ML13267A422

Final Operating Exam (Sections a, B, and C) (Folder 3)

ML13267A422
Person / Time
Site:	Hope Creek
Issue date:	08/19/2013
From:	Todd Fish Operations Branch I
To:	Public Service Enterprise Group
Jackson D
Shared Package
ML13077A118	List: IR 05000354/2013301 ML13108A195 ML13227A102 ML13227A107 ML13227A117 ML13227A127 ML13227A207 ML13267A380 ML13267A389 ML13267A415 ML13267A422 ML14010A064 ML14070A491 ML14070A492
References
TAC U01872
Download: ML13267A422 (389)

Text

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves TASK NUMBER: 2991660301 JPM NUMBER: 2013 NRC RO A-1 REV #: 02 SAP BET: NOH05JPZZ01E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6/10/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: RO A-1 REV: 02 SYSTEM: Radiation Control TASK NUMBER: 2991660301 TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves ALTERNATE PATH: K/A NUMBER: 2.3.11 IMPORTANCE FACTOR: 3.8 4.3 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

OP-HC-103-105 Rev 1 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 14

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves TASK NUMBER: 2991660301 INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0836 today Operational Condition 4 was entered.

5. At 1142 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

6. Todays CRS is A. West.

INITIATING CUE:

COMPLETE todays Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-103-105. The SM/CRS will perform step 4.4.6.

Page 3 of 14

TQ-AA-106-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue AND a copy of OP-HC-103-105 Operator repeats back initiating cue.

WITH the attached paperwork.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.4.

4.4 Calculating Valve Open Time N/A 4.4.1 In Section C of Form 2, ENTER the time the valve(s) listed in Section 2.2 or the line(s) listed in Section 2.4 or 2.5 are opened in Condition 1, 2, or 3 N/A (Filled in by previous Operator) or when Condition 2 OR 3 is entered from Condition 4 with the valve(s)/line(s) open.

4.4.2 In Section C of Form 2, ENTER the

• time the valve(s) listed in Section 2.2 Operator enters 0836 in section C of or the line(s) listed in Section 2.4 or Form 2 in the Time at which valve/line 2.5 are closed in Condition 1, 2, or 3 was closed or Condition 4 or 5 was or when Condition 4 is entered from entered with valve/line opened space.

Condition 2 or 3 with the valve(s)/line(s) open. [T/S 1.34]

Page 4 of 14

TQ-AA-106-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 4.4.3 COMPUTE the total hours (round up Operator calculates the open cycle as to the nearest 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or to the 7.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (6.6 rounded up to 7.0) and nearest 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />) for each open cycle. enters in Section C Total number of hours valve/line opened this cycle space.

4.4.4 When the valve permit is no longer

• valid due to either the evolution is complete, Operator totals the hours that the or mode change to Condition 4 has valve(s)/line(s) were open. (7.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) occurred, and enters in Section C Total number or the day has ended of hours valves/line open this permit TOTAL the hours that the space.

valve(s)/line(s) were open (should be less than the time authorized in Section B of Form 2). [T/S 1.52]

4.4.5 The NCO performing the section C Operator signs the NCO performing calculations should sign in the calculations space and enters appropriate space and enter the time Date/Time in Section C.

and date.

4.4.6 The SM/CRS should verify the calculations, sign in the appropriate Operator hands the paperwork to the space for verification and close out CRS.

and enter the time and date.

CUE SIGN and DATE the appropriate N/A spaces and RETURN to the operator.

Page 5 of 14

TQ-AA-106-0303 JPM: 2013 NRC RO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 4.4.7 On Form 1, ENTER the name of the SM/CRS closing out the valve permit On Form 1, the operator enters the and the number of hours the valves name of the SM/CRS closing out the were open on this permit. The NCO valve permit.

entering this information should initial On Form 1, the operator enters the in the appropriate space. number of hours the valves were open.

(7.0 hrs THIS PERMIT/ 42.5 TOTAL)

On Form 1, the operator initials entry.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Task Standard: Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log, OP-HC-103-105, completed in accordance with attached key Page 6 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-1 TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves TASK NUMBER: 2991660301 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 14

OP-HC-103-105 Revision 1 Page 8 of 9 FORM 1 Page_____of_____

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1) 3/3/13 22.5 24 H. Davidson SD 5.5 28.0 A. West SD 6/25/13 18.5 24 G. Washington TRW 3.5 22.0 G. Clooney TRW 8/1/13 22.0 24 O.W. Holmes R 24.00 46.0 V. Price R 8/12/13 46.0 24 B. Lee E 2.5 48.5 V. Bono E Today 35.5 24 A. Jones JS 7.0 42.5 SM/CRS Name INIT Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Hope Creek Rev. 5

OP-HC-103-105 Revision 2 Page 9 of 9 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 020020001 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) (-) 35.5 DATE NUMBER OF HOURS Hours available this date (=) 416.5 3/3/13 5.5 (line 1 minus line 2)

Hours authorized this date 24 6/25/13 3.5 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or Line (3), whichever is less 8/1/13 24.0 8/12/13 2.5 NCO performing calculation Date/Time John Smith Today/0100 SM/CRS verification and authorization Date/Time Andrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 0836 7.0 Total number of hours valves/line open this permit:

NCO performing calculations Operator Signature Date/Time Date/Time SM/CRS Closing permit Examiner Signature Date/Time Date/Time Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

Hope Creek

OP-HC-103-105 Revision 2 Page 9 of 9 REVISION HISTORY JPM NUMBER: 2013 NRC RO A-1 Rev # Date Description Validation Required?

2 7/1/13 Revised IAW current revision of OP-HC-103-105. Removed N critical step (4.4.3). Added SM/CRS will perform step 4.4.6 to the cue sheet.

Hope Creek

OP-HC-103-105 Revision 2 Page 9 of 9 VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-1 REV#: 2 TASK: Monitor, Log and Control the Drywell and Suppression Chamber Purge System Valves Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On file 6-25-13 Name Qual Signature Date Jim Southerton On File 6-10-13 Name Qual Signature Date Hope Creek

OP-HC-103-105 Revision 1 Page 8 of 9 FORM 1 Page_____of_____

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1) 3/3/13 22.5 24 H. Davidson SD 5.5 28.0 A. West SD 6/25/13 18.5 24 G. Washington TRW 3.5 22.0 G. Clooney TRW 8/1/13 22.0 24 O.W. Holmes R 24.00 46.0 V. Price R 8/12/13 46.0 24 B. Lee E 2.5 48.5 V. Bono E Today 35.5 24 A. Jones JS Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Hope Creek Rev. 5

OP-HC-103-105 Revision 1 Page 9 of 9 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 020020001 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs (2) Total previous year (NOTE 1) (-) 35.5 DATE NUMBER OF HOURS Hours available this date (=) 24 3/3/13 5.5 (line 1 minus line 2)

Hours authorized this date 24 6/25/13 3.5 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or Line (3), whichever is less 8/1/13 24.0 8/12/13 2.5 NCO performing calculation Date/Time John Smith Today/0100 SM/CRS verification and authorization Date/Time Andrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Time at which valve/line was closed or Total number of hours valve/line Condition 1, 2, or 3 was entered with valve/line Condition 4 or 5 was entered with valve/line opened this cycle open opened (NOTE 3) 0200 Total number of hours valves/line open this permit:

NCO performing calculations Date/Time SM/CRS Closing permit Date/Time Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0836 today Operational Condition 4 was entered.

5. At 1142 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

6. Todays CRS is A. West INITIATING CUE:

COMPLETE todays Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log in accordance with OP-HC-103-105. The SM/CRS will perform step 4.4.6.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 JPM NUMBER: 2013 NRC RO A-2 REV #: 2 SAP BET: NOH05JPZZ11E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO DEVELOPED BY: NRC DATE: 6-1-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC RO A-2 REV: 2 SYSTEM: Reactor Recirculation TASK NUMBER: 2020160101 TASK: Perform a Reactor Recirculation Pump Quick Restart ALTERNATE PATH: K/A NUMBER: 2.2.40 IMPORTANCE FACTOR: 3.4 4.7 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.RPV-0003 Rev 23 TOOLS, EQUIPMENT AND PROCEDURES:

Steam Tables/Calculator ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 17

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 INITIAL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped.

2. Evidence of thermal stratification is present.

3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11.

INITIATING CUE:

Complete HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump.

Page 3 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.RPV-0003.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be G.12.

G.12 ENSURE Differential Temperature Operator obtains HC.OP-AB.RPV-0003 requirements are met by completing Attachment 2.

Attachment 2. [T/S 4.4.1.4]

Page 4 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

HC.OP-AB-RPV-0003 Attachment 2 1.0 REACTOR VESSEL TO BOTTOM HEAD DRAIN LINE DIFFERENTIAL TEMPERATURE CRITERIA NA 1.1 Rx Pressure Vessel Steam Space Coolant Saturation Temperature. (Rx Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure 885 psig. (900 psia)

(Psia = 14.7 + Psig)

Operator determines Steam space

• Coolant Saturation Temperature to be 900 psia = 532 degF (Steam Tables/

AB.RPV-0003 Attachment 2) + 0.5F Operator records value in space provided on Attachment 1.

Page 5 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Note 1 Steam Table as part of this attachment may be utilized to determine temperature rounding the numbers in a conservative fashion.

For a more accurate conversion from NA pressure to temperature a more detailed set of steam tables should be utilized.

1.2 Bottom Head Drain Coolant Temperature. (Note 2) (Computer Point A2942) Operator accesses CRIDS terminal.

Note 2 RWCU Flow required for accurate Bottom Head Drain Coolant Temperature indication. Operator reads Note 2.

Operator determines RWCU is in service and the Bottom Head Drain Coolant Temperature is valid.

Operator obtains value of 491 degF *

(+ 0.5F) from CRIDS point A2942.

Page 6 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.3 < 145°F between Rx Pressure Vessel

• Steam Space Coolant AND Bottom Operator subtracts value of step 1.2 Head Drain Line Coolant (A - B). [T/S from value of step 1.1. and determines 4.4.1.4] value of 41 degF + 1F.

Operator records value in space provided.

1.4 Time Readings taken: ___________ Operator records current time in space provided.

2.0 REACTOR VESSEL TO RECIRCULATION LOOP DIFFERENTIAL TEMPERATURE NA CRITERIA.

Page 7 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 2.1 Temperature of the Rx Coolant within the idle loop to be started up.

Operator reads Note 3.

(Note 3)

Note 3 Use TR-650-B31 Recirc Pump Suction Loop A(B) (if available) OR if above 400° F - CRIDS points A221 and A222 for A loop (A223 and A224 for B loop). IF below 400°F AND TR-650-B31 not available, THEN have NA I&C obtain temperatures using RTD ohm values (reference RTD ohm values to calibration data in TDR using HC.OP-GP.ZZ-0008(Q))

Page 8 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator determines Idle Recirc Loop Temp for A Loop is above 400 F. (~517 degF) 2.2 Temperature of coolant in the Rx Pressure Vessel. (RX Pressure and Steam Tables) (Note 1) Operator reads Note 1.

Operator determines RPV pressure is

• 885 psig. (900 psia)

(Psia = 14.7 + Psig)

Operator determines Steam space Coolant Saturation Temperature to be:

900 psia = 532 degF (Steam Tables/

AB.RPV-0003 Attachment 2)

Operator records value in space provided on Attachment 1.

Page 9 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 2.3 < 50°F between the Rx Coolant within Operator determines differential temp is

• the loop not in operation AND the < 50 F.

Coolant in the Rx Pressure Vessel (A-B). [T/S 4.4.1.4] Examiner Note:

Actual value is 15 degF + 1F.

2.4 Time Readings taken: ____________ Operator records current time in space

• provided. (Pump must be started within 15mins of times in Steps 1.4 & 2.4)

HC.OP-AB-RPV-0003 ENSURE Differential Temperature G.12

• requirements are met by completing Operator initials step G.12.

Attachment 2. [T/S 4.4.1.4]

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 10 of 17

TQ-AA-106-0303 JPM: 2013 NRC RO A-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform a Reactor Recirculation Pump Quick Restart

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Task Standard: A Reactor Recirc restart requirements of HC.OP-AB.RPV-0003 Attachment 2 completed per the attached key Page 11 of 17

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-2 TASK: Perform a Reactor Recirculation Pump Quick Restart TASK NUMBER: 2020160101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 12 of 17

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL.

Trip both Reactor Recirc Pump Drive Motor Breakers.

Take appropriate Scram actions IAW HC.OP-AB.ZZ-0001.

IMPLEMENT EOP-101 to stabilize plant at 885 psig RPV pressure on DEHC.

IMPLEMENT HC.OP-AB.RPV-0003 up to and including step G.11.

Acknowledge alarms.

Put Simulator in FREEZE.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description MARKUP a copy of HC.OP-AB.RPV-0003 up to and including step G.11.

ENSURE Mode Switch key is removed.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code:

Description:

Event code:

Description:

Event code:

Description:

Page 13 of 17

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Insert 9M13_R_AO to value necessary Ensure HPCI Steam Inlet Pressure None None to ensure PI-3684A-1 (10C650B) indicates approximately 885 psig.

indicates approximately 885 psig.

Page 14 of 17

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC RO A-2 Rev # Date Description Validation Required?

2 7-1-13 Moved cue sheet to last page. Minor grammatical changes. Y Changed CRIDS data points to match simulator. Clarified critical tasks and calculation values. Revised simulator setup.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-2 REV#: 2 TASK: Perform a Reactor Recirculation Pump Quick Restart Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On file 6-25-13 Name Qual Signature Date Jim Southerton SRO On File 6-10-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor was scrammed when both Reactor Recirculation Pumps tripped.

2. Evidence of thermal stratification is present.

3. Actions have been taken in accordance with HC.OP-AB.RPV-0003 through step G.11.

INITIATING CUE:

Complete HC.OP-AB.RPV-0003 step G.12 as necessary for restart of A Reactor Recirc Pump.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Core Spray TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths TASK NUMBER:

JPM NUMBER: 2013 NRC RO A-3 REV #: 02 SAP BET:

ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO TASK STANDARD: Core Spray Isolations, Vent & Drain Paths Identified IAW Key.

DEVELOPED BY: NRC DATE: 6/10/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: NRC RO A-3 REV: 02 SYSTEM: Core Spray TASK NUMBER:

TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths ALTERNATE PATH: K/A NUMBER: 2.2.41 IMPORTANCE FACTOR: 3.5 3.9 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

M-52-1 Sht.1, E-0021 Sht.1 E-006 Sht.1, E-6022 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 30 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 10

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-B RHR Pump is C/T for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

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.

Page 3 of 10

TQ-AA-106-0303 JPM: 2013 NRC RO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

Operator obtains appropriate Operator obtains the correct drawings drawings which include: M-52-1 Sh. 1 Core Spray P&ID and Electrical Core Spray prints E-6022, E-0021 Sht.1, E-006 Sht.1 (not all required)

EXAMINER NOTE: Provide copies once prints are identified.

START TIME:

• 1. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical isolation valves:

required to ISOLATE the leak on

• HV-F001A SHUT the suction of the AP206 Core Spray pump.

• V-009 SHUT (ITEMS BOLDED are CRITICAL)

• V-027 SHUT

• V-037 OPEN (check valve bypass) (NOT REQUIRED)

• V-045 SHUT (normally closed)

• V-049 SHUT (normally closed)

Page 4 of 10

TQ-AA-106-0303 JPM: 2013 NRC RO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• 2. Applicant reviews P&IDs and Applicant identifies the following identifies electrical components electrical components required for required to ISOLATE the leak on isolation:

the suction of the AP206 Core

• MCC 10B212, breaker 012 (HV-Spray pump. F001A)

• 10A401, breaker 05 (A CSS Pump Motor)

• 3. Applicant reviews P&ID and Applicant identifies the following identifies mechanical components mechanical VENT valves in the OPEN required to VENT the isolated position:

section of the Core Spray train.

• V-041 OPEN (Valves OPEN)

• V-9975 and/or V-9974 NOTE: May OPEN one, two or all valves to vent

• 4. Applicant reviews P&ID and Applicant identifies the following identifies mechanical components mechanical DRAIN valves in the OPEN required to DRAIN the isolated position:

section of the Core Spray train.

• V-108 (Valves OPEN)

5. STOP TIME:

Task Standard: Mechanical AND electrical components to isolate, vent, and drain the A CS pump are identified IAW P&IDs, E prints per the key.

Page 5 of 10

TQ-AA-106-0303 Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Page 6 of 10

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: ____ _______________________

DATE:_____ __________________

SYSTEM: Core Spray - Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

QUESTION: _____________________________________________________________________

RESPONSE: ____________________________________________________________________

RESULT: - SAT - UNSAT QUESTION: ____________________________________________________________________

RESPONSE: ____________________________________________________________________

RESULT: - SAT - UNSAT Page 7 of 10

TQ-AA-106-0303 REVISION HISTORY JPM NUMBER: 2013 NRC RO A-3 Rev # Date Description Validation Required?

02 7/1/13 Revised IAW current revision of TQ-AA-106-0303 and for Y NRC exam. Added Not Required for V-037 Open Page 8 of 10

TQ-AA-106-0303 VALIDATION CHECKLIST JPM NUMBER: 2013 NRC RO A-3 REV#: 02 TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On File 6-25-13 Name Qual Signature Date Jim Southerton SRO On File 6-10-13 Name Qual Signature Date Page 9 of 10

TQ-AA-106-0303 INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-B RHR Pump is C/T for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station electrical & mechanical drawings.

Page 10 of 10

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 JPM NUMBER: 2013 NRC RO A-4 REV #: 2 SAP BET: NOH05JPZZ19E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO DEVELOPED BY: NRC DATE: 6-1-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC RO A-4 REV: 2 SYSTEM: Administrative TASK NUMBER: 4000270401 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates ALTERNATE PATH: K/A NUMBER: 295938 EA1.01 IMPORTANCE FACTOR: 3.9 4.2 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.CONT-0004 Rev. 6 HC.OP-DL.ZZ-0026 Rev. 128 TOOLS, EQUIPMENT AND PROCEDURES: Calculator ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 INITIAL CONDITIONS:

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. NPV Exh Flow instrumentation channel 9AX300 is inoperable. Flow is being estimated in accordance with HC.OP-DL.ZZ-0026(Q), Attachment 3u (Provided).

5. Monitor Item 136 display is 001.

INITIATING CUE:

Determine the Release Rate of NOBLE GAS from the NPV in accordance with HC.OP-AB.CONT-0004, Action A.4.

Page 3 of 13

TQ-AA-106-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.CONT-0004.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be A.4 A.4 DETERMINE the Total Release Rates Operator determines that to calculate of Noble Gas and Iodine as follows: the Noble Gas release from the NPV USE the SPDS Noble Gas Total. the formulas in Table A must be used.

OR USE one of the Formulas in Table A.

Page 4 of 13

TQ-AA-106-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

IF the effluent (µCi/sec) channel on the RM-11 is NOT operating for a specific plant vent, THEN CALCULATE the Noble Gas release rate for that vent using the following:

• 472 =

Plant Vent Exh µCi/sec (n.g.)

µCi/cc (n.g.)

Flow in cfm Where:

µCi/sec (n.g.) - the calculated release rate from the specified plant vent (Noble Gas)

µCi/cc (n.g.) - The concentration of Noble Gas obtained from the RM-11 (the operable channel will be highlighted in GREEN) OR from an actual sample of the plant vent 472 - The conversion factor in units of cc/sec/cfm Operator manipulates the RM-11

• terminal to obtain the value of NPV Noble Gas release from the 9RX602 Low Range detector and enters the value into the formula.

3.65E-5 uCi/cc.

Operator transfers the Plant Vent Exh

• Flow value from Attachment 3u of HC.OP-DL.ZZ-0026 (provided).

49613.9 CFM (49614 CFM acceptable)

Page 5 of 13

TQ-AA-106-0303 JPM: 2013 NRC RO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator calculates the NPV Noble Gas

• release rate.

Calculated Value =

3.65E-5 µCi/cc

• 49613.9 CFM

• 472

= 854.7 µCi/sec (+ 0.5)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Task Standard: The Release Rate of NOBLE GAS from the NPV is determined in accordance with HC.OP-AB.CONT-0004, Action A.4.

and key.

Page 6 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC RO A-4 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates TASK NUMBER: 4000270401 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 7 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL.

INSERT Malfunctions:

• RM9590 @ 0.0E+00

• RM9602 @ 3.65E-5

• CC01 CRIDS Computer Failure Acknowledge alarms.

Put Simulator in FREEZE.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description ENSURE CRIDS Displays are not functioning.

ENSURE MARKUP copy of HC.OP-DL.ZZ-0026 Attachment 3u available.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code:

Description:

Event code:

Description:

Event code:

Description:

Page 8 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description 9RX590, NPV EFF - North Plant Vent None None Insert malfunction RM9590 to 0.00000 Noble Gas Effluent 9RX602, NPV LOW - North Plant None None Insert malfunction RM9602 to 3.65E-5 Vent Range Noble Gas None None Insert malfunction CC01 CRIDS Computer Failure REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 9 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC RO A-4 Rev # Date Description Validation Required?

2 7-1-13 Moved applicant handouts to end of JPM. Changes to cue Y sheet. NPV Noble Gas release (from the 9RX602 Low Range detector) value changed from 3.65E-7 to 3.65E-5, and updated simulator setup.

Page 10 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM NUMBER: 2013 NRC RO A-4 REV#: 2 TASK: Respond To An Abnormal Release Of Gaseous Radioactivity - Calculate Noble Gas Release Release Rates Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On file 6-25-13 Name Qual Signature Date Jim Southerton SRO On File 6-10-13 Name Qual Signature Date INITIAL CONDITIONS:

Page 11 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE

1. North Plant Vent (NPV) Stack radiation monitoring activity was rising on RM-11 point 9RX590.

2. SPDS is unavailable.

3. HC.OP-AB.CONT-0004 is being executed to determine and stop the release of activity.

4. NPV Exh Flow instrumentation channel 9AX300 is inoperable. Flow is being estimated in accordance with HC.OP-DL.ZZ-0026(Q), Attachment 3u (Provided).

5. Monitor Item 136 display is 001.

INITIATING CUE:

Determine the Release Rate of NOBLE GAS from the NPV in accordance with HC.OP-AB.CONT-0004, Action A.4.

Page 12 of 13

TQ-AA-106-0303 HC.OP-DL.ZZ-0026(Q)

JOB PERFORMANCE MEASURE ATTACHMENT 3u Page 1 of 1 Radioactive Gaseous Effluent Monitoring (North Plant Vent)

T/S 6.8.4.g ODCM TABLE 3.3.7.11-1 ACTION 122 If the North Plant Vent Flow Rate Monitor is Inoperable, then Effluent Releases via this pathway may continue for up to 30 days provided flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Readings are taken every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to ensure that the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Tech Spec Action limit is not exceeded per administrative requirements and after a change in the ventilation line-up.

If flow indication(s) become unavailable, then the NORM flow value may be logged for the specific fan alignment.

HCGS DATE: Todays Date Location Aux/Turb/Radwaste ENTER TIME OF EACH READING BELOW PARAMETER NORM NOW COMMENTS SOLID RADWASTE EXH FAN A318 17,000 17358 SOLID RADWASTE EXH FAN B318 17,000 17163 CHEM LAB EXH A307 7,500 7528 CHEM LAB EXH B307 7,500 7519 OFFGAS DISCHARGE HA-XR- ---

10022 OR HA- 45.9 FI5665 TOTAL FLOW 49613.9 ESTIMATED TOTAL FLOW REPORTED TO RAD PRO - (YES) Yes

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 JPM NUMBER: 2013 NRC SRO A-1 REV #: 02 SAP BET: NOH05JPZZ03E ALTERNATE PATH:

APPLICABILITY:

EO RO STA SRO X DEVELOPED BY: NRC DATE: 6-10-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRO A-1 REV: 02 SYSTEM: Radiation Control TASK NUMBER: 2990420302 TASK: Verify Compliance with Gaseous Release Permit ALTERNATE PATH: K/A NUMBER: 2.3.6 IMPORTANCE FACTOR: 2.0 3.8 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

OP-HC-103-105 Rev 1 TOOLS, EQUIPMENT AND PROCEDURES:

Prepared OP-HC-103-105 Forms 1 & 2, Calculator ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

Review AND Close Out todays Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit in accordance with OP-HC-103-105.

Page 3 of 13

TQ-AA-106-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue AND:

Prepared OP-HC-103-105 log Operator repeats back initiating cue.

Forms 1 & 2 (Attached)

Copy of OP-HC-103-105 CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 4.4.6.

Page 4 of 13

TQ-AA-106-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate Operator reviews Forms 1 & 2.

space for verification and close out and enter the time and date.

IAW Step 4.4.3 of OP-HC-103-105

• during calculation of valve open time the number must be rounded up.

The Operator recognizes NCO incorrectly rounded down from 2.6 to 2.5 instead of rounding up to 3.0 in Section C of Form 2.

In Section C of Form 2, Operator

• recognizes NCO incorrectly used securing of purge lineup for end time of second purge period instead of using entry into OPCON 4 time IAW step 4.4.2. Total hours should be 5 vice 8 (1252 vice 1548).

Page 5 of 13

TQ-AA-106-0303 JPM: 2013 NRC SRO A-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Radiation Control TASK: Verify Compliance with Gaseous Release Permit

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE IF the operator requests the NCO to make changes, THEN DIRECT the operator to make N/A any required changes.

4.4.6 The SM/CRS should verify the Operator makes corrections to Form 2

• calculations, sign in the appropriate Stop times and Total Hours.

space for verification and close out Examiner Note: Refer to Examiners and enter the time and date. Copy for appropriate corrections.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Task Standard: Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit reviewed with issues identified per the key Page 6 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-1 TASK: Verify Compliance with Gaseous Release Permit TASK NUMBER: 2990420302 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT

TQ-AA-106-0303 JOB PERFORMANCE MEASURE FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 020130003 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open During Previous Year (Note 1) (1) Max. allowed for 365 days (Admin Limit) 452 hrs DATE NUMBER OF HOURS (2) Total previous year (NOTE 1) (-) 35.5 (3) Hours available this date (=) 416.5 4/3/13 5.5 (line 1 minus line 2) 6/25/13 3.5 Hours authorized this date 8/1/13 24.0 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or Line (3), whichever is less) 24 8/12/13 2.5 NCO performing calculation Date/Time John Smith Today/0100 SM/CRS verification and authorization Date/Time Andrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Condition Time at which valve/line was closed or Total number of hours valve/line 1, 2, or 3 was entered with valve/line open Condition 4 or 5 was entered with valve/line opened this cycle opened (NOTE 3) 0200 0436 2.5 3.0 0800 1548 1252 8.0 5.0 Total number of hours valves/line open this permit: 10.5 8.0 NCO performing calculations Andy Granatelli Date/Time Today/Now SM/CRS Closing permit Operator Signature Date/Time Date/Time Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-1 Rev # Date Description Validation Required?

2 7-1-13 Revised dates to coincide with NRC Exam. Revised Forms to Yes current revision of procedure. Added clarifying comments to examiner guide.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-1 REV#: 02 TASK: Verify Compliance with Gaseous Release Permit Prior to each JPM use verify the revision of the procedure referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Jim Southerton SRO On File 6-10-13 Name Qual Signature Date Laura Myers SRO On File 6-25-13 Name Qual Signature Date

OP-HC-103-105 Revision 1 Page 8 of 9 FORM 1 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG Page 1 of 1 DATE HOURS HOURS NAME OF SM/CRS NCO HOURS TOTAL NAME OF SM/CRS NCO PREV. AUTH. AUTHORIZING THIS INITIAL USED THIS HOURS CLOSING THIS PERMIT INITIAL YEAR THIS PERMIT PERMIT PREVIOUS (Note 1) PERMIT YEAR (Note 1) 4/3/13 22.5 24 H. David SD 5.5 28.0 S. West SD 6/25/13 18.5 24 G. Williams TRW 3.5 22.0 G. Cloon TRW 8/1/13 22.0 24 W. Holmes R 24.00 46.0 P. Price R 8/12/13 46.0 24 B. Lee E 2.5 48.5 V. Bonovan E Today 35.5 24 A. Jones JS Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

OP-HC-103-105 Revision 1 Page 9 of 9 FORM 2 CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT SECTION A Date: Today NOTE: This permit is valid only until 2400 of this date Gaseous Effluent Permit #: 020130003 SECTION B HOURS VALVES/LINES OPEN PREVIOUS YEAR (Note 1)

Calculate Total Hours Open (1) Max. allowed for 365 days (Admin Limit) 452 hrs During Previous Year (Note 1)

DATE NUMBER OF HOURS (2) Total previous year (NOTE 1) (-) 35.5 (3) Hours available this date (=) 416.5 4/3/13 5.5 (line 1 minus line 2) 6/25/13 3.5 8/1/13 24.0 Hours authorized this date (max 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 24 8/12/13 2.5 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or Line (3), whichever is less)

NCO performing calculation Date/Time John Smith Today/0100 SM/CRS verification and authorization Date/Time Andrew Jones Today/0130 SECTION C VALVE/LINE OPEN TIME (Note 2)

START TIME STOP TIME TOTAL HOURS Time at which valve/line was open or Condition Time at which valve/line was closed or Total number of hours valve/line 1, 2, or 3 was entered with valve/line open Condition 4 or 5 was entered with valve/line opened this cycle opened (NOTE 3) 0200 0436 2.5 0800 1548 8.0 Total number of hours valves/line open this permit: 10.5 NCO performing calculations Andy Granatelli Date/Time Today/Now SM/CRS Closing permit Date/Time Note 1: The previous year includes the period from 2400 on todays date back to 0001 on the same date one year earlier.

Note 2: Completed Form 2 should be filed in the AP-104 binder in the control room.

Note 3: When computing the total hours (round up to the nearest 0.5 or to the nearest 1.0 hr.)

TQ-AA-106-0303 INITIAL CONDITIONS:

1. A plant shutdown is in progress for a Refueling outage.

2. The Reactor is shutdown.

3. At 0200 today Purging of the Primary Containment commenced.

4. At 0436, the Purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation, due to a damper problem.

5. At 0800, Purging of Primary Containment re-commenced.

6. At 1252 today Operational Condition 4 was entered.

7. At 1548 today the purge lineup was secured in accordance with HC.OP-SO.GS-0001, Containment Atmosphere Control System Operation.

INITIATING CUE:

Review AND Close Out todays Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit in accordance with OP-HC-103-105.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 2013 NRC SRO A-2 JPM NUMBER: REV #: 02 (305H-JPM.ZZ031)

SAP BET: NOH05JPZZ31E ALTERNATE PATH:

APPLICABILITY:

EO RO STA SRO X DEVELOPED BY: NRC DATE: 6-10-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: ZZ031 REV: 2 SYSTEM: Conduct of Operations TASK NUMBER: 2991110302 TASK: Initiate and Review System Lineup Sheets ALTERNATE PATH: X K/A NUMBER: 2.1.29 IMPORTANCE FACTOR: 3.4 3.3 APPLICABILITY: RO SRO EO RO STA SRO X EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-IO.ZZ-0003 Rev 84 M-42-1 Sheet 2 Tech Spec 3.3.2 TOOLS, EQUIPMENT AND PROCEDURES:

Simulated Off-Normal Report, Prepared HC.OP-IO.ZZ-0003 Attachment 4 ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 16

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 INITIAL CONDITIONS:

1. A start-up is in progress IAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 IAW Attachment 4 of the IOP.

3. The Current Mode has been changed to Mode 1 IAW step 1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated IAW step 1.2.3 of HC.OP-IO.ZZ-0003 Attachment 4.

INITIATING CUE:

COMPLETE step 1.2.4 of HC.OP-IO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Page 3 of 16

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue AND:

Prepared HC.OP-IO.ZZ-0003 Attachment 4 (Attached) Operator repeats back initiating cue.

Prepared Components In Off-Normal Position Report (Labeled FIRST HANDOUT)

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

HC.OP-IO.ZZ-0003 Attachment 4 N/A 1.2.3 GENERATE a Components In Off-Normal Position Report N/A USING WCM Reports/Off Normal Report function.

Page 4 of 16

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.2.4 POSITION all components as Operator reviews Components In required. Off-Normal Position Report.

Operator recognizes the following

• isolation valves are closed and should be open:

• H1AB -1ABV9979-B

• H1AB -1ABV9980-B Operator determines these valves are

• required for isolation instrumentation in OPCON 1.

Examiner Note:

M-42-1 Sheet 2 - Transmitters are Main Steam Low Pressure to NSSSS T/S Table 3.3.2-1 Trip Function 3c Page 5 of 16

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE AFTER the operator determines the V9979-B and V9980-B are required to be open, THEN:

• INFORM the operator investigation has determined the valves were inadvertently closed during I&C work on the opposite Operator repeats initiating cue and channels and have been accepts updated Off-Normal.

re-opened.

