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| number = ML100880356
| number = ML100880356
| issue date = 11/02/2009
| issue date = 11/02/2009
| title = Palo Verde-2009-22-Final Operating Test
| title = 2009-22-Final Operating Test
| author name = Garchow S M
| author name = Garchow S
| author affiliation = NRC/RGN-IV
| author affiliation = NRC/RGN-IV
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 1 JPM BASIS INFORMATION TASK: 1250440201 Perform Event Control Actions for a Control Room Fire TASK STANDARD: Diesel Generator 'B' is running.
{{#Wiki_filter:JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250440201 Perform Event Control Actions for a Control Room Fire TASK STANDARD: Diesel Generator B is running.
K/A: 4.2.068.AA1.10 K/A RATING: RO:
K/A: 4.2.068.AA1.10                               K/A RATING:       RO:   3.7   SRO:   3.9 K/A: 4.2.068.AA1.31                               K/A RATING:       RO:   3.9   SRO:   4.0 APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:         15 minutes
3.7 SRO: 3.9 K/A: 4.2.068.AA1.31 K/A RATING: RO:
3.9 SRO: 4.0 APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes  


==REFERENCES:==
==REFERENCES:==
40AO-9ZZ19, Control Room Fire, Appendix E Rev 22 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X     JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) Yes     APPROVAL Developed By: Alan Malley Date: 08/31/2004 Revised By: Alan Malley Date: 04/14/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X     TESTING METHOD: SIMULATE X PERFORM       EVALUATION Examinee Name:
40AO-9ZZ19, Control Room Fire, Appendix E Rev 22 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR                 PLANT           X JPM TYPE Time Critical? (Yes/No)     Yes     Alternative Path? (Yes/No)       Yes APPROVAL Developed By:     Alan Malley                   Date:   08/31/2004 Revised By:       Alan Malley                   Date:   04/14/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT         X TESTING METHOD:                           SIMULATE           X     PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
1                                    Revised 9/23/08


JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 2 1. SIMULATOR SETUP:
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
A. IC#: N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 1.     SIMULATOR SETUP:
: 1. N/A 2. 3. 4. C. SPECIAL INSTRUCTIONS: NONE D. REQUIRED CONDITIONS: NONE E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
A. IC#: N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT             COMMAND                                     DESCRIPTION
: 2. SPECIAL TOOLS/EQUIPMENT: A copy of Appendix E of 40AO-9ZZ19, Rev 22 Pictures of the inside of a 4.16 kV breaker cubicle.  
: 1.       N/A 2.
3.
4.
C. SPECIAL INSTRUCTIONS:
* NONE D. REQUIRED CONDITIONS:
* NONE E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 2. SPECIAL TOOLS/EQUIPMENT:
* A copy of Appendix E of 40AO-9ZZ19, Rev 22
* Pictures of the inside of a 4.16 kV breaker cubicle.
2


JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 3 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The control room has been evacuated due to a fire.
* There has been a loss of offsite power. No automatic start and loading of the Emergency Diesel Generators, or load shed has occurred.
* The B DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire).
* The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Generator (another operator performed steps 1-9 to position disconnect switches and start the DG).
* The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES).
* Assume you have a portable lantern per Step 1 of Appendix E.
This JPM is time critical.
3


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
INITIATING CUE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
4


The control room has been evacuated due to a fire. There has been a loss of offsite power. No au tomatic start and loading of the Emergency Diesel Generators, or load shed has occurred. The 'B' DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire). The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Generator (another op erator performed steps 1-9 to position disconnect switches and start the DG). The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES). Assume you have a portable lantern per Step 1 of Appendix E.
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
This JPM is time critical.
STEP                                CUE                            STANDARD
: 1.     Step 10 of Appendix E:              Provide the following cues as the Examinee identifies indication on examinee looks at the appropriate Diesel Generator control cabinet.
Check that Both of the following    instrument:                      NOTE: Time critical portion starts conditions for closing the DG Output here.
Breaker are met:
* DG B Voltage is 4220
* Diesel Generator B voltage is            VAC START Time:      ___________
3740 - 4580
* DG B speed is 600 rpm
* Diesel Generator B speed is approximately 600 rpm.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 2.     Step 11 of Appendix E:              Provide the following cue:        Examinee simulates closing PBB-S04B by using the handswitch on the Close breaker PBB-S04B, Diesel       The green light is ON and the   front of the breaker.
Generator PEB-G02, using the local  red light is OFF on PBB-S04B.
control switch.
The white light is OUT on PBB-S04B.
SAT / UNSAT Comments (required for UNSAT):
5


JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 4 INFORMATION FOR EVALUATOR'S USE:
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                  CUE                        STANDARD
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 3.      Step 11.1 of Appendix E:              Provide the following cue:        Examinee goes to Step 12 of the appendix IF PBB-S04B did NOT close,             The control room has directed you THEN perform the following:            to close the breaker manually.
JP-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  5 JPM START TIME:
: a. IF the breaker will be closed Give the examinee the enclosed manually, THEN GO TO          pictures and inform the examinee Step 12. of this appendix. that he/she does not need to open the switchgear door. Use the pictures to explain your actions.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                        STANDARD
: 4.     Step 12 of Appendix E:                Provide the following cue:        Examinee goes to Step 12.1 of the appendix.
IF breaker PBB-S04B, Diesel            The closing spring indicates Generator PEB-G02, will be closed      DISCHGD.
manually, THEN perform the following:                            Alternate Path starts here.
: a. Check the closing spring      After examinee goes to step 12.1 indicates CHGD.
: b. Press the MANUAL              If asked:
CLOSE plunger for the breaker.                       The CRS directs you to close the breaker manually.
SAT / UNSAT Comments (required for UNSAT):
6


STEP CUE STANDARD 1. Step 10 of Appendix E:
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                 CUE                           STANDARD
Check that Both of the following conditions for closing the DG Output Breaker are met:  Diesel Generator B voltage is 3740 - 4580  Diesel Generator B speed is approximately 600 rpm.
: 5.
Provide the following cues as the examinee looks at the appropriate
* Step 12.1.a-d of Appendix E:         Provide the following cue:         Examinee explains using the provided pictures how he/she would IF PBB-S04B will be closed           The closing spring indicates       manually charge the springs.
 
manually, AND the closing spring     DISCHGD.
instrument:  DG "B" Voltage is 4220 VAC  DG "B" speed is 600 rpm Examinee identifies indication on Diesel Generator control cabinet.
indicator does NOT indicate CHGD, THEN perform the              Provide the following cues as the following to manually close the       trainee simulates the steps.
NOTE: Time critical portion starts here.
breaker:
START Time: ___________
: a. Obtain ALL of the                 a. The equipment has been      Examinee simulates obtaining following equipment from             obtained from the cabinet  equipment from the cabinet located FPN-C02, Emergency                                               by the door to the DC equipment Equipment Cabinet.                                               room.
SAT / UNSAT Comments (required for UNSAT):
* Ratchet
 
* Extension
STEP CUE STANDARD 2. Step 11 of Appendix E: Close breaker PBB-S04B, Diesel Generator PEB-G02, using the local control switch.
* 5/8 inch socket
Provide the following cue:
: b. The 125 Vdc breaker is in    The examinee opens the 125 V dc
The green light is "ON" and the red light is "OFF" on PBB-S04B. The white light is "OUT" on PBB-S04B. Examinee simulates closing PBB-S04B by using the handswitch on the front of the breaker.
: b. Open the 125 Vdc control the OFF position.        breaker.
SAT / UNSAT Comments (required for UNSAT):
power breaker.
 
: c. Place the ratchet on the
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 6  STEP CUE STANDARD 3. Step 11.1 of Appendix E:
: c. The ratchet is on the stud. The examinee places the ratchet on charging spring motor the stud.
IF PBB-S04B did NOT close, THEN perform the following:
eccentric, hex charging stud (Right had side between the                                     The examinee ratchets the stud to charging springs).               d. The closing spring indicator obtain a CHGD indication.
: a. IF the breaker will be closed manually, THEN GO TO Step 12. of this appendix.
: d. Ratchet the hexed charging            indicates CHGD.
Provide the following cue:
stud clockwise to obtain a CHGD indication.
The control room has directed you to close the breaker manually.
SAT / UNSAT Comments (required for UNSAT):
Give the examinee the enclosed pictures and inform the examinee that he/she does not need to open the switchgear door. Use the pictures to explain your actions.
STEP                                 CUE                           STANDARD
Examinee goes to Step 12 of the appendix  SAT / UNSAT Comments (required for UNSAT):
: 6.
 
* Step 12.1.e of Appendix E:           Provide the following cue:         Examinee simulates closing PBB-S04B by pressing the Manual Press the Manual CLOSE plunger      The breaker position indicator      Close Plunger.
STEP CUE STANDARD 4. Step 12 of Appendix E:
for the breaker.                      reads CLOSED.
IF breaker PBB-S04B, Diesel Generator PEB-G02, will be closed manually, THEN perform the following:
SAT / UNSAT Comments (required for UNSAT):
: a. Check the closing spring indicates "CHGD".
7
: b. Press the "MANUAL CLOSE" plunger for the
 
breaker. Provide the following cue:
The closing spring indicates "DISCHGD". Alternate Path starts here. After examinee goes to step 12.1 If  asked:
The CRS directs you to close the breaker manually.
Examinee goes to Step 12.1 of the appendix.  
 
SAT / UNSAT Comments (required for UNSAT):
 
JP-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  7  STEP CUE STANDARD 5.
* Step 12.1.a-d of Appendix E:
IF PBB-S04B will be closed manually, AND the closing spring indicator does NOT indicate "CHGD", THEN perform the following to manually close the  
 
breaker: a. Obtain ALL of the following equipment from FPN-C02, Emergency Equipment Cabinet. Ratchet Extension 5/8 inch socket  
: b. Open the 125 Vdc control power breaker.  
: c. Place the ratchet on the charging spring motor  
 
eccentric, hex charging stud (Right had side between the charging springs).  
: d. Ratchet the hexed charging stud clockwise to obtain a  
 
"CHGD" indication. Provide the following cue:
The closing spring indicates "DISCHGD".
Provide the following cues as the trainee simulates the steps.  
: a. The equipment has been obtained from the cabinet
: b. The 125 Vdc breaker is in the "OFF" position.
: c. The ratchet is on the stud.
: d. The closing spring indicator indicates "CHGD".
Examinee explains using the provided pictures how he/she would manually charge the springs.
 
Examinee simulates obtaining equipment from the cabinet located by the door to the DC equipment room.
The examinee opens the 125 V dc breaker. The examinee places the ratchet on the stud. The examinee ratchets the stud to obtain a "CHGD" indication.  
 
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 6.
* Step 12.1.e of Appendix E:
Press the "Manual CLOSE" plunger for the breaker. Provide the following cue:
The breaker position indicator reads "CLOSED".
 
Examinee simulates closing PBB-S04B by pressing the "Manual Close" Plunger.
SAT / UNSAT Comments (required for UNSAT):  
 
JP-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  8  STEP CUE STANDARD 7.
* Step 13.e of Appendix E: Close breaker PBB-S04C, Essential Spray Pond Pump SPB-P01. Provide the following cue:
The green light is "OFF" and the red light is "ON". 
 
Another operator will complete this Appendix.


JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                          STANDARD
: 7.
* Step 13.e of Appendix E:          Provide the following cue:        Examinee simulates closing PBB-S04C by using the handswitch on the Close breaker PBB-S04C, Essential The green light is OFF and the  front of the breaker.
Spray Pond Pump SPB-P01.          red light is ON.
NOTE: Time critical portion stops here.
STOP Time        ___________
(Time should be less than 15 minutes Another operator will complete    from Start time).
this Appendix.
This JPM is complete.
This JPM is complete.
Examinee simulates closing PBB-S04C by using the handswitch on the front of the breaker.
SAT / UNSAT Comments (required for UNSAT):
NOTE: Time critical portion stops here.
 
STOP Time  ___________
(Time should be less than 15 minutes from Start time).
SAT / UNSAT Comments (required for UNSAT):  
 
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 8


JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 9  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1 08/31/04 3 Procedure removed direction to open PHB-M3209 and PHB-M3210. 2 09/08/2006 6 Changed cues for step 11 3 04/14/2009 6 Changed alternate path to DG breaker not closing.
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                                 COMMENTS 1           08/31/04             3         Procedure removed direction to open PHB-M3209 and PHB-M3210.
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
2           09/08/2006           6         Changed cues for step 11 3           04/14/2009           6         Changed alternate path to DG breaker not closing.
REASON REVISED             Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 1. Vendor reference document upgrade
: 2. Plant modification (include number)
: 3. Procedure upgrade
: 4. Internal or External Agency Commitment (indicate item number)
: 5. Technical Specification Change (indicate amendment number)
: 6. Other (explain in comments) 9


consecutively in each revision.
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 1. Vendor reference document upgrade
* The control room has been evacuated due to a fire.
: 2. Plant modification (include number)
* There has been a loss of offsite power. No automatic start and loading of the Emergency Diesel Generators, or load shed has occurred.
: 3. Procedure upgrade
* The B DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire).
: 4. Internal or External Agency Commitment (indicate item number)
* The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Generator (another operator performed steps 1-9 to position disconnect switches and start the DG).
: 5. Technical Specification Change (indicate amendment number)
* The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES).
: 6. Other (explain in comments)
* Assume you have a portable lantern per Step 1 of Appendix E.
JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 10 INITIAL CONDITIONS INITIATING CUE:
This JPM is time critical.
The control room has been evacuated due to a fire. There has been a loss of offsite power.
CANDIDATE 10
No automatic start and loading of the Emergency Diesel Generators, or load shed has occurred. The 'B' DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire). The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Ge nerator (another operator performed steps 1-9 to position disconnect switches and start the DG). The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES). Assume you have a portable lantern per Step 1 of Appendix E.
This JPM is time critical.  


CANDIDATE JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 11 JPM BASIS INFORMATION TASK: 1240070004 Perform Auxiliary Operator Actions Per 40EP-9EO07, Loss Of Offsite Power TASK STANDARD: Align Train B EW to Spent Fuel Pool Cooling K/A: 4.2-062-AA1.03 K/A RATING: RO:
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240070004 Perform Auxiliary Operator Actions Per 40EP-9EO07, Loss Of Offsite Power TASK STANDARD: Align Train B EW to Spent Fuel Pool Cooling K/A: 4.2-062-AA1.03                               K/A RATING:         RO:   3.6   SRO: 3.6 K/A: 3.8-033-A2.02                                 K/A RATING:         RO:   2.7   SRO: 3.0 APPLICABLE POSITION(S):             AO/RO/SRO VALIDATION TIME:               10 minutes
3.6 SRO: 3.6 K/A: 3.8-033-A2.02 K/A RATING: RO:
2.7 SRO: 3.0 APPLICABLE POSITION(S): AO/RO/SRO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40EP-9EO10 Standard Appendices, Appendix 64, Attachment 64-B, Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X     JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Mike Selland Date: 03/09/2006 Revised By: Alan Malley Date: 03/12/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X     TESTING METHOD: SIMULATE X PERFORM       EVALUATION Examinee Name:
40EP-9EO10 Standard Appendices, Appendix 64, Attachment 64-B, Rev 60 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR                   PLANT           X JPM TYPE Time Critical? (Yes/No)       No     Alternative Path? (Yes/No)       No APPROVAL Developed By:     Mike Selland                   Date:   03/09/2006 Revised By:       Alan Malley                   Date:   03/12/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                   PLANT         X TESTING METHOD:                           SIMULATE           X       PERFORM EVALUATION Examinee Name:                                                     Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
11                                    Revised 9/23/08


JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 12 2. SIMULATOR SETUP:
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
F. IC#: N/A G. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 2.     SIMULATOR SETUP:
: 5. N/A 6. 7. 8. H. SPECIAL INSTRUCTIONS: NONE I. REQUIRED CONDITIONS: NONE J. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
F. IC#: N/A G. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT             COMMAND                                   DESCRIPTION
: 3. SPECIAL TOOLS/EQUIPMENT: Copy of 40EP-9EO10, Standard Appendices, Attachment 64-B, Rev 60  
: 5.       N/A 6.
7.
8.
H. SPECIAL INSTRUCTIONS:
* NONE I. REQUIRED CONDITIONS:
* NONE J. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 3. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40EP-9EO10, Standard Appendices, Attachment 64-B, Rev 60 TASK CONDITIONS 12


TASK CONDITIONS JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 13 INFORMATION PRESENTED TO EXAMINEE:
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The plant has experienced a loss of offsite power and recovery is not expected soon.
* The control room is currently performing steps from the Loss of Offsite Power EOP.
* The CRS has directed you to perform the Area 3 actions from Attachment 64-B to align Train B EW to Spent Fuel Pool Cooling.
* Another operator has been stationed at Essential Chiller B to perform required actions.
* Permission has been granted to break 40AC-9ZZ06 locks as required.
13


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
INITIATING CUE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
14


The plant has experienced a loss of offsite power and recovery is not expected soon.
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
The control room is currently performing st eps from the Loss of Offsite Power EOP.
STEP                              CUE                          STANDARD
The CRS has directed you to perform the Area 3 actions from Attachment 64-B to align Train B EW to Spent Fuel Pool Cooling.
: 1.      Step 1 of Attachment 64-B:        Spray Pond Pump B is running.     Examinee simulates calling control room for verification that Ensure Spray Pond Pump B is SP Pump B is running.
Another operator has been stationed at Essen tial Chiller B to perform required actions.
operating SAT / UNSAT Comments (required for UNSAT):
Permission has been granted to break 40AC-9ZZ06 locks as required.
STEP                              CUE                          STANDARD
: 2.      Step 2 of Attachment 64-B:        EW Pump B is running.              Examinee simulates calling control room for verification that Ensure Essential Cooling Water EW Pump B is running.
Pump B is operating.
SAT / UNSAT Comments (required for UNSAT):
STEP                              CUE                          STANDARD
: 3.
* Step 3 of Attachment 64-B:        NCB-HCV-245 stem lock is          Examinee simulates loosening valve loosened and ZZ06 lock is broken. stem lock.
Perform the following:
(EW Heat Exchanger B Room)        NCB-HCV-245 has been rotated in    Examinee simulates closing NCN-the clockwise direction and has    HCV-245.
Close NCB-HCV-245, NC stopped moving.
ISOLATION TO SFP HEAT EXCHANGER.                        The position indication pointer is Note: Valve is located in EW heat indicating closed.
exchanger B room.
SAT / UNSAT Comments (required for UNSAT):
15


JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 14  INFORMATION FOR EVALUATOR'S USE:
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                 CUE                           STANDARD
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 4.
JP-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  15 JPM START TIME:
* Continuation of step 3 of Attachment NCB-HCV-259 stem lock is           Examinee simulates loosening valve 64-B:                                loosened and ZZ06 lock is broken. stem lock.
STEP CUE STANDARD 1. Step 1 of Attachment 64-B:
Close NCB-HCV-259, NC               NCB-HCV-259 has been rotated in   Examinee simulates closing NCN-ISOLATION FROM SFP HEAT              the clockwise direction and has   HCV-259.
Ensure Spray Pond Pump B is operating Spray Pond Pump B is running.
EXCHANGER.                          stopped moving.
Examinee simulates calling control room for verification that SP Pump B is running.
The position indication pointer is Note: Valve is located in EW heat indicating closed.
SAT / UNSAT Comments (required for UNSAT):
exchanger B room.
 
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 2. Step 2 of Attachment 64-B:
STEP                                 CUE                           STANDARD
Ensure Essential Cooling Water Pump B is operating.
: 5.
EW Pump B is running. Examinee simulates calling control room for verification that EW Pump B is running.
* Continuation of step 3 of Attachment UNIT 3 ONLY:                       UNIT 3 ONLY:
SAT / UNSAT Comments (required for UNSAT):  
64-B:                                EWB-HCV-68 stem lock is           Examinee simulates loosening valve loosened and ZZ06 lock is broken. stem lock.
 
Open EWB-HCV-68, EW ISOLATION FROM SFP HEAT             EWB-HCV-68 has been rotated in     Examinee simulates unlocking and EXCHANGER.                          the counter-clockwise direction   opening EWB-HCV-68 and has stopped moving.
STEP CUE STANDARD 3.
The position indication pointer is indicating open.                   Note: Valve is located in EW heat exchanger B room.
* Step 3 of Attachment 64-B:
SAT / UNSAT Comments (required for UNSAT):
Perform the following: (EW Heat Exchanger B Room) Close NCB-HCV-245, NC ISOLATION TO SFP HEAT
16
 
EXCHANGER. NCB-HCV-245 stem lock is loosened and ZZ06 lock is broken. NCB-HCV-245 has been rotated in the clockwise direction and has
 
stopped moving.
The position indication pointer is indicating closed.
Examinee simulates loosening valve stem lock. Examinee simulates closing NCN-HCV-245. Note: Valve is located in EW heat exchanger B room.
SAT / UNSAT Comments (required for UNSAT):
 
JP-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  16  STEP CUE STANDARD 4.
* Continuation of step 3 of Attachment 64-B: Close NCB-HCV-259, NC ISOLATION FROM SFP HEAT
 
EXCHANGER. NCB-HCV-259 stem lock is loosened and ZZ06 lock is broken. NCB-HCV-259 has been rotated in the clockwise direction and has  
 
stopped moving.
The position indication pointer is indicating closed.
Examinee simulates loosening valve stem lock. Examinee simulates closing NCN-HCV-259.
 
Note: Valve is located in EW heat exchanger B room.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 5.
* Continuation of step 3 of Attachment 64-B: Open EWB-HCV-68, EW ISOLATION FROM SFP HEAT
 
EXCHANGER. UNIT 3 ONLY:
EWB-HCV-68 stem lock is loosened and ZZ06 lock is broken.
EWB-HCV-68 has been rotated in the counter-clockwise direction
 
and has stopped moving.
The position indication pointer is indicating open.
UNIT 3 ONLY:
Examinee simulates loosening valve stem lock. Examinee simulates unlocking and opening EWB-HCV-68 Note: Valve is located in EW heat exchanger B room.
SAT / UNSAT Comments (required for UNSAT):
 
JP-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  17  STEP CUE STANDARD 6.
* Continuation of step 3 of Attachment 64-B: Unlock and open EWB-HCV-134, EW ISOLATION TO SFP HEAT  
 
EXCHANGER. EWB-HCV-134 stem lock is loosened and ZZ06 lock is broken. EWB-HCV-134 has been rotated in the counter-clockwise direction  
 
and has stopped moving.
The position indication pointer is indicating open.
Examinee simulates loosening valve stem lock. Examinee simulates unlocking and opening EWB-HCV-134 Note: Valve is located in EW heat exchanger B room.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 7. Step 4 of Attachment 64-B:
Direct an operator to perform the following to override and open EWB-PCV-174 "REFRIGERANT
 
HEAD PRESSURE CONTROL
 
VALVE".


JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                            STANDARD
: 6.
* Continuation of step 3 of Attachment EWB-HCV-134 stem lock is          Examinee simulates loosening valve 64-B:                                loosened and ZZ06 lock is broken. stem lock.
Unlock and open EWB-HCV-134,        EWB-HCV-134 has been rotated      Examinee simulates unlocking and EW ISOLATION TO SFP HEAT            in the counter-clockwise direction opening EWB-HCV-134 EXCHANGER.                          and has stopped moving.
Note: Valve is located in EW heat The position indication pointer is exchanger B room.
indicating open.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 7.      Step 4 of Attachment 64-B:          Another operator has overridden    Examinee simulates calling another and opened EWB-PCV-174            operator or the control room to open Direct an operator to perform the EWB-PCV-174.
following to override and open EWB-PCV-174 REFRIGERANT HEAD PRESSURE CONTROL VALVE.
Turn the Pilot Bypass Stem in he fully counter clockwise position.
Turn the Pilot Bypass Stem in he fully counter clockwise position.
Another operator has overridden and opened EWB-PCV-174 Examinee simulates calling another operator or the control room to open EWB-PCV-174.
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):  
17


JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 18  STEP CUE STANDARD Step 5 of Attachment 64-B:
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                   CUE                             STANDARD
Place NCN-FI-257, FPHX B OUTLET FLOWMETER, in service by performing the following:
: 8.
Ensure the local equalizing valve is open. The local equalizing valve will rotate freely in the closed  
* Step 5 of Attachment 64-B:                                               Examinee simulates placing flow meter in service. Steps must be Place NCN-FI-257, FPHX B performed in the exact order listed to OUTLET FLOWMETER, in service be satisfactory.
 
by performing the following:
direction, but only slightly open. Open NCB-V113, NCN-FI-257 Root Isolation. NCB-V113 has been rotated counter-clockwise and has stopped moving. Open NCB-V114, NCN-FI-257 Root Isolation. NCB-V114 has been rotated counter-clockwise and has stopped moving. Open the local low side isolation valve. The local low side isolation has been rotated in the counter-
* Ensure the local equalizing valve The local equalizing valve will     Note: Flowmeter is located in Fuel is open.                          rotate freely in the closed         Bldg 100 ft. on West side of direction, but only slightly open. stanchion South of PCHX A.
 
* Open NCB-V113, NCN-FI-257         NCB-V113 has been rotated Root Isolation.                  counter-clockwise and has stopped moving.
clockwise direction and has  
* Open NCB-V114, NCN-FI-257         NCB-V114 has been rotated Root Isolation.                  counter-clockwise and has stopped moving.
 
* Open the local low side isolation The local low side isolation has valve.                            been rotated in the counter-clockwise direction and has stopped moving.
stopped moving. Close the equalizing valve.
* Close the equalizing valve.       The equalizing valve has been rotated clockwise and has stopped moving.
The equalizing valve has been rotated clockwise and has stopped moving. 8.
* Slowly open the local high side   The local high side isolation has isolation valve                  been rotated in the counter-clockwise direction and has stopped moving.
* Slowly open the local high side isolation valve The local high side isolation has been rotated in the counter-
If requested cue: Flow is currently at 1300 gpm on NCN-FI-257.
 
SAT / UNSAT Comments (required for UNSAT):
clockwise direction and has  
18
 
stopped moving.
If requested cue: Flow is currently at 1300 gpm on NCN-FI-257. Examinee simulates placing flow meter in service. Steps must be performed in the exact order listed to be satisfactory.
 
