;~_,// *;;>'/, ,.;, ,v';f/i[~"; ' ' 1 ~~:i~< '. ,/ LOG, Simulator Operator: Insert RT-7 on.directionJrom Lead Evaluator once.RO reports spray effectiveness.

MALF: 23 RCP tri RO reoorts 23 RCP tri~.

Note: The crew is in a "do loop" when reducing RCS pressure using spray, and will return to Step 19.2 RO reports with loss of 23 RCP, spray is no lonaer effectivelv reducina RCS pressure.

Simulator Operator: IF crew continues to use spray flow to lower RCS pressure, .THEN insert RT*9 on direction from Lead Evaluator to trio 21 RCP.

RO shuts both PZR Sorav valves.

RO reoorts both PZR PORVs are available.

Crew reviews depressurization criteria.

IF 2PR1 is selected as the PORV to deoressurize, RO reports 2PR1 will not open.

RO opens 2PR2.

Simulator Ooerator: Insert RT-13 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 24 of 32

'E.valuaterir * * ' * ¥\' 1" { ' ' * ,,' ' ' \" <l"

+~4 E:xpe~ted ,Plant/Student,Re$ponse" j / , 111~

> Yj",Y""-~'~ ' ,1§""~ 'v/ '."""~"t'<t' 11 ;!SBT:, *

,-;C*'""

tYci1;iJ:2f11C~m~'~t;i)-1 , ,. ,

-~,,~J:,f~}~\(ic'*,*,);i$~).~ :* '.% t.f14 I'"'! ;;.J ;Pf'.*11 ,;,. " * . * . *1c,(1P'1 . LOG;'

as soon as 2PR2 is open.

MALF:. 2PR2.fails to 100%.

RO reoorts when condition in Table E is met.

8. PZR PORV fails to shut RO reoorts 2PR2 will not shut.

CRS directs closure of 2PR7 PZR PORV Block Valve.

Simulator Operator: Ensure ~

is TRUE when 2PR7 shut PB is depressed. This fails 2PR7 90%

ooen.

RO reports that after initiating closed on 2PR7, the open limit extinguished but the closed limit has not illuminated.

CRS transitions to EOP-SGTR-3, SGTR with LOCA- Subcooled Recoverv.

Terminate the scenario when the transition to SGTR-3 is announced.

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TQ-AA-106-0204 Page 25 of 32 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-10.ZZ-0004, Power Operation F. S2.0P-SO.DG-0003, 2C Diesel Generator Operation G. S2.0P-ST.500-0001, Electrical Power Systems AC Sources Alignment H. S2.0P-AB.SG-0001, Steam Generator Tube Leak I. S2.0P-AB.LOAD-0001, Rapid Load Reduction J. 2-EOP-TRIP-1, Reactor Trip or Safety Injection K. 2-EOP-SGTR-1, Steam Generator Tube Rupture PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 26 of 32 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 89.4% RCS BORON: 1114 MWe 1080 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED):

NA REACTIVITY PARAMETERS Control Bank D is at 193 steps.

Xenon is building in at 25 pcm I hr following downpower last shift MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

S2.0P-PT.TRB-0003, Main Turbine Valve testing is being briefed by a dedicated test team to be performed in one hour.

ABNORMAL PLANT CONFIGURATIONS:

2C EOG Jacket Water heater is failed and CIT.

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

SECONDARY:

Condensate Polisher is in service RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

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TQ-AA-106-0204 Page 27 of 32 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked "Training Use Only" and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

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TQ-AA-106-0204 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 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 Page 29 of 32 SCENARIO IDENTIFIER: 15-01 ILOT NRC ESG-2 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario.

CR 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.

CR 3. The scenario consists mostly of related events.

CR 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 CR 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.

CR 6. The events are valid with regard to physics and thermodynamics.

CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

CR 8. The simulator modeling is not altered.

CR 9. All crew competencies can be evaluated.

CR 10. The scenario has been validated.

CR 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.

CR 12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

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TQ-AA-106-0204 Page 30 of 32 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section D.5.d)

GG 2 Malfunctions after EOP entry: 1-2 GG 3 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 1 EOPs entered/requiring substantive actions: 1-2 GG 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS:

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TQ-AA-106-0204 Page 31of32 15-01 ILOT NRC ESG-2 CT#1 (CT-18) Isolate feed flow into and steam flow from 21 SG prior to a transition to SGTR-3 being required.