• PROVIDE the operator the updated Off-Normal with the V9979-B and V9980-B removed.

• (Labeled SECOND HANDOUT) 1.2.4 POSITION all components as Operator reviews Components In required. Off-Normal Position Report.

Operator recognizes NO components require re-positioning.

Operator initials IO.ZZ-0003

• Attachment 4 step 1.2.4.

Page 6 of 16

TQ-AA-106-0303 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Task Standard: Off normal report reviewed with components listed in key identified Page 7 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: SRO A-2 TASK: Initiate and Review System Lineup Sheets TASK NUMBER: 2991110302 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: ZZ031 Rev # Date Description Validation Required?

1 11/9/08 Converted ZZ031 to new JPM format. Y Changed critical Off-Normal components to MSL Low Pressure transmitters, which are NOT required in OPCON 2, but ARE required in OPCON 1.

Updated Off-Normal distractor items to more current dates.

Added CUE that valves were re-positioned and a corrected Off-Normal to provide to the operator and allow completion of the task.

2 7/2/2013 Off normal report updated Y Page 9 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-2 REV#: 02 TASK: Initiate and Review System Lineup Sheets Prior to each JPM use verify the revision of the procedure referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Jim Southerton SRO On File 6-10-13 Name Qual Signature Date Laura Myers SRO On File 6-25-13 Name Qual Signature Date Page 10 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A start-up is in progress IAW HC.OP-IO.ZZ-0003.

2. Preparations are being made to enter Operational Condition 1 IAW Attachment 4 of the IOP.

3. The Current Mode has been changed to Mode 1 IAW step 1.2.1 of Attachment 4.

4. A Components in OFF-Normal Position Report has been generated IAW step 1.2.3 of HC.OP-IO.ZZ-0003 Attachment 4.

INITIATING CUE:

COMPLETE step 1.2.4 of HC.OP-IO.ZZ-0003 Attachment 4.

You will be allowed access to SAP and DCRMS to research component data.

The provided Off Normal Report does NOT reflect the current status of the actual plant.

Do NOT perform ANY changes to actual plant data.

Page 11 of 16

TRAINING USE ONLY ATTACHMENT 4 STARTUP FROM COLD SHUTDOWN TO RATED POWER FINAL CHECKS (ENTERING OPERATIONAL CONDITION 1)

(Page 1 of 2)

NOTE The following checks may be performed in any order.

1. FINAL CHECKS 1.1 System requirements AND surveillances required for entering Operational Condition 1 are completed. This review must include the disposition of all outstanding Equipment Non-Conformances to determine impact on system operability.

1.1.1 Operations Bob Jones Today 1.1.2 I&C Bill Smith Today 1.1.3 Reactor Engineering Susan Anthony Today 1.1.4 Chemistry Chris Anderson Today 1.1.5 System Engineering Betty Kidman Today Date 1.2 PRIOR to taking the RPS MODE SWITCH to RUN, PERFORM the following:

1.2.1. CHANGE WCM "Current Operating Mode" from 2 to 1 USING the Mode Dependent Tagging/Current Mode/Change function. JMB 1.2.2. ENSURE all current notifications are screened for operability prior to mode change. [70021851]

Joe Johnson Today/Now SM/CRS DATE-TIME NOTE The Components in off - Normal Position Report will indicate all components NOT in the required position for POWER OPERATION.

1.2.3. GENERATE a Components In Off-Normal Position Report USING WCM Reports/Off Normal Report function. JMB Continued on next page

TRAINING USE ONLY ATTACHMENT 4 STARTUP FROM COLD SHUTDOWN TO RATED POWER FINAL CHECKS (ENTERING OPERATIONAL CONDITION 1)

(Page 2 of 2) 1.2.4. POSITION all components as required. ___

1.2.5. UPDATE WCM using the Mode/Dependent Tagging/Normal Positions/Change Function. ___

1.2.6. The above items have been completed with all equipment required for going into POWER OPERATION available.

SM/CRS DATE-TIME 1.3 Pre-Startup Walk down COMPLETED. IF NOT required, INDICATE "NA". IF completed, ATTACH completed NC.CC-AP.ZZ-0011(Q), Form-1, Pre-Startup Missile Hazard Inspection Report, to this procedure.

SM/CRS DATE-TIME Reviewed By:

SM/CRS DATE-TIME

TRAINING USE ONLY User: TRAIN20 Off Normal Report Date: TODAY Plant: NNUC Mode 01 Time: NOW Technical Object Description Current Normal Location Loc. Description Status ChangeDate Remark H0FA FA-V366 "C" AUX BLR MAIN STEAM STOP VALVE X O 13102101C HC BOILER C AREA OffNormal 07/20/2007 CONTROLED PER SOP, N#20330388 H0FA FA-V423 FAFV-3457C BYPASS VALVE O X 13102101C HC BOILER C AREA OffNormal 04/11/2007 TVC NOT WORKING H0GA GA-V197 DOM WTR HTR 0BE503 HTG STM VLV X O 031023342A HC HOT WATER HEATER ROOM A OffNormal 08/26/2006 CONTROLLED PER SOP H0GA GA-V539 HTG STM LO PT DRN V 0-P-GA-01 X O 031023342B HC HOT WATER HEATER ROOM B OffNormal 08/26/2006 CONTROLLED PER SOP H0JA JA-V051 FO SYS BLR A FO RECIRC ISLN VL X O 13102101A HC BOILER A AREA OffNormal 10/16/2006 ABANDONED EQUIPMENT H0KD KD-V450 EXTERIOR HYDRANT ISLN VLV O X 001020AQ HC YARD-SOUTH OF POWER BLOCK OffNormal 00/00/0000 H0KD KD-V452 SEW TREAT TRK W/DN EXTRN HYDRT O X 18102WWTF HC WASTEWATER TREATMENT FACILITY OffNormal 00/00/0000 H0NQ -00L520-23 SPARE X O 13102103F HC FRESH WATER SUPPLY PANEL AREA OffNormal 00/00/0000 H0QB L-547-02 SPARE X O 0201 HC SWIS BLDG MCC AREA OffNormal 08/07/2005 RETURNED TO NORMAL H0ZZ -00L154-01 RECPT WEST WALL/CORRIDOR O X 021022000A HC ADMIN FACILITY EL.102 OffNormal 08/15/2006 BKR NOW SPARED PER DCP H0ZZ -00L154-03 RECPT RM #109/CORRIDOR O X 021022000A HC ADMIN FACILITY EL.102 OffNormal 08/15/2006 BKR NOW SPARED PER DCP H0ZZ -00L156-10 LTG,ADMIN RM 253 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-12 LTG,ADMIN RM 255&61 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-14 LTG,ADMIN RM 255 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-16 LTG,ADMIN RM 256 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-18 INTERLOCKED W/16 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L157-26 SPARE X O 021022000A HC ADMIN FACILITY EL.102 OffNormal 02/15/2006 CHANGED FOR A DCP 80087126 H0ZZ -00L327-08 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/28/2005 X PER ORDER # 60054720 H0ZZ -00L327-09 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/24/2005 X PER ORDER # 60053935 H0ZZ -00L327-10 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/28/2005 X PER ORDER # 60054720 H0ZZ -00L327-12 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/22/2005 PER ORDER # 60055303 H0ZZ -00L327-23 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/24/2005 X PER ORDER # 60053935 H0ZZ -00L439-12 SPARE X O 021232000C HC ADMIN FACILITY EL 123 OffNormal 05/11/2006 TP&L PER ORDER 60061688 H0ZZ -2RFSS06 SPARE BKR 200AMP SERVICE DISC X O 070897000A HC HC/SALEM COMMON GDHSE EL.89' OffNormal 07/03/2007 X FOR TEMP LIGHT/DCP WORK H0ZZ -AC-2-15 SPARE X O 001020AX HC FUTURE ASSIGNMENT OffNormal 03/30/2006 CLOSED TILL 70051846 OP90 CONFIRMED H1AB -1ABV9979-B INST ISLN VLV FOR 1SMPT-N076A X LO 011201406A HC ELECT EQUIP MEZZANINE A OffNormal 11/13/2008 CLOSED FOR I&C H1AB -1ABV9980-B INST ISLN VLV FOR 1SMPT-N076C X LO 011201406A HC ELECT EQUIP MEZZANINE A OffNormal 11/13/2008 CLOSED FOR I&C H1CD CD-V021 TURB END H2 DETRNG SECT DRN X LX 011021302A HC ELECTRICAL EQUIPMENT AREA A OffNormal 07/03/2007 COULD NOT ACCESS TO PLACE LOCK.

H1KC KC-V282 STRAINER B/D VLV X XC 050545106D HC FUTURE CONTROLLED STOR AREA D OffNormal 05/25/2005 20240203 NO THREADS TO PUT CAP ON

• • FIRST HANDOUT**

• • • SECOND HANDOUT***

TRAINING USE ONLY User: TRAIN20 Off Normal Report Date: TODAY Plant: NNUC Mode 01 Time: NOW Technical Object Description Current Normal Location Loc. Description Status ChangeDate Remark H0FA FA-V366 "C" AUX BLR MAIN STEAM STOP VALVE X O 13102101C HC BOILER C AREA OffNormal 07/20/2007 CONTROLED PER SOP, N#20330388 H0FA FA-V423 FAFV-3457C BYPASS VALVE O X 13102101C HC BOILER C AREA OffNormal 04/11/2007 TVC NOT WORKING H0GA GA-V197 DOM WTR HTR 0BE503 HTG STM VLV X O 031023342A HC HOT WATER HEATER ROOM A OffNormal 08/26/2006 CONTROLLED PER SOP H0GA GA-V539 HTG STM LO PT DRN V 0-P-GA-01 X O 031023342B HC HOT WATER HEATER ROOM B OffNormal 08/26/2006 CONTROLLED PER SOP H0JA JA-V051 FO SYS BLR A FO RECIRC ISLN VL X O 13102101A HC BOILER A AREA OffNormal 10/16/2006 ABANDONED EQUIPMENT H0KD KD-V450 EXTERIOR HYDRANT ISLN VLV O X 001020AQ HC YARD-SOUTH OF POWER BLOCK OffNormal 00/00/0000 H0KD KD-V452 SEW TREAT TRK W/DN EXTRN HYDRT O X 18102WWTF HC WASTEWATER TREATMENT FACILITY OffNormal 00/00/0000 H0NQ -00L520-23 SPARE X O 13102103F HC FRESH WATER SUPPLY PANEL AREA OffNormal 00/00/0000 H0QB L-547-02 SPARE X O 0201 HC SWIS BLDG MCC AREA OffNormal 08/07/2005 RETURNED TO NORMAL H0ZZ -00L154-01 RECPT WEST WALL/CORRIDOR O X 021022000A HC ADMIN FACILITY EL.102 OffNormal 08/15/2006 BKR NOW SPARED PER DCP H0ZZ -00L154-03 RECPT RM #109/CORRIDOR O X 021022000A HC ADMIN FACILITY EL.102 OffNormal 08/15/2006 BKR NOW SPARED PER DCP H0ZZ -00L156-10 LTG,ADMIN RM 253 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-12 LTG,ADMIN RM 255&61 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-14 LTG,ADMIN RM 255 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-16 LTG,ADMIN RM 256 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L156-18 INTERLOCKED W/16 O X 021202000B HC ADMIN FACILITY EL 120 OffNormal 12/05/2005 BREAKER IS SPARED BY DCP H0ZZ -00L157-26 SPARE X O 021022000A HC ADMIN FACILITY EL.102 OffNormal 02/15/2006 CHANGED FOR A DCP 80087126 H0ZZ -00L327-08 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/28/2005 X PER ORDER # 60054720 H0ZZ -00L327-09 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/24/2005 X PER ORDER # 60053935 H0ZZ -00L327-10 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/28/2005 X PER ORDER # 60054720 H0ZZ -00L327-12 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/22/2005 PER ORDER # 60055303 H0ZZ -00L327-23 SPARE X O 031023305B HC UNRESTRICTED MACHINE SHOP B OffNormal 06/24/2005 X PER ORDER # 60053935 H0ZZ -00L439-12 SPARE X O 021232000C HC ADMIN FACILITY EL 123 OffNormal 05/11/2006 TP&L PER ORDER 60061688 H0ZZ -2RFSS06 SPARE BKR 200AMP SERVICE DISC X O 070897000A HC HC/SALEM COMMON GDHSE EL.89' OffNormal 07/03/2007 X FOR TEMP LIGHT/DCP WORK H0ZZ -AC-2-15 SPARE X O 001020AX HC FUTURE ASSIGNMENT OffNormal 03/30/2006 CLOSED TILL 70051846 OP90 CONFIRMED H1CD CD-V021 TURB END H2 DETRNG SECT DRN X LX 011021302A HC ELECTRICAL EQUIPMENT AREA A OffNormal 07/03/2007 COULD NOT ACCESS TO PLACE LOCK.

H1KC KC-V282 STRAINER B/D VLV X XC 050545106D HC FUTURE CONTROLLED STOR AREA D OffNormal 05/25/2005 20240203 NO THREADS TO PUT CAP ON

• • • SECOND HANDOUT***

TQ-AA-106-0303 JOB PERFORMANCE MEASURE

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Core Spray TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths TASK NUMBER:

JPM NUMBER: 2013 NRC SRO A-3 REV #: 02 SAP BET:

ALTERNATE PATH:

APPLICABILITY:

EO RO STA SRO X Core Spray Isolations, Vent & Drain Paths Identified IAW Key.

TASK STANDARD:

Applicable TS identified DEVELOPED BY: NRC DATE: 6/10/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: NRC SRO A-3 REV: 02 SYSTEM: Core Spray TASK NUMBER:

TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths ALTERNATE PATH: K/A NUMBER: 2.2.41 IMPORTANCE FACTOR: 3.5 3.9 APPLICABILITY: RO SRO EO RO X STA SRO EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

M-52-1 Sht.1, E-0021 Sht.1 E-006 Sht.1 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 30 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 9

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-C RHR Pump is C/T for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

• Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

• Identify the most limiting Tech Spec condition (if any) AFTER the leak has been isolated.

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.

Page 3 of 9

TQ-AA-106-0303 JPM: 2013 NRC SRO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

Operator obtains M-52-1 Sh. 1 Core Operator obtains the correct drawings Spray P&ID and Electrical Core Spray P&ID for F001A AND CSS A Pump Motor START TIME:

• 1. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical isolation valves:

required to ISOLATE the leak on

• HV-F001A SHUT the suction of the AP206 Core Spray pump.

• V-009 SHUT (ITEMS BOLDED are CRITICAL)

• V-027 SHUT

• V-037 OPEN (check valve bypass) (NOT REQUIRED)

• V-045 SHUT (normally closed)

• V-049 SHUT (normally closed)

2. Applicant reviews P&IDs and Applicant identifies the following identifies electrical components electrical components required for required to ISOLATE the leak on isolation:

the suction of the AP206 Core

• MCC 10B212, breaker 012 (HV-Spray pump. F001A)

• 10A401, breaker 05 (A CSS Pump Motor)

Page 4 of 9

TQ-AA-106-0303 JPM: 2013 NRC SRO A-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• 3. Applicant reviews P&ID and Applicant identifies the following identifies mechanical components mechanical VENT valves in the OPEN required to VENT the isolated position:

section of the Core Spray train.

• V-041 OPEN (Valves OPEN)

• V-9975 and/or V-9974 NOTE: May OPEN one, two or all valves to vent

• 4. Applicant reviews P&IDs and Applicant identifies the following identifies mechanical components mechanical DRAIN valves in the OPEN required to DRAIN the isolated position:

section of the Core Spray train.

• V-108 (Valves OPEN)

5. Applicant reviews Tech Specs and Applicant identified the following as the identifies the most limiting Tech most limiting Tech Spec Action Spec action statement AFTER Statement:

leak isolation.

• 3.5.1.a.1 Restore within 7 days of be in Hot S/D within 12hrs and Cold S/D within 24hrs

6. STOP TIME:

Task Standard: Core Spray Leak Isolations, Vent & Drain Paths identified IAW the key.

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Page 5 of 9

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: ____ _______________________

DATE:_____ __________________

SYSTEM: Equipment Control TASK: Identify Core Spray Leak Isolations and Vent & Drain Paths TASK NUMBER:

QUESTION: _____________________________________________________________________

RESPONSE: ____________________________________________________________________

RESULT: - SAT - UNSAT QUESTION: ____________________________________________________________________

RESPONSE: ____________________________________________________________________

RESULT: - SAT - UNSAT Page 6 of 9

TQ-AA-106-0303 REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-3 Rev # Date Description Validation Required?

02 7/1/13 Revised IAW current revision of TQ-AA-106-0303 and for NRC Y exam. Removed unnecessary drawing from reference list (E-6022). Added Not Required for identification of V-037 in examiner guide. Changed B RHR pump C/T out to C RHR pump C/T out. This is necessary to ensure proper Tech Spec application.

Page 7 of 9

TQ-AA-106-0303 VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-3 REV#: 02 TASK: Identify Core Spray Leak Isolations, Vent & Drain Paths Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Jim Southerton SRO On File 6-10-13 Name Qual Signature Date Laura Myers SRO On File 6-25-13 Name Qual Signature Date Page 8 of 9

TQ-AA-106-0303 INITIAL CONDITIONS:

-100% Power

-Core Spray is in its normal standby lineup

-C RHR Pump is C/T for routine maintenance

- A pencil size leak has been reported by the Reactor Building Operator to the Shift manager on the Core Spray suction piping between the CSS Pump Suppression Pool Suction Valve (HV-F001A) and the AP206 Core Spray pump suction inlet.

INITIATING CUE:

The shift manager directs you to:

• Identify mechanical AND electrical components to isolate, vent, and drain the pump using controlled station mechanical drawings.

• Identify the most limiting Tech Spec condition (if any) AFTER the leak has been isolated.

Page 9 of 9

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

TASK NUMBER: 2990010101 JPM NUMBER: 2013 NRC SRO A-4 REV #: 2 SAP BET: NOH05JPZZ36E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X TASK STANDARD: Completes HC.OP-DL.ZZ-0026 Attachment 1a ITEM 47 Day Shift reading for the RMS Cooling Tower Blowdown Weir Flow Rate Monitor IAW JPM Key DEVELOPED BY: NRC DATE: 6/10/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRO A-4 REV: 2 SYSTEM: Equipment Control TASK NUMBER: 2990010101 TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

ALTERNATE PATH: K/A NUMBER: 2.2.23 IMPORTANCE FACTOR: 3.1 4.6 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Classroom/Perform

REFERENCES:

HC.OP-DL.ZZ-0026 Rev 136 TOOLS, EQUIPMENT AND PROCEDURES:

Blank HC.OP-DL.ZZ-0026 ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 15

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

TASK NUMBER: 2990010101 INITIAL CONDITIONS:

1. The plant is at 100% power.

2. B Circ Water Pump is tagged for motor replacement.

3. A, C, and D Circ Water Pumps are in service.

4. 3 Service Water Pumps are in service

5. Cooling Tower Blowdown Weir Flow Rate Monitor 0SP-RI4861 is reading blank and is INOPERABLE. TSAS # 2012-001 entered.

6. RM-11 point 9AX327 historical data is NOT available.

7. SSW Loop Flow CRIDS Point values as follows:

• A2440 SERVICE WATER FLOW RATE DIV A = 13,560 gpm

• A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE:

You are the Control Room Supervisor.

The Reactor Operator has asked you to review a completed HC.OP-DL.ZZ-0026 a ITEM 47 Day Shift reading and Att. 3y for the inoperable RMS Cooling Tower Blowdown Weir Flow Rate Monitor.

Page 3 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue AND:

• The completed copy of Operator repeats back initiating cue.

HC.OP-DL.ZZ-0026 (both pages).

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

HC.OP-DL.ZZ-0026 Attachment 1a N/A ITEM CHANNEL CHECK: COOLING Operator reads ITEM 47.

47 TOWER BLOWDOWN WEIR FLOW RATE MONITOR OPER COND Operator determines the ITEM is AT ALL TIMES applicable is the current Op Condition ACCEPTABLE LIMITS MIN NORM MAX Operator reads the limits.

ITEM 002 < 40K 70K INSTRUMENT (PANEL) 0SP-RI4861 (10C604) Operator reads NOTE 45 and ITEM 029 determines that data is not available RM-11 (9AX327) (NOTE 45) from the Initial Conditions.

Page 4 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

NOTE Operator reads NOTE 33 and 33 determines that data is not available from the Initial Conditions.

NOTE Operator reads NOTE 35 and 35 determines that data is not available from the Initial Conditions.

NOTE IF INSTRUMENT IS INOP, USE 46 ATTACHMENT 3Y TO ESTIMATE Operator reads NOTE 46 and

• WEIR FLOW. THIS IS REQUIRED determines that Attachment 3Y is REGARDLESS OF WHETHER A applicable.

RADIOACTIVE LIQUID RELEASE IS IN PROGRESS.

Operator locates Attachment 3Y.

Examiner Note: Refer to steps below and Examiner Copy of Attachment 3Y for Standards associated with this step.

Page 5 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

HC.OP-DL.ZZ-0026 Attachment 3Y DATE Operator verifies current date on Attachment 3Y. (Note: TODAY is acceptable)

METHOD 1 Operator determines data for Method 1 completion is not available and continues to METHOD 2.

TIME Operator verifies current time on Attachment 3Y under Method 2 (Note:

Now is acceptable for current time.)

SSW LOOP A FLOW # Operator reads # Footnote Page 6 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

1. READ FROM FIT-2218A/B OR FR-2218-1/2 OR CRIDS A2440/A2441.

(B SSW LOOP FLOW (FIT-2218B) IS OBTAINED LOCALLY AT Operator determines A SSW Loop Flow PANAMETRICS MONITOR. FLOW is 13,560 gpm from CRIDS point A2440 VALUE IS THE AVERAGE in the Initial Conditions and that it is VOLUMETRIC FLOW RATE WHICH recorded correctly on ATT 3Y under IS DISPLAYED AS AVG SSW LOOP A FLOW #.

VOLUMETRIC GAL/MIN ON THE MONITOR DISPLAY.

SSW LOOP B FLOW # Operator reads # Footnote

1. READ FROM FIT-2218A/B OR FR-2218-1/2 OR CRIDS A2440/A2441.

(B SSW LOOP FLOW (FIT-2218B) IS OBTAINED LOCALLY AT Operator determines B SSW Loop Flow PANAMETRICS MONITOR. FLOW is 21,345 gpm from CRIDS point A2441 VALUE IS THE AVERAGE in the Initial Conditions and that it is VOLUMETRIC FLOW RATE WHICH recorded correctly on ATT 3Y under IS DISPLAYED AS AVG SSW LOOP B FLOW #.

VOLUMETRIC GAL/MIN ON THE MONITOR DISPLAY.

TOTAL SSW FLOW Operator verifies calculation of Total SSW Flow at 34,905 gpm by summing Loop A and Loop B flows.

Page 7 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

EVAPORATIVE LOSSES*. Operator reads

• Footnote

• REFERENCE PRINT 10855-M15-181-1 FOR EVAPORATIVE LOSS ESTIMATES. USE 16,700 GPM FOR Operator determines Evaporative DEFAULT VALUE(MIN. DILUTION Losses from

• Footnote at bottom of FLOW), FOR EVAPORATIVE LOSS page for 3 Circ Water Pump operation ESTIMATES IF 4 CIRCULATING is INCORRECTLY recorded as WATER PUMPS ARE IN SERVICE, 16,700gpm.

OR 12,500 GPM IF ONLY 3 Examiner Note: If applicant asks, CIRCULATING WATER PUMPS inform applicant that he/she is to ARE IN SERVICE. THIS BLOCK IS correct any identified incorrect N/A IF THE COOLING TOWER IS values.

OUT OF SERVICE.

Operator determines correct value of

• Evaporative Losses to be 12,500gpm (3 CW pumps in service) and enters the value 12,500 under EVAPORATIVE LOSSES* on ATT 3Y.

Page 8 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

TOTAL WEIR FLOW Operator determines that recorded TOTAL WEIR FLOW of 18,205 gpm is incorrect. Operator determines that recorded TOTAL WEIR FLOW should be 22,405gpm by subtracting Evaporative Losses (12,500 gpm) from Total SSW Loop Flow (34,905 gpm).

Operator enters the correct value of

• 22,405 under TOTAL WEIR FLOW on ATT 3Y.

HC.OP-DL.ZZ-0026 Attachment 1a N/A ITEM CHANNEL CHECK: COOLING Operator reads ITEM 47.

47 TOWER BLOWDOWN WEIR FLOW RATE MONITOR DAY Operator verifies DAY reading of F/I logged on ATTACHMENT 1a for ITEM 47.

INST TRIPPED Operator verifies F/I logged on ATTACHMENT 1a for ITEM 47 INST TRIPPED.

Page 9 of 15

TQ-AA-106-0303 JPM: 2013 NRC SRO A-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Equipment Control Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring TASK: System Cooling Tower Blowdown Weir Flow)

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

REPEAT BACK any message from N/A the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Task Standard: Completed HC.OP-DL.ZZ-0026 Attachment 1a ITEM 47 Day Shift reading and Att. 3y for the inoperable RMS Cooling Tower Blowdown Weir Flow Rate Monitor reviewed with issues identified per the key.

Page 10 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-4 Rev # Date Description Validation Required?

01 6/10/13 Revise IAW latest revision of HC.OP-DL.ZZ-0026 for use on Y NRC exam 02 7/3/13 Revised JPM to make SRO level (review completed form vice Y completing form from scratch).

TQ-AA-106-0303 JOB PERFORMANCE MEASURE JPM NUMBER: 2013 NRC SRO A-4 REV#: 02 TASK: Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or

2. justification is provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Sequence Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

12. Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by

13. the operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Jim Southerton SRO On File 6-10-13 Name Qual Signature Date Laura Myers SRO On File 6-25-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-4 TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

TASK NUMBER: 2990010101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT

TQ-AA-106-0303 JOB PERFORMANCE MEASURE TRAINING USE ONLY Rev. 128

TQ-AA-106-0303 JOB PERFORMANCE MEASURE TRAINING USE ONLY Rev. 128

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power.

2. B Circ Water Pump is tagged for motor replacement.

3. A, C, and D Circ Water Pumps are in service.

4. 3 Service Water Pumps are in service.

5. Cooling Tower Blowdown Weir Flow Rate Monitor 0SP-RI4861 is reading blank and is INOPERABLE. TSAS # 2012-001 entered.

6. RM-11 point 9AX327 historical data is NOT available.

7. SSW Loop Flow CRIDS Point values as follows:

• A2440 SERVICE WATER FLOW RATE DIV A = 13,560 gpm

• A2441 SERVICE WATER FLOW RATE DIV B = 21,345 gpm INITIATING CUE:

You are the Control Room Supervisor.

The Reactor Operator has asked you to review a completed HC.OP-DL.ZZ-0026 Attachment 1a ITEM 47 Day Shift reading and Att. 3y for the inoperable RMS Cooling Tower Blowdown Weir Flow Rate Monitor.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 JPM NUMBER: 2013 NRC SRO A-5 REV #: 02 SAP BET: NOH05JPCL05E ALTERNATE PATH:

APPLICABILITY:

EO RO STA X SRO X TASK STANDARD: Event correctly classified within the time critical limits.

DEVELOPED BY: NRC DATE: 6/10/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC SRO A-5 SYSTEM: Administrative Duties/Reporting Requirements TASK NUMBER: 2000500302/2000020505 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition ALTERNATE PATH: K/A NUMBER: 2.4.38 IMPORTANCE FACTOR: 2.2 4.0 APPLICABILITY: RO SRO EO RO STA X SRO X EVALUATION SETTING/METHOD: Simulator/Perform or In Plant/Simulate

REFERENCES:

Hope Creek Event Classification Guide, TOC Rev 0 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15/13 Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: / Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 21

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 INITIAL CONDITIONS:

1. The plant was at 100% power with the AD483 inverter isolated to its backup AC supply.

2. Then, a Loss of Offsite Power occurred.

3. All Emergency Diesel Generators have failed to start and all vital buses are de-energized.

4. Due to a loss of rod position indication, the Control Room was unable to verify the reactor shutdown, and EOP-101A is being implemented.

5. The following conditions exist:

• A, C, and E APRMs are de-energized

• B, D, and F APRMS are reading 0% power.

• RCIC is injecting.

• RPV Level is -80, rising after reaching a minimum value of -90.

• RPV pressure is 900# being controlled with SRVs.

6. Efforts to energize the Vital buses have been unsuccessful; maintenance has reported that they should be able to restore the B EDG to service in one hour.

7. The current 33 ft. elevation wind direction is from 332° at 21 mph.

8. Plant Effluents: 1.10 E+01µCi/Sec Noble Gas & 1.30 E-01 µCi/Sec I-131 INITIATING CUE:

Based on this information, classify this event and make the initial notifications.

This is a Time Critical Task.

Time zero for this event is now.

EXAMINER NOTE: HAND APPROPRIATE ATTACHMENT TO THE APPLICANT WHEN ASKED (DO NOT HAVE APPLICANT WRITE IN REFERENCE BOOKS)

Page 3 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct Operator obtains Hope Creek Event procedure. Classification Guide.

ECG The primary tools for determining the Section emergency classification level are the 8.4 EAL flowcharts or EAL wallcharts. The user of the EAL flowcharts or wallcharts may (but is not required to) consult the EAL Technical Basis in order to obtain additional information concerning the EALs under classification consideration.

To use the EAL flowcharts or wallcharts, follow this sequence:

ECG ASSESS the event and/or plant Operator assesses the initial conditions, Section conditions and DETERMINE which and determines that S1, Loss Of AC 8.4.1 ECG-EAL Group/Section is most Power, and S3, ATWS/Criticality are appropriate. appropriate ECG sections.

Page 4 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG REVIEW EAL categories and Operator refers to Flowchart Diagrams Section subcategories on the appropriate and/or Wallcharts and identifies that the 8.4.2 flowcharts/wallcharts. Initial Conditions for EALs SS1.1, SG1.1, and SA3.1 are related to the event that has occurred.

ECG If using the ECG - EAL flowcharts, for Section each applicable subcategory, 8.4.3 REVIEW EALs in the subcategory beginning with the lowest emergency classification level to the highest classification level (left to right).

ENSURE all pages of a particular subcategory being considered are reviewed.

ECG If using the ECG - EAL Wallcharts, Section for each applicable subcategory, 8.4.4 REVIEW EALs in the subcategory beginning with the highest emergency classification level to the lowest classification level (left to right).

Page 5 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG If in OPCON 1, 2 or 3, also REVIEW Section the Fission Product Barrier (FPB)

Table: N/A 8.4.5 ECG EXAMINE the FPB categories in the Operator refers to FPB Table and Section left column of the table. identifies that the Initial Conditions do 8.4.5.a not meet any FPB Table thresholds.

ECG SELECT the category that most likely N/A Section coincides with event conditions.

8.4.5.b ECG REVIEW all thresholds in this Section category for each fission product N/A 8.4.5.c barrier.

Page 6 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG For each threshold that is exceeded, Section IDENTIFY its point value and 8.4.5.d DETERMINE the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Bases, Attachment 1).

N/A If sum Classify Emergency Action Levels Refer to is: as: (EALs) ECG ATT#

UNUSUAL ANY loss or ANY potential loss 1

2, 3 EVENT of Containment (NOTE 1)

ANY loss or ANY potential loss ALERT 2 4, 5 of either Fuel Clad or RCS Loss or potential loss of ANY SITEAREA 3 6-11 two barriers EMERGENCY Loss of ANY two barriers GENERAL 4 12,13 ANDLoss or potential loss of the EMERGENCY third barrier Page 7 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

FPB The Primary Containment Barrier Operator reads NOTE.

Table should not be declared lost or NOTE potentially lost based on exceeding 1

Technical Specification action statement criteria, unless there is an event in progress requiring mitigation by the Primary Containment barrier.

When no event is in progress (Loss or Potential Loss of either Fuel Clad and/or RCS barrier) the Primary Containment Barrier status is addressed by Technical Specifications.

Page 8 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG REVIEW the associated EALs as Section compared to the event and SELECT 8.4.6 the highest appropriate emergency. If identification of an EAL is questionable refer to paragraph 8.1 above.

If there is any doubt with regard to assessment of a particular EAL, the Operator reviews the EALs in section S, ECG EAL Technical Bases Document and determines that EAL # SS1.1 is the should be reviewed. Words contained highest emergency action level met or in an EAL that appear in uppercase exceeded (SITE AREA EMERGENCY).

and bold print (e.g., VALID) are defined at the end of the bases for the particular EAL or in ECG - EAL Time Declared ________.