Note: Flowmeter is located in Fuel Bldg 100 ft. on West side of stanchion South of PCHX A.
SAT / UNSAT Comments (required for UNSAT):  
 
JP-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  19  STEP CUE STANDARD 9.
* Step 6 of Attachment 64-B:
Unlock and adjust NCB-HCV-265, FPHX B OUTLET ISOLATION, to obtain 1400-2400 gpm.
Flow is currently at 1300 gpm.
After examinee simulates opening-NCB-HV-265, flow is at 1700 gpm.
After examinee adjusts flow provide the following Cue: Another operator will complete the rest of Attachment 64-B.
 
This JPM is complete. Examinee simulates opening NCB-HCV-265. Examinee checks flow on NCN-FI-257.
Note: Valve is in Fuel Bldg 100 ft at PC Heat Exchanger B outlet.
 
SAT / UNSAT Comments (required for UNSAT):


JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                            CUE                          STANDARD
: 9.
* Step 6 of Attachment 64-B:      Flow is currently at 1300 gpm.      Examinee simulates opening NCB-HCV-265. Examinee checks flow on Unlock and adjust NCB-HCV-265,  After examinee simulates opening-NCN-FI-257.
FPHX B OUTLET ISOLATION, to      NCB-HV-265, flow is at 1700 gpm.
obtain 1400-2400 gpm.
After examinee adjusts flow        Note: Valve is in Fuel Bldg 100 ft at provide the following Cue:          PC Heat Exchanger B outlet.
Another operator will complete the rest of Attachment 64-B.
This JPM is complete.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 19
 
JP-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  20  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 001 02/10/06 3 Updated JPM to 40EP-9EO10 Rev 45. Updated cues. 002 02/24/06 6 Change cue for step 10 to coincide with plant indications. Updated Validation time from 20 to 30 minutes. 003 03/09/06 6 Change cue in step 8. Included appropriate cues for NC/EW valves that have stem locks. Updated Validation time from 30 to 40 minutes. Editorial changes. 004 03/16/06 6 Updated step 5 cue to highlight that both U1 & U3 have stem locks on EWB-HCV-68. Added valve position indicator cue to


step 6. 005 03/23/06 6 Updated step 5 cue to indicate that only U3 has the stem lock on EWB-HCV-68. Deleted step 12 and changed step 11cue to end the JPM with another operator performing the remaining steps. 006 03/12/2009 Updated to new format REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 001          02/10/06            3        Updated JPM to 40EP-9EO10 Rev 45. Updated cues.
002          02/24/06            6        Change cue for step 10 to coincide with plant indications.
Updated Validation time from 20 to 30 minutes.
003          03/09/06            6        Change cue in step 8. Included appropriate cues for NC/EW valves that have stem locks. Updated Validation time from 30 to 40 minutes. Editorial changes.
004          03/16/06            6        Updated step 5 cue to highlight that both U1 & U3 have stem locks on EWB-HCV-68. Added valve position indicator cue to step 6.
005           03/23/06             6         Updated step 5 cue to indicate that only U3 has the stem lock on EWB-HCV-68. Deleted step 12 and changed step 11cue to end the JPM with another operator performing the remaining steps.
006         03/12/2009                     Updated to new format REASON REVISED             Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 7. Vendor reference document upgrade
: 8. Plant modification (include number)
: 9. Procedure upgrade
: 10. Internal or External Agency Commitment (indicate item number)
: 11. Technical Specification Change (indicate amendment number)
: 12. Other (explain in comments) 20


consecutively in each revision.
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 7. Vendor reference document upgrade
* The plant has experienced a loss of offsite power and recovery is not expected soon.
: 8. Plant modification (include number)
* The control room is currently performing steps from the Loss of Offsite Power EOP.
: 9. Procedure upgrade
* The CRS has directed you to perform the Area 3 actions from Attachment 64-B to align Train B EW to Spent Fuel Pool Cooling.
: 10. Internal or External Agency Commitment (indicate item number)
* Another operator has been stationed at Essential Chiller B to perform required actions.
: 11. Technical Specification Change (indicate amendment number)
* Permission has been granted to break 40AC-9ZZ06 locks as required.
: 12. Other (explain in comments)
CANDIDATE 21
JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 21 INITIAL CONDITIONS INITIATING CUE:
The plant has experienced a loss of offsite power and recovery is not expected soon.
The control room is currently performing steps from the Loss of Offsite Power EOP.
The CRS has directed you to perform the Area 3 actions from 4-B to align Train B EW to Spent Fuel Pool Cooling.
Another operator has been stationed at Essential Chiller B to perform required actions.
Permission has been granted to break 40AC-9ZZ06 locks as required.  


CANDIDATE JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 22 JPM BASIS INFORMATION TASK: 1240023901 Perform operation of AFA-P01 at the Remote Shutdown Panel TASK STANDARD: Feeding the Steam Generators with AFA-P01 from the Remote Shutdown Panel K/A: 3.4-061-A3.01 K/A RATING: RO:
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240023901 Perform operation of AFA-P01 at the Remote Shutdown Panel TASK STANDARD: Feeding the Steam Generators with AFA-P01 from the Remote Shutdown Panel K/A: 3.4-061-A3.01                                 K/A RATING:       RO:   4.2   SRO: 4.2 K/A:                                               K/A RATING:       RO:         SRO:
4.2 SRO: 4.2 K/A: K/A RATING: RO:
APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:         10 minutes
SRO: APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40AO-9ZZ18, Shutdown Outside the Control Room, Appendix E Auxiliary Feed Pumps Operation, Rev 7 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X     JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 02/27/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X     TESTING METHOD: SIMULATE X PERFORM       EVALUATION Examinee Name:
40AO-9ZZ18, Shutdown Outside the Control Room, Appendix E Auxiliary Feed Pumps Operation, Rev 7 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR                 PLANT           X JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   02/27/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT         X TESTING METHOD:                           SIMULATE           X     PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
22                                  Revised 9/23/08


JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 23 3. SIMULATOR SETUP:
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
K. IC#: N/A L. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 3.       SIMULATOR SETUP:
: 9. N/A 10. 11. 12. M. SPECIAL INSTRUCTIONS: NONE N. REQUIRED CONDITIONS: NONE O. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
K. IC#: N/A L. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT             COMMAND                                   DESCRIPTION
: 4. SPECIAL TOOLS/EQUIPMENT: Copy of 40AO-9ZZ18, Shutdown Outside Control Room (Appendix E - Auxiliary Feed Pumps Operations), Rev 7 JP-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 24 
: 9.       N/A 10.
11.
12.
M. SPECIAL INSTRUCTIONS:
* NONE N. REQUIRED CONDITIONS:
* NONE O. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 4. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40AO-9ZZ18, Shutdown Outside Control Room (Appendix E - Auxiliary Feed Pumps Operations), Rev 7 23


TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* You are a reactor operator on crew.
* The crew has implemented 40AO-9ZZ18, Shutdown Outside the Control Room to shutdown the unit.
* The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed the Steam Generators using AFA-P01 (Train A Auxiliary Feedwater Pump) from the Remote Shutdown Panel.
24


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
INITIATING CUE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
25


You are a reactor operator on crew. The crew has implemented 40AO-9ZZ18, Shut down Outside the Control Room to shutdown the unit. The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed the Steam Generators using AFA-P 01 (Train 'A' Auxiliary Feedwater Pump) from the Remote Shutdown Panel.
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                          CUE                            STANDARD
: 1.      Step 2.                         After the examinee simulates      NOTE: Examinee simulates turning turning the speed potentiometer  the speed potentiometer in the IF AFA-P01 will be used THEN counter-clockwise provide the    counter-clockwise direction until the perform the following:
following cue:                    dial is at minimum.
Adjust AFA-SK-52B, Auxiliary The potentiometer has stopped Feedwater Pump A Speed to moving and reads 0.
minimum SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                            STANDARD
: 2.
* Continuation of Step 2:        After the examinee simulates      NOTE: Examinee simulates turning turning the speed control        the speed control transfer switch left Place AFA-SK-52A, Speed Control handswitch to the REMOTE        to the REMOTE SHUTDOWN Transfer, to the REMOTE        SHUTDOWN position provide        position.
SHUTDOWN position.            the following cue:
The handswitch is pointing to the left.
SAT / UNSAT Comments (required for UNSAT):
26


JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 25 
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                            STANDARD
: 3.
* Continuation of Step 2:            After the examinee simulates        Examinee simulates opening either turning handswitch for either      SGA-UV-134 or SGA-UV-138.
Open one of the following Steam    SGA-UV-134 or SGA-UV-138 Supply Valves                      provide the following cue for the appropriate valves:
* SGA-UV-134
* SGA-UV-138                The indication for SGA-UV-134(8)A red light is on. 30 seconds later the red light for SGA-UV-134 came on and both Green lights are off.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 4.
* Continuation of Step 2:            As the examinee goes to increase  The examinee looks at the speed on the speed potentiometer          indicator for AFA-P01 (AFA-SI-Adjust turbine speed using AFA-SK- provide the following cue:          52B) on the Remote Shutdown Panel 52B to ONE of the following:      Unit 1 and 3 Cue:                  and adjusts the potentiometer to raise speed to 3590-3600 rpm in Unit 1 Unit 1 & 3 only -
* Speed is now 3600 rpm      and 3 or 3560-3570 in Unit 2..
* 3590-3600 rpm Unit 2 only                        Unit 2 Cue:
* 3560-3570 rpm
* Speed is now 3560 rpm SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 5.
* Continuation of Step 2:            When the examinee takes the        Examinee simulates placing the handswitches for AFA-UV-37 and      handswitches for AFA-UV-37 and Open BOTH of the following AFW 36 to open provide the following    AFA-UV-36 Pump A to Steam Generator cue:
Downstream Valves:
* AFA-UV-37                The red lights for AFA-UV-37 and
* AFA-UV-36                36 are on and the green lights are off.
SAT / UNSAT Comments (required for UNSAT):
27


INFORMATION FOR EVALUATOR'S USE:
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                 CUE                           STANDARD
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 6.
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 26 JPM START TIME:
* Continuation of Step 2:             When examinee looks at SG level    Examine determines SG WR level transmitters provide the following  and throttles open both SG Upstream Maintain steam generator levels 35-cue:                               valves.
STEP CUE STANDARD 1. Step 2. IF AFA-P01 will be used THEN perform the following:
80% WR with ANY of the following AFA Pump A to Steam Generator       Steam Generator Wide Range Upstream Valves::                  Levels are 30% WR.
Adjust AFA-SK-52B, Auxiliary Feedwater Pump A Speed to minimum After the examinee simulates turning the speed potentiometer
* AFA-UV-32                  If asked the as found position of
 
* AFA-UV-33                  AFA-UV-23 and 33 are as indicated on the panel.
counter-clockwise provide the
When the examine simulates jogging open AFA-UV-32 and 33 provide the following cue:
 
AFA-UV-32 red and green lights are on.
following cue:
When examine looks at position indication for valves provide the following cue:
The potentiometer has stopped moving and reads "0".
NOTE:  Examinee simulates turning the speed potentiometer in the
 
counter-clockwise direction until the dial is at minimum.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 2.
* Continuation of Step 2:
Place AFA-SK-52A, Speed Control Transfer, to the "REMOTE SHUTDOWN" position.
After the examinee simulates turning the speed control
 
handswitch to the "REMOTE
 
SHUTDOWN" position provide  
 
the following cue:
The handswitch is pointing to the left. NOTE: Examinee simulates turning the speed control transfer switch left to the "REMOTE SHUTDOWN" position.
SAT / UNSAT Comments (required for UNSAT):
 
JP-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  27  STEP CUE STANDARD 3.
* Continuation of Step 2:
Open one of the following Steam Supply Valves  SGA-UV-134  SGA-UV-138 After the examinee simulates turning handswitch for either
 
SGA-UV-134 or SGA-UV-138
 
provide the following cue for the appropriate valves:
The indication for SGA-UV-134(8)A red light is on. 30 seconds later the red light for SGA-UV-134
 
came on and both Green lights are
 
off. Examinee simulates opening either SGA-UV-134 or SGA-UV-138.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 4.
* Continuation of Step 2:
Adjust turbine speed using AFA-SK-52B to ONE of the following: Unit 1 & 3 only -  3590-3600 rpm Unit 2 only  3560-3570 rpm As the examinee goes to increase on the speed potentiometer 
 
provide the following cue
: Unit 1 and 3 Cue:  Speed is now 3600 rpm Unit 2 Cue:  Speed is now 3560 rpm The examinee looks at the speed indicator for AFA-P01 (AFA-SI-52B) on the Remote Shutdown Panel and adjusts the potentiometer to raise speed to 3590-3600 rpm in Unit 1 and 3 or 3560-3570 in Unit 2..
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 5.
* Continuation of Step 2:
Open BOTH of the following AFW Pump A to Steam Generator Downstream Valves:  AFA-UV-37  AFA-UV-36 When the examinee takes the handswitches for AFA-UV-37 and 36 to open provide the following
 
cue: The red lights for AFA-UV-37 and 36 are on and the green lights are
 
off. Examinee simulates placing the handswitches for AFA-UV-37 and
 
AFA-UV-36 SAT / UNSAT Comments (required for UNSAT):
 
JP-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  28  STEP CUE STANDARD When examinee looks at SG level transmitters provide the following
 
cue: Steam Generator Wide Range Levels are 30% WR.
If asked the as found position of  
 
AFA-UV-23 and 33 are as  
 
indicated on the panel.
When the examine simulates jogging open AFA-UV-32 and 33  
 
provide the following cue:
AFA-UV-32 red and green lights are on. When examine looks at position indication for valves provide the  
 
following cue:
Valve position indicators read approximately _20_ % (depending on what operator says).
Valve position indicators read approximately _20_ % (depending on what operator says).
When examine looks at AF flow indicator provide the following  
When examine looks at AF flow indicator provide the following cue:
 
The gauge indication is reading 350 gpm.
cue: The gauge indication is reading 350 gpm. 6.
After feed is established provide the following cue:
* Continuation of Step 2: Maintain steam generator levels 35-80% WR with ANY of the following AFA Pump A to Steam Generator Upstream Valves::  AFA-UV-32  AFA-UV-33  After feed is established provide the following cue: Another operator will finish Appendix E. This JPM is complete. Examine determines SG WR level and throttles open both SG Upstream valves. SAT / UNSAT Comments (required for UNSAT):  
Another operator will finish Appendix E.
 
This JPM is complete.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 28


JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 29  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 0 2/27/09 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                               COMMENTS 0             2/27/09             6         Record created REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 13. Vendor reference document upgrade
: 14. Plant modification (include number)
: 15. Procedure upgrade
: 16. Internal or External Agency Commitment (indicate item number)
: 17. Technical Specification Change (indicate amendment number)
: 18. Other (explain in comments) 29


consecutively in each revision.
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 13. Vendor reference document upgrade
* You are a reactor operator on crew.
: 14. Plant modification (include number)
* The crew has implemented 40AO-9ZZ18, Shutdown Outside the Control Room to shutdown the unit.
: 15. Procedure upgrade
* The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed the Steam Generators using AFA-P01 (Train A Auxiliary Feedwater Pump) from the Remote Shutdown Panel.
: 16. Internal or External Agency Commitment (indicate item number)
CANDIDATE 30
: 17. Technical Specification Change (indicate amendment number)
: 18. Other (explain in comments)
JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 30 INITIAL CONDITIONS INITIATING CUE:
You are a reactor operator on crew. The crew has implemented 40AO-9ZZ18, Shutdown Outside the Control Room to shutdown the unit. The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed th e Steam Generators using AFA-P01 (Train 'A' Auxiliary Feedwater Pump) from the Remote Shutdown Panel.    


CANDIDATE JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 31 JPM BASIS INFORMATION TASK: 0010030401 Perform a SG 1 (2) high rate blowdown to the main condenser. TASK STANDARD: Use the high rate blowdown system to lower SG level K/A: 4.1 038 EA1.18 K/A RATING: RO:
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 0010030401 Perform a SG 1 (2) high rate blowdown to the main condenser.
4.0 SRO: 3.9 K/A: K/A RATING: RO:
TASK STANDARD: Use the high rate blowdown system to lower SG level K/A: 4.1 038 EA1.18                               K/A RATING:       RO:   4.0   SRO:   3.9 K/A:                                               K/A RATING:       RO:         SRO APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:         10 minutes
SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40EP-9EO10 Standard Appendices, Appendix 33 - Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes     APPROVAL Developed By: Alan Malley Date: 04/14/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40EP-9EO10 Standard Appendices, Appendix 33 - Rev 60 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       Yes APPROVAL Developed By:     Alan Malley                   Date:   04/14/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
31                                  Revised 9/23/08


JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 32 4. SIMULATOR SETUP:
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
: 4.     SIMULATOR SETUP:
P. If running JS1 and JS2 together reset to IC#: 106 (For 2009 NRC exam only)
P. If running JS1 and JS2 together reset to IC#: 106 (For 2009 NRC exam only)
If running JS1and JS3 together reset to IC# 110 (For 2009 NRC exam only)
If running JS1and JS3 together reset to IC# 110 (For 2009 NRC exam only)
Q. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
Q. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT                       COMMAND                                           DESCRIPTION
: 13. WHEN direct to open SGE-V293, SGE-V267, and SGE-VA33 perform the following: Go to page WD6 and click on the handswitch for 500Q. Use the override to take the valve to close.
: 13. WHEN direct to open SGE-V293, SGE-               When examinee directs AO to open bypass valves for V267, and SGE-VA33 perform the                   500S. (Valves are SGE-V293, SGE-V267, and SGE-following:                                       VA33).
THEN Delete the override for the handswitch above, THEN dmf cmAVWD06SGBUV500Q_4 (listed under "Comp Malfs" on the header at the top of the simulator  
* Go to page WD6 and click on the         The handswitch is taken to close to ensure the valve handswitch for 500Q. Use the           does not open when the malfunction is deleted. This override to take the valve to close. ensures the examinee has to open the valve.
 
THEN
page) THEN report the valves are open. When examinee directs AO to open bypass valves for 500S. (Valves are SGE-V293, SGE-V267, and SGE-
* Delete the override for the handswitch above, THEN
 
* dmf cmAVWD06SGBUV500Q_4 (listed under Comp Malfs on the header at the top of the simulator page)
VA33). The handswitch is taken to close to ensure the valve does not open when the malfunction is deleted. This
THEN report the valves are open.
 
: 14. WHEN directed to close SGE-V293, SGE-V267, and SGE-VA33, wait a minute and report the valves closed.
ensures the examinee has to open the valve.  
: 14. WHEN directed to close SGE-V293, SGE-V267, and SGE-VA33, wait a minute and  
 
report the valves closed.
: 15. WHEN directed to open SCN-V088, V099, V071, and V072, wait a few minutes and report the valves are open. These are opened in the simulator setup.
: 15. WHEN directed to open SCN-V088, V099, V071, and V072, wait a few minutes and report the valves are open. These are opened in the simulator setup.
R. SPECIAL INSTRUCTIONS: Reset to IC- 106 This JPM is set up to run with JS-2 and JS-3 for the 2009 NRC exam S. REQUIRED CONDITIONS: SG NR level approximately 65-75% NR.
R. SPECIAL INSTRUCTIONS:
T. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
* Reset to IC- 106
* This JPM is set up to run with JS-2 and JS-3 for the 2009 NRC exam S. REQUIRED CONDITIONS:
* SG NR level approximately 65-75% NR.
T. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
32


JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 33 5. SPECIAL TOOLS/EQUIPMENT: Copy of Standard Appendix 33 This scenario is set up in IC-106. If for some reason IC-106 is not available, reset to IC 6, use AF to fill SG#1 to approximately 70% NR and close all the Blowdown containment isolation valves. Then perform the following to open SCNV088 and SCNV071: mrf rfWD29 OPEN mrf rfWD30 OPEN imf cmAVWD06SGBUV500Q_4 (mechanical Seizure of 500Q)
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
: 5. SPECIAL TOOLS/EQUIPMENT:
* Copy of Standard Appendix 33 This scenario is set up in IC-106. If for some reason IC-106 is not available, reset to IC 6, use AF to fill SG#1 to approximately 70% NR and close all the Blowdown containment isolation valves. Then perform the following to open SCNV088 and SCNV071:
* mrf rfWD29 OPEN
* mrf rfWD30 OPEN
* imf cmAVWD06SGBUV500Q_4 (mechanical Seizure of 500Q)
TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
 
IN PLANT JPMs ONLY
IN PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high  
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
 
* Inform the control room staff of any discovered deficiencies.
radiation areas. ALL JPMs You may use any source of information normally available.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
INITIATING CUE:  
ALL JPMs
 
* You may use any source of information normally available.
Unit 1 is cooling down following a SGTR SG #1 NR level is approximately 74%. The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.
INITIATING CUE:
* Unit 1 is cooling down following a SGTR
* SG #1 NR level is approximately 74%.
* The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.
INFORMATION FOR EVALUATOR'S USE:
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments.
* Denotes Critical Step
JS-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 34 If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
JS-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  35 JPM START TIME:
* Any step marked UNSAT requires comments.
33


STEP CUE STANDARD 1. Step 1of Standard Appendix 33:
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
Place SCN-HS-1, SG 1 Blowdown Path Selector in "OFF".
* If this is the first JPM of the set then ensure the examinee has been briefed.
Examinee places SCN-HS-1 in "OFF". SAT / UNSAT Comments (required for UNSAT):
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
34


STEP CUE STANDARD 2.
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
* Step 2 of Standard Appendix 33:
STEP                                CUE                        STANDARD
Ensure SGA-UV-500P, SG 1 Common Upstream Isolation, is  
: 1.      Step 1of Standard Appendix 33:                                        Examinee places SCN-HS-1 in OFF.
Place SCN-HS-1, SG 1 Blowdown Path Selector in OFF.
SAT / UNSAT Comments (required for UNSAT):
STEP                               CUE                         STANDARD
: 2.
* Step 2 of Standard Appendix 33:                                       Examinee opens SGA-UV-500P.
Ensure SGA-UV-500P, SG 1 Common Upstream Isolation, is open.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                        STANDARD
: 3.
* Step 3 of Standard Appendix 33:    If asked as CRS which valve to use Examinee opens either SGE-HV-43 provide the following cue:        or SGE-HV-41.
Ensure that ONE of the following valves is open:                    Select either valve.
* SGE-HV-43, SG 1 Hot Leg Isolation
* SGE-HV-41, SG 2 Cold Leg Isolation SAT / UNSAT Comments (required for UNSAT):
35


open. Examinee opens SGA-UV-500P.
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                  CUE                            STANDARD
SAT / UNSAT Comments (required for UNSAT):  
: 4.      Step 4 of Standard Appendix 33:                                            The examinee determines SGB-UV-500Q is closed and goes to the Check that SGB-UV-500Q is open.
contingency step 4.1.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                            STANDARD
: 5.
* Step 4.1 of Standard Appendix 33:    Simulator Driver action required    Examinee directs an operator to open at this time!!!                      SGE-V293, SGE-V267, and SGE-Perform the following to open SGB-                                        VA33.
UV-500Q:                              Have the trainee use the radio to communicate with the Sim Driver. When the operator reports these
: a. Direct an operator to perform the The driver will provide the cues for valves are open, the examinee opens following:
the valve positions.                SGB-UV-500Q.
: 1) Unlock and open SGE-V293, SGB-UV-500Q BYPASS HDR INLET ISOL VALVE
: 2) Open SGE-V267, SGB-UV-                                              After SGB-UV-500Q is open, the 500Q BYPASS HDR                                                    examinee directs the operator to OUTLET ISOL VALVE                                                close SGE-V293, SGE-V267, and
: 3) Slowly open SGE-VA33,                                                SGE-VA33.
SGB-UV-500Q BYPASS HEADER THROTTLE VALVE
: b. Open SGB-UV-500Q, SG 1 Common Downstream Isolation
: c. Direct an operator to close ALL of the following valves:
* SGE-V293
* SGE-V267
* SGE-VA33 SAT / UNSAT Comments (required for UNSAT):
36


STEP CUE STANDARD 3.
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                               CUE                             STANDARD
* Step 3 of Standard Appendix 33:
: 6.     Step 5 of Standard Appendix 33:   (All valves have been positioned in  Examinee directs an operator to open the simulator setup).                 the following valves:
Ensure that ONE of the following valves is open:  SGE-HV-43, SG 1 Hot Leg Isolation  SGE-HV-41, SG 2 Cold Leg Isolation If asked as CRS which valve to use provide the following cue:
Direct an operator to open ALL of
Select either valve. Examinee opens either SGE-HV-43 or SGE-HV-41.
* SCN-V088 the following valves:
 
* SCN-V099
SAT / UNSAT Comments (required for UNSAT):
* SCN-V088, SCN-HV-018C       The sim driver will inform the
 
* SCN-V071 OUTLET ISOLATION             candidate that these valves are open.
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 36  STEP CUE STANDARD 4. Step 4 of Standard Appendix 33:
* SCN-V072 VALVE (S/G 1 HIGH RATE B/D TO CONDENSER)
Check that SGB-UV-500Q is open. The examinee determines SGB-UV-500Q is closed and goes to the contingency step 4.1.
* SCN-V099, SCN-HV-018C INLET ISOLATION VALVE (S/G 1 HIGH RATE B/D TO CONDENSER)
SAT / UNSAT Comments (required for UNSAT):  
* SCN-V071, SCN-HV-018B OUTLET ISOLATION VALVE (S/G 1 ABNORMAL RATE B/D TO CONDENSER)
 
* SCN-V072, SCN-HV-018B INLET ISOLATION VALVE (S/G 1 ABNORMAL RATE B/D TO CONDENSER)
STEP CUE STANDARD 5.
SAT / UNSAT Comments (required for UNSAT):
* Step 4.1 of Standard Appendix 33:
STEP                               CUE                             STANDARD
Perform the following to open SGB-UV-500Q: a. Direct an operator to perform the following:
: 7.
: 1) Unlock and open SGE-V293, "SGB-UV-500Q BYPASS
* Step 6 of Standard Appendix 33:                                         Examinee places SCN-HS-18 in HIGH RATE.
 