Basis: Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. The fact that the crew allows the differential pressure to dissipate and, as a result, are then forced to transition to a contingency ERG constitutes an incorrect performance that "necessitates the crew taking compensating action that would complicate the event mitigation strategy .... "

CT #2: {CT-19) Establish and maintain an RCS temperature so that transition from SGTR does not occur because temperature is too high to maintain minimum subcooling, or so low it causes transition to FRTS or FRSM.

Basis: Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency ERG. This failure constitutes an incorrect performance that "necessitates the crew taking compensating action that would complicate the event mitigation strategy .... "

Note to Evaluator: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 32 of 32 ATTACHMENT6 - -

ESG~PRA REl..ATIONSHIP E~AlUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water y Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR Tc:>~lll.I N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area Y Any Diesel Generator N RHR Suction Line valves from Hot Leg Y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST Y Cooldown the RCS and depressurize the system Y Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.

TQ-AA-106-0204 Page 1of29 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: 15-01 NRC ESG-3 SCENARIO NUMBER: 15-01 NRC ESG-3 EFFECTIVE DATE: See Approval Dates EXPECTED DURATION: 60 minutes REVISION NUMBER: 00 PROGRAM: ~-~' LO. REQUAL X ! INITIAL LICENSE

~~!STA

~-~'OTHER Revision Summary New issue for 15-01 ILOT NRC exam PREPARED BY: G Gauding 8-11-16 Lead Regulatory Exam Author Date APPROVED BY: ~V\ (o/,/c,

'oate APPROVED BY:

~ JdllkUlj aciiifyResentative 1ofit!afc, ate PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 2 of 29

TQ-AA-106-0204 Page 3 of 29 A. 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 S1/S2.0P-S2.0P-AB.PZR-0001.

B. Given indication of a pressurizer control system malfunction, DIRECT the response to the malfunction in accordance with S2.0P-AB.PZR-0001.

C. Given indication of a dropped control rod perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with S2.0P-AB.ROD-0002.

D. Given indication of a dropped control rod DIRECT the response to the malfunction in accordance with S2.0P-AB.ROD-0002.

E. Given the order or indications of a loss of secondary coolant, perform actions as the nuclear control operator to RESPOND to the coolant loss in accordance with EOP-LOSC-1.

F. Given indication of a loss of secondary coolant, DIRECT the response to the loss of secondary coolant, in accordance with EOP-LOSC-1.

G. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with 2-EOP-TRIP-1.

H. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with 2-EOP-TRIP-1.

I. Given the order or indications of a safety injection, perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

J. Given indication of a safety injection, DIRECT the response to the safety injection in accordance with the approved station procedures.

K. Given the order or indications of a multiple steam generator depressurization, perform actions as the nuclear control operator to RESPOND to the generator depressurization in accordance with EOP-LOSC-2.

L. Given indication of a multiple steam generator depressurization, DIRECT the response to the generator depressurization in accordance with EOP-LOSC-2.

A. Power Ascension B. Controlling PZR Pressure Instrument fails high C. Dropped control rod D. Steam Leak/Rupture in containment PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 4 of 29 A. The crew will take the watch with the unit stable at 1x1 o-s Amps during a plant startup, BOL.

21 SGFP is in service and 22 SGFP is O/S. Steam dumps are in MS Pressure Control - Auto

@ 1,000 psig. 25 CFCU is CIT for maintenance. 23 charging pump is CIT for emergent maintenance. The crew will be instructed to raise power to 2%.

B. The crew will initiate a power ascension to 2% using Main Steam Dumps and control rods.

C. After the power ascension is started the controlling PZR Pressure instrument will fail high, deenergizing PZR heaters and causing both PZR Spray valves to open fully. The crew will respond IAW S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction to establish manual control of PZR pressure control and restore pressure to normal, swap to an operable channel, and remove the failed channel from service. The CRS will identify applicable LCO's.

D. After the Pressurizer Pressure control system failure has been addressed, a control rod will drop fully into the core. The crew will respond IAW S2.0P-AB.ROD-0002, Dropped Rod. The crew will identify the Rx is subcritical, and initiate control rod insertion to fully insert all Control and Shutdown rods. The CRS will identify applicable LCO's.

