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Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML13267A422
Person / Time
Site:	Hope Creek
Issue date:	08/19/2013
From:	Fish T H; Operations Branch I
To:	; Public Service Enterprise Group
	Jackson D E
Shared Package
ML13077A118	List: IR 05000354/2013301; ML13108A195; ML13227A102; ML13227A107; ML13227A117; ML13227A127; ML13227A207; ML13267A380; ML13267A389; ML13267A415; ML13267A422; ML14010A064; ML14070A491; ML14070A492;
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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 #: 0 2 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 Page 2 of 14 STATION: Hope Creek JPM NUMBER:

RO A-1 REV: 0 2 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 14 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. Today's CRS is A. West.

INITIATING CUE:

COMPLETE today's 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.

TQ-AA-106-0303 Page 4 of 14 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE PROVID E the operator the initiating cue AND a copy of OP

-HC-103-105 WITH the attached paperwork.

Operator repeats back initiating cue.

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

N/A Operator determines beginning ste p

of the procedure.

Operator determines correct beginning 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

or when Condition 2 OR 3 is entered from Condition 4 with the valve(s)/line(s) open.

N/A (Filled in by previous Operator) 4.4.2 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 closed in Condition 1, 2, or 3

or when Condition 4 is entered from Condition 2 or 3 with the valve(s)/line(s) open. [T/S 1.34]

Operator enters 0836 in section C of Form 2 in the "Time at which valve/line was closed or Condition 4 or 5 wa s

entered with valve/line opened" space.

TQ-AA-106-0303 Page 5 of 14 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

4.4.3 COMPUTE

the total hours (round up to the nearest 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or to the nearest 1.0 hour0 days 0 hours 0 weeks 0 months ) for each open cycle.

Operator calculates the open cycle as

7.0 hour0 days 0 hours 0 weeks 0 months s

(6.6 rounded up to 7.0) and 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, or mode change to Condition 4 has occurred, or the day has ended TOTAL the hours that the valve(s)/line(s) were open (should be less than the time authorized in Section B of Form 2). [T/S 1.52]

Operator totals the hours that the valve(s)/line(s) were open. (7.0 hours0 days 0 hours 0 weeks 0 months ) and enters in Section C "Total number of hours valves/line open this permit" space.

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

4.4.6 The SM/CRS should verify the calculations, sign in the appropriate space for verification and close out and enter the time and date.

Operator hands the paperwork to the CRS. CUE SIGN and DATE the appropriate spaces and RETURN to the operator.

N/A TQ-AA-106-0303 Page 6 of 14 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 4.4.7 On Form 1, ENTER the name of the SM/CRS closing out the valve permit and the number of hours the valves were open on this permit. The NCO entering this information should initial in the appropriate space.

On Form 1, the operator enters the name of the SM/CRS closing out the valve permit.

On Form 1, the operator enters the 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 the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME:

N/A Task Standard:

Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit and Log, OP-HC-103-105, completed in accordance with attached key

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 7 of 14 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 OP-HC-103-105 Revision 1 Page 8 of 9 Hope Creek Rev. 5 FORM 1 Page_____of_____

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS PREV. YEAR (Note 1) HOURS AUTH. THIS PERMIT NAME OF SM/CRS AUTHORIZING THIS PERMIT NCO INITIAL HOURS USED THIS PERMIT TOTAL HOURS PREVIOUS YEAR (Note 1) NAME OF SM/CRS CLOSING THIS PERMIT NCO INITIAL 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 today's date back to 0001 on the same date one year earlier.

OP-HC-103-105 Revision 2 Page 9 of 9 Hope Creek 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 DATE NUMBER OF HOURS (2) Total previous year (NOTE 1) (-) 35.5 3/3/13 5.5 Hours available this date (line 1 minus line 2)

(=) 416.5 6/25/13 3.5 Hours authorized this date (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or Line (3), whichever is less 24 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 Condition 1, 2, or 3 was entered with valve/line open Time at which valve/line was closed or Condition 4 or 5 was entered with valve/line

opened Total number of hours valve/line opened this cycle (NOTE 3) 020 0 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 today's 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.)

OP-HC-103-105 Revision 2 Page 9 of 9 Hope Creek 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 critical step (4.4.3). Added 'SM/CRS will perform step 4.4.6' to the cue sheet

. N OP-HC-103-105 Revision 2 Page 9 of 9 Hope Creek 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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. 8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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.

13. Statements describing important actions or observations that should be made by 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 OP-HC-103-105 Revision 1 Page 8 of 9 Hope Creek Rev. 5 FORM 1 Page_____of_____

CONTAINMENT PREPURGE CLEANUP, INERTING, OR PRESSURE CONTROL VALVE PERMIT LOG DATE HOURS PREV. YEAR (Note 1) HOURS AUTH. THIS PERMIT NAME OF SM/CRS AUTHORIZING THIS PERMIT NCO INITIAL HOURS USED THIS PERMIT TOTAL HOURS PREVIOUS YEAR (Note 1) NAME OF SM/CRS CLOSING THIS PERMIT NCO INITIAL 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 today's 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 #:

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 DATE NUMBER OF HOURS (2) Total previous year (NOTE 1) (-) 35.5 3/3/13 5.5 Hours available this date (line 1 minus line 2

) (=) 24 6/25/13 3.5 Hours authorized this date (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or Line (3), whichever is less 24 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 Condition 1, 2, or 3 was entered with valve/line open Time at which valve/line was closed or Condition 4 or 5 was entered with valve/line

opened Total number of hours valve/line opened this cycle (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 today's 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. Today's CRS is A. West INITIATING CUE:

COMPLETE today's 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 Page 2 of 17 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/METHO D: 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 17 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.

TQ-AA-106-0303 Page 4 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

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

N/A Operator obtains the correct procedure.

Operator obtains procedure HC.OP-AB.RPV-0003. Operator determines beginning step of the procedure.

Operator determines correct beginning step to be G.12.

G.12 ENSURE Differential Temperature requirements are met by completing Attachment 2. [T/S 4.4.1.4]

Operator obtains HC.OP

-AB.RPV-0003 Attachment 2.

TQ-AA-106-0303 Page 5 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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.

TQ-AA-106-0303 Page 6 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 pressure to temperature a more detailed set of steam tables should be utilized. NA 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.

TQ-AA-106-0303 Page 7 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.3 < 145°F between Rx Pressure Vessel Steam Space Coolant AND Bottom Head Drain Line Coolant (A

- B). [T/S 4.4.1.4] Operator subtracts value of step 1.2 from value of step 1.1. and determines 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 CRITERIA. NA TQ-AA-106-0303 Page 8 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

2.1 Temperature

of the Rx Coolant within the idle loop to be started up.

(Note 3) Operator reads 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 I&C obtain temperatures using RTD ohm values (reference RTD ohm values to calibration data in TDR using HC.OP

-GP.ZZ-0008(Q)) NA TQ-AA-106-0303 Page 9 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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.

TQ-AA-106-0303 Page 10 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 2.3 < 50°F between the Rx Coolant within the loop not in operation AND the Coolant in the Rx Pressure Vessel (A

-B). [T/S 4.4.1.4]

Operator determines differential temp is

< 50 F. 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 G.12 ENSURE Differential Temperature requirements are met by completing Attachment 2. [T/S 4.4.1.4]

Operator initials step G.12.

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 TQ-AA-106-0303 Page 11 of 17 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 12 of 17 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 13 of 17 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:

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

Page 14 of 17 MALFUNCTION SCHEDULE

Initial @Time Event Action Description REMOTE SCHEDUL E: Initial @Time Event Action Description

OVERRIDE SCHEDULE

Initial @Time Event Action Description None None Insert 9M13_R_AO to value necessary to ensure PI

-3684A-1 (10C650B) indicates approximately 885 psig.

Ensure HPCI Steam Inlet Pressure indicates approximately 885 psig.

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. Changed CRIDS data points to match simulator. Clarified critical tasks and calculation values. Revised simulator setup.

Y 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 STA NDARD: 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 Page 2 of 10 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 10 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.

TQ-AA-106-0303 Page 4 of 10 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

Operator obtains appropriate 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.

Operator obtains the correct drawings START TIME:

1. Applicant reviews P&IDs and identifies mechanical components required to ISOLATE the leak on the suction of the AP206 Core Spray pump.

(ITEMS BOLDED are CRITICAL)

Applicant identifies the following mechanical isolation valves:

HV-F001A SHUT V-009 SHUT V-027 SHUT V-037 OPEN (check valve bypass) (NOT REQUIRED)

V-045 SHUT (normally closed) V-049 SHUT (normally closed)

TQ-AA-106-0303 Page 5 of 10 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

2. Applicant reviews P&IDs and identifies electrical components required to ISOLATE the leak on the suction of the AP206 Core Spray pump.

Applicant identifies the following electrical components required for isolati on: MCC 10B212, breaker 012 (HV

-F001A) 10A401, breaker 05 ('A' CSS Pump Motor)

3. Applicant reviews P&ID and identifies mechanical components required to VENT the isolated section of the Core Spray train.

(Valves OPEN)

NOTE: May OPEN one, two or all valves to vent Applicant identifies the following mechanical VENT valves in the OPEN position: V-041 OPEN V-9975 and/or V

-9974

4. Applicant reviews P&ID and identifies mechanical components required to DRAIN the isolated section of the Core Spray train.

(Valves OPEN)

Applicant identifies the following mechanical DRAIN valves in the OPEN position: V-108 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.

TQ-AA-106-0303 Page 6 of 10 Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" TQ-AA-106-0303 Page 7 of 10 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 TQ-AA-106-0303 Page 8 of 10 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 NRC exam. Added "Not Required" for V

-037 Open Y TQ-AA-106-0303 Page 9 of 10 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 Fi le 6-25-13 Name Qual Signature Date Jim Southerton SRO On File 6-10-13 Name Qual Signature Date TQ-AA-106-0303 Page 10 of 10 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.

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 Page 2 of 13 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 TIM E: 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 13 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.

TQ-AA-106-0303 Page 4 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

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

N/A Operator obtains the correct procedure.

Operator obtains procedure HC.OP-AB.CONT-0004. Operator determines beginning step of the procedure.

Operator determines correct beginning step to be A.4 A.4 DETERMINE the Total Release Rates of Noble Gas and Iodine as follows:

USE the SPDS Noble Gas Total.

OR USE one of the Formulas in Table "A". Operator determines that to calculate the Noble Gas release from the NPV the formulas in Table "A" must be used.

TQ-AA-106-0303 Page 5 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 = µCi/cc (n.g.)

Plant Vent Exh Flow in cfm

µCi/sec (n.g.)

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)

TQ-AA-106-0303 Page 6 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

Operator calculates the NPV Noble Gas release rate.

Calculated Value =

3.65E-5 µCi/cc

49613.9 CFM

472

= 8 54.7 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.

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:

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

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 7 of 13 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 8 of 13 I. INITIAL CONDITIONS:

I.C. Initial INITIALIZE the simulator to 100% power, MOL.

INSERT Malfunctions:

RM9590 @ 0.0E+00 RM9602 @ 3.65E-5 CC0 1 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:

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

Page 9 of 13 MALFUNCTION SCHEDULE

Initial @Time Event Action Description None None Insert malfunction RM9590 to 0.00000 9RX590, NPV EFF

- North Plant Vent Noble Gas Effluent None None Insert malfunction RM9602 to 3.65E-5 9RX602, NPV LOW

- North Plant Vent Range Noble Gas None None Insert malfunction CC0 1 CRIDS Computer Failure REMOTE SCHEDULE

Initial @Time Event Action Description

OVERRIDE SCHEDULE

Initial @Time Event Action Description

TQ-AA-106-0303 JOB PERFORMANCE MEASUR E Page 10 of 13 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 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

. Y TQ-AA-106-0303 JOB PERFORMANCE MEASUR E Page 11 of 13 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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:

TQ-AA-106-0303 JOB PERFORMANCE MEASUR E Page 12 of 13 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.

TQ-AA-106-0303 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Readings are taken every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to ensure that the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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: Today's 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-FI5665 --- 45.9 TOTAL FLOW 49613.9 ESTIMATED TOTAL FLOW REPORTED TO RAD PRO

- (YES) Yes HC.OP-DL.ZZ-0026(Q)

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 Page 2 of 13 STATION: Hope Creek JPM NUMBER:

2013 NRC SRO A

-1 REV: 0 2 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 13 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 today's Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit in accordance with OP-HC-103-105.

TQ-AA-106-0303 Page 4 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE PROVIDE the operator the initiating cue AND: Prepared OP

-HC-103-105 log Forms 1 & 2 (Attached)

Copy of OP

-HC-103-105 Operator repeats back initiating cue.

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

N/A Operator determines beginning step of the procedure.

Operator determines correct beginning step to be 4.4.6.

TQ-AA-106-0303 Page 5 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate space for verification and close out and enter the time and date.

Operator reviews Forms 1 & 2. 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).

TQ-AA-106-0303 Page 6 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

N/A 4.4.6 The SM/CRS should verify the calculations, sign in the appropriate space for verification and close out and enter the time and date.

Operator makes corrections to Form 2 Stop times and Total Hours.

Examiner Note:

Refer to Examiners 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.

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:

Containment Prepurge Cleanup, Inerting, Or Pressure Control Valve Permit reviewed with issues identified per the key 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 4/3/13 5.5 (3) Hours available this date (line 1 minus line 2)

(=) 416.5 6/25/13 3.5 Hours authorized this date 24 8/1/13 24.0 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or Line (3), whichever is less) 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 1, 2, or 3 was entered with valve/line open Time at which valve/line was closed or Condition 4 or 5 was entered with valve/line opened Total number of hours valve/line opened this cycle (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 today's 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 current revision of procedure.

Added clarifying comments to examiner guide.

Yes 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

p. 13. Statements describing important actions or observations that should be made by 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 PREV. YEAR (Note 1) HOURS AUTH. THIS PERMIT NAME OF SM/CRS AUTHORIZING THIS PERMIT NCO INITIAL HOURS USED THIS PERMIT TOTAL HOURS PREVIOUS YEAR (Note 1) NAME OF SM/CRS CLOSING THIS PERMIT NCO INITIAL 4/3/1 3 22.5 24 H. David SD 5.5 28.0 S. West SD 6/25/1 3 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 2 4 A. Jones JS Note 1: The previous year includes the period from 2400 on today's 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 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 4/3/13 5.5 (3) Hours available this date

(=) 416.5 (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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) 24 8/12/13 2.5 (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 1, 2, or 3 was entered with valve/line open Time at which valve/line was closed or Condition 4 or 5 was entered with valve/line

opened Total number of hours valve/line opened this cycle (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 today's 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 today's 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 JPM NUMBER:

2013 NRC SRO A

-2 (305H-JPM.ZZ031) REV #: 02 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 Page 2 of 16 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 16 NAME: DATE: SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets TASK NUMBER:

2991110302 INITIAL CONDITIONS:

1. A star t-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.

TQ-AA-106-0303 Page 4 of 16 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE PROVIDE the operator the initiating cue AND: Prepared HC.OP

-IO.ZZ-0003 Attachment 4 (Attached)

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

) Operator repeats back initiating cue.

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

N/A HC.OP-IO.ZZ-0003 Attachment 4 N/A 1.2.3 GENERATE a Components In Off

-Normal Position Report

USING WCM Reports/Off Normal Report function.

N/A TQ-AA-106-0303 Page 5 of 16 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

1.2.4 POSITION

all components as required. Operator reviews Components In 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

TQ-AA-106-0303 Page 6 of 16 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 channels and have been

re-opened. PROVIDE the operator the updated Off

-Normal with the V9979-B and V9980-B removed.

(Labeled 'SECOND HANDOUT')

Operator repeats initiating cue and accepts updated Off

-Normal. 1.2.4 POSITION all components as required. Operator reviews Components In

Off-Normal Position Report.

Operator recognizes NO components require re

-positioning.

Operator initials IO.ZZ

-0003 Attachment 4 step 1.2.4.

TQ-AA-106-0303 Page 7 of 16 JPM: ZZ031 OPERATOR TRAINING PROGRAM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Conduct of Operations TASK: Initiate and Review System Lineup Sheets STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:

Off normal report reviewed with components listed in key identified

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 8 of 16 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 9 of 16 REVISION HISTORY JPM NUMBER: ZZ031 Rev # Date Description Validation Required? 1 11/9/08 Converted ZZ031 to new JPM format.

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. Y 2 7/2/2013 Off normal report updated Y

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 10 of 16 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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. 13. Statements describing important actions or observations that should be made by 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 Page 11 of 16 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.

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 P lant: NNUC Mode 01 Time: NOW Technical Object Description Current Normal Location Loc. Descriptio n 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 04/11/200 7 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 FACILIT Y 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 Of fNormal 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 12/0 5/2005 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 DC P 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 ELECTR ICAL 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 P lant: 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-V 423 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 L O 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 HYD RANT 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 SUPP LY 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 PE R 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 -00L 156-16 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 UNRESTRI CTED 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 OffNor mal 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 6006 1688 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 CONFI RMED 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 05/25/200 5 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 TASK STA NDARD: Core Spray Isolations, Vent & Drain Paths Identified IAW Key. 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 Page 2 of 9 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 9 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.