Technical Basis Document, Attachment 3, EP-HC-111-232, EAL Definitions. Words or numbers contained in an EAL that are in bold print but not uppercase are EAL threshold values (e.g., 15 minutes).

Page 9 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG If an EAL has been exceeded, equal Section level EALs or lower level EALs are 8.4.7 not required to be seperately reported as long as the applicable information Examiner Note: Filling out the NRC is communicated to the NRC using Data Sheet is beyond the scope of this ECG Attachment 5, EP-HC-111-F5, JPM.

NRC Data Sheet & Completion Reference.

ECG When the Shift Manager (SM) is the Section Emergency Coordinator, the Shift 8.4.8 Technical Advisor (STA) is responsible to perform an independent verification of the EAL IF time permits, classification. The STA verification THEN Operator requests STA/IA does not alleviate the requirement of verification of classification.

the SM to make a timely Examiner Note: Due to time spent classification. Should the SM fill the assessing and/or nature of JPM STA role, independent verification of administration, Operator may not the EAL classification will be request a verification.

delegated to another on-shift SRO, the Independent Assessor.

Page 10 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE IF the Operator requests the STA/IA to independently verify the EAL Classification, THEN INFORM the Operator the N/A STA/IA is not available.

ECG IDENTIFY and IMPLEMENT the Section referenced ECG form based on the 8.4.9 Emergency Classification Level.

• Unusual Event Implement EP-HC-111-F1

• Alert Implement EP-HC-111-F2 Operator identifies and implements EP-HC-111-F3 Attachment 3 Site Area

• Site Area Emergency Implement EP-HC-111-F3 Emergency.

• General Emergency Implement EP-HC-111-F4

• Unusual Event (Common Site) Implement EP-HC-111-F24 ECG I. EMERGENCY COORDINATOR Att. 3 (EC) LOG SHEET ECG CLASSIFICATION Att. 3.

A ECG CALL communicators to the Control Operator calls communicators to the Att. 3 Room. Control Room.

1.

Page 11 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE After 2 minutes, report as the N/A communicators and give your name as CM1 and CM2.

ECG If a security event is in progress, Att. 3 THEN, IMPLEMENT the prompt

2. Operator determines this step is not actions of NC.EP-EP.ZZ-0102, EC applicable.

Response, Attachment 10, prior to classification.

ECG As time allows, OBTAIN Classification Att. 3 IF time permits, Independent Verification (ensure THEN Operator requests STA/IA 3.

verifier understands the EAL verification of classification.

assessment clock is running); Examiner Note: Due to time spent

• STA or designee performs assessing and/or nature of JPM Independent Verification for administration, Operator may not SM request a verification.

• SM or designee performs Independent Verification for EDO

• EDO or designee performs Independent Verification for ERM Page 12 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE IF the Operator requests the STA/IA to independently verify the EAL Classification, THEN INFORM the Operator the N/A STA/IA is not available.

ECG While classification verification is in Operator commences filling out ICMF.

Att. 3 progress and if time allows, 4.

COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

ECG After classification verification and Operator declares a Site Area Att. 3 before 15 minute EAL assessment Emergency, places the EAL # SS1.1,

5. time and date in the appropriate spots clock expires, DECLARE a SITE AREA EMERGENCY at Hope Creek. in Attachment 3, and initials the step as the EC.

EAL #(s) ______, ______, _______

Examiners Note: ENTER the DECLARED AT _____ hrs on ______ declaration time that the operator time date entered on Att. 3. The difference between the START TIME and the DECLARED AT TIME is the first critical time (15 min.) Initialing the step is not critical.

Page 13 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG NOTIFICATIONS Att. 3 B.

ECG ACTIVATE ERO Emergency Callout Operator activates the ERO per posted Att. 3 per posted instructions titled: instructions titled Training Use B.1. Emergency Callout Activation.

Emergency Callout Activation (EP96-003) Examiner Note: ENSURE the operator is using the Simulator Training Activation instructions.

ECG COMPLETE the INITIAL CONTACT Operator Completes the ICMF.

Att. 3 MESSAGE FORM (ICMF) (last page Examiners Note: See the attached B.2.

of this attachment). ICMF for an example of what the form should look like when filled out properly.

Note that the exact words do not have to be in the DESCRIPTION OF EVENT, but the description must convey the sense of the Initiating Condition for EAL SS1.1. The operator may place the Examiners name as the Communicator or tell the Examiner to place his/her name as the Communicator.

Page 14 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG IF time allows, OBTAIN an accuracy Att. 3 peer check of the completed ICMF. Operator requests a Peer Check of the B.3. completed ICMF.

CUE IF the Operator requests a Peer Check, THEN INFORM the Operator a Peer Check has been performed as N/A requested.

ECG PROVIDE the ICMF to the Primary Att. 3 Communicator (CM1) and DIRECT Operator provides the ICMF to CM1 B.4. the Communicator to implement ECG and directs implementation of Att.6.

Attachment 6.

CUE LOG the time the ICMF is provided to CM1.

Examiners Note: The difference LOG TIME: _____________ between the DECLARED AT TIME Role-play as CM1 and repeat back and this LOG TIME is the second the direction as given. critical time (13 min.)

Page 15 of 21

TQ-AA-106-0303 JPM: 2013 NRC SRO A-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative Duties/Reporting Requirements TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ECG DIRECT the Secondary Operator directs CM2 to implement Att.

Att. 3 Communicator (CM2) to implement 8 for a SITE AREA EMERGENCY.

B.6.

ECG Attachment 8 for a SITE AREA EMERGENCY.

CUE ROLE-PLAY as CM2 and REPEAT BACK the direction as given. N/A CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Operator declares a Site Area N/A TASK STANDARD:

Emergency IAW ECG SS1.1, and makes notifications within identified Critical Times.

Page 16 of 21

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC SRO A-5 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition TASK NUMBER: 2000500302/2000020505 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 17 of 21

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Not Required X Todays Time Todays Date SS1.1 Loss of Power to All Vital Buses X

332 21 Initials

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC SRO A-5 Rev # Date Description Validation Required?

1 6/10/13 Revise Initiating conditions for use on NRC exam Y 2 7/1/13 Removed and has two time critical tasks from cue sheet and N added clarifying examiner note.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC SRO A-5 REV#: 02 TASK: Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition Prior to each JPM use verify the revision of the procedure(s) referenced by the JPM

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: SRO Jim Sotherton SRO On File 6-10-13 Name Qual Signature Date Laura Myers SRO On File 6-25-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 100% power with the AD483 inverter isolated to its backup AC supply.

2. Then, a Loss of Offsite Power occurred.

3. All Emergency Diesel Generators have failed to start and all vital buses are de-energized.

4. Due to a loss of rod position indication, the Control Room was unable to verify the reactor shutdown, and EOP-101A is being implemented.

5. The following conditions exist:

• A, C, and E APRMs are de-energized

• B, D, and F APRMS are reading 0% power.

• RCIC is injecting.

• RPV Level is -80, rising after reaching a minimum value of -90

• RPV pressure is 900# being controlled with SRVs.

6. Efforts to energize the Vital buses have been unsuccessful; maintenance has reported that they should be able to restore the B EDG to service in one hour.

7. The current 33 ft. elevation wind direction is from 332° at 21 mph.

8. Plant Effluents: 1.10 E+01µCi/Sec Noble Gas & 1.30 E-01 µCi/Sec I-INITIATING CUE:

Based on this information, classify this event and make the initial notifications.

This is a Time Critical Task.

Time zero for this event is now.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 JPM NUMBER: 2013 NRC P-1 REV #: 02 SAP BET: NOH05JPBC07E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-10-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC P-1 REV: 02 SYSTEM: Residual Heat Removal TASK NUMBER: 2000490504 TASK: Align Fire Water System For Alternate RPV Injection ALTERNATE PATH: K/A NUMBER: 295031 A1.08 IMPORTANCE FACTOR: 3.8 3.9 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP-EO.ZZ-0310 Rev. 7 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0310 EOP-310 equipment located in EOP locker on E1.102' Diesel Bldg. Key(s) specified in section 4.0 of HC.OP-EO.ZZ-0310.

ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 16

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 INITIAL CONDITIONS:

1. A Station Blackout has occurred due to severe weather conditions.

2. The reactor is shutdown; all control rods are in.

3. A, C, and D Emergency Diesel Generators have failed to start.

4. B Emergency Diesel Generator has started and loaded onto its respective bus.

5. B RHR pump has tripped on overcurrent and cannot be started.

6. The Diesel Driven Fire pump has started and is operating properly.

7. Due to severe weather conditions, the DG building watertight doors are not accessible.

INITIATING CUE:

Lineup for alternate injection using Fire Water IAW HC.OP-EO.ZZ-0310.

Use the local fire hose station isolation valve as the supply of Fire Water.

The Reactor Building EO is standing by to assist as necessary.

Page 3 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-0310 Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator N/A that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1.1.

Page 4 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

EQUIPMENT REQUIRED Key # (G1) for EOP Locker on El.

102 diesel bldg. From either: Operator obtains the following required equipment:

o SM office or o From EOP Locker in OSC (Use Key #(G1) for EOP Locker on El.102 Key #9 obtained from SM office or diesel bldg. From either:

by breaking red key holder glass in OSC). o SM office or o From EOP Locker in OSC (use key AND #9 obtained from SM office or by breaking red key holder glass in Equipment located in EOP locker on OSC)

El.102 diesel bldg.

Equipment located in EOP locker on El Contents: 102 diesel bldg.

1- 2.5 hose to flange adapter Examiner Note: After operator has 1- 1.5 hose to flange adapter demonstrated ability to obtain 150 of 2.5 Fire Hose 50 of 1.5 Fire Hose (for Fire Hose required equipment, ensure that the Station) equipment is returned to its 2- 1-1/16 Box Wrenches appropriate storage location.

2- Fire Hose Wrenches 1- Hydrant Wrench 5.1.1 ENSURE all prerequisites of Section Operator ensures that all prerequisites 2.1 are satisfied. have been satisfied.

Page 5 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

CUE IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

5.1.2 CONNECT hose to the appropriate Operator accesses the EOP locker and flange adaptor AND TIGHTEN. identifies the 1.5" fire hose and correct adapter.

o 1.5" hose and adapter for fire hose Examiner Note: Based on the Initiating station Cue, Operator determines the 1.5" hose and adapter is the correct equipment.

o 2.5" hose and adapter for yard fire From this point on, actions will be hydrant or fire truck simulated. The installed white hose on the Fire Hose Station is NOT the correct hose for this task.

CUE Once the operator identifies the correct equipment, INFORM the Operator the remainder of the JPM N/A will be simulated.

Operator connects the correct hose to

• the correct adapter.

Page 6 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation) 5.1.3 REMOVE fire hose fill connection

• Y N STAR Operator removes the four bolts on the blank flange on 1-BC-V426 (local, 1-BC-V426 blank flange. (Bolts Diesel Building, Elev. 102', see removed and re-installed using the 1-Attachment 2) AND INSTALL hose to 1/16" Box wrenches).

flange adapter.

Operator removes the blank flange.

• CUE The flange you indicated is removed.

Operator installs the 1.5" hose to flange

• adapter using the same four bolts.

(Bolts removed and re-installed using the 1- 1/16" Box wrenches).

CUE The hose to flange adapter has been installed in the place you indicated.

Page 7 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation) 5.1.4 CONNECT fire hose to one of the following sources of Fire Water:

Operator removes installed Fire Station o Fire Hose Station hose from standpipe.

o Yard Fire Hydrant o Fire Truck Operator installs free end of 1.5" fire

• hose to the Fire Hose Station standpipe.

CUE The fire hose has been connected to the fire water source stated.

Page 8 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation) 5.1.5 OPEN one of the following as

• applicable:

o Fire Hose Station Isolation Operator opens the Fire Hose Station Valve Isolation Valve.

o Fire Hydrant Line Valve (side) and Plug Valve (top) o Fire Truck Valves CUE The valve you have indicated is open, flow noise can be heard past the valve and the fire hose is swelling.

5.1.6 In the South-east corner of the Rx

• Y N 3-Way Operator contacts RB Equipment Communications Bldg, Elev. 102', OPEN breaker 52- Operator and directs the opening at 222082. breaker 52-222082.

CUE As the RB Equipment Operator, report that breaker 52-222082 has been opened.

Page 9 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation) 5.1.7 OPEN 1-BC-V426, SSWS Sup to

• Y N STAR RHR Fire Hose Fill Conn Sup Vlv (local, diesel truck bay, elevation 102 Operator opens 1-BC-V426.

inside stairway door - see Attachment 2).

Examiner Cue: The valve you indicated is open; flow noise can be heard past the valve.

5.1.8 Operator requests that the Control

• Y N 3-Way OPEN BC-HV-F075, SSWS TO RHR Communications LOOP B SUP MOV (panel 10C650). Room operator open BC-HV-F075.

CUE Acknowledge messages from the operator and report that BC-HV-F075 has been opened.

Page 10 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Align Fire Water System For Alternate RPV Injection

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Operator lines up for alternate injection N/A TASK STANDARD:

using Fire Water IAW HC.OP-EO.ZZ-0310 using the local fire hose station isolation valve as the supply of Fire Water.

Page 11 of 16

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC P-1 TASK: Align Fire Water System For Alternate RPV Injection TASK NUMBER: 2000490504 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 12 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Simulator setup instructions: (if required):

JPM NUMBER: 2013 NRC P-1 REV#: 2 I. INITIAL CONDITIONS:

I.C.

Initial PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description EVENT TRIGGERS:

Initial ET # Description EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 13 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC P-1 Rev # Date Description Validation Required?

2 7/1/2013 Changed Rev number for consistency with rest of exam. No N changes between Rev 1 and Rev 2.

Page 14 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC P-1 REV#: 2 TASK: Align Fire Water System For Alternate RPV Injection

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date Page 15 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A Station Blackout has occurred due to severe weather conditions.

2. The reactor is shutdown; all control rods are in.

3. A, C, and D Emergency Diesel Generators have failed to start.

4. B Emergency Diesel Generator has started and loaded onto its respective bus.

5. B RHR pump has tripped on overcurrent and cannot be started.

6. The Diesel Driven Fire pump has started and is operating properly.

7. Due to severe weather conditions, the DG building watertight doors are not accessible.

INITIATING CUE:

Lineup for alternate injection using Fire Water IAW HC.OP-EO.ZZ-0310.

Use the local fire hose station isolation valve as the supply of Fire Water.

The Reactor Building EO is standing by to assist as necessary.

Page 16 of 16

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Emergency Diesel Generator TASK: Manual Emergency Start of EDG from the Remote Panel TASK NUMBER: 2640170404 JPM NUMBER: 2013 NRC P-2 REV #: 3 SAP BET:

ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-10-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

STATION: Hope Creek JPM NUMBER: 2013 NRC P-2 REV: 02 SYSTEM: Emergency Diesel Generator TASK NUMBER: 2640170404 TASK: Manual Emergency Start of EDG from the Remote Panel ALTERNATE PATH: K/A NUMBER: 264000 A2.09 IMPORTANCE FACTOR: 3.7 4.1 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP-AB.ZZ-0135 Rev. 38 TOOLS, EQUIPMENT AND PROCEDURES:

HC.OP-AB.ZZ-0135 Rev. 38 Key #51 - KIRK - (work control)

ESTIMATED COMPLETION TIME: 20 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 16

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

NAME:

DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel TASK NUMBER: 2640170404 INITIAL CONDITIONS:

1. An earthquake and Loss of Coolant Accident have occurred.

2. The Aux Bldg Operator has been called to the Control Room to perform Communicator duties.

3. The Reactor is shutdown. All rods are full in.

4. Emergency Diesel Generator AG400 has failed to automatically start and will not start from the Control Room.

5. HC.OP-AB.ZZ-0135 is being implemented.

INITIATING CUE:

You are an extra Operator.

Start & Load to bus the A Emergency Diesel Generator AG400 from the Remote Panel 1A-C423 (El. 130') IAW AB.ZZ-0135 Att.6.

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.

Page 3 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

START TIME: Operator obtains the correct procedure.

Operator obtains procedure HC.OP-AB-ZZ-0135. ATT.6 EQUIPMENT REQUIRED Operator obtains Key #51 - KIRK -

Diesel Eng Takeover/Local Cont. (Work Key #51 - KIRK - Diesel Eng Control)

Takeover/Local Cont. (Work Control)

After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator reviews Note and Caution Note and caution reviewed 1.0 OBSERVE that READY FOR AUTO Operator observes the READY FOR START is ON AUTO START is on.

(Panel 1A(B,C,D)-C423 El. 130). Examiner Cue: The light identified is illuminated.

The operator then initials the appropriate procedure step.

Page 4 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation) 2.0 OBSERVE that Control is transferred Operator requests that the Control to Remote Panels through one of the Room press the REMOTE push button following: for AG400.

• PRESS REMOTE PB Examiner Cues:

AND ENSURE (10C651E). IF the operator requests the Control REMOTE light is ON. Room to press REMOTE, THEN OR respond as the Control Room you are NOT able to transfer the AG400 to Remote control. REMOTE push button for AG400 has been depressed and the REMOTE light is NOT on.

IF the operator requests the status of the local indications THEN inform them:

• On the 423 panel the Main Control Room has Control light is illuminated and the Remote Engine Panel has Control light is extinguished.

• On the 422 panel, the Main Control Room has Control lights are illuminated and the Remote Generator Panel has Control lights are extinguished.

OR Page 5 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• 2.0

• OBTAIN key #51 - KIRK - Diesel Operator obtains key #51 from WCC, Emg Takeover/Local Cont., from unlocks the AG400 EMERGENCY Work Control Center TAKE-OVER Switch, and places the AND PLACE EMERGENCY AG400 EMERGENCY TAKE-OVER TAKE-OVER Switch in Switch in EMERG position EMERG position. The operator then initials the appropriate procedure step.

Examiner Cues:

The switch identified is in the stated position.

IF the operator requests the status of the local indications THEN tell them:

• On the 423 panel the Main Control Room has Control light is extinguished and the Remote Emergency Takeover light is illuminated.

• On the 422 panel, the Main Control Room has Control AND Emergency Takeover in Normal lights are extinguished. The Remote Emergency Takeover light is illuminated.

Page 6 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• 3.0 PLACE REMOTE ENGINE Operator places the AG400 REMOTE CONTROL in START ENGINE CONTROL in START.

(Panel 1A(B,C,D)-C423 El. 130).

EXAMINER NOTE: The following cues are dependent upon correct step performance. Cue appropriately.

EXAMINER CUE: On panel 1AC423:

1. The Diesel Engine can be heard starting.

2. Engine Stopped indicator is extinguished The operator then initials the appropriate procedure step.

4.0 OBSERVE the following: Operator observes: GENERATOR FREQUENCY indicates about 60 Hz.

• GENERATOR FREQUENCY indicates about 60 Hz. Examiner Cue: The indicator identified indicates 60 Hz.

The operator then initials the appropriate procedure step.

• GENERATOR VOLTS indicates GENERATOR VOLTS indicates about about 4160 Volts. 4160 Volts.

Examiner Cue: The indicator identified indicates 4160 volts.

The operator then initials the appropriate procedure step.

Page 7 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation) 5.0 OBSERVE the status of the following Operator observes:

indicating lights JACKET WATER HEATER OFF light is (Panel 1A(B,C,D)-C423 El. 130). illuminated and JACKET WATER

• JACKET WATER HEATER is HEATER ON light is extinguished.

OFF. Examiner Cue: The JACKET WATER HEATER OFF light is illuminated and JACKET WATER HEATER ON light is extinguished.

The operator then initials the appropriate procedure step.

• LUBE OIL KEEPWARM HEATER Operator observes:

is OFF. LUBE OIL KEEPWARM SYSTEM HEATER OFF light is illuminated and LUBE OIL KEEPWARM SYSTEM HEATER ON light is extinguished.

Examiner Cue: The LUBE OIL KEEPWARM SYSTEM HEATER OFF light is illuminated and LUBE OIL KEEPWARM SYSTEM HEATER ON light is extinguished.

The operator then initials the appropriate procedure step.

Page 8 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• JACKET WATER KEEPWARM Operator observes:

PUMP is OFF. JACKET WATER KEEPWARM PUMP OFF light is illuminated and JACKET WATER KEEPWARM PUMP ON light is extinguished.

Examiner Cue: JACKET WATER KEEPWARM PUMP OFF light is illuminated and JACKET WATER KEEPWARM PUMP ON light is extinguished.

The operator then initials the appropriate procedure step.

• GENERATOR SPACE HEATER is Operator observes:

OFF. GENERATOR SPACE HEATER OFF light is illuminated and GENERATOR SPACE HEATER ON light is extinguished.

Examiner Cue: GENERATOR SPACE HEATER OFF light is illuminated and GENERATOR SPACE HEATER ON light is extinguished.

The operator then initials the appropriate procedure step.

Page 9 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• DIESEL RUNNING - NOT DIESEL RUNNING - NOT LOADED is LOADED is ON. on.

Examiner Cue: The light identified is illuminated.

The operator then annotates the appropriate procedure step.

Page 10 of 16

TQ-AA-106-0303 JPM: 2013 NRC P-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 03 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Diesel Generator TASK: Manually Emergency Start A Diesel Generator From The Remote Panel STEP COMMENTS

• STEP

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

1. NO. STANDARD

(#Denotes a Sequential Step) S/U evaluation)

• 6.0

• ENSURE that the respective bus ENSURE that bus infeed breakers infeed breakers are OPEN, A 52-40101 / 52-40108

1. are OPEN, THEN PLACE Generator Breaker Control Switch, THEN PLACES Generator Breaker at Panel(s) 1A(B,C,D)-C422 to Control Switch, CLOSE. ____ at Panel(s) 1AC422 to CLOSE.

EDG INFEED BREAKERS A 52-40101 / 52-40108 B 52-40201 / 52-40208 Examiner Cue for observing indications for infeed breakers open C 52-40301 / 52-40308 The green light is on, the red light is D 52-40401 / 52-40408 extinguished.

Examiner Cue for observing Generator Breaker Control Switch to CLOSE:

STOP TIME:_________

The control switch you identified has been re-positioned.

The breaker Red light is lit and the Green light is extinguished TASK STANDARD: Operator starts and loads to bus the A Emergency Diesel Generator AG400 from the Remote Panel 1A-C423 (El.

130') in accordance with HC.OP-AB.ZZ-0135 Att.6.

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Page 11 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

SYSTEM: Emergency Diesel Generator TASK: 2013 NRC P-2 Manual Emergency Start of A Diesel Generator From The Remote Panel TASK NUMBER: 2640170404 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 12 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Simulator Setup Instructions (if required): N/A JPM NUMBER: 2013 NRC P-2 REV#: 2 I. INITIAL CONDITIONS:

I.C.

Initial PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description EVENT TRIGGERS:

Initial ET # Description EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 13 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC P-2 Rev # Date Description Validation Required?

1 6-10-13 Formatting, Initiating Cue Changes - use on NRC exam Y 2 7-1-13 Clarified examiner cue in Step 6. N 3 7-6-13 Editorial verbage in cue N Page 14 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC P-2 REV#: 3 TASK: Manual Emergency Start of EDG from Remote Panel

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date Page 15 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. An earthquake and Loss of Coolant Accident have occurred.

2. The Aux Bldg Operator has been called to the Control Room to perform Communicator duties.

3. The Reactor is shutdown. All rods are full in.

4. Emergency Diesel Generator AG400 has failed to automatically start and will not start from the Control Room.

5. HC.OP-AB.ZZ-0135 is being implemented.

INITIATING CUE:

You are an extra Operator.

Start & Load to bus the A Emergency Diesel Generator AG400 from the Remote Panel 1A-C423 (El. 130') IAW AB.ZZ-0135 Att.6.

Page 16 of 16

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 JPM NUMBER: 2013 NRC P-3 REV #: 2 SAP BET: NOH05JPBF04E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-10-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC P-3 REV: 2 SYSTEM: Control Rod Drive Hydraulics TASK NUMBER: 2000430504 TASK: Manually Vent SCRAM Air Header ALTERNATE PATH: K/A NUMBER: 295037 A1.05 IMPORTANCE FACTOR: 3.9 4.0 APPLICABILITY: RO SRO EO X RO X STA SRO X EVALUATION SETTING/METHOD: Plant/Simulate

REFERENCES:

HC.OP-EO.ZZ-0306 Rev. 5 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0306, Pipe wrench ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 INITIAL CONDITIONS:

1. The plant has experienced an ATWS

2. The Scram Air Header has failed to vent.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Manual insertion of control rods from the Control Room IAW HC.RE-AB.ZZ-0001, Transient Plant Conditions in Response to an ATWS, is in progress.

INITIATING CUE:

Manually vent the Scram Air Header IAW HC.OP-EO.ZZ-0306.

Page 3 of 13

TQ-AA-106-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-0306.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, N/A THEN INFORM operator that all are satisfied.

CUE IF excessive time is taken reviewing prerequisites, N/A THEN INFORM operator that all are satisfied.

Page 4 of 13

TQ-AA-106-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation) 4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:

4.1 Key #9 for EOP Locker in OSC (obtain from OS office or break red Key #9 from SM office or key from key holder glass in OSC) break glass key holder in OSC for OSC EOP locker AND AND EOP-306 Implementation kit (EOP Locker in OSC) EOP-306 Implementation Kit from EOP Locker in OSC.

Contents: 1 14" Pipe Wrench 1 Wire Cutter Examiner Note: Obtaining a pipe wrench from an alternate location is 1 Flashlight considered satisfactory completion of this step. After operator has demonstrated ability to obtain the required equipment, ensure that the equipment is returned to its appropriate storage location.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.1 CUE If at any time the operator requests permission to use section 5.2, DENY permission due to ongoing Control Room actions to manually N/A insert control rods with RMCS.

Page 5 of 13

TQ-AA-106-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

NOTE All operations are performed locally at the CRD Flow Control Area, Rx Bldg Operator reads NOTE.

Elev. 102'.

Y N STAR 5.1.1 UNLOCK AND CLOSE 1BFV-073 Operator simulates removing the lock *

//B/U SCRAM PILOT VLVS AIR SUP from 1BFV-073.

VLV//. #

CUE The locking device has been N/A removed.

Y N STAR Operator simulates closing 1BFV-073

• by turning valve handwheel clockwise until coming to a hard stop.

CUE The valve you indicated is in the N/A position stated.

UNCAP AND OPEN 1BFV-802 //ARI Y N STAR 5.1.2 VLVS AIR SUP HDR DRN VLV//

Operator simulates removing the cap

• from 1BFV-802 by using the pipe between the scram air header ARI wrench and rotating the cap in the #

valves.

counter-clockwise direction until the cap comes off.

CUE The cap device has been removed. N/A Y N STAR Operator opens 1BFV-802 by turning

• valve handwheel counter-clockwise until coming to a hard stop.

Page 6 of 13

TQ-AA-106-0303 JPM: 2013 NRC P-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header

(* Denotes a Critical Element

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

• ELEMENT S/U evaluation)

CUE The valve you indicated is in the N/A position stated. Air can be heard flowing from the drain opening.

5.1.3 OBSERVE PI-R013 SCRAM AIR HEADER PRESSURE (10-C-264 Operator observes pressure reading on panel at the CRD flow control panel)

PI-R013 on panel 10C264.

to verify the air header fully depressurizes.

CUE The gauge you have indicated is reading zero.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator manually vents the Scram Air Header in accordance with HC.OP-EO.ZZ-0306.

Page 7 of 13

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC P-3 TASK: Manually Vent SCRAM Air Header TASK NUMBER: 2000430504 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 2013 NRC P-3 REV#: 2 I. INITIAL CONDITIONS:

I.C.

Initial PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description EVENT TRIGGERS:

Initial ET # Description EVENT ACTION:

1 COMMAND:

PURPOSE:

Page 9 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

JPM NUMBER: 2013 NRC P-3 REV#: 2 MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

I/O OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

--- --- NONE --- ---

Page 10 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC P-3 Rev # Date Description Validation Required?

2 7-1-13 Minor grammatical change to cue sheets N Page 11 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC P-3 REV#: 2 TASK: Manually Vent SCRAM Air Header

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date Page 12 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced an ATWS

2. The Scram Air Header has failed to vent.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Manual insertion of control rods from the Control Room IAW HC.RE-AB.ZZ-0001, Transient Plant Conditions in Response to an ATWS, is in progress.

INITIATING CUE:

Manually vent the Scram Air Header IAW HC.OP-EO.ZZ-0306.

Page 13 of 13

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation TASK NUMBER: 2020080101 JPM NUMBER: 2013 NRC S-1 REV #: 2 SAP BET: NOH05JPBB03E ALTERNATE PATH: X APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 7/1/13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-1 REV: 2 SYSTEM: Reactor Recirculation TASK NUMBER: 2020080101 TASK: Perform Scoop Tube Positioner Lock-up Operation ALTERNATE PATH: X K/A NUMBER: 202002 A2.05 IMPORTANCE FACTOR: 3.1 3.1 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.RPV-0001, Rev 12 HC.OP-SO.BB-0002, Rev 78 TOOLS, EQUIPMENT AND PROCEDURES: Annotated copy of HC.SO.BB-0002.

ESTIMATED COMPLETION TIME: 25 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 12

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation TASK NUMBER: 2020080101 INITIAL CONDITIONS:

1. The plant was at 80% Reactor Power with power ascension in progress.

2. The SPRI guidance is valid.

3. A control signal failure caused the A Reactor Recirc Pump Motor/Generator Scoop Tube to lock-up.

4. The A Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation IAW HC.OP-SO.BB-0002.

5. I&C has repaired the control signal failure.

6. An NCO is stationed at the A Reactor Recirc Pump Motor/Generator Scoop Tube Positioner.

7. Manual adjustment of the A Reactor Recirc Scoop Tube has been terminated.

8. The A Reactor Recirc Scoop Tube Positioner Power Switch is ON.

INITIATING CUE:

Reset the Scoop Tube lockup on the A Reactor Recirc pump IAW HC.OP-SO.BB-0002.

Page 3 of 12

TQ-AA-106-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines correct beginning Operator determines beginning step step to be HC.OP-SO.BB-0002. Step of the procedure.

5.9.1 ENSURE all prerequisites have been Operator ensures prerequisites are satisfied IAW Section 2.9. satisfied.

5.9.1 Page 4 of 12

TQ-AA-106-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.9.2 Using Attachment 3, Operator determines the desired

• DETERMINE the desired SIC-R621A SPEED DEMAND to be SIC-621A(B) SPEED DEMAND 58-62% IAW Attachment 3.

for the actual SPEED indicated on Examiner Note: The target SPEED SIC-621A(B). DEMAND is 60%. Some leeway has been added for meter readability and the potential interpolation of Attachment 3 data.

5.9.3 PRESS SIC-R621A(B) SPD CONT Operator presses the SIC-R621A

• INCREASE OR DECREASE LOOP A SPD INCR and/or DECR pb pushbutton as necessary to obtain the until SIC-R621A SPEED DEMND #

desired SIC-621A(B) SPEED matches the SPEED DEMAND from DEMAND from Step 5.9.4. Step 5.9.4.

Examiner Note: + 2% of the operator determined desired value is acceptable.

For example, if the operator determined 52% was desired, 50-54% would be acceptable.

5.9.4 PRESS SCOOP TUBE TRIP RESET Operator presses the Pump A TRIPS

• AND ENSURE SCOOP TUBE LOCK- RESET PB.

UP light extinguishes. #

Operator observes that the SCOOP TUBE LOCK-UP light is extinguished.

Operator observes A Recirc Pump speed and Reactor power rising.

HC.OP-AB.RPV-0001 Single Reactor Recirc Pump runaway.

Page 5 of 12

TQ-AA-106-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1 PRESS the SCOOP TUBE TRIP Operator presses the Pump A SCOOP

• Pushbutton for the affected Recirc TUBE TRIP pushbutton.

Pump Controller. #

Examiner Note: The Scoop Tube may have already tripped due to control signal failure high. If the Scoop Tube is already tripped, it is not critical to push the SCOOP TUBE TRIP pushbutton.

2 REDUCE the NON-affected Reactor Operator presses the SIC-R621B

• Recirc Pump Speed to Reduce Power LOOP B SPD DECR pb until reactor to Pre-Transient value. power is 80%. #

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

(It is not necessary to observe the operator take actions for the resulting Recirc Pump vibration alarms, take local control of the scoop tube, or evaluate Tech Specs.)

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 6 of 12

TQ-AA-106-0303 JPM: 2013 NRC S-1 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Recirculation TASK: Perform Scoop Tube Positioner Lock-up Operation

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

N/A TASK STANDARD: Operator responds to a Single Recirculation Pump Runaway in accordance with HC.OP-AB.RPV-0001.