E. During the rod insertion, a steam leak in containment will occur on 21 SG. The crew will diagnose changing containment conditions, and determine a Rx trip is required and MSLI will be required in an attempt to isolate the steam leak.

F. The crew will trip the Rx. The steamline will rupture. MSLI (auto and manual) will fail to shut any MSIV. The crew will initiate Safety Injection when it is identified that the source of the steam leak is not isolated.

G. The crew will perform plant stabilization actions in EOP-TRIP-1, Reactor Trip or Safety Injection. With all SGs faulted, the crew will maintain AFW flow to each SG. 21 AFW pump will trip during TRIP-1 performance. Containment Spray pumps will not automatically start when demanded on hi-hi containment pressure, and the crew will manually start at least one CS pump (CT-1 ). The crew will transition to EOP-LOSC-1, Loss of Secondary Coolant.

H. The crew will transition to EOP-LOSC-2, Multiple Steam Generator Depressurization with all SG's faulted.

I. The crew will identify the RCS cooldown rate of >100°F I hr, and control AFW flow to minimize RCS cooldown (CT-2). The crew will reset Safeguards. When evaluating SI Flow Reduction Criteria, local operators will successfully shut a MSIV. The crew will recognize rising pressure in that SG, and transition to LOSC-1.

J. The scenario will be terminated upon transition to LOSC-1.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 5 of 29 IC-233 PREP FOR' TRAINH~G (i.e. ,,computer setpoints, procedures, bezel e~vers

,tagged eqt1ipment)

Initial I Description 1 VC1 and VC4 CIT 2 RCPs (SELF CHECK)

_ 3 RTBs (SELF CHECK)

_ 4 MS167s (SELF CHECK)

_ 5 500 KV SWYD (SELF CHECK)

_ 6 SGFP Trip (SELF CHECK)

_ 7 23 CV PP (SELF CHECK)

__ 8 21 Charging pump in service 9 25 CFCU CIT

_ 10 23 Charging pump CIT 11 IOP-3 open and complete up to Section 4.3, Power Operation.

12 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 6 of 29 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group Description EVENT ACTION: MONP254 <10 II CONT ROD BANK C < 10 ( RX TRIP )

1 COMMAND:

PURPOSE: <update as needed>

SELF- Description Delay Initial Ramp Trigger Severity CHECK Time Value Time 01 PR0016A PZR PRESS CH I PT455 FAILS H/L N/A N/A N/A RT-1 2500 02 RD0267 ANY ROD S INADVERTENTLY DROPS NIA N/A N/A RT-3 3 MS0090Ar 21 Main Steam Line Leak Inside Cont 03 N/A N/A N/A RT-5 2 AFTER orifice 04 RP0279A AUTO MSLIS FAILS TO ACT, TRNA NIA NIA NIA NIA 05 RP0279B AUTO MSLIS FAILS TO ACT, TRN B N/A N/A NIA NIA 06 MS0092E 21MS167 FAILS OPEN N/A NIA NIA NIA 07 MS0092F 22MS167 FAILS OPEN Ni A NIA N/A N/A 08 MS0092G 23MS167 FAILS OPEN NiA NIA NIA N/A 09 MS0092H 24MS167 FAILS OPEN N/A NIA N/A NIA 10 RP0274A AUTO SI FAILS TO ACT, TRNA NIA N/A N/A N/A 11 RP0274B AUTO SI FAILS TO ACT, TRN B NIA NIA N/A NiA 12 AF0181A 21 AUX FEEDWATER PUMP TRIP 00:05:00 N/A NIA ET-1 13 RP318L 1 21 CS Pum Fails to Start on SEC NIA N/A NIA NIA 14 RP318L2 22 CS Pum Fails to Start on SEC NIA NIA NIA NIA SELF- Description Delay Initial Ramp Trigger Condition CHECK Time Value Time 01 CV52D 23 CHG PUMP BKR CONTROL POWER N/A N/A N/A NIA OFF 02 PR34D PORV STOP VALVE 2PR6 TAGGED N/A NIA N/A RT-7 TAGGED 03 SP01A1 Prevailing Wind Speed NIA N/A N/A N/A 10 04 SP01A2 Prevailin Wind Direction N/A N/A NIA NIA 160 05 CT195-1D 25 CFCU BKR #1 Hi h S eed 125VDC N/A N/A NIA NIA OFF 06 CT195-2D 25 CFCU BKR #2 Hi h Speed 125VDC N/A NIA NIA NIA OFF PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 7 of 29 07 I CT195-3D 25 CFCU BKR #3 Low Speed 125VDC NIA N/A N/A N/A I ___OFF_]