TQ-AA-106-0303 Page 4 of 9 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

1. Applicant reviews P&IDs and identifies mechanical components required to ISOLATE the leak on the suction of the AP206 Core Spray pump.

(ITEMS BOLDED are CRITICAL)

Applicant identifies the following mechanical isolation valves:

HV-F001A SHUT V-009 SHUT 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 identifies electrical components required to ISOLATE the leak on the suction of the AP206 Core Spray pump.

Applicant identifies the following electrical components required for isolation:

MCC 10B212, breaker 012 (HV

-F001A) 10A401, breaker 05 ('A' CSS Pump Motor)

TQ-AA-106-0303 Page 5 of 9 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

3. Applicant reviews P&ID and identifies mechanical components required to VENT the isolated section of the Core Spray train.

(Valves OPEN)

NOTE: May OPEN one, two or all valves to vent Applicant identifies the following mechanical VENT valves in the OPEN position: V-041 OPEN V-9975 and/or V

-9974

4. Applicant reviews P&IDs and identifies mechanical components required to DRAIN the isolated section of the Core Spray train.

(Valves OPEN) Applicant identifies the following mechanical DRAIN valves in the OPEN position: V-108 5. Applicant reviews Tech Specs and identifies the most limiting Tech Spec action statement AFTER leak isolation.

Applicant identified the following as the most limiting Tech Spec Action Statement:

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" TQ-AA-106-0303 Page 6 of 9 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 TQ-AA-106-0303 Page 7 of 9 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 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.

Y TQ-AA-106-0303 Page 8 of 9 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 Page 9 of 9 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.

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: NOH05JPZZ3 6 E ALTERNATE PATH:

APPLICABILITY:

EO RO X STA SRO X TASK STANDARD:

Complete s 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 Page 2 of 15 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 1 36 TOOLS, EQUIPMENT AND PROCEDURES:

Blank HC.OP

-DL.ZZ-0026 ESTIMATED COMPLETION TIME: 1 5 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 15 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 We ir 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 complete d 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.

TQ-AA-106-0303 Page 4 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE PROVIDE the operator the initiating cue AND: The completed copy of HC.OP-DL.ZZ-0026 (both pages)

. Operator repeats back initiating cue.

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

N/A HC.OP-DL.ZZ-0026 Attachment 1 a N/A ITEM 47 CHANNEL CHECK: COOLING TOWER BLOWDOWN WEIR FLOW RATE MONITOR Operator reads ITEM 47. OP ER COND AT ALL TIMES Operator determines the ITEM is applicable is the current Op Condition ACCEPTABLE LIMITS MIN NORM MAX ITEM 002 < 40K 70K Operator reads the limits.

INSTRUMENT (PANEL) 0SP-RI4861 (10C604)

ITEM 029 RM-11 (9AX327) (NOTE 45)

Operator reads NOTE 45 and determines that data is not available

from the Initial Conditions

.

TQ-AA-106-0303 Page 5 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

. NOTE 3 5 Operator reads NOTE 35 and determines that data is not available from the Initial Conditions

. NOTE 46 IF INSTRUMENT IS INOP, USE ATTACHMENT 3Y TO ESTIMATE WEIR FLOW. THIS IS REQUIRED REGARDLESS OF WHETHER A RADIOACTIVE LIQUID RELEASE IS

IN PROGRESS. Operator reads NOTE 46 and determines that Attachment 3Y is applicable

.

Operator locates Attachment 3Y

. Examiner Note:

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

TQ-AA-106-0303 Page 6 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 TQ-AA-106-0303 Page 7 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

READ FROM FIT

-2218A/B OR FR

-2218-1/2 OR CRIDS A2440/A2441. (B SSW LOOP FLOW (FIT

-2218B) IS OBTAINED LOCALLY AT PANAMETRICS MONITOR. FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH IS DISPLAYED AS "AVG VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

Operator determines A SSW Loop Flow is 13,560 gpm from CRIDS point A2440 in the Initial Conditions and that it is recorded correctly on ATT 3Y under 'SSW LOOP A FLOW #'.

SSW LOOP B FLOW #

Operator reads #

Footnote # READ FROM FIT

-2218A/B OR FR

-2218-1/2 OR CRIDS A2440/A2441. (B SSW LOOP FLOW (FIT

-2218B) IS OBTAINED LOCALLY AT PANAMETRICS MONITOR. FLOW VALUE IS THE AVERAGE VOLUMETRIC FLOW RATE WHICH

IS DISPLAYED AS "AVG VOLUMETRIC GAL/MIN" ON THE MONITOR DISPLAY.

Operator determines B SSW Loop Flow is 21,345 gpm from CRIDS point A2441 in the Initial Conditions and that it is recorded correctly on ATT 3Y under

'SSW LOOP B FLOW #'.

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

TQ-AA-106-0303 Page 8 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

EVAPORATIVE LOSSES*.

Operator reads

Footnote

REFERENCE PRINT 10855

-M15-181-1 FOR EVAPORATIVE LOSS ESTIMATES. USE 16,700 GPM FOR DEFAULT VALUE(MIN. DILUTION FLOW), FOR EVAPORATIVE LOSS ESTIMATES IF 4 CIRCULATING WATER PUMPS ARE IN SERVICE, OR 12,500 GPM IF ONLY 3 CIRCULATING WATER PUMPS ARE IN SERVICE. THIS BLOCK IS N/A IF THE COOLING TOWER IS OUT OF SERVICE.

Operator determines Evaporative Losses from

Footnote at bottom of page for 3 Circ Water Pump operation is INCORRECTLY recorded as 16,700gpm.

Examiner Note: If applicant asks, inform applicant that he/she is to correct any identified incorrect values. 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.

TQ-AA-106-0303 Page 9 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 1 a N/A ITEM 47 CHANNEL CHECK: COOLING TOWER BLOWDOWN WEIR FLOW RATE MONITOR Operator reads ITEM 47.

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

TQ-AA-106-0303 Page 10 of 15 JPM: 2013 NRC SRO A

-4 OPERATOR TRAINING PROGRAM NAME: Rev: 01 JOB PERFORMANCE MEASURE DATE: SYSTE M: Equipment Control TASK: Perform the Watchstanding Duties of the Nuclear Control Room Operator (Determine Liquid Radwaste Radiation Monitoring System Cooling Tower Blowdown Weir Flow)

STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:

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.

TQ-AA-106-0 303 JOB PERFORMANCE MEASURE REVISION HISTORY JP M 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 NRC exam Y 02 7/3/13 Revised JPM to make SRO level (review completed form vice completing form from scratch).

Y TQ-AA-106-0 303 JOB PERFORMANCE MEASURE JPM NUMBER:

2013 NRC SRO A

-4 REV#: 0 2 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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-106-0 303 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 replacemen

t. 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 # 20 12-001 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 complete d 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 #: 0 2 SAP BET: NOH05JPCL 0 5 E 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 Page 2 of 21 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 21 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 10 0% power with the AD483 inverter isolated to it's 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+01

µCi/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)

TQ-AA-106-0303 Page 4 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:

N/A Operator obtains the correct procedure.

Operator obtains Hope Creek Event Classification Guide.

ECG Section 8.4 The primary tools for determining the emergency classification level are the 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 Section 8.4.1 ASSESS the event and/or plant conditions and DETERMINE which ECG-EAL Group/Section is most appropriate.

Operator assesses the initial conditions, and determines that S1, Loss Of AC Power, and S3, ATWS/Criticality are appropriate ECG sections.

TQ-AA-106-0303 Page 5 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Section 8.4.2 REVIEW EAL categories and subcategories on the appropriate flowcharts/wallcharts.

Operator refers to Flowchart Diagrams and/or Wallcharts and identifies that the Initial Conditions for EALs SS1.1, SG1.1, and SA3.1 are related to the event that has occurred.

ECG Section 8.4.3 If using the ECG - EAL flowcharts, for each applicable subcategory, 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 Section 8.4.4 If using the ECG - EAL Wallcharts, for each applicable subcategory, REVIEW EALs in the subcategory beginning with the highest emergency classification level to the lowest classification level (left to right).

TQ-AA-106-0303 Page 6 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Section 8.4.5 If in OPCON 1, 2 or 3, also REVIEW the Fission Product Barrier (FPB) Table: N/A ECG Section 8.4.5.a EXAMINE the FPB categories in the left column of the table.

Operator refers to FPB Table and identifies that the Initial Conditions do not meet any FPB Table thresholds

. ECG Section 8.4.5.b SELECT the category that most likely coincides with event conditions.

N/A ECG Section 8.4.5.c REVIEW all thresholds in this category for each fission product barrier. N/A TQ-AA-106-0303 Page 7 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Section 8.4.5.d For each threshold that is exceeded, IDENTIFY its point value and DETERMINE the classification level in accordance with the instructions on the Fission Product Barrier Table (or in EAL Technical Bases, Attachment 1). If sum is: Classify as: Emergency Action Levels (EALs) Refer to ECG ATT# 2, 3 UNUSUAL EVEN T (NOTE 1) ANY loss or ANY potential loss of Containment 1 4, 5 ALERT ANY loss or ANY potential loss of either Fuel Clad or RCS 2 6 -11 SITE AREA EMERGENCY Loss or potential loss of ANY two barriers 3 12, 1 3 GENERAL EMERGENCY Loss of ANY two barrie rs ANDLoss or potential loss of the third barrier 4 N/A TQ-AA-106-0303 Page 8 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

FPB Table NOTE 1 The Primary Containment Barrier should not be declared lost or potentially lost based on exceeding 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.

Operator reads NOTE.

TQ-AA-106-0303 Page 9 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Section 8.4.6 REVIEW the associated EALs as compared to the event and SELECT 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 ECG EAL Technical Bases Document should be reviewed. Words contained in an EAL that appear in uppercase and bold print (e.g., VALID) are defined at the end of the bases for the particular EAL or in ECG

- EAL Technical Basis Document, , 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., ). Operator reviews the EALs in section S , and determines that EAL # SS1.1 is the highest emergency action level met or exceeded (SITE AREA EMERGENCY

). Time Declared ________.

TQ-AA-106-0303 Page 10 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Section 8.4.7 If an EAL has been exceeded, equal level EALs or lower level EALs are not required to be seperately reported as long as the applicable information is communicated to the NRC using ECG Attachment 5, EP

-HC-111-F5, NRC Data Sheet & Completion Reference.

Examiner Note:

Filling out the NRC Data Sheet is beyond the scope of this JPM. ECG Section 8.4.8 When the Shift Manager (SM) is the Emergency Coordinator, the Shift Technical Advisor (STA) is responsible to perform an independent verification of the EAL classification. The STA verification does not alleviate the requirement of the SM to make a timely classification. Should the SM fill the STA role, independent verification of the EAL classification will be delegated to another on

-shift SRO, the Independent Assessor.

IF time permits, THEN Operator requests STA/IA verification of classification.

Examiner Note:

Due to time spent assessing and/or nature of JPM administration, Operator may not request a verification.

TQ-AA-106-0303 Page 11 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

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

Unusual Event Implement EP

-HC-111-F1 Alert Implement EP

-HC-111-F2 Site Area Emergency Implement EP

-HC-111-F3 General Emergency Implement EP

-HC-111-F4 Unusual Event (Common Site) Implement EP

-HC-111-F24 Operator identifies and implements EP

-HC-111-F3 Attachment 3 Site Area Emergency.

ECG Att. 3 I. EMERGENCY COORDINATOR (EC) LOG SHEET ECG Att. 3. A CLASSIFICATION ECG Att. 3 1. CALL communicators to the Control Room. Operator calls communicators to the Control Room.

TQ-AA-106-0303 Page 12 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

N/A ECG Att. 3 2. If a security event is in progress, THEN, IMPLEMENT the prompt actions of NC.EP

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

Operator determines this step is not applicable.

ECG Att. 3 3. As time allows, OBTAIN Classification Independent Verification (ensure verifier understands the EAL assessment clock is running);

STA or designee performs Independent Verification for

SM SM or designee performs Independent Verification for EDO EDO or designee performs Independent Verification for ERM IF time permits, THEN Operator requests STA/IA verification of classification.

Examiner Note:

Due to time spent assessing and/or nature of JPM administration, Operator may not request a verification.

TQ-AA-106-0303 Page 13 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

N/A ECG Att. 3 4. While classification verification is in progress and if time allows, COMMENCE filling out the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment).

Operator commences filling out ICMF.

ECG Att. 3 5. After classification verification and before 15 minute EAL assessment clock expires, DECLARE a SITE AREA EMERGENCY at Hope Creek.

EAL #(s) ______, ______, _______ DECLARED AT _____ hrs on ______

time date Operator declares a Site Area Emergency, places the EAL # SS1.1, time and date in the appropriate spots in Attachment 3, and initials the step as the EC. Examiners Note: ENTER the declaration time that the operator 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.

TQ-AA-106-0303 Page 14 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Att. 3 B. NOTIFICATIONS ECG Att. 3 B.1. ACTIVATE "ERO Emergency Callout" per posted instructions titled: "Emergency Callout Activation" (EP96-003) Operator activates the ERO per posted instructions titled Training Use Emergency Callout Activation.

Examiner Note:

ENSURE the operator is using the Simulator Training Activation instructions.

ECG Att. 3 B.2. COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of this attachment).

Operator Completes the ICMF.

Examiners Note: See the attached 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 Examiner's name as the Communicator or tell the Examiner to place his/her name as the Communicator.

TQ-AA-106-0303 Page 15 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Att. 3 B.3. IF time allows, OBTAIN an accuracy peer check of the completed ICMF.

Operator requests a Peer Check of the completed ICMF.

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

N/A ECG Att. 3 B.4. PROVIDE the ICMF to the Primary Communicator (CM1) and DIRECT the Communicator to implement ECG .

Operator provides the ICMF to CM1 and directs implementation of Att.6.

CUE LOG the time the ICMF is provided to CM1. LOG TIME: _____________

Role-play as CM1 and repeat back the direction as given.

Examiners Note: The difference between the "DECLARED AT" TIME and this LOG TIME is the second critical time (13 min.)

TQ-AA-106-0303 Page 16 of 21 JPM: 2013 NRC SRO A

-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

ECG Att. 3 B.6. DIRECT the Secondary Communicator (CM2) to implement ECG Attachment 8 for a SITE AREA EMERGENCY. Operator directs CM2 to implement Att.

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.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME:

N/A N/A TASK STANDARD:

Operator declares a Site Area Emergency IAW ECG SS1.1 , and makes notifications within identified Critical Times.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 17 of 21 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE Todays Time Todays Date SS1.1 Not Required X 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 added clarifying examiner note.

N 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 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 it's 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+01

µCi/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 Page 2 of 16 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 16 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.

TQ-AA-106-0303 Page 4 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

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

N/A Operator obtains the correct procedure.

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

Operator reviews precautions and limitations.

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

N/A Operator determines beginning step of the procedure.

Operator determines correct beginning step to be 5.1.1.

TQ-AA-106-0303 Page 5 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

EQUIPMENT REQUIRED Key # (G1) for EOP Locker on El. 102' diesel bldg. From either:

o SM office or o From EOP Locker in OSC (Use Key #9 obtained from SM office or by breaking red key holder glass in OSC). AND Equipment located in EOP locker on El.102' diesel bldg.

Contents:

1- 2.5" hose to flange adapter 1- 1.5" hose to flange adapter 150' of 2.5" Fire Hose 50' of 1.5" Fire Hose (for Fire Hose Station) 2- 1-1/16" Box Wrenches 2- Fire Hose Wrenches 1- Hydrant Wrench Operator obtains the following required equipment:

Key #(G1) for EOP Locker on El.102' diesel bldg. From either:

o SM office or o From EOP Locker in OSC (use key

9 obtained from SM office or by breaking red key holder glass in OSC)

Equipment located in EOP locker on El 102' diesel bldg.

Examiner Note: After operator has demonstrated ability to obtain required equipment, ensure that the equipment is returned to its appropriate storage location.

5.1.1 ENSURE

all prerequisites of Section 2.1 are satisfied.

Operator ensures that all prerequisites have been satisfied.

TQ-AA-106-0303 Page 6 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

N/A 5.1.2 CONNECT hose to the appropriate flange adaptor AND TIGHTEN. o 1.5" hose and adapter for fire hose station o 2.5" hose and adapter for yard fire hydrant or fire truck Operator accesses the EOP locker and identifies the 1.5" fire hose and correct adapter. Examiner Note:

Based on the Initiating Cue, Operator determines the 1.5" hose and adapter is the correct equipment.

From this point on, actions will be 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 will be simulated.

N/A Operator connects the correct hose to the correct adapter.

TQ-AA-106-0303 Page 7 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.1.3 REMOVE

fire hose fill connection blank flange on 1

-BC-V426 (local, Diesel Building, Elev. 102', see Attachment 2) AND INSTALL hose to flange adapter.