Page 7 of 12

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-1 TASK: Perform Scoop Tube Positioner Lock-up Operation TASK NUMBER: 2020080101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 8 of 12

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 80% power, MOL.

o REDUCE Reactor Recirc pump speeds to 60% (It is critical that A Recirc pump speed is 60%).

o INSERT 9B rods to 00.

PRESS the REACTOR RECIRCULATION PUMP A TRIPS SCOOP TUBE TRIP pushbutton.

ENSURE SIC-R621A AND SIC-R621B are in Manual.

REDUCE SIC-R621A Demand Output by 4% AND allow SIC-R621A SPEED DEMAND to saturate low.

ENSURE SIC-R620 MAST CONT OUTPUT A SELECT is selected.

REMOVE Crossflow from service by toggling Remote Function PP04 to Not Applied.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description INITIAL a copy of HC.OP-SO.BB-0002 Section 5.5 for the A Reactor Recirc Pump.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

ENSURE Data Collection is trending the following parameters:

• APRM Power Channel A EVENT TRIGGERS:

Initial ET # Description EVENT ACTION: rr:k5(1) >= 1.0 // A Recirc Scoop Tube Trip Reset 1 COMMAND:

PURPOSE: Triggers A Recirc Runaway EVENT ACTION:

2 COMMAND:

PURPOSE:

Page 9 of 12

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val RR08A A Recirc Pump Runaway --- --- ET-1 --- ---

REMOTE/FIELD FUNCTION

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val I/O OVERRIDE

SUMMARY

Initial Description Delay Ramp Trigger Init Val Final Val Page 10 of 12

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-1 Rev # Date Description Validation Required?

2 7/1/2013 Added procedure number to cue sheet. Moved applicant copy N of cue sheet to end of JPM. Made minor changes to examiner script.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant was at 80% Reactor Power with power ascension in progress.

2. The SPRI guidance is valid.

3. A control signal failure caused the A Reactor Recirc Pump Motor/Generator Scoop Tube to lock-up.

4. The A Reactor Recirc pump was placed in Scoop Tube Positioner Lockup Operation IAW HC.OP-SO.BB-0002.

5. I&C has repaired the control signal failure.

6. An NCO is stationed at the A Reactor Recirc Pump Motor/Generator Scoop Tube Positioner.

7. Manual adjustment of the A Reactor Recirc Scoop Tube has been terminated.

8. The A Reactor Recirc Scoop Tube Positioner Power Switch is ON.

INITIATING CUE:

Reset the Scoop Tube lockup on the A Reactor Recirc pump IAW HC.OP-SO.BB-0002.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 JPM NUMBER: 2013 NRC S-4 REV #: 2 SAP BET: NOH05JPBC15E ALTERNATE PATH: X APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-25-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-4 REV: 2 SYSTEM: Residual Heat Removal TASK NUMBER: 2050120101 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop ALTERNATE PATH: X K/A NUMBER: 205000 A4.03 IMPORTANCE FACTOR: 3.6 3.5 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-SO.BC-0002 Rev. 29 TOOLS, EQUIPMENT AND PROCEDURES: None.

ESTIMATED COMPLETION TIME: Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: 15 Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 16

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 INITIAL CONDITIONS:

1. The plant is in OPCON 4.

2. The reactor has been shutdown for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.

3. B RHR pump has been in shutdown cooling at 10,000 gpm for several hours.

4. RCS temperature is 100 °F.

5. The A SACS and SSW loops are aligned to support the evolution.

6. BC-HV-F007A and BC-HV-F027A have been tagged closed to support the evolution.

7. A flush of A RHR Loop is not required.

8. Field operators have been briefed and are standing by on location.

INITIATING CUE:

You are an extra NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

HC.OP-SO.BC-0002 is complete up to step 5.3.5.

The required shutdown cooling flow for the A RHR pump is between 9,500 -10,000 gpm.

Page 3 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains procedure HC.OP-SO.BC-0002 Operator obtains the correct procedure.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are N/A satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.3.5.

Page 4 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.5. SECURE the inservice Shutdown N/A Cooling Loop as follows:

5.3.5. ENSURE 1-BC-V262 (1-BC-V212), Operator contacts Equipment Operator A ECCS Jockey Pmp D(C) DISCH to and directs opening 1-BC-V262.

RHR Loop B(A) is LOCKED OPEN (local), AND INITIAL Attachment 1.

The valve is in the position CUE N/A requested.

NOTE Operator reads NOTE.

Steps 5.3.5.B through 5.3.5.C should be performed in rapid succession.

5.3.5. CLOSE BC-HV-F015B(A) RHR LOOP Operator presses and holds the BC-

• B B(A) RET TO RECIRC AND INITIAL HV-F015B RHR LOOP B RET TO Attachment 1. RECIRC CLSD pb.

Page 5 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.5. WHEN BC-HV-F015B(A) RHR LOOP Operator observes the BC-HV-F015B C B(A) RET TO RECIRC is fully closed, RHR LOOP B RET TO RECIRC CLSD THEN, IMMEDIATELY STOP light illuminated and OPEN is B(A)P202 RHR PUMP. extinguished.

Operator presses BP202 RHR PUMP

• STOP pb.

Page 6 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.5. CLOSE BC-HV-F006B(A) RHR PMP Operator presses the BC-HV-F006B D RHR PMP B(A) SUCT FROM RECIRC B(A) SUCT FROM RECIRC AND CLSD pb.

INITIAL Attachment 1.

Operator observes the BC-HV-F006B RHR PMP B(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished.

5.3.6. ENSURE SACS is in service to the Operator observes the HV-2512A RHR Heat Exchanger for the RHR OPEN light illuminated and CLSD light loop to be placed in service IAW extinguished.

HC.OP-SO.EG-0001(Q).

Operator observes RHR A HX SACS Flow approximately 10,000 gpm.

Page 7 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CAUTION Operator reads CAUTION.

Manual OR automatic opening of BC-HV-F007A(B) RHR PMP A(B)

MIN FLOW MOV will drain Reactor Vessel to Suppression Pool.

If BC-HV-F015 A(B) RHR LOOP A(B) RET TO RECIRC does NOT open immediately to establish flow, then the RHR pump should be secured.

BC-HV-F027A(B) RHR LOOP A(B)

SUPP POOL SPRAY HDR ISLN MOV will drain the Reactor Vessel to the Suppression Pool if opened while the associated RHR pump is in shutdown cooling.

Page 8 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.3.7. START RHR PUMP A(B)P202 AND Operator presses the AP202 START

• IMMEDIATELY THROTTLE OPEN pb.

BC-HV-F015A(B) RHR LOOP A(B)

RET TO RECIRC LOOP UNTIL FI-R603A(B) OR FR-R608A(B) - CRIDS A3137(A3139), LOOP A(B) FLOW indicates 3000 gpm.

Operator observes the AP202 START light illuminated and STOP light extinguishes.

Examiner Note: F015A will fail Operator immediately presses and closed and not establish flow. holds the BC-HV-F015A RHR LOOP A Operator should secure the pump. RET TO RECIRC LOOP OPEN pb.

Operator observes the CLSD light remains illuminated.

Operator observes the FI-R603A OR FR-R608A - CRIDS A3137, LOOP A FLOW indicates 0 gpm.

Page 9 of 16

TQ-AA-106-0303 JPM: 2013 NRC S-4 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Residual Heat Removal TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator determines CAUTION applies.

Operator presses AP202 STOP pb.

• CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Operator lines up and starts A RHR pump N/A TASK STANDARD: in Shutdown Cooling. When the F015A fails to open, the operator stops the A RHR pump.

Page 10 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-4 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop TASK NUMBER: 2050120101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 11 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to an OPCON 4 IC with B RHR in Shutdown Cooling at 10,000 gpm and an RCS temp of 100 degF.

OPEN BC-HV-F007B breaker OPEN BC-HV-F027B breaker ENSURE BC-HV-F003A is closed.

ENSURE BC-HV-F004A is closed.

ENSURE BC-HV-F007A is closed.

ENSURE EG-HV-2512A is open.

ENSURE BC-HV-F006A is open.

ENSURE associated Schedule File is loaded.

OPEN BC-HV-F007A breaker using ET-1.

OPEN BC-HV-F027A breaker using ET-2.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description PLACE red bezel covers on the BC-HV-F007B AND the BC-HV-F027B.

PLACE red bezel covers on the BC-HV-F007A AND the BC-HV-F027A.

MARK procedure HC.OP-SO.BC-0002 complete up to step 5.3.4.

Page 12 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

REMOTE SCHEDULE:

Initial @Time Event Action Description RH30 HV-F007B RHR Pump A Min Flow None None Insert remote RH30B to TAGGED Valve ET006 GROUP 3B HV-F027B RHR None None Insert remote ET006 to RACK_CLOSE Supp. Pool Spray Insert remote RH30A to TAGGED on RH30 HV-F007A RHR Pump A Min Flow None None event 1 Valve Insert remote ET005 to RACK_CLOSE ET005 GROUP 3B HV-F027A RHR None None on event 2 Supp. Pool Spray RH29 GROUP 3E HV-F015A RHR SDC None None Insert remote RH29A to FAIL_CLOSE Return Isol Page 13 of 16

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-4 Rev # Date Description Validation Required?

2 7-1-13 Grammatical changes to tear cue sheet. Updated Rev Y number of reference procedure. Added validation time.

Updated RHR flow in step 5.3.6 to update sim conditions.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-4 REV#: 2 TASK: Transfer Shutdown Cooling to the Standby Shutdown Cooling Loop

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On File 6-25-13 Name Qual Signature Date Steve Loper RO On File 6-26-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant is in OPCON 4.

2. The reactor has been shutdown for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.

3. B RHR pump has been in shutdown cooling at 10,000 gpm for several hours.

4. RCS temperature is 100 °F.

5. The A SACS and SSW loops are aligned to support the evolution.

6. BC-HV-F007A and BC-HV-F027A have been tagged closed to support the evolution.

7. A flush of A RHR Loop is not required.

8. Field operators have been briefed and are standing by on location.

INITIATING CUE:

You are an extra NCO.

Transfer RHR Shutdown Cooling to the A RHR loop.

HC.OP-SO.BC-0002 is complete up to step 5.3.5.

The required shutdown cooling flow for the A RHR pump is between 9,500 -10,000 gpm.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator TASK NUMBER: 3450030101 JPM NUMBER: 2013 NRC S-6 REV #: 02 SAP BET: NOH05JPMA02E ALTERNATE PATH: X APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-22-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-6 SYSTEM: Main Generator TASK NUMBER: 3450030101 TASK: Synchronize And Load The Main Generator ALTERNATE PATH: X K/A NUMBER: 262001 A4.04 IMPORTANCE FACTOR: 3.6 3.7 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-SO.MA-0001 Rev 57 HC.OP-AB.BOP-0002 Rev 13 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 20

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator TASK NUMBER: 3450030101 INITIAL CONDITIONS:

1. A plant startup from a forced outage is in progress.

2. The Main Generator and Transformer have been placed in standby.

3. Main Turbine is operating at 1800 rpm.

4. Unit Protection Lockout Relays (5)86UR and (5)86UB have been reset.

5. Load Dispatcher/System Operator has been notified of impending loading.

6. The Fire Water System is in-service.

7. The Switchyard has been aligned IAW Section 5.4. of HC.OP-SO.MA-0001.

8. 1EGTIC-2625 is in AUTO with setpoint at 95°F.

9. HC.OP-SO.MA-0001 is complete up to and including step 5.2.15

10. TBEO and YDEO have been briefed and are standing by to support synchronization.

INITIATING CUE:

You are an extra NCO.

Synchronize and load the Main Generator IAW HC.OP-SO.MA-0001.

Perform the initial synchronization using the 500KV BS6-5 breaker.

Maintain Load Set at 30% to support four hour soak for required testing.

Page 3 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains the correct procedure. Operator obtains procedure HC.OP-SO.MA-0001.

Operator reviews precautions and limitations. Operator reviews precautions and limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied. N/A Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.2.16 Page 4 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

NOTE Rapidly changing main generator armature currents may cause the following DEHC diagnostic alarms shortly after synchronizing the main generator to the grid:

S1_P240 <R> SLOT 17 VGEN DIAGNOSTIC ALARM S1\XVGENR0S17_A DIAG S1_P241 <R> SLOT 18 VGEN DIAGNOSTIC ALARM S1\XVGENR0S18_A DIAG S1_P242 SLOT 17 VGEN Operator reads NOTE.

DIAGNOSTIC ALARM S1\XVGENS0S17_A DIAG S1_P243 SLOT 18 VGEN DIAGNOSTIC ALARM S1\XVGENS0S18_A DIAG S1_P244 <T> SLOT 17 VGEN DIAGNOSTIC ALARM S1\XVGENT0S17_A DIAG S1_P245 <T> SLOT 18 VGEN DIAGNOSTIC ALARM S1\XVGENT0S18_A DIAG Page 5 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

C After synchronization and closing a A Generator Breaker, Load Setpoint U should be increased to 30%

T IMMEDIATELY. If the following I steps are not completed or O expected indications received, the N CRS should consider tripping the Operator reads CAUTION.

Main Turbine and ensuring the Generator is isolated from the 500 Kv System and the Turbine is coasting down.

5.2.16 PERFORM the following to synchronize the Main Generator using Manual Load Control:

SELECT Control , Speed-Load On DEHC HMI, operator selects

• Control , Speed-Load . #

Page 6 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Ramp Rate will indicate 20 %/min until NOTE breaker is closed.

Upon breaker closure, ramp rate will be 60%/min for 2 seconds (2 % load) Operator reads NOTE.

Ramp Rate will then go to setpoint entered.

5.2.16. SELECT Load Set, Ramp Rate AND On DEHC HMI, operator selects

• B ENTER 10 %/min Load Set, Ramp Rate and enters #

10 %/min.

1-XIL-6741D SYNCH WINDOW green NOTE light turns on when SYNCHROSCOPE point passes thru the 12 oclock position AND line/bus voltage is within the Operator reads NOTE.

normal operating range AND synchroscope rotation is < 3 RPM.

Page 7 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.16. SELECT Load Set, Manual Adj.: On DEHC HMI, operator selects

• C Raise OR Lower until pointer on Load Set, Manual Adj. and presses: #

SYNCHROSCOPE is moving slowly Raise OR Lower until the pointer on in the FAST direction. (10C651D) the UNIT SYNCHRONIZING SYNCHROSCOPE is moving slowly in the FAST direction.

5.2.16. IF the SYNCH WINDOW green light D does NOT turn on as described in the note above, THEN REQUEST permission from SM/CRS to bypass Operator observes SYNCH WINDOW the synch check relay AND GO TO green light turns on.

Step 5.2.17.

5.2.16. PERFORM the following (with Steps E 5.2.16.E.1 thru 5.2.16.E.3 being performed in rapid succession): N/A Page 8 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.16. WHEN the SYNCHROSCOPE Pointer Operator presses the BS 6-5 CLOSE

• E.1 is at 2 minutes before 12 Oclock pushbutton WHEN the #

position, AND the SYNCH WINDOW SYNCHROSCOPE Pointer is at 2 green light is illuminated, THEN minutes before 12 Oclock position, CLOSE BS 6-5 (BS 2-6) Breaker. AND the SYNCH WINDOW green light is illuminated.

Operator observes the 500 KV BUS BS 6-5 red BS6-5 CLOSE light illuminates and green TRIP light extinguishes.

5.2.16. Immediately SELECT Load Set, :

• E.2 Setpoint On the DEHC HMI, operator selects Load Set, : Setpoint #

AND ENTER 30 %.

and enters 30 % .

WHEN LOAD SET is raised TRIGGER ET-1. N/A Page 9 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.16. IMMEDIATELY OBSERVE the E.3 following:

• Bypass Valves close as Generator loads to 30 % Load Set On the DEHC HMI, operator observes bypass valves sequentially close.

• Generator phase current increases Operator observes Main Generator phase current increases.

• MW load and MVAR load increases Operator observes MW load and MVAR load increases.

• Synchroscope pointer steady at 12 Operator observes UNIT oclock position SYNCHRONIZING SYNCHROSCOPE pointer steady at 12 oclock position.

OHA D3-B5 TURBINE GENERATOR VIB HI OHA D3-B5 TURBINE GENERATOR Operator informs CRS of Main Turbine VIB HI received. high vibration condition.

Page 10 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE Acknowledge any RO alarm N/A reports.

Take any required actions.

CUE N/A DETERMINE bearing(s) in alarm

1. Operator reviews Alarm Response CRIDS points A2519 - A2530.

Procedure.

IF unable to determine on CRIDS OR Main Control Room System 1 computer, THEN DISPATCH an operator to Panel 10C366 to monitor vibration IAW Attachment C5-1.

Operator determines bearing #10 vibration in alarm CRIDS points A2528.

Operator dispatches an operator to the

1. 10 bearing.

CUE As Turbine Building Operator, N/A REPORT strong vibrations felt at the bearing.

Page 11 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

2. ENTER HC.OP-AB.BOP-0002(Q), Operator notifies CRS to enter HC.OP-Main Turbine. AB.BOP-0002.

CUE As CRS acknowledge operator N/A notification to enter BOP-0002.

3. IF a valid Journal Vibration exceeds RO determines Bearing #10 vibration

• the following, immediately PRESS has reached 12 mils.

Main Turbine TRIP PBs.

RO trips Main Turbine using the 2

• MAIN TURBINE TRIP pbs on 10C651D within 45 seconds of reaching 12mils.

Page 12 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

HC.OP-AB.BOP-0002 Main Turbine RETAINMENT OVERRIDE CONDITION Examiners Note:

II. Bearing 1-10 Vibration 11 mils Since reactor power is <24% the

@ 1800 RPM

• reactor SHOULD NOT be scrammed.

ROs are directed to carry out ACTION RETAINMENT OVERRIDE ACTIONS.

II.A IF Reactor Power is 24%

THEN PERFORM the following:

a. REDUCE Recirc. Pump speed to Operator trips Main Turbine using the 2 MINIMUM. MAIN TURBINE TRIP pbs on 10C651D

b. LOCK the Mode Switch in within 45 seconds of reaching 12mils.

SHUTDOWN.

II.B IMMEDIATELY TRIP the Main Turbine.

Page 13 of 20

TQ-AA-106-0303 2013 NRC S-6, Rev 2 OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator responds to Main Turbine High Vibration in accordance with HC.OP-AB.BOP-0002.

Page 14 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: MA002 TASK: Synchronize And Load The Main Generator TASK NUMBER: 3450030101 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 15 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to an IC with the Main Turbine rolling at 1800 rpm, ready to synchronize the Main Generator.

ENSURE on DEHC HMI, Turbine Load Set Ramp Rate is set at 5%.

ENSURE on DEHC HMI that any screen OTHER THAN Control , Speed-Load is selected.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description ENSURE the simulator is reset.

EVENT FILE:

Initial ET #

Event code:

1

Description:

Event code:

2

Description:

Event code:

Description:

Page 16 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Insert malfunction TU1510 to 0 in 60 None None Turbine bearing #10 vibration high on event 1 Insert malfunction TU1509 to 5.50000 None None Turbine bearing #9 vibration high in 120 on event 1 Insert malfunction TU1511 to 5.00000 None None Turbine bearing #11 vibration high in 120 on event 1 REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 17 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: MA002 Rev # Date Description Validation Required?

00 5/27/13 New JPM. Y 02 7/1/13 Added within 45 seconds of reaching 12mils to critical task. Y Deleted redundant steps in examiner guide. Moved applicant cue sheet to last page.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: MA002 REV#: 02 TASK: Synchronize And Load The Main Generator

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On File 6-25-13 Name Qual Signature Date Dave Hardin RO On File 6-24-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. A plant startup from a forced outage is in progress.

2. The Main Generator and Transformer have been placed in standby.

3. Main Turbine is operating at 1800 rpm.

4. Unit Protection Lockout Relays (5)86UR and (5)86UB have been reset.

5. Load Dispatcher/System Operator has been notified of impending loading.

6. The Fire Water System is in-service.

7. The Switchyard has been aligned IAW Section 5.4. of HC.OP-SO.MA-0001.

8. 1EGTIC-2625 is in AUTO with setpoint at 95°F.

9. HC.OP-SO.MA-0001 is complete up to and including step 5.2.15

10. TBEO and YDEO have been briefed and are standing by to support synchronization.

INITIATING CUE:

You are an extra NCO.

Synchronize and load the Main Generator IAW HC.OP-SO.MA-0001.

Perform the initial synchronization using the 500KV BS6-5 breaker.

Maintain Load Set at 30% to support four hour soak for required testing.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 JPM NUMBER: 2013 NRC S-2 REV #: 2 SAP BET: NOH05JPBE05E ALTERNATE PATH: X APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-25-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-2 REV: 2 SYSTEM: Core Spray TASK NUMBER: 2090030101 TASK: Manually Start the Core Spray System ALTERNATE PATH: X K/A NUMBER: 209001 A4.01 IMPORTANCE FACTOR: 3.8 3.7 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.ZZ-0001 Attachment 5 Rev. 25 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 15

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER: 2090030101 INITIAL CONDITIONS:

1. The plant has experienced a loss of all offsite power coincident with a small break LOCA.

2. A and C Emergency Diesel Generators have failed to start.

3. HPCI has just tripped.

4. Reactor pressure is approximately 500 psig and lowering.

5. Reactor level is approximately -70 inches and lowering.

INITIATING CUE:

Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The simulator is in FREEZE until you are ready to begin.

Page 3 of 15

TQ-AA-106-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating Operator repeats back initiating cue.

cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK Examiner Note: If applicant asks INITIATING CUE: about RHR injection control, inform START TIME: applicant that another operator will control RHR flow.

Operator obtains/locates procedure Operator obtains the correct procedure.

HC.OP-AB.ZZ-0001, Attachment 5.

1.0 IF an Initiation Signal is present, Operator determines that an Initiation THEN PERFORM the following: Signal is present based on overhead annunciators B3-A1/A2/A3/A4, CORE SPRAY PUMP AUTO START are in alarm.

1.0.A. ENSURE B Core Spray Pump is Operator observes the B Core Spray RUNNING. Pump is not running.

Operator depresses the BP206 START

• push button.

Page 4 of 15

TQ-AA-106-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator observes that B Core Spray Pump is running.

1.0.B. ENSURE D Core Spray Pump is Operator observes the D Core Spray RUNNING. Pump is not running.

Operator depresses the DP206 START

• push button.

Operator observes that D Core Spray Pump is running.

1.0.C. ENSURE HV-F015B is CLOSED. Operator observes that HV-F015B is CLOSED.

1.0.D. ENSURE HV-F004B is OPEN. Operator observes that HV-F004B is OPEN.

Page 5 of 15

TQ-AA-106-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.E. WHEN REACTOR PRESSURE is Operator observes Reactor Pressure.

< 461 psig, ENSURE HV-F005B is OPEN.

Operator observes that HV-F005B did not open with Reactor pressure below 461 psig.

1.0.F. PERFORM the following as necessary to control Reactor Level:

1.0.F. PRESS HV-F005B AUTO OPEN Operator depresses the HV-F005B 1 OVRD. AUTO OPEN OVRD pb.

Operator observes that HV-F005B AUTO OPEN OVRD illuminates.

1.0.F. CYCLE HV-F005B as necessary to Operator depresses the HV-F005B

• 2 control Reactor Level. OPEN pb.

Operator observes the HV-F005B red OPEN light illuminates and the green CLSD light extinguishes.

Page 6 of 15

TQ-AA-106-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.G. WHEN flow is > 775 gpm, ENSURE Operator observes Core Spray System HV-F031B is CLOSED. B flow on FI-R601B to be >775 gpm.

Examiner Note: HV-F031 has failed Operator observes HV-F031B is open.

to auto close.

Operator depresses the HV-F031B

• CLOSE pb.

Operator observes the HV-F031B green CLSD light illuminates and the red OPEN light extinguishes.

Page 7 of 15

TQ-AA-106-0303 JPM: 2013 NRC S-2 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Core Spray TASK: Manually Start the Core Spray System

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator restores reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop (-38 to +54).

Page 8 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-2 TASK: Manually Start the Core Spray System QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial Insert below listed malfunctions.

Take simulator out of freeze.

Place Mode Switch in Shutdown.

Inhibit ADS.

Let vessel water level drop to approximately -70 inches.

Reduce reactor pressure to approximately 500 psig.

Freeze the simulator.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code: ZDCS31CB >=1.0 4

Description:

HV-F031B Close PB pressed // Deletes stuck open min-flow valve.

Event code:

Description:

Event code:

Description:

Page 10 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction DG02A Diesel generator A failure None None Insert malfunction DG02C Diesel generator C failure None None Insert malfunction HP03 HPCI turbine trip None None Insert malfunction CS03B Core spray HV-F005B fail to auto open None None Insert malfunction CS04B Core spray pump B fail to auto start None None Insert malfunction CS04D Core spray pump D fail to auto start None None Insert malfunction EG12 on event 1 Loss of all off site power Insert malfunction RR31A1 to Recirc loop A small break [V] (10%~60 None None 10.00000 on event 2 gpm, 100%~600 gpm)

Insert malfunction RR31A2 to 0 on Recirc loop A large break [V] (10%~6000 None None event 2 gpm, 100%~60000 gpm)

Insert malfunction MS01 to 9.00000 on None None Steam line break in drywell event 3 REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote RH19B to FAIL_CLOSE RH19 HV-F017B RHR INJ VALVE None None Insert remote RH19D to FAIL_CLOSE RH19 HV-F017D RHR INJ VALVE Page 11 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

OVERRIDE SCHEDULE:

Initial @Time Event Action Description Insert override 8S29_B_LO to Off on None None HV-F031B CLOSED (LO) event 4 Insert override 8S29_C_LO to On on None None HV-F031B OPEN (LO) event 4 Page 12 of 15

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-2 Rev # Date Description Validation Required?

2 7-1-13 Added critical step (Depress HV-F031B CLOSE Pb). Updated Y validation time. Moved applicant cue sheet to final page of JPM. Added clarifying comments in examiner script.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-2 REV#: 02 TASK: Manually Start the Core Spray System

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Dave Hardin RO On File 6-25-15 Name Qual Signature Date Steve Loper On File 6-25-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced a loss of all offsite power coincident with a small break LOCA.

2. A and C Emergency Diesel Generators have failed to start.

3. HPCI has just tripped.

4. Reactor pressure is approximately 500 psig and lowering.

5. Reactor level is approximately -70 inches and lowering.

INITIATING CUE:

Restore reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop. The simulator is in FREEZE until you are ready to begin.

JOB PERFORMANCE MEASURE 2013 NRC S-7 STATION: Hope Creek SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks TASK NUMBER: 2001040501 JPM NUMBER: 2013 NRC S-7 REV #: 2 SAP BET: NOH05JPSB12E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-22-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-7 REV: 2 SYSTEM: Reactor Protection System TASK NUMBER: 2001040501 TASK: Defeat RPS Interlocks ALTERNATE PATH: K/A NUMBER: 295037 EA1.01 IMPORTANCE FACTOR: 4.6 4.6 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0320, Rev 6 TOOLS, EQUIPMENT AND PROCEDURES: EOP-320 Implementation kit ESTIMATED COMPLETION TIME: 25 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks TASK NUMBER: 2001040501 INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All scram valves have opened but the Scram Discharge Volume is full.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Draining the SDV and attempting a manual scram is required.

5. HC.OP-EO.ZZ-0302 has NOT been implemented.

6. ARI interlocks have been defeated in accordance with Section 5.1 of HC.OP-EO.ZZ-0320.

INITIATING CUE:

Defeat RPS interlocks IAW HC.OP-EO.ZZ-0320.

Page 3 of 13

TQ-AA-106-0303 JPM: SB012 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE: N/A START TIME:

Operator obtains procedure Operator obtains procedure HC.OP-EO.ZZ-0320.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

Note: If applicant checks RPS Xfer switch lights on back panels IAW prerequisites step 2.2.2, inform applicant that they are lit.

CUE If excessive time is taken reviewing N/A precautions and limitations, inform operator that all are satisfied.

Page 4 of 13

TQ-AA-106-0303 JPM: SB012 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 4.0 EQUIPMENT REQUIRED Operator obtains the following required equipment:

EOP-320 Implementation Kit (NSS office EOP Drawer) contents: EOP-320 Implementation kit from SM 1 set of fuse pullers Office Clerk Area EOP drawer.

1 flashlight OR 1 plastic bag for ARI fuses 4 banana plug jumpers OR Key #9 from OSC office or key from break glass key holder in OSC for OSC Key #9 for EOP Locker in OSC EOP locker.

(obtain from SNSS office or break red key holder glass in OSC) AND AND EOP-320 Implementation kit from EOP locker in OSC.

EOP-320 Implementation kit (EOP Locker in OSC) contents:

1 set of fuse pullers 1 flashlight 1 plastic bag for ARI fuses 4 banana plug jumpers CUE Supply operator with EOP-320 N/A implementation kit.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.2.1.

Page 5 of 13

TQ-AA-106-0303 JPM: SB012 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.1 ENSURE that Prerequisites have Operator ensures Prerequisites are been satisfied IAW Section 2.2. satisfied.

CUE If excessive time is taken reviewing N/A Prerequisites, inform operator that all are satisfied.

5.2.2 On H11-P609, front, Division 1, left

• test box, INSERT a jumper between Operator installs jumper at H11-P609 test point C71A-K10A-2A (first between test points C71A-K10A-2A and column-first row, red jack) and test C71A-K12E-2B.

point C71A-K12E-2B (fourth column-second row, black jack).

CUE IF the JPM is being simulated in the N/A Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

Page 6 of 13

TQ-AA-106-0303 JPM: SB012 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.3 On H11-P609, front, Division 3, left Operator installs jumper at H11-P609

• test box, INSERT a jumper between between test points C71A-K10C-2A test point C71A-K10C-2A (third and C71A-K12G-2B.

column-fourth row, red jack) and test point C71A-K12G-2B (fourth column-third row, black jack).

CUE IF the JPM is being simulated in the N/A Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

5.2.4 On H11-P611, front, Division 2, left Operator installs jumper at H11-P611

• test box, INSERT a jumper between between test points C71A-K10B-2A and test point C71A-K10B-2A (fourth C71A-K12F-2B.

column-fourth row, red jack) and test point C71A-K12F-2B (first column-second row, black jack).

CUE IF the JPM is being simulated in the N/A Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

Page 7 of 13

TQ-AA-106-0303 JPM: SB012 OPERATOR TRAINING PROGRAM NAME:

Rev: 05 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.5 On H11-P611, front, Division 4, left Operator installs jumper at H11-P611

• test box, INSERT a jumper between between test points C71A-K10D-2A test point C71A-K10D-2A (third and C71A-K12H-2B.

column-third row, red jack) and test point C71A-K12H-2B (fourth column-second row, black jack).

CUE IF the JPM is being simulated in the N/A Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.

WHEN operator informs you the task is N/A complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Operator defeats RPS interlock IAW N/A TASK STANDARD:

HC.OP-EO.ZZ-0320.

Page 8 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: SB012 TASK: Defeat RPS Interlocks TASK NUMBER: 2001040501 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT

TQ-AA-106-0303 JOB PERFORMANCE MEASURE I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL.

INSERT malfunction RP06.

LOCK Reactor Mode Switch in SHUTDOWN.

IMPLEMENT EOP 101A and stabilize RPV level -50 to -100 inches.

AFTER conditions stabilize, ACKNOWLEDGE all overhead and RM11 alarms.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code:

Description:

Event code:

Description:

Event code:

Description:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction RP06 RPS half core ATWS - Left Side REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: SB012 Rev # Date Description Validation Required?

01 3/26/13 Converted SB012 to new JPM format. Since Critical JPM Y actions are now uniquely identified by the format, all statements identifying critical portion of action were redundant and deleted.

This change is editorial. Updated Reference procedure revision number. Modified Malfunction, Remote, Override, and Event list sections for TREX event syntax. Added Task Standard to JPM.

Added procedure step numbers. Updated Validation Checklist to current form from TQ-AA-106-0304. Editorial change only. JPM validation times needed.

02 7/1/2013 Added Note to examiner guide. Minor grammatical changes. N Added validation time.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The plant has experienced a failure to scram.

2. All scram valves have opened but the Scram Discharge Volume is full.

3. HC.OP-EO.ZZ-0101A, ATWS-RPV Control, is being executed.

4. Draining the SDV and attempting a manual scram is required.

5. HC.OP-EO.ZZ-0302 has NOT been implemented.

6. ARI interlocks have been defeated in accordance with Section 5.1 of HC.OP-EO.ZZ-0320.

INITIATING CUE:

Defeat RPS interlocks IAW HC.OP-EO.ZZ-0320.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc TASK NUMBER: 2060180201 JPM NUMBER: 2013 NRC S-3 REV #: 2 SAP BET: NOH05JPBJ06E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X 7-1-13 DEVELOPED BY: NRC DATE:

Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-3 REV: 2 SYSTEM: High Pressure Coolant Injection TASK NUMBER: 2060180201 TASK: Place HPCI In Full Flow Recirc ALTERNATE PATH: K/A NUMBER: 206000 A4.06 IMPORTANCE FACTOR: 4.3 4.3 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-AB.ZZ-0001 Rev 25 TOOLS, EQUIPMENT AND PROCEDURES:

ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 13

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc TASK NUMBER: 2060180201 INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slowly rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-DL.ZZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode and initiate a plant cooldown with a target pressure band of 500 to 700 psig.