SELF- Description Delay Initial Ramp Trigger Condition/

CHECK Time Value Time Severity 01 Cl11 CLO QCl11HR2 TURNING GEAR-ENGAGED N/A N/A N/A NIA ON 02 Cl11 E LO QCl11PR2 TURNING GEAR-STARTED N/A NIA N/A NIA ON 03 Cl11 FLO QCl11TG2 TURNING GEAR-STOPPED N/A NIA N/A NIA OFF 04 Cl11 D LO QCl11LG2 TURNING GEAR-DISENGAGED NIA ~~!A NIA WA OFF

1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 8 of 29 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 29 Eva'1aitodln$fructQr~ActivitY' , 'Ex'Pected 1?lan,t1stildi;tnt Response SBT' *.*'#'~

,wv' 0 vommen< '"t*".

~t //**1i~'~

,. 'w */'.; ;(f' ; ;"' *./ : 'we -*Y0J'o' .~il!i ~'Ir' l!OG, ,*

1. Power ascension CRS directs power ascension using Main Steam Dumps and control rods.

PO raises steam dump demand.

RO adjusts control rods to maintain Tave on program.

RO announces when POAH is observed.

Continue to next event on direction from Lead evaluator.

2. Controlling PZR pressure instrument fails HIGH SimulatQr Operato,r: Insert RT-1 on directiOn from Lead EvalUatOr:° MALF: MALF: PR0016A PZR Press CHI (PT-455) fails H/L Final Value: 2500

RO announces unexpected OHA alarms D-8 RC Press HI, and E-42 2PR1 Yz Trip.

RO determines actual pressure is not high and reports spray valves open, and recommends placinq Master Pressure Controller in manual.

CRS directs RO to place Master Pressure Controller in manual.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Pag.e 10 of 29 Evafuatoilinsfructor,~ctlvi~ Eii>ec\iae1antl~tua~.111*. Response **seT l

i'g~j /il q :i; .*~** .1t~** ,. ,)ii, . : ;*r/*' J*~ LOG/ .

RO takes manual control of Master Pressure controller, and lowers demand (increase pressure) to close sprays.

CRS enters S2.0P-AB.PZR-001, Pressurizer Pressure Malfunction.

CRS directs initiation of AB.PZR CAS.

CRS gives band for control of PZR pressure.

RO identifies PZR Press Channel I failed high.

RO selects Channel Ill for control.

RO matches master pressure controller demand to current pressure and returns Master Pressure Controller to AUTO.

RO shuts 2PR6.

Note: The requirement to shut 2PR6 and deenergize it is within one hour of the PZR Pressure Channel I instrument failure IAW Tech Specs.

CRS directs WCC to remove power from 2PR6.

Simulator Operator: Insert RT-7 2 minutes after being directed to remove power from 2PR6.

REMOTE: PR340 PORV Stop PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 11of29

1~pwev:a1uatc>rnat1tructor Aottiify 'Tuexpected)>fiint/~tudenf Response ;;iffS'BT iiii'!ivr*** *~!:'aorri'ment ,}}}}Tu.~ **

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Valve 2PR6 taaaed CRS directs PO to initiate removing failed channel from service and contact l&C for support IAW S2.0P-SO.RPS-003. PO checks that tripping associated bistables will not result in an ESF or RPS actuation. Note: Crew may wait for l&C response before performing any actions in S2. OP-SO. RPS-0003. PO verifies that Channel Ill is selected for Master Pressure Control. PO selects PZR Pressure recorder to channel other than I. CRS enters TSAS 3.3.1.1 Action 6, 3.3.2.1.b Action 19*, 3.4.5.b, and 3.2.5. Proceed to next event on direction from Lead Evaluator.