Place SCN-HS-18, SG 1 Blowdown Rate Selector in HIGH RATE.
HDR INLET ISOL VALVE"
SAT / UNSAT Comments (required for UNSAT):
: 2) Open SGE-V267, "SGB-UV-500Q BYPASS HDR
37
 
OUTLET ISOL VALVE"
: 3) Slowly open SGE-VA33, "SGB-UV-500Q BYPASS
 
HEADER THROTTLE
 
VALVE" b. Open SGB-UV-500Q, SG 1 Common Downstream Isolation
: c. Direct an operator to close ALL of the following valves:  SGE-V293  SGE-V267  SGE-VA33 Simulator Driver action required at this time!!!
Have the trainee use the radio to communicate with the Sim Driver.
The driver will provide the cues for the valve positions.
Examinee directs an operator to open SGE-V293, SGE-V267, and SGE-
 
VA33. When the operator reports these valves are open, the examinee opens SGB-UV-500Q.
 
After SGB-UV-500Q is open, the examinee directs the operator to close SGE-V293, SGE-V267, and
 
SGE-VA33.
SAT / UNSAT Comments (required for UNSAT):
 
JS-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  37  STEP CUE STANDARD 6.      Step 5 of Standard Appendix 33:
Direct an operator to open ALL of the following valves:   SCN-V088, "SCN-HV-018C OUTLET ISOLATION  
 
VALVE" (S/G 1 HIGH RATE  
 
B/D TO CONDENSER) SCN-V099, "SCN-HV-018C INLET ISOLATION VALVE" (S/G 1 HIGH RATE B/D TO  
 
CONDENSER) SCN-V071, "SCN-HV-018B OUTLET ISOLATION VALVE" (S/G 1 ABNORMAL  
 
RATE B/D TO CONDENSER) SCN-V072, "SCN-HV-018B INLET ISOLATION VALVE" (S/G 1 ABNORMAL RATE  
 
B/D TO CONDENSER) (All valves have been positioned in the simulator setup).
 
The sim driver will inform the candidate that these valves are open. Examinee directs an operator to open the following valves:  SCN-V088  SCN-V099  SCN-V071  SCN-V072 SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 7.
* Step 6 of Standard Appendix 33:
Place SCN-HS-18, SG 1 Blowdown Rate Selector in "HIGH RATE". Examinee places SCN-HS-18 in "HIGH RATE".
SAT / UNSAT Comments (required for UNSAT):
 
JS-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  38  STEP CUE STANDARD 8.
* Step 7 of Standard Appendix 33: Maintain SG level by performing the following:
: a. Place SCN-HS-1, SG 1 Blowdown Path Selector in  
 
"COND". b. WHEN SG 1 level reaches the desired level, THEN place SCH-HS-1, SG1 Blowdown Path
 
Selector in "OFF".
When examiner has seen level decrease, provide the following
 
cue:
Another operator will monitor SG level and secure blowdown at 50%.
 
This JPM is complete.
Examinee places SCN-HS-1 in "COND" and monitors SG level.
SAT / UNSAT Comments (required for UNSAT):  


JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                              CUE                          STANDARD
: 8.
* Step 7 of Standard Appendix 33:    When examiner has seen level      Examinee places SCN-HS-1 in decrease, provide the following    COND and monitors SG level.
Maintain SG level by performing the cue:
following:
: a. Place SCN-HS-1, SG 1 Blowdown Path Selector in Another operator will monitor SG COND.
level and secure blowdown at 50%.
: b. WHEN SG 1 level reaches the desired level, THEN place SCH-HS-1, SG1 Blowdown Path Selector in OFF.            This JPM is complete.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 38


NORMAL TERMINATION POINT
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                               COMMENTS 0           04/14/2009           6         Record created REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
 
: 19. Vendor reference document upgrade
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 39  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 0 04/14/2009 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
: 20. Plant modification (include number)
 
: 21. Procedure upgrade
consecutively in each revision.  
: 22. Internal or External Agency Commitment (indicate item number)
: 19. Vendor reference document upgrade  
: 23. Technical Specification Change (indicate amendment number)
: 20. Plant modification (include number)  
: 24. Other (explain in comments) 39
: 21. Procedure upgrade  
: 22. Internal or External Agency Commitment (indicate item number)  
: 23. Technical Specification Change (indicate amendment number)  
: 24. Other (explain in comments)
JS-1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  40 INITIAL CONDITIONS CANDIDATE 


INITIATING CUE:
JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:
Unit 1 is cooling down following a SGTR SG #1 NR level is approximately 74%. The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.  
* Unit 1 is cooling down following a SGTR
* SG #1 NR level is approximately 74%.
* The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.
CANDIDATE 40


CANDIDATE JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 41 JPM BASIS INFORMATION TASK: 1240001601 Perform LM-HPSI pump cold leg injection TASK STANDARD: Borate the RCS using Charging Pump through Hot leg Injection K/A: 4.2-024-AA1.09 K/A RATING: RO:
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240001601 Perform LM-HPSI pump cold leg injection TASK STANDARD: Borate the RCS using Charging Pump through Hot leg Injection K/A: 4.2-024-AA1.09                               K/A RATING:         RO:   3.5   SRO: 3.5 K/A: 4.2-024-AA1.22                               K/A RATING:         RO:   3.2   SRO 3.2 APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:           10 minutes
3.5 SRO: 3.5 K/A: 4.2-024-AA1.22 K/A RATING: RO:
3.2 SRO 3.2 APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40EP-9EO10 - Standard Appendices, Appendix 209, LM-Charging Pump Hot Leg Injection Tran B HPSI, Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 3/10/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40EP-9EO10 - Standard Appendices, Appendix 209, LM-Charging Pump Hot Leg Injection Tran B HPSI, Rev 60 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR             X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   3/10/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR           X       PLANT TESTING METHOD:                           SIMULATE                   PERFORM       X EVALUATION Examinee Name:                                                     Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
41                                    Revised 9/23/08


JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 42 5. SIMULATOR SETUP:
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
U. IC#: 106 (For 2009 NRC exam only)
: 5.       SIMULATOR SETUP:
V. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
U. IC#: 106 (For 2009 NRC exam only)
: 16. None required W. SPECIAL INSTRUCTIONS: This is scheduled to run with JPM JS1 for the 2009 NRC exam.
V. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT                 COMMAND                                         DESCRIPTION
X. REQUIRED CONDITIONS: Ensure Charging Pump B is NOT running Y. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
: 16.         None required W. SPECIAL INSTRUCTIONS:
: 6. SPECIAL TOOLS/EQUIPMENT: Copy of 40EP-9EO10, Standard Appendices 209, LM-Charging Pump Hot Leg Injection Tran B HPSI.
* This is scheduled to run with JPM JS1 for the 2009 NRC exam.
If IC-106 is not available, reset to IC-6 and perform the following: Depressurize RCS to ~ 250 psia Shift to RCPs 1A and 1B running Close SIB-UV-656 using the handswitch Open SIB-UV-307 using the handswitch Mrf crRH05SIBHV692_1 CLOSE (Closes the breaker for SIB-UV-692)   Open SIB-UV-692 using the handswitch   Open SIB-UV-322 using the handswitch   Mrf rfSI06 OPEN (opens SIV508) Mrf rfCV33 CLOSE (closes CH-V337) Mrf rfCV35 CLOSE (closes CH-V319) Mrf rfCV28 OPEN (opens CH-V327) Mrf rfCV26 OPEN (opens CH-756) Mrf rvCV30 OPEN (opens CH-797)
X. REQUIRED CONDITIONS:
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 43 
* Ensure Charging Pump B is NOT running Y. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
: 6. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40EP-9EO10, Standard Appendices 209, LM-Charging Pump Hot Leg Injection Tran B HPSI.
If IC-106 is not available, reset to IC-6 and perform the following:
* Depressurize RCS to ~ 250 psia
* Shift to RCPs 1A and 1B running
* Close SIB-UV-656 using the handswitch
* Open SIB-UV-307 using the handswitch
* Mrf crRH05SIBHV692_1 CLOSE (Closes the breaker for SIB-UV-692)
* Open SIB-UV-692 using the handswitch
* Open SIB-UV-322 using the handswitch
* Mrf rfSI06 OPEN (opens SIV508)
* Mrf rfCV33 CLOSE (closes CH-V337)
* Mrf rfCV35 CLOSE (closes CH-V319)
* Mrf rfCV28 OPEN (opens CH-V327)
* Mrf rfCV26 OPEN (opens CH-756)
* Mrf rvCV30 OPEN (opens CH-797) 42


TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
 
IN PLANT JPMs ONLY
IN PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL JPMs You may use any source of information normally available.
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
INITIATING CUE:  
* Inform the control room staff of any discovered deficiencies.
 
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
The plant is shutdown in Mode 5. The CRS has entered the Lower Mode Functional Recovery Procedure. Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the 'B' Charging pump.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The plant is shutdown in Mode 5.
* The CRS has entered the Lower Mode Functional Recovery Procedure.
* Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the B Charging pump.
INFORMATION FOR EVALUATOR'S USE:
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
* Denotes Critical Step
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 44 Locked valves may be involved. No attempt will be made to actually operate any valves.
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  45 JPM START TIME:
* Any step marked UNSAT requires comments.
STEP CUE STANDARD 1. Step 1 of Appendix 209:
* If this is the first JPM of the set then ensure the examinee has been briefed.
Check BOTH of the following:  SDC Train B is NOT is service  SIB-UV-656, Loop 2 to SDC LPSI pump B Suction Valve is
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
43


closed  NOTE:  Examinee verifies Train B SDC is NOT in service and verifies SIB-UV-656 is closed.
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
SAT / UNSAT Comments (required for UNSAT):
* Locked valves may be involved. No attempt will be made to actually operate any valves.
44


STEP CUE STANDARD 2. Step 2 of Appendix 209:
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
IF it desired to align Charging Pump A, THEN perform the following:  
STEP                                CUE                          STANDARD
: a. Place Charging Pump A in the "PULL-TO-LOCK" position.  
: 1.      Step 1 of Appendix 209:                                              NOTE: Examinee verifies Train B SDC is NOT in service and verifies Check BOTH of the following:                                          SIB-UV-656 is closed.
: b. Direct an operator to PERFORM Attachment 209-A, Charging Pump A Hot Leg Injection Train B HPSI. If needed cue: The CRS directed you to use Charging Pump B. Examinee determines that Charging Pump A will not be used (in Initiating cue to use Charging Pump
* SDC Train B is NOT is service
* SIB-UV-656, Loop 2 to SDC LPSI pump B Suction Valve is closed SAT / UNSAT Comments (required for UNSAT):
STEP                                 CUE                         STANDARD
: 2.     Step 2 of Appendix 209:               If needed cue: The CRS directed Examinee determines that Charging you to use Charging Pump B. Pump A will not be used (in IF it desired to align Charging Pump Initiating cue to use Charging Pump A, THEN perform the following:
B).
: a. Place Charging Pump A in the PULL-TO-LOCK position.
: b. Direct an operator to PERFORM Attachment 209-A, Charging Pump A Hot Leg Injection Train B HPSI.
SAT / UNSAT Comments (required for UNSAT):
45


B). SAT / UNSAT Comments (required for UNSAT):  
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                            STANDARD
: 3.      Step 3 of Appendix 209:              After examinee directs an operator Examinee ensures Charging Pump B to Perform Attachment 209-B:      in PULL-TO-LOCK.
IF it desired to align Charging Pump B, THEN perform the following:        The area operator has completed    Examinee directs an Area Operator
: c. Place Charging Pump B in      Attachment 209-B.                  to perform Attachment 209-B.
the PULL-TO-LOCK position.
* Direct an operator to PERFORM Attachment 209-B, Charging Pump B Hot Leg Injection Train B HPSI.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 4.     Step 4 of Appendix 209:              If needed cue: The CRS directed    Examinee determines that Charging you to use Charging Pump B.        Pump E will not be used (in IF it desired to align Charging Pump Initiating cue to use Charging Pump E, THEN perform the following:
B).
: d. Place Charging Pump E in the PULL-TO-LOCK position.
* Direct an operator to PERFORM Attachment 209-C, Charging Pump E Hot Leg Injection Train B HPSI SAT / UNSAT Comments (required for UNSAT):
46


JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 46  STEP CUE STANDARD 3. Step 3 of Appendix 209:
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                               CUE                           STANDARD
IF it desired to align Charging Pump B, THEN perform the following:
: 5.
: c. Place Charging Pump B in the "PULL-TO-LOCK" position. Direct an operator to PERFORM Attachment 209-B, Charging Pump B Hot Leg Injection Train B HPSI. After examinee directs an operator to Perform Attachment 209-B:
* Step 5 of Appendix 209:                                             The examinee closes SIB-HV-609, HPSI B Long Term Recirc, and WHEN ANY of the following are closes SIB-UV-332, SIT Fill Header complete:
The area operator has completed Attachment 209-B.
Isolation.
Examinee ensures Charging Pump B in "PULL-TO-LOCK. Examinee directs an Area Operator to perform Attachment 209-B.
* Attachment 209-A
SAT / UNSAT Comments (required for UNSAT):
* Attachment 209-B
 
* Attachment 209-C THEN ensure BOTH of the following valves are closed:
STEP CUE STANDARD 4. Step 4 of Appendix 209:
* SIB-HV-609, HPSI B Long Term Recirc
IF it desired to align Charging Pump E, THEN perform the following:
* SIB-UV-332 SIT Fill Header Isolation SAT / UNSAT Comments (required for UNSAT):
: d. Place Charging Pump E in the "PULL-TO-LOCK" position. Direct an operator to PERFORM Attachment 209-C, Charging Pump E Hot Leg Injection Train B HPSI If needed cue: The CRS directed you to use Charging Pump B. Examinee determines that Charging Pump E will not be used (in Initiating cue to use Charging Pump
STEP                               CUE                           STANDARD
 
: 6.     Step 6 of Appendix 209:           After the examinee informs the  The examinee informs the CRS that Inform the CRS that the Charging   CRS that Charging Pump B is      Charging Pump B is aligned for Hot Pump(s) are aligned for Hot Leg   aligned for Hot Leg Injection to Leg Injection to HPSI Header B.
B). SAT / UNSAT Comments (required for UNSAT):
Injection to HPSI Header B.        HPSI Header B provide the following cue:
 
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  47  STEP CUE STANDARD 5.
* Step 5 of Appendix 209:
WHEN ANY of the following are complete:  Attachment 209-A Attachment 209-B Attachment 209-C THEN ensure BOTH of the following valves are closed: SIB-HV-609, HPSI B Long Term Recirc  SIB-UV-332 SIT Fill Header Isolation The examinee closes SIB-HV-609, HPSI B Long Term Recirc, and
 
closes SIB-UV-332, SIT Fill Header Isolation.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 6. Step 6 of Appendix 209: Inform the CRS that the Charging Pump(s) are aligned for Hot Leg  
 
Injection to HPSI Header B.
After the examinee informs the CRS that Charging Pump B is
 
aligned for Hot Leg Injection to  
 
HPSI Header B provide the  
 
following cue:
The CRS directs you to commence Hot Leg Injection.
The CRS directs you to commence Hot Leg Injection.
The examinee informs the CRS that Charging Pump B is aligned for Hot
SAT / UNSAT Comments (required for UNSAT):
 
47
Leg Injection to HPSI Header B.
SAT / UNSAT Comments (required for UNSAT):  
 
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  48  STEP CUE STANDARD 7.
* Step 7 of Appendix 209:
WHEN directed by the CRS to commence Hot Leg Injection, THEN perform the following:
: a. Open SID-HV-331, HPSI B Long Term Recirc Throttle
 
Valve. The plaque on the board that references 40DP-9OP07 is informing the operator that a valve stroke surveillance must be done before Mode 4 once these valves have been moved. The examinee opens SID-HV-331, HPSI B Long Term Recirc Throttle
 
Valve. SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 8.
* Step 7 of Appendix 209:
WHEN directed by the CRS to commence Hot Leg Injection, THEN perform the following:
: b. Start the Charging Pump(s) aligned for Hot Leg Injection.
After the examinee starts borating provide the following cue: Another operator will continue with this Appendix. This JPM is complete.
The examinee starts Charging Pump B. SAT / UNSAT Comments (required for UNSAT):


JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                          STANDARD
: 7.
* Step 7 of Appendix 209:            The plaque on the board that        The examinee opens SID-HV-331, WHEN directed by the CRS to        references 40DP-9OP07 is informing  HPSI B Long Term Recirc Throttle commence Hot Leg Injection, THEN    the operator that a valve stroke    Valve.
perform the following:              surveillance must be done before Mode 4 once these valves have been
: a. Open SID-HV-331, HPSI B    moved.
Long Term Recirc Throttle Valve.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                          STANDARD
: 8.
* Step 7 of Appendix 209:            After the examinee starts borating  The examinee starts Charging Pump WHEN directed by the CRS to        provide the following cue:          B.
commence Hot Leg Injection, THEN perform the following:              Another operator will continue with this Appendix.
: b. Start the Charging Pump(s) aligned for Hot Leg        This JPM is complete.
Injection.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 48


NORMAL TERMINATION POINT
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          03/10/2009            6        JPM created.
REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 25. Vendor reference document upgrade
: 26. Plant modification (include number)
: 27. Procedure upgrade
: 28. Internal or External Agency Commitment (indicate item number)
: 29. Technical Specification Change (indicate amendment number)
: 30. Other (explain in comments) 49


JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 49  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 03/10/2009 6 JPM created.
JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
* The plant is shutdown in Mode 5.
* The CRS has entered the Lower Mode Functional Recovery Procedure.
* Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the B Charging pump.
CANDIDATE 50


consecutively in each revision.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250280201 Respond to an Inadvertent RAS TASK STANDARD: RAS reset K/A: 3.7 012 A4.02                                 K/A RATING:       RO:   3.3   SRO:   3.4 K/A:                                               K/A RATING:       RO:         SRO APPLICABLE POSITION(S):             RO             VALIDATION TIME:         10 minutes
: 25. Vendor reference document upgrade
: 26. Plant modification (include number)
: 27. Procedure upgrade
: 28. Internal or External Agency Commitment (indicate item number)
: 29. Technical Specification Change (indicate amendment number)
: 30. Other (explain in comments)
JS-2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  50 INITIAL CONDITIONS CANDIDATE 
 
INITIATING CUE:
The plant is shutdown in Mode 5. The CRS has entered the Lower Mode Functional Recovery Procedure. Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the 'B' Charging pump.   
 
CANDIDATE JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 51 JPM BASIS INFORMATION TASK: 1250280201 Respond to an Inadvertent RAS TASK STANDARD: RAS reset K/A: 3.7 012 A4.02 K/A RATING: RO:
3.3 SRO: 3.4 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40AO-9ZZ17, Inadve rtent PPS-ESFAS Actuations, Rev 13 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes     APPROVAL Developed By: Alan Malley Date: 08/30/2005 Revised By: Alan Malley Date: 10/05/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations, Rev 13 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       Yes APPROVAL Developed By:     Alan Malley                   Date:   08/30/2005 Revised By:       Alan Malley                   Date:   10/05/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR           X     PLANT TESTING METHOD:                           SIMULATE                   PERFORM       X EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
51                                  Revised 9/23/08


JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 52 6. SIMULATOR SETUP:
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
: 6.       SIMULATOR SETUP:
Z. If running JS3 and JS4 together reset to IC#: 103 (For 2009 NRC exam only)
Z. If running JS3 and JS4 together reset to IC#: 103 (For 2009 NRC exam only)
If running JS3 and JS1 together reset to IC# 110 (For 2009 NRC exam only)
If running JS3 and JS1 together reset to IC# 110 (For 2009 NRC exam only)
AA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
AA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                         DESCRIPTION
: 17. None Required BB. SPECIAL INSTRUCTIONS: This JPM is designed to run with JS-4 or JS-1 for the 2009 NRC exam.
: 17.         None Required BB. SPECIAL INSTRUCTIONS:
CC. REQUIRED CONDITIONS: Ensure Charging Pump B is NOT running DD. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
* This JPM is designed to run with JS-4 or JS-1 for the 2009 NRC exam.
: 7. SPECIAL TOOLS/EQUIPMENT: Copy 40AO-9ZZ17, Inadvertent PPS Actuations, Appendix B If IC-103 is not available, then reset to IC-20. Then perform the following: imf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B) imf cmSRRP01IRRASBD2_1 (fails the RAS relay) imf RP06J1 (RAS Leg 1 blown fuse)
CC. REQUIRED CONDITIONS:
THEN dmf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B) dmf cmSRRP01IRRASBD2_1 (fails the RAS relay) dmf RP06J1 (RAS Leg 1 blown fuse) Override and close the Train B RAS Sump valves on B02. The following lights should be lit: Annunciator Window 6B2A (lower half only) Annunciator Window 6B2B (upper and lower half) The Channel B Lo RWT Level Trip and Pre-trip lights on B05 and at the PPS B cabinet Flashing light for the "Reset Actuation Trip Path 2" above the handswitch for the actuation path reset button on Channel B PPS Cabinet The following light should be out: RAS Initiation light on B05 and Channel B PPS cabinet Channel A RAS 2-4 leg actua tion light at A PPS cabinet Channel B RAS 1-3 and 2-4 act uation light at B PPS Cabinet
* Ensure Charging Pump B is NOT running DD. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
: 7. SPECIAL TOOLS/EQUIPMENT:
* Copy 40AO-9ZZ17, Inadvertent PPS Actuations, Appendix B If IC-103 is not available, then reset to IC-20. Then perform the following:
* imf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B)
* imf cmSRRP01IRRASBD2_1 (fails the RAS relay)
* imf RP06J1 (RAS Leg 1 blown fuse)
THEN
* dmf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B)
* dmf cmSRRP01IRRASBD2_1 (fails the RAS relay)
* dmf RP06J1 (RAS Leg 1 blown fuse)
* Override and close the Train B RAS Sump valves on B02.
The following lights should be lit:
* Annunciator Window 6B2A (lower half only)
* Annunciator Window 6B2B (upper and lower half)
* The Channel B Lo RWT Level Trip and Pre-trip lights on B05 and at the PPS B cabinet
* Flashing light for the Reset Actuation Trip Path 2 above the handswitch for the actuation path reset button on Channel B PPS Cabinet The following light should be out:
* RAS Initiation light on B05 and Channel B PPS cabinet
* Channel A RAS 2-4 leg actuation light at A PPS cabinet
* Channel B RAS 1-3 and 2-4 actuation light at B PPS Cabinet 52


JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 53 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
(For 100% power Initial Conditions)
* Unit 1 is at 100% power.
* An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
* The power supply problem has been corrected.
* The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.
(For low power Initial Conditions)
* Unit 1 is at in Mode 5 on Shutdown Cooling.
* An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
* All SDC valves have been realigned as needed for SDC.
* The power supply problem has been corrected.
* The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.
53


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
INITIATING CUE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
54


(For 100% power Initial Conditions)
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
Unit 1 is at 100% power. An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem. The power supply problem has been corrected. The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.  
STEP                            CUE                    STANDARD
(For low power Initial Conditions)
: 1.     Step 1 of Appendix B of 40AO-                              Examinee marks step as N/A.
Unit 1 is at in Mode 5 on Shutdown Cooling. An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem. All SDC valves have been realigned as needed for SDC. The power supply problem has been corrected. The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.  
9ZZ17:
IF PPS-ESFAS actuation was caused by a failure to reset the SG or PZR                        Examinee may perform lamp checks Press variable setpoints during a                          to ensure no other parameters are controlled cooldown                                        tripped.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                    STANDARD
: 2.     Step 2 and 2.1 of Appendix B of                            The examinee determines channel B 40AO-9ZZ17:                                                LO RWT LEVEL is LIT and resets the Channel B Trip Lamp by pushing Check the Trip lamps (B05) for the                          the reset pushbutton.
affected PPS-ESFAS actuation input parameters on all PPS channels satisfy ONE of the following:
* NOT lit
* Bypassed SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                    STANDARD
: 3.     Step 3 of Appendix B of 40AO-                              RAS Initiation lamps (B05) are NOT 9ZZ17:                                                      lit, so examinee goes to contingency step 3.2.
Check the affected PPS-ESFAS actuation Initiation Relay lamps lit                        Step 3.1 should be marked N/A.
(B05) on all PPS channels.
SAT / UNSAT Comments (required for UNSAT):
55


JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 54  INFORMATION FOR EVALUATOR'S USE:
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                            CUE                    STANDARD
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 4.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  55 JPM START TIME:
* Step 3.2 of Appendix B of 40AO-                           Examinee obtains RPS/ESFAS reset 9ZZ17:                                                     key and resets RAS initiation pathways on Channel B. (Places Perform the following for any de-                         keylock switch to UNLK position energized PPS-ESFAS Initiation                             and then pushes RAS reset Paths:                                                     pushbutton).
STEP CUE STANDARD 1. Step 1 of Appendix B of 40AO-9ZZ17: IF PPS-ESFAS actuation was caused by a failure to reset the SG or PZR Press variable setpoints during a controlled cooldown-Examinee marks step as N/A.
* Reset the affected initiation path (PPS Cabinet)
 
* Check the affected Initiation Signal lamps lit (PPS Status Panels above the PPS Cabinets).
Examinee may perform lamp checks to ensure no other parameters are tripped. SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
 
STEP                           CUE                   STANDARD
STEP CUE STANDARD 2. Step 2 and 2.1 of Appendix B of 40AO-9ZZ17:
: 5.     Step 4 of Appendix B of 40AO-                              The examinee determines RAS leg 1-9ZZ17:                                                     3 and 2-4 are NOT lit.
Check the Trip lamps (B05) for the affected PPS-ESFAS actuation input parameters on all PPS channels satisfy ONE of the following:  NOT lit  Bypassed    The examinee determines channel B LO RWT LEVEL is LIT and resets the Channel B Trip Lamp by pushing the reset pushbutton.
Check the actuated PPS-ESFAS leg 1-3 and leg 2-4 lamps lit for PPS actuation signals A and B (PPS Status Panels above the PPS Cabinets).
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
 
56
STEP CUE STANDARD 3. Step 3 of Appendix B of 40AO-9ZZ17: Check the affected PPS-ESFAS actuation Initiation Relay lamps lit (B05) on all PPS channels. RAS Initiation lamps (B05) are NOT lit, so examinee goes to contingency step 3.2. Step 3.1 should be marked N/A.
 