Page 3 of 13

TQ-AA-106-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-AB.ZZ-0001 Attachment 6.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 1.0.

1.0 IF HPCI is NOT in the Injection mode of operation PERFORM the following: N/A 1.0.A ENSURE OP216 VAC TK VACUUM Operator presses the OP216 START STAR Y N PUMP is RUNNING. pb.

Operator observes the red RUNNING light illuminates.

Page 4 of 13

TQ-AA-106-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.B ENSURE HV-F059 is OPEN. Operator presses the HV-F059 OPEN

• STAR Y N pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

1.0.C ENSURE HPCI AND RCIC Suctions are Operator observes the HPCI HV-F004 lined up to the CST. OPEN light is illuminated and green CLSD light is extinguished.

Operator observes the RCIC HV-F010 OPEN light is illuminated and green CLSD light is extinguished.

1.0.D PRESS HV-F008 INCR PB for 20 Operator presses HV-F008 INCR pb for

• STAR Y N seconds. approximately 20 seconds. #

Operator observes the HV-F008 OPEN light illuminates.

Page 5 of 13

TQ-AA-106-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.E ADJUST FIC-R600 HPCI FLOW setpoint Operator presses the LOWER

• STAR Y N to 1000 gpm. SETPOINT pb on the FIC-R600 #

controller until the pointer is on 1000 gpm.

1.0.F SIMULTANEOUSLY PERFORM the following: N/A 1.0.F. START AUXILIARY OIL PUMP Operator presses the AUXILIARY OIL

• 1 PUMP OP213 START pb. #

Operator observes the red RUNNING light illuminates.

1.0.F. PRESS FD-HV-F001 OPEN Pushbutton Operator presses the HV-F001 OPEN

• 2 pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

Page 6 of 13

TQ-AA-106-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.G IMMEDIATELY OPEN AP-HV-F011. Operator presses the AP-HV-F011

• OPEN pb. #

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

1.0.H WHEN Discharge Pressure turns Operator observes HPCI Pump STAR Y N ADJUST FIC-R600 setpoint to 3000 gpm. Discharge Pressure on PI-R601-E41 (red) indicator rises and lowers.

Operator presses the RAISE

• SETPOINT or LOWER SETPOINT pbs as necessary to obtain a flow setpoint of 3000 gpm. (~50%)

Page 7 of 13

TQ-AA-106-0303 JPM: 2013 NRC S-3 OPERATOR TRAINING PROGRAM NAME:

Rev: 2 JOB PERFORMANCE MEASURE DATE:

SYSTEM: High Pressure Coolant Injection TASK: Place HPCI In Full Flow Recirc

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 1.0.I THROTTLE HV-F008 AND ADJUST FIC- Operator presses the HV-F008 INCR or STAR Y N R600 setpoint, as necessary, up to and DECR pbs and/or RAISE SETPOINT or including full flow rate, to control HPCI LOWER SETPOINT pbs as necessary pump parameters/reactor pressure. to adjust pump parameters.

Operator observes reactor pressure lowering.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME. EXAMINER NOTE: When pressure turns and begins lowering, examiner REPEAT BACK any message from the may terminate the JPM.

operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator places HPCI in Full Flow Test at approximately rated flow.

Page 8 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: BJ006 TASK: Place HPCI In Full Flow Recirc TASK NUMBER: 2060180201 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL.

Place Mode Switch to S/D.

Stabilize RPV level at approximately 30 inches with RFPs. Do NOT allow water lvl to drop to lvl 2.

Arm and depress channels A and D NSSSS, then disarm. (Simulates spurious Group 1 isolation)

Manually initiate RCIC, runback flow controller setpoint to maintain RPV level at approximately 32 inches.

Place B RHR in Suppression Pool Cooling.

Freeze simulator.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description ENSURE Mode Switch key is removed.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET # Description Event code:

1

Description:

Page 10 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

MALFUNCTION SCHEDULE:

Initial Description Delay Ramp Trigger Init Val Final Val REMOTE SCHEDULE:

Initial Description Delay Ramp Trigger Init Val Final Val I/O OVERRIDE SCHEDULE:

Initial Description Delay Ramp Trigger Init Val Final Val Page 11 of 13

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-3 Rev # Date Description Validation Required?

2 7-1-2013 Minor grammatical and editorial changes to examiner script. N Moved applicant cue sheet to final page.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The Reactor has scrammed due to a spurious Group 1 isolation.

2. All control rods are full in.

3. RCIC was manually initiated and is injecting to the RPV.

4. Reactor water level is approximately -15 inches and slowly rising.

5. Reactor pressure is being controlled with Lo-Lo Set.

6. RHR loop B is in suppression pool cooling.

7. Another operator is taking the HC.OP-DL.ZZ-0026, Attachment 3.m, Suppression Chamber Average Water Temp 5 Minute Log.

INITIATING CUE:

Place HPCI into the Full Flow Test Mode and initiate a plant cooldown with a target pressure band of 500 to 700 psig.

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B TASK NUMBER:

JPM NUMBER: 2013 NRC S-5 REV #: 2 SAP BET:

ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 6-25-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-5 REV: 02 SYSTEM: Primary Containment TASK NUMBER:

TASK:

Suppression Chamber Makeup From Service Water Loop B ALTERNATE PATH: K/A NUMBER: 223001 A2.11 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0314 Rev. 05 TOOLS, EQUIPMENT AND PROCEDURES: HC.OP-EO.ZZ-0314 ESTIMATED COMPLETION TIME: 12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF JPM UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 14

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Primary Containment TASK:

Suppression Chamber Makeup From Service Water Loop B TASK NUMBER:

INITIAL CONDITIONS:

1. Suppression Chamber level is ~70 inches and normal means of make-up are unavailable.

2. RHR Pump BP202 is shutdown and is not required to assure adequate core cooling.

INITIATING CUE:

Restore suppression chamber level to 74-78 using Suppression Chamber Make-up from Service Water Loop B IAW HC.OP-EO.ZZ-0314.

Page 3 of 14

TQ-AA-106-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: N/A START TIME:

Operator obtains the correct Operator obtains procedure procedure. HC.OP-EO.ZZ-0314.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are N/A satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure. step to be 5.2.1.

Page 4 of 14

TQ-AA-106-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.2.1 START TIME: Operator Verifies Prerequisites.

ENSURE that all prerequisites have been satisfied IAW Section 2.2 of this procedure.

5.2.2. CLOSE BC-HV-F003B //RHR HX The operator depresses the close

• SHELL SIDE OUTLET MOV// pushbutton for BC-HV-F003B The operator observes that the CLOSED indicator illuminates and the OPEN indicator extinguishes VERIFY CLOSED BC-HV-F048B //B Operator verifies closed BC-HV-F048B 5.2.3.

RHR HX SHELL SIDE BYP MOV//

OPEN EA-HV-2238 SERVICE The operator inserts key, rotates 5.2.4

• WATER LOOP B EMERG M/U keylock to ON, and depresses the open pushbutton for EA-HV-2238. #

OUTBD ISLN (10C651).

The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes Page 5 of 14

TQ-AA-106-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

ENSURE breaker 52-222082 is The operator calls booth to ensure 5.2.5 CLOSED, breaker 52-222082 is closed #

(to allow 1EAHV-F073 to be opened). CUE: Report that breaker 52-222082 is CLOSED.

OPEN EA-HV-F073 SERVICE The operator inserts key into keylock,

• 5.2.6 WATER LOOP B EMERG M/U rotates to ON, and depresses the open pushbutton for EA-HV-F073 #

INBD ISLN (10C651).

The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes 5.2.7 OPEN BC-HV-F075 //SSWS TO RHR The operator inserts keylock, roates to

• LOOP B SUP MOV//. OPEN & then OVLD ENBL, and #

depresses the open pushbutton for BC-HC-F075 The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes.

WHILE diverting the Service Water 5.2.8 flow to the Suppression Chamber, MONITOR temperatures of Operator monitors temperatures all on-service, SACS and RACS cooling loads.

Page 6 of 14

TQ-AA-106-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

THROTTLE OPEN BC-HV-F024B

• 5.2.9 Operator depresses the open

//RHR LOOP B TEST RET pushbutton for BC-HV-F024B. #

MOV// to control suppression chamber fill rate MONITOR Service Water Pump 5.2.10 BP502 and/or DP502 Motor Operator monitors motor amps and Amps and Vibration for indications of vibration.

pump run-out due to increased system flow WHEN suppression chamber level Operator determines that suppression

• 5.2.11 returns to the desired band, chamber level is in the 74-78 target RESTORE the RHR and Service band. #

Water systems to normal using NOTE: JPM may be terminated when Attachment 2 level increase is observed.

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP TIME.

N/A REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

Page 7 of 14

TQ-AA-106-0303 JPM: 2013 NRC S-5 OPERATOR TRAINING PROGRAM NAME:

Rev: 02 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

N/A TASK STANDARD: Operator Restores Suppression Chamber Level By Using Suppression Chamber Makeup From Service Water Loop B Page 8 of 14

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-5 TASK: Suppression Chamber Makeup From Service Water Loop B QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 9 of 14

TQ-AA-106-0303 JPM NUMBER: 2013 NRC S-5 REV#: 02 I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to IC (Shutdown)

ESTABLISH Suppression chamber level at 70.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description TOGGLE Control Room Horns to OFF.

ENSURE the simulator is reset AND in FREEZE.

COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code:

Description:

Event code:

Description:

Event code:

Description:

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Page 10 of 14

TQ-AA-106-0303 REMOTE SCHEDULE:

Initial @Time Event Action Description OVERRIDE SCHEDULE:

Initial @Time Event Action Description Page 11 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-5 Rev # Date Description Validation Required?

01 12/11/12 New JPM for NRC exam. Y 2 7/1/13 Numerous enhancements to examiner guide. Enhancements to Y cue sheet.

Page 12 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-5 REV#: 2 TASK: Suppression Chamber Makeup from Service Water Loop B

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

Procedure(s) referenced by this JPM match the most current revision of that

10. procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch position, meter reading) even if these criteria are not specified in the

12. procedural step.

Statements describing important actions or observations that should be made by the

13. operator are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Ryan Kelly RO On File 6-25-13 Name Qual Signature Date Steve Loper RO On File 6-26-13 Name Qual Signature Date Page 13 of 14

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. Suppression Chamber level is ~70 inches and normal means of make-up are unavailable.

2. RHR Pump BP202 is shutdown and is not required to assure adequate core cooling.

INITIATING CUE:

Restore suppression chamber level to 74-78 using Suppression Chamber Make-up from Service Water Loop B IAW HC.OP-EO.ZZ-0314.

Page 14 of 14

JOB PERFORMANCE MEASURE STATION: Hope Creek SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 JPM NUMBER: 2013 NRC S-8 REV #: 2 SAP BET: NOH05JPGS05E ALTERNATE PATH: X APPLICABILITY:

EO RO X STA SRO X DEVELOPED BY: NRC DATE: 5-22-13 Instructor REVIEWED BY: DATE:

Operations Representative APPROVED BY: DATE:

Training Department

TQ-AA-106-0303 STATION: Hope Creek JPM NUMBER: 2013 NRC S-8 REV: 2 SYSTEM: Containment Atmosphere Control TASK NUMBER: 2000950501 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches ALTERNATE PATH: X K/A NUMBER: 295024 EA1.19 IMPORTANCE FACTOR: 3.3 3.4 APPLICABILITY: RO SRO EO RO X STA SRO X EVALUATION SETTING/METHOD: Simulator/Perform

REFERENCES:

HC.OP-EO.ZZ-0318(Q) Rev. 7 TOOLS, EQUIPMENT AND PROCEDURES: None ESTIMATED COMPLETION TIME: 25 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Minutes JPM PERFORMED BY: GRADE: SAT UNSAT ACTUAL COMPLETION TIME: Minutes ACTUAL TIME CRITICAL COMPLETION TIME: N/A Minutes REASON, IF UNSATISFACTORY:

EVALUATORS SIGNATURE: DATE:

Page 2 of 20

TQ-AA-106-0303 NAME:

DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 INITIAL CONDITIONS:

1. The B RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.ZZ-0102, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 90 inches.

6. The Emergency Instrument Air Compressor has been restored IAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001(Q).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001(Q).

9. The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10. Salem Operations has been notified that containment venting will be performed.

11. The Aux. Bldg. EO is standing by at panel 1Y-F404.

12. The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE:

Vent the Containment via the Hard Torus Vent IAW HC.OP-EO.ZZ-0318. Notify the CRS when venting has commenced.

Page 3 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.

CUE ENTER START TIME AFTER OPERATOR REPEATS BACK INITIATING CUE:

START TIME:

Operator obtains/locates procedure Operator obtains the correct procedure.

HC.OP-EO.ZZ-0318.

Operator reviews precautions and Operator reviews precautions and limitations. limitations.

CUE If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines beginning step Operator determines correct beginning of the procedure step to be 5.1.1.

Page 4 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.1 VENT the containment via the Hard Operator reviews Prerequisites and Torus Vent as follows: ensures Prerequisites complete.

A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.

CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

5.1.1 B. NOTIFY the Emergency Duty Operator notifies the CRS to notifiy the Officer that containment venting EDO that containment venting via the via the Hard Torus Vent will be Hard Torus Vent will be performed.

performed.

CUE Acknowledge the communication to the EDO.

5.1.1 C. In the Lower Relay Room, Elev Operator directs the field operator to

• 102' at panel 1YF404 (see install fuse F22 at panel 1YF404.

Attachment 2), INSTALL F22 (6 #

amp fuse).

Page 5 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN directed to install 1YF404 fuse F22, THEN TRIGGER ET-3 AND REPORT the fuse is installed.

5.1.1 D. DEPRESS ISLN OVRD and Operator depresses the ISLN OVRD

• OPEN GS-HV-4964 SUPP pushbutton for the HV-4964.

CHMBR TO CPCS DMP. #

Operator observes the amber OVER-RIDDEN indicator illuminates.

Operator depresses the HV4964 OPEN

• PB.

Operator observes the red OPEN indicator illuminates and the green CLSD indicator extinguishes.

5.1.1 E. ANNOUNCE that containment Operator announces containment venting will commence at the venting will commence at the South end South end of the Reactor Building of the Reactor Building via the Hard via the Hard Torus Vent. Torus Vent over the plant paging system.

Page 6 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.1 F. When HV-4964 SUPP CHMBR TO Operator observes that the HV4964 CPCS DMP is full open, then OPEN indicator is illuminated.

OPEN GS-HV-11541 TORUS Operator observes that the HV4964 VENT ISOLATION VALVE. CLSD indicator is extinguished.

Operator rotates HV11541 keylock

• switch to the OPEN position.

Operator observes the red HV11541 OPEN indicator REMAINS EXTINGUISHED and the green CLOSED indicator REMAINS ILLUMINATED.

Operator informs CRS.

CUE Repeat back report from Operator Examiner Note: Based on the Initial and direct Operator to continue to Conditions, the Reactor Building is NOT implement the procedure until a accessible. Manually opening the vent path is established. HV-11541 is not an option.

Page 7 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.1 G. When drywell pressure can be Operator determines drywell pressure maintained below 60 psig, then is not being maintained below 60 psig, CLOSE GS-HV-11541 TORUS continues on in the procedure.

VENT ISOLATION VALVE.

5.1.1 H. REPEAT steps 5.1.1.O thru Operator determines repeating these 5.1.1.G as necessary to reduce steps will not establish a vent path.

and maintain drywell pressure below 65 psig.

5.1.1 I. If actions taken to reduce Operator determined actions taken thus containment pressure have been far have not been successful, continues unsuccessful, then continue in this in the procedure.

procedure.

5.1.2 VENT the containment via the Operator determines this path is not Suppression Chamber supply and available since it requires access to the ILRT piping as follows: Reactor Building and the reactor Building is not accessible.

Page 8 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE IF the Operator requests the status of the angled piping downstream of 1-GS-V058, THEN INFORM the Operator the piping has NOT been rotated to align the vent path and the Reactor Building is NOT accessible.

5.1.3 VENT the containment via the Drywell Operator determines this path is not supply and ILRT piping as follows: available since it requires access to the Reactor Building and the reactor Building is not accessible.

5.1.4 VENT the containment via the Operator determines the Suppression Suppression Chamber 2" exhaust as Chamber 2 exhaust is the next most follows: preferable path.

Examiner Note: 3.1.4 states: The selection of vent paths has been presented in priority order. However, if it can be determined that a particular path is unavailable or undesirable, the section addressing that vent path may be omitted (see Attachment 4).

Page 9 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.4 A. ENSURE that all prerequisites Operator reviews Prerequisites and have been satisfied in accordance ensures Prerequisites complete.

with Section 2.0 of this procedure.

CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.

5.1.4 B. NOTIFY the Emergency Duty Operator notifies the CRS to notifiy the Officer that containment venting of EDO that containment venting of the the Suppression Chamber to the Suppression Chamber to the Reactor Reactor Building will be Building will be performed.

performed.

CUE Acknowledge the communication to the EDO.

5.1.4 C. DEPRESS ISLN OVRD and Operator presses the DRYWELL

• OPEN GT-HD-9372A Drwl Purge PURGE SHUT OFF DMPRS ISLN Vent Exh Dmpr. OVRD pushbutton. #

Operator observes the pushbutton backlights.

Page 10 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

Operator presses the DRYWELL

• PURGE SHUT OFF DMPRS HD9372A OPEN pushbutton. #

Operator observes the red HD9372A OPEN light illuminates and green CLOSED light extinguishes.

5.1.4 D. DEPRESS ISLN OVRD and Operator observes the amber OVER-OPEN GS-HV-4964 SUPP RIDDEN light for the HV-4964 ISLN CHMBR TO CPCS DMP. OVRD is already illuminated.

Operator observes red HV4964 OPEN light is already illuminated and green CLSD light is already extinguished.

Examiner Note: It is only critical the HV-4964 is open. It is not critical whether it was left open from step 5.1.1.C, or closed and then re-opened at this step.

5.1.4 E. ANNOUNCE containment venting Operator announces containment

• of the Suppression Chamber to venting of the Suppression Chamber to the Reactor Building. the Reactor Building over the plant #

page.

Page 11 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.4 F. When GS-HV-4964 SUPP Operator observes red HV4964 OPEN CHMBR TO CPCS DMP is full light is illuminated and green CLSD open, then DEPRESS ISLN light is extinguished.

OVRD and OPEN GS-HV-4963 SUPP CHMBR N 2 M/U EXH.

Operator presses ISLN OVRD for the

• HV4963.

Operator observes the amber OVER-RIDDEN light illuminates.

Operator presses the HV4963 OPEN

• pushbutton.

Operator observes the red OPEN light illuminates and green CLSD light extinguishes.

Page 12 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation) 5.1.4 G. When drywell pressure can be Operator informs CRS that drywell maintained below 60 psig, then venting has commenced and monitors CLOSE GS-HV-4963 SUPP drywell pressure.

CHMBR N 2 M/U EXH and GS- Examiner Note: If drywell pressure HV-4964 SUPP CHMBR TO drifts below 60psig during performance CPCS DMP. of JPM, direct applicant to continue with venting.

CUE IF the operator cannot see the Examiner Note: The rate of drywell pressure reduction on the 10C650E pressure reduction through this path indicators, alone is slow and will not be readily visible on the 10C650E indicators due THEN inform the operator Drywell to the absence of a tenth digit. The pressure reduction is observable response IS readily observable on on SPDS.

SPDS. The operator may not be satisfied with the initial response and may elect to open an additional vent path.

Page 13 of 20

TQ-AA-106-0303 JPM: 2013 NRC S-8 OPERATOR TRAINING PROGRAM NAME:

Rev: 01 JOB PERFORMANCE MEASURE DATE:

SYSTEM: Containment Atmosphere Control TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

(*Denotes a Critical Step)

• COMMENTS STEP ELEMENT (#Denotes a Sequential Step) EVAL (Required for UNSAT NO. #

STANDARD S/U evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated for other reasons, THEN RECORD the STOP time.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete".

STOP TIME:

N/A TASK STANDARD: Operator vents primary containment through alternate vent path.

Page 14 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGRAM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME:

DATE:

JPM Number: 2013 NRC S-8 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches TASK NUMBER: 2000950501 QUESTION:

RESPONSE

RESULT: SAT UNSAT QUESTION:

RESPONSE

RESULT: SAT UNSAT Page 15 of 20

TQ-AA-106-0303 JOB PERFORMANCE MEASURE I. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL, EPU.

CLOSE the BC-HV-F004B RHR pump suction valve.

ISOLATE drywell cooling by closing the inboard and outboard drywell chilled water isolation valves.

TRIGGER ET-1 and ESTABLISH post large break LOCA conditions with a downcomer break and drywell pressure approximately 60 psig. Malfunctions may be modified as necessary.

CLOSE the MSIVs and drains.

IMPLEMENT EOP-101 AND EOP-102 AFTER drywell pressure is raised to approximately 60 psig.

RESTORE Instrument Air IAW EOP-319.

PLACE Temporary Air Compressor in service.

PLACE A RHR pump in drywell spray with the exception of opening the HV-F021A.

FAIL OPEN an ADS SRV.

USE Insight Item rhv021(1) (set to ~0.00 to 0.04) to crack open the F021A as necessary to establish drywell pressure at 60 psig and rising slowly.

ENSURE CREF is in service in the ISOLATE/RECIRC Mode IAW SO.GK-0001.

ENSURE FRVS is in Service IAW SO.GU-0001.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description COMPLETE Simulator Ready-for-Training/Examination Checklist.

EVENT FILE:

Initial ET #

Event code: pcpdw >= 16.2 // Drywell Pressure in psia 2

Description:

Inserts Feedwater line break and LOCA after drywell preheated Event code:

Description:

Event code:

Description:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE MALFUNCTION SCHEDULE:

Initial @Time Event Action Description Insert malfunction FW32 to Feedwater line break inside None None 100.00000 on event 2 containment Insert malfunction FW04A after 60 Secondary condensate pump None None on event 2 AP137 trip Insert malfunction FW04B after 60 Secondary condensate pump None None on event 2 BP137 trip Insert malfunction FW04C after Secondary condensate pump None None 60 on event 2 CP137 trip Insert malfunction MS01 after 90 None None Steam line break in drywell to 4.00000 on event 2 Insert malfunction PC04 on event None None Downcomer break 4

REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote RH23B to TAGGED RH23 RHR Pump B Insert remote RH20A to RH20 HV-F021A RHR CTMT None None RACK_OUT SPRAY Insert remote ET067 to None None ET067 HV-11541 Torus vent INSTALLED on event 3 IA10 Temporary station air None None Insert remote IA10 to RUN compressor EP38 EOP-319, Restoring None None Insert remote EP38 to Emergency Instrument Air in an Emergency OVERRIDE SCHEDULE:

Initial @Time Event Action Description None None Insert override 6S151_A_DI to Off HV-11541 OPEN KEY SW (DI)

TQ-AA-106-0303 JOB PERFORMANCE MEASURE REVISION HISTORY JPM NUMBER: 2013 NRC S-8 Rev # Date Description Validation Required?

2 6/25/13 Updated validation time. Moved cue sheet to last page. Y Updated cue sheet sup pool level to reflect simulator conditions. Added examiner note.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S-8 REV#: 02 TASK: Vent to Control Containment Pressure With Suppression Pool Level Less Than 180 inches

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

Knowledge and Abilities (K/A) is identified, and is >3.0 (LOR) or >2.5 (ILT) or justification is

2. provided.

3. License level identified. (SRO,RO,STA,NLO)

4. Performance location specified (in-plant, control room, simulator, or classroom).

5. Initial setup conditions are identified.

6. Initiating and terminating cues are properly identified.

7. Task standards for successful completion are identified.

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

8. Critical Steps are identified with a pound sign (#).

9. JPM has multiple Critical Tasks, or justification of the basis for a single critical task.

10. Procedure(s) referenced by this JPM match the most current revision of that procedure.

11. Cues both verbal and visual are complete and correct.

Performance standards are specific in exact control and indication nomenclature (switch

12. position, meter reading) even if these criteria are not specified in the procedural step.

Statements describing important actions or observations that should be made by the operator

13. are included (if required.)

14. Validation time is included.

15. JPM is identified as Time Critical Y/N and includes Critical Time (if required).

VALIDATED BY:

Qualification Level Required: RO Jeff Koskey RO On File 5-22-13 Name Qual Signature Date Ryan Kelly SRO On File 6-25-13 Name Qual Signature Date

TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

1. The B RHR pump suction was isolated due to a leak.

2. The Plant experienced a large break LOCA.

3. HC.OP-EO.ZZ-0102, Primary Containment Control has been implemented.

4. Drywell pressure is approximately 60 psig and rising AND Suppression Chamber pressure is approximately 59 psig and rising.

5. Suppression Pool Level indicates approximately 90 inches.

6. The Emergency Instrument Air Compressor has been restored IAW HC.OP-EO.ZZ-0319.

7. The Control Room Emergency Filtration System is operating in the Isolate/Recirculation Mode in accordance with HC.OP-SO.GK-0001(Q).

8. FRVS is in operation in accordance with HC.OP-SO.GU-0001(Q).

9. The Emergency Duty Officer/Emergency Response Manager has been informed that containment venting will be performed.

10. Salem Operations has been notified that containment venting will be performed.

11. The Aux. Bldg. EO is standing by at panel 1Y-F404.

12. The Reactor Building is inaccessible and has been evacuated.

INITIATING CUE:

Vent the Containment via the Hard Torus Vent IAW HC.OP-EO.ZZ-0318. Notify the CRS when venting has commenced.

SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Loss of RBVS, Loss of 10A120, Recirc Vibes, FW Break SCENARIO NUMBER: NRC 2013 Scenario #1 (ESG 029)

EFFECTIVE DATE:

EXPECTED DURATION: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> REVISION NUMBER: 4 PROGRAM: L.O. REQUAL X INITIAL LICENSE OTHER REVISION

SUMMARY

1. Deleted Critical Task related to 124 Torus level. Not possible in a one hour scenario.

2. Updated ESG to current standards and format. Editorial changes.

3. Deleted partial Recirc Seal failure.

4. Deleted Power Oscillations.

5. Added RHR pump trip at onset of LOCA.

6. Added A and B RHR auto initiation failures.

7. Added Drywell Spray valve failure.

8. Added Reactivity manipulation with Recirc.

9. Reorganized Event triggers to match scenario.

PREPARED BY: NRC 7/22/13 Instructor DATE APPROVED BY:

LORT Group Lead or Designee DATE APPROVED BY:

Shift Operations Supervisor or Designee DATE

I. OBJECTIVE(S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an *.)

II. MAJOR EVENTS:

A. Alternate RACS pumps (Optional)

B. Loss of RBVS C. Loss of 10A120 D. Recirc Pump high Vibrations E. Feedwater Line Break Inside Containment III. SCENARIO

SUMMARY

The scenario begins with the plant at approximately 100% power with RCIC C/T for a leak on the steam line drain pot. At the Lead Examiners discretion, RACS pumps may be swapped to support an oil change on the B RACS pump. The RO will commence power reduction from 100% to 90% with reactor recirc. RBVS Exhaust isolation damper GU-HD-9414A fails shut, causing a loss of RBVS and requiring FRVS to be placed in service. After FRVS is in service, the 10A120 bus is lost resulting in Single Loop operations in Region 1 of the Power to Flow Map.

Shortly after the 10A120 bus loss, the remaining Reactor Recirc pump develops high vibrations, which require removing the pump from service. This necessitates a reactor scram. During the scram, the alpha feedwater line breaks inside containment upstream of the inboard check valve.

This results in a High Drywell Pressure, a slow lowering of RPV level due to leakage past the check valve and an increase in Suppression Pool pressure. The line break also prevents stabilizing level with feedwater or HPCI. The A RHR pump will trip after manual start. The B RHR pump can be successfully started but the corresponding drywell spray valve fails to open.

Emergency Depressurization will be required due to a violation of the PSP curve due to a failure of the RHR Pump and Drywell spray valve (Critical Task #1). When Emergency Depressurization is initiated, one ADS SRV will not open due to faulted solenoids. An additional SRV will need to be opened by the Crew (Critical Task #2).

NRC 2013 Scenario #1 Page 2 of 29 Rev.: 4

IV. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power.

C/T RCIC as follows.

1. CLOSE the HV-4282

2. CLOSE the HV-F007

3. CLOSE the HV-F008

4. ALLOW RCIC supply pressure to decay to 0 psig

5. CLOSE the HV-F025

6. CLOSE the HV-F026 ENSURE B and C RACS pumps are in service.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description PLACE red bezel covers on the following RCIC controls:

• HV-F007

• HV-F008

• HV-F076

• HV-F045

• HV-F025

• HV-F026 ENSURE MOL CRAM Rod Listing is placed in Pull Sheet Book.

INITIAL IO-6 for power reduction.

INITIAL HC.OP-SO.ED-0001 through step 5.3.5 UPDATE LCO Status book for RCIC outage: T/S 3.7.4 14 days COMPLETE Simulator Ready-for-Training/Examination Checklist.

NRC 2013 Scenario #1 Page 3 of 29 Rev.: 4

EVENT FILE:

Initial ET #

Event code: zcrprun <= 0.0 // Mode Switch NOT in RUN 6

Description:

Triggers Feedwater Line Break and LOCA on scram.

Event code: Pcpdw > 17.0 // DW pressure above 2 psig 7

Description:

Trips A RHR Pump after start Event code: ad_k40b(2) >= 1.0 // SRV F013B B Channel solenoid energized 10

Description:

Triggers blowing of fuses when valve opened to ED.

Event code: ad_k40d(2) >= 1.0 // SRV F013B D Channel solenoid energized 11

Description:

Triggers blowing of fuses when valve opened to ED.

Event code:

Description:

Event code:

Description:

Event code:

Description:

Event code:

Description:

Event code:

Description:

NRC 2013 Scenario #1 Page 4 of 29 Rev.: 4

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction RC02 RCIC auto start failure None None Insert malfunction AD01 Failure of ADS valves to open None None Insert malfunction TC01-10 All turbine bypass valves fail closed RHR System A auto injection failed to None None Insert malfunction RH08A energized RHR System B auto injection failed to None None Insert malfunction RH08B energized None None Insert malfunction ED04 on event 4 Loss of 7.2 KV bus F 10A120 Insert malfunction RR26A2 to Recirc pump AP201 elevated (added to None None 10.00000 in 300 on event 5 calc) Pump Vib Insert malfunction FW32 to 10.00000 None None Feedwater line break inside containment on event 6 None None Insert malfunction FW26A on event 6 Feedwater pump turbine AS105 trip None None Insert malfunction FW26B on event 6 Feedwater pump turbine BS105 trip None None Insert malfunction FW26C on event 6 Feedwater pump turbine CS105 trip Insert malfunction QQ20 to SHORT None None RHR pump AP202 Malfunctions after 3 on event 7 Insert malfunction CD09A after 90 to Drive water flow control valve F002A None None 75.00000 on event 15 failure Insert malfunction CD09B to 0 on Drive water flow control valve F002B None None event 15 failure None None Insert malfunction PC04 on event 6 Downcomer failure

REMOTE SCHEDULE:

Initial @Time Event Action Description RC03 GROUP 6A HV-F007 RCIC Steam None None Insert remote RC03 to RACK_CLOSE Supply Isol RC04 GROUP 6A HV-F076 RCIC Steam None None Insert remote RC04 to RACK_CLOSE Supply Isol RC05 GROUP 6A HV-F008 RCIC Steam None None Insert remote RC05 to RACK_CLOSE Supply Isol Insert remote AN24 after 5 to NORM AN24 E6-C5 RBVS & Wing Area HVAC None None on event 2 Pnl 10C382 Insert remote HV01 to STOP on event None None HV01 RBVS Exhaust fan A 2

Insert remote HV02 to STOP on event None None HV02 RBVS Exhaust fan B 2

Insert remote HV03 to STOP on event None None HV03 RBVS Exhaust fan C 2

Insert remote HV04 to STOP on event None None HV04 RBVS Supply fan A 2

Insert remote HV05 to STOP on event None None HV05 RBVS Supply fan B 2

Insert remote HV06 to STOP on event None None HV06 RBVS Supply fan C 2

Insert malfunction QQ20 to SHORT None None RHR pump AP202 Malfunctions after 3 on event 7 Insert remote AD01B-B to REMOVED AD01 ADS/Relief valve F013B channel B None None on event 10 fuse Insert remote AD01B-D to REMOVED AD01 ADS/Relief valve F013B channel D None None on event 11 fuse Insert remote CD04 to OPEN on event CD04 CRD suction filter isolation valve None None 14 V030 Insert remote CD06 to 100.00000 in 60 CD06 Drive water press cont bypass None None on event 15 valve V062 (0-100%)

Insert remote CD10 after 120 to ON on None None CD10 CRD FCV B event 15

OVERRIDE SCHEDULE:

Initial @Time Event Action Description None None Insert override 9S9_A_LO to On HV-F045 OVLD/PWR FAIL (LO)

None None Insert override 9S10_A_DI to Off HV-F045 OPEN (DI)

None None Insert override 9S10_B_LO to Off HV-F045 CLOSED (LO)

None None Insert override 9S8_A_DI to Off HV-F025 OPEN (DI)

None None Insert override 9DS26_B_LO to Off HV-F025 CLOSED (LO)

None None Insert override 9S16_A_DI to Off HS-F026 (DI)

None None Insert override 9DS27_B_LO to Off HV-F026 CLOSED (LO)

None None Insert override 9S45_A_DI to Off RCIC MAN INIT-DA (DI)

HV-F032A CLOSE-FW SUPPLY LINE A None None Insert override 4A1_F_DI to Off (DI)

Insert override 1A159_F_DI to On on HD-9414A CLOSE-INBD EXH-REACTOR None None event 1 BUILDING (DI)

Insert override 1A159_E_DI to On on HD-9414A OPEN-INBD EXH-REACTOR None None event 1 BUILDING (DI)

Insert override 10S192_A_DI to Off on HV-F016B OPEN (DI)

None None event 6 Insert override 10DS40_A_LO after 3 to PUMP MOTOR OVER CURRENT-RHR A-None None On on event 7 LOOP A (LO)

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Swapping RACS pumps:

• CRS directs PO to place AP209 Crew places AP209 RACS RACS pump in service and pump in service and secures secure BP209 RACS pump.