3. Dropped control rod Simulator Operator: Insert RT-3 1: oh direction from Lead Evaluator.

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MALF: .RD0064.ANY.ROD INADVERTENTLY DROPS Severitv: 3 RO reports unexpected OHA E-48 ROD PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 12 of 29

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BOTTOM, and reports Shutdown Bank rod 1SA3 rod bottom liaht is illuminated. CRS enters S2.0P-AB.ROD-0002, Dropped Rod. RO reoorts control rods are in manual. PO reoorts Main Turbine is S/D. RO reports the reactor is subcritical as a result of the droooed rod. CRS directs RO to insert all control and shutdown bank rods. RO initiates insertion of control rods in manual. Simulator Operator: Once rod insertion has commenced, insert RT-5 on direction from Lead Evaluator' MALF: MS0090Ar . Severitv: 2

4. 21 SG steam leak I rupture in containment PO announces OHA C-38, CFCU LK DET HI as unexpected, and shortly after, OHA C-30, CFCU LK DET HI-HI as well.

PO refers to ARP for OHA C-38 and C-30. PO reoorts indications of a steam leak inside PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 13 of 29 Evaluator/Instructor Activity Expected Plant/Student Response SBT Comment LOG containment including:

                                             - Containment pressure rising
                                             - Tavg slowly lowering
                                             - Rising steam flows on all loops
                                             - Steam dump demand lowerinq CRS enters S2.0P-AB.STM-0001, Excessive Steam Flow.

CRS directs monitorinq of AB.STM CAS. CRS notifies Emergency Services of the steam leak. PO reports that the Main Turbine is not latched. PO reports no indication of MS10 or steam dump valves malfunction. RO reports no indication of a SG Safety Valve partially open or leakinq. RO reports Rx power and RCS temperature are NOT stable. CRS directs the RO to trip the Rx. Note: A MSLI will be required to attempt to isolate the steam leak in containment. The CRS can use the CAS of AB.STM for direction, or will use Step 11 in TRIP-1 when containment pressure exceeds 15 psig. Auto and Manual MSLI are PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 14 of 29

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Simulator Operator: After the Rx is tripped, then MODIFY MALF MS0090Ar to 100 with a 5 minute ramo. RO trios the Rx and confirms the Rx tri~ . .Simulator .op.erafo6'Ellsure ET~f is true upon the Rxtrip.' Thistrips 21 AFW.pump after a 5 minute delav.

5. All MSIVs fail to shut IF using AB.STM CAS, then RO will attempt a MSLI, and reoorts it did not actuate.

IF using AB.STM CAS, RO reports the steam leak is NOT isolated. RO continues Immediate Actions of TRIP-1: Reports the Main Turbine is tripped. Reports all 4KV vital buses are energized. Reports a demand for Safety Injection is present and Safety Injection has NOT actuated (or reports Safety injection was manuallv initiated as described in PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 15 of 29 .J,;><.~:eva1uator1fr:l$t

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RO initiates Safety Injection (if not previously performed.) Note: With all SGs faulted, AFW flow should not be isolated to any SG. PO reports SEC loading is not complete. PO reports all available equipment started. PO reports 21 and 22 AFW pumps are running, and if not previously performed, receives permission to throttle total AFW flow to no less than 22E4 lbm/hr. PO reports valve groups in Table B are in Safequards position. RO reports 21 and 22CA330 are shut.

6. 21 AFW pump trip PO reports when 21 AFW pump trips, and adjusts AFW flow if required.

7. Containment Spray pumps fail to start RO reports containment pressure has not remained less than 15 psig.

RO initiates Phase B and Spray actuation. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 16 of 29

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RO reports neither Containment Spray pump has started.

RO blocks 2A and 2C SECs. PO resets 2A and 2C SEC's. RO starts 21 and 22 CS pumps. CT#.1 (CT-3) Manually start at least one Containment Spray . pump before a red path

challenge develops c>n'thEt containment CSF. '

SAT UNSAT RO reports MSLI has failed to close any MSIV. RO stops all RCPs. RO reports MSLI has failed to close any MSIV. CRS dispatches operators to place valves from Table D {locally close MSIVs) in safeguards position if not previously performed. PO reports all 4KV vital buses are energized. RO reports control room ventilation is in Accident Pressurized mode. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 17 of 29

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i .. RO reports 2 switchgear supply and 1 exhaust fan are runninq. RO reports 2 CCW pumps runninq. RO reports ECCS flow as expected for current RCS pressure. PO maintains total AFW flow greater than 22E4 lbm/hr until at least one SG NR level is

                    >15% (adverse), then maintains SG NR level 19-33%.