Operator removes the four bolts on the 1-BC-V426 blank flange. (Bolts removed and re

-installed using the 1

- 1/16" Box wrenches).

Y N STAR 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.

TQ-AA-106-0303 Page 8 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.1.4 CONNECT

fire hose to one of the following sources of Fire Water:

o Fire Hose Station o Yard Fire Hydrant o Fire Truck Operator removes installed Fire Station hose from standpipe.

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.

TQ-AA-106-0303 Page 9 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.5 OPEN one of the following as applicable:

o Fire Hose Station Isolation Valve o Fire Hydrant Line Valve (side) and Plug Valve (top) o Fire Truck Valves Operator opens the Fire Hose Station Isolation Valve.

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 Bldg, Elev. 102', OPEN breaker 52

-222082. Operator contacts RB Equipment Operator and directs the opening at

breaker 52-222082.

Y N 3-Way Communications CUE As the RB Equipment Operator, report that breaker 52

-222082 has been opened.

TQ-AA-106-0303 Page 10 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.7 OPEN 1-BC-V426, SSWS Sup to RHR Fire Hose Fill Conn Sup Vlv (local, diesel truck bay, elevation 102 inside stairway door - see Attachment 2). Operator opens 1

-BC-V426.

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

5.1.8 OPEN BC-HV-F075, SSWS TO RHR LOOP B SUP MOV (panel 10C650).

Operator requests that the Control Room operator open BC

-HV-F075.

Y N 3-Way Communications CUE Acknowledge messages from the operator and report that BC

-HV-F075 has been opened.

TQ-AA-106-0303 Page 11 of 16 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE WHEN operator informs you the task is complete, OR the JPM has been terminated fo r 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 N/A TASK STANDARD:

Operator lines up for alternate injection using Fire Water IAW HC.O P-EO.ZZ-0310 using the local fire hose station isolation valve as the supply of Fire Water.

TQ-AA-106-0303 Page 12 of 16 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 TQ-AA-106-0303 JOB PERFORMANCE MEAS URE Page 13 of 16 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 1 EVENT ACTION:

COMMAND: PURPOSE:

TQ-AA-106-0303 JOB PERFORMANCE MEAS URE Page 14 of 16 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 changes between Rev 1 and Rev 2.

N TQ-AA-106-0303 JOB PERFORMANCE MEAS URE Page 15 of 16 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date TQ-AA-106-0303 JOB PERFORMANCE MEAS URE Page 16 of 16 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.

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:

Page 2 of 16 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 R O 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 UNSATISFACTOR Y: EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE:

Page 3 of 16 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.

TQ-AA-106-0303 Page 4 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

START TIME:

Operator obtains procedure HC.OP-AB-ZZ-0135. ATT.6 Operator obtains the correct procedure.

EQUIPMENT REQUIRED Key #51 - KIRK - Diesel Eng Takeover/Local Cont. (Work Control)

Operator obtains Key #51

- KIRK - Diesel Eng 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 START is ON (Panel 1A(B,C,D)

-C423 El. 130').

Operator observes the READY FOR AUTO START is on.

Examiner Cue: The light identified is illuminated.

The operator then initials the appropriate procedure step.

TQ-AA-106-0303 Page 5 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

2.0 OBSERVE

that Control is transferred to Remote Panels through one of the following:

PRESS REMOTE PB AND ENSURE (10C651E). REMOTE light is ON.

OR Operator requests that the Control Room press the REMOTE push button for AG400.

Examiner Cues:

IF the operator requests the Control Room to press REMOTE, THEN 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 extinguishe

d. OR TQ-AA-106-0303 Page 6 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

# 2.0 OBTAIN key #51 - KIRK - Diesel Emg Takeover/Local Cont., from Work Control Center AND PLACE EMERGENCY TAKE-OVER Switch in EMERG position.

Operator obtains key #51 from WCC, unlocks the AG400 EMERGENCY TAKE-OVER Switch, and places the AG400 EMERGENCY TAKE

-OVER Switch in 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.

TQ-AA-106-0303 Page 7 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

# 3.0 PLACE REMOTE ENGINE CONTROL in START (Panel 1A(B,C,D)

-C423 El. 130').

Operator places the AG400 REMOTE ENGINE CONTROL in START.

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:

GENERATOR FREQUENCY indicates about 60 Hz

. Operator observes: 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 about 4160 Volts.

Examiner Cue: The indicator identified indicates 4160 volts.

The operator then initials the appropriate procedure step.

TQ-AA-106-0303 Page 8 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.0 OBSERVE

the status of the following indicating lights (Panel 1A(B,C,D)

-C423 El. 130').

JACKET WATER HEATER is OFF. Operator observes:

JACKET WATER HEATER OFF light is illuminated and JACKET WATER HEATER ON light is extinguished.

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 is OFF. Operator observes:

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.

TQ-AA-106-0303 Page 9 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

JACKET WATER KEEPWARM PUMP is OFF.

Operator observes:

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 OFF. Operator observes:

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.

TQ-AA-106-0303 Page 10 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

DIESEL RUNNING

- NOT LOADED is ON.

DIESEL RUNNING

- NOT LOADED is on. Examiner Cue: The light identified is illuminated.

The operator then annotates the appropriate procedure step.

TQ-AA-106-0303 Page 11 of 16 JPM: 2013 NR C 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 NO. STEP (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD EVAL S/U COMMENTS (Required for UNSAT evaluation)

# 6.0 ENSURE that the respective bus infeed breakers are OPEN, THEN PLACE Generator Breaker Control Switch, at Panel(s) 1A(B,C,D)

-C422 to CLOSE. ____

EDG INFEED BREAKERS A 52-40101 / 52

-40108 B 52-40201 / 52

-40208 C 52-40301 / 52

-40308 D 52-40401 / 52

-40408

STOP TIME:_________

ENSURE that bus infeed breakers A 52-40101 / 52

-40108 are OPEN, THEN PLACES Generator Breaker Control Switch, at Panel(s) 1AC422 to CLOSE.

Examiner Cue for observing indications for infeed breakers open "The green light is on, the red light is extinguished.

" Examiner Cue for observing Generator Breaker Control Switch to CLOSE: "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" TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 12 of 16 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 13 of 16 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 1 EVENT ACTION:

COMMAND: PURPOSE:

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 14 of 16 REVISION HISTORY J PM 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

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 15 of 16 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 16 of 16 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.

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 Page 2 of 13 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 13 NAM E: DATE: SYSTEM: Control Rod Drive Hydraulics TASK: Manually Vent SCRAM Air Header TASK NUMBE R: 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.

TQ-AA-106-0303 Page 4 of 13 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

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

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

N/A Operator obtains the correct procedure.

Operator obtains procedure HC.OP-EO.ZZ-0306. Operator reviews precautions and limitations.

Operator reviews precautions and limitations.

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

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

N/A TQ-AA-106-0303 Page 5 of 13 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation) 4.0 4.1 EQUIPMENT REQUIRED Key #9 for EOP Locker in OSC (obtain from OS office or break red key holder glass in OSC)

AND EOP-306 Implementation kit (EOP Locker in OSC)

Contents: 1 14" Pipe Wrench 1 Wire Cutter 1 Flashlight Operator obtains the following required equipment:

Key #9 from SM office or key from break glass key holder in OSC for OSC EOP locker AND EOP-306 Implementation Kit from EOP Locker in OSC.

Examiner Note: Obtaining a pipe wrench from an alternate location is 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 of the procedure.

Operator determines correct beginning step to be 5.1 C UE If at any time the operator requests permission to use section 5.2, DENY permission due to ongoing Control Room actions to manually insert control rods with RMCS.

N/A TQ-AA-106-0303 Page 6 of 13 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

NOTE All operations are performed locally at the CRD Flow Control Area, Rx Bldg

Elev. 102'.

Operator reads NOTE.

5.1.1 UNLOCK

AND CLOSE 1BFV-073 //B/U SCRAM PILOT VLVS AIR SUP VLV//. Operator simulates removing the lock from 1BFV-073. * # Y N STAR CUE The locking device has been removed. N/A Operator simulates closing 1BFV-073 by turning valve handwheel clockwise until coming to a hard stop.

Y N STAR CUE The valve you indicated is in the position stated.

N/A 5.1.2 UNCAP AND OPEN 1BFV-802 //ARI VLVS AIR SUP HDR DRN VLV// between the scram air header ARI valves. Operator simulates removing the cap from 1BFV-802 by using the pipe wrench and rotating the cap in the counter-clockwise direction until the cap comes off.

# Y N STAR CUE The cap device has been removed.

N/A Operator opens 1BFV

-802 by turning valve handwheel counter

-clockwise until coming to a hard stop.

Y N STAR

TQ-AA-106-0303 Page 7 of 13 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 STEP NO. ( Denotes a Critical Element of a Critical Step)

ELEMENT (*Denotes a Critical Step)

STANDARD

EVAL S/U COMMENTS (Required for UNSAT evaluation)

CUE The valve you indicated is in the position stated. Air can be heard flowing from the drain opening.

N/A 5.1.3 OBSERVE PI-R013 SCRAM AIR HEADER PRESSURE (10

-C-264 panel at the CRD flow control panel) to verify the air header fully depressurizes.

Operator observes pressure reading on

PI-R013 on panel 10C264.

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.

REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME:

N/A N/A TASK STANDARD:

Operator manually vents the Scram Ai r Header in accordance with HC.OP

-EO.ZZ-0306.

TQ-AA-106-0303 Page 8 of 13 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 TQ-AA-106-03 03 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 9 of 13 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 1 EVENT ACTION:

COMMAND: PURPOSE:

TQ-AA-106-03 03 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 10 of 13 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 --- ---

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 11 of 13 REVISION HISTORY JPM NUMBER: 2013 NRC P

-3 Rev # Date Description Validation Required? 2 7-1-13 Minor grammatical change to cue sheets N

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 12 of 13 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.

2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

13. Statements describing important actions or observations that should be made by 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 Steve Loper RO On File 6-10-13 Name Qual Signature Date Mike Oeullette RO On File 6-26-13 Name Qual Signature Date TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 13 of 13 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.

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 Page 2 of 12 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 12 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.

TQ-AA-106-0303 Page 4 of 12 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 limitations.

Operator reviews precautions and limitations. Examiner Cue: If excessive time is taken reviewing precautions and limitations, inform operator that all are satisfied.

Operator determines beginning step of the procedure.

Operator determines correct beginning step to be HC.OP-SO.BB-0002. Step 5.9.1 5.9.1 ENSURE all prerequisites have been satisfied IAW Section 2.9.

Operator ensures prerequisites are satisfied.

TQ-AA-106-0303 Page 5 of 12 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation

) 5.9.2 Using Attachment 3, DETERMINE the desired SIC-621A(B) SPEED DEMAND for the actual SPEED indicated on SIC-621A(B). Operator determines the desired SIC-R621A SPEED DEMAND to be 58-62% IAW Attachment 3.

Examiner Note: The target SPEED DEMAND is 60%. Some leeway has been added for meter readability and the potential interpolation of Attachment 3 data.

5.9.3 PR ESS SIC-R621A(B) SPD CONT INCREASE OR DECREASE pushbutton as necessary to obtain the desired SIC

-621A(B) SPEED DEMAND from Step 5.9.4.

Operator presses the SIC

-R621A LOOP A SPD INCR and/or DECR pb until SIC-R621A SPEED DEMND matches the SPEED DEMAND from 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 AND ENSURE SCOOP TUBE LOCK

-UP light extinguishes.

Operator presses the Pump A TRIPS RESET PB. * # 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.

TQ-AA-106-0303 Page 6 of 12 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation

) 1 PRESS the SCOOP TUBE TRIP Pushbutton for the affected Recirc Pump Controller.

Operator presses the Pump A SCOOP TUBE TRIP pushbutton.

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 Recirc Pump Speed to Reduce Power to Pre-Transient value

. Operator presses the SIC

-R621B LOOP B SPD DECR pb until reactor 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:

TQ-AA-106-0303 Page 7 of 12 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation

) N/A TASK STANDARD:

Operator responds to a Single Recirculation Pump Runaway in accordance with HC.OP-AB.RPV-0001.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 8 of 12 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 9 of 12 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 1 EVENT ACTION:

COMMAND: PURPOSE: rr:k5(1) >= 1.0

// 'A' Recirc Scoop Tube Trip Reset Triggers 'A' Recirc Runaway 2 EVENT ACTION:

COMMAND: PURPOSE:

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

Page 10 of 12 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 --- --- --- --- --- --- --- --- --- ---

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 of cue sheet to end of JPM. Made minor changes to examiner script. N 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 Page 2 of 16 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. 2 9 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 16 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 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

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.

INI TIATING 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.

TQ-AA-106-0303 Page 4 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 limitations.

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

N/A Operator determines beginning step

of the procedure.

Operator determines correct beginning step to be 5.3.

5.

TQ-AA-106-0303 Page 5 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.3.5. SECURE

the inservice Shutdown Cooling Loop as follows:

N/A 5.3.5.A ENSURE 1-BC-V262 (1-BC-V212), ECCS Jockey Pmp D(C) DISCH to RHR Loop B(A) is LOCKED OPEN (local), AN D INITIAL Attachment 1.

Operator contacts Equipment Operator and directs opening 1

-BC-V262. CUE The valve is in the position requested.

N/A NOTE Steps 5.3.5.B through 5.3.5.C should be performed in rapid succession.

Operator reads NOTE.

5.3.5.B CLOSE BC-HV-F015B(A) RHR LOOP B(A) RET TO RECIRC AND INITIAL .

Operator presses and holds the BC-HV-F015B RHR LOOP B RET TO RECIRC CLSD pb.

TQ-AA-106-0303 Page 6 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.3.5.C WHEN BC-HV-F015B(A) RHR LOOP B(A) RET TO RECIRC is fully closed, THEN, IMMEDIATELY STOP B(A)P202 RHR PUMP.

Operator observes the BC

-HV-F015B RHR LOOP B RET TO RECIRC CLSD light illuminated and OPEN is extinguished.

Operator presses BP202 RHR PUMP STOP pb.

TQ-AA-106-0303 Page 7 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.3.5.D CLOSE BC-HV-F006B(A) RHR PMP B(A) SUCT FROM RECIRC AND INITIAL Attachment 1.

Operator presses the BC-HV-F0 06 B RHR PMP B(A) SUCT FROM RECIRC CLSD pb. Operator observes the BC

-HV-F0 06 B RHR PMP B(A) SUCT FROM RECIRC CLSD light illuminated and OPEN is extinguished.

5.3.6. ENSURE

SACS is in service to the RHR Heat Exchanger for the RHR loop to be placed in service IAW HC.OP-SO.EG-0001(Q). Operator observes the HV

-2512A OPEN light illuminated and CLSD light extinguished.

Operator observes RHR A HX SACS Flow approximately 10,000 gpm.

TQ-AA-106-0303 Page 8 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

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.

Operator reads CAUTION.

TQ-AA-106-0303 Page 9 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)

5.3.7. START

RHR PUMP A(B)P202 AND IMMEDIATELY THROTTLE OPEN 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 Operator presses the AP202 START pb.

Operator observes the AP202 START light illuminated and STOP light extinguishes.

Examiner Note:

F015A will fail closed and not establish flow.

Operator should secure the pump.

Operator immediately presses and holds the BC-HV-F015A RHR LOOP A 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.

TQ-AA-106-0303 Page 10 of 16 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 STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:

N/A TASK STANDARD:

Operator lines up and starts A RHR pump in Shutdown Cooling.

When the F015A fails to open, the operator stops the A RHR pump.

TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 11 of 16 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: SA T UNSAT QUESTION: RESPONSE: RESULT: SAT UNSAT TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)

Page 12 of 16 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 OPEN BC-HV-F007 B breaker OPEN BC-HV-F027 B breaker ENSURE BC-HV-F003A is closed. ENSURE BC-HV-F004A is closed. ENSURE BC-HV-F007A is close d. 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-F007 B AND the BC-HV-F027 B. PLACE red bezel covers on the BC

-HV-F007 A AND the BC-HV-F027 A. MARK procedure HC.OP-SO.BC-0002 complete up to step 5.3.4.

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

Page 13 of 16 REMOTE SCHEDULE: Initial @Time Event Action Description None None Insert remote RH30 B to TAGGED RH30 HV-F007 B RHR Pump A Min Flow Valve None None Insert remote ET00 6 to RACK_CLOSE ET00 6 GROUP 3B HV

-F027 B RHR Supp. Pool Spray None None Insert remote RH30A to TAGGED on event 1 RH30 HV-F007A RHR Pump A Min Flow Valve None None Insert remote ET005 to RACK_CLOSE on event 2 ET005 GROUP 3B HV

-F027A RHR Supp. Pool Spray None None Insert remote RH29A to FAIL_CLOSE RH29 GROUP 3E HV

-F015A RHR SDC Return Isol

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 number of reference procedure. Added validation time. Updated RHR flow in step 5.3.6 to update sim conditions. Y 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 identifie

d. 2. Knowledge and Abilities (K/A) is identified, and is

>3.0 (LOR) or

>2.5 (ILT) or 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.