SAT / UNSAT Comments (required for UNSAT):
 
JS-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  56  STEP CUE STANDARD 4.
* Step 3.2 of Appendix B of 40AO-9ZZ17: Perform the following for any de-energized PPS-ESFAS Initiation  
 
Paths: Reset the affected initiation path (PPS Cabinet) Check the affected Initiation Signal lamps lit (PPS Status  
 
Panels above the PPS Cabinets). Examinee obtains RPS/ESFAS reset key and resets RAS initiation
 
pathways on Channel B. (Places keylock switch to UNLK position and then pushes RAS reset pushbutton).
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 5. Step 4 of Appendix B of 40AO-9ZZ17: Check the actuated PPS-ESFAS leg 1-3 and leg 2-4 lamps lit for PPS  
 
actuation signals A and B (PPS  
 
Status Panels above the PPS Cabinets). The examinee determines RAS leg 1-3 and 2-4 are NOT lit.
 
SAT / UNSAT Comments (required for UNSAT):  
 
JS-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  57  STEP CUE STANDARD 6.
* Step 4.1 of Appendix B of 40AO-9ZZ17: Perform the following:  Reset the actuation path for the RAS actuation (Aux Relay
 
cabinet)  Check the red "ON" light lit for the affected PPS-ESFAS actuation (Aux Relay Cabinet).
When this step is completed provide the following cue:
 
The CRS will have another operator complete the remainder
 
of this procedure. This JPM is complete. The examinee resets the RAS actuation path in the "A" and "B" Aux Relay cabinets. Only Channel
 
'B' needs to be reset.
EVALUATOR NOTE:  Only one pushbutton needs to be depressed in
 
each ESFAS Train Cabinet to completely reset the RAS initiation logic. EVALUATOR NOTE:  Only resetting the actuation path is critical
 
for this step.
SAT / UNSAT Comments (required for UNSAT):


JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                          STANDARD
: 6.
* Step 4.1 of Appendix B of 40AO-      When this step is completed      The examinee resets the RAS 9ZZ17:                              provide the following cue:      actuation path in the A and B Aux Relay cabinets. Only Channel Perform the following:                                                B needs to be reset.
* Reset the actuation path for the RAS actuation (Aux Relay        The CRS will have another        EVALUATOR NOTE: Only one cabinet)                        operator complete the remainder  pushbutton needs to be depressed in
* Check the red ON light lit for of this procedure.              each ESFAS Train Cabinet to the affected PPS-ESFAS                                            completely reset the RAS initiation actuation (Aux Relay Cabinet).                                    logic.
This JPM is complete.            EVALUATOR NOTE: Only resetting the actuation path is critical for this step.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 57


NORMAL TERMINATION POINT
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 1          08/07/2009            6        Updated format 2          10/05/2009            6        Incorporated comments from the NRC validation.
REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 31. Vendor reference document upgrade
: 32. Plant modification (include number)
: 33. Procedure upgrade
: 34. Internal or External Agency Commitment (indicate item number)
: 35. Technical Specification Change (indicate amendment number)
: 36. Other (explain in comments) 58


JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 58  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 1 08/07/2009 6 Updated format 2 10/05/2009 6 Incorporated comments from the NRC validation.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
(For 100% power Initial Conditions)
* Unit 1 is at 100% power.
* An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
* The power supply problem has been corrected.
* The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.
CANDIDATE 59


consecutively in each revision.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 31. Vendor reference document upgrade
(For low power Initial Conditions)
: 32. Plant modification (include number)
* Unit 1 is at in Mode 5 on Shutdown Cooling.
: 33. Procedure upgrade
* An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
: 34. Internal or External Agency Commitment (indicate item number)
* All SDC valves have been realigned as needed for SDC.
: 35. Technical Specification Change (indicate amendment number)
* The power supply problem has been corrected.
: 36. Other (explain in comments)
* The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.
JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 59 INITIAL CONDITIONS INITIATING CUE: (For 100% power Initial Conditions)
CANDIDATE 60
Unit 1 is at 100% power. An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem. The power supply problem has been corrected. The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.  


CANDIDATE JS-3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  60 INITIAL CONDITIONS INITIATING CUE: (For low power Initial Conditions)
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 0500010401 Initiate a containment vent TASK STANDARD: Containment purge system in operation in the VENT mode.
Unit 1 is at in Mode 5 on Shutdown Cooling. An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem. All SDC valves have been realigned as needed for SDC. The power supply problem has been corrected. The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.
K/A: 3.8 029 A2.03                                 K/A RATING:         RO:   2.7   SRO:   3.1 K/A:                                               K/A RATING:         RO:         SRO APPLICABLE POSITION(S):             RO             VALIDATION TIME:           15 minutes
 
CANDIDATE JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 61 JPM BASIS INFORMATION TASK: 0500010401 Initiate a containment vent TASK STANDARD: Containment purge system in operation in the VENT mode.
K/A: 3.8 029 A2.03 K/A RATING: RO:
2.7 SRO: 3.1 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes  


==REFERENCES:==
==REFERENCES:==
40OP-9CP01, Containment Purge System (Rev 18) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: John Dedon Date: 04/04/2004 Revised By: Alan Malley Date: 10/05/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40OP-9CP01, Containment Purge System (Rev 18)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR             X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     John Dedon                     Date:   04/04/2004 Revised By:       Alan Malley                   Date:   10/05/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR           X       PLANT TESTING METHOD:                           SIMULATE                   PERFORM       X EVALUATION Examinee Name:                                                     Date:
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
61                                    Revised 9/23/08


JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 62 7. SIMULATOR SETUP:
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
EE. IC#: 103 (For 2009 NRC exam only)
: 7.       SIMULATOR SETUP:
FF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
EE. IC#: 103 (For 2009 NRC exam only)
: 18. If IC-103 is not available, the reset to IC-20 and perform the following: Mrf rfCH04 OPEN (opens IA-BV45) Mrf rfIP38 1.3 (puts containmen t pressure at 1.3 psig)
FF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                         DESCRIPTION
GG. SPECIAL INSTRUCTIONS: This JPM is set to run with JS3 for the 2009 NRC exam HH. REQUIRED CONDITIONS: Containment pressure ~ 1.3 psig.
: 18.                                       If IC-103 is not available, the reset to IC-20 and perform the following:
II. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
* Mrf rfCH04 OPEN (opens IA-BV45)
: 8. SPECIAL TOOLS/EQUIPMENT: Copy of 40OP-9CP01, Containment Purge System, Section 5.0, Rev 18 JJ. COMMUNICATIONS DURING JPM:
* Mrf rfIP38 1.3 (puts containment pressure at 1.3 psig)
STEP COMMAND CUE 1 After examinee directs AO to close IA-VB47 provide the following Cue:
GG. SPECIAL INSTRUCTIONS:
IA-VB47, Instrument Air Supply valve to the Containment Power Access Purge Isolation Valve CP-UV4A, is closed. (In simulator setup) 2 After examinee directs AO to open IA-VB45 provide the following Cue:
* This JPM is set to run with JS3 for the 2009 NRC exam HH. REQUIRED CONDITIONS:
IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43 , is open. (In simulator setup) 3 After examinee directs AO to open/check open CP-V024 and to close/check closed CP-V023. CP-V024, Isolation between Refueling Purge Duct and RU-34, is open CP-V023, isolation between Refueling Purge Duct and RU-34, is closed 4 If examinee asks Effluent Tech if ST for RU-37 and RU-38 is current Shiftly Surveillance Test for RU-37 and RU-38 is current. 10 If the examinee sends an Area Operator to check the positions of M03 and/or M06 report the following as appropriate:
* Containment pressure ~ 1.3 psig.
M03 damper is closed  M06 damper is open
II. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
: 8. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40OP-9CP01, Containment Purge System, Section 5.0, Rev 18 JJ. COMMUNICATIONS DURING JPM:
STEP                     COMMAND                                                 CUE 1       After examinee directs AO to close IA-       IA-VB47, Instrument Air Supply valve to the VB47 provide the following Cue:              Containment Power Access Purge Isolation Valve CP-UV4A, is closed. (In simulator setup) 2       After examinee directs AO to open IA-       IA-VB45, Air Supply to CPB-UV-5B and CP-PV-VB45 provide the following Cue:              43, is open. (In simulator setup) 3       After examinee directs AO to
* CP-V024, Isolation between Refueling open/check open CP-V024 and to                     Purge Duct and RU-34, is open close/check closed CP-V023.
* CP-V023, isolation between Refueling Purge Duct and RU-34, is closed 4       If examinee asks Effluent Tech if ST for    Shiftly Surveillance Test for RU-37 and RU-38 is RU-37 and RU-38 is current                  current.
10       If the examinee sends an Area Operator
* M03 damper is closed to check the positions of M03 and/or
* M06 damper is open M06 report the following as appropriate:
62


JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 63 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
 
IN PLANT JPMs ONLY
IN PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL JPMs You may use any source of information normally available.
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
INITIATING CUE:  
* Inform the control room staff of any discovered deficiencies.
 
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System. An area operator is standing by in the RCA to assist you. RU-34 is available. Authorization has been given to break ZZ06 locks as needed. Venting of Containment is for pressure reduction All prerequisites are complete. The Effluent Release Permit is for today's date from 0700 to 2400 and is approved. The shiftly Surveillance Test for RU-37 and RU-38 is current.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System.
* An area operator is standing by in the RCA to assist you.
* RU-34 is available.
* Authorization has been given to break ZZ06 locks as needed.
* Venting of Containment is for pressure reduction
* All prerequisites are complete.
* The Effluent Release Permit is for todays date from 0700 to 2400 and is approved.
* The shiftly Surveillance Test for RU-37 and RU-38 is current.
INFORMATION FOR EVALUATOR'S USE:
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard.
* Denotes Critical Step
JS-4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 64 Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
JS-4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  65 JPM START TIME:
* Any step marked UNSAT requires comments.
STEP CUE STANDARD 1. Step 5.3.1 of 40OP-9CP01:
* If this is the first JPM of the set then ensure the examinee has been briefed.
Ensure IA-VB47, Instrument Air Supply valve to the Containment
* Step sequence is not critical unless noted or will prevent achieving the task standard.
63


Power Access Purge Isolation Valve
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.          Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
64


CP-UV4A is closed. Simulator driver will report IA-VB47 is closed Examinee directs AO to verify IA-VB47 is closed.
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
SAT / UNSAT Comments (required for UNSAT):  
STEP                              CUE                            STANDARD
: 1.      Step 5.3.1 of 40OP-9CP01:          Simulator driver will report IA-VB47 Examinee directs AO to verify IA-is closed                            VB47 is closed.
Ensure IA-VB47, Instrument Air Supply valve to the Containment Power Access Purge Isolation Valve CP-UV4A is closed.
SAT / UNSAT Comments (required for UNSAT):
STEP                              CUE                            STANDARD
: 2.      Step 5.3.2 of 40OP-9CP01:          Simulator driver will report IA-   Examinee directs AO to unlock and VB45 is open.                        open IA-VB45.
Unlock and open IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43 per 40AC-0ZZ06.
SAT / UNSAT Comments (required for UNSAT):
STEP                              CUE                            STANDARD
: 3.      Step 5.3.3 of 40OP-9CP01:          Simulator driver will report CP-V024 Examinee directs AO to open/check is open and CP-V023 is closed..      open CP-V024 and to close/check IF RU-34 is available, THEN                                            closed CP-V023.
perform BOTH of the following to place it in service:
: 2. Ensure CP-V024 (isolation between Power Access Purge Duct and RU-34) is open.
: 3. Ensure CP-V023 (isolation between Refueling Purge Duct and RU-34) is closed.
SAT / UNSAT Comments (required for UNSAT):
65


STEP CUE STANDARD 2. Step 5.3.2 of 40OP-9CP01:
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                   CUE                           STANDARD
Unlock and open IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43 per 40AC-0ZZ06. Simulator driver will report IA-VB45 is open. Examinee directs AO to unlock and open IA-VB45.
: 4.     Step 5.3.4 of 40OP-9CP01:             If asked, the simulator driver will Examinee signs off this step from provide the cue that the ST for RU- information provided in the Initiating Direct the RMS/Effluents technician  37 and 38 is current. This info was CUE.
SAT / UNSAT Comments (required for UNSAT):  
to ensure the Shiftly ST (per 74ST-  in the initiating cue.
9SQ07) as required by SR 3.3.8.1 is current on RU37 and/or RU-38 prior to each system startup.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                            STANDARD
: 5.      Step 5.3.5 of 40OP-9CP01:                                                The examinee N/As this step since the vent is for none of the reasons IF venting Containment to perform                                        listed.
ANY of the following:
* Section XI testing of CP valves
* Starting Power Access Purge
* Starting Refueling Purge
* PAL testing per 73ST-9CL05, Containment Airlock Leakage Rate Test.
THEN notify security that Containment will be vented to less than +0.25 psig.
SAT / UNSAT Comments (required for UNSAT):
66


STEP CUE STANDARD 3. Step 5.3.3 of 40OP-9CP01:
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                   CUE                         STANDARD
IF RU-34 is available, THEN perform BOTH of the following to place it in service:
: 6.     NOTE before step 5.3.6                 Provide this cue on the floor. The examinee may decide to set an An ERFDADS alarm may be                                                 ERFDADS alarm. If so, give the inserted to alarm at +0.3 psig to alert If examinee decides to set an    cue. The examinee may decide to set the operator not to go below +0.25     ERFDADS alarm provide the       an ERFDADS alarm. If so, give the psig.                                  following Cue:                   Cue.
: 2. Ensure CP-V024 (isolation between Power Access Purge Duct and RU-34) is open.
Another operator will set the ERFDADS alarm. The CRS directs you to continue with the procedure.
: 3. Ensure CP-V023 (isolation between Refueling Purge Duct and RU-34) is closed. Simulator driver will report CP-V024 is open and CP-V023 is closed..
SAT / UNSAT Comments (required for UNSAT):
Examinee directs AO to open/check open CP-V024 and to close/check closed CP-V023.
STEP                                   CUE                         STANDARD
 
: 7.     Step 5.3.6 of 40OP-9CP01:                                               The examinee initials this step and continues.
SAT / UNSAT Comments (required for UNSAT):
 
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 66  STEP CUE STANDARD 4. Step 5.3.4 of 40OP-9CP01:
Direct the RMS/Effluents technician to ensure the Shiftly ST (per 74ST-9SQ07) as required by SR 3.3.8.1 is current on RU37 and/or RU-38 prior to each system startup. If asked, the simulator driver will provide the cue that the ST for RU-37 and 38 is current. This info was in the initiating cue. Examinee signs off this step from information provided in the Initiating
 
CUE. SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 5. Step 5.3.5 of 40OP-9CP01:
IF venting Containment to perform ANY of the following:  Section XI testing of CP valves  Starting Power Access Purge  Starting Refueling Purge  PAL testing per 73ST-9CL05, Containment Airlock Leakage
 
Rate Test.
THEN notify security that Containment will be vented to less than +0.25 psig. The examinee N/As this step since the vent is for none of the reasons listed. SAT / UNSAT Comments (required for UNSAT):  
 
JS-4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  67  STEP CUE STANDARD 6. NOTE before step 5.3.6 An ERFDADS alarm may be inserted to alarm at +0.3 psig to alert the operator not to go below +0.25 psig. Provide this cue on the floor.
If examinee decides to set an ERFDADS alarm provide the following Cue: Another operator will set the ERFDADS alarm. The CRS  
 
directs you to continue with the  
 
procedure.
The examinee may decide to set an ERFDADS alarm. If so, give the cue. The examinee may decide to set an ERFDADS alarm. If so, give the Cue. SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 7. Step 5.3.6 of 40OP-9CP01:
IF venting Containment is only for pressure reduction, THEN do not vent less than +0.25 psig.
IF venting Containment is only for pressure reduction, THEN do not vent less than +0.25 psig.
The examinee initials this step and continues.
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):  
STEP                                   CUE                         STANDARD
 
: 8.     Step 5.3.7 of 40OP-9CP01:                                               Examinee N/As this step.
STEP CUE STANDARD 8. Step 5.3.7 of 40OP-9CP01:
IF venting Containment in support of PAL testing per 73ST-9CL05, Containment Airlock Leakage Rate Test, THEN vent Containment as close to 0.1 psig, as practical.
IF venting Containment in support of PAL testing per 73ST-9CL05, Containment Airlock Leakage Rate Test, THEN vent Containment as  
SAT / UNSAT Comments (required for UNSAT):
 
67
close to 0.1 psig, as practical. Examinee N/As this step.
SAT / UNSAT Comments (required for UNSAT):  


JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 68  STEP CUE STANDARD 9.
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                   CUE                                 STANDARD
* Step 5.3.8 of 40OP-9CP01:
: 9.
* Step 5.3.8 of 40OP-9CP01:                                                     The examinee places CPN-HS-1 to VENT.
Place CPN-HS-1, Containment Purge Mode Selector Switch, in the VENT position to start venting containment.
Place CPN-HS-1, Containment Purge Mode Selector Switch, in the VENT position to start venting containment.
The examinee places CPN-HS-1 to VENT. SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
STEP                                   CUE                                 STANDARD
STEP CUE STANDARD 10. Step 5.3.9 of 40OP-9CP01:
: 10. Step 5.3.9 of 40OP-9CP01:             If requested, the simulator driver will The examinee ensures CPN-M06 provide the following cue:              opens.
Ensure Damper CPN-M06 opens.
Ensure Damper CPN-M06 opens.
If requested, the simulator driver will provide the following cue:  M03 damper is closed M06 damper is open The examinee ensures CPN-M06 opens. This will cause dual indication for the position of M03/M06. The examinee may send an Area Operator to check the position locally.
* M03 damper is closed           This will cause dual indication for
SAT / UNSAT Comments (required for UNSAT):  
* M06 damper is open            the position of M03/M06. The examinee may send an Area Operator to check the position locally.
 
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 11.
STEP                                   CUE                                 STANDARD
* Step 5.3.10 of 40OP-9CP01:
: 11.
Place CPA-HS-4, Containment Power Access Purge Upstream Isolation Valve CP-UV4B to the OPEN position. The examinee places CPA-HS-4 to the OPEN position.
* Step 5.3.10 of 40OP-9CP01:                                                     The examinee places CPA-HS-4 to the OPEN position.
NOTE: Per the note preceding this step, dual indication will be received on HS-4 because UV4A remains
Place CPA-HS-4, Containment Power Access Purge Upstream                                                   NOTE: Per the note preceding this Isolation Valve CP-UV4B to the                                                step, dual indication will be received OPEN position.                                                                on HS-4 because UV4A remains closed.
 
SAT / UNSAT Comments (required for UNSAT):
closed. SAT / UNSAT Comments (required for UNSAT):
68
 
JS-4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  69  STEP CUE STANDARD 12.
* Step 5.3.11 of 40OP-9CP01:
Place CPB-HS-5, Containment Power Access Purge Upstream Isolation Valve CP-UV5B to the OPEN position.
When the operator completes this step provide the following cue:  Another operator will complete the rest of this procedure. This JPM is complete. The examinee places CPA-HS-5 to the OPEN position.
NOTE: Per the note preceding this step, dual indication will be received on HS-4 because UV5A remains  
 
closed. SAT / UNSAT Comments (required for UNSAT):  


JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                              CUE                            STANDARD
: 12.
* Step 5.3.11 of 40OP-9CP01:        When the operator completes this    The examinee places CPA-HS-5 to step provide the following cue:    the OPEN position.
Place CPB-HS-5, Containment Power Access Purge Upstream      Another operator will complete the  NOTE: Per the note preceding this Isolation Valve CP-UV5B to the    rest of this procedure.            step, dual indication will be received OPEN position.                                                        on HS-4 because UV5A remains This JPM is complete.              closed.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 69


NORMAL TERMINATION POINT
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 1          03/10/2009            6        Updated format 2          10/05/2009            6        Incorporated comments from the NRC validation team REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 37. Vendor reference document upgrade
: 38. Plant modification (include number)
: 39. Procedure upgrade
: 40. Internal or External Agency Commitment (indicate item number)
: 41. Technical Specification Change (indicate amendment number)
: 42. Other (explain in comments) 70


JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 70  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 1 03/10/2009 6 Updated format 2 10/05/2009 6 Incorporated comments from the NRC validation team REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:
* The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System.
* An area operator is standing by in the RCA to assist you.
* RU-34 is available.
* Authorization has been given to break ZZ06 locks as needed.
* Venting of Containment is for pressure reduction
* All prerequisites are complete.
* The Effluent Release Permit is for todays date from 0700 to 2400 and is approved.
* The shiftly Surveillance Test for RU-37 and RU-38 is current.
CANDIDATE 71


consecutively in each revision.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1140010401, lineup the steam bypass control system for normal operation TASK STANDARD: The not in operate lights are extinguished; SBCS abnormal alarm and SBCS condenser interlock alarms are reset.
: 37. Vendor reference document upgrade
K/A: 3.4-041-A4.08                                 K/A RATING:         RO:   3.0   SRO: 3.1 K/A:                                               K/A RATING:         RO:         SRO APPLICABLE POSITION(S):             RO             VALIDATION TIME:           10 minutes
: 38. Plant modification (include number)
: 39. Procedure upgrade
: 40. Internal or External Agency Commitment (indicate item number)
: 41. Technical Specification Change (indicate amendment number)
: 42. Other (explain in comments)
JS-4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  71 INITIAL CONDITIONS CANDIDATE 
 
INITIATING CUE:
The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System. An area operator is standing by in the RCA to assist you. RU-34 is available. Authorization has been given to break ZZ06 locks as needed. Venting of Containment is for pressure reduction  All prerequisites are complete. The Effluent Release Permit is for today's date from 0700 to 2400 and is approved. The shiftly Surveillance Test for RU-37 and RU-38 is current.
 
CANDIDATE JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 72 JPM BASIS INFORMATION TASK: 1140010401, lineup the steam bypass control system for normal operation TASK STANDARD: The "not in operate" lights are extinguished; SBCS abnormal alarm and SBCS condenser interlock alarms are reset. K/A: 3.4-041-A4.08 K/A RATING: RO:
3.0 SRO: 3.1 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40OP-9SF05, Operation of Steam Bypass Control System (Rev 20) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: John Dedon Date: 11/18/2003 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40OP-9SF05, Operation of Steam Bypass Control System (Rev 20)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR             X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)         No APPROVAL Developed By:     John Dedon                     Date:     11/18/2003 Revised By:       Alan Malley                     Date:     04/16/2009 Technical Review                                   Operations Approval E-Plan Review                   N/A               Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:                 SIMULATOR           X       PLANT TESTING METHOD:                             SIMULATE                     PERFORM       X EVALUATION Examinee Name:                                                       Date:
Evaluator Name:
Time to complete:                 Minutes           GRADE (Circle   One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
72                                    Revised 9/23/08


JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 73 8. SIMULATOR SETUP:
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
A. IC#: 104 (For 2009 NRC exam only)
: 8.       SIMULATOR SETUP:
B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
A. IC#: 104 (For 2009 NRC exam only)
: 19. None   KK. SPECIAL INSTRUCTIONS: This JPM is set to run with JS6 for the 2009 NRC exam LL. REQUIRED CONDITIONS: The following RED LEDs will be lit at the SBCS test panel:
B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                         DESCRIPTION
o Emergency Off o Both "Condenser Interlocks" o Both "Not in Operate" o AMI MM. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
: 19.       None KK. SPECIAL INSTRUCTIONS:
: 9. SPECIAL TOOLS/EQUIPMENT: Copy of 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C, Rev 20 If IC-104 is unavailable, reset to IC-20 and perform the following: On the SBCS Test panel:
* This JPM is set to run with JS6 for the 2009 NRC exam LL. REQUIRED CONDITIONS:
o Press the "Emergency Off" pushbutton o Place the "System Mode Selection" switch to the "TEST" position Place the SBCS Master Cont roller on B06 in "Manual" o Emergency Off o Both "Condenser Interlocks" o Both "Not in Operate" o AMI JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 74 
* The following RED LEDs will be lit at the SBCS test panel:
o   Emergency Off o   Both Condenser Interlocks o   Both Not in Operate o   AMI MM. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
: 9. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C, Rev 20 If IC-104 is unavailable, reset to IC-20 and perform the following:
* On the SBCS Test panel:
o Press the Emergency Off pushbutton o Place the System Mode Selection switch to the TEST position
* Place the SBCS Master Controller on B06 in Manual o Emergency Off o Both Condenser Interlocks o Both Not in Operate o   AMI 73


TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to:
* Reconnect and reset the Steam Bypass Control System.
74


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
INITIATING CUE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
75


The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to: Reconnect and reset the Steam Bypass Control System.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                          CUE                    STANDARD
: 1.      Step 1 of Appendix C:                                      Examinee marks this step N/A and goes to step 2.0 to reconnect and IF the SBCS needs to be reset,                              reset SBCS.
THEN perform steps 2.9 through 2.15.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 2.      Step 2.1 of Appendix C:                                    Verifies both RED lights are lit.
Check at least 1 Not In Operate light is lit on the SBCS test panel.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 3.
* Step 2.2 of Appendix C:                                     Examinee depresses the "EMERGENCY OFF" pushbutton Depress and release the                                    (no change in status of SBCS Test "EMERGENCY OFF" pushbutton                                  Panel).
on the SBCS test panel.
SAT / UNSAT Comments (required for UNSAT):
76


JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 75  
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                CUE                            STANDARD
: 4.      Step 2.3 of Appendix C:              When the examinee opens the door    The examinee ensures the EMERG to the cabinet provide the          OFF backlight is illuminated.
Ensure BOTH of the following:        following CUE: The power supply lights in SFN-CO3Y, nest 4, 5, 7
* Check the EMERG OFF                                              NOTE: The power supply lights are are not lit.
backlight is illuminated.                                        not modeled in the simulator so it is
* Check that the power supply                                      necessary to give the cue.
lights (-15,+15) in SFN-C03Y, nests 4, 5 and 7 are (These lights are not modeled in the not illuminated.            simulator).
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 5.
* Step 2.4 of Appendix C:                                                  The examinee places the System Mode Select switch in Place the System Mode Selection                                          "DISCONNECT".
switch in "DISCONNECT".
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 6.
* Step 2.5 of Appendix C:                                                  The examinee depresses and releases Depress and release the Light and                                        the LIGHT AND TIMER TEST Timer test button on the SBCS test                                        pushbutton.
panel.
SAT / UNSAT Comments (required for UNSAT):
77


INFORMATION FOR EVALUATOR'S USE:
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                          CUE                    STANDARD
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 7.      Step 2.6 of Appendix C:                                  The NOT IN OPERATE lights 1 and Check that the Not In Operate 1                        2 will extinguish then come back and 2 lights extinguish and then                         ON in 30 seconds.
JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  76 JPM START TIME:
come back on in approximately 30 seconds.
STEP CUE STANDARD 1. Step 1 of Appendix C:
SAT / UNSAT Comments (required for UNSAT):
IF the SBCS needs to be reset, THEN perform steps 2.9 through 2.15. Examinee marks this step N/A and goes to step 2.0 to reconnect and
STEP                         CUE                   STANDARD
: 8.
* Step 2.7 of Appendix C:                                   The examinee places the System Place the System Mode Selection                          Mode Selection Switch in switch in the Operate position on                      "OPERATE".
the SBCS Test Panel SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 9.     Step 2.8 of Appendix C:                                  The NOT IN OPERATE lights will Ensure that the Not In Operate 1                        extinguish in 30 seconds.
and 2 lights extinguish in approximately 30 seconds.
SAT / UNSAT Comments (required for UNSAT):
78


reset SBCS.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                          CUE                    STANDARD
SAT / UNSAT Comments (required for UNSAT):  
: 10. Step 2.9 of Appendix C:                                    The examinee ensures the SBCS Ensure that the SBCS Master                                Master Controller in "MANUAL" Controller is in the `Manual' mode                        mode with backlight illuminated.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 11. Step 2.10 of Appendix C:                                  The examinee ensures zero output on Ensure that the output of the SBCS                        SBCS controller.
Master Controller is zero.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 12.
* Step 2.11 of Appendix C:                                  Switch SGN-HS-1010 to "RESET" Take SGN-HS-1010 to RESET, to                            (spring return to neutral).
reset the SBCS emergency off.
NOTE: The following alarms should clear:
* SBCS ABNORMAL
* SBCS COND INTLK
* NSSS SBCS RACK U POWER
* NSSS SBCS RACK Y POWER SAT / UNSAT Comments (required for UNSAT):
79


STEP CUE STANDARD 2. Step 2.1 of Appendix C:
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                           CUE                 STANDARD
Check at least 1 "Not In Operate" light is lit on the SBCS test panel. Verifies both RED lights are lit.
: 13. Step 2.12 of Appendix C:                                 Turb Bypass Demand Alarm is not in IF the Turb Bypass Demand Alarm                           alarm.
SAT / UNSAT Comments (required for UNSAT):
is received, THEN ensure that the output of the SBCS Master Controller is zero.
 