RO reports no RCPs are runninq. RO reports RCS Tcolds are droppinq. PO reports no dumpinq steam. RO reports MSLI failed to isolate anv MSIV. RO reports both RTBs are open. RO reports both PZR PORVs are closed. RO reports 2PR6 is shut, and 2PR7 is open. CRS dispatches operator to restore power to 2PR6 if deenerqized. RO reports no RCPs are running. RO maintains seal injection flow to all RCPs. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 18 of 29

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d ~* PO reports all SG pressures are dropping in an uncontrolled manner or completely depressurized with MSLI failure. CRS transitions to EOP-LOSC-1, Loss of Secondary Coolant. Note: CFSTs are in effect when transition out of TRIP-1 occurs. STA will report to control room 10 minutes after being summoned via page to monitor CFSTs. RO reports MSLI failed to shut any MSIV, all MS? and MS18 valves are shut, and action has been directed to locally shut MSIVs. PO reports all SG pressures are dropping in an uncontrolled manner. CRS transitions to EOP-LOSC-2, Multiple Steam Generator Depressurization. PO reports all valves in table A are shut except for all MSIVs. CRS dispatches operators, if not previously performed, to locally shut valves in Table A one loop at a time. CRS determines 23 AFW pump in service, and either stops 23 AFW pump or leaves it in service. Note: 23 AFW pump may be left in PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 19 of 29 EvalMe1f8r~1,nitructo~Ac** * ,, E"pe,c:;ted PlanfiStuCleQtResp'onse , ,p;;'?:SBT1;.iiir' co.mment 4.i;;

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service if it is determined it is necessary to maintain minimum AFW flow to keep SG tubes wet. IF required, PO lowers 23 AFW pump speed to minimum, trips then stops 23 AFW pump. IF required, CRS dispatches operator to shut 21 and 23MS45 steam supplies to 23 AFW pump. RO reports RCS cooldown rate is >100°F I hr. PO reduces AFW flow to each SG to no less than 1.0E4 lbm I hr. CT#2 (CT.;33) Control the AFW rate to notless'than 1E4 lbm/hr to minimize the cooldownrate. SAT UNSAT When STA reports RED path on Heat Sink, CRS transitions to FRHS-1, verifies operator action was cause of RED path, and returns to procedure in effect. RO reports RCS Thots are dropping. RO reports RCS pressure, and reports a cooldown is in progress or RCPs are secured. RO reports both PZR PORVs are closed. RO reports 2PR6 is shut, and 2PR7 is open. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 20 of 29

        , EvaluatorUnstructor Aalvi~}t                                                    E;xpecteCl.:.PJanllSfUdenf Re,sponse     SBT                    '?rii%;:,~3;f:~+t/:, . .

, ;'.;,l~Jti ) 1,' /,;t(~J:},~ (~;~; / 'i!~{'~'""" ;;{ :~<thl~'~ ' "";';'"",~}>~t"' RO resets SI, Phase A, and Phase B. RO opens 21 and 22CA330. PO reports all SECs are reset. PO reports all 230V Control Centers reset. RO resets SGBD Sample Isolation Bypass, and opens 21-24SS94s. CRS directs Chemistry to sample SGs for activity and boron. PO reports no indication of any SGTR. RO reports RHR pumps running with suction from RWST, and no discharqe flow. RO reports RCS pressure is stable or rising, and stops both RHR pumps .. RO reports both CS pumps are runninq. RO reports containment pressure. If/when containment pressure is <13 psig, then RO:

Resets Spray actuation
Stops both CS pumps
Shuts 21 and 22CS2 CS pump discharge valves PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 21of29 ,1;1ir"evii'uatorlinstrllctoFActi~itY'::;* ** ffEx.lfe'l:t ianffstuUenf"'ResP'Qose SSTi7i!l corii'riient'1i1ft** v~~r:: [; ; J' 3' , ,,01": *.~:rz 1:tz LO(J" :: *~ ',;-\' RO reports RWST lo level alarm has not actuated. RO reports RCS Thats status. IF <375, PO removes lockouts for 21-24SJ54's, and RO shuts 21-24SJ54's. RO reports subcoolinQ is >0°F. RO reports RCS pressure and trend. RO reports RCS pressure is stable or rising and:

Realigns charging pump through normal charging line and adjusts 2CV55 to maintain PZR level >33%.
Reports PZR level trend .