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

(*). 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.

13. Statements describing important actions or observations that should be made by 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 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 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

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: NOH05JPMA0 2 E 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 Page 2 of 20 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:

EVALUATOR'S SIGNATURE:

DATE:

TQ-AA-106-0303 Page 3 of 20 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.

TQ-AA-106-0303 Page 4 of 20 2013 NRC S

-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:

N/A 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 of the procedure.

Operator determines correct beginning step to be 5.2.1 6

TQ-AA-106-0303 Page 5 of 20 2013 NRC S

-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)

(#Denotes a Sequential Step)

STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 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 Operator reads NOTE.~~

~~TQ-AA-106-0303 Page 6 of 20 2013 NRC S~~

~~-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)~~

~~(#Denotes a Sequential Step)~~

~~STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)~~

~~C A U T I O N After synchronization and closing a Generator Breaker, Load Setpoint should be increased to 30%~~

IMMEDIATELY. If the following steps are not completed or expected indications received, the CRS should consider tripping the Main Turbine and ensuring the Generator is isolated from the 500 Kv System and the Turbine is coasting down.

~~Operator reads CAUTION.~~

~~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 . * #~~

~~TQ-AA-106-0303 Page 7 of 20 2013 NRC S~~

~~-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)~~

~~(#Denotes a Sequential Step)~~

~~STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)~~

~~NOTE Ramp Rate will indicate 20 %/min until breaker is closed.~~

~~Upon breaker closure, ramp rate will be 60%/min for 2 seconds (2 % load)~~

~~Ramp Rate will then go to setpoint entered. Operator reads NOTE.~~

5.2.16.B SELECT Load Set, Ramp Rate AND ENTER 10 %/min On DEHC HMI, operator selects Load Set, Ramp Rate and enters 10 %/min. * # NOTE 1-XIL-6741D SYNCH WINDOW green light turns on when SYNCHROSCOPE point passes thru the 12 o'clock position AND line/bus voltage is within the normal operating range AND synchroscope rotation is < 3 RPM. Operator reads NOTE.

~~TQ-AA-106-0303 Page 8 of 20 2013 NRC S~~

~~-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)~~

~~(#Denotes a Sequential Step)~~

~~STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.2.16.C SELECT Load Set, Manual Adj.:~~

~~Raise OR Lower until pointer on SYNCHROSCOPE is moving slowly in the FAST direction. (10C651D)~~

~~On DEHC HMI, operator selects Load Set, Manual Adj. and presses:~~

~~Raise OR Lower until the pointer on the UNIT SYNCHRONIZING SYNCHROSCOPE is moving slowly in the FAST direction.~~

~~# 5.2.16.D IF the SYNCH WINDOW green light does NOT turn on as described in the note above, THEN REQUEST permission from SM/CRS to bypass the synch check relay AND GO TO Step 5.2.17.~~
Operator observes SYNCH WINDOW green light turns on.
5.2.16.E PERFORM the following (with Steps 5.2.16.E.1 thru 5.2.16.E.3 being performed in rapid succession):
N/A TQ-AA-106-0303 Page 9 of 20 2013 NRC S
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.2.16.E.1 WHEN the SYNCHROSCOPE Pointer is at 2 minutes before 12 O'clock position, AND the SYNCH WINDOW green light is illuminated, THEN CLOSE BS 6
-5 (BS 2-6) Breaker.
Operator presses the BS 6
-5 CLOSE pushbutton WHEN the SYNCHROSCOPE Pointer is at 2 minutes before 12 O'clock position, 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.E.2 Immediately SELECT Load Set, :
Setpoint AND ENTER 30 %. On the DEHC HMI, operator selects Load Set, :
Setpoint and enters 30 % .
~~# WHEN LOAD SET is raised TRIGGE R ET-1. N/A TQ-AA-106-0303 Page 10 of 20 2013 NRC S~~
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.2.16.E.3 IMMEDIATELY OBSERVE the 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 o'clock position Operator observes UNIT SYNCHRONIZING SYNCHROSCOPE pointer steady at 12 o'clock position.
OHA D3-B5 TURBINE GENERATOR VIB HI OHA D3-B5 TURBINE GENERATOR VIB HI received.
Operator informs CRS of Main Turbine high vibration condition
.
TQ-AA-106-0303 Page 11 of 20 2013 NRC S
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
CUE Acknowledge any RO alarm reports. N/A CUE Take any required actions.
N/A 1. DETERMINE bearing(s) in alarm CRIDS points A2519
- A2530. 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 reviews Alarm Response Procedure. Operator determines bearing #10 vibration in alarm CRIDS points A2528.
Operator dispatches an operator to t he #10 bearing.
CUE As Turbine Building Operator, REPORT "strong vibrations felt at the bearing."
N/A TQ-AA-106-0303 Page 12 of 20 2013 NRC S
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~2. ENTER HC.OP-AB.BOP-0002(Q), Main Turbine.~~
Operator notifies CRS to enter HC.OP
-AB.BOP-0002. CUE As CRS acknowledge operator notification to enter BOP
-0002. N/A 3. IF a valid Journal Vibration exceeds the following, immediately PRESS Main Turbine TRIP PBs.
RO determines Bearing #10 vibration has reached 12 mils.
~~RO trips Main Turbine using the 2 MAIN TURBINE TRIP pbs on 10C651D within 45 seconds of reaching 12mils.~~
~~TQ-AA-106-0303 Page 13 of 20 2013 NRC S~~
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
HC.OP-AB.BOP-0002 Main Turbine RETAINMENT OVERRIDE CONDITION II. Bearing 1
-10 Vibration @ 1800 RPM
~~ACTION THEN PERFORM the following:~~
~~a. REDUCE Recirc. Pump speed to MINIMUM. b. LOCK the Mode Switch in SHUTDOWN. II.B IMMEDIATELY TRIP the Main Turbine. Examiners Note:~~
Since reactor power is <24% the
reactor SHOULD NOT be scrammed.
RO's are directed to carry out RETAINMENT OVERRIDE ACTIONS.
Operator trips Main Turbine using the 2 MAIN TURBINE TRIP pbs on 10C651D within 45 seconds of reaching 12mils.
TQ-AA-106-0303 Page 14 of 20 2013 NRC S
-6, Rev 2 OPERATOR TRAINING PROGRAM NAME: JOB PERFORMANCE MEASURE DATE: SYSTEM: Main Generator TASK: Synchronize And Load The Main Generator STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 N/A TASK STANDARD:
Operator responds to Main Turbine High Vibration in accordance with HC.OP-AB.BOP-0002.
TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 15 of 20 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 16 of 20 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 # 1 Event code:
~~Description:~~
~~2 Event code:~~
~~Description:~~
~~Event code:~~
~~Description:~~
TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 17 of 20 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction TU1510 to 0 in 60 on event 1 Turbine bearing #10 vibration high None None Insert malfunction TU1509 to 5.50000 in 120 on event 1 Turbine bearing #9 vibration high None None Insert malfunction TU1511 to 5.00000 in 120 on event 1 Turbine bearing #1 1 vibration high 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: 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. Deleted redundant steps in examiner guide. Moved applicant cue sheet to last page.
Y 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.~~
~~2. Knowledge and Abilities (K/A) is identified, and is~~
>3.0 (LOR) or
>2.5 (ILT) or 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.~~
~~8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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.~~
~~13. Statements describing important actions or observations that should be made by 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 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 loadin~~
~~g. 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 Page 2 of 15 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. 2 5 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:
EVALUATOR'S SIGNATURE:
DATE:
TQ-AA-106-0303 Page 3 of 15 NAME: DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System TASK NUMBER:
209003 0101 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.
TQ-AA-106-0303 Page 4 of 15 JPM: 2013 NRC S
-2 OPERATOR TRAINING PROGR AM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:
Examiner Note: If applicant asks about RHR injection control, inform applicant that another operator will control RHR flow.
Operator obtains/locates procedure HC.OP-AB.ZZ-0001, Attachment 5.
Operator obtains the correct procedure.
1.0 IF an Initiation Signal is present
, THEN PERFORM the following:
Operator determines that an Initiation 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 RUNNING. Operator observes the B Core Spray Pump is not running.
Operator depresses the BP206 START push button
.
~~TQ-AA-106-0303 Page 5 of 15 JPM: 2013 NRC S~~
-2 OPERATOR TRAINING PROGR AM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
Operator observes that B Core Spray Pump is running.
1.0.B. ENSURE D Core Spray Pump is RUNNING. Operator observes the D Core Spray 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.
TQ-AA-106-0303 Page 6 of 15 JPM: 2013 NRC S
-2 OPERATOR TRAINING PROGR AM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.0.E. WHEN REACTOR PRESSURE is
< 461 psig, ENSURE HV-F005B is OPEN. Operator observes Reactor Pressure.
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.1 PRESS HV-F005B AUTO OPEN OVRD. Operator depresses the HV
-F005B AUTO OPEN OVRD pb.
Operator observes that HV
-F005B AUTO OPEN OVRD illuminates.
1.0.F.2 CYCLE HV-F005B as necessary to control Reactor Level.
Operator depresses the HV
-F005B OPEN pb. * # Operator observes the HV-F005B red OPEN light illuminates and the green CLSD light extinguishes.
TQ-AA-106-0303 Page 7 of 15 JPM: 2013 NRC S
-2 OPERATOR TRAINING PROGR AM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.0.G. WHEN flow is > 775 gpm, ENSURE HV-F031B is CLOSED.
Operator observes Core Spray System B flow on FI
-R601B to be >775 gpm.
Examiner Note:
HV-F031 has failed to auto close.
Operator observes HV
-F031B is open.
Operator depresses the HV
-F031B CLOSE pb.
~~Operator observes the HV-F031B green CLSD light illuminates and the red OPEN light extinguishes.~~
TQ-AA-106-0303 Page 8 of 15 JPM: 2013 NRC S
-2 OPERATOR TRAINING PROGR AM NAME: Rev: 2 JOB PERFORMANCE MEASURE DATE: SYSTEM: Core Spray TASK: Manually Start the Core Spray System STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 restore s reactor level to RPV Level 2 to Level 8 band with B Core Spray Loop (-38" to +54").
TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 9 of 15 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 10 of 15 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 # 4 Event code