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 3.
STEP                           CUE                 STANDARD
* Step 2.2 of Appendix C:
: 14. Step 2.13 of Appendix C:                                 Verify "SBCS ABNORMAL" alarm Ensure the `SBCS Abnormal' alarm                         clear.
Depress and release the "EMERGENCY OFF" pushbutton on the SBCS test panel. Examinee depresses the "EMERGENCY OFF" pushbutton (no change in status of SBCS Test
(Window 6A16A) is clear if condenser pressure is less than 5 HgA.
 
SAT / UNSAT Comments (required for UNSAT):
Panel). SAT / UNSAT Comments (required for UNSAT):
STEP                           CUE                 STANDARD
 
: 15. Step 2.14 of Appendix C:                                 Verify "SBCS COND INTLK" alarm Ensure the SBCS COND INLK                               clear.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 77  STEP CUE STANDARD 4. Step 2.3 of Appendix C:
alarm (Window 6A16B) is clear.
Ensure BOTH of the following: Check the EMERG OFF backlight is illuminated. Check that the power supply lights (-15,+15) in SFN-C03Y, nests 4, 5 and 7 are not illuminated.
SAT / UNSAT Comments (required for UNSAT):
When the examinee opens the door to the cabinet provide the
80
 
following CUE: The power supply lights in SFN-CO3Y, nest 4, 5, 7
 
are not lit.
(These lights are not modeled in the simulator). The examinee ensures the EMERG OFF backlight is illuminated.
NOTE:  The power supply lights are not modeled in the simulator so it is
 
necessary to give the cue.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 5.
* Step 2.4 of Appendix C:
Place the System Mode Selection switch in "DISCONNECT". The examinee places the System Mode Select switch in "DISCONNECT".
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 6.
* Step 2.5 of Appendix C:
Depress and release the Light and Timer test button on the SBCS test panel. The examinee depresses and releases the LIGHT AND TIMER TEST pushbutton.
SAT / UNSAT Comments (required for UNSAT):
 
JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  78  STEP CUE STANDARD 7. Step 2.6 of Appendix C:
Check that the "Not In Operate" 1 and 2 lights extinguish and then come back on in approximately 30
 
seconds. The NOT IN OPERATE lights 1 and 2 will extinguish then come back "ON" in 30 seconds.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 8.
* Step 2.7 of Appendix C:
Place the System Mode Selection switch in the "Operate" position on the SBCS Test Panel  The examinee places the System Mode Selection Switch in "OPERATE".
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 9. Step 2.8 of Appendix C:
Ensure that the "Not In Operate" 1 and 2 lights extinguish in approximately 30 seconds. The NOT IN OPERATE lights will extinguish in 30 seconds.
SAT / UNSAT Comments (required for UNSAT):
 
JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  79  STEP CUE STANDARD 10. Step 2.9 of Appendix C:
Ensure that the SBCS Master Controller is in the `Manual' mode The examinee ensures the SBCS Master Controller in "MANUAL" mode with backlight illuminated.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 11. Step 2.10 of Appendix C:
Ensure that the output of the SBCS Master Controller is zero. The examinee ensures zero output on SBCS controller.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 12.
* Step 2.11 of Appendix C:
Take SGN-HS-1010 to "RESET, to reset the SBCS emergency off. Switch SGN-HS-1010 to "RESET" (spring return to neutral).
NOTE: The following alarms should clear:  SBCS ABNORMAL  SBCS COND INTLK  NSSS SBCS RACK U POWER  NSSS SBCS RACK Y POWER SAT / UNSAT Comments (required for UNSAT):
 
JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  80  STEP CUE STANDARD 13. Step 2.12 of Appendix C:
IF the Turb Bypass Demand Alarm is received, THEN ensure that the output of the SBCS Master Controller is zero. Turb Bypass Demand Alarm is not in alarm. SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 14. Step 2.13 of Appendix C:
Ensure the `SBCS Abnormal' alarm (Window 6A16A) is clear if condenser pressure is less than 5"
 
HgA. Verify "SBCS ABNORMAL" alarm clear. SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 15. Step 2.14 of Appendix C:
Ensure the "SBCS COND INLK" alarm (Window 6A16B) is clear. Verify "SBCS COND INTLK" alarm clear. SAT / UNSAT Comments (required for UNSAT):  
 
JS-5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  81  STEP CUE STANDARD 16. Step 2.15 of Appendix C:
GO TO ONE of the following to place the BCS Master Controller in the desired mode of operation. Section 4.3, Lineup of the SBCS for Normal Operation. Section 4.4, Shifting Master Controller Modes Another operator will lineup the SBCS.
This JPM is complete.
SAT / UNSAT Comments (required for UNSAT):


JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                              CUE                        STANDARD
: 16. Step 2.15 of Appendix C:            Another operator will lineup the GO TO ONE of the following to      SBCS.
place the BCS Master Controller in the desired mode of operation.
* Section 4.3, Lineup of the    This JPM is complete.
SBCS for Normal Operation.
* Section 4.4, Shifting Master Controller Modes SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 81


NORMAL TERMINATION POINT
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                               COMMENTS 2           04/16/2009           6         Changed format REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
 
: 43. Vendor reference document upgrade
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 82  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 2 04/16/2009 6 Changed format                                             REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
: 44. Plant modification (include number)
: 45. Procedure upgrade
: 46. Internal or External Agency Commitment (indicate item number)
: 47. Technical Specification Change (indicate amendment number)
: 48. Other (explain in comments) 82


consecutively in each revision.
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:
: 43. Vendor reference document upgrade
The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to:
: 44. Plant modification (include number)
* Reconnect and reset the Steam Bypass Control System.
: 45. Procedure upgrade
CANDIDATE 83
: 46. Internal or External Agency Commitment (indicate item number)
: 47. Technical Specification Change (indicate amendment number)
: 48. Other (explain in comments)
JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 83 INITIAL CONDITIONS  


CANDIDATE INITIATING CUE:
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250370201, Perform actions for loss of letdown.
The Steam Bypass Control System has b een disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to:  Reconnect and reset the Steam Bypass Control System.
TASK STANDARD: All charging pumps are stopped and CHB-UV-255 closed K/A: 3.3.2-004-A2.07                               K/A RATING:       RO:   3.4   SRO:   3.7 K/A:                                               K/A RATING:       RO:         SRO APPLICABLE POSITION(S):             RO             VALIDATION TIME:         10 minutes
CANDIDATE JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 84 JPM BASIS INFORMATION TASK: 1250370201, Perform actions for loss of letdown. TASK STANDARD: All charging pumps are stopped and CHB-UV-255 closed K/A: 3.3.2-004-A2.07 K/A RATING: RO:
3.4 SRO: 3.7 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes  


==REFERENCES:==
==REFERENCES:==
40AO-9ZZ05 Loss of Letdown (Rev 18) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes     APPROVAL Developed By: Alan Malley Date: 04/25/2007 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40AO-9ZZ05 Loss of Letdown (Rev 18)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       Yes APPROVAL Developed By:     Alan Malley                   Date:   04/25/2007 Revised By:       Alan Malley                   Date:   04/16/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR           X     PLANT TESTING METHOD:                           SIMULATE                   PERFORM       X EVALUATION Examinee Name:                                                   Date:
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
84                                  Revised 9/23/08


JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 85 9. SIMULATOR SETUP:
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
C. IC#: 104 D. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 9.       SIMULATOR SETUP:
: 20. Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.
C. IC#: 104 D. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT                 COMMAND                                       DESCRIPTION
NN. SPECIAL INSTRUCTIONS: Place simulator in FREEZE. Place simulator in RUN and acknowledge alarms.
: 20.         Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.
Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.
NN. SPECIAL INSTRUCTIONS:
Provide Cue.
* Place simulator in FREEZE.
Place simulator in RUN.
* Place simulator in RUN and acknowledge alarms.
This JPM is set to run with JS5 for the 2009 NRC exam.
* Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.
A. REQUIRED CONDITIONS: Letdown isolated, Letdown Control Valves in manual and closed, the normally running Charging Pump in PTL, Pressurizer level at 56% and rising. IC 104 has these  
* Provide Cue.
* Place simulator in RUN.
* This JPM is set to run with JS5 for the 2009 NRC exam.
A.       REQUIRED CONDITIONS:
* Letdown isolated, Letdown Control Valves in manual and closed, the normally running Charging Pump in PTL, Pressurizer level at 56% and rising. IC 104 has these conditions built in.
: 2.      SPECIAL TOOLS/EQUIPMENT:
* Copy of 40AO-9ZZ05, Loss of Letdown, Appendix C (Rev 18)
* No Simulator Driver actions are required for this JPM.
OO. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________                Date: ____________________
If IC-104 is not available, reset to IC-20 and perform the following:
* Close CHB-UV-515 using the handswitch on B03
* Allow Pzr Level to increase to 54%
* Place the normally running Charging Pump in PTL imf cmAVCV04CHEFV244_4 (Mechanical seizure) 85


conditions built in. 
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
: 2. SPECIAL TOOLS/EQUIPMENT:  Copy of 40AO-9ZZ05, Loss of Letdown, Appendix C (Rev 18)  No Simulator Driver actions are required for this JPM.
SPECIAL CONSIDERATIONS:
OO. SIMULATOR EVALUATION PRE-CHECK  Correct IC  Alarm Silence Off  Procedures available, page checked, and clean  For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________    Date: ____________________ If IC-104 is not available, reset to IC-20 and perform the following:  Close CHB-UV-515 using the handswitch on B03  Allow Pzr Level to increase to 54%  Place the normally running Charging Pump in PTL imf cmAVCV04CHEFV244_4 (Mechanical seizure)
IN PLANT JPMs ONLY
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 86 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
SPECIAL CONSIDERATIONS:
* Inform the control room staff of any discovered deficiencies.
 
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
IN PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL JPMs You may use any source of information normally available.
ALL JPMs
INITIATING CUE:  
* You may use any source of information normally available.
 
INITIATING CUE:
The Unit is in mode 1. Letdown was lost. The CRS has determined that letdown can NOT be restored. CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix "C", Extended Operations Without Letdown. The pressurizer is not in boron equalization.
* The Unit is in mode 1.
* Letdown was lost.
* The CRS has determined that letdown can NOT be restored.
* CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown.
* The pressurizer is not in boron equalization.
INFORMATION FOR EVALUATOR'S USE:
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance.
* Denotes Critical Step
JS-6  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 87 Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
JS-6  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  88 JPM START TIME:
* Any step marked UNSAT requires comments.
STEP CUE STANDARD 1. Step 1 of Appendix C: WHEN letdown can be restored, THEN GO TO Appendix A, Restoration of Letdown with a Pressurizer Steam Bubble.
* If this is the first JPM of the set then ensure the examinee has been briefed.
If Requested: Letdown can not be restored  Examinee should determine from Initiating Cue that letdown cannot be
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
86


restored.  
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
* Performance of this JPM may require entry into areas with alarmed doors.         Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
87


SAT / UNSAT Comments (required for UNSAT):  
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                                  CUE                            STANDARD
: 1.      Step 1 of Appendix C:                If Requested: Letdown can not be    Examinee should determine from restored                            Initiating Cue that letdown cannot be WHEN letdown can be restored,                                            restored.
THEN GO TO Appendix A, Restoration of Letdown with a Pressurizer Steam Bubble.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                            STANDARD
: 2.      Step 2 of Appendix C:                                                    Examinee determines Boron equalization is not in progress by IF Boron equalization is in progress,                                    information provided in Initiating THEN STOP Boron equalization.                                            Cue.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                            STANDARD
: 3.      Step 3 of Appendix C:                Chemistry is notified of the status Examinee calls chemistry and of letdown.                        informs them of the status of Notify chemistry that the plant will                                      letdown.
be operated with letdown flow isolated.
SAT / UNSAT Comments (required for UNSAT):
88


STEP CUE STANDARD 2. Step 2 of Appendix C:  IF Boron equalization is in progress, THEN STOP Boron equalization. Examinee determines Boron equalization is not in progress by information provided in Initiating Cue. SAT / UNSAT Comments (required for UNSAT):  
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                               CUE                               STANDARD
: 4.     Step 4.a of Appendix C:               The CRS will ensure compliance      Examinee determines that pressurizer with LCO 3.4.9 if pressurizer level level is 56% and rising (or will WHEN the CRS determines seal          exceeds the Tech Spec limit.        exceed 56% shortly).
injection and charging are to be stopped, OR pressurizer level is 56%
or more and rising, THEN perform the following:
* IF the unit is in Mode 1, 2 or 3, THEN ensure compliance with LCO 3.4.9, Pressurizer.
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                              STANDARD
: 5.      Step 4.b of Appendix C:                                                  Examinee determines RCP controlled Bleedoff valves should be open and Ensure controlled Bleedoff is                                             are open.
isolated on all standby RCPs prior to Seal 2 Outlet Temperature exceeding 250°F.
SAT / UNSAT Comments (required for UNSAT):
89


STEP CUE STANDARD 3. Step 3 of Appendix C:  Notify chemistry that the plant will be operated with letdown flow
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                           CUE                     STANDARD
 
: 6.     Step 4.c of Appendix C:                                   Examinee places the individual seal injection flow controllers in manual Close the seal injection flow control                      and adjusts the output TO 100% to valves.                                                    close the valves by using:
isolated.
RCP 1(2) / A (B) SEAL INJECTION FLOW CONTROL CHN-FIC-241 THRU 244 Note:
Chemistry is notified of the status of letdown.
* These are reverse acting valves 100% output is full closed
Examinee calls chemistry and informs them of the status of letdown. SAT / UNSAT Comments (required for UNSAT):
* This action may be performed by fully closing one valve at a time or partially closing each valve followed by full closure.
 
NOTE: ALTERNATE PATH. The flow control valve for RCP 2B (CHN-FIC-244) will not respond and will not close so the examinee should go to the contingency step and close CHB-HV-255.
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 89  STEP CUE STANDARD 4. Step 4.a of Appendix C:
SAT / UNSAT Comments (required for UNSAT):
WHEN the CRS determines seal injection and charging are to be stopped, OR pressurizer level is 56% or more and rising, THEN perform the following: IF the unit is in Mode 1, 2 or 3, THEN ensure compliance with LCO 3.4.9, Pressurizer.
STEP                           CUE                     STANDARD
The CRS will ensure compliance with LCO 3.4.9 if pressurizer level
: 7.
 
* Step 4.c.1 of Appendix C:                                 Examinee closes CHB-HV-255, Seal Injection Supply Header Isolation Close CHB-HV-255, Seal Injection                           Valve.
exceeds the Tech Spec limit. Examinee determines that pressurizer level is  56% and rising (or will exceed 56% shortly).
Supply Header Isolation Valve.
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
 
90
STEP CUE STANDARD 5. Step 4.b of Appendix C: Ensure controlled Bleedoff is isolated on all standby RCPs prior to Seal 2 Outlet Temperature exceeding
 
250°F. Examinee determines RCP controlled Bleedoff valves should be open and
 
are open.
SAT / UNSAT Comments (required for UNSAT):
 
JS-6  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  90  STEP CUE STANDARD 6. Step 4.c of Appendix C:
Close the seal injection flow control valves. Examinee places the individual seal injection flow controllers in manual and adjusts the output TO 100% to close the valves by using:
RCP 1(2) / A (B) SEAL INJECTION FLOW CONTROL CHN-FIC-241 THRU 244  
 
Note:   These are reverse acting valves 100% output is full  
 
closed  This action may be performed by fully closing one valve at a time or  
 
partially closing each valve followed by full closure.
NOTE: ALTERNATE PATH.
The flow control valve for RCP 2B (CHN-FIC-244) will not respond and will not close so the examinee should go to the contingency step and close CHB-HV-255.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 7.
* Step 4.c.1 of Appendix C: Close CHB-HV-255, Seal Injection Supply Header Isolation Valve.
Examinee closes CHB-HV-255, Seal Injection Supply Header Isolation  
 
Valve. SAT / UNSAT Comments (required for UNSAT):  
 
JS-6  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  91  STEP CUE STANDARD 8.
* Step 4.d of Appendix C: Place all charging pumps in pull to lock (PTL).
Another operator will complete this appendix. 
 
This JPM is complete.
Examinee places all charging pumps in pull to lock (PTL) by using: CHARGING PUMP 1 P01 *CHA-HS-216 And CHARGING PUMP 3 P01 *CHA-HS-218A CHB-HS-218 (no breaker therefore not required to go to PTL)
And CHARGING PUMP 2 P01 CHB-HS-217 (in PTL is setup)
 
NOTE:  Critical nature of this step is that all running charging pumps are stopped. SAT / UNSAT Comments (required for UNSAT):


JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                              CUE                          STANDARD
: 8.
* Step 4.d of Appendix C:            Another operator will complete  Examinee places all charging pumps this appendix.                  in pull to lock (PTL) by using:
Place all charging pumps in pull to CHARGING PUMP 1 P01 lock (PTL).
                                                                            *CHA-HS-216 This JPM is complete.          And CHARGING PUMP 3 P01
                                                                            *CHA-HS-218A CHB-HS-218 (no breaker therefore not required to go to PTL)
And CHARGING PUMP 2 P01 CHB-HS-217 (in PTL is setup)
NOTE: Critical nature of this step is that all running charging pumps are stopped.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 91


JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 92  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1 04/16/2009 6 Revised for format and procedure rev                                             REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                                 COMMENTS 1           04/16/2009           6         Revised for format and procedure rev REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 49. Vendor reference document upgrade
: 50. Plant modification (include number)
: 51. Procedure upgrade
: 52. Internal or External Agency Commitment (indicate item number)
: 53. Technical Specification Change (indicate amendment number)
: 54. Other (explain in comments) 92


consecutively in each revision.
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 49. Vendor reference document upgrade
* The Unit is in mode 1.
: 50. Plant modification (include number)
* Letdown was lost.
: 51. Procedure upgrade
* The CRS has determined that letdown can NOT be restored.
: 52. Internal or External Agency Commitment (indicate item number)
* CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown.
: 53. Technical Specification Change (indicate amendment number)
* The pressurizer is not in boron equalization.
: 54. Other (explain in comments)
CANDIDATE 93
JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 93 INITIAL CONDITIONS INITIATING CUE:
The Unit is in mode 1. Letdown was lost. The CRS has determined that letdown can NOT be restored. CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix "C", Extended Operations Without Letdown. The pressurizer is not in boron equalization.  


CANDIDATE JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 94 JPM BASIS INFORMATION TASK: 0780031301, Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02 TASK STANDARD: Transfers 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02, Rev 50 K/A: 3.6-062-K1.04 K/A RATING: RO:
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK:     0780031301, Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02 TASK STANDARD: Transfers 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02, Rev 50 K/A: 3.6-062-K1.04                                 K/A RATING:       RO:   3.7   SRO: 4.2 K/A:                                               K/A RATING:       RO:         SRO APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:         15 minutes
3.7 SRO: 4.2 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes  


==REFERENCES:==
==REFERENCES:==
40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) 41AL-1RK1A, Panel B01A Alarm Responses (Rev 49) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes     APPROVAL Developed By: Alan Malley Date: 10/22/2003 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT       TESTING METHOD: SIMULATE   PERFORM X     EVALUATION Examinee Name:
40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) 41AL-1RK1A, Panel B01A Alarm Responses (Rev 49)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       Yes APPROVAL Developed By:     Alan Malley                   Date:   10/22/2003 Revised By:       Alan Malley                   Date:   04/16/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR           X     PLANT TESTING METHOD:                           SIMULATE                   PERFORM       X EVALUATION Examinee Name:                                                   Date:
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
94


JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 95 10. SIMULATOR SETUP:
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
: 10.       SIMULATOR SETUP:
PP. IC#: 105 (For 2009 NRC exam only)
PP. IC#: 105 (For 2009 NRC exam only)
QQ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
QQ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT                 COMMAND                                         DESCRIPTION
: 21. None   RR. SPECIAL INSTRUCTIONS: This JPM is set to run with JS8 for the 2009 NRC exam.
: 21.         None RR. SPECIAL INSTRUCTIONS:
SS. REQUIRED CONDITIONS: NAN-S01 and NAN-S02 energized from the NAN-S03 and NAN-S04 respectively.
* This JPM is set to run with JS8 for the 2009 NRC exam.
TT. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
SS. REQUIRED CONDITIONS:
: 10. SPECIAL TOOLS/EQUIPMENT:  
* NAN-S01 and NAN-S02 energized from the NAN-S03 and NAN-S04 respectively.
: a. Copy of 40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) Section 4.8 and 4.9 Copy of 41AL-1RK1A, Panel B01A Alarm Responses (Rev 50) Window 18B  
TT. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________               Date: ____________________
: 10. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of 40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) Section 4.8 and 4.9
* Copy of 41AL-1RK1A, Panel B01A Alarm Responses (Rev 50) Window 18B If IC-105 is not available, reset to IC-20 and perform the following:
* Transfer NAN-S01 and NAN-S02 to the Startup Transformers per 40OP-9NA03 per Sections 7.0 and 11.0.
* imf cmBKED05NANS04B_1 (Auto Trip logic failure) 95


If IC-105 is not available, reset to IC-20 and perform the following:  Transfer NAN-S01 and NAN-S02 to the Startup Transformers per 40OP-9NA03 per Sections 7.0 and 11.0. imf cmBKED05NANS04B_1 (Auto Trip logic failure)
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 96
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers).
* The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9.
* All prerequisites have been performed.
96


TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
SPECIAL CONSIDERATIONS: 
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
97


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPMs  You may use any source of information normally available.
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
INITIATING CUE:  
Note: This JPM involves two procedure sections. The JPM starts at procedure section 4.8. If examinee goes to section 4.9 first, start at JPM step 7.
STEP                                  CUE                          STANDARD
: 1.
* From step 4.8.3.1 of 40OP-9NA03:                                      Examinee places synchronizing switch NAN-SS-S01A to ON and Turn the Synchronizing Switch for                                    verifies proper synchronization NAN-S01 Supply Breaker, NAN-SS-                                      indicated by MAN-EI-002I, MAN-S01A, to ON and check for proper                                    EI-002R and synchronizing scope at synchronization.                                                      the 12 oclock position.
SAT / UNSAT Comments (required for UNSAT):
STEP                                  CUE                          STANDARD
: 2.
* From step 4.8.3.2 of 40OP-9NA03:                                      Examinee closes NAN-S01A using NAN-HS-S01A and checks red Close the NAN-S01 Supply breaker                                      closed light illuminated.
NAN-S01A by turning handswitch NAN-HS-S01A to CLOSE.
SAT / UNSAT Comments (required for UNSAT):
98


The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers). The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9. All prerequisites have been performed.  
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                          CUE                    STANDARD
: 3.      From step 4.8.3.3 of 40OP-9NA03:                        Examinee verifies NAN-S03B opens when NAN-HS-S01A is released by Check that the NAN-S03-NAN-S01                         checking the green open light is Supply breaker, NAN-S03B,                              illuminated on NAN-HS-S03B.
automatically opens when handswitch NAN-HS-S01A is released.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 4.      From step 4.8.3.4 of 40OP-9NA03:                        Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter Check that NAN-S01 voltage is                          NAN-EI-S01.
between 12.42KV - 14.49KV.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                    STANDARD
: 5.      From step 4.8.3.5 of 40OP-9NA03:                        Examinee places synchronizing switch, NAN-SS-S01A to OFF.
Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S01A to OFF.
SAT / UNSAT Comments (required for UNSAT):
99


JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 97 
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                            CUE                    STANDARD
: 6.      From step 4.8.3.6 of 40OP-9NA03:                          Examinee determines that the related Startup Transformer is not supplying Perform the appropriate section of                        more than one unit and does not Appendix D - S/U Xfmr Winding                            perform Appendix D.
Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                    STANDARD
: 7.
* From step 4.9.3.1 of 40OP-9NA03:                          Examinee places synchronizing switch NAN-SS-S02A to ON and Turn the Synchronizing Switch for                        verifies proper synchronization NAN-S02 Supply Breaker, NAN-SS-                          indicated by MAN-EI-002I, MAN-S02A to ON and check for proper                        EI-002R and synchronizing scope at synchronization.                                          the 12 oclock position.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                    STANDARD
: 8.
* From step 4.9.3.2 of 40OP-9NA03:                          Examinee closes NAN-S02A using NAN-HS-S02A and checks red Close the NAN-S02 Supply Breaker                          closed light illuminated.
NAN-S02A by turning handswitch NAN-HS-S02A to CLOSE.
SAT / UNSAT Comments (required for UNSAT):
100


INFORMATION FOR EVALUATOR'S USE:
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                               CUE                             STANDARD
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 9.
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 98 JPM START TIME:
* From step 4.9.3.3 of 40OP-9NA03:   If requested CUE: Understand that Examinee verifies NAN-S04B did NAN-SO4B did not open.             NOT automatically open when Check that the NAN-S04-NAN-SO2                                         NAN-HS-S02A is released by Supply Breaker NAN-S04B,                                              checking that the red closed light is automatically opens when                                              still illuminated on NAN-HS-S04B.
Note:  This JPM involves two procedure sections. The JPM starts at procedure section 4.8.
handswitch NAN-HS-S02A is released.                                                              Note: Refers to alarm response procedure 41AL-1RK1A, window 1A18B. The examinee may not refer to this procedure, although he/she should.
If examinee goes to section 4.9 first, start at JPM step 7.
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 1.
STEP                               CUE                             STANDARD
* From step 4.8.3.1 of 40OP-9NA03:
: 10.
Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S01A, to "ON" and check for proper synchronization.
* From step 2 of Window 1A18B         If examinee requests permission to Examinee manually opens NAN-Alarm Response Procedure:          open S04B, CUE: Open breaker       S04B using NAN-HS-S04B and NAN-S04B.                          checks green open light is IF the running breaker did not trip                                    illuminated.
Examinee places synchronizing switch NAN-SS-S01A to "ON" and verifies proper synchronization indicated by MAN-EI-002I, MAN-EI-002R and synchronizing scope at the 12 o'clock position.
automatically when the oncoming breaker control switch was returned                                    Note: The examinee may perform to the normal position, THEN trip                                      this action without reference to the the running breaker.                                                  alarm response procedure. This is acceptable but not preferred.
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
 
101
STEP CUE STANDARD 2.
* From step 4.8.3.2 of 40OP-9NA03: Close the NAN-S01 Supply breaker NAN-S01A by turning handswitch
 
NAN-HS-S01A to "CLOSE". Examinee closes NAN-S01A using NAN-HS-S01A and checks red closed light illuminated.
 