BP209 RACS pump after assuming the watch.

IF dispatched to AP209,

• PO dispatches RBEO to perform THEN REPORT the AP209 pre-start checks and locally RACS pump is ready for a observe start of AP209 RACS start. pump IAW OP-HC-108-106-1001.

AFTER AP209 is in service,

• PO starts AP209 and secures HPI USED:

THEN REPORT AP209 is BP209 IAW SO.ED-0001 Section STAR running SAT. 5.3.6 (Marked up through 5.3.5) PEER CHECK Monitor Items: FLAGGING

• Normalized AP209 speed OP BARRIERS cwnra209 Power reduction with Recirc:

• CRS directs RO to reduce After assuming the watch. reactor power to 90% IAW Reactor Engineering guidance and HC.OP-IO.ZZ-0006.

SUPPORT crews actions to

• RO to reduce reactor power to HPI USED:

TOGGLE Crossflow. 90% IAW Reactor Engineering STAR guidance OP-AB-300-1003. PEER CHECK FLAGGING OP BARRIERS NRC 2013 Scenario #1 Page 8 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Loss of RBVS:

• Crew recognizes Loss of RBVS After the Crew lowers reactor by:

power, OHA E1-F5 COMPUTER PT OR at the discretion of the IN ALARM Lead Examiner, CRIDS B7164 REACTOR TRIGGER ET-1 (RBVS BLDG DIFF PRESS Exhaust Damper HD-9414A OHA E6-C5 RBVS & WING Fails shut). AREA HVAC PNL 10C382 (delayed)

CRIDS D3960 RBVS EXH RMT PNL C382 TRBL CRIDS D3961 RBVS SUPPLY RMT PNL C382 TRBL RB D/P indication on 10C650E SPDS RB PARAMETERS D/P indication.

• CRS implements AB.CONT-003:

Condition A IF dispatched to 10C382,

• Crew dispatches RBEO to THEN REPORT Low Flow Trip 10C382 to investigate.

alarms on all Reactor Bldg Supply and exhaust fans.

• RO/PO recognize HD-9414A failed shut by 10C651E indication and inform CRS.

IF directed to secure RBVS,

• RO/PO place FRVS in service HPI USED:

THEN TRIGGER ET-2. IAW SO.GU-0001 -or- hardcard. STAR PEER CHECK FLAGGING OP BARRIERS IF dispatched to HD-9414A,

• Crew dispatches NEO and THEN REPORT there is no Maintenance to investigate obvious reason for the closure. closure of HD-9414A.

NRC 2013 Scenario #1 Page 9 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS recognize the following Tech Specs apply:

Secondary Containment Integrity 3.6.5.1 Secondary Containment Automatic Isolation Dampers 3.6.5.2 action a or b or c Loss of 10A120 Bus:

• Crew recognizes:

15 minutes after the Loss of Reactor power lowering RBVS, Reactor level swell OR, at the discretion of the Lead

Examiner, TRIGGER ET-4.

• Crew monitors Reactor power, pressure, and level until plant conditions are stable.

• PO ensures feedwater restores and maintains RPV level between LVL 4 and LVL 7.

• Crew recognizes Loss of B Reactor Recirc pump by:

C1-D5 REACTOR RECIRC B TROUBLE CRIDS D2918 RECIRC MG DRIVE MOTOR B BRKR Flashing TRIP light for B Recirc MG Drive Motor bkr B Reactor Recirc pump flow and d/p indications on 10C651C

• RO ensures at least one recirc pump still running.

NRC 2013 Scenario #1 Page 10 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes trip of B PCP The trips of B PCP and and B SCP by: B SCP are silent and OVLD/PWR FAIL lights may not be immediately STOP lights lit recognized by the Motor amps zero Crew.

• Crew validates automatic actions:

Feedwater PCP Speed Limiter on Recirc pump Int Runback

• Crew recognizes entry into the OPRM Enable Region by:

C3-F1 OPRM TRIP ENABLE

• Crew recognizes loss of BK111 The trip of BK111 is TB chiller by: silent and may not be OVLD/PWR FAIL light immediately recognized STOP light lit by the Crew.

Motor amps zero

• Crew recognizes loss of 10A120 bus from:

OHA E3-E1 7.2 KV SYS INCOMING BRKR MALF Solid OVLD/PWR FAIL lights on loads lost Flashing TRIP light for infeed bkr 52-12008 CRIDS D3682 SWGR BUS A120 DIFF LOCKOUT CRIDS D3684 SWGR BUS A120 UNDERVOLTAGE

• Crew announces loss of 10A120 on the plant page.

NRC 2013 Scenario #1 Page 11 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS implements AB.RPV-0003: The pace of the Condition A scenario will not allow Condition B the Crew to fully address single loop requirements.

IF the Crew manually scrams,

• IF in Region 1 of the Pwr/Flow HPI USED:

THEN the Feedwater Line map, STAR Break and LOCA will be THEN RO inserts rods IAW ESG PEER CHECK automatically inserted. guidance as necessary to exit Region 1.

• RO/PO close HV-F031B Recirc HPI USED:

pump discharge valve for 5 STAR minutes, then re-open. PEER CHECK FLAGGING OP BARRIERS

• RO/PO implement DL.ZZ-0026 Att. 3v.

• CRS implements AB.RPV-0001:

Condition B

• CRS implements AB.RPV-0004:

Condition D Condition G

• PO closes HV-1680B PCP HPI USED:

discharge valve. STAR PEER CHECK FLAGGING OP BARRIERS

• PO closes HV-1651B SCP HPI USED:

discharge valve. STAR PEER CHECK FLAGGING OP BARRIERS NRC 2013 Scenario #1 Page 12 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• PO bypasses Feedwater HPI USED:

Runbacks. STAR PEER CHECK WHEN dispatched,

• Crew dispatches TBEO and THEN REPORT the 10A120 Maintenance to investigate loss Bus Differential Overcurrent of 10A120 bus.

Relays are tripped. There is no visible indication of damage to the bus.

As RE, REPORT the Enhanced

• Crew contacts RE for guidance Stability guidance should be and to check thermal limits.

used to exit Region 1. The first 12 rods of the CRAM RODS list will also satisfy the 80% rod line sequence for single loop IAW AB.RPV-0003.

• Crew references Power Maneuvering Tech Specs in OP-HC-108-106-1001 Equipment Operational Control.

• CRS recognize the following actions apply:

Recirculation Loops 3.4.1.1 action a Reactor Coolant System Specific Activity T/S Table 4.4.5-1 Item 4(b)

ODCM Table 4.11.2.1.2-1 Items (c) & (f)

• CRS notifies Shift Rad Pro and Shift Chem Tech to take samples IAW:

T/S Table 4.4.5-1 Item 4(b)

ODCM Table 4.11.2.1.2-1 Items (c) & (f)

NRC 2013 Scenario #1 Page 13 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS recognize the following Tech Specs apply:

Recirculation Loops 3.4.1.1 action a 4.4.1.1.1

• Crew contacts ESOC and Trading Floor, gives estimate of MWe output limitations and duration of limitation.

• CRS contacts Operations Management.

A Recirc Pump High

• Crew recognizes rising vibrations Vibration will jump 3 Vibration: on A Reactor Recirc pump by: mils then rise at a rate 15 minutes after the Loss of CRIDS A2601 RECIRC PMP of one mil per minute.

10A120, A RADIAL VIB MON C1-E4 and C1-F5 will OR, OHA C1-F5 COMPUTER PT alarm at 11 mils.

at the discretion of the Lead IN ALARM Examiner, TRIGGER ET-5. OHA C1-E4 REACTOR RECIRC PUMP VIB HI CRIDS D2920 RECIRC PUMP MOTOR A VIBRATION CRIDS D5351RECIRC PUMP AP201 VIBRATION

• CRS implements AB.RPV-0003:

Condition F WHEN it is determined that A Recirc Pump Vibration points cannot be maintained below the DANGER limits (16mils) THEN the CRS orders manual scram to support removing A Reactor Recirc pump from service.

NRC 2013 Scenario #1 Page 14 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• RO locks the Mode Switch in HPI USED:

SHUTDOWN and performs STAR scram actions IAW AB.ZZ-0001 HARD CARD Att. 1.

• Crew recognizes RPV Level Below 12.5 EOP entry condition by:

OHA C5-A4 RPV WATER LEVEL LO OHA A7-D5 RPV LEVEL 3 Various water level indicators Feedwater Line Break:

• Crew recognizes High Drywell RECORD Drywell The feedwater line break inside Pressure EOP entry condition: Pressure reached 1.68 containment with leakage past OHA A7-D4 DRYWELL psig for 15 min ECG the check valve will be PRESSURE HI/HI Classification.

automatically inserted when the OHA C5-B5 DRYWELL Mode Switch is taken out of PRESSURE HI Time: __________

RUN. Various system initiations and isolations

• CRS implements:

EOP-101 EOP-102

• PO attempts to maintain level as HPI USED:

directed by CRS. STAR HARD CARD The feedwater line break will prevent restoring level with HPCI or feedwater.

• CRS determines an Alert RECORD time Alert Classification is required IAW declared.

ECG Section RB2.L (Drywell Time pressure >1.68 psig due to RCS Declared: ________

leakage). (May be done after scenario completion.)

NRC 2013 Scenario #1 Page 15 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF directed to open the breaker

• Crew recognizes A feedwater for the HPCI HV-8278 in an line break by:

attempt to fail the valve shut, High Flow / Low Discharge THEN REPORT the breaker Pressure on condensate handle on the cubicle door High Flow / Low Discharge does not appear to be Pressure on HPCI engaging the breaker paddle Ability to vary HPCI flow with inside the cubicle. You cannot Setpoint get the cubicle door open and Absence of OHA B1-E5 have called the 12 Hour HPCI PUMP DISCHARGE Maintenance Supervisor and FLOW LO asked for an Electrician to help. Rapidly rising torus level Do NOT fail the valve shut. Lowering hotwell level RPV Pressure trend not consistent with a LOCA greater than the capacity of HPCI/Condensate IF directed to close the F032A,

• Crew may attempt to isolate the HPI USED:

THEN REPORT the actuator A Feedwater line if they STAR appears to be broken. The successfully diagnose a FW line The HV-F032A will not valve will not stroke from the break. close from the Control bucket or locally with the Room.

manual handwheel.

• Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

OHA C8-F1 SUPPR POOL TEMP HIGH Flashing 95 degree status light on 10C650C RM11 9AX833/834 alarm Various Suppression Pool temperature indicators

• CRS re-enters EOP-102.

NRC 2013 Scenario #1 Page 16 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• IF feedwater and condensate remained aligned to feed the reactor vessel, THEN Crew recognizes low main condenser hotwell levels by:

OHA A6-F1 CONDENSATE TRAIN A TROUBLE OHA A6-F2 CONDENSATE TRAIN B TROUBLE OHA A6-F3 CONDENSATE TRAIN C TROUBLE CRIDS D2943 CONDENSER AE108 LEVEL CRIDS D2945 CONDENSER BE108 LEVEL CRIDS D2947 CONDENSER CE108 LEVEL 10C651A Hotwell Level indication

• CRS directs injection with:

SLC Two CRD pumps (If RPV level continues to lower)

• RO/PO initiate SLC. HPI USED:

STAR NRC 2013 Scenario #1 Page 17 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF directed to align for two CRD

• RO/PO align CRD for Emergency HPI USED:

pump injection, Two CRD Pump Injection IAW STAR THEN PERFORM the SO.BF-0001 Section 5.4. HARD CARD following:

REFER to SO.BF-0001 Sect 5.4.

TRIGGER ET-14 (Suction filter).

SET Remote Function for Stby CRD pump discharge valve to 0% (CD01/CD02).

REPORT Stby CRD pump ready for start.

WHEN Stby CRD is running, THEN RAMP discharge valve to 100% open.

AFTER HV-F003 is open, THEN TRIGGER ET-15.

WHEN two minutes have

elapsed, THEN MODIFY Malfunctions CD09A/B to control injection.

Bypass Valves Fail Shut:

• Crew recognizes bypass valves OHA E1-F4 will not be The Bypass Valves will Fail will not open by: received if no bypass shut three minutes after the OHA E1-F4 COMPUTER valves were open at the EHC pump trips. POINT RETURNED TO time of the failure.

NORMAL OHA D3-D5 will not be OHA D3-D5 EHC UNIT received until there is PANEL 10C363 an open demand to the Bypass valve indication bypass valves.

BPV Positioning Error alarms Reactor pressure rising above Pressure Setpoint

• CRS directs pressure control IAW EOP-101 using Steam Line Drains and/or RFPTs.

• RO/PO control pressure as HPI USED:

directed by CRS IAW STAR AB.ZZ-0001 Attachment 15. HARD CARD NRC 2013 Scenario #1 Page 18 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RHR Pump A and B Fail to

• Crew recognizes A and B Auto Start, A Trips & HV- RHR pumps fail to auto-start on F016B fails to open: LOCA signal by:

The A RHR pump immediately Pump STOP, amp and flow trips after being manually indications started AND HV-F016B Drywell Spray Valve fails to open.

• Crew manually starts A and B RHR pumps.

• Crew recognizes A RHR pump trip by:

OHA RHR LOGIC OUT OF SERVICE OUT OF SERVICE status light PUMP MOTOR OVERCURRENT status light Pump STOP, amp and flow indications IF dispatched to investigate the

• Crew dispatches operator and trip of the A RHR pump, Maintenance to the tripped RHR THEN REPORT: pump and breaker.

• The breaker has target flags dropped on the 51A and 51B Time Overcurrent relays (401/402 bkr 06)

• The pump motor is hot to the touch and bearing oil levels are normal NRC 2013 Scenario #1 Page 19 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• IF the CRS determines B RHR pump is NOT required to assure adequate core cooling by operating in LPCI mode, THEN CRS directs placing:

B RHR pump in Suppression Chamber Cooling/Spray or Drywell spray (if >9.5psig in the suppression chamber).

• RO/PO places B RHR pump in HPI USED:

Suppression Chamber STAR Cooling/Spray or Drywell Spray HARD CARD IAW AB.ZZ-0001 Att. 3.

• Crew recognizes the failure of HV-F016B to open (Drywell Spray Valve)

• Crew recognizes containment not performing properly by:

Suppression Chamber pressure approaching Action Required area of PSP curve Suppression Chamber airspace temperature significantly above water temperature Drywell Pressure response

• WHEN the Crew determines Suppression Chamber pressure cannot be maintained below the Action Required region of the PSP curve, THEN the CRS implements EOP-202 to Emergency Depressurize.

NRC 2013 Scenario #1 Page 20 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL

• Crew prevents injection from TRANSIENT MITIGATION Core Spray and LPCI pumps not For non-ATWS emergency required for adequate core depressurizations, the Control Room Supervisor should establish and cooling.

maintain an RPV level band between

-38 to +54 on Wide Range indication. This transient level band will prevent adverse hydraulic effects caused by high outside shroud reactor level while maintaining adequate core submergence based on Fuel Zone indication. Following the emergency depressurization, level will be restored and maintained to the preferred EOP reactor level band by using a suggested Wide Range compensated level band of

+12.5 to +54 if possible using Condensate and Startup Level Control or the Control Room Supervisor can maintain an RPV level band of -38 to +54 if still batch feeding with low pressure ECCS to maintain RPV level.

• RO/PO open ADS valves IAW HPI USED:

AB.ZZ-0001 Attachment 13. STAR HARD CARD INPO Fundamentals:

CONTROL

• Crew actuates five SRVs when the Action Required Region of the PSP curve is entered OR when it is determined that Suppression Chamber pressure cannot be maintained below the Action Required Region of the PSP curve.

NOTE:

Preventing entry into the Action Required Region of the PSP curve satisfies this critical task.

NRC 2013 Scenario #1 Page 21 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes failure of PSV-F013B to remain open by:

Acoustic Monitor position indication on 10C650C Tailpipe temperature on TR-R614

• WHEN Emergency Depressurization is initiated and the PSV-F013B fails to remain open, THEN before RPV pressure drops below 50psig, the Crew places the Control Switch for an additional SRV to OPEN to achieve five open SRVs.

• RO/PO opens additional SRV HPI USED:

IAW AB.ZZ-0001 Att. 13, informs STAR CRS of PSV-F013B failure. HARD CARD

• CRS directs restoring RPV level to -38 to 54 with Low Pressure ECCS.

• RO/PO restore RPV level as HPI USED:

directed by CRS IAW STAR AB.ZZ-0001: HARD CARD Att. 4 for RHR IF RPV water level Att. 5 for Core Spray drops below -311, THEN the CRS may implement EOP-206.

• WHEN adequate core cooling is assured, THEN CRS directs placing:

One loop of RHR in Drywell Spray NRC 2013 Scenario #1 Page 22 of 29 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• RO/PO align RHR IAW HPI USED:

AB.ZZ-0001: STAR Att 2 Drywell Spray HARD CARD Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when either:

• RPV level has been restored above -129 and containment parameters are improving OR

• EOP-202 is being implemented and RPV pressure is being maintained 50 psig above Suppression Chamber pressure with five SRVs open.

NRC 2013 Scenario #1 Page 23 of 29 Rev.: 4

VI. SCENARIO

REFERENCES:

A. NUREG 1021 Examiner Standards B. JTA Listing C. Probabilistic Risk Assessment D. Technical Specifications E. Emergency Plan (ECG)

F. Alarm Response Procedures (Various)

G. HU-AA-101 Performance Tools and Verification Practices H. OP-AA-101-111-1004 Operations Standards I. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel J. OP-AA-106-101-1001 Event Response Guidelines K. OP-AA-108-114 Post Transient Review L. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program M. OP-HC-108-106-1001 Equipment Operational Control N. HC.OP-SO.AE-0001 Feedwater System Operation O. HC.OP-SO.BF-0001 CRD Hydraulic System Operation P. HC.OP-SO.ED-0001 Reactor Auxiliaries Cooling Water System Operation Q. HC.OP-SO.GU-0001 Filtration, Recirculation, and Ventilation System Operation R. HC.OP-AB.ZZ-0001 Transient Plant Conditions S. HC.OP-AB.RPV-0001 Reactor Power T. HC.OP-AB.RPV-0003 Recirculation System / Reactor Power Oscillations U. HC.OP-AB.RPV-0004 Reactor Level Control V. HC.OP-AB.CONT-0003 Reactor Building W. HC.OP-AB.ZZ-0000 Reactor Scram X. HC.OP-EO.ZZ-0101 RPV Control Y. HC.OP-EO.ZZ-0102 Primary Containment Control Z. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization AA. HC.OP-EO.ZZ-0206 RPV Flooding BB. NOTF 20149832 Feedwater Piping Wall Thickness NRC 2013 Scenario #1 Page 24 of 29 Rev.: 4

VII. ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #1, Rev. 04 1.

Crew actuates five SRVs when the Action Required Region of the PSP curve is entered OR when it is determined that Suppression Chamber pressure cannot be maintained below the Action Required Region of the PSP curve.

K/A 295024 High Drywell Pressure EA2 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

EA2.04 Suppression chamber pressure RO 3.9 SRO 3.9 K/A 223001 Primary Containment Systems and Auxiliaries A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions of operations:

A2.02 Steam bypass of the suppressions pool RO 3.9 SRO 4.1 If suppression chamber pressure cannot be maintained below the pressure suppression pressure (PSP), EOPs direct actions to emergency depressurize the reactor. A LOCA condition while in the action required region of the Pressure Suppression Pressure Curve, could cause design containment limits to be exceeded. Preventing entry into the Action Required Region of the PSP curve satisfies this critical task.

2.

WHEN Emergency Depressurization is initiated and the PSV-F013B fails to remain open, THEN before RPV pressure drops below 50 psig, the Crew places the Control Switch for an additional SRV to OPEN to achieve five open SRVs.

K/A 295031 Reactor Low Water Level EA1. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL:

EA1.07 Safety/Relief Valves RO 3.7 SRO 3.7 The Minimum Number of SRVs required for Emergency Depressurization (MNSRED) is five. The MNSRED is utilized to assure the RPV will depressurize and remain depressurized when Emergency Depressurization is required. When the fuses for the PSV-F013B fail, the Crew needs to ensure an additional SRV control switch is in the OPEN position to achieve five SRVs for Emergency Depressurization. This is directed by both EOP-202 and AB.ZZ-0001. SRVs are designed to open with a minimum differential pressure of 50 psid between the reactor vessel and the suppression chamber. Below this d/p, they may not open. If the Crew does not attempt to open the fifth SRV before this minimum d/p is lost, they cannot validate its operation. This would prevent them from detecting the failure and pursuing the use of the Alternate Depressurization Systems in EOP-202.

NRC 2013 Scenario #1 Page 25 of 29 Rev.: 4

2013 NRC Scenario #1, Rev. 04 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE Y/N EVENT Y/N EVENT Loss Of Offsite Power/SBO Internal Flooding Y LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N KEY SYSTEMS HPCI Y SRVs Y RCIC Y Condensate/Feedwater B/D EDG SSW Y A/B RHR Pump RPS A/B SACS Loop 1E 4.16KV Bus 1E 480 VAC Bus 120VAC 481 Inverter 1E 125VDC Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Y Manual Depressurization of the RPV w/ no HP Injection Available Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal Control RPV Water Level w/ HP Injection during ATWS Sequence Align Portable Power Supply to Battery Chargers Venting of Primary Containment Restore Switchgear Cooling Restart Condensate Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG.

NRC 2013 Scenario #1 Page 26 of 29 Rev.: 4

VIII. TURNOVER SHEET:

ONLINE RISK: GREEN WORK WEEK CHANNEL: B PROTECTED EQUIPMENT HPCI/250VDC A Channel EDG, SWGR, 1E Logic Panels, REACTIVITY / Plant Status 100% Power Power reduction to 90% IAW HC.OP-IO.ZZ-0006 and REMA.

ESF/SAFETY SYSTEMS RCIC C/T for scheduled drain pot steam leak repair.

COOLING WATER Place A RACS pump I/S and secure B RACS pump for oil change. No maintenance has been performed on B RACS pump.

BOP None ELECTRICAL None ADVERSE CONDITION MONITORING None NRC 2013 Scenario #1 Page 27 of 29 Rev.: 4

IX. SIMULATOR ESG REVIEW/VALIDATION CHECKLIST EXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG: Scenario #1 SELF-CHECK

1. Total malfunctions inserted: 5-8

2. Malfunctions that occur after EOP entry: 1-4

3. Abnormal Events: 1-2

4. Major Transients: 1-2

5. EOPs used beyond primary scram response EOP: 1-3

6. EOP Contingency Procedures used: 0-3

7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8. EOP run time: 40-70% of scenario run time

9. Crew Critical Tasks: 2-5

10. Technical Specifications are exercised during the test: >1 Comments:

Page 28 of 29 Rev.: 4

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)

Crew Validation Rev: 4 Date Validated: 7/23/13 Validated with one crew of 3 Shift. Validation time 60 minutes.

Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition Page 29 of 29 Rev.: 4

SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Recirc Pump Seal Failure, ATWS with BPV Failure SCENARIO NUMBER: NRC 2013 Exam Scenario #2 EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60 minutes REVISION NUMBER: 4 PROGRAM: L.O. REQUAL X INITIAL LICENSE OTHER REVISION

SUMMARY

1. Changes ATWS from electrical to hydraulic full core.

2. Deletes trip of A SBLC pump.

3. Deletes CR HVAC failure to auto-start.

4. Deletes APRM Flow Summer Failure.

5. Extends EHC pump trip time delay by 2 minutes.

6. Remove Power Oscillation malfunction after scram.

PREPARED BY: NRC 7/23/13 Instructor DATE APPROVED BY:

LORT Group Lead or Designee DATE APPROVED BY:

Shift Operations Supervisor or Designee DATE

I. OBJECTIVE(S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CREW CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Crew critical tasks within this examination scenario guide are identified with an *.)

II. MAJOR EVENTS:

A. Loss of 1CD481 Inverter B. Recirc Pump Seal Failure C Power Oscillations D. ATWS with ARI failure, RWCU and SLC Failure E. EHC Pump Failure F. RHR Torus Cooling Valve Fails To Open III. SCENARIO

SUMMARY

The scenario begins with the plant at 100% power; with A EHC Pump OOS. N2 makeup to the Primary Containment is required. After establishing N2 makeup, the crew will be directed to lower power to 90% using Recirc pump flow to prepare for a rod pattern adjustment. After reactivity change is completed, the 1CD481 inverter will fail. After the inverter failure, the A Recirc pump will experience a seal failure and the crew will have to reduce power and the pump will be tripped & isolated. After single loop operation is established, power oscillations will occur, necessitating a reactor SCRAM. The SCRAM will not be successful and will result in a full core ATWS with an initial power level of about 40%. ARI will fail to operate. RWCU will fail to isolate and B SLC pump will trip when started. The crew will attempt to drive individual rods manually.

Additional SCRAM attempts will not be successful. Pressure will be initially controlled with the BPVs, but the BPVs will gradually fail close subsequent to the EHC pump trip, requiring the crew to establish pressure control with the SRVs. When Torus cooling is placed into service, the RHR torus cooling valve fails to open. Once torus cooling is placed in service and pressure and level are being maintained, SCRAM attempts will be successful and the scenario may be terminated.

2013 NRC Scenario #2 Page 2 of 30 Rev: 4

IV. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, 3840 MWth, MOL.

IF N2 makeup to containment will be performed, THEN REDUCE drywell and suppression chamber pressure to approximately 0.30 psig.

ENSURE D SACS pump is in service.

ENSURE B CRD pump is in service.

ENSURE B FPCC pump is in service.

ENSURE B Control Room Vent Train is in service.

ENSURE BOTH Steam Tunnel unit Coolers are in service.

ENSURE B EHC pump is in service.

ENSURE B PCIG Compressor is in AUTO LEAD.

ENSURE associated Schedule file open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description INITIAL IO.ZZ-006 for the power reduction.

IF performing N2 Makeup, THEN INITIAL HC.OP-SO.GS-0001 up to the and including increasing vaporizer temperature to 100 degF (Step 5.2.9 of Rev 33).

Protect B EHC Pump ENSURE Data Collection is trending the following parameters:

• W/R Reactor Water Level

• Fuel Zone Reactor Water Level

• W/R Reactor Pressure At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(80091396 0270)

COMPLETE the Simulator Ready for Training/Examination Checklist.

2013 NRC Scenario #2 Page 3 of 30 Rev: 4

EVENT FILE:

Initial ET #

Event code: rr_52(1) < 1.0 // A Recirc pump breaker 5

Description:

A RRP stopped initiates power oscillations.

Event code: crqnmi <=30 Reactor Power less than 30%

7

Description:

Trips SBLC Pumps after MS placed in SD.

Event code: zcrprun <= 0.0 // Mode Switch NOT in RUN 8

Description:

Initiates hydraulic full core ATWS Event code: rhf24(1) > 300 // A RHR in Chamber Cooling 16

Description:

Trips BC-HV-F024A when placed in Chamber Cooling Event code: rhf24(2) > 300 // B RHR in Chamber Cooling 17

Description:

Trips BC-HV-F024B when placed in Chamber Cooling Event code: et_array(16) //

18

Description:

Detects BC-HV-F024A tripped to remove B malfunction Event code: et_array(17) //

19

Description:

Detects BC-HV-F024B tripped to remove A malfunction Event code: ZLSLPMAS 30

Description:

SBLC PUMP A started 2013 NRC Scenario #2 Page 4 of 30 Rev: 4

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None None Insert malfunction TC07A EHC pump A trip RWCU isolation valve F001 failure to None None Insert malfunction CU11A auto close RWCU isolation valve F004 failure to None None Insert malfunction CU11B auto close Loss of 120 VAC class 1E inst bus None None Insert malfunction ED09C1 on event 2 1CD481 Insert malfunction RR05A to None None Recirc pump A inboard seal failure 100.00000 in 60 on event 3 Insert malfunction RR06A after 180 None None Recirc pump A outboard seal failure from 12.00000 to 100.00000 in 360 Insert malfunction CR02A after 60 to None None Reactor Core Instabilities (LPRMs) 80.00000 in 300 on event 5 Insert malfunction AN-C3F2 after 300 None None CRYWOLF ANN C3F2 OPRM ALARM on event 5 Insert malfunction SL01B after 120 on None None SBLC injection pump BP208 failure event 7 Insert malfunction TC07B after 360 on None None EHC pump B trip event 7 Insert malfunction RP06 after 2 on None None Half-core ATWS - left side event 8 Insert malfunction RP07 after 2 on None None Half-core ATWS - right side event 8 Insert malfunction CR02A after 1 to None None Reactor Core Instabilities (LPRMs) 0.00000 on event 8 None None Insert malfunction CW15B on event 2 Prevents auto-start of SACS Pump B Insert malfunction SL01B after 240 on None None Trips SBLC Pump B event 30 2013 NRC Scenario #2 Page 5 of 30 Rev: 4

REMOTE SCHEDULE:

Initial @Time Event Action Description None None Insert remote HV12 to RUN HV12 Steam tunnel unit cooler BVH216 Insert remote EP01 after 360 to BYPASS on EP01 EOP-301, Bypass MSIV (-129") &

None None event 11 High Temp Isolations Insert remote EP02 after 480 to BYPASS on EP02 EOP-311, Bypass PCIG (-129")

None None event 12 Isolation Insert remote EP38 after 180 to BYPASS on EP05 EOP-319, LOCA level 2 interlock None None event 13 for 10K100 Insert remote EP09 after 240 to REMOVED EP09 EOP-320 (step 5.1.2), ARI valve None None on event 14 fuses F6A/F5A Insert remote EP10 after 240 to REMOVED EP10 EOP-320 (step 5.1.4), ARI valve None None on event 14 fuses F6B/F5B Insert remote EP11 to INSTALLED after 360 EP11 EOP-320 (step 5.2.2), RPS division None None to INSTALLED on event 14 1 jumper Insert remote EP13 to INSTALLED after 360 EP13 EOP-320 (step 5.2.3), RPS division None None to INSTALLED on event 14 3 jumper Insert remote EP12 after 720 to INSTALLED EP12 EOP-320 (step 5.2.4), RPS division None None on event 14 2 jumper Insert remote EP14 after 720 to INSTALLED EP14 EOP-320 (step 5.2.5), RPS division None None on event 14 4 jumper Insert remote EP35 after 180 to None None EP35 EOP-322 HV-F006 HPCI to CS FAIL_CLOSE on event 15 Insert remote RH25A to RACK_OUT on RH25 GROUP 3A HV-F024A RHR Supp.

None None event 16 Pool Clg Insert remote RH25B to RACK_OUT on RH25 GROUP 3A HV-F024B RHR Supp.

None None event 17 Pool Clg RH25 GROUP 3A HV-F024A RHR Supp.