~~Description:~~
ZDCS31CB >=1.0 HV-F031B Close PB pressed // Deletes stuck open min
-flow valve.
Event code:
~~Description:~~
~~Event code:~~
~~Description:~~
TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 11 of 15 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction DG02 A 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 CS0 4B 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 None None Insert malfunction RR31A1 to 10.00000 on event 2 Recirc loop A small break [V] (10%~60 gpm, 100%~600 gpm)
None None Insert malfunction RR31A2 to 0 on event 2 Recirc loop A large break [V] (10%~6000 gpm, 100%~60000 gpm)
None None Insert malfunction MS01 to 9.00000 on event 3 Steam line break in drywell 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
TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 12 of 15 OVERRIDE SCHEDULE:
Initial @Time Event Action Description None None Insert override 8S29_B_LO to Off on event 4 HV-F031B CLOSED (LO)
None None Insert override 8S29_C_LO to On on event 4 HV-F031B OPEN (LO)
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 validation time. Moved applicant cue sheet to final page of JPM. Added clarifying comments in examiner script.
Y TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER: 2013 NRC S
-2 REV#: 0 2 TASK: Manually Start the Core Spray System
~~1. Task description and number, JPM description and number are identified.~~
~~2. Knowledge and Abilities (K/A) is identified, and is~~
>3.0 (LOR) or
>2.5 (ILT) or 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.~~
~~8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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.~~
~~13. Statements describing important actions or observations that should be made by 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 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: NOH05JPSB1 2 E 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 Page 2 of 13 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 REFERENC ES: HC.OP-EO.ZZ-0320, Rev 6 TOOLS, EQUIPMENT AND PROCEDURES:
EOP-3 20 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:
EVALUATOR'S SIGNATURE:
DATE:
TQ-AA-106-0303 Page 3 of 13 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.
TQ-AA-106-0303 Page 4 of 13 JPM: SB012 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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:
N/A Operator obtains procedure Operator obtains procedure HC.OP-EO.ZZ-0320. Operator reviews precautions and limitations.
Operator reviews precautions and 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 precautions and limitations, inform operator that all are satisfied.
N/A TQ-AA-106-0303 Page 5 of 13 JPM: SB012 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~4.0 EQUIPMENT~~
REQUIRED EOP-320 Implementation Kit (NSS office EOP Drawer) contents:
1 set of fuse pullers 1 flashlight 1 plastic bag for ARI fuses 4 banana plug jumpers OR Key #9 for EOP Locker in OSC (obtain from SNSS office or break red key holder glass in OSC)
AND 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 Operator obtains the following required equipment:
EOP-320 Implementation kit from SM Office Clerk Area EOP drawer.
OR Key #9 from OSC office or key from break glass key holder in OSC for OSC EOP locker.
AND EOP-320 Implementation kit from EOP locker in OSC.
CUE Supply operator with EOP-320 implementation kit.
N/A Operator determines beginning step of the procedure.
Operator determines correct beginning step to be 5.2.1.
TQ-AA-106-0303 Page 6 of 13 JPM: SB012 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~5.2.1 ENSURE~~
that Prerequisites have been satisfied IAW Section 2.2.
Operator ensures Prerequisites are satisfied. CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.
N/A 5.2.2 On H11-P609, front, Division 1, left test box, INSERT a jumper between test point C71A
-K10A-2A (first column-first row, red jack) and test point C71A
-K12E-2B (fourth column-second row, black jack).
Operator installs jumper at H11
-P609 between test points C71A
-K10A-2A and C71A-K12E-2B.
~~CUE IF the JPM is being simulated in the Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.~~
N/A TQ-AA-106-0303 Page 7 of 13 JPM: SB012 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.2.3 On H11-P609, front, Division 3, left test box, INSERT a jumper between test point C71A
-K10C-2A (third column-fourth row, red jack) and test point C71A
-K12G-2B (fourth column-third row, black jack).
Operator installs jumper at H11
-P609 between test points C71A
-K10C-2A and C71A-K12G-2B.
CUE IF the JPM is being simulated in the Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated. N/A 5.2.4 On H11-P611, front, Division 2, left test box, INSERT a jumper between test point C71A
-K10B-2A (fourth column-fourth row, red jack) and test point C71A
-K12F-2B (first column
-second row, black jack).
Operator installs jumper at H11
-P611 between test points C71A
-K10B-2A and C71A-K12F-2B.
~~CUE IF the JPM is being simulated in the Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.~~
N/A TQ-AA-106-0303 Page 8 of 13 JPM: SB012 OPERATOR TRAINING PROGRAM NAME: Rev: 05 JOB PERFORMANCE MEASURE DATE: SYSTEM: Reactor Protection System TASK: Defeat RPS Interlocks STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.2.5 On H11-P611, front, Division 4, left test box, INSERT a jumper between test point C71A
-K10D-2A (third column-third row, red jack) and test point C71A
-K12H-2B (fourth column
-second row, black jack).
Operator installs jumper at H11
-P611 between test points C71A
-K10D-2A and C71A-K12H-2B.
~~CUE IF the JPM is being simulated in the Control Room, THEN inform the Operator that a jumper has been placed between the test jacks you indicated.~~
N/A 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 N/A TASK STANDARD:
Operator defeats RPS interlock IAW HC.OP-EO.ZZ-0320.
TQ-AA-106-0303 JOB PERFORMANCE MEASURE OPERATOR TRAINING PROGR AM EVALUATOR FOLLOWUP QUESTION DOCUMENTATION NAME: DATE: JPM Number: SB012 TASK: Defeat RPS Interloc ks 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? 0 1 3/26/13 Converted SB0 12 to new JPM format. Since Critical JPM 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.
Y 02 7/1/2013 Added Note to examiner guide. Minor grammatical changes. Added validation time.
N TQ-AA-106-0303 JOB PERFORMANCE MEASURE INITIAL CONDITION S: 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
DEVELOPED BY:
NRC DATE: 7-1-13 Instructor REVIEWED BY:
DATE: Operations Representativ e APPROVED BY:
DATE: Training Department
TQ-AA-106-0303 Page 2 of 13 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 2 5 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:
EVALUATOR'S SIGNATURE:
DATE:
TQ-AA-106-0303 Page 3 of 13 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
.
TQ-AA-106-0303 Page 4 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential St ep) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME:
N/A Operator obtains the correct procedure.
Operator obtains procedure HC.OP-AB.ZZ-0001 Attachment 6
. Operator determines beginning step of the procedure.
Operator determines correct beginning 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 PUMP is RUNNING.
Operator presses the OP216 START
pb. STAR Y N Operator observes the red RUNNING light illuminates.
TQ-AA-106-0303 Page 5 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential St ep) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.0.B ENSURE HV-F059 is OPEN.
Operator presses the HV
-F059 OPEN pb. * # STAR Y N Operator observes the red OPEN light illuminates and green CLSD light extinguishes.
1.0.C ENSURE HPCI AND RCIC Suctions are lined up to the CST.
Operator observes the HPCI HV
-F004 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-seconds. Operator presses HV
-F008 INCR pb for approximately 20 seconds.
~~STAR Y N Operator observes the HV~~
-F008 OPEN light illuminates.
TQ-AA-106-0303 Page 6 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential St ep) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.0.E ADJUST FIC-R600 HPCI FLOW setpoint to 1000 gpm.
Operator presses the LOWER SETPOINT pb on the FIC
-R600 controller until the pointer is on 1000 gpm. *# STAR Y N 1.0.F SIMULTANEOUSLY PERFORM the following:
N/A 1.0.F.1 START AUXILIARY OIL PUMP Operator presses the AUXILIARY OIL PUMP OP213 START pb.
~~Operator observes the red RUNNING light illuminates.~~
1.0.F.2 PRESS FD-HV-F001 OPEN Pushbutton Operator presses the HV
-F001 OPEN pb. *# Operator observes the red OPEN light illuminates and green CLSD light extinguishes.
TQ-AA-106-0303 Page 7 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential St ep) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 ADJUST FIC-R600 setpoint to 3000 gpm.
Operator observes HPCI Pump Discharge Pressure on PI-R601-E41 (red) indicator rises and lowers.
STAR Y N Operator presses the RAISE SETPOINT or LOWER SETPOINT pbs as necessary to obtain a flow setpoint of 3000 gpm.
(~50%)
~~TQ-AA-106-0303 Page 8 of 13 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential St ep) STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 1.0.I THROTTLE HV-F008 AND ADJUST FIC-R600 setpoint, as necessary, up to and including full flow rate, to control HPCI pump parameters/reactor pressure.
Operator presses the HV
-F008 INCR or DECR pbs and/or RAISE SETPOINT or LOWER SETPOINT pbs as necessary to adjust pump parameters.
STAR Y N 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.
REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME:
EXAMINER NOTE: When pressure turns and begins lowering, examiner may terminate the JPM.
N/A TASK STANDARD:
Operator places HPCI in Full Flow Test at approximately rated flow.
TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 9 of 13 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 TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 10 of 13 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 1 Event code:
~~Description:~~
TQ-AA-106-0303 JOB PERFORMANCE MEASURE SIMULATOR SETUP INSTRUCTIONS (OPTIONAL)
Page 11 of 13 MALFUNCTION SCHEDULE: Initia l 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 Trigg er Init Val Final Val 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.
Moved applicant cue sheet to final page
. N 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 Page 2 of 14 STATION: Hope Creek JPM NUMBER:
2013 NRC S
-5 REV: 0 2 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:
EVALUATOR'S SIGNATURE: DATE:
TQ-AA-106-0303 Page 3 of 14 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 Ma ke-up from Service Water Loop B IAW HC.OP~~
-EO.ZZ-0314.
TQ-AA-106-0303 Page 4 of 14 JPM: 2013 NRC S
-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 JOB PERFORMANCE MEAS URE DATE: SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
CUE PROVIDE the operator the initiating cue. Operator repeats back initiating cue.
CUE ENTER START TIME AFTER Operator repeats back the Initiating Cue: START TIME:
N/A Operator obtains the correct procedure.
Operator obt ains procedure HC.OP-E O.ZZ-0314. Operator reviews precautions and limitations.
Operator reviews precautions and limitations.
CUE IF excessive time is taken reviewing precautions and limitations, THEN INFORM operator that all are satisfied.
N/A Operator determines beginning step of the procedure.
Operator determines correct beginning step to be 5.
2.1.
TQ-AA-106-0303 Page 5 of 14 JPM: 2013 NRC S
-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 JOB PERFORMANCE MEAS URE DATE: SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~5.2.1 START~~
TIME:
ENSURE that all prerequisites have been satisfied IAW Section 2.2 of this procedure.
Operator Verifies Prerequisites
. 5.2.2. CLOSE BC-HV-F003B //RHR HX SHELL SIDE OUTLET MOV//
The operator depresses the close pushbutton for BC-HV-F003B * # The operator observes that the CLOSED indicator illuminates and the OPEN indicator extinguishes
~~5.2.3. VERIFY~~
CLOSED BC-HV-F048B //B RHR HX SHELL SIDE BYP MOV// Operator verifies closed BC
-HV-F048B # 5.2.4 OPEN EA-HV-2238 SERVICE WATER LOOP B EMERG M/U OUTBD ISLN (10C651).
The operator inserts key, rotates keylock to 'ON', and depresses the open pushbutton for EA-HV-2238. * # The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes
TQ-AA-106-0303 Page 6 of 14 JPM: 2013 NRC S
-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 JOB PERFORMANCE MEAS URE DATE: SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~5.2.5 ENSURE~~
breaker 52
-222082 is CLOSED, (to allow 1EAHV
-F073 to be opened).
The operator calls booth to ensure breaker 52
-222082 is close d CUE: Report that breaker 52
-222082 is CLOSED.
~~5.2.6 OPEN EA-HV-F073 SERVICE WATER LOOP B EMERG M/U INBD ISLN (10C651).~~
The operator inserts key into keylock, rotates to 'ON', and depresses the open pushbutton for EA-HV-F073 * # The operator observes that the OPEN indicator illuminates and the CLOSED indicator extinguishes 5.2.7 OPEN BC-HV-F075 //SSWS TO RHR LOOP B SUP MOV//.
The operator inserts keylock, roates to
'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.
~~5.2.8 WHILE~~
diverting the Service Water flow to the Suppression Chamber, MONITOR temperatures of all on-service, SACS and RACS cooling loads.
Operator monitors temperatures
TQ-AA-106-0303 Page 7 of 14 JPM: 2013 NRC S
-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 JOB PERFORMANCE MEAS URE DATE: SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
~~5.2.9 THROTTLE~~
OPEN BC-HV-F024B //RHR LOOP B TEST RET MOV// to control suppression chamber fill rate Operator depresses the open pushbutton for BC-HV-F024 B. * # 5.2.10 MONITOR Service Water Pump BP502 and/or DP502 Mot or Amps and Vibration for indications of pump run-out due to increased system flow Operator monitor s motor amps and vibration. 5.2.11 WHEN suppression chamber level returns to the desired band, RESTORE the RHR and Service Water systems to normal using Attachment 2 Operator determines that suppression chamber level is in the 74"-78" target band. NOTE: JPM may be terminated when 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.~~
REPEAT BACK any message from the operator on the status of the JPM, and then state "This JPM is complete". STOP TIME:
N/A TQ-AA-106-0303 Page 8 of 14 JPM: 2013 NRC S
-5 OPERATOR TRAINING PROGRAM NAME: Rev: 0 2 JOB PERFORMANCE MEAS URE DATE: SYSTEM: Primary Containment TASK: Suppression Chamber Makeup From Service Water Loop B STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation)
N/A TASK STANDARD:
Operator Restores Suppression Chamber Level By Using Suppression Chamber Makeup From Service Water Loop B
TQ-AA-106-0303 Page 9 of 14 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 TQ-AA-106-0303 Page 10 of 14 JPM NUMBER:
2013 NRC S
-5 REV#: 0 2 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~~
~~TQ-AA-106-0303 Page 11 of 14 REMOTE SCHEDULE~~
~~Initial @Time Event Action Description OVERRIDE SCHEDULE~~
~~Initial @Time Event Action Description~~
TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 12 of 14 REVISION HISTORY JPM NUMBER: 2013 NRC S
-5 Rev # Date Description Validation Required? 0 1 12/11/12 New JPM for NRC exam. Y 2 7/1/13 Numerous enhancements to examiner guide. Enhancements to cue sheet.
Y TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 13 of 14 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.~~
~~2. Knowledge and Abilities (K/A) is identified, and is~~
>3.0 (LOR) or
>2.5 (ILT) or 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.~~
~~8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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 th e procedural step.~~
~~13. Statements describing important actions or observations that should be made by 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 Steve Loper RO On File 6-26-13 Name Qual Signature Date TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 14 of 14 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 t o 74"-78" using Suppression Chamber Ma ke-up from Service Water Loop B IAW HC.OP
-EO.ZZ-0314.
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 Page 2 of 20 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: EVALUATOR'S SIGNATURE:
DATE:
TQ-AA-106-0303 Page 3 of 20 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.
TQ-AA-106-0303 Page 4 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 HC.OP-EO.ZZ-0318. Operator obtains the correct procedure.
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.
Operator determines beginning step of the procedure Operator determines correct beginning step to be 5.1.1.
TQ-AA-106-0303 Page 5 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.1 VENT the containment via the Hard Torus Vent as follows:
A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.
Operator reviews Prerequisites and ensures Prerequisites complete.
CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.
5.1.1 B. NOTIFY the Emergency Duty Officer that containment venting via the Hard Torus Vent will be performed.
Operator notifies the CRS to notifiy the EDO that containment venting via the Hard Torus Vent will be performed.
CUE Acknowledge the communication to the EDO.
5.1.1 C. In the Lower Relay Room, Elev 102' at panel 1YF404 (see Attachment 2), INSTALL F22 (6 amp fuse).
Operator directs the field operator to install fuse F22 at panel 1YF404.
#
TQ-AA-106-0303 Page 6 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 a nd OPEN GS-HV-4964 SUPP CHMBR TO CPCS DMP.
Operator depresses the ISLN OVRD pushbutton for the HV
-4964. * # 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 venting will commence at the South end of the Reactor Building via the Hard Torus Vent.
Operator announces containment venting will commence at the South end of the Reactor Building via the Hard Torus Vent over the plant paging system.
TQ-AA-106-0303 Page 7 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.1 F. When HV-4964 SUPP CHMBR TO CPCS DMP is full open, then OPEN GS-HV-11541 TORUS VENT ISOLATION VALVE.
Operator observes that the HV4964 OPEN indicator is illuminated. Operator observes that the HV4964 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 and direct Operator to continue to implement the procedure until a vent path is established.
Examiner Note:
Based on the Initial Conditions, the Reactor Building is NOT accessible. Manually opening the
HV-11541 is not an option.
TQ-AA-106-0303 Page 8 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.1 G. When drywell pressure can be maintained below 60 psig, then CLOSE GS-HV-11541 TORUS VENT ISOLATION VALVE.
Operator determines drywell pressure is not being maintained below 60 psig, continues on in the procedure.
5.1.1 H. REPEAT steps 5.1.1.O thru 5.1.1.G as necessary to reduce and maintain drywell pressure below 65 psig.
Operator determines repeating these steps will not establish a vent path.
5.1.1 I. If actions taken to reduc e containment pressure have been unsuccessful, then continue in this procedure.
Operator determined actions taken thus far have not been successful, continues in the procedure.
5.1.2 VENT the containment via the Suppression Chamber supply and ILRT piping as follows:
Operator determines this path is not available since it requires access to the Reactor Building and the reactor Building is not accessible.
TQ-AA-106-0303 Page 9 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 supply and ILRT piping as follows:
Operator determines this path is not available since it requires access to the Reactor Building and the reactor Building is not accessible.
5.1.4 VENT the containment via the Suppression Chamber 2" exhaust as follows: Operator determines the Suppression Chamber 2" exhaust is the next most 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).
TQ-AA-106-0303 Page 10 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.4 A. ENSURE that all prerequisites have been satisfied in accordance with Section 2.0 of this procedure.
Operator reviews Prerequisites and ensures Prerequisites complete.
CUE If excessive time is taken reviewing Prerequisites, inform operator that all are satisfied.
5.1.4 B. NOTIFY the Emergency Duty Officer that containment venting of the Suppression Chamber to the Reactor Building will be performed.
Operator notifies the CRS to notifiy the EDO that containment venting of the Suppression Chamber to the Reactor Building will be performed.
CUE Acknowledge the communication to the EDO.
5.1.4 C. DEPRESS ISLN OVRD and OPEN GT-HD-9372A Drwl Purge Vent Exh Dmpr.
Operator presses the DRYWELL PURGE SHUT OFF DMPRS ISLN OVRD pushbutton.
~~# Operator observes the pushbutton backlights.~~
TQ-AA-106-0303 Page 11 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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 OPEN GS-HV-4964 SUPP CHMBR TO CPCS DMP.
Operator observes the amber OVER
-RIDDEN light for the HV
-4964 ISLN 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 of the Suppression Chamber to the Reactor Building. Operator announces containment venting of the Suppression Chamber to the Reactor Building over the plant page. * #
TQ-AA-106-0303 Page 12 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.4 F. When GS-HV-4964 SUPP CHMBR TO CPCS DMP is full open, then DEPRESS ISLN OVRD and OPEN GS-HV-4963 SUPP CHMBR N 2 M/U EXH. Operator observes red HV4964 OPEN light is illuminated and green CLSD light is extinguished.
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.
TQ-AA-106-0303 Page 13 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT evaluation) 5.1.4 G. When drywell pressure can be maintained below 60 psig, then CLOSE GS-HV-4963 SUPP CHMBR N 2 M/U EXH and GS
-HV-4964 SUPP CHMBR TO CPCS DMP. Operator informs CRS that drywell venting has commenced and monitors drywell pressure.
Examiner Note:
If drywell pressure drifts below 60psig during performance of JPM, direct applicant to continue with venting. CUE IF the operator cannot see the pressure reduction on the 10C650E indicators, THEN inform the operator Drywell pressure reduction is observable on SPDS. Examiner Note:
The rate of drywell pressure reduction through this path alone is slow and will not be readily visible on the 10C650E indicators due to the absence of a tenth digit. The response IS readily observable on SPDS. The operator may not be satisfied with the initial response and may elect to open an additional vent path.
TQ-AA-106-0303 Page 14 of 20 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 STEP NO. ELEMENT (*Denotes a Critical Step)
(#Denotes a Sequential Step)
STANDARD * # EVAL S/U COMMENTS (Required for UNSAT 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.
TQ-AA-106-0303 JOB PERFORMANCE MEASURE Page 15 of 20 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 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 # 2 Event co de:~~
~~Description:~~
pcpdw >= 16.2
// Drywell Pressure in psia 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 None N one Insert malfunction FW32 to 100.00000 on event 2 Feedwater line break inside containment None None Insert malfunction FW04A after 60 on event 2 Secondary condensate pump AP137 trip None None Insert malfunction FW04B after 60 on event 2 Secondary condensate pump BP137 trip None None Insert malfunction FW04C after 60 on event 2 Secondary condensate pump CP137 trip None None Insert malfunction MS01 after 90 to 4.00000 on event 2 Steam line break in drywell None None Insert malfunction PC04 on even t 4 Downcomer break REMOTE SCHEDULE
Initial @Time Event Action Description None None Insert remote RH23B to TAGGED RH23 RHR Pump B None None Insert remote RH20A to RACK_OUT RH20 HV-F021A RHR CTMT SPRAY None None Insert remote ET067 to INSTALLED on event 3 ET067 HV-11541 Torus vent None None Insert remote IA10 to RUN IA10 Temporary station air compressor None None Insert remote EP38 to Emergency EP38 EOP-319, Restoring 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. Updated cue sheet sup pool level to reflect simulator conditions. Added examiner note.
Y TQ-AA-106-0303 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST JPM NUMBER:
2013 NRC S
-8 REV#: 0 2 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.~~
~~2. Knowledge and Abilities (K/A) is identified, and is~~
>3.0 (LOR) or
>2.5 (ILT) or 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.~~
~~8. Critical steps meet the criteria for critical steps and are identified with an asterisk (*). 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.~~
~~13. Statements describing important actions or observations that should be made by 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 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 7/2 2/13 Instructor DATE APPROVED BY:~~
LORT Group Lead or Designee DATE APPROVED BY:
Shift Operations Supervisor or Designee DATE NRC 2013 Scenario #1 Page 2 of 29 Rev.: 4 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-9414 A 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 wi ll 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 3 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 4 of 29 Rev.: 4 EVENT FILE:
Initial ET # 6 Event code:
~~Description:~~
zcrprun <= 0.0
// Mode Switch NOT in RUN Triggers Feedwater Line Break and LOCA on scram.
7 Event code:
~~Description:~~
Pcpdw > 17.0
// DW pressure above 2 psig Trips A RHR Pump after start 10 Event code:
~~Description:~~
ad_k40b(2) >= 1.0
// SRV F013B 'B' Channel solenoid energized Triggers blowing of fuses when valve opened to ED.
11 Event code:
~~Description:~~
ad_k40d(2) >= 1.0
// SRV F013B 'D' Channel solenoid energized Triggers blowing of fuses when valve opened to ED.
Event code:
~~Description:~~
~~Event code:~~
~~Description:~~
~~Event code:~~
~~Description:~~
~~Event code:~~
~~Description:~~
~~Event code:~~
~~Description:~~
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 None None Insert malfunction RH08A RHR System A auto injection failed t o energized None None Insert malfunction RH08 B RHR System B auto injection failed to energized None None Insert malfunction ED04 on event 4 Loss of 7.2 KV bus F 10A120 None None Insert malfunction RR26A2 to 10.00000 in 300 on event 5 Recirc pump AP201 elevated (added to calc) Pump Vib None None Insert malfunction FW32 to 10.00000 on event 6 Feedwater line break inside containment 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 None None Insert malfunction QQ20 to SHORT after 3 on event 7 RHR pump AP202 Malfunctions None None Insert malfunction CD09A after 90 to 75.00000 on event 15 Drive water flow control valve F002A failure None None Insert malfunction CD09B to 0 on event 15 Drive water flow control valve F002B failure None None Insert malfunction PC04 on event 6 Downcomer failure
REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote RC03 to RACK_CLOSE RC03 GROUP 6A HV
-F007 RCIC Steam Supply Isol None None Insert remote RC04 to RACK_CLOSE RC04 GROUP 6A HV
-F076 RCIC Steam Supply Isol None None Insert remote RC05 to RACK_CLOSE RC05 GROUP 6A HV
-F008 RCIC Steam Supply Isol None None Insert remote AN24 after 5 to NORM on event 2 AN24 E6-C5 RBVS & Wing Area HVAC Pnl 10C382 None None Insert remote HV01 to STOP on event 2 HV01 RBVS Exhaust fan A N one None Insert remote HV02 to STOP on event 2 HV02 RBVS Exhaust fan B None None Insert remote HV03 to STOP on event
2 HV03 RBVS Exhaust fan C None None Insert remote HV04 to STOP on event 2 HV04 RBVS Supply fan A None None Insert remote HV05 to STOP on event 2 HV05 RBVS Supply fan B None None Insert remote HV06 to STOP on event 2 HV06 RBVS Supply fan C None None Insert malfunction QQ20 to SHORT after 3 on event 7 RHR pump AP202 Malfunctions None None Insert remote AD01B
-B to REMOVED on event 10 AD01 ADS/Relief valve F013B channel B fuse None None Insert remote AD01B
-D to REMOVED on event 11 AD01 ADS/Relief valve F013B channel D fuse None None Insert remote CD04 to OPEN on event 14 CD04 CRD suction filter isolation valve V030 None None Insert remote CD06 to 100.00000 in 60 on event 15 CD06 Drive water press cont bypass valve V062 (0
-100%) None None Insert remote CD10 after 120 to ON on event 15 CD10 CRD FCV B
OVERRIDE SCHEDULE:
Initial @Time Event Action Description Non e 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) None None Insert override 4A1_F_DI to Off HV-F032A CLOSE
-FW SUPPLY LINE A (DI) None None Insert override 1A159_F_DI to On on event 1 HD-9414A CLOSE
-INBD EXH-REACTOR BUILDING (DI)
None None Insert override 1A159_E_DI to On on event 1 HD-9414A OPEN
-INBD EXH-REACTOR BUILDING (DI)
None None Insert override 10S192_A_DI to Off on event 6 HV-F016B OPEN (DI)
None None Insert override 10DS40_A_LO after 3 to On on event 7 PUMP MOTOR OVER CURRENT
-RHR A-LOOP A (LO)
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 Swapping RACS pumps
~~Crew places AP209 RACS pump in service and secures BP209 RACS pump after assuming the watch~~
. CRS directs PO to place AP209 RACS pump in service and secure BP209 RACS pump.
IF dispatched to AP209, THEN REPORT the AP209 RACS pump is ready for a start. PO dispatches RBEO to perform pre-start checks and locally observe start of AP209 RACS pump IAW OP-HC-108-106-1001. AFTER AP209 is in service, THEN REPORT AP209 is running SAT.
Monitor Items:
Normalized AP209 speed cwnra209 PO starts AP209 and secures BP209 IAW SO.ED
-0001 Section 5.3.6 (Marked up through 5.3.5)
HPI USED: STAR PEER CHECK FLAGGING OP BARRIERS Power reduction with Recir c: After assuming the watch
. CRS directs RO to reduce reactor power to 90% IAW Reactor Engineering guidance
and HC.OP-IO.ZZ-0006. SUPPORT crews actions to TOGGLE Crossflow.
RO to reduce reactor power to 90% IAW Reactor Engineering guidance OP
-AB-300-100 3. HPI USED: STAR PEER CHECK FLAGGING OP BARRIERS 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 Loss of RBVS
~~After the Crew lowers reactor power , OR at the discretion of the Lead Examiner, TRIGGER ET~~
-1 (RBVS Exhaust Damper HD
-9414A Fails shut).
Crew recognizes Loss of RBVS by: OHA E1-F5 "COMPUTER PT IN ALARM" CRIDS B7164 "REACTOR BLDG DIFF PRESS" OHA E6-C5 "RBVS & WING 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, THEN REPORT Low Flow Trip alarms on all Reactor Bldg Supply and exhaust fans.
Crew dispatches RBEO to 10C382 to investigate.
RO/PO recognize HD
-9414A failed shut by 10C651E indication and inform CRS.
IF directed to secure RBVS, THEN TRIGGER ET
-2. RO/PO place FRVS in service IAW SO.GU-0001 -or- hardcard. HPI USED: STAR PEER CHECK FLAGGING OP BARRIERS IF dispatched to HD
-9414 A , THEN REPORT there is no obvious reason for the closure.
Crew dispatches NEO and Maintenance to investigate closure of HD
-9414 A.
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 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
~~15 minutes after the Loss of RBVS, OR, at the discretion of the Lead Examiner, TRIGGER ET~~
-4. Crew recognizes:
Reactor power lowering Reactor level swell 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 11 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 and 'B' SCP by:
OVLD/PWR FAIL lights STOP lights lit Motor amps zero The trips of 'B' PCP and 'B' SCP are silent and may not be immediately recognized by the 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 TB chiller by:
OVLD/PWR FAIL light STOP light lit Motor amps zero The trip of BK111 is silent and may not be immediately recognized by the Crew.
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 12 of 29 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments CRS implements AB.RPV
-000 3: Condition A Condition B The pace of the scenario will not allow the Crew to fully address single loop requirements.
IF the Crew manually scrams, THEN the Feedwater Line Break and LOCA will be automatically inserted.
IF in Region 1 of the Pwr/Flow map, THEN RO inserts rods IAW ESG guidance as necessary to exit Region 1. HPI USED: STAR PEER CHECK RO/PO close HV
-F031B Recirc pump discharge valve for 5 minutes, then re
-open. HPI USED: STAR 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 discharge valve.
HPI USED: STAR PEER CHECK FLAGGING OP BARRIERS PO closes HV
-1651B SCP discharge valve. HPI USED: STAR PEER CHECK FLAGGING OP BARRIERS 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 PO bypasses Feedwater Runbacks. HPI USED: STAR PEER CHECK WHEN dispatched, THEN REPORT the 10A120 Bus Differential Overcurrent Relays are tripped. There is no visible indication of damage to the bus. Crew dispatches TBEO and Maintenance to investigate loss of 10A120 bus.
As RE, REPORT the Enhanced Stability guidance should be 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 contacts RE for guidance and to check thermal limits.
Crew references Power Maneuvering Tech Specs in OP-HC-108-106-1001 Equipment Operational Contro
~~l. 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 14 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 Managemen t. 'A' Recirc Pump High Vibration: 15 minutes after the Loss of 10A120, OR , at the discretion of the Lead Examiner, TRIGGER ET
-5. Crew recognizes rising vibrations on 'A' Reactor Recirc pump by:
CRIDS A2601 "RECIRC PMP A RADIAL VIB MON" OHA C1-F5 "COMPUTER PT IN ALARM" OHA C1-E4 "REACTOR RECIRC PUMP VIB HI" CRIDS D2920 "RECIRC PUMP MOTOR A VIBRATION" CRIDS D5351"RECIRC PUMP AP201 VIBRATION" Vibration will jump 3 mils then rise at a rate of one mil per minute.
C1-E4 and C1-F5 will alarm at 11 mils.
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 15 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 SHUTDOWN and performs scram actions IAW AB.ZZ
-0001 Att. 1. HPI USED: STAR HARD CARD 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
The feedwater line break inside containment with leakage past the check valve will be automatically inserted when the Mode Switch is taken out of RUN. Crew recognizes High Drywell Pressure EOP entry condition:
OHA A7-D4 "DRYWELL PRESSURE HI/HI" OHA C5-B5 "DRYWELL PRESSURE HI" Various system initiations and isolations RECORD Drywell Pressure reached 1.68 psig for 15 min ECG Classification.
Time: __________
CRS implements:
EOP-101 EOP-102 PO attempts to maintain level as directed by CRS.
HPI USED: STAR HARD CARD The feedwater line break will prevent restoring level with HPCI or feedwater.
CRS determines an Alert Classification is required IAW ECG Section RB2.L (Drywell pressure >1.68 psig due to RCS leakage). (May be done after scenario completion.)
RECORD time Alert declared. Time Declared: ________
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 directed to open the breaker for the HPCI HV
-8278 in an attempt to fail the valve shut, THEN REPORT the breaker handle on the cubicle door does not appear to be engaging the breaker paddle inside the cubicle. You cannot get the cubicle door open and have called the 12 Hour Maintenance Supervisor and asked for an Electrician to help.
Do NOT fail the valve shut.
Crew recognizes 'A' feedwater line break by:
High Flow / Low Discharge Pressure on condensate High Flow / Low Discharge Pressure on HPCI Ability to vary HPCI flow with Setpoint Absence of OHA B1
-E5 "HPCI PUMP DISCHARGE FLOW LO" Rapidly rising torus level Lowering hotwell level RPV Pressure trend not consistent with a LOCA greater than the capacity of HPCI/Condensate IF directed to close the F032A, THEN REPORT the actuator appears to be broken. The valve will not stroke from the bucket or locally with the manual handwheel.
Crew may attempt to isolate the 'A' Feedwater line if they successfully diagnose a FW line break. HPI USED: STAR The HV-F032A will not close from the Control Room. 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 17 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 b y: 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 18 of 29 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments I F directed to align for two CRD pump injection, THEN PERFORM the 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.
RO/PO align CRD for Emergency Two CRD Pump Injection IAW SO.BF-0001 Section 5.4.
HPI USED: STAR HARD CARD Bypass Valves Fail Shut
~~The Bypass Valves will Fail shut three minutes after the EHC pump trips.~~
Crew recognizes bypass valves will not open by:
OHA E1-F4 "COMPUTER POINT RETURNED TO NORMAL" OHA D3-D5 "EHC UNIT PANEL 10C363" Bypass valve indication BPV Positioning Error alarms Reactor pressure rising above Pressure Setpoint OHA E1-F4 will not be received if no bypass valves were open at the time of the failure.
OHA D3-D5 will not be received until there is an open demand to the bypass valves.
CRS directs pressure control IAW EOP-101 using Steam Line Drains and/or RFPTs.
RO/PO control pressure as directed by CRS IAW AB.ZZ-0001 Attachment 15.
HPI USED: STAR HARD CARD
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 RHR Pump A and B Fail to Auto Start, A Trip s & HV-F016B fails to open
~~The 'A' RHR pump immediately trips after being manually started AND HV-F016B Drywell Spray Valve fails to open.~~
Crew recognizes "A" and "B" RHR pumps fail to auto
-start on LOCA signal by: Pump STOP, amp and flow indications 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 trip of the 'A' RHR pump, THEN REPORT: 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 Crew dispatches operator and Maintenance to the tripped RHR pump and breaker.
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 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 Suppression Chamber Cooling/Spray or Drywell Spray IAW AB.ZZ-0001 Att. 3. HPI USED: STAR HARD CARD 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 21 of 29 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION For non-ATWS emergency depressurizations, the Control Room Supervisor should establish and 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.
Crew prevents injection from Core Spray and LPCI pumps not required for adequate core cooling. RO/PO open ADS valves IAW AB.ZZ-0001 Attachment 13.
HPI USED: 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 22 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 IAW AB.ZZ-0001 Att. 13, informs CRS of PSV-F013B failure.
HPI USED: STAR HARD CARD CRS directs restoring RPV level to -38" to 54" with Low Pressure ECCS. RO/PO restore RPV level as directed by CRS IAW AB.ZZ-0001: Att. 4 for RHR Att. 5 for Core Spray HPI USED: STAR HARD CARD IF RPV water level 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 23 of 29 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments RO/PO align RHR IAW AB.ZZ-0001: Att 2 Drywell Spray HPI USED: STAR 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 24 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-00 00 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 25 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. SRV's 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 it's 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 26 of 29 Rev.: 4 2013 NRC Scenario #1, Rev. 0 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 TRANSIENTS:
LOSS OF SUPPORT 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 27 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 MONITORI NG None Page 28 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 29 of 29 Rev.: 4 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't)
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
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 2013 NRC Scenario #2 Page 2 of 30 Rev: 4 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 1CD48 1 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 3 of 30 Rev: 4 IV. INITIAL CONDITIONS:
I.C. Initial INITIALIZE the simulator to 100% power, 3840 MW t h, 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 3 3). 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 4 of 30 Rev: 4 EVENT FILE:
Initial ET # 5 Event code:
~~Description:~~
rr_52(1) < 1.0 // 'A' Recirc pump breaker A RRP stopped initiates power oscillations
. 7 Event code:
~~Description:~~
crqnmi <=30 Reactor Power less than 30%
Trips SBLC Pumps after MS placed in SD.
8 Event code:
~~Description:~~
~~zcrprun <= 0.0 // Mode Switch NOT in RUN Initiates hydraulic full core ATWS 16 Event code:~~
~~Description:~~
~~rhf2 4(1) > 300 // 'A' RHR in Chamber Cooling Trips B C-HV-F024A when placed in Chamber Cooling 17 Event code:~~
~~Description:~~
~~rhf2 4(2) > 300 // 'B' RHR in Chamber Cooling Trips BC-HV-F024 B when placed in Chamber Cooling 18 Event code:~~
~~Description:~~
et_array(16)
// Detects BC-HV-F024A tripped to remove B malfunction 19 Event code:
~~Description:~~
et_array(17)
// Detects BC-HV-F024B tripped to remove A malfunction 30 Event code:
~~Description:~~
ZLSLPMAS SBLC PUMP A started
2013 NRC Scenario #2 Page 5 of 30 Rev: 4 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction TC07A EHC pump A trip None None Insert malfunction CU11A RWCU isolation valve F001 failure to auto close None None Insert malfunction CU1 1B RWCU isolation valve F004 failure to auto close None None Insert malfunction ED09C1 on event 2 Loss of 120 VAC class 1E inst bus 1CD481 None None Insert malfunction RR05A to 100.00000 in 60 on event 3 Recirc pump A inboard seal failure None None Insert malfunction RR06A after 180 from 12.00000 to 100.00000 in 360 Recirc pump A outboard seal failure None None Insert malfunction CR02A after 60 to 80.00000 in 3 00 on event 5 Reactor Core Instabilities (LPRMs)
None None Insert malfunction AN
-C3F2 after 300 on event 5 CRYWOLF ANN C3F2 OPRM ALARM None None Insert malfunction SL01B after 120 on event 7 SBLC injection pump BP208 failure None None Insert malfunction TC07B after 360 on event 7 EHC pump B trip None None Insert malfunction RP06 after 2 on event 8 Half-core ATWS
- left side None None Insert malfunction RP07 after 2 on event 8 Half-core ATWS
- right side None None Insert malfunction CR02A after 1 to 0.00000 on event 8 Reactor Core Instabilities (LPRMs)
None None Insert malfunction CW15B on event 2 Prevents auto
-start of SACS Pump B None None Insert malfunction SL01B after 240 on event 30 Trips SBLC Pump B
2013 NRC Scenario #2 Page 6 of 30 Rev: 4 REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote HV12 to R UN HV12 Steam tunnel unit cooler BVH216 None None Insert remote EP01 after 36 0 to BYPASS on event 11 EP01 EOP-301, Bypass MSIV (-129") & High Temp Isolations None None Insert remote EP02 after 480 to BYPASS on event 1 2 EP02 EOP-311, Bypass PCIG (-129") Isolation None None Insert remote EP 38 after 180 to BYPASS on event 1 3 EP05 EOP-319, LOCA level 2 interlock for 10K100 None None Insert remote EP09 after 240 to REMOVED on event 14 EP09 EOP-320 (step 5.1.2), ARI valve fuses F6A/F5A None None Insert remote EP10 after 240 to REMOVED on event 14 EP10 EOP-320 (step 5.1.4), ARI valve fuses F6B/F5B None None Insert remote EP11 to INSTALLED after 360 to INSTALLED on event 14 EP11 EOP-320 (step 5.2.2), RPS division 1 jumper None None Insert remote EP13 to INSTALLED after 360 to INSTALLED on event 14 EP13 EOP-320 (step 5.2.3), RPS division 3 jumper None None Insert remote EP12 after 720 to INSTALLED on event 14 EP12 EOP-320 (step 5.2.4), RPS division 2 jumper None None Insert remote EP14 after 720 to INSTALLED on event 14 EP14 EOP-320 (step 5.2.5), RPS division 4 jumper None None Insert remote EP35 after 180 to FAIL_CLOSE on event 15 EP35 EOP-322 HV-F006 HPCI to CS None None Insert remote RH25A to RACK_OUT on event 16 RH25 GROUP 3A HV
-F024A RHR Supp. Pool Clg None None Insert remote RH25B to RACK_OUT on event 17 RH25 GROUP 3A HV
-F024B RHR Supp. Pool Clg None 19 Remove remote RH25A to NORMAL RH25 GROUP 3A HV
-F024A RHR Supp. Pool Clg None 18 Remove remote RH25B to NORMAL RH25 GROUP 3A HV
-F024B RHR Supp. Pool Clg None None Insert remote AN24 after 5 to NORM on event 2 0 AN24 E6-C5 RBVS & Wing Area HVAC Pnl 10C382 None None Insert remote HV01 to STOP on event 2 0 HV01 RBVS Exhaust fan A None None Insert remote HV02 to STOP on event 2 0 HV02 RBVS Exhaust fan B None None Insert remote HV03 to STOP on event 2 0 HV03 RBVS Exhaust fan C None None Insert remote HV04 to STOP on event 2 0 HV04 RBVS Supply fan A None None Insert remote HV05 to STOP on event 2 0 HV05 RBVS Supply fan B None None Insert remote HV06 to STOP on event 2 0 HV06 RBVS Supply fan C
2013 NRC Scenario #2 Page 7 of 30 Rev: 4 OVERRIDE SCHEDULE:
Initial @Time Event Action Description
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 N2 M/U to the Primary Containment
~~CRS directs N2 Makeup to the Primary Containment.~~
Refer to SO.GS
-0001 Section 5.2 and SUPPORT requests for field manipulations with appropriate reports.
(The simulator does not model any of these functions. The N2 vaporizer is always lined up for make-up). PO conducts N2 makeup to the Primary Containment IAW SO.GS-0001 Section 5.2 and 5.3. Power Reduction
~~Crew lowers power to 90% RTP using recirculation pumps~~
. CRS directs RO to reduce reactor power to 90% IAW Reactor Engineering guidance and 5.2 of HC.OP
-IO.ZZ-0006. HPI USED: STAR PEER CHECK 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
~~After the Crew assumes the watch and at the discretion of the Lead Examiner, TRIGGER ET~~
-2 (Loss of CD481 120AC 1E Inverter).
Crew recognizes loss of CD481 by: OHA D3-E3 "120VAC UPS TROUBLE" OHA C6-A1 "RSP/RSS 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 9 of 30 Rev: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched to 10C382, THEN REPORT Low Flow Trip alarms on all Reactor Bldg Supply and Exhaust fans.
IF directed to secure RBVS, THEN TRIGGER ET
-2 0. Crew recognizes loss of Reactor Building Ventilation by:
Supply/Exhaust Dampers HD
-9370A AND HD
-9414A closure Fans trip 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 T ACS 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 10 of 30 Rev: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments IF dispatched 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 Crew dispatches ABEO and Maintenance to CD481 inverter.
CRS implements AB.CONT-0002: Condition B CRS recognize the following Tech Spec actions apply:
Distribution
- Operating 3.8.3.1 action a Must restore CD481 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
CRS contacts Operations Management.
Recirc Pump Seal Failure
~~After loss of Inverter actions are complete, AND at the discretion of the Lead Examiner, TRIGGER ET~~
-3 ('A' Recirc Pump Dual Seal Failure).
Crew recognizes second stage seal failure on 'A' Recirc pump by: OHA C1-F5 "COMPUTER PT IN ALARM" CRIDS D2924 "RECIRC PUMP A SEAL LKG FLOW HI" CRIDS D2926 "RECIRC PUMP A SEAL STAGE FLOW HILO" Lowering second stage seal pressure First stage seal failure will occur three minutes after the second stage.
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 CRS implements AB.RPV
-0003: Condition D Condition E IF dispatched to report local seal pressures on 77' Rx Bldg, THEN REPORT readings consistent with CRIDS (Page 85), OR the following Monitor Items:
(Monitor Items are psia)
'A' Recirc Inbd (#1) Seal rrpsl1(1) - 15 = psig 'A' Recirc Outbd (#2) Seal rrpsl2(1) - 15 = psig Crew recognizes 'A' Recirc pump dual seal failure by:
OHA C1-F5 "COMPUTER PT IN ALARM" reflash Changing seal pressures Rising seal temperatures OHA C6-B1 "DLD SYSTEM ALARM/TRBL" RM11 9AX317/318/320 DLD CCM alarms RM11 9AX314 DLD Floor Drain Flow alarm Rising drywell pressure RECORD time dual recirc pump seal failure is recognized OR OHA C6-B1 is received (whichever is first) for ECG Classification
. Time: ________
CRS implements AB.CONT
-001: Condition A RO/PO ensure drywell cooling is maximized.
HPI USED: STAR Monitor Items:
HV-F023A rrvf23(1) HV-F100 cuvf100 HV-F031A rrvf31(1) CREW trips and isolates the 'A' RR pump before DRWL pressure reaches 1.68 psig by closing the:
HV-F023A HV-F100 HV-F031A RECORD drywell pressure when 'A' Reactor Recirc pump is isolated:
Drywell Pressure: ____
CRS implements AB.RPV
-0006: Condition B Condition C
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 IF the Crew scrams during the seal failure, THEN proceed to the ATWS. Power Oscillations NOT observed. Crew validates successful recirc isolation by:
Seal pressures and temperatures Trending DLD flows Trending drywell pressure and temperature Crew monitors plant response to the transient.
Power Oscillations ENSURE Trigger ET-5 , Power Oscillations, is activated when Recirc Pump A is tripped.
Crew recognizes power oscillation and locks the mode switch in Shutdown IAW AB.RPV-0003 Immediate Operator Actions RO performs scram actions IAW AB.ZZ-0001 Attachment 1.
ATWS >4%: Full core hydraulic ATWS w/ failure of ARI.
Crew recognizes Scram Condition and Reactor Power Above 4% EOP entry condition:
APRM indications Absence of rod FULL IN lights on the Full Core Display Rod position indications RECO RD time of Mode Switch to SHUTDOWN or Turbine Trip (whichever was first) for 15 min ECG Classification.
Time: _______
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 Reactor Scram Reports 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 t he Control Room staff IAW HC.OPAB.ZZ
-0001. RO performs ATWS actions IAW AB.ZZ-0001 Attachment 1.
HPI USED: STAR HARD CARD 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 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.
CRS implements EOP
-101A.
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 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION For ATWS conditions where reactor 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.
PO stabilizes and maintains RPV level as directed by CRS.
CRS directs:
Initiating SLC Verifying RWCU Isolates RO/PO initiate SLC and verify RWCU isolates.
HPI USED: 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:
HV-F001 cuvf001 HV-F004 cuvf004 RO/PO close RWCU HV
-F001 and HV-F004. HPI USED: STAR Immediate Operator action IAW AB.CONT-0002.
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 Crew initiates closure of RWCU HV-F001 OR HV-F004 after SBLC Pumps started.
RECORD time between starting SBLC pump and valve closure.
Time: ________
Trip of SLC Pump s: BP208 failure inserted 120 seconds after reactor power is less than 30% AP208 trips 240 seconds after start. Crew recognizes trip of AP208 SLC pump by:
OHA C1-B1 "SLC PUMP/VALVE O/PF" OHA C1-F1 "SLC/RRCS INITIATION FAILURE" CRIDS D3023 "SLC INJ PMP AP208 TROUBLE TRBL" Flashing STOP light for AP208 IF dispatched to investigate trip of A(B)P2 08, THEN REPORT that the motor is hot to the touch and the breaker will not reset.
(52-212063/52-222101) Crew dispatches NEO and Maintenance to investigate trip of A(B)P208 SLC pump.
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 17 of 30 Rev: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments CRS declares SAE IAW ECG Section SS3.1.
(Note: Declaration may be completed after scenario termination at lead evaluators discretion)
RECORD time SAE declared.
Time Declared: _______
CRS directs inhibiting ADS.
RO/PO inhibit ADS IAW AB.ZZ-0001 Att. 13.
HPI USED: STAR HARD CARD CREW prevents an uncontrolled depressurization during ATWS conditions by preventing ADS ACTUATION.
This Critical Task is not applicable if RPV level never reaches
-129". See justification for failure criteria.
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 REFER to the appropriate EOP and SUPPORT Crew requests for EOPs IAW with the following. Validated execution time delays are built
-in: EOP-301: ET-11 EOP-311: ET-12 EOP-319: ET-13 EOP-320: ET-14 EOP-322: ET-15 STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Promptly initiate actions IAW the 300 series EOPs to shutdown the reactor. Timely actions will reduce the 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 performance of the following EOPs:
EO.ZZ-0320 "Defeating ARI and RPS Interlocks" EO.ZZ-0301 "Bypassing MSIV Isolation Interlocks" EO.ZZ-0311 "Bypassing Primary Containment Instrument Gas Isolation Interlocks" EO.ZZ-0319 "Restoring Instrument Air in an Emergency" EO.ZZ-0322 "Core Spray Injection Valve Override" The timing, order, and priority of the EOP performance may vary.
CRS directs terminating and preventing injection to the RPV with the exception of:
SLC CRD RCIC RO/PO terminate and prevent injection IAW AB.ZZ
-0001: Attachment 16 (10C651)
Attachment 17 (10C650) HPI USED: STAR 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 CRS directs maintaining RPV water level between
-50" and -185". (CRS may direct level band of -185" to -129" if level drops low enough)
Typically, the lower end of the level band is set above -129". RO/PO control level as directed by CRS with:
Feedwater IAW AB.ZZ
-0001 Att. 14 RCIC IAW AB.ZZ
-0001 Att. 6 HPCI IAW EOP
-322 HPI USED: STAR HARD CARD If the turbine trips before the reactor is scrammed, an RRCS feedwater runback may occur. CREW maintains or restore s
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 operation IAW AB.ZZ
-0001 Attachment 18.
HPI USED: STAR HARD CARD RO/PO bypass RWM and insert control rods IAW RE
-AB.ZZ-0001 Attachment. 1.
HPI USED: STAR HARD CARD 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 Total Loss of EHC
~~~6 min after the plant is tripped, OR at the discretion of the Lead Examiner, ENS URE/TRIGGER ET-7 (Trip of the 'B' EHC pump).~~
Note: the BPVs will fail close
~3 min after total loss of EHC.
Crew recognizes trip of the 'B' EHC pump by:
OHA D3-F5 "TURB HYDR PUMP TROUBLE" 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 TRANSIENT MITIGATION Pressure Leg Direct initial pressure control as Stabilize pressure 800 psig to 1000 psig. The lower limit of 800 psig will not complicate RPV level maintenance and will prevent an unwanted cooldown. The upper limit of 1000 psig is a round number below 1047 psig.
CRS directs stabilizing pressure below 1037 psig with:
Main Steam Line Drains SRV s RPFT When pressure control swaps to SRVs, maintaining RPV water level between
-50" and -129" will be very challenging due to shrink and swell and changing reactor pressure with the RFPTs in MAN.
RO/PO control pressure as directed by CRS with:
Main Steam Line Drains IAW AB.ZZ-0001 Att. 15 SRVs IAW AB.ZZ
-0001 Att. 13 RFPTs HPI USED: STAR HARD CARD 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 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 Torus Temperature Leg Start all available Torus cooling as soon as possible to remove heat from containment.
CRS implements EOP
-102. CRS directs placing AP202 RHR pump in Suppression Pool Cooling and Suppression Chamber Spray (as required)
. RO/PO place AP202 RHR pump in Suppression Pool Cooling and Suppression Chamber Spray (as required) IAW AB.ZZ-0001 Att. 3.
HPI USED: STAR HARD CARD
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 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 Valve to Open NOTE: The first loop of RHR placed in Suppression Pool Cooling will have its F024 valve trip its breaker. Response shown for A Loop.
Crew recognizes failure of
HV-F024A by: OHA A6-B1 "RHR LOOP A TROUBLE" Flashing OVLD/PWR FAIL Loss of position indication No indication of SP cooling flow CRIDS D4439 "RHR PMP A TEST HV-F024A OPF" IF dispatched to investigate trip of HV-F024A breaker, THEN REPORT the breaker is tripped and will not reset.
Crew dispatches NEO an d
Maintenance to breaker for HV-F024A (52-212192).
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 CRS directs B Loop of RHR placed in Suppression Pool Cooling. RO/PO places B RHR Loop in Suppression Pool Cooling IAW AB.ZZ-0001 Att. 3.
HPI USED: STAR 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", THEN RO/PO terminate and prevents injection from Core Spray IAW AB.ZZ
-0001 Attachment 16.
HPI USED: STAR HARD CARD WHEN the Crew has reset RPS, THEN DELETE Malfunction s RP06 and RP07 to allow full rod insertion on the next scram. WHEN EOP-320 Section 5.1 and 5.2 are complete, THEN the Crew implements EOP-320 Section 5.3 and reset RPS. HPI USED: STAR PEER CHECK At the Lead Examiners discretion, MODIFY InSight Item lclsdv to accelerate draining of the SDV.
WHEN OHA C6-E4 clears, THEN the Crew initiates a manual scram IAW EOP
-320 Section 5.3.
HPI USED: STAR PEER CHECK CREW fully inserts all control rods via RMCS and/or manual scram(s) IAW HC.OP-EO.ZZ-0320.
2013 NRC Scenario #2 Page 24 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:
The scenario may be terminated at the discretion of the Lead Examiner when:
RPV Level is being maintained above
-185" AND All rods are fully inserted CRS exits EOP
-101A, enters EO P-101.
2013 NRC Scenario #2 Page 25 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.Z Z-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 26 of 30 Rev: 4 VII. ESG CRITICAL TASK RATIONAL 2013 NRC Scenario #2, Rev 0 4 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 satisfactoril y 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 th is 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 27 of 30 Rev: 4 2013 NRC Scenario #2, Rev 0 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 LOCA TRANSIENTS: LOSS OF SUPPORT 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 28 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 Scenario 2 Page 29 of 30 Rev.: 02 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 30 of 30 Rev.: 09 2 EXAMINATION SCENARIO GUIDE (ESG) VALIDATION (con't)
Crew Validation Rev: 0 4 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
SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE:
APRM Upscale, Single Rod Scram, Loss of Drywell Clg, Loss of 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 2013 NRC Scenario #3 Page 2 of 33 Rev.: 4 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 powe r 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 3 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 file s 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 4 of 33 Rev.: 4 EVENT FILE: Initial ET # 6 Event code:
~~Description:~~
hpvv(1) <= 0.90
// HPCI HV
-F003 valve position Trips breaker for HPCI HV
-F003 when closure is attempted from the Control Room.
7 Event code:
~~Description:~~
hvtr4111 > 160
// HPCI Room Temp Triggers RCIC Steam leak to allow raising RCIC Room temp.
8 Event code:
~~Description:~~
crqnmi <= 15
// Reactor Power Inserts HPCI Steam Leak at 40% on reactor scram.
9 Event code:
~~Description:~~
rrprv < 650