SAT / UNSAT Comments (required for UNSAT):
 
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  99  STEP CUE STANDARD 3. From step 4.8.3.3 of 40OP-9NA03:
Check that the NAN-S03-NAN-S01 Supply breaker, NAN-S03B, automatically opens when
 
handswitch NAN-HS-S01A is
 
released. Examinee verifies NAN-S03B opens when NAN-HS-S01A is released by checking the green open light is illuminated on NAN-HS-S03B.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 4. From step 4.8.3.4 of 40OP-9NA03:
Check that NAN-S01 voltage is between 12.42KV - 14.49KV.
Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter
 
NAN-EI-S01.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 5. From step 4.8.3.5 of 40OP-9NA03:
Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-
 
S01A to "OFF". Examinee places synchronizing switch, NAN-SS-S01A to "OFF".
SAT / UNSAT Comments (required for UNSAT):
 
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  100  STEP CUE STANDARD 6. From step 4.8.3.6 of 40OP-9NA03: Perform the appropriate section of Appendix D - S/U Xfmr Winding
 
Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit. Examinee determines that the related Startup Transformer is not supplying more than one unit and does not perform Appendix D.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 7.
* From step 4.9.3.1 of 40OP-9NA03:
Turn the Synchronizing Switch for NAN-S02 Supply Breaker, NAN-SS-S02A to "ON" and check for proper synchronization. Examinee places synchronizing switch NAN-SS-S02A to "ON" and verifies proper synchronization indicated by MAN-EI-002I, MAN-EI-002R and synchronizing scope at the 12 o'clock position.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 8.
* From step 4.9.3.2 of 40OP-9NA03: Close the NAN-S02 Supply Breaker NAN-S02A by turning handswitch
 
NAN-HS-S02A to CLOSE. Examinee closes NAN-S02A using NAN-HS-S02A and checks red closed light illuminated.
SAT / UNSAT Comments (required for UNSAT):
 
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  101  STEP CUE STANDARD 9.
* From step 4.9.3.3 of 40OP-9NA03:
Check that the NAN-S04-NAN-SO2 Supply Breaker NAN-S04B, automatically opens when
 
handswitch NAN-HS-S02A is  
 
released. If requested CUE: Understand that NAN-SO4B did not open. Examinee verifies NAN-S04B did NOT automatically open when NAN-HS-S02A is released by
 
checking that the red closed light is still illuminated on NAN-HS-S04B.
Note: Refers to alarm response procedure 41AL-1RK1A, window 1A18B. The examinee may not refer to this procedure, although he/she should. SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 10.
* From step 2 of Window 1A18B Alarm Response Procedure:
IF the running breaker did not trip automatically when the oncoming
 
breaker control switch was returned to the normal position, THEN trip the running breaker.
If examinee requests permission to open S04B, CUE: Open breaker  
 
NAN-S04B. Examinee manually opens NAN-S04B using NAN-HS-S04B and checks green open light is illuminated. Note: The examinee may perform this action without reference to the alarm response procedure. This is  
 
acceptable but not preferred.
SAT / UNSAT Comments (required for UNSAT):  
 
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  102  STEP CUE STANDARD 11. From step 4.9.3.4 of 40OP-9NA03:
Check that NAN-S02 voltage is between 12.42KV - 14.49KV.
Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter
 
NAN-EI-S02.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 12. From step 4.9.3.5 of 40OP-9NA03:
Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-
 
S02A to "OFF". Examinee places synchronizing switch, NAN-SS-S02A to "OFF".
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 13. From step 4.9.3.6 of 40OP-9NA03: Perform the appropriate section of Appendix D - S/U Xfmr Winding
 
Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit. Examinee determines that the related Startup Transformer is not supplying more than one unit and does not perform Appendix D.
SAT / UNSAT Comments (required for UNSAT):


JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                            CUE                  STANDARD
: 11. From step 4.9.3.4 of 40OP-9NA03:                          Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter Check that NAN-S02 voltage is                            NAN-EI-S02.
between 12.42KV - 14.49KV.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                  STANDARD
: 12. From step 4.9.3.5 of 40OP-9NA03:                          Examinee places synchronizing switch, NAN-SS-S02A to OFF.
Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S02A to OFF.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                  STANDARD
: 13. From step 4.9.3.6 of 40OP-9NA03:                          Examinee determines that the related Startup Transformer is not supplying Perform the appropriate section of                        more than one unit and does not Appendix D - S/U Xfmr Winding                            perform Appendix D.
Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT 102


NORMAL TERMINATION POINT
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS Rev 1        04/16/2009            6        Reformatted to new template and rewrote note.
REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 55. Vendor reference document upgrade
: 56. Plant modification (include number)
: 57. Procedure upgrade
: 58. Internal or External Agency Commitment (indicate item number)
: 59. Technical Specification Change (indicate amendment number)
: 60. Other (explain in comments) 103


JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 103  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS Rev 1 04/16/2009 6 Reformatted to new template and rewrote note.
JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
* The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers).
* The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9.
* All prerequisites have been performed.
CANDIDATE 104


consecutively in each revision.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250300301: Perform actions to restore equipment following inadvertent CSAS TASK STANDARD: Respond to an inadvertent CSAS on Train "B" K/A: 3.5 026 A2.03                                 K/A RATING:       RO:   4.1   SRO:   4.4 K/A:                                               K/A RATING:       RO:         SRO APPLICABLE POSITION(S):             RO/SRO         VALIDATION TIME:         15 minutes
: 55. Vendor reference document upgrade
: 56. Plant modification (include number)
: 57. Procedure upgrade
: 58. Internal or External Agency Commitment (indicate item number)
: 59. Technical Specification Change (indicate amendment number)
: 60. Other (explain in comments)
JS-7  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  104 INITIAL CONDITIONS INITIATING CUE:
The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers). The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9. All prerequisites have been performed.
 
CANDIDATE JS-8  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 105 JPM BASIS INFORMATION TASK: 1250300301: Perform actions to restore equipment following inadvertent CSAS TASK STANDARD: Respond to an inadvertent CSAS on Train "B" K/A: 3.5 026 A2.03 K/A RATING: RO:
4.1 SRO: 4.4 K/A: K/A RATING: RO:
SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes  


==REFERENCES:==
==REFERENCES:==
40AO-9ZZ17, Inadve rtent PPS-ESFAS Actuations Rev 13 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 08/25/2005 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations Rev 13 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     Yes     Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   08/25/2005 Revised By:       Alan Malley                   Date:   04/16/2009 Technical Review                                 Operations Approval E-Plan Review                   N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
105                                  Revised 9/23/08


JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 106 11. SIMULATOR SETUP:
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
A. IC#: 105 (For 2009 NRC exam only)
: 11.     SIMULATOR SETUP:
B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS: EVENT COMMAND DESCRIPTION  
A.     IC#: 105 (For 2009 NRC exam only)
: 22. If IC-105 is not available, reset to IC-20 and perform the following: imf RP06H1 (Blown fuse for CSAS B) imf RP06H2 (Blown fuse for CSAS B) Allow time for equipment to actuate Silence the annunciators C. SPECIAL INSTRUCTIONS: This JPM is set to run with JS7 during the 2009 NRC exam D. REQUIRED CONDITIONS: Place simulator in FREEZE Provide initiating cue to examinee Place simulator in RUN E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
B.     MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
: 11. SPECIAL TOOLS/EQUIPMENT: Copy of 40AO-9ZZ17, Section 5.0, Rev 13 JS-8  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 107 
EVENT             COMMAND                                           DESCRIPTION
: 22.                                       If IC-105 is not available, reset to IC-20 and perform the following:
* imf RP06H1 (Blown fuse for CSAS B)
* imf RP06H2 (Blown fuse for CSAS B)
* Allow time for equipment to actuate
* Silence the annunciators C.     SPECIAL INSTRUCTIONS:
* This JPM is set to run with JS7 during the 2009 NRC exam D.     REQUIRED CONDITIONS:
* Place simulator in FREEZE
* Provide initiating cue to examinee
* Place simulator in RUN E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________             Date: ____________________
: 11. SPECIAL TOOLS/EQUIPMENT:
* Copy of 40AO-9ZZ17, Section 5.0, Rev 13 106


TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPMs ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
* The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred.
* The CRS directs you to respond to the inadvertent CSAS per 40AO-9ZZ17, Section 5.0.
* THIS IS A TIME CRITICAL JPM.
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
107


IN  PLANT JPMs ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
108


radiation areas. ALL  JPMs  You may use any source of information normally available.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
INITIATING CUE:
STEP                               CUE                           STANDARD
 
: 1.     From step 1 of Section 5.0 of 40AO- If Requested: CSAS occurred at the The examinee notes the time of the 9ZZ17:                              current time.                      actuation.
The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred. The CRS directs you to respond to the inadvertent CSAS per 40AO-9ZZ17, Section 5.0.
Record the time of the CSAS                                            Start Time _______________
THIS IS A TIME CRITICAL JPM.
Actuation. _________
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 108 Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
JS-8  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  109 JPM START TIME:
STEP CUE STANDARD 1. From step 1 of Section 5.0 of 40AO-9ZZ17: Record the time of the CSAS Actuation. _________
If Requested
: CSAS occurred at the current time. The examinee notes the time of the actuation. Start Time _______________
Time critical evolution starts here.
Time critical evolution starts here.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
STEP                                CUE                            STANDARD
: 2.      From step 2 of Section 5.0 of 40AO-                                    Examinee determines SIAS has not 9ZZ17:                                                                actuated and N/As this step.
IF ANY Containment Spray Pump is running, AND BOTH of the following conditions exist:
* Containment Spray Pump is NOT being used for SDC
* SIAS has actuated THEN override and stop the Containment Spray Pump.
SAT / UNSAT Comments (required for UNSAT):
109


STEP CUE STANDARD 2. From step 2 of Section 5.0 of 40AO-9ZZ17: IF ANY Containment Spray Pump is running, AND BOTH of the following conditions exist: Containment Spray Pump is NOT being used for SDC SIAS has actuated THEN override and stop the Containment Spray Pump. Examinee determines SIAS has not actuated and N/As this step.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                           CUE                   STANDARD
SAT / UNSAT Comments (required for UNSAT):  
: 3.
* From step 3 of Section 5.0 of 40AO-                       The examinee places the CS 9ZZ17:                                                   handswitch in stop to anti-pump the CS pump and verifies the pump IF ANY Containment Spray Pump is                         stops.
running, AND BOTH of the following conditions exist:
* Containment Spray Pump is NOT being used for SDC
* SIAS has NOT actuated THEN place the Containment Spray Pump hand switch in STOP to anti-pump the CS Pump.
SAT / UNSAT Comments (required for UNSAT):
STEP                            CUE                  STANDARD
: 4.
* From step 4 of Section 5.0 of 40AO-                      Examinee overrides and closes SIB-9ZZ17:                                                    UV-671.
Override and close all open Containment Spray Header Isolation Valves.
SAT / UNSAT Comments (required for UNSAT):
110


JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 110  STEP CUE STANDARD 3.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                                 CUE                               STANDARD
* From step 3 of Section 5.0 of 40AO-9ZZ17: IF ANY Containment Spray Pump is running, AND BOTH of the following conditions exist: Containment Spray Pump is NOT being used for SDC  SIAS has NOT actuated THEN place the Containment Spray Pump hand switch in "STOP" to anti-pump the CS Pump.
: 5.     From step 5 of Section 5.0 of 40AO-                                       Examinee verifies Seal injection is in 9ZZ17:                                                                   service, therefore no action should be taken unless the candidate exceeds IF seal injection is in service, AND 10 minutes to restore NC to the cooling water is NOT restored to RCPs.
The examinee places the CS handswitch in stop to anti-pump the CS pump and verifies the pump stops. 
ANY operating RCP within 10 minutes of the initial loss, THEN perform the following:
 
: a. Ensure the reactor is tripped.
SAT / UNSAT Comments (required for UNSAT):
: b. Stop all of the RCPs.
 
STEP CUE STANDARD 4.
* From step 4 of Section 5.0 of 40AO-9ZZ17: Override and close all open Containment Spray Header Isolation
 
Valves. Examinee overrides and closes SIB-UV-671. SAT / UNSAT Comments (required for UNSAT):
 
JS-8  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  111  STEP CUE STANDARD 5. From step 5 of Section 5.0 of 40AO-9ZZ17: IF seal injection is in service, AND cooling water is NOT restored to ANY operating RCP within 10 minutes of the initial loss, THEN perform the following:  
: a. Ensure the reactor is tripped.  
: b. Stop all of the RCPs.  
: c. Isolate controlled bleedoff.
: c. Isolate controlled bleedoff.
Examinee verifies Seal injection is in service, therefore no action should be
SAT / UNSAT Comments (required for UNSAT):
 
STEP                                 CUE                               STANDARD
taken unless the candidate exceeds 10 minutes to restore NC to the
: 6.
 
* From step 5 of Section 5.0 of 40AO-   Upon completion of this step CUE:  Examinee opens the following 9ZZ17:                                                                   valves:
RCPs. SAT / UNSAT Comments (required for UNSAT):  
Another operator will complete Open ANY of the following as
 
* NCB-UV-403, NCW Section 5.0.
STEP CUE STANDARD 6.
needed to restore Nuclear Cooling                                               Containment Upstream Return Water to Containment:                                                           Isolation Valve
* From step 5 of Section 5.0 of 40AO-9ZZ17: Open ANY of the following as needed to restore Nuclear Cooling Water to Containment: NCA-UV-402, NCW Containment Downstream Return Isolation Valve  NCB-UV-403, NCW Containment Upstream Return Isolation Valve  NCB-UV-401, NCW Containment Upstream Supply Isolation Valve Upon completion of this step CUE:  Another operator will complete Section 5.0.
* NCA-UV-402, NCW
 
* NCB-UV-401, NCW Containment Downstream            This JPM is complete.                   Containment Upstream Supply Return Isolation Valve                                                     Isolation Valve
This JPM is complete.
* NCB-UV-403, NCW                                                       Note: The examinee should open Containment Upstream Return                                          UV-403 first and then UV-401. If Isolation Valve                                                      UV-401 is opened first this is NOT a
Examinee opens the following valves:  NCB-UV-403, NCW Containment Upstream Return Isolation Valve NCB-UV-401, NCW Containment Upstream Supply Isolation Valve Note: The examinee should open UV-403 first and then UV-401. If UV-401 is opened first this is NOT a  
* NCB-UV-401, NCW                                                        failure.
 
Containment Upstream Supply Isolation Valve                                                      Record the time that the RCP Nuclear Cooling Water Low Flow alarms clear on B04: ___________
failure. Record the time that the RCP Nuclear Cooling Water Low Flow alarms clear on B04: ___________  
 
Time Critical steps end here. Time should be less than 10 minutes.
Time Critical steps end here. Time should be less than 10 minutes.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 111


JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 112  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 001 10/12/2004 3 Revised to reflect procedure change to prevent pressurizer level from exceeding Tech Spec limit. 002 04/20/2005 6 Revised to make step 7 non-critical sin ce no action is required. 003 4/25/2007 6 Enhancements to bring in line with procedure. 004 03/25/2209 6 Changed to new JPM format 005 04/16/2009 6 Changed to new format and to add procedure Revision No.                             REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE         REVISED                                 COMMENTS 001         10/12/2004           3         Revised to reflect procedure change to prevent pressurizer level from exceeding Tech Spec limit.
002         04/20/2005           6         Revised to make step 7 non-critical since no action is required.
003           4/25/2007           6         Enhancements to bring in line with procedure.
004         03/25/2209           6         Changed to new JPM format 005         04/16/2009           6         Changed to new format and to add procedure Revision No.
REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 61. Vendor reference document upgrade
: 62. Plant modification (include number)
: 63. Procedure upgrade
: 64. Internal or External Agency Commitment (indicate item number)
: 65. Technical Specification Change (indicate amendment number)
: 66. Other (explain in comments) 112


consecutively in each revision.
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
: 61. Vendor reference document upgrade
* The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred.
: 62. Plant modification (include number)
* The CRS directs you to respond to the inadvertent CSAS per 40AO-9ZZ17, Section 5.0.
: 63. Procedure upgrade
* THIS IS A TIME CRITICAL JPM.
: 64. Internal or External Agency Commitment (indicate item number)
CANDIDATE 113
: 65. Technical Specification Change (indicate amendment number)
: 66. Other (explain in comments)
JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 113 INITIAL CONDITIONS INITIATING CUE:
The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred. The CRS directs you to respond to the inadvertent CSAS per 40AO-9ZZ17, Section 5.0.
THIS IS A TIME CRITICAL JPM.


CANDIDATE RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 114 JPM BASIS INFORMATION TASK: 1270130401 Implement reactor Coolant System Draining Operations TASK STANDARD: Determine amount of water drained and actual RCS level.
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1270130401 Implement reactor Coolant System Draining Operations TASK STANDARD: Determine amount of water drained and actual RCS level.
K/A: 2.1.25 K/A RATING: RO:
K/A: 2.1.25                                       K/A RATING:       RO:   3.9   SRO:   4.2 K/A:                                               K/A RATING:       RO:         SRO:
3.9 SRO: 4.2 K/A: K/A RATING: RO:
APPLICABLE POSITION(S):             RO             VALIDATION TIME:         20 minutes
SRO: APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes  


==REFERENCES:==
==REFERENCES:==
40OP-9ZZ16, RCS Drain Operations (Rev 66) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40OP-9ZZ16, RCS Drain Operations (Rev 66)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   04/17/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
114                                  Revised 9/20/08


RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 115 12. SIMULATOR SETUP:
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
UU. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 12.     SIMULATOR SETUP:
VV. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
UU. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 23. N/A 24. 25. 26. WW. SPECIAL INSTRUCTIONS: None XX. REQUIRED CONDITIONS: None YY. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
VV. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                   DESCRIPTION
: 12. SPECIAL TOOLS/EQUIPMENT:  
: 23.       N/A 24.
: a. Copy of 40OP-9ZZ16, RCS Drain Op erations Rev 66 Appendix D and E.  
25.
26.
WW. SPECIAL INSTRUCTIONS:
* None XX. REQUIRED CONDITIONS:
* None YY. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 12. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of 40OP-9ZZ16, RCS Drain Operations Rev 66 Appendix D and E.
115


RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 116 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
ALL JPMs You may use any source of information normally available.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
INITIATING CUE:
You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange level) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.
You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange level) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.
Unit 2 RCS level is currently 102 ft. 6 inches.  
Unit 2 RCS level is currently 102 ft. 6 inches.
Train A Shutdown Cooling is in service.
The Steam Generator Nozzle dams are installed.
The CRS directs that you perform the following and record your answers in the table provided:
: 1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114 to 1031 Increase in HUT level should be ____________ ft.
AND
: 2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train A local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16.
* Given the following information, determine and record the actual RCS level per Appendix D Section 5.0:
Time        Indicated level from LG -752        Train A SDC          Actual RCS level (Train A)                            flow is:
0800                    102 ft. 6 in.            4500 gpm                ______________
0815                  101 ft. 10 in.            4000 gpm                ______________
116


Train 'A' Shutdown Cooling is in service.
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
The Steam Generator Nozzl e dams are installed.  
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
117


The CRS directs that you perform the following and record your answers in the table provided:
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
: 1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114' to 103'1" Increase in HUT level should be ____________  ft.
STEP                       CUE                     STANDARD
AND  2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train 'A' local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16. Given the following information, determ ine and record the actual RCS level per Appendix D Section 5.0:
: 1.
Time Indicated level from LG -752 (Train A)
* The examinee determines the                         The examinee determines the level change in level in the HUT                         increase in the HUT by one of the following methods:
Train "A" SDC flow is: Actual RCS level 0800 102 ft. 6 in. 4500 gpm  ______________ 0815 101 ft. 10 in. 4000 gpm ______________
: 1. Uses the graph to determine the gallons of water drained from RCS is (93,800 - 70500 =
 
23300) 23300 gallons divided by 12,704 gallons / foot in the HUT
RA 1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 117  INFORMATION FOR EVALUATOR'S USE:
                                                                  = a change of 1.834 ft OR
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
: 2. Uses the graph to determine directly that the change is HUT level is (7.4 - 5.5 = 1.9 ft) is 1.9 ft.
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 118 JPM START TIME:
Acceptable answer 1.8 to 2.0 ft.
STEP CUE STANDARD 1.
SAT / UNSAT Comments (required for UNSAT):
* The examinee determines the change in level in the HUT The examinee determines the level increase in the HUT by one of the following methods:  
STEP                       CUE                     STANDARD
: 1. Uses the graph to determine the gallons of water drained from  
: 2.     The examinee determines the P                      The examinee determines the P is (inches) from the Unit 2 graph for                 approximately 28 inches (+ 2 inches).
 
a SDC flow of 4500 gpm.
RCS is (93,800 - 70500 =
SAT / UNSAT Comments (required for UNSAT):
23300) 23300 gallons divided by  
118
 
12,704 gallons / foot in the HUT  
 
= a change of 1.834 ft OR 2. Uses the graph to determine directly that the change is HUT  
 
level is (7.4 - 5.5 = 1.9 ft) is 1.9  
 
ft. Acceptable answer 1.8 to 2.0 ft.
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 2. The examinee determines the P (inches) from the Unit 2 graph for a SDC flow of 4500 gpm.
The examinee determines the P is approximately 28 inches (+
2 inches).
SAT / UNSAT Comments (required for UNSAT):
 
RA 1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  119  STEP CUE STANDARD 3.
* The examinee adds indicated level and P (inches) to determine actual level.
The examinee determines actual level for the 0800 reading is approximately
 
104 ft. 10 in.  (+
2 inches)
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 4. The examinee determines the P (inches) from the Unit 2 graph for a SDC flow of 4000 gpm.
The examinee determines the P is approximately 22.5 inches (+
2 inches).
SAT / UNSAT Comments (required for UNSAT):  
 
STEP CUE STANDARD 5.
* The examinee adds indicated level and P (inches) to determine actual level.
The examinee determines actual level is approximately 103 ft. 8.5 in.  (+
2 inches)  SAT / UNSAT Comments (required for UNSAT):


RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                        CUE                      STANDARD
: 3.
* The examinee adds indicated                        The examinee determines actual level level and P (inches) to                            for the 0800 reading is approximately determine actual level.                            104 ft. 10 in. (+ 2 inches)
SAT / UNSAT Comments (required for UNSAT):
STEP                        CUE                      STANDARD
: 4.      The examinee determines the P                      The examinee determines the P is (inches) from the Unit 2 graph for                  approximately 22.5 inches (+ 2 inches).
a SDC flow of 4000 gpm.
SAT / UNSAT Comments (required for UNSAT):
STEP                        CUE                      STANDARD
: 5.
* The examinee adds indicated                        The examinee determines actual level is level and P (inches) to                            approximately 103 ft. 8.5 in. (+ 2 determine actual level.                            inches)
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 119


RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 120  
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Increase in HUT level should be _____ 1.9 ( + 0.1 ft) _____ ft.
Time      Indicated level from LG -    Train A      Actual RCS level 752 (Train A)                SDC flow is:
0800              102 ft. 6 in.        4500 gpm      __104 ft 10 in ( + 2 inches) __
0815            101 ft. 10 in.        4000 gpm      __103 ft 8.5 in ( + 2 inches) __
ANSWER KEY 120


Increase in HUT level should be _____ 1.9 ( +
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          04/17/2009            6        Record created REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
0.1 ft) _____ ft.  
: 67. Vendor reference document upgrade
: 68. Plant modification (include number)
: 69. Procedure upgrade
: 70. Internal or External Agency Commitment (indicate item number)
: 71. Technical Specification Change (indicate amendment number)
: 72. Other (explain in comments) 121