Simulator Operator: When Step 20 is complete then shut 23MS167 by deleting MAL.F MS0092G and . ensurino 23MS167 shuts. PO reports indication of 23MS 167 being shut. CRS determines pressure rise in 23 SG requires transition to LOSC-1. CRS transitions to LOSC-1. Terminate the scenario when the transition to LOSC-1 is announced. PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 22 of 29 A. Alarm Response Procedures (Various) B. Technical Specifications C. Emergency Plan (ECG) D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load F. S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction G. S2.0P-AB.ROD-0002, Dropped Rod H. S2.0P-AB.STM-0001, Excessive Steam Flow I. 2-EOP-TRIP-1, Reactor Trip or Safety Injection J. 2-EOP-LOSC-1 Loss of Secondary Coolant K. 2-EOP-LOSC-2 Multiple Steam Generator Depressurization PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 23 of 29 ATTACHMENT 1 UNIT TWO PLANT STATUS TODAY MODE: 1 POWER: 1x10-8 A RCS BORON: 1711 MWe 0 SHUTDOWN SAFETY SYSTEM STATUS (5, 6 & DEFUELED): NA REACTIVITY PARAMETERS Control Bank D at 130 steps withdrawn. Core burnup 500 EFPH. MOST LIMITING LCO AND DATE/TIME OF EXPIRATION: 3.6.2.3 for 25 CFCU action a expires in 165 hours. EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS: S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load complete up to Section 4.3, Power Operation. ABNORMAL PLANT CONFIGURATIONS: CONTROL ROOM: Unit 1 and Hope Creek at 100% power. PRIMARY: 21 Charging pump in service 23 Charging pump CIT for emergent repair, expected return in 2 hours 25 CFCU CIT for breaker replacement SECONDARY: 21 SGFP in service 22 SGFP O/S with steam supply valves shut RADWASTE: No discharges in progress CIRCULATING WATER/SERVICE WATER: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 24 of 29 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

26. Verify EGC paperwork is marked "Training Use Only" and is current revision.

27. Ensure sufficient copies of ECG paperwork are available.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 25 of 29 ATTACHMENT3 CRITICAL TASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant. The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an 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 26 of 29 SCENARIO IDENTIFIER: 15-01 NRC ESG-3 REVIEWER: C Recchione Initials Qualitative Attributes CR 1. The scenario has clearly stated objectives in the scenario. CR 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. CR 3. The scenario consists mostly of related events. CR 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 CR 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.

CR 6. The events are valid with regard to physics and thermodynamics. CR 7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives. CR 8. The simulator modeling is not altered. CR 9. All crew competencies can be evaluated. CR 10. The scenario has been validated. CR 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. CR 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 Page 27 of 29 Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section 0.5.d) GG 2 Malfunctions after EOP entry: 1-2 GG 3 Abnormal Events: 2-4 GG 1 Major Transients: 1-2 GG 2 EOPs entered/requiring substantive actions: 1-2 GG 0 EOP contingencies requiring substantive actions: 0-2 GG 2 EOP based Critical tasks: 2-3 COMMENTS: PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 28 of 29 15-01 NRC ESG-3 CT#1 (CT-3) Manually actuate at least one Containment Spray pump before an extreme challenge develops to the containment CSF. Basis: Failure to manually actuate the minimum required complement of containment cooling equipment under the postulated conditions demonstrates the inability of the crew to "recognize a failure or an incorrect automatic actuation of an ESF system or component." CT#2 (CT-33) Control the AFW rate to not less than 1E4 lbm/hr to minimize the cooldown rate. Basis: Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the critical task increases the challenges to the subcriticality and the containment CSFs beyond those irreparably introduced by the postulated plant conditions. Thus, failure to perform the critical task constitutes a demonstrated inability by the crew to "take one or more actions that would prevent a challenge to plant safety." It also fails to prevent "a significant reduction of safety margin beyond that irreparably introduced by the scenario." Note to Evaluator: CT numbers in parentheses are the corresponding Westinghouse ERG Rev. 2- based Critical Tasks procedure WCAP-17711-NP PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 29 of 29 ATTACHMENT 6 ESG.;PRA RELATIONSHIP EVALUATION EVENTS LEADING TO CORE DAMAGE Y/N Event Y/N Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N COMPONENT, SYSTEM, OR TRAIN Y/N COMPONENT, SYSTEM, OR TD~ll\I N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s) N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.}}

ML17031A347

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ML17031A347

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