None 19 Remove remote RH25A to NORMAL Pool Clg RH25 GROUP 3A HV-F024B RHR Supp.

None 18 Remove remote RH25B to NORMAL Pool Clg Insert remote AN24 after 5 to NORM on AN24 E6-C5 RBVS & Wing Area HVAC None None event 20 Pnl 10C382 None None Insert remote HV01 to STOP on event 20 HV01 RBVS Exhaust fan A None None Insert remote HV02 to STOP on event 20 HV02 RBVS Exhaust fan B None None Insert remote HV03 to STOP on event 20 HV03 RBVS Exhaust fan C None None Insert remote HV04 to STOP on event 20 HV04 RBVS Supply fan A None None Insert remote HV05 to STOP on event 20 HV05 RBVS Supply fan B None None Insert remote HV06 to STOP on event 20 HV06 RBVS Supply fan C 2013 NRC Scenario #2 Page 6 of 30 Rev: 4

OVERRIDE SCHEDULE:

Initial @Time Event Action Description 2013 NRC Scenario #2 Page 7 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments N2 M/U to the Primary

• CRS directs N2 Makeup to the Containment: Primary Containment.

Refer to SO.GS-0001 Section

• PO conducts N2 makeup to the 5.2 and SUPPORT requests for Primary Containment IAW field manipulations with SO.GS-0001 Section 5.2 and appropriate reports. 5.3.

(The simulator does not model any of these functions. The N2 vaporizer is always lined up for make-up).

Power Reduction:

• CRS directs RO to reduce HPI USED:

Crew lowers power to 90% reactor power to 90% IAW STAR RTP using recirculation pumps. Reactor Engineering guidance PEER CHECK and 5.2 of HC.OP-IO.ZZ-0006.

• RO reduces and maintains RO to reduce reactor power to 90%

IAW Reactor Engineering guidance and 5.2 of HC.OP-IO.ZZ-0006.

Loss of CD481:

• Crew recognizes loss of CD481 After the Crew assumes the by:

watch and at the discretion of OHA D3-E3 120VAC UPS the Lead Examiner, TROUBLE TRIGGER ET-2 (Loss of OHA C6-A1 RSP/RSS CD481 120AC 1E Inverter). TAKEOVER Downscale indications for A Channel DC systems and CD481 on 10C650D C Channel ECCS TRIP UNIT OUT OF FILE OR PWR FAIL lights CRIDS page 167 indications 2013 NRC Scenario #2 Page 8 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched to 10C382,

• Crew recognizes loss of Reactor THEN REPORT Low Flow Trip Building Ventilation by:

alarms on all Reactor Bldg Supply/Exhaust Dampers HD-Supply and Exhaust fans. 9370A AND HD-9414A closure Fans trip IF directed to secure RBVS, THEN TRIGGER ET-20.

• CRS implements AB.ZZ-0136.

• Crew verifies that B Control Room vent train automatically starts.

• Crew recognizes that TACS loops failed to automatically swap

• CRS directs manually swapping TACS IAW HC.OP-AB.ZZ-0001, Att 10.

• Crew recognizes various other effects of CD481 loss:

AP210 SACS pump running C Channel LOCA LVL 2 load shed breakers open on 10C650E PCIG valve isolations including common suction line isolation HPCI suction swap to torus 2013 NRC Scenario #2 Page 9 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched to CD481

• Crew dispatches ABEO and inverter , Maintenance to CD481 inverter.

THEN REPORT:

• The Inverter Output breaker CB10 is tripped.

• The AC Reg Output breaker CB302 is tripped

• There is an acrid odor coming from the static switch section

• CRS implements AB.CONT-0002:

Condition B

• CRS recognize the following Must restore CD481 Tech Spec actions apply: within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in Distribution - Operating at least HOT 3.8.3.1 action a SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• CRS contacts Operations Management.

Recirc Pump Seal Failure:

• Crew recognizes second stage First stage seal failure After loss of Inverter actions seal failure on A Recirc pump will occur three minutes are complete, AND at the by: after the second stage.

discretion of the Lead OHA C1-F5 COMPUTER PT Examiner, IN ALARM TRIGGER ET-3 (A Recirc CRIDS D2924 RECIRC Pump Dual Seal Failure). PUMP A SEAL LKG FLOW HI CRIDS D2926 RECIRC PUMP A SEAL STAGE FLOW HILO Lowering second stage seal pressure 2013 NRC Scenario #2 Page 10 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS implements AB.RPV-0003:

Condition D Condition E IF dispatched to report local

• Crew recognizes A Recirc pump RECORD time dual seal pressures on 77 Rx Bldg, dual seal failure by: recirc pump seal failure THEN REPORT readings OHA C1-F5 COMPUTER PT is recognized OR OHA consistent with CRIDS IN ALARM reflash C6-B1 is received (Page 85), Changing seal pressures (whichever is first) for OR the following Monitor Items: Rising seal temperatures ECG Classification.

(Monitor Items are psia) OHA C6-B1 DLD SYSTEM Time: ________

• A Recirc Inbd (#1) Seal ALARM/TRBL rrpsl1(1) - 15 = psig RM11 9AX317/318/320 DLD

• A Recirc Outbd (#2) Seal CCM alarms rrpsl2(1) - 15 = psig RM11 9AX314 DLD Floor Drain Flow alarm Rising drywell pressure

• CRS implements AB.CONT-001:

Condition A

• RO/PO ensure drywell cooling is HPI USED:

maximized. STAR Monitor Items: CREW trips and isolates the RECORD drywell

• HV-F023A A RR pump before DRWL pressure when A rrvf23(1) pressure reaches 1.68 psig by Reactor Recirc pump is

• HV-F100 closing the: isolated:

cuvf100 HV-F023A

• HV-F031A HV-F100 Drywell Pressure: ____

rrvf31(1) HV-F031A

• CRS implements AB.RPV-0006:

Condition B Condition C 2013 NRC Scenario #2 Page 11 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF the Crew scrams during the

• Crew validates successful recirc seal failure, isolation by:

THEN proceed to the ATWS. Seal pressures and Power Oscillations NOT temperatures observed. Trending DLD flows Trending drywell pressure and temperature

• Crew monitors plant response to the transient.

Power Oscillations

• Crew recognizes power ENSURE Trigger ET-5, Power oscillation and locks the mode Oscillations, is activated when switch in Shutdown IAW Recirc Pump A is tripped. AB.RPV-0003 Immediate Operator Actions

• RO performs scram actions IAW AB.ZZ-0001 Attachment 1.

ATWS >4%:

• Crew recognizes Scram RECORD time of Mode Full core hydraulic ATWS w/ Condition and Reactor Power Switch to SHUTDOWN failure of ARI. Above 4% EOP entry condition: or Turbine Trip APRM indications (whichever was first) for Absence of rod FULL IN lights 15 min ECG on the Full Core Display Classification.

Rod position indications Time: _______

2013 NRC Scenario #2 Page 12 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL

• RO performs ATWS actions IAW HPI USED:

TRANSIENT MITIGATION AB.ZZ-0001 Attachment 1. STAR Reactor Scram Reports HARD CARD Following a Reactor scram, the NCO should make an initial scram report by announcing reactor status IAW HC.OP-AB.ZZ-0001. Crew personnel should hold all other non-essential communications until after the initial scram report is complete. The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement directing the NCO to check the overhead alarms, since these actions are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff IAW HC.OPAB.ZZ-0001.

2013 NRC Scenario #2 Page 13 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

• CRS implements EOP-101A.

• Prioritize the Power Leg to establish SLC injection as soon as possible.

• Terminating and Preventing HPCI in a timely manner is critical in order to reduce reactor power by establishing and maintaining a -

50 to -100 RPV level band.

• Maximize steam loads IAW with the post scram pressure control hard card actions when reactor power exceeds bypass valve capability.

• Although Abnormal Operating Procedure HC.OPAB. BOP-0002 guidance for tripping the turbine should still be followed, the impact of tripping the turbine on RPV pressure control should be evaluated and actions taken ahead of time to minimize the impact of the loss of the turbine (e.g., all other steam demands are maximized, turbine parameters are closely monitored to provide the longest time possible for other reactor shutdown actions to be implemented prior to tripping the turbine). If reactor power is within the capability of the turbine bypass valves, the turbine should be tripped without any additional delay.

• After Terminating and Preventing low pressure ECCS, place RHR in suppression pool cooling in order to mitigate reaching 110 degrees F in the Torus with SRVs cycling.

• With limited injection sources, if RPV level stabilizes below -185",

the decision on whether reactor level can be restored above -185" will be based on the time required to insert sufficient negative reactivity to allow reactor level to stabilized above -185".

• As control rods are inserted, reduce injection flow to maintain reactor level low in the assigned band to reduce reactor power.

2013 NRC Scenario #2 Page 14 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

• PO stabilizes and maintains RPV For ATWS conditions where reactor level as directed by CRS.

power remains >4% RTP, the CRS should direct the PO to remain at feedwater to stabilize RPV level.

Under these conditions, the Recirc pumps are already tripped and RWCU has already isolated and the PO should be assigned the action to initiate SLC. The RO, following completion of the post scram hard card ATWS mitigation actions (manual scram and ARI initiation),

should be directed to Terminate and Prevent HPCI injection prior to implementing any other EOP-101A actions such as inhibiting ADS or inserting control rods. The basis for this direction is; 1) to facilitate PO control of RPV level; 2) mitigate the reactor power excursion due to the cold water HPCI injection inside the shroud; and 3) ensure that the main turbine remains available to facilitate RPV pressure control.

• CRS directs:

Initiating SLC Verifying RWCU Isolates

• RO/PO initiate SLC and verify HPI USED:

RWCU isolates. STAR PEER CHECK RWCU Failure to Auto Isolate

• Crew recognizes failure of RWCU to isolate by:

BG-HV-F001 open BG-HV-F004 open InSight Items:

• RO/PO close RWCU HV-F001 HPI USED:

• HV-F001 and HV-F004. STAR cuvf001 Immediate Operator

• HV-F004 action IAW cuvf004 AB.CONT-0002.

2013 NRC Scenario #2 Page 15 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew initiates closure of RWCU RECORD time between HV-F001 OR HV-F004 after starting SBLC pump SBLC Pumps started. and valve closure.

Time: ________

Trip of SLC Pumps:

• Crew recognizes trip of AP208

• BP208 failure inserted SLC pump by:

120 seconds after OHA C1-B1 SLC reactor power is less PUMP/VALVE O/PF than 30% OHA C1-F1 SLC/RRCS INITIATION FAILURE

• AP208 trips 240 CRIDS D3023 SLC INJ PMP seconds after start.

AP208 TROUBLE TRBL Flashing STOP light for AP208 IF dispatched to investigate trip of A(B)P208,

• Crew dispatches NEO and THEN REPORT that the motor Maintenance to investigate trip of is hot to the touch and the A(B)P208 SLC pump.

breaker will not reset.

(52-212063/52-222101)

• CRS determines a SAE Classification is required IAW ECG Section SS3.1 (An automatic scram failed to shutdown the reactor as indicated by reactor power > 4%

AND Manual scram actions taken at the reactor control console (mode switch, manual scram pushbuttons, manual ARI actuation) DO NOT shutdown the reactor as indicated by reactor power > 4%).

2013 NRC Scenario #2 Page 16 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS declares SAE IAW ECG RECORD time SAE Section SS3.1. declared.

(Note: Declaration may be Time completed after scenario termination Declared: _______

at lead evaluators discretion)

• CRS directs inhibiting ADS.

• RO/PO inhibit ADS IAW HPI USED:

AB.ZZ-0001 Att. 13. STAR HARD CARD CREW prevents an This Critical Task is not uncontrolled depressurization applicable if RPV level during ATWS conditions by never reaches -129.

preventing ADS ACTUATION. See justification for failure criteria.

2013 NRC Scenario #2 Page 17 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments REFER to the appropriate EOP

• CRS directs performance of the The timing, order, and and SUPPORT Crew requests following EOPs: priority of the EOP for EOPs IAW with the EO.ZZ-0320 Defeating ARI performance may vary.

following. Validated execution and RPS Interlocks time delays are built-in: EO.ZZ-0301 Bypassing EOP-301: ET-11 MSIV Isolation Interlocks EOP-311: ET-12 EO.ZZ-0311 Bypassing EOP-319: ET-13 Primary Containment EOP-320: ET-14 Instrument Gas Isolation EOP-322: ET-15 Interlocks EO.ZZ-0319 Restoring STRATEGIES FOR SUCESSFUL Instrument Air in an TRANSIENT MITIGATION Emergency Promptly initiate actions IAW the 300 EO.ZZ-0322 Core Spray series EOPs to shutdown the reactor.

Timely actions will reduce the Injection Valve Override potential continued challenges to containment. In addition, once the post scram hard card actions have been completed and RPV level has stabilized in the required band, an NCO should be assigned the responsibility to insert control rods IAW the post ATWS CRD operation hard card and CRAM move sheets.

When control room portions of EOP-320 have been completed and the NCO is ready to re-insert a manual scram, the NCO should perform a crew update and utilize the post scram hard card to implement the applicable post scram actions following the manual scram attempt.

• CRS directs terminating and preventing injection to the RPV with the exception of:

SLC CRD RCIC

• RO/PO terminate and prevent HPI USED:

injection IAW AB.ZZ-0001: STAR Attachment 16 (10C651) HARD CARD Attachment 17 (10C650) 2013 NRC Scenario #2 Page 18 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS directs maintaining RPV Typically, the lower end water level between -50 and of the level band is set

-185. (CRS may direct level above -129.

band of -185 to -129 if level drops low enough)

• RO/PO control level as directed HPI USED:

by CRS with: STAR Feedwater IAW AB.ZZ-0001 HARD CARD Att. 14 If the turbine trips RCIC IAW AB.ZZ-0001 Att. 6 before the reactor is HPCI IAW EOP-322 scrammed, an RRCS feedwater runback may occur.

CREW maintains or restores adequate core cooling by restoring/maintaining Reactor water level to >-185" IAW HC.OP-EO.ZZ-0101A without Emergency Depressurizing.

• CRS directs bypassing the RWM and commencing manual rod insertion.

• RO/PO align CRD for ATWS HPI USED:

operation IAW AB.ZZ-0001 STAR Attachment 18. HARD CARD

• RO/PO bypass RWM and insert HPI USED:

control rods IAW RE-AB.ZZ-0001 STAR Attachment. 1. HARD CARD 2013 NRC Scenario #2 Page 19 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Total Loss of EHC:

• Crew recognizes trip of the B

~6 min after the plant is EHC pump by:

tripped, OR at the discretion of OHA D3-F5 TURB HYDR the Lead Examiner, PUMP TROUBLE ENSURE/TRIGGER ET-7 (Trip of the B EHC pump).

Note: the BPVs will fail close

~3 min after total loss of EHC.

• Crew recognizes turbine bypass valves failing shut by:

OHA D3-D5 EHC UNIT PANEL 10C363 DEHC Bypass Valve Positioning Error alarms Reactor pressure rising above Pressure Setpoint STRATEGIES FOR SUCESSFUL When pressure control TRANSIENT MITIGATION

• CRS directs stabilizing pressure Pressure Leg below 1037 psig with: swaps to SRVs, Direct initial pressure control as Main Steam Line Drains maintaining RPV water Stabilize pressure 800 psig to 1000 SRVs level between -50 and psig. The lower limit of 800 psig will RPFT -129 will be very not complicate RPV level challenging due to maintenance and will prevent an unwanted cooldown. The upper limit shrink and swell and of 1000 psig is a round number below changing reactor 1047 psig. pressure with the RFPTs in MAN.

• RO/PO control pressure as HPI USED:

directed by CRS with: STAR Main Steam Line Drains IAW HARD CARD AB.ZZ-0001 Att. 15 SRVs IAW AB.ZZ-0001 Att. 13 RFPTs 2013 NRC Scenario #2 Page 20 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

OHA C8-F1 SUPPR POOL TEMP HIGH Flashing 95 degree status light on 10C650C RM11 9AX833/834 alarm Various Suppression Pool temperature indicators Strategies For Successful Transient Mitigation

• CRS implements EOP-102.

Torus Temperature Leg Start all available Torus cooling as soon as possible to remove heat from containment.

• CRS directs placing AP202 RHR pump in Suppression Pool Cooling and Suppression Chamber Spray (as required).

• RO/PO place AP202 RHR pump HPI USED:

in Suppression Pool Cooling and STAR Suppression Chamber Spray (as HARD CARD required) IAW AB.ZZ-0001 Att. 3.

2013 NRC Scenario #2 Page 21 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP-102 Primary Containment Control.

Primary Containment Pressure Leg When controlling Primary Containment Pressure and it becomes apparent that the PSP curve is going to be exceeded and Torus level is in the normal band, the Control Room Supervisor should pick 15 psig Torus Pressure to determine if the pressure can be maintained below the PSP limit. The 15 psig limit is below the PSP limit and will allow sufficient time to evaluate further actions needed such as EOP-202 RPV blowdown. If no systems are available to restore and maintain Torus Pressure, it is expected that you would enter EOP-202 and blowdown prior to exceeding PSP.

HPI USED:

STAR HARD CARD BP202 is not available due to 10D420 failure.

Failure of RHR Torus Cooling

• Crew recognizes failure of Valve to Open HV-F024A by:

OHA A6-B1 RHR LOOP A NOTE: The first loop of RHR TROUBLE Flashing OVLD/PWR FAIL placed in Suppression Pool Loss of position indication Cooling will have its F024 valve No indication of SP cooling trip its breaker. Response shown for A Loop. flow CRIDS D4439 RHR PMP A TEST HV-F024A OPF IF dispatched to investigate trip

• Crew dispatches NEO and of HV-F024A breaker, Maintenance to breaker for THEN REPORT the breaker is HV-F024A (52-212192).

tripped and will not reset.

2013 NRC Scenario #2 Page 22 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS directs B Loop of RHR placed in Suppression Pool Cooling.

• RO/PO places B RHR Loop in HPI USED:

Suppression Pool Cooling IAW STAR AB.ZZ-0001 Att. 3. HARD CARD

• IF Suppression Pool temperature is >110 degrees, AND Reactor power is >4%,

AND SRVs are open or cycling, THEN Crew terminates and prevents injection to the RPV with the exception of SLC, CRD, and RCIC, UNTIL Reactor power is <4%,

OR RPV level reaches -129, OR SRVs remain closed.

• IF RPV level reaches -129, HPI USED:

THEN RO/PO terminate and STAR prevents injection from Core HARD CARD Spray IAW AB.ZZ-0001 Attachment 16.

WHEN the Crew has reset

• WHEN EOP-320 Section 5.1 and HPI USED:

RPS, 5.2 are complete, STAR THEN DELETE Malfunctions THEN the Crew implements PEER CHECK RP06 and RP07 to allow full EOP-320 Section 5.3 and reset rod insertion on the next scram. RPS.

At the Lead Examiners

• WHEN OHA C6-E4 clears, HPI USED:

discretion, MODIFY InSight THEN the Crew initiates a STAR Item lclsdv to accelerate manual scram IAW EOP-320 PEER CHECK draining of the SDV. Section 5.3.

CREW fully inserts all control rods via RMCS and/or manual scram(s) IAW HC.OP-EO.ZZ-0320.

2013 NRC Scenario #2 Page 23 of 30 Rev: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes the reactor is shutdown by:

SPDS ALL RODS IN RWM Confirm Shutdown CRIDS Rod positions Termination Requirement:

• CRS exits EOP-101A, enters The scenario may be EOP-101.

terminated at the discretion of the Lead Examiner when:

• RPV Level is being maintained above -185 AND

• All rods are fully inserted 2013 NRC Scenario #2 Page 24 of 30 Rev: 4

VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-101-111-1003 Use of Procedures M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-101-111-1004 Operations Standards O. OP-AA-101-112-1002 On-Line Risk Assessment P. OP-AA-106-101-1001 Event Response Guidelines Q. OP-HC-108-106-1001 Equipment Operational Control R. OP-AA-108-114 Post Transient Review S. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program T. HC.OP-SO.AE-0001 Feedwater System Operation U. HC.OP-SO.EC-0001 Fuel Pool Cooling and Cleanup System V. HC.OP-SO.SF-0003 Rod Worth Minimizer Operation W. HC.OP-AB.ZZ-0001 Transient Plant Conditions X. HC.OP-AB.CONT-0001 Drywell Pressure Y. HC.OP-AB.CONT-0001 Drywell Leakage Z. HC.OP-AB.COOL-0003 Reactor Auxiliary Cooling AA. HC.OP-EO.ZZ-0311 Bypassing Primary Containment Instrument Gas Isolation Interlocks BB. HC.OP-EO.ZZ-0319 Restoring Instrument Air in an Emergency CC. HC.OP-EO.ZZ-0320 Defeating ARI and RPS Interlocks DD. HC.OP-EO.ZZ-0322 Core Spray Injection Valve Override EE. HC.OP-EO.ZZ-0306 Venting the Scram Air Header FF. HC.OP-EO.ZZ-0101 RPV Control GG. HC.OP-EO.ZZ-0101A ATWS-RPV Control HH. HC.OP-EO.ZZ-0102 Primary Containment Control 2013 NRC Scenario #2 Page 25 of 30 Rev: 4

VII. ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #2, Rev 04 1.

CREW prevents an uncontrolled depressurization during ATWS conditions by preventing ADS ACTUATION.

K/A 218000 Automatic Depressurization System A4 Ability to manually operate and/or monitor in the control room:

A4.04 ADS inhibit RO 4.1 SRO 4.1 Given the current ATWS conditions of this scenario, preventing ADS automatic operation and potential uncontrolled reactor level flood up prevents a significant transient and subsequent positive reactivity addition to the reactor. EOPs direct this action under the current conditions.

This critical task is only applicable if RPV water level goes below -129. Failure to satisfactorily complete the task is demonstrated by an automatic ACTUATION of ADS such that the ADS SRVs open and reduce reactor pressure by 300 psig.

2.

CREW maintains or restores adequate core cooling by restoring/maintaining Reactor water level to >-185" IAW HC.OP-EO.ZZ-0101A without Emergency Depressurizing.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2 Ability to determine and/or interpret the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA2.02 Reactor water level RO 4.1 SRO 4.2 Maintaining adequate Core cooling under ATWS conditions is accomplished by maintaining/restoring level above -185". HPCI and RCIC are capable of maintaining level under the current conditions. AB.ZZ-0001 provides directions on manual initiation of HPCI which will mitigate the automatic initiation failure. An Emergency Depressurization is not warranted and would result in a large injection of cold water and the potential displacement of boron from the core.

3.

CREW fully inserts all control rods via RMCS and/or manual scram(s) IAW HC.OP-EO.ZZ-0320.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1. Ability to operate and/or monitor the following as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:

EA1.01 Reactor Protection System RO 4.6 SRO 4.6 EA1.07 RMCS RO 3.9 SRO 4.0 Inserting all control rods provides a substantial negative reactivity addition. It is critical for the crew to implement a method to insert control rods and shut the reactor down. Failure to complete this action may result in requiring RPV level to be lowered to or below TAF to reduce power to

<4%. This represents a significant challenge to maintaining adequate core cooling.

2013 NRC Scenario #2 Page 26 of 30 Rev: 4

2013 NRC Scenario #2, Rev 04 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE Y/N EVENT Y/N EVENT Loss Of Offsite Power/SBO Internal Flooding LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Y Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N KEY SYSTEMS HPCI SRVs RCIC Condensate/Feedwater B/D EDG SSW A/B RHR Pump RPS A/B SACS Loop 1E 4.16KV Bus 1E 480 VAC Bus Y 120VAC 481 Inverter 1E 125VDC Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Manual Depressurization of the RPV w/ no HP Injection Available Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal Y Control RPV Water Level w/ HP Injection during ATWS Sequence Align Portable Power Supply to Battery Chargers Venting of Primary Containment Restore Switchgear Cooling Restart Condensate Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG.

2013 NRC Scenario #2 Page 27 of 30 Rev: 4

VIII. TURNOVER SHEET:

ONLINE RISK: GREEN WORK WEEK CHANNEL: A PROTECTED EQUIPMENT B EHC Pump REACTIVITY / Plant Status 100% Power Reduce power to 90% IAW RE Guidance and HC.OP-IO.ZZ-0006.

ESF/SAFETY SYSTEMS Initiate N2 makeup to the primary containment to test the flow recorder (a calibration was just performed).

HC.OP-SO.GS-0001 completed through step 5.2.8.

COOLING WATER None BOP A EHC Pump tagged for planned maintenance ELECTRICAL None ADVERSE CONDITION MONITORING None 2013 NRC Scenario #2 Page 28 of 30 Rev: 4

IX. SIMULATOR ESG REVIEW/VALIDATION CHECKLIST Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG: Scenario 2 SELF-CHECK

1. Total malfunctions inserted: 5-8

2. Malfunctions that occur after EOP entry: 1-4

3. Abnormal Events: 1-2

4. Major Transients: 1-2

5. EOPs used beyond primary scram response EOP: 1-3

6. EOP Contingency Procedures used: 0-3

7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8. EOP run time: 40-70% of scenario run time

9. Crew Critical Tasks: 2-5

10. Technical Specifications are exercised during the test: >1 Comments:

Scenario 2 Page 29 of 30 Rev.: 02

EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (cont)

Crew Validation Rev: 04 Date Validated: 7/23/13 One Hour Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition Scenario 2 Page 30 of 30 Rev.: 092

SIMULATOR EXAMINATION SCENARIO GUIDE APRM Upscale, Single Rod Scram, Loss of Drywell Clg, Loss of SCENARIO TITLE:

10B430, HPCI Steam Leak, ED SCENARIO NUMBER: Scenario #3 2013 NRC Exam EFFECTIVE DATE: Effective when approved.

EXPECTED DURATION: 60 minutes REVISION NUMBER: 4 PROGRAM: L.O. REQUAL X INITIAL LICENSE OTHER REVISION

SUMMARY

1. 2013 Initial NRC Exam.

2. Deletes FRVS Vent Fan trip.

3. Deletes both EHC pump trips.

4. Deletes TBV failure to open.

5. Deletes D SRV stuck open.

6. Adds Malf RP04, RZ03B, and RZ03C for RPS failure with ARI works.

7. Adds 1&2 FWHTR condensate valves fail closed during scram.

PREPARED BY: On File 5/27/13 NRC Examiner DATE Reviewed BY: On File Chief Examiner DATE APPROVED BY: On File OLB Branch Chief DATE APPROVED BY:

LORT Group Lead or Designee DATE APPROVED BY:

Shift Operations Supervisor or Designee DATE

I. OBJECTIVE(S):

Enabling Objectives A. The crew must demonstrate the ability to operate effectively as a team while completing a series of CRITICAL TASKS, which measure the crew's ability to safely operate the plant during normal, abnormal, and emergency plant conditions.

(Critical tasks within this examination scenario guide are identified with an *.)

II. MAJOR EVENTS:

A. APRM channel C Upscale w/Single Rod Scram B. Loss of TB Chilled water C. Loss of 10B430 D. HPCI Steam Leak w/Failure to Isolate E. RPS manual and auto failure (ARI successful)

F. RCIC Pump Room High Temperature III. SCENARIO

SUMMARY

The scenario begins with the plant at 75% power and TACS on the B SACS loop. The DK111 Turbine Chiller is C/T for a Freon leak and CP161 is C/T for a bearing oil leak. The turnover directed the crew to raise power using recirc flow. After the power maneuver, C APRM fails upscale causing a half scram. Due to a mispositioned SRI Test Toggle switch, a single rod will scram in when the RPS half scram occurs. After Tech Specs have been referenced, the AP161 will trip due to a bearing problem. The BP161 goes into runout and trips shortly thereafter. This results in a loss of TB Chilled water, which will require the Crew to align RACS to cool the drywell and vent the drywell to restore pressure back below 0.75 psig. After the Loss of Drywell Cooling has been addressed, the 10B430 1E 480 VAC Unit Substation will be lost due to a transformer failure. This will result in a loss of the operating CRD pump and the CP228 ECCS jockey pump.

HPCI will then inadvertently initiate, requiring the crew to take action to prevent unwarranted injection. After these failures are addressed, a steam leak develops in the HPCI room. The inboard steam isolation valve is not available due to the loss of the 10B430 Substation, and the outboard steam isolation valve binds and will not close. The leak will impact the RCIC room, due to the door between HPCI and RCIC not being properly dogged shut. When HPCI room temperature reaches 200 degrees, the door will pop open, admitting steam to the RCIC room.

The unisolable leak will require the Crew to scram. RPS and the mode switch will fail to SCRAM the unit, requiring ARI for successful shutdown. The 1 & 2 FWHTR condensate valves will fail closed after the scram complicating level control. The rising temperatures in the HPCI and RCIC rooms will ultimately require Emergency Depressurization.

2013 NRC Scenario #3 Page 2 of 33 Rev.: 4

IV. INITIAL CONDITIONS:

I.C.

Initial INITIALIZE the simulator to 100% power, MOL.

REDUCE reactor power to 75% using recirc.

REMOVE and BLOCK Crossflow BEFORE going to RUN.

ENSURE BOTH Steam Tunnel unit Coolers are in service.

ENSURE the A CRD pump is in service.

ENSURE the A EHC pump is in service.

ENSURE TACS is being supplied by the B SACS loop.

ENSURE the B Control Room Vent Train is in service.

ENSURE the C SSW pump is in standby.

ENSURE the C SACS pump is in standby.

C/T CP161 TB Chilled water circ pump as follows:

• ENSURE CP161 is not in service.

• PLACE CP161 in MAN.

C/T DK111 as follows:

• ENSURE DK111 is not in service

• PRESS DK111 STOP pushbutton

• ENSURE HV-9503D is CLOSED ENSURE associated Schedule files open and running.

ENSURE associated Events file open.

PREP FOR TRAINING (i.e., RM11 set points, procedures, bezel covers)

Initial Description PLACE red bezel cover on DK111.

PLACE red bezel cover on HV-9503D.

PLACE red bezel cover on CP161.

PREPARE a Fire Alarm for FA015 Fire Zone 4109.

At a minimum review the Scenario Reference section and CLEAN the bolded EOPs, ABs and SOPs listed.

(80091396 0270)

TREND plant parameters needed for Critical Task determination:

o HPCI Room Temperature o RCIC Room Temperature o Reactor Pressure o Wide Range RPV Level COMPLETE Simulator Ready-for-Training/Examination Checklist.

2013 NRC Scenario #3 Page 3 of 33 Rev.: 4

EVENT FILE:

Initial ET #

Event code: hpvv(1) <= 0.90 // HPCI HV-F003 valve position 6

Description:

Trips breaker for HPCI HV-F003 when closure is attempted from the Control Room.

Event code: hvtr4111 > 160 // HPCI Room Temp 7

Description:

Triggers RCIC Steam leak to allow raising RCIC Room temp.

Event code: crqnmi <= 15 // Reactor Power 8

Description:

Inserts HPCI Steam Leak at 40% on reactor scram.

Event code: rrprv < 650 // Reactor Pressure in psia 9

Description:

Raises severity of HPCI leak if Crew depressurizes Event code: hvtr4111 > 200 // HPCI Room Temp 10

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 210 // HPCI Room Temp 11

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 220 // HPCI Room Temp 12

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 230 // HPCI Room Temp 13

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 240 // HPCI Room Temp 14

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 250 // HPCI Room Temp 15

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 255 // HPCI Room Temp 16

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 260 // HPCI Room Temp 17

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 265 // HPCI Room Temp 18

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 270 // HPCI Room Temp 19

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 271 // HPCI Room Temp 20

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 272 // HPCI Room Temp 21

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 273 // HPCI Room Temp 22

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 274 // HPCI Room Temp 23

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 275 // HPCI Room Temp 24

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 276 // HPCI Room Temp 25

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 277 // HPCI Room Temp 26

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code: hvtr4111 > 278 // HPCI Room Temp 27

Description:

Raises RCIC Room Temperature as HPCI Room Temperature rises.