Time Indicated level from LG -
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
752 (Train A)
You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange level) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.
Train "A" SDC flow is: Actual RCS level 0800 102 ft. 6 in. 4500 gpm  __104 ft 10 in  ( +
2 inches) __ 0815 101 ft. 10 in. 4000 gpm  __103 ft 8.5 in  ( +
2 inches) __
 
ANSWER KEY ANSWER KEY RA 1  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  121  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 04/17/2009 6  Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
 
consecutively in each revision.
: 67. Vendor reference document upgrade
: 68. Plant modification (include number)
: 69. Procedure upgrade
: 70. Internal or External Agency Commitment (indicate item number)
: 71. Technical Specification Change (indicate amendment number)
: 72. Other (explain in comments)
RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 122 INITIATING CUE:
You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange leve l) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.
Unit 2 RCS level is currently 102 ft. 6 inches.
Unit 2 RCS level is currently 102 ft. 6 inches.
Train 'A' Shutdown Cooling is in service. The Steam Generator Nozzl e dams are installed.
Train A Shutdown Cooling is in service.
The CRS directs that you perform the following and record your answers in the table provided:  
The Steam Generator Nozzle dams are installed.
: 1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114' to 103'1" Increase in HUT level should be ____________ ft.
The CRS directs that you perform the following and record your answers in the table provided:
AND 2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train 'A' local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16. Given the following information, determ ine and record the actual RCS level per Appendix D Section 5.0:
: 1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114 to 1031 Increase in HUT level should be ____________ ft.
Time Indicated level from LG -752 (Train A)
AND
Train "A" SDC flow is: Actual RCS level 0800 102 ft. 6 in.
: 2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train A local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16.
4500 gpm _____________
* Given the following information, determine and record the actual RCS level per Appendix D Section 5.0:
0815 101 ft. 10 in.
Time       Indicated level from LG -752         Train A SDC            Actual RCS (Train A)                           flow is:                 level 0800                   102 ft. 6 in.           4500 gpm                   _____________
4000 gpm _____________
0815                   101 ft. 10 in.           4000 gpm                   _____________
CANDIDATE 122


CANDIDATE RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 123 JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active a nd which operator can stand shift as a Reactor Operator. K/A: 2.1.4 K/A RATING: RO:
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active and which operator can stand shift as a Reactor Operator.
3.3 SRO: 3.8 K/A: K/A RATING: RO:
K/A: 2.1.4                                         K/A RATING:       RO:   3.3   SRO: 3.8 K/A:                                               K/A RATING:       RO:         SRO:
SRO: APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes  
APPLICABLE POSITION(S):             RO             VALIDATION TIME:         20 minutes


==REFERENCES:==
==REFERENCES:==
40DP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40DP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   04/17/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
123                                  Revised 9/20/08


RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 124 13. SIMULATOR SETUP:
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
ZZ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 13.     SIMULATOR SETUP:
AAA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
ZZ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 27. N/A 28. 29. 30. BBB. SPECIAL INSTRUCTIONS: None CCC. REQUIRED CONDITIONS: None DDD. SIMULATOR EVALUATION PRE-CHECK N/A 13. SPECIAL TOOLS/EQUIPMENT:  
AAA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT           COMMAND                                   DESCRIPTION
: a. Copy of 40DP-9OP02, Conduct of Shift Operations, Rev 46 RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 125 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
: 27.     N/A 28.
29.
30.
BBB.SPECIAL INSTRUCTIONS:
* None CCC.REQUIRED CONDITIONS:
* None DDD. SIMULATOR EVALUATION PRE-CHECK
* N/A
: 13. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of 40DP-9OP02, Conduct of Shift Operations, Rev 46 124
 
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
ALL JPM's You may use any source of information normally available.  
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE ON THE NEXT PAGE 125


INITIATING CUE ON THE NEXT PAGE RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 126 INITIATING CUE:
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position. (Assume all medical and training requirements are met).
Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position. (Assume all medical and training requirements are met).
Operator #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project. 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 03/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
Operator #1 12/21/2008       Operator taken off-shift to support the procedure upgrade project.
Operator #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
01/20/2009       Stood 12 hour shift as 3rd Reactor Operator in Unit 3.
Operator #1 can / cannot sta nd the position because ________________________________
02/12/2009       Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
_____________________________________________________________________________.
02/13/2009       Stood 12 hour shift as 3rd Reactor Operator in Unit 2 02/14/2009       Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
03/13/2009       Stood 4 hour shift as 3rd Reactor Operator in Unit 3.
03/25/2009       Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
03/26/2009       Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
Operator #2 01/15/2009       Received a new NRC Reactor Operator License 01/20/2009       Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
01/21/2009       Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
02/25/2009       Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
02/26/2009       Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
Operator #1 can / cannot stand the position because ________________________________
Operator #2 can / cannot stand the position because ________________________________
126


Operator #2 can / cannot sta nd the position because ________________________________
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
_____________________________________________________________________________.
* Denotes Critical Step
 
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 127 INFORMATION FOR EVALUATOR'S USE:
* Any step marked UNSAT requires comments.
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* If this is the first JPM of the set then ensure the examinee has been briefed.
RA 2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  128 JPM START TIME:
* Step sequence is not critical unless noted or will prevent achieving the task standard.
STEP CUE STANDARD 1. Obtain 40DP-9OP02, Conduct of Shift Operations.
* Notify unit Shift Manager of in-plant JPM performance.
Obtain 40DP-9OP02, Conduct of Shift Operations.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
SAT / UNSAT Comments (required for UNSAT):
* Locked valves may be involved. No attempt will be made to actually operate any valves.
 
127
STEP CUE STANDARD 2.
* The examinee determines that operator #1 cannot stand the shift
 
and the reason.
The examinee reviews the 40DP-9OP02 and determines the following reason for
 
operator #1 not being able to stand shift.
Operator #1 did not complete 60 hours on shift because 12 of his/her hours
 
were not on one shift.
SAT / UNSAT Comments (required for UNSAT):
 
STEP CUE STANDARD 3.
* The examinee determines that operator #2 can stand the shift
 
and the reason.
The examinee reviews the 40DP-9OP02 and determines the following reason for
 
operator #2 being able to stand shift.
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60
 
hours. SAT / UNSAT Comments (required for UNSAT):


RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                        CUE                      STANDARD
: 1.      Obtain 40DP-9OP02, Conduct of                      Obtain 40DP-9OP02, Conduct of Shift Shift Operations.                                  Operations.
SAT / UNSAT Comments (required for UNSAT):
STEP                        CUE                      STANDARD
: 2.
* The examinee determines that                        The examinee reviews the 40DP-9OP02 operator #1 cannot stand the shift                  and determines the following reason for and the reason.                                    operator #1 not being able to stand shift.
Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift.
SAT / UNSAT Comments (required for UNSAT):
STEP                        CUE                      STANDARD
: 3.
* The examinee determines that                        The examinee reviews the 40DP-9OP02 operator #2 can stand the shift                    and determines the following reason for and the reason.                                    operator #2 being able to stand shift.
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 128


RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 129  ANSWER KEY  
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Operator #1 can / cannot stand the position because :
(Circle one)
Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift.
Operator #2 can / cannot stand the position because:
(Circle one)
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours.
ANSWER KEY 129


Operator #1 can / cannot stand the position because
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          04/17/2009            6        Record created REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: (Circle one) Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift. Operator #2 can / cannot stand the position because:
: 73. Vendor reference document upgrade
  (Circle one)
: 74. Plant modification (include number)
Operator #2 received an Initial NRC license duri ng the previous quarter so he/she is not required to complete 60 hours.
: 75. Procedure upgrade
: 76. Internal or External Agency Commitment (indicate item number)
: 77. Technical Specification Change (indicate amendment number)
: 78. Other (explain in comments) 130


ANSWER KEY
RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).
Operator #1 12/21/2008    Operator taken off-shift to support the procedure upgrade project.
01/20/2009    Stood 12 hour shift as 3rd Reactor Operator in Unit 3.
02/12/2009    Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
02/13/2009    Stood 12 hour shift as 3rd Reactor Operator in Unit 2 02/14/2009    Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
03/13/2009    Stood 4 hour shift as 3rd Reactor Operator in Unit 3.
03/25/2009    Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
03/26/2009    Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
Operator #2 01/15/2009    Received a new NRC Reactor Operator License 01/20/2009    Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
01/21/2009    Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
02/25/2009    Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
02/26/2009    Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
Operator #1 can / cannot stand the position because ________________________________________
(Circle one)
Operator #2 can / cannot stand the position because ________________________________________
(Circle one)
CANDIDATE 131


RA 2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  130  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 04/17/2009 6  Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290310301 Perform a Tech Review of a Permit TASK STANDARD: Tech Review a Permit and determine three errors with the permit.
 
K/A: 2.2.13                                       K/A RATING:         RO:   4.1   SRO: 4.3 K/A:                                               K/A RATING:         RO:         SRO:
consecutively in each revision.
APPLICABLE POSITION(S):             RO             VALIDATION TIME:           20 minutes
: 73. Vendor reference document upgrade
: 74. Plant modification (include number)
: 75. Procedure upgrade
: 76. Internal or External Agency Commitment (indicate item number)
: 77. Technical Specification Change (indicate amendment number)
: 78. Other (explain in comments)
RA 2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  131 INITIATING CUE:
Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position.  (Assume all medical, training requirements, and overtime limitations are met).
Operator #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.
01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 3.
02/12/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2.
02/13/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2.
03/13/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 3.
03/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
03/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
Operator #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1.
01/21/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1.
02/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
02/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
Operator #1 can / cannot stand the position because
________________________________________
  (Circle one)
_________________________________________________________________________________________.
Operator #2 can / cannot stand the position because
________________________________________
  (Circle one)
_________________________________________________________________________________________.
CANDIDATE RA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 132 JPM BASIS INFORMATION TASK: 1290310301 Perform a Tech Review of a Permit TASK STANDARD: Tech Review a Permit and determine three errors with the permit.
K/A: 2.2.13 K/A RATING: RO:
4.1 SRO: 4.3 K/A: K/A RATING: RO:
SRO: APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes  


==REFERENCES:==
==REFERENCES:==
40DP-9OP29, Permit and Tagging Process Rev 35, Drawings 01-E-DWB-01 & 01-M-DWP-02 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Tom Stahler Date: 05/03/2003 Revised By: Alan Malley Date: 05/19/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40DP-9OP29, Permit and Tagging Process Rev 35, Drawings 01-E-DWB-01 & 01-M-DWP-02 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR             X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Tom Stahler                   Date:   05/03/2003 Revised By:       Alan Malley                   Date:   05/19/2009 Technical Review                                 Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                   PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                     Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
132                                    Revised 9/20/08


RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 133 14. SIMULATOR SETUP:
RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
EEE. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 14.     SIMULATOR SETUP:
FFF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
EEE. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 31. N/A 32. 33. 34. GGG. SPECIAL INSTRUCTIONS: None HHH. REQUIRED CONDITIONS: None III. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
FFF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                     DESCRIPTION
: 14. SPECIAL TOOLS/EQUIPMENT: 40DP-9OP29, Permit and Tagging Process Rev 35,   Drawing 01-E-DWB-01   Drawing 01-M-DWP-02  
: 31.         N/A 32.
33.
34.
GGG. SPECIAL INSTRUCTIONS:
* None HHH. REQUIRED CONDITIONS:
* None III. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 14. SPECIAL TOOLS/EQUIPMENT:
* 40DP-9OP29, Permit and Tagging Process Rev 35,
* Drawing 01-E-DWB-01
* Drawing 01-M-DWP-02 133


RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 134 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
ALL JPMs You may use any source of information normally available.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
INITIATING CUE:
Unit 1 is 100% power The 'B' Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water. Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.
Unit 1 is 100% power The B Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water.
The CRS has directed you to perform Tech Review of Permit 1-110909-1. Identify three (3) errors (Non-clerica l - not typos) on the permit.
Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.
The CRS has directed you to perform Tech Review of Permit 1-110909-1.
* Identify three (3) errors (Non-clerical - not typos) on the permit.
INFORMATION FOR EVALUATOR'S USE:
INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* Denotes Critical Step
RA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  135 JPM START TIME:
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
STEP CUE STANDARD 1. Reviews Permit or Work Order to determine scope of work to be performed. Examinee reviews Permit or Work Order and determines work scope to be replacing gasket on 1P-DWN-V050.
* Any step marked UNSAT requires comments.
SAT / UNSAT Comments (required for UNSAT):
* If this is the first JPM of the set then ensure the examinee has been briefed.
 
* Step sequence is not critical unless noted or will prevent achieving the task standard.
STEP CUE STANDARD 2.
* Notify unit Shift Manager of in-plant JPM performance.
* Identifies one (1) error on the permit. Tag 2 has the wrong circuit breaker identified.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
Examinee determines the following
* Locked valves may be involved. No attempt will be made to actually operate any valves.
 
134
inaccuracy/inadequacy. Tag 2 is the wrong circuit breaker (breaker is for the "A" pump)


RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                          CUE                      STANDARD
: 1.      Reviews Permit or Work Order to                          Examinee reviews Permit or Work Order determine scope of work to be                            and determines work scope to be replacing performed.                                              gasket on 1P-DWN-V050.
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                      STANDARD
: 2.
* Identifies one (1) error on the permit.                  Examinee determines the following Tag 2 has the wrong circuit breaker                      inaccuracy/inadequacy.
identified.
* Tag 2 is the wrong circuit breaker (breaker is for the A pump)
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
STEP                           CUE                       STANDARD
STEP CUE STANDARD 3.
: 3.
* Identifies one (1) error on the permit.
* Identifies one (1) error on the permit.                  Examinee determines the following inaccuracy/inadequacy.
Tag 5 has the wrong position (open) for the discharge valve.
Tag 5 has the wrong position (open)
Examinee determines the following
* Tag 5 has wrong position (OPEN) for for the discharge valve.
 
the discharge valve.
inaccuracy/inadequacy. Tag 5 has wrong position (OPEN) for the discharge valve.  
 
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
135
RA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  136  STEP CUE STANDARD 4.
* Identifies one (1) error on the permit. Tag 7 has the right valve number, but the wrong system designator.
Examinee determines the following
 
inaccuracy/inadequacy. Tag 7 has right valve number but wrong system designator (DS).


RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                          CUE                      STANDARD
: 4.
* Identifies one (1) error on the permit.                  Examinee determines the following inaccuracy/inadequacy.
Tag 7 has the right valve number, but
* Tag 7 has right valve number but the wrong system designator.
wrong system designator (DS).
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 136


RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 137  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1 05/19/2009 6 Update format to new JPM format. Revise numbering for 2009 NRC exam.
RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION       REVISION        REASON NUMBER           DATE           REVISED                               COMMENTS 1           05/19/2009           6         Update format to new JPM format. Revise numbering for 2009 NRC exam.
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered  
REASON REVISED           Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 79. Vendor reference document upgrade
: 80. Plant modification (include number)
: 81. Procedure upgrade
: 82. Internal or External Agency Commitment (indicate item number)
: 83. Technical Specification Change (indicate amendment number)
: 84. Other (explain in comments) 137


consecutively in each revision.
RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam CANDIDATE INITIATING CUE:
: 79. Vendor reference document upgrade
Unit 1 is 100% power The B Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water.
: 80. Plant modification (include number)  
Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.
: 81. Procedure upgrade
The CRS has directed you to perform Tech Review of Permit 1-110909-1.
: 82. Internal or External Agency Commitment (indicate item number)  
* Identify three (3) errors (Non-clerical - not typos) on the permit.
: 83. Technical Specification Change (indicate amendment number)  
CANDIDATE 138
: 84. Other (explain in comments)  


RA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  138  CANDIDATE
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine RP entry requirements to operate a valve.
 
K/A: 2.3.13                                       K/A RATING:       RO:   3.4   SRO: 3.8 K/A:                                               K/A RATING:       RO:         SRO:
INITIATING CUE:
APPLICABLE POSITION(S):             RO             VALIDATION TIME:         20 minutes
Unit 1 is 100% power The 'B' Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water. Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.
The CRS has directed you to perform Tech Review of Permit 1-110909-1. Identify three (3) errors (Non-clerica l - not typos) on the permit.
 
CANDIDATE RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 139 JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine RP entry requirements to operate a valve.
K/A: 2.3.13 K/A RATING: RO:
3.4 SRO: 3.8 K/A: K/A RATING: RO:
SRO: APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes  


==REFERENCES:==
==REFERENCES:==
NGW01, Initial Radiation Worker Practices; 75DP-9RP01 Radiation Exposure and Access Control Rev 16 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 05/13/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
NGW01, Initial Radiation Worker Practices; 75DP-9RP01 Radiation Exposure and Access Control Rev 16 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR           X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   05/13/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
139                                  Revised 9/20/08


RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 140 15. SIMULATOR SETUP:
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
JJJ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 15.     SIMULATOR SETUP:
KKK. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
JJJ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 35. N/A 36. 37. 38. LLL. SPECIAL INSTRUCTIONS: None MMM. REQUIRED CONDITIONS: None NNN. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
KKK. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                   DESCRIPTION
: 15. SPECIAL TOOLS/EQUIPMENT:  
: 35.       N/A 36.
: a. Survey map
37.
: b. 75DP-9RP01 Radiation Exposur e and Access Control Rev 16  
38.
: c. Calculator  
LLL. SPECIAL INSTRUCTIONS:
* None MMM. REQUIRED CONDITIONS:
* None NNN. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 15. SPECIAL TOOLS/EQUIPMENT:
: a. Survey map
: b. 75DP-9RP01 Radiation Exposure and Access Control Rev 16
: c. Calculator 140


RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 141 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
ALL JPMs You may use any source of information normally available.
ALL JPMs
INITIATING CUE: Your dose exposure this year has been 664 mrem. Unit 1 is coming out of a refueling outage. Restoration of the Train 'A' Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress. You are assigned the task of venting the EW side of the SDCHX through EWA-V020. Determine the following:  
* You may use any source of information normally available.
: 1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verde's first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.) ANSWER ____________________  
INITIATING CUE:
: 2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room). Radiation area   High radiation area   Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area  
* Your dose exposure this year has been 664 mrem.
: 3) What are the requirements to enter this area? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room). Double PCs   Single PCs   Respirator   Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry  
* Unit 1 is coming out of a refueling outage.
* Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
* You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
* Determine the following:
: 1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)
ANSWER ____________________
: 2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
Radiation area High radiation area Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area
: 3) What are the requirements to enter this area? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
Double PCs Single PCs Respirator Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry 141


RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 142  INFORMATION FOR EVALUATOR'S USE:
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* Denotes Critical Step
RA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  143 JPM START TIME:
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
142


STEP CUE STANDARD 1.
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
* How many minutes (MAXIMUM) can you stay in  
STEP                         CUE                     STANDARD
: 1.
* How many minutes                                       Examinee reviews RP map and (MAXIMUM) can you stay in                             determines highest radiation reading is the area with the highest dose                        1140 mr/hr since there is no other rate without exceeding Palo                            designation per note 1 on the map.
Verdes first administrative limit                    Examinee may refer to 75DP-9RP01 to per 75DP-9RP01?                                        determine first administrative limit is 1.5 rem/yr. Since the examinee already has 664 mrem this year (per the cue) he/she may only receive 836 mrem for the rest of the year. In a radiation field of 1140 mrem/hr, the dose is 19mr/min, therefore 836 mrem/19 mrem/hr equals 44 minutes.
Answer: 44 minutes (or .73 hours).
SAT / UNSAT Comments (required for UNSAT):
STEP                          CUE                      STANDARD
: 2.
* What type of radiation posting                          Examinee should check the following:
should this are have? Check only those that apply to the area you will
* Contamination Area need to access.
* Locked High Radiation Area
* Could include Radiation area, but this is not critical.
SAT / UNSAT Comments (required for UNSAT):
143


the area with the highest dose
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                        CUE                  STANDARD
: 3.
* What are the requirements to enter                    Examinee should check the following:
this area? Check only those that apply to the area you will need to
* Continuous RP coverage or Stay Times.
access?
* Briefing by RP
* Single PCs SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
NORMAL TERMINATION POINT 144


rate without exceeding Palo Verde's first administrative limit
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY INITIATING CUE:
 
* Your dose exposure this year has been 664 mrem.
per 75DP-9RP01?
* Unit 1 is coming out of a refueling outage.
Examinee reviews RP map and determines highest radiation reading is 1140 mr/hr since there is no other designation per note 1 on the map.
* Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
Examinee may refer to 75DP-9RP01 to determine first administrative limit is 1.5 rem/yr. Since the examinee already has 664 mrem this year (per the cue) he/she may only receive 836 mrem for the rest of the year. In a radiation field of 1140 mrem/hr, the dose is 19mr/min, therefore 836 mrem/19 mrem/hr equals 44 minutes. Answer: 44 minutes (or .73 hours).  
* You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
 
* Determine the following:
SAT / UNSAT Comments (required for UNSAT):  
: 1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)
 
ANSWER ___44 minutes or 0.73 hours_______________
STEP CUE STANDARD 2.
: 2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
* What type of radiation posting should this are have? Check only those that apply to the area you will  
Radiation area High radiation area X      Locked High Radiation area Very High Radiation area X      Contamination area High Contamination area Airborne radiation area Hot particle area
 
: 3) What are the requirements to enter this area? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
need to access.
Double PCs X      Single PCs Respirator X      Briefing by RP Emergency Dosimetry Portable Dose Rate Meter X      Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry ANSWER KEY 145
Examinee should check the following:  Contamination Area  Locked High Radiation Area  Could include Radiation area, but this is not critical.
SAT / UNSAT Comments (required for UNSAT):


RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 144  STEP CUE STANDARD 3.
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          05/13/2009            6        New JPM REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
* What are the requirements to enter this area? Check only those that apply to the area you will need to  
: 85. Vendor reference document upgrade
: 86. Plant modification (include number)
: 87. Procedure upgrade
: 88. Internal or External Agency Commitment (indicate item number)
: 89. Technical Specification Change (indicate amendment number)
: 90. Other (explain in comments) 146


access? Examinee should check the following: Continuous RP coverage or Stay Times. Briefing by RP  Single PCs SAT / UNSAT Comments (required for UNSAT):
RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
* Your dose exposure this year has been 664 mrem.
* Unit 1 is coming out of a refueling outage.
* Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
* You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
* Determine the following:
: 1) How many minutes can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)
ANSWER ____________________________
: 2) What type of radiation posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
Radiation area High radiation area Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area
: 3) What are the requirements to enter this area? Check only those that apply to the area you will need to access perform the venting (not all areas of the room).
Double PCs Single PCs Respirator Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry CANDIDATE 147


JPM STOP TIME:
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active and which operator can stand shift as a Reactor Operator. Determine if shift staffing is met K/A: 2.1.4                                         K/A RATING:         RO:   3.3   SRO: 3.8 K/A: 2.1.5                                         K/A RATING:         RO:   2.9   SRO: 3.9 APPLICABLE POSITION(S):             SRO             VALIDATION TIME:             20 minutes
NORMAL TERMINATION POINT
 
RA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  145  ANSWER KEY INITIATING CUE:
Your dose exposure this year has been 664 mrem. Unit 1 is coming out of a refueling outage. Restoration of the Train 'A' Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress. You are assigned the task of venting the EW side of the SDCHX through EWA-V020. Determine the following:
: 1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verde's first administrative limit per 75DP-9RP01?  (Assume you are not a Declared Pregnant Woman or a Decl ared Fertile Woman.)  ANSWER ___44 minutes or 0.73 hours_______________
: 2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).
Radiation area High radiation area X Locked High Radiation area Very High Radiation area X Contamination area High Contamination area Airborne radiation area Hot particle area
: 3) What are the requirements to enter this area? Check on ly those that apply to the area you will need to access to perform the venting (not all areas of the room).
Double PCs X Single PCs Respirator X Briefing by RP Emergency Dosimetry Portable Dose Rate Meter X Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry ANSWER KEY RA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  146  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 05/13/2009 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
 
consecutively in each revision.
: 85. Vendor reference document upgrade
: 86. Plant modification (include number)
: 87. Procedure upgrade
: 88. Internal or External Agency Commitment (indicate item number)
: 89. Technical Specification Change (indicate amendment number)
: 90. Other (explain in comments)
RA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  147 INITIATING CUE:
Your dose exposure this year has been 664 mrem. Unit 1 is coming out of a refueling outage. Restoration of the Train 'A' Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress. You are assigned the task of venting the EW side of the SDCHX through EWA-V020. Determine the following:
: 1) How many minutes can you stay in the area with the highest dose rate without exceeding Palo Verde's first administrative limit per 75DP-9RP01?  (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)
ANSWER ____________________________
: 2) What type of radiation posting should this area have? Check only those that apply to the area you will need to access to perform th e venting (not all areas of the room).
Radiation area High radiation area Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area
: 3) What are the requirements to enter this area?
Check only those that apply to the area you will need to access perform the venting (not all areas of the room).
Double PCs Single PCs Respirator Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry CANDIDATE SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 04/22/08 148 JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active a nd which operator can stand shift as a Reactor Operator. Determine if shift staffing is met K/A: 2.1.4 K/A RATING: RO:
3.3 SRO: 3.8 K/A: 2.1.5 K/A RATING: RO:
2.9 SRO: 3.9 APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes  


==REFERENCES:==
==REFERENCES:==
40OP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
40OP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR               X     PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)           No APPROVAL Developed By:     Alan Malley                     Date:     04/17/2009 Revised By:       N/A                             Date:     N/A Technical Review                                   Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                     PLANT TESTING METHOD:                           SIMULATE                     PERFORM EVALUATION Examinee Name:                                                       Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes           GRADE (Circle   One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
148                                      Revised 04/22/08


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 149 16. SIMULATOR SETUP:
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
OOO. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 16.     SIMULATOR SETUP:
PPP. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
OOO. IC#: N/A (May be performed in the simulator or classroom, NO setup required)
: 39. N/A 40. 41. 42. QQQ. SPECIAL INSTRUCTIONS: None RRR. REQUIRED CONDITIONS: None SSS. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
PPP. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                   DESCRIPTION
: 16. SPECIAL TOOLS/EQUIPMENT:  
: 39.       N/A 40.
: a. Copy of Conduct of Shift Op erations, 40DP-9OP02, Rev 46  
41.
42.
QQQ. SPECIAL INSTRUCTIONS:
* None RRR.REQUIRED CONDITIONS:
* None SSS. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 16. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of Conduct of Shift Operations, 40DP-9OP02, Rev 46 149


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 150 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
ALL JPM's You may use any source of information normally available.
ALL JPMs
* You may use any source of information normally available.
INITIATING CUE:
INITIATING CUE:
Given the attached history of 2 Licensed opera tors and the planned shift manning perform the following: Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009. State the reason why they can or cannot stand th e position. (Assume all medical, training requirements, and overtime limitations are met). Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verde's staffing requirements. A ssume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highlighted operators.
Given the attached history of 2 Licensed operators and the planned shift manning perform the following:
* Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009.
* State the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).
* Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verdes staffing requirements. Assume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highlighted operators.
Use the following to document you answers
Use the following to document you answers
: 1. RO #1 can / cannot stand the position because
: 1. RO #1 can / cannot stand the position because ________________________________
________________________________  
(Circle one)
(Circle one)
: 2. RO #2 can / cannot stand the position because _______________________________
_______________________________________________________________________________.
(Circle one)
: 2. RO #2 can / cannot stand the position because
: 3. Staffing requirements are / are not met.
_______________________________  
(Circle one)
(Circle one)
_______________________________________________________________________________.
: 3. Staffing requirements are / are not met.  
(Circle one)  
: 4. If staffing requirements are not met, they can be met by _________________
: 4. If staffing requirements are not met, they can be met by _________________
___________________________________________________________________.
150


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 151 Operator License History RO #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project. 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 03/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Operator License History RO #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.
RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.  
01/20/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 3.
02/12/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
02/13/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
03/13/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 3.
03/25/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
03/26/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
01/21/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
02/25/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
02/26/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
151


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 152 PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position Unit 1 Unit 2 Unit 3 SM SRO SRO SRO CRS SRO SRO SRO STA STA STA STA Reactor Operator RO #1 RO #2 RO Control Operator RO RO RO 3 rd Reactor Operator Vacant Vacant SRO Area 1 AO AO RO Area 2 AO AO AO Area 3 AO AO AO Area 4 AO AO AO Radwaste AO  
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position             Unit 1             Unit 2     Unit 3 SM                   SRO               SRO         SRO CRS                   SRO               SRO         SRO STA                   STA               STA         STA Reactor Operator     RO #1             RO #2       RO Control Operator     RO                 RO         RO 3rd Reactor Operator Vacant             Vacant     SRO Area 1               AO                 AO         RO Area 2               AO                 AO         AO Area 3               AO                 AO         AO Area 4               AO                 AO         AO Radwaste             AO 152


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 153  INFORMATION FOR EVALUATOR'S USE:
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* Denotes Critical Step
SA 2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  154 JPM START TIME:
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
153


STEP CUE STANDARD 1. Obtain 40DP-9OP02, Conduct of Shift Operations.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
Obtain 40DP-9OP02, Conduct of Shift Operations.
STEP                         CUE                     STANDARD
SAT / UNSAT Comments (required for UNSAT):  
: 1.     Obtain 40DP-9OP02, Conduct of                       Obtain 40DP-9OP02, Conduct of Shift Shift Operations.                                    Operations.
 