// Reactor Pressure in psia Raises severity of HPCI leak if Crew depressurizes 10 Event code:
~~Description:~~
hvtr4111 > 200
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
11 Event code:
~~Description:~~
hvtr4111 > 210
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
12 Event code:
~~Description:~~
hvtr4111 > 220
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
13 Event code:
~~Description:~~
hvtr4111 > 230
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
14 Event code:
~~Description:~~
hvtr4111 > 240
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
15 Event code:
~~Description:~~
hvtr4111 > 250
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
16 Event code:
~~Description:~~
hvtr4111 > 255
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
17 Event code:
~~Description:~~
hvtr4111 > 260
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises. 18 Event code:
~~Description:~~
hvtr4111 > 265
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
19 Event code:
~~Description:~~
hvtr4111 > 270
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises. 20 Event code:
~~Description:~~
hvtr4111 > 271
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
21 Event code:
~~Description:~~
hvtr4111 > 272
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
22 Event code:
~~Description:~~
hvtr4111 > 273
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
23 Event code:
~~Description:~~
hvtr4111 > 274
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
24 Event code:
~~Description:~~
hvtr4111 > 275
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
25 Event code:
~~Description:~~
hvtr4111 > 276
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
26 Event code:
~~Description:~~
hvtr4111 > 277
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
27 Event code:
~~Description:~~
hvtr4111 > 278
// HPCI Room Temp Raises RCIC Room Temperature as HPCI Room Temperature rises.
Event cod e:
~~Description:~~
2013 NRC Scenario #3 Page 5 of 33 Rev.: 4 MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None None Insert malfunction AN
-E5F1 CRYWOLF ANN E5F1 CHILLED WTR SYSTEM TROUBLE None None Insert malfunction HP10 HPCI steam isolation valves F002 & F003 failure to auto close None None Insert malfunction RP04 on event 6 Failure of RPS to SCRAM (ATWS)
None None Insert malfunction RZ03B RRCS Channel A
- Logic B Failure to Auto Initiate None None Insert malfunction RZ03 C RRCS Channel B
- Logic A Failure to 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 None None Insert malfunction CW18B after 5 on event 2 Chilled water circ pump BP161 trip None None Insert malfunction ED13C1 on event 3 Loss of 480 VAC essential bus C 10B430 None None Insert malfunction HP09 from 5.00000 to 40.00000 in 60 on event 5 HPCI steam line break inside HPCI Room 4111 None None Insert malfunction AN
-A2A5 on event 5 CRYWOLF ANN A2A5
-FIRE PROT PANEL 10C671 None None Insert malfunction RC09 to 1.00000 on event 7 RCIC steam line break inside the RCIC 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 2 B hi level switch failure None None Insert malfunction FW30C on event 8 Heater 2C hi level switch failure None None Insert malfunction CD030227 on event 28 Control Rod 02
-27 stuck MALFUNCTION SCHEDULE:
Initial @Time Event Action Description None 4 Set hp_k 90 = true 1020 HPCI MAN INIT None 5 Set hvtr4111 = 135 None 7 Set hvtr4110 = 135 None 8 Insert malfunction HP09 after 1 from 40.00000 to 40.00000 HPCI steam line break inside HPCI Room 4111 None 9 Insert malfunction HP09 after 1 from 60.00000 to 60.00000 HPCI steam line break inside HPCI Room
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 2 1 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
2013 NRC Scenario #3 Page 7 of 33 Rev.: 4 REMOTE SCHEDULE:
Initial @Time Event Action Description None None Insert remote CW33B to 50 CW33 Turbine Bldg chiller CK111 Winterization None None Insert remote HP04 to FAIL_OPEN HP04 GROUP 5A HV
-F002 HPCI Steam Supply Isol None None Insert remote HP06 to RACK_OUT on event 6 HP06 GROUP 5A HV
-F003 HPCI Steam Supply Isol None None Insert remote HV06 to STOP on event 29 HV06 RBVS Supply fan C None None Insert remote HV05 after 1 to STOP on event 29 HV05 RBVS Supply fan B None None Insert remote HV04 after 1 to STOP on event 29 HV04 RBVS Supply f an A None None Insert remote HV03 after 2 to STOP on event 29 HV03 RBVS Exhaust fan C None None Insert remote HV02 after 3 to STOP on event 29 HV02 RBVS Exhaust fan B None None Insert remote HV01 after 3 to STOP on event 29 HV01 RBVS Exhaust fan A None None Insert remote CX11 after 120 to OPEN on event 3 0 CX11 CX valve AP
-V041 to Core Spray header A None None Insert remote CX15 to OPEN on event 3 0 CX15 CX valve AP
-V044 to RHR header A None None Insert remote CX17 after 60 to OPEN on event 3 0 CX17 CX valve AP
-V047 to RHR header C
2013 NRC Scenario #3 Page 8 of 33 Rev.: 4 OVERRIDE SCHEDULE:
Initial @Time Event Action Description None None Insert override 1A181_A2_LO to On INOP-CHILLED WATER CPRSR DC111
-CPRSR MOT (LO)
None None Insert override 1A181_D_DI to Off DK111 START
-CHILLED WATER CPRSR DC111-CPRSR MOT (DI)
None None Insert override 1A181_E1_DI to Off SAFETY CKT COMPLETE/ON
-CHILLED WATER CPRSR DK111 (DI)
None None Insert override 1A181_F_LO to Off STOP-CHILLED WATER CPRSR DC111
-CPRSR MOT (LO)
None None Insert override 1A182_E_DI to Off HV-9503D OPEN
-CH W DISCH SHUTOFF V (DI) None None Insert override 1A182_F_LO to Off HV-9503D CLOSE
-CH W DISCH 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 9 of 33 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Raise Power Using Recirc Flow: After the crew assumes the watch they will raise power per maneuvering sheet.
CRS directs ATC to raise power 5% using Recirc Flow.
ATC adjusts Recirc flow and monitors Reactor power, pressure, and level and ensure plant conditions are stable.
APRM C Upscale w/Single Rod Scram: After the Crew raises power, OR, at the discretion of the Lead Examiner, TRIGGER ET
-1. Crew monitors Reactor power, pressure, and level and ensure plant conditions are stable. Ensures no scram setpoints have been exceeded 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 10 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 11 of 33 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments WHEN requested, THEN as RE, REPORT: 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 rod 02-27 scram, THEN REPORT you found the 'B' S.R.I. test toggle on the 02-27 HCU out of "Normal". There are workers decontaminating the HCU bank, and one of them remembers bumping something. (02-27 is in the North HCU bank by HPCI pipechase. See EOP
-303 map.) CRS implements AB.IC
-0001 Condition C
Crew dispatches RBEO to 02
-27 HCU. Crew contacts Rad Pro to survey scram discharge volume due to change in radiological conditions.
RO resets the Rod Drift alarm IAW HC.OP-AR.ZZ-0020.
REMOVE Malfunction CD060227 when RPS is reset.
RO bypasses APRM C.
RO resets RPS half scram.
Crew contacts Maintenance to troubleshoot APRM C failure.
SM contacts Operations Management
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 IF directed to electrically disarm rod 02
-27, THEN TRIGGER ET
-28 to INSERT Malfunction cd030227 (stuck rod).
CRS determine Tech Spec actions required. Enter Action statement for:
Reactor Protection System Instrumentation
~~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). For both T/S, still meet the Minimum Operable Channels per Trip Function. Tracking Action statement only.
Loss of Drywell Cooling
~~After TS call has bee n addressed or at the discretion of the Lead Examiner, TRIGGER ET~~
-2 (Loss of TB Chilled Water/Drywell Cooling)
. Loss of Drywell Cooling by:
OHA E5-E1 "CHILLED WTR PANEL 10C152" OHA E5-F1 "CHILLED WTR SYSTEM TROUBLE" Flashing "OVLD/PWR FAIL",
"HI/LOW FLOW", and "STOP" lights on AP161 and BP161 TB Chilled Water Circ pumps 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 Drywell pressure will peak at less than 1.2 psig; however, IF the Crew manually scrams during the Loss of Drywell Cooling, THEN the HPCI Steam Leak will be automatically inserted.
CRS implements AB.CONT
-001: Condition A Condition B
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 Crew announces loss of Turbine Building Chilled Water on the plant page.
RO/PO ensure drywell cooling is maximized.
IF dispatched to investigate loss of TB Chilled Water, 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 Crew dispatches TBEO and Maintenance to investigate.
RO/PO align RACS to supply drywell cooling IAW AB.CONT-0001 Condition B
. Drywell pressure will 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 permit, THEN REPORT it will take about 30 minutes and REQUEST the Crew to record start and stop times for the release. IF Drywell Pressure is not restored below 0.75 psig, THEN CRS implements AB.CONT-0001: Condition C IF directed, THEN PO Vents the drywell IAW AB.CONT-001 Condition C
.
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 CRS contacts Operations Management to initiate a Prompt Investigation and ERT callout.
Loss of 10B430 Unit Sub
~~After the Crew aligns RACS to cool the drywell, OR , at the discretion of the Lead Examiner, TRIGGER ET~~
-3. Crew monitors Reactor power, pressure, and level and ensures plant conditions are stable.
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 15 of 33 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments Crew recognizes loss of CP228 ECCS Jockey pump by:
OHA A6-C3 "ECCS JOCKEY PUMP 1CP228 TROUBLE" Jockey pump indications on 10C650A OHA A6-B1 "RHR LOOP A TROUBLE" OHA A6-B2 "RHR LOOP C 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" RHR and Core Spray Low Pressure alarms will not be received if Condensate Transfer is lined up before discharge header pressures decay to alarm setpoints.
Crew recognizes loss of AK202 PCIG compressor by:
OHA A1-A1 "INST GAS SYSTEM A TROUBLE" OHA A1-A3 "INST GAS RECEIVER A PRESSURE LO" OHA A1-A5 "INST GAS PANEL A/B C213" Loss of "START" and "STOP" indication for AK202 Instrument gas pressure is not actually low. The alarm is the result of a loss of power to the AC213 panel.
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 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, THEN REPORT: 52-40310 has 51B and 51C Time overcurrent trip flags dropped CX400 xfmr is very warm with acrid odor and telltale in the red zone Crew dispatches ABEO and Maintenance to investigate the loss of the 10B430 bus.
CRS implements AB.ZZ
-0172. SUPPORT any requests for BP207 discharge valve manipulations with Remote Function CD02. Crew places BP207 CRD pump in service IAW either:
SO.BF-0001 Sect 5.2 OR HC.OP-AB.22-0001 Hardcard OR ARP for CRIDS D2244 Accumulator trouble alarms will begin to come in after about 14 minutes with no CRD pump in service.
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 AVERAGE HCU accumulator pressure can be read with InSight Item lcpac. INDIVIDUAL HCU accumulator pressures can be read with InSight Item lcpaccx(n). See Sim Op Manual under Reactor Building Operator for "n" value.
CRS directs aligning Condensate Transfer keepfill to 'A' Core Spray loop and A/C RHR loops.
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' Core Spray and A & C RHR THEN: REFER to SO.BC-0001 Section 5.9 TRIGGER ET
-3 0 to open AP-V044/V047/V041 RO/PO coordinate with RBEO to align Condensate Transfer IAW SO.BC-0001 for removal of CP228 from service.
Crew places BK202 PCIG compressor in AULD.
CRS/STA recognize the following Tech Spec applies:
Distribution
- Operating 3.8.3.1 action a Must re-energize 10B430 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within th e next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . May cascade to T/S 3.8.2.1.a due to loss of CD444 battery charger (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO)
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 IF any HCU accumulators become inoperable with no CRD pump I/S, THEN CRS recognize the following Tech Spec applies:
Control Rod Scram Accumulators 3.1.3.5 action a.2.a Within 20 minutes of discovery, restore charging water pressure >= 940 psig or place Mode switch in SHUTDOWN. IF directed to perform fill and vent. THEN REPORT no air found.
CRS refer to OP-HC-108-115-1001 for loss of CP228 ECCS jockey pump AND for SSW to RACS isolation valves.
Actions required for jockey pump are dependent on whether discharge header low pressure alarms were received for Core Spray and RHR loops.
CRS contacts Operations Management to initiate an ERT callout. Inadvertent H PCI Initiation
~~After loss of 10B430 actions are complete OR At the discretion of the lead evaluator, TRIGGER ET~~
-4 Inadvertent HPCI Initiation Crew recognizes inadvertent HPCI initiation by:
OHA B3-B5 "CORE SPRAY LINE BREAK" OHA B1-E5 "HPCI PUMP DISCHARGE FLOW LO" 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 19 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
~~After actions for inadvertent HPCI initiation are completion~~
, OR at the discretion of the Lead Examiner, TRIGGER ET-5 AND PROVIDE Fire Computer indication of point FA015 (Fire Computer point may be provided by Examiner or by Fire Computer Simulation).
Crew recognizes a steam line break in the HPCI room by:
OHA B1-A5 "HPCI STEAM LINE DIFF PRESSURE HI" OHA A2-A5 "FIRE PROT PANEL 10C671" Fire Comp Pt FA015 "RM 4111 HPCI PUMP AND TURBINE ROOM" HPCI room temperature trending up (Rm 4111)
Lowering Main Gen MWe Offsite release rate trending
up HPCI Turbine Inlet Pressure on PI-R602. ISLN INIT status lights B1-A5 and ISLN INIT status lights will be received when the leak severity reaches 23% (about 30 seconds
) InSight Items: HPCI Room Temp hvtr4111 RCIC Room Temp hvtr4110 Crew announces steam leak in HPCI room on plant page.
IF dispatched to HPCI Room, THEN REPORT the room is filled with steam.
Crew recognizes failure of HPCI to isolate by:
HV-F002 power failure F003 valve position HPCI room temperature trending up (Rm 4111)
The HV-F002 is powered from the
10 B 4 30 bus. PO attempts to close HV
-F003 using Control Room keylock switch. Immediate Operator Action IAW AB.CONT-0002 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 Crew recognizes failure of HV-F003 to close by:
OHA B1-F3 "HPCI COMPONENT O/PF" OVLD/PWR FAIL light CRIDS D3513 "HPCI ST 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 RECORD time when switch for HV
-F003 is in CLOSE AND OHA B1-A5 is in alarm for 15 min ECG Classification.
Time: _______ IF dispatched to reclose breaker 52
-212053, THEN REPORT the breaker will not close.
IF dispatched to the HV
-F003 valve, THEN REPORT the valve is bound and will not close.
Crew dispatches RBEO and Maintenance to breaker for
HV-F003 (52-212053) ARP for D3513 gives breaker number.
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 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 22 of 33 Rev.: 4 V. SCENARIO GUIDE SEQUENCE AND EXPECTED RESPONSE Event / Instructor Activity Expected Plant/Student Response Comments STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION EOP-103 Secondary Containment Control. 1. It is impossible to predict all 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 5 00-600 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. WHEN HPCI Room temperature reaches 115 degrees, THEN CRS implements EOP-103. CRS implements AB.CONT-004: Condition A Condition C
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 IF dispatched to secure Rx Bldg Ventilation, THEN: REFER to SO.GU-0001 Section 5.3 TRIGGER ET-29 to secure fans PO places FRVS in service IAW SO.GU-0001 Section 5.3.
STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Reports 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. BEFORE HPCI Room temperature reaches 250 degrees, THEN CRS directs reducing recirc pumps to minimum speed
and locking the Mode Switch in SHUTDOWN RO reduces recirc pumps to minimum speed and locks the Mode Switch in SHUTDOWN.
Before HPCI Room temperature exceeds 250 °F by Control Room indication, the Crew places the Mode Switch in SHUTDOWN.
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 Crew recognizes Scram Condition and Reactor Power Above 4% EOP entry condition.
RECORD time of Mode Switch to SHUTDOWN OR RPV LVL 3 (whichever was first) for 15 min ECG Classification.
Time: _______
STRATEGIES FOR SUCESSFUL TRANSIENT MITIGATION Reactor Scram Report s 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. RO performs scram actions IAW AB.ZZ-0001 Att. 1.
HPI USED: STAR HARD CARD The Mode Switch will not actuate RPS
. ARI will not automatically initiate, but can be manually initiated.
Before Reactor Water Level reaches LVL 1
(-129"), the Crew manually actuates ARI to shutdown the reactor.
RECORD the RPV level at which ARI is actuated. 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 25 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 Inlet valve closures: After reactor power lowers to <15% following scram actions
. Crew recognizes FWHTR 1&2 Condensate valve closures RO/PO opens FWHTR 1&2 Condensate Bypass valve HV
-1625. Crew recognizes lowering reactor pressure by:
OHA C8-B3 "NSSSS ISLN SI G - 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 26 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 to be 275 degF before reactor pressure drops below 200 psig.
IF necessary, THEN manually raise HPCI Room temperature using 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)
WHEN HPCI AND RCIC room temperatures exceed 250 degrees (Max Safe Op), THEN CRS implements EOP-202 to Emergenc y Depressurize.
RO/PO opens five SRVs IAW AB.ZZ-0001 Att. 13.
Crew actuates five SRV s when RCIC room temperature exceed s 250 degrees by Control Room indication (SPDS/CRIDS).
(2 nd room above MAX SAFE)
RECORD time from RCIC reaching 250 degrees to SRV actuation.
TIME: _______
2013 NRC Scenario #3 Page 27 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 28 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 29 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 exceed s 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 it's 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 30 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 TRANSIENTS:
LOSS OF SUPPORT 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 31 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 8 0% power (scheduled for next shift).
ELECTRICAL None ADVERSE CONDITION MONITORING None 2013 NRC Scenario #3 Page 32 of 33 Rev.: 3 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 33 of 33 Rev.: 3 EXAMINATION SCENARIO GUIDE (ESG) REVIEW/VALIDATION (con't) Crew Validation Rev: 0 4 Date Validated:
7/22/13 Validation Comments Disposition Crew Validation Rev: Date Validated:
Validation Comments Disposition Crew Validation Rev: Date Validated:
Validation Comments Disposition

@@ Line 2: / Line 2: @@
 | number = ML13267A422
 | issue date = 08/19/2013
-| title = Hope Creek - Final Operating Exam (Sections a, B, and C) (Folder 3)
+| title = Final Operating Exam (Sections a, B, and C) (Folder 3)
 | author name = Fish T H
 | author affiliation = NRC/RGN-I/DRS/OB

v t e Letter Sequence Other
TAC:U01872, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML13267A380, ML13267A389, ML13267A415, ML13267A422, ML14010A064
MONTHYEAR2013-08-19 [Table View]

ML13267A422: Difference between revisions

Revision as of 02:34, 4 April 2019

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