Event code:

Description:

2013 NRC Scenario #3 Page 4 of 33 Rev.: 4

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description CRYWOLF ANN E5F1 CHILLED WTR None None Insert malfunction AN-E5F1 SYSTEM TROUBLE HPCI steam isolation valves F002 & F003 None None Insert malfunction HP10 failure to auto close None None Insert malfunction RP04 on event 6 Failure of RPS to SCRAM (ATWS)

None None RRCS Channel A - Logic B Failure to Insert malfunction RZ03B Auto Initiate None None RRCS Channel B - Logic A Failure to Insert malfunction RZ03C Auto Initiate None None Insert malfunction NM21C to 100 on event 1 APRM C failure None None Insert malfunction CD060227 on event 1 Control Rod 02-27 SCRAM None None Insert malfunction CW18A on event 2 Chilled water circ pump AP161 trip Insert malfunction CW18B after 5 on None None Chilled water circ pump BP161 trip event 2 None None Insert malfunction ED13C1 on event 3 Loss of 480 VAC essential bus C 10B430 Insert malfunction HP09 from 5.00000 HPCI steam line break inside HPCI Room None None to 40.00000 in 60 on event 5 4111 CRYWOLF ANN A2A5-FIRE PROT None None Insert malfunction AN-A2A5 on event 5 PANEL 10C671 Insert malfunction RC09 to 1.00000 on RCIC steam line break inside the RCIC None None event 7 ROOM 4110 None None Insert malfunction FW30A on event 8 Heater 2A hi level switch failure None None Insert malfunction FW30B on event 8 Heater 2B hi level switch failure None None Insert malfunction FW30C on event 8 Heater 2C hi level switch failure Insert malfunction CD030227 on event None None Control Rod 02-27 stuck 28 2013 NRC Scenario #3 Page 5 of 33 Rev.: 4

MALFUNCTION SCHEDULE:

Initial @Time Event Action Description None 4 Set hp_k90 = true 1020 HPCI MAN INIT None 5 Set hvtr4111 = 135 None 7 Set hvtr4110 = 135 Insert malfunction HP09 after 1 from HPCI steam line break inside HPCI Room None 8 40.00000 to 40.00000 4111 Insert malfunction HP09 after 1 from HPCI steam line break inside HPCI Room None 9 60.00000 to 60.00000 4111 None 10 Set hvtr4110 = 150 None 11 Set hvtr4110 = 170 None 12 Set hvtr4110 = 180 None 13 Set hvtr4110 = 190 None 14 Set hvtr4110 = 200 None 15 Set hvtr4110 = 210 None 16 Set hvtr4110 = 220 None 17 Set hvtr4110 = 230 None 18 Set hvtr4110 = 240 None 19 Set hvtr4110 = 245 None 20 Set hvtr4110 = 246 None 21 Set hvtr4110 = 247 None 22 Set hvtr4110 = 248 None 23 Set hvtr4110 = 249 None 24 Set hvtr4110 = 250 None 25 Set hvtr4110 = 251 None 26 Set hvtr4110 = 252 None 27 Set hvtr4110 = 253

REMOTE SCHEDULE:

Initial @Time Event Action Description CW33 Turbine Bldg chiller CK111 None None Insert remote CW33B to 50 Winterization HP04 GROUP 5A HV-F002 HPCI Steam None None Insert remote HP04 to FAIL_OPEN Supply Isol Insert remote HP06 to RACK_OUT on HP06 GROUP 5A HV-F003 HPCI Steam None None event 6 Supply Isol Insert remote HV06 to STOP on event None None HV06 RBVS Supply fan C 29 Insert remote HV05 after 1 to STOP on None None HV05 RBVS Supply fan B event 29 Insert remote HV04 after 1 to STOP on None None HV04 RBVS Supply fan A event 29 Insert remote HV03 after 2 to STOP on None None HV03 RBVS Exhaust fan C event 29 Insert remote HV02 after 3 to STOP on None None HV02 RBVS Exhaust fan B event 29 Insert remote HV01 after 3 to STOP on None None HV01 RBVS Exhaust fan A event 29 Insert remote CX11 after 120 to OPEN CX11 CX valve AP-V041 to Core Spray None None on event 30 header A Insert remote CX15 to OPEN on event CX15 CX valve AP-V044 to RHR header None None 30 A Insert remote CX17 after 60 to OPEN CX17 CX valve AP-V047 to RHR header None None on event 30 C 2013 NRC Scenario #3 Page 7 of 33 Rev.: 4

OVERRIDE SCHEDULE:

Initial @Time Event Action Description INOP-CHILLED WATER CPRSR DC111-None None Insert override 1A181_A2_LO to On CPRSR MOT (LO)

DK111 START-CHILLED WATER CPRSR None None Insert override 1A181_D_DI to Off DC111-CPRSR MOT (DI)

SAFETY CKT COMPLETE/ON-CHILLED None None Insert override 1A181_E1_DI to Off WATER CPRSR DK111 (DI)

STOP-CHILLED WATER CPRSR DC111-None None Insert override 1A181_F_LO to Off CPRSR MOT (LO)

HV-9503D OPEN-CH W DISCH SHUTOFF None None Insert override 1A182_E_DI to Off V (DI)

HV-9503D CLOSE-CH W DISCH None None Insert override 1A182_F_LO to Off SHUTOFF V (LO)

None None Insert override 1A136_A2_LO to On INOP-CH W CIRC PUMP CP161 (LO)

None None Insert override 1A136_D_DI to Off AUTO-CH W CIRC PUMP CP161 (DI)

None None Insert override 1A136_E_DI to Off START-CH W CIRC PUMP CP161 (DI)

None None Insert override 1A136_F_LO to Off STOP-CH W CIRC PUMP CP161 (LO) 2013 NRC Scenario #3 Page 8 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Raise Power Using Recirc Flow:

• CRS directs ATC to raise power 5% using Recirc Flow.

After the crew assumes the watch they will raise power per ATC adjusts Recirc flow and maneuvering sheet. monitors Reactor power, pressure, and level and ensure plant conditions are stable.

APRM C Upscale w/Single

• Crew monitors Reactor power, Rod Scram: pressure, and level and ensure After the Crew raises power, plant conditions are stable.

OR, Ensures no scram setpoints have at the discretion of the Lead been exceeded

Examiner, TRIGGER ET-1.

• Crew recognizes RPS 1/2 scram by:

OHA C3-A3 REACTOR SCRAM TRIP LOGIC A2 RPS Trip Logic A2 NORMAL/RESET status lights extinguished Pilot Scram Valve Solenoid LOGIC A NORMAL status lights for all four groups extinguished.

CRIDS D2132 REACTOR SCRAM Y TRIP 2013 NRC Scenario #3 Page 9 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes APRM C Upscale by:

C5-A1 NEUTRON MONITORING SYSTEM C3-C4 APRM SYS A TRIP/INOP C3-D4 APRM UPSCALE D2143 APRM CHANNEL C UPSCALE TRIP D4306 APRM CH C UPSCALE THERMAL TRIP C023 APRM INOPERATIVE

• Crew recognizes single rod scram by:

OHA C6-E3 ROD DRIFT Rod 02-27 DRIFT, SCRAM, and FULL IN lights on Full Core display RWM DR 02-27 indication CRIDS C078 ROD DRIFT ALARM ALM

• Crew ensures only one rod is drifting.

2013 NRC Scenario #3 Page 10 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments WHEN requested,

• CRS implements AB.IC-0001 THEN as RE, REPORT: Condition C

• Thermal Limits are SAT.

• All other control rods are at target their position.

• There is no immediate problem with leaving 02-27 inserted.

• You will develop a recovery plan to withdraw 02-27.

IF dispatched to troubleshoot Crew dispatches RBEO to 02-27 rod 02-27 scram, HCU.

THEN REPORT you found the B S.R.I. test toggle on the

• Crew contacts Rad Pro to survey 02-27 HCU out of Normal.

scram discharge volume due to There are workers change in radiological conditions.

decontaminating the HCU bank, and one of them

• RO resets the Rod Drift alarm remembers bumping IAW HC.OP-AR.ZZ-0020.

something. (02-27 is in the North HCU bank by HPCI pipechase. See EOP-303 map.)

REMOVE Malfunction

• RO bypasses APRM C.

CD060227 when RPS is reset.

• RO resets RPS half scram.

• Crew contacts Maintenance to troubleshoot APRM C failure.

• SM contacts Operations Management 2013 NRC Scenario #3 Page 11 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF directed to electrically

• CRS determine Tech Spec For both T/S, still meet disarm rod 02-27, actions required. Enter Action the Minimum Operable THEN TRIGGER ET-28 to statement for: Channels per Trip INSERT Malfunction cd030227 Reactor Protection System Function. Tracking (stuck rod). Instrumentation Action statement only.

3.3.1 Control Rod Block Instrumentation 3.3.6 (Crew may declare rod 02-27 inoperable until cause of scram is determined and enter T/S 3.1.3.1).

Loss of Drywell Cooling:

• Loss of Drywell Cooling by: Drywell pressure will After TS call has been OHA E5-E1 CHILLED WTR peak at less than 1.2 addressed or at the discretion PANEL 10C152 psig; however, of the Lead Examiner, OHA E5-F1 CHILLED WTR IF the Crew manually TRIGGER ET-2 (Loss of TB SYSTEM TROUBLE scrams during the Loss Chilled Water/Drywell Cooling). Flashing OVLD/PWR FAIL, of Drywell Cooling, HI/LOW FLOW, and STOP THEN the HPCI Steam lights on AP161 and BP161 Leak will be TB Chilled Water Circ pumps automatically inserted.

Loss of START lights on AK111/BK111 TB Chillers CRIDS D5608 CHW PUMP AP161 MALFUNCTION CRIDS D5609 CHW PUMP BP161 MALFUNCTION CRIDS D4053 WTR CHILLER AK111 REMOTE PANEL TRBL CRIDS D4054 WTR CHILLER BK111 REMOTE PANEL TRBL Rising drywell temperature Rising drywell pressure

• CRS implements AB.CONT-001:

Condition A Condition B 2013 NRC Scenario #3 Page 12 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew announces loss of Turbine Building Chilled Water on the plant page.

• RO/PO ensure drywell cooling is maximized.

IF dispatched to investigate

• Crew dispatches TBEO and loss of TB Chilled Water, Maintenance to investigate.

THEN REPORT:

• AK111 and BK111 have Evaporator Low Water Flow alarms in

• AP161 and BP161 have Discharge Flow Hi/Low alarms in

• Both AP161 and BP161 motors are hot to the touch

• AP161 inboard pump bearing is hot to the touch

• RO/PO align RACS to supply drywell cooling IAW Drywell pressure will AB.CONT-0001 Condition B. begin to drop as soon as the RACS and Chilled Water valves start to swap. The 9532-1/2 are not in the RACS flowpath.

IF directed to prepare a release

• IF Drywell Pressure is not permit, restored below 0.75 psig, THEN REPORT it will take THEN CRS implements about 30 minutes and AB.CONT-0001:

REQUEST the Crew to record Condition C start and stop times for the release.

• IF directed, THEN PO Vents the drywell IAW AB.CONT-001 Condition C.

2013 NRC Scenario #3 Page 13 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS contacts Operations Management to initiate a Prompt Investigation and ERT callout.

Loss of 10B430 Unit Sub:

• Crew monitors Reactor power, After the Crew aligns RACS to pressure, and level and ensures cool the drywell, plant conditions are stable.

OR, at the discretion of the Lead

Examiner, TRIGGER ET-3.

• Crew recognizes loss of AP207 CRD pump by:

OHA C6-F2 CRD SYSTEM TROUBLE AP207 OVLD/PWR FAIL light AP207 flashing STOP light CRIDS D2244 CRD WATER PUMP A MOTOR TRBL 2013 NRC Scenario #3 Page 14 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes loss of CP228 RHR and Core Spray ECCS Jockey pump by: Low Pressure alarms OHA A6-C3 ECCS JOCKEY will not be received if PUMP 1CP228 TROUBLE Condensate Transfer is Jockey pump indications on lined up before 10C650A discharge header OHA A6-B1 RHR LOOP A pressures decay to TROUBLE alarm setpoints.

OHA A6-B2 RHR LOOP C (11 minutes)

TROUBLE OHA B3-C1 CORE SPRAY LOOP A TROUBLE CRIDS D4434 ECCS JOCKEY PMP CP228 OPF CRIDS D4373 RHR PUMP A DISCHARGE PRESSURE HILO CRIDS D4397 RHR PUMP C DISCHARGE PRESSURE HILO CRIDS D3157 CS LOOP A INJECTION LINE PRESSURE HILO

• Crew recognizes loss of AK202 Instrument gas PCIG compressor by: pressure is not actually OHA A1-A1 INST GAS low. The alarm is the SYSTEM A TROUBLE result of a loss of power OHA A1-A3 INST GAS to the AC213 panel.

RECEIVER A PRESSURE LO OHA A1-A5 INST GAS PANEL A/B C213 Loss of START and STOP indication for AK202 2013 NRC Scenario #3 Page 15 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes loss of 10B430 Unit Substation by:

OHA E3-E3 USS FEEDER BRKR TRBL OHA E3-F2 4.16KV FDR TO USS XFMR BRKR MALF CRIDS D4565 4.16KV BUS A403 FDR CKT BRKR TRBL CRIDS D4611 UNIT SUBSTA 10B430 FDR CKT BRK TRBL Flashing TRIP light on 40310 breaker Various OVLD/PWR FAIL lights on C Channel equipment

• Crew announces loss of the 10B430 bus on the plant page.

IF dispatched to 10B430,

• Crew dispatches ABEO and THEN REPORT: Maintenance to investigate the

• 52-40310 has 51B and 51C loss of the 10B430 bus.

Time overcurrent trip flags dropped

• CX400 xfmr is very warm with acrid odor and telltale in the red zone

• CRS implements AB.ZZ-0172.

SUPPORT any requests for

• Crew places BP207 CRD pump Accumulator trouble BP207 discharge valve in service IAW either: alarms will begin to manipulations with Remote SO.BF-0001 Sect 5.2 come in after about 14 Function CD02. OR minutes with no CRD HC.OP-AB.22-0001 Hardcard pump in service.

OR ARP for CRIDS D2244 2013 NRC Scenario #3 Page 16 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments AVERAGE HCU accumulator

• CRS directs aligning Condensate pressure can be read with Transfer keepfill to A Core InSight Item lcpac. Spray loop and A/C RHR loops.

INDIVIDUAL HCU accumulator pressures can be read with InSight Item lcpaccx(n). See Sim Op Manual under Reactor Building Operator for n value.

• IF any HCU accumulators become inoperable with no CRD pump I/S, THEN CRS implements AB.IC-0001:

Condition A IF dispatched to align AP to A

• RO/PO coordinate with RBEO to Core Spray and A & C RHR align Condensate Transfer IAW THEN: SO.BC-0001 for removal of

• REFER to SO.BC-0001 CP228 from service.

Section 5.9

• TRIGGER ET-30 to open AP-V044/V047/V041

• Crew places BK202 PCIG compressor in AULD.

• CRS/STA recognize the following Must re-energize Tech Spec applies: 10B430 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Distribution - Operating or be in at least HOT 3.8.3.1 action a SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

May cascade to T/S 3.8.2.1.a due to loss of CD444 battery charger (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO) 2013 NRC Scenario #3 Page 17 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• IF any HCU accumulators Within 20 minutes of become inoperable with no CRD discovery, restore pump I/S, charging water THEN CRS recognize the pressure >= 940 psig or following Tech Spec applies: place Mode switch in Control Rod Scram SHUTDOWN.

Accumulators 3.1.3.5 action a.2.a IF directed to perform fill and

• CRS refer to OP-HC-108-115- Actions required for vent. 1001 for loss of CP228 ECCS jockey pump are THEN REPORT no air found. jockey pump AND for SSW to dependent on whether RACS isolation valves. discharge header low pressure alarms were received for Core Spray and RHR loops.

• CRS contacts Operations Management to initiate an ERT callout.

Inadvertent HPCI Initiation:

• Crew recognizes inadvertent After loss of 10B430 actions HPCI initiation by:

are complete OHA B3-B5 CORE SPRAY OR LINE BREAK At the discretion of the lead OHA B1-E5 HPCI PUMP evaluator, TRIGGER ET-4 DISCHARGE FLOW LO Inadvertent HPCI Initiation OHA A7-B5 RPV LEVEL 7

• Crew implements HC.OP-AB.RPV-0001, Condition C

• Crew verifies Reactor Level > -

38 AND Drywell Pressure <

1.68#

• Crew terminates AND Prevents HPCI Injection IAW HC.OP-AB.ZZ-0001 Attachment 16 2013 NRC Scenario #3 Page 18 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew DEPRESSES the initiation Logic RESET PB AND VERIFIES HV-F006 is CLOSED (if required, override and close IAW Att 2)

Steam Leak in HPCI Room:

• Crew recognizes a steam line B1-A5 and ISLN INIT After actions for inadvertent break in the HPCI room by: status lights will be HPCI initiation are completion, OHA B1-A5 HPCI STEAM received when the leak OR at the discretion of the LINE DIFF PRESSURE HI severity reaches 23%

Lead Examiner, OHA A2-A5 FIRE PROT (about 30 seconds)

TRIGGER ET-5 AND PANEL 10C671 PROVIDE Fire Computer Fire Comp Pt FA015 RM indication of point FA015 (Fire 4111 HPCI PUMP AND Computer point may be TURBINE ROOM provided by Examiner or by HPCI room temperature Fire Computer Simulation). trending up (Rm 4111)

Lowering Main Gen MWe Offsite release rate trending up HPCI Turbine Inlet Pressure on PI-R602.

ISLN INIT status lights InSight Items:

• Crew announces steam leak in

• HPCI Room Temp HPCI room on plant page.

hvtr4111

• RCIC Room Temp hvtr4110 IF dispatched to HPCI Room,

• Crew recognizes failure of HPCI The HV-F002 is THEN REPORT the room is to isolate by: powered from the filled with steam. HV-F002 power failure 10B430 bus.

F003 valve position HPCI room temperature trending up (Rm 4111)

• PO attempts to close HV-F003 Immediate Operator using Control Room keylock Action IAW switch. AB.CONT-0002 2013 NRC Scenario #3 Page 19 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes failure of RECORD time when HV-F003 to close by: switch for HV-F003 is in OHA B1-F3 HPCI CLOSE AND OHA COMPONENT O/PF B1-A5 is in alarm for 15 OVLD/PWR FAIL light min ECG Classification.

CRIDS D3513 HPCI ST Time: _______

LINE ISLN HV-F003 OPF HPCI room temperature continuing to trending up (Rm 4111)

Main Gen MWe continuing to trend down Offsite release rate continuing to trend up IF dispatched to reclose

• Crew dispatches RBEO and ARP for D3513 gives breaker 52-212053, Maintenance to breaker for breaker number.

THEN REPORT the breaker HV-F003 (52-212053) will not close.

IF dispatched to the HV-F003

valve, THEN REPORT the valve is bound and will not close.

2013 NRC Scenario #3 Page 20 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• CRS determines an SAE Classification is required IAW ECG Section:

RB3.L VALID isolation signal exists with an UNISOLABLE Break outside primary containment (after isolation from the Control Room has or should have been attempted) in ANY of the following systems: HPCI steam line (5 pts.)

CB3.L UNISOLABLE leakage outside primary containment (after isolation from the Control Room has or should have been attempted)

AND Direct downstream pathway to the environment exists. (3 pts.) OR CB5.L UNISOLABLE primary system leakage outside primary containment (after isolation from the Control Room has or should have been attempted) as indicated by exceeding EITHER of the following: (3 pts.)

• ANY EOP 103 Reactor Bldg room temp Table 1, Column 2 (Max Safe)

• ANY Reactor Bldg rad level > 1000 times normal 2013 NRC Scenario #3 Page 21 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

• WHEN HPCI Room temperature EOP-103 Secondary Containment reaches 115 degrees, Control. THEN CRS implements

1. It is impossible to predict all EOP-103.

possible break points in a system and proceduralize all possible points of isolation. Therefore, for reasons of system isolation as directed by EOP-103, the operator does not need written guidance beyond EOP-103 direction to isolate faulted systems.

2. It is important to remember it takes 2 or more areas (as defined in the EOP) with max safe Rads or Temps or Levels AND a Primary system discharging into the Reactor Building to enter EOP-202 RPV Blowdown.

3. Verification of discharging can be by either of the following:

a. Visual verification of a leak or break in an area.

b. Rising temperatures and/or rising radiation levels in an area.

4. Post scram, if the main condenser and sufficient RPV feed sources are available, the Control Room Supervisor should consider depressurizing the reactor within the cooldown limits (to approximately 500-600 psig) to reduce the driving head of the leak. If EOP-202 implementation is anticipated, then the depressurization is allowed to exceed the cooldown rate.

• CRS implements AB.CONT-004:

Condition A Condition C 2013 NRC Scenario #3 Page 22 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched to secure Rx

• PO places FRVS in service IAW Bldg Ventilation, SO.GU-0001 Section 5.3.

THEN:

• REFER to SO.GU-0001 Section 5.3

• TRIGGER ET-29 to secure fans STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION

• BEFORE HPCI Room Reactor Scram Reports temperature reaches 250 Following a Reactor scram, the NCO degrees, should make an initial scram report THEN CRS directs reducing by announcing reactor status IAW recirc pumps to minimum speed HC.OP-AB.ZZ-0001.

Crew personnel should hold all other and locking the Mode Switch in non-essential communications until SHUTDOWN after the initial scram report is complete.

The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement

• RO reduces recirc pumps to directing the NCO to check the minimum speed and locks the overhead alarms, since these actions Mode Switch in SHUTDOWN.

are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff IAW HC.OPAB.ZZ-0001.

Before HPCI Room temperature exceeds 250 °F by Control Room indication, the Crew places the Mode Switch in SHUTDOWN.

2013 NRC Scenario #3 Page 23 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes Scram RECORD time of Mode Condition and Reactor Power Switch to SHUTDOWN Above 4% EOP entry condition. OR RPV LVL 3 (whichever was first) for 15 min ECG Classification.

Time: _______

STRATEGIES FOR SUCESSFUL

• RO performs scram actions IAW HPI USED:

TRANSIENT MITIGATION STAR Reactor Scram Reports AB.ZZ-0001 Att. 1.

Following a Reactor scram, the NCO HARD CARD should make an initial scram report The Mode Switch will by announcing reactor status IAW not actuate RPS.

HC.OP-AB.ZZ-0001. ARI will not Crew personnel should hold all other automatically initiate, non-essential communications until after the initial scram report is but can be manually complete. initiated.

The Control Room Supervisor should silence alarms during the scram report and the SM/CRS is not required to make a statement directing the NCO to check the overhead alarms, since these actions are already expected immediately following the scram.

During the scram report, the NCO should report reactor level and pressure and their trends to the Control Room staff IAW HC.OPAB.ZZ-0001.

Before Reactor Water Level RECORD the RPV level reaches LVL 1 (-129), the at which ARI is Crew manually actuates ARI to actuated.

shutdown the reactor. RPV Level: _______

• Crew recognizes RPV Level Below 12.5 EOP entry condition by:

OHA C5-A4 RPV WATER LEVEL LO OHA A7-D5 RPV LEVEL 3 Various water level indicators

• CRS implements EOP-101.

2013 NRC Scenario #3 Page 24 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• PO stabilizes and restores level IAW AB.ZZ-0001 Att. 14 as directed by CRS.

FWHTR 1&2 Condensate

• Crew recognizes FWHTR 1&2 Inlet valve closures: Condensate valve closures After reactor power lowers to

<15% following scram actions.

• RO/PO opens FWHTR 1&2 Condensate Bypass valve HV-1625.

• Crew recognizes lowering reactor pressure by:

OHA C8-B3 NSSSS ISLN SIG - MN STM PRESSURE LO Various reactor pressure indications

• IF reactor pressure lowers to 550 psig, THEN CRS enters AB.RPV-0005:

Retainment Override

• STA monitors AB.RPV-0005 implementation and Retainment Override applicability.

• CRS directs closing:

MSIVs HV-F016 HV-F019

• RO/PO close:

MSIVs HV-F016 HV-F019 2013 NRC Scenario #3 Page 25 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes rising temperature in the RCIC pump room by:

OHA B1-A1 RCIC TURBINE TRIP OHA B1-B2 RCIC OUT OF SERVICE OHA D3-A2 RCIC/RHR B AREA LEAK TEMP HI RCIC Logic B/D ISLN INIT lights RCIC HV-F007/8 closing SPDS Room temp indication HPCI Room temperature needs

• WHEN HPCI AND RCIC room to be 275 degF before reactor temperatures exceed 250 pressure drops below 200 psig. degrees (Max Safe Op),

IF necessary, THEN CRS implements THEN manually raise HPCI EOP-202 to Emergency Room temperature using Depressurize.

InSight Item hvtr4111:

• Raise to 270 degrees in 5 degree increments

• Raise from 270 to 277 degrees in 1 degree increments (RCIC Room temp will reach 250 when HPCI room temp reaches 275)

• RO/PO opens five SRVs IAW AB.ZZ-0001 Att. 13.

Crew actuates five SRVs when RECORD time from RCIC room temperature RCIC reaching 250 exceeds 250 degrees by degrees to SRV Control Room indication actuation.

(SPDS/CRIDS). (2nd room above MAX SAFE) TIME: _______

2013 NRC Scenario #3 Page 26 of 33 Rev.: 4

V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments

• Crew recognizes Supp Pool Temp Above 95°F EOP entry condition by:

OHA C8-F1 SUPPR POOL TEMP HIGH Flashing 95 degree status light on 10C650C RM11 9AX833/834 alarm Various Suppression Pool temperature indicators

• CRS enters EOP-102.

• CRS directs placing all available RHR pumps in Suppression Pool Cooling.

• RO/PO place RHR in Supp Pool Cooling IAW AB.ZZ-0001 Att. 3.

• RO/PO align SACS to support second RHR Hx IAW SO.EG-0001 Section 5.9.

Termination Requirement:

The scenario may be terminated at the discretion of the Lead Examiner when the reactor has been depressurized.

2013 NRC Scenario #3 Page 27 of 33 Rev.: 4

VI. SCENARIO

REFERENCES:

A. TQ-AA-106-0304 Licensed Operator Requal Training Exam Development Job Aid B. NUREG 1021 Examiner Standards C. JTA Listing D. Probabilistic Risk Assessment E. Technical Specifications F. Emergency Plan (ECG)

G. Alarm Response Procedures (Various)

H. HU-AA-101 Performance Tools and Verification Practices I. HU-AA-104-101 Procedure Use and Adherence J. HU-AA-1081 Fundamentals Toolkit K. HU-AA-1211 Briefing L. OP-AA-101-111-1004 Operations Standards M. OP-AA-101-111 Roles and Responsibilities of On Shift Personnel N. OP-AA-106-101-1001 Event Response Guidelines O. OP-AA-108-114 Post Transient Review P. OP-HC-108-115-1001 Operability Assessment and Equipment Control Program Q. OP-HC-108-106-1001 Equipment Operational Control R. HC.OP-SO.AE-0001 Feedwater System Operation S. HC.OP-SO.SF-0001 Reactor Manual Control T. HC.OP-SO.SF-0003 Rod Worth Minimizer Operation U. HC.OP-AB.ZZ-0001 Transient Plant Conditions V. HC.OP-AB.RPV-0005 Reactor Pressure W. HC.OP-AB.IC-0001 Control Rod X. HC.OP-AB.CONT-0001 Drywell Pressure Y. HC.OP-AB.CONT-0002 Primary Containment Z. HC.OP-AB.CONT-0004 Radioactive Gaseous Release AA. HC.OP-AB.ZZ-0172 Loss of 4.16 KV Bus 10A403 C Channel BB. HC.OP-AB.ZZ-000 Reactor Scram CC. HC.OP-EO.ZZ-0101 RPV Control DD. HC.OP-EO.ZZ-0102 Primary Containment Control EE. HC.OP-EO.ZZ-0103 Reactor Building Control FF. HC.OP-EO.ZZ-0202 Emergency RPV Depressurization GG. HC.RE-AB.ZZ-0001 Insertion of Control Rods in Response to an ATWS HH. HC.OP-IO.ZZ-0006 Power Changes During Operation II. Strategies For Successful Transient Mitigation 2013 NRC Scenario #3 Page 28 of 33 Rev.: 4

VII. ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #3, Rev. 4 1.

Before HPCI Room temperature exceeds 250 °F by Control Room indication, the Crew places the Mode Switch in SHUTDOWN.

K/A 295032 High Secondary Containment Area Temperature EK3 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK3.02 Reactor SCRAM RO 3.6 SRO 3.8 EA2 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EA2.01 Area temperature RO 3.8 SRO 3.8 The steam leak from HPCI cannot be isolated. Since isolation cannot be accomplished, the only remaining course of action is to remove the energy input to the RCS by scramming the reactor. 250°F is the Max Safe Op temperature for the HPCI Room (4111), and EOP-103 directs reducing recirc to minimum and initiating a manual scram. In this scenario, the rate of rise in room temperature provides ample time to implement the guidance in EOP-103. Reducing recirc to minimum is not critical to shutting down the reactor, and is not included as part of this critical task. The first action AB.ZZ-0001 directs for initiating a manual scram is to LOCK the Mode Switch in SHUTDOWN. For the purposes of shutting down the reactor, LOCKING the Mode Switch in SHUTDOWN is not required, only initiating a scram is critical.

2.

Before Reactor Water Level reaches LVL 1 (-129), the Crew manually actuates ARI to shutdown the reactor.

K/A 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.03 - Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : ARI/RPT/ATWS: Plant-Specific 4.1/4.1 Given a failure of RPS the rods must be inserted using ARI. This will eliminate further actions in EOP-101A and allow use of EOP-101 and 102 for containment and RPV control without a required of lowering RPV level 3.

Crew actuates five SRVS when RCIC room temperature exceeds 250 degrees by Control Room indication (SPDS/CRIDS).

K/A 295032 High Secondary Containment Area Temperature EK3 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EK3.01 Emergency/normal depressurization RO 3.5 SRO 3.8 EA2 Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE EA2.01 Area temperature RO 3.8 SRO 3.8 The steam leak in the HPCI room is now affecting a second area. The reactor must be depressurized to place it in its lowest energy state due to the potential for multiple inoperable safety systems, to reduce the driving head for the leak, and to reject decay heat to the suppression pool rather than the Reactor Building.

2013 NRC Scenario #3 Page 29 of 33 Rev.: 4

2013 NRC Scenario #3, Rev. 4 HOPE CREEK ESG - PRA RELATIONSHIPS EVALUATION FORM INITIATING EVENTS THAT LEAD TO CORE DAMAGE Y/N EVENT Y/N EVENT Loss Of Offsite Power/SBO Internal Flooding Y LOCA LOSS OF SUPPORT TRANSIENTS: SYSTEMS:

Turbine Trip Loss of SSW Loss of Condenser Vacuum Loss of SACS Loss of Feedwater Y Manual Scram COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY Y/N KEY EQUIPMENT Y/N KEY SYSTEMS Y HPCI SRVs Y RCIC Condensate/Feedwater B/D EDG SSW A/B RHR Pump RPS A/B SACS Loop 1E 4.16KV Bus 1E 480 VAC Bus 120VAC 481 Inverter 1E 125VDC Hard Torus Vent OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE Y/N OPERATOR ACTION Manual Depressurization of the RPV w/ no HP Injection Available Reopen SSW Discharge Valve to SACS Hx After Level 1 or Hi DW Press. Signal Control RPV Water Level w/ HP Injection during ATWS Sequence Align Portable Power Supply to Battery Chargers Venting of Primary Containment Restore Switchgear Cooling Restart Condensate Control Plant via Remote Shutdown Panel during Control Room Flooding Sequence Complete this evaluation form for each ESG.

2013 NRC Scenario #3 Page 30 of 33 Rev.: 4

VIII. TURNOVER SHEET:

ONLINE RISK: GREEN WORK WEEK CHANNEL: C PROTECTED EQUIPMENT None REACTIVITY / Plant Status 75% Power. Plan is to raise power to 80% IAW HC.OP-IO.ZZ-0006 and REMA 003, and hold for evaluation.

ESF/SAFETY SYSTEMS None COOLING WATER None BOP DK111 tagged for freon leak CP161 tagged for bearing oil leak Third RFP to be placed in service after engineering evaluation of RFP operations at 80% power (scheduled for next shift).

ELECTRICAL None ADVERSE CONDITION MONITORING None 2013 NRC Scenario #3 Page 31 of 33 Rev.: 4

IX. SIMULATOR ESG REVIEW/VALIDATION CHECKLIST EXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION Note: The following criteria list scenario traits that are numerical in nature for a single scenario.

ESG: Scenario 3 SELF-CHECK

1. Total malfunctions inserted: 5-8

2. Malfunctions that occur after EOP entry: 1-4

3. Abnormal Events: 1-2

4. Major Transients: 1-2

5. EOPs used beyond primary scram response EOP: 1-3

6. EOP Contingency Procedures used: 0-3

7. Approximate scenario run time: 45-60 minutes (one scenario may approach 90 minutes)

8. EOP run time: 40-70% of scenario run time

9. Crew Critical Tasks: 2-5

10. Technical Specifications are exercised during the test: >1 Comments:

2013 NRC Scenario #3 Page 32 of 33 Rev.: 3

EXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION (cont)

Crew Validation Rev: 04 Date Validated: 7/22/13 Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition Crew Validation Rev: Date Validated:

Validation Comments Disposition 2013 NRC Scenario #3 Page 33 of 33 Rev.: 3