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 2.
STEP                         CUE                     STANDARD
* The examinee determines that #1 cannot stand the shift and the  
: 2.
 
* The examinee determines that #1                     The examinee states the following cannot stand the shift and the                       reason for operator #1 not being able to reason.                                              stand shift.
reason. The examinee states the following reason for operator #1 not being able to  
Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift.
 
SAT / UNSAT Comments (required for UNSAT):
stand shift.
STEP                         CUE                     STANDARD
Operator #1 did not complete 60 hours on shift because 12 of his/her hours  
: 3.
 
* The examinee determines                             The examinee states the following operator #2 can stand the shift                     reason for operator #2 being able to and the reason.                                      stand shift.
were not on one shift.
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
154
STEP CUE STANDARD 3.
* The examinee determines operator #2 can stand the shift  
 
and the reason.
The examinee states the following reason for operator #2 being able to  
 
stand shift.
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60  


hours. SAT / UNSAT Comments (required for UNSAT):
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                       CUE                     STANDARD
 
: 4.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 155  STEP CUE STANDARD 4.
* Determine if staffing                               The examinee determines that Unit 1 requirements are met and what                       would not have the required number of actions would be necessary (if                     reactor operators.
* Determine if staffing requirements are met and what actions would be necessary (if any) to meet Palo Verde's staffing requirements (with the following crew manning list).
any) to meet Palo Verdes staffing What could be done?
The examinee determines that Unit 1 would not have the required number of
requirements (with the following crew manning list).                                 Answer #1 Could move SRO (3rd Reactor Operator from Unit 3) to fill a reactor operator position in Unit #1.
 
reactor operators.
What could be done?
Answer #1 Could move SRO (3 rd Reactor Operator from Unit 3) to fill a reactor operator position in Unit #1.
Answer #2 Could call in another reactor operator to man Unit #1.
Answer #2 Could call in another reactor operator to man Unit #1.
Either answer is acceptable.
Either answer is acceptable.
SAT / UNSAT Comments (required for UNSAT):  
SAT / UNSAT Comments (required for UNSAT):
 
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 155


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 156 ANSWER KEY  
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY
: 1. Operator #1 can / cannot stand the position because
: 1. Operator #1 can / cannot stand the position because :
:  Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift.
Operator #1 did not complete 60 hours on shift because 12 of his/her hours were not on one shift.
: 2. Operator #2 can / cannot stand the position because:
: 2. Operator #2 can / cannot stand the position because:
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours.
Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours.
: 3. Staffing requirements are / are not met.  
: 3. Staffing requirements are / are not met.
(Circle one)  
(Circle one)
: 4. If staffing requirements are not met, they can be met by: (Either answer acceptable) Could move SRO or RO from Unit 3 to fill a reactor operator position in Unit #1.
: 4. If staffing requirements are not met, they can be met by: (Either answer acceptable)
Could call in another reactor operator to man Unit #1.
* Could move SRO or RO from Unit 3 to fill a reactor operator position in Unit #1.
* Could call in another reactor operator to man Unit #1.
ANSWER KEY 156


ANSWER KEY
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          04/17/2009            6        New JPM REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 91. Vendor reference document upgrade
: 92. Plant modification (include number)
: 93. Procedure upgrade
: 94. Internal or External Agency Commitment (indicate item number)
: 95. Technical Specification Change (indicate amendment number)
: 96. Other (explain in comments) 157


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 157  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 04/17/2009 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
Given the attached history of 2 Licensed operators and the planned shift manning perform the following:
* Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009.
* State the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).
* Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verdes staffing requirements. Assume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highligh9+1ted operators.
Use the following to document you answers
: 1. RO #1 can / cannot stand the position because ________________________________
(Circle one)
: 2. RO #2 can / cannot stand the position because _______________________________
(Circle one)
: 3. Staffing requirements are / are not met.
(Circle one)
: 4. If staffing requirements are not met, they can be met by _________________
CANDIDATE 158


consecutively in each revision.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Operator License History RO #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.
: 91. Vendor reference document upgrade
01/20/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 3.
: 92. Plant modification (include number)
02/12/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
: 93. Procedure upgrade
02/13/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 2.
: 94. Internal or External Agency Commitment (indicate item number)
03/13/2009 Stood 4 hour shift as 3rd Reactor Operator in Unit 3.
: 95. Technical Specification Change (indicate amendment number)
03/25/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
: 96. Other (explain in comments)
03/31/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 158 INITIATING CUE:
RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
Given the attached history of 2 Licensed operators and the planned shift manning perform the following:  Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009. State the reason why they can or canno t stand the position. (Assume all medical, training requirements, and overtime limitations are met). Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verde's staffi ng requirements. Assume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highligh9+1ted operators.
01/21/2009 Stood 12 hour shift as 3rd Reactor Operator in Unit 1.
Use the following to document you answers
02/25/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
: 1. RO #1 can / cannot stand the position because
02/26/2009 Stood 12 hour shift as 2nd Reactor Operator in Unit 1.
________________________________
CANDIDATE 159
(Circle one)
_______________________________________________________________________________.  
: 2. RO #2 can / cannot stand the position because
_______________________________
(Circle one)
_______________________________________________________________________________.  
: 3. Staffing requirements are / are not met.  
(Circle one)
: 4. If staffing requirements are not met, they can be met by _________________
___________________________________________________________________.
CANDIDATE  


SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 159 Operator License History RO #1  12/21/2008 Operator taken off-shift to support the procedure upgrade project. 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 03/31/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position           Unit 1             Unit 2     Unit 3 SM                 SRO               SRO         SRO CRS               SRO               SRO         SRO STA               STA               STA         STA Reactor Operator   RO #1             RO #2       RO Control Operator   RO                 RO         RO 3rd Reactor       Vacant             Vacant     SRO Operator Area 1             AO                 AO         RO Area 2             AO                 AO         AO Area 3             AO                 AO         AO Area 4             AO                 AO         AO Radwaste           AO CANDIDATE 160
RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour shift as 2 nd Reactor Operator in Unit 1.
CANDIDATE SA 2  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  160  PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position Unit 1 Unit 2 Unit 3 SM SRO SRO SRO CRS SRO SRO SRO STA STA STA STA Reactor Operator RO #1 RO #2 RO Control Operator RO RO RO 3 rd Reactor Operator Vacant Vacant SRO Area 1 AO AO RO Area 2 AO AO AO Area 3 AO AO AO Area 4 AO AO AO Radwaste AO CANDIDATE  


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 161 JPM BASIS INFORMATION TASK: 1290190102 Ensure compliance with Tech Specs TASK STANDARD: Identify applicable LCO / LCO conditions and completion times.
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290190102 Ensure compliance with Tech Specs TASK STANDARD: Identify applicable LCO / LCO conditions and completion times.
K/A: 2.2.40 K/A RATING: RO:
K/A: 2.2.40                                       K/A RATING:       RO:   3.4   SRO:   4.7 K/A:                                               K/A RATING:       RO:         SRO:
3.4 SRO: 4.7 K/A: K/A RATING: RO:
APPLICABLE POSITION(S):             SRO           VALIDATION TIME:         20 minutes
SRO: APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes  


==REFERENCES:==
==REFERENCES:==
Technical Specifications SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 04/23/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
Technical Specifications SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR                 PLANT JPM TYPE Time Critical? (Yes/No)     No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                   Date:   04/23/2009 Revised By:       N/A                           Date:   N/A Technical Review                                 Operations Approval E-Plan Review                     N/A             Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:               SIMULATOR                 PLANT TESTING METHOD:                           SIMULATE                   PERFORM EVALUATION Examinee Name:                                                   Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
161                                  Revised 9/20/08


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 162 17. SIMULATOR SETUP:
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
TTT. IC#: N/A UUU. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 17.     SIMULATOR SETUP:
: 43. N/A 44. 45. 46. VVV. SPECIAL INSTRUCTIONS: None WWW. REQUIRED CONDITIONS: None XXX. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
TTT. IC#: N/A UUU. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                   DESCRIPTION
: 17. SPECIAL TOOLS/EQUIPMENT:  
: 43.       N/A 44.
: a. Copy of Tech Specs  
45.
: b. Copy of print 01-E-SIB-0001  
46.
: c. Copy of 40OP-9PB01  
VVV. SPECIAL INSTRUCTIONS:
* None WWW. REQUIRED CONDITIONS:
* None XXX. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 17. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of Tech Specs
: b. Copy of print 01-E-SIB-0001
: c. Copy of 40OP-9PB01 162


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 163 INFORMATION PRESENTED TO EXAMINEE:
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
 
IN PLANT JPM's ONLY
IN PLANT JPM's ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL JPM's You may use any source of information normally available.
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
SA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 164 INITIATING CUE:
* Inform the control room staff of any discovered deficiencies.
 
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
Given the following plant conditions in Unit 3 on the same day:  Unit 3 is at 100% power.
ALL JPMs
Event 1  At 1315 the area operator reports oil all over the floor of the 'B' High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler. Maintenance has investigated the 'B' HPSI pump and determined it will take 2 hours to repair the oil leak.
* You may use any source of information normally available.
Event 2  At 1427 a SESS alarm comes in for the 'A' Low Pressure Safety Injection pump (SIA-P01). The control room indication for the 'A
163
' LPSI pump breaker has been lost. The area operator reports that all lights are off at the breaker for the 'A' LPSI pump with the breaker open.
Determine any applicable LCO(s) and TLCO(s) and completion time(s).   
(Assume Event 1 is still in progress when Event 2 occurs.)


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
Given the following plant conditions in Unit 3 on the same day:
* Unit 3 is at 100% power.
Event 1
* At 1315 the area operator reports oil all over the floor of the B High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler.
* Maintenance has investigated the B HPSI pump and determined it will take 2 hours to repair the oil leak.
Event 2
* At 1427 a SESS alarm comes in for the A Low Pressure Safety Injection pump (SIA-P01).
* The control room indication for the A LPSI pump breaker has been lost.
* The area operator reports that all lights are off at the breaker for the A LPSI pump with the breaker open.
Determine any applicable LCO(s) and TLCO(s) and completion time(s).
(Assume Event 1 is still in progress when Event 2 occurs.)
Use the following to document your answers:
Use the following to document your answers:
At time: Enter LCO condition(s) (if applicable)
At time:     Enter LCO condition(s)       Completion    Enter TLCO condition(s)       Completion time(s)                                       time(s)
Completion time(s) Enter TLCO condition(s) (if applicable)
(if applicable)                             (if applicable) 1315 Event 1 1427 Event 2 164
Completion time(s) 1315 Event 1     1427 Event 2 SA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 165  INFORMATION FOR EVALUATOR'S USE:
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
SA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  166 JPM START TIME:
STEP CUE STANDARD 1.
* The examinee refers to Tech Specs and the TRM (Technical Requirements Manual).
The examinee determines the applicable LCO is LCO 3.5.3 condition B and the completion time is 72 hours.
SAT / UNSAT Comments (required for UNSAT):


STEP CUE STANDARD 2.
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
* Determine the applicable LCO(s) / TLCO(s) and completion times, if any for time 1315.
* Denotes Critical Step
The examinee determines the applicable LCO is LCO 3.5.3 condition B and the completion time is 72 hours.
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
SAT / UNSAT Comments (required for UNSAT):
* Any step marked UNSAT requires comments.
 
* If this is the first JPM of the set then ensure the examinee has been briefed.
STEP CUE STANDARD 3.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Determine the applicable LCO(s) / TLCO(s) and completion times, if any for time 1427 The examinee determines the applicable LCO is 3.5.3 condition A and the completion time is 7 days. The examinee determines the applicable TLCO is 3.5.201 condition A and the completion time is 7 days.
* Notify unit Shift Manager of in-plant JPM performance.
SAT / UNSAT Comments (required for UNSAT):
* Performance of this JPM may require entry into areas with alarmed doors.               Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
165


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                      CUE                    STANDARD
: 1.
* The examinee refers to Tech                        The examinee determines the applicable Specs and the TRM (Technical                      LCO is LCO 3.5.3 condition B and the Requirements Manual).                              completion time is 72 hours.
SAT / UNSAT Comments (required for UNSAT):
STEP                      CUE                    STANDARD
: 2.
* Determine the applicable LCO(s)                    The examinee determines the applicable
        / TLCO(s) and completion times,                    LCO is LCO 3.5.3 condition B and the if any for time 1315.                              completion time is 72 hours.
SAT / UNSAT Comments (required for UNSAT):
STEP                      CUE                    STANDARD
: 3.
* Determine the applicable LCO(s)                    The examinee determines the applicable
        / TLCO(s) and completion times,                    LCO is 3.5.3 condition A and the if any for time 1427                              completion time is 7 days.
The examinee determines the applicable TLCO is 3.5.201 condition A and the completion time is 7 days.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 166


SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 167  
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY At time: Enter LCO          Completion    Enter TLCO      Completion condition(s)        time(s)        condition(s)    time(s)
(if applicable)                    (if applicable) 1315    LCO 3.5.3          72 hours      N/A            N/A condition B Event 1 1427    LCO 3.5.3          7 days        TLCO 3.5.201    7 days condition A                        Condition A Event 2 ANSWER KEY 167


ANSWER KEY
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          04/23/2009            6        New record REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
: 97. Vendor reference document upgrade
: 98. Plant modification (include number)
: 99. Procedure upgrade 100. Internal or External Agency Commitment (indicate item number) 101. Technical Specification Change (indicate amendment number) 102. Other (explain in comments) 168


At time: Enter LCO condition(s) (if applicable)
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
Completion time(s)  Enter TLCO condition(s)  (if applicable)
Given the following plant conditions in Unit 3 on the same day:
Completion time(s) 1315 Event 1  LCO 3.5.3 condition B 72 hours N/A N/A 1427 Event 2  LCO 3.5.3 condition A 7 days TLCO 3.5.201 Condition A 7 days 
* Unit 3 is at 100% power.
 
Event 1
ANSWER KEY
* At 1315 the area operator reports oil all over the floor of the B High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler.
 
* Maintenance has investigated the B HPSI pump and determined it will take 2 hours to repair the oil leak.
SA 3  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  168  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 04/23/2009 6 New record REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
Event 2
 
* At 1427 a SESS alarm comes in for the A Low Pressure Safety Injection pump (SIA-P01).
consecutively in each revision.
* The control room indication for the A LPSI pump breaker has been lost.
: 97. Vendor reference document upgrade
* The area operator reports that all lights are off at the breaker for the A LPSI pump with the breaker open.
: 98. Plant modification (include number)
Determine any applicable LCO(s) and TLCO(s) and completion time(s).
: 99. Procedure upgrade 100. Internal or External Agency Commitment (indicate item number) 101. Technical Specification Change (indicate amendment number) 102. Other (explain in comments)
(Assume Event 1 is still in progress when Event 2 occurs.)
SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 169  INITIATING CUE:
Use the following to document your answers:
Given the following plant conditions in Unit 3 on the same day: Unit 3 is at 100% power.
At time:     Enter LCO condition(s)     Completion            Enter TLCO condition(s)             Completion time(s)                                                     time(s)
Event 1 At 1315 the area operator reports oil all over the floor of the 'B' High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler. Maintenance has investigated the 'B' HPSI pump and determined it will take 2 hours to repair the oil leak.
(if applicable)                                   (if applicable) 1315 Event 1 1427 Event 2 CANDIDATE 169
Event 2 At 1427 a SESS alarm comes in for the 'A' Low Pressure Safety Injection pump (SIA-P01). The control room indication for the 'A
' LPSI pump breaker has been lost. The area operator reports that a ll lights are off at the breaker for the 'A' LPSI pump with the breaker open.
Determine any applicable LCO(s) and TLCO(s) and completion time(s).   (Assume Event 1 is still in progress when Event 2 occurs.) Use the following to document your answers:
At time: Enter LCO condition(s) (if applicable)
Completion time(s) Enter TLCO condition(s) (if applicable)
Completion time(s) 1315 Event 1     1427 Event 2       CANDIDATE  


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 170 JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine exposure, stay time, develop Pre-Job Brief and determine who will provide a second check. K/A: 2.3.13 K/A RATING: RO:
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine exposure, stay time, develop Pre-Job Brief and determine who will provide a second check.
3.4 SRO: 3.8 K/A: K/A RATING: RO:
K/A: 2.3.13                                         K/A RATING:         RO:   3.4   SRO: 3.8 K/A:                                                 K/A RATING:         RO:         SRO:
SRO: APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes  
APPLICABLE POSITION(S):             SRO             VALIDATION TIME:           20 minutes


==REFERENCES:==
==REFERENCES:==
Technical Specifications SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT       JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No     APPROVAL Developed By: Jordan Johnston Date: 5/29/2007 Revised By: Alan Malley Date: 4/29/2009 Technical Review Operations Approval   E-Plan Review                 N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
Technical Specifications SUGGESTED TESTING ENVIRONMENT:                     SIMULATOR                   PLANT JPM TYPE Time Critical? (Yes/No)       No       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Jordan Johnston                 Date:   5/29/2007 Revised By:       Alan Malley                     Date:   4/29/2009 Technical Review                                   Operations Approval E-Plan Review                     N/A               Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:                 SIMULATOR                   PLANT TESTING METHOD:                             SIMULATE                   PERFORM EVALUATION Examinee Name:                                                       Date:
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
Evaluator Name:
Time to complete:                 Minutes           GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
170                                    Revised 9/20/08


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 171 18. SIMULATOR SETUP:
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
YYY. IC#: N/A ZZZ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 18.     SIMULATOR SETUP:
: 47. N/A 48. 49. 50. AAAA. SPECIAL INSTRUCTIONS: None BBBB. REQUIRED CONDITIONS: None CCCC. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters. NA if Simulator setup not required Verified by: ____________________________     Date: ____________________  
YYY. IC#: N/A ZZZ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT               COMMAND                                   DESCRIPTION
: 18. SPECIAL TOOLS/EQUIPMENT: 75DP-9RP01, Radiation Exposure and Access Control REP# 9-9999Z Survey map of SDC HX room. Calculator  
: 47.       N/A 48.
49.
50.
AAAA. SPECIAL INSTRUCTIONS:
* None BBBB. REQUIRED CONDITIONS:
* None CCCC. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.
NA if Simulator setup not required Verified by: ____________________________         Date: ____________________
: 18. SPECIAL TOOLS/EQUIPMENT:
* 75DP-9RP01, Radiation Exposure and Access Control
* REP# 9-9999Z
* Survey map of SDC HX room.
* Calculator 171


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 172 INFORMATION PRESENTED TO EXAMINEE:
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
IN PLANT JPM's ONLY
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
* Inform the control room staff of any discovered deficiencies.
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
ALL JPMs
* You may use any source of information normally available.
172


IN  PLANT JPM's ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL  JPM's You may use any source of information normally available.
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 173 INITIATING CUE:  
You are the Control Room Supervisor in Unit 1. Operations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work.
 
Radiation Protection has informed you that they will be using REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.
You are the Control Room Supervisor in Unit 1.
Operations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work. Radiation Protection has informed you that they will be using REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.
The operator assigned to the job has a current year to date exposure of 664 mr.
The operator assigned to the job has a current year to date exposure of 664 mr.
It is estimated to take 15 minutes to complete the venting.  
It is estimated to take 15 minutes to complete the venting.
 
Your task as the CRS is as follows:
Your task as the CRS is as follows:  
Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics:
 
* Task # to be used to perform the job.
Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics: Task # to be used to perform the job. How much dose is expected to be received by the operator Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded RP coverage that is required for this task. Given the exposure of other operators in th e table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is  
* How much dose is expected to be received by the operator
 
* Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded
closed after venting is completed. (Assume it will take two minutes to perform the  
* RP coverage that is required for this task.
 
* Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).
second check).
Note: This will not take the place of the pre-job brief with RP.
Note: This will not take the place of the pre-job brief with RP.
Operator Exposure history Other information 1 1489 mrem year to date 2 37 mrem this month Has declared she is attempting to become pregnant and has filled out a "Pre-Natal Dose Limit Statement".
Operator           Exposure history                     Other information 1             1489 mrem year to date 2           37 mrem this month       Has declared she is attempting to become pregnant and has filled out a Pre-Natal Dose Limit Statement.
3 420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.
3           420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.
SA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 174 Task #    Expected Dose Max Stay time before first admin hold point Expected amount of RP coverage Which operator should perform 2 nd check SA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 175  INFORMATION FOR EVALUATOR'S USE:
173
* Denotes Critical Step  At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard. Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
SA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  176 JPM START TIME:
STEP CUE STANDARD 1.
* Determine Task.
Examinee determines that Task 3 will be used. SAT / UNSAT Comments (required for UNSAT):


STEP CUE STANDARD 2.
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Task #
* Determine expected dose to be received.  (Based on the 15 minute stay time estimate given in the cue.)
Expected Dose Max Stay time before first admin hold point Expected amount of RP coverage Which operator should perform 2nd check 174
Determines 285 mrem will be received.
SAT / UNSAT Comments (required for UNSAT):


STEP CUE STANDARD 3.
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:
* Determine maximum stay time before the first administrative hold
* Denotes Critical Step
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Any step marked UNSAT requires comments.
* If this is the first JPM of the set then ensure the examinee has been briefed.
* Step sequence is not critical unless noted or will prevent achieving the task standard.
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.                Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
175


point is exceeded Determines that max stay time 44 minutes.
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
SAT / UNSAT Comments (required for UNSAT):  
STEP                        CUE                    STANDARD
 
: 1.
STEP CUE STANDARD 4.
* Determine Task.                                        Examinee determines that Task 3 will be used.
* Determine RP Coverage requirements per the REP.
SAT / UNSAT Comments (required for UNSAT):
Determines that the REP will require continuous RP coverage or stay time.
STEP                         CUE                     STANDARD
SAT / UNSAT Comments (required for UNSAT):  
: 2.
 
* Determine expected dose to be                          Determines 285 mrem will be received.
SA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  177  STEP CUE STANDARD 5.
received. (Based on the 15 minute stay time estimate given in the cue.)
* Determine which operator will perform the Independent Verification Determines that the operator 3 will perform
SAT / UNSAT Comments (required for UNSAT):
 
STEP                        CUE                    STANDARD
the independent ve rification because Operator 1 would exceed the first admin
: 3.
 
* Determine maximum stay time                            Determines that max stay time 44 minutes.
hold point and Operator 2 would exceed her dose limit due to declaring attempting to become pregnant. Only operator 3 would not exceed a dose limit of any type.
before the first administrative hold point is exceeded SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):  
STEP                         CUE                     STANDARD
: 4.
* Determine RP Coverage                                  Determines that the REP will require requirements per the REP.                               continuous RP coverage or stay time.
SAT / UNSAT Comments (required for UNSAT):
176


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP                        CUE                      STANDARD
: 5.
* Determine which operator will                        Determines that the operator 3 will perform perform the Independent Verification                the independent verification because Operator 1 would exceed the first admin hold point and Operator 2 would exceed her dose limit due to declaring attempting to become pregnant. Only operator 3 would not exceed a dose limit of any type.
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 177


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 178    ANSWER KEY  
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Task #              Task 3 Expected Dose      285 millirem Max Stay time      44 minutes before first admin hold point RP coverage        Continuous RP coverage or Stay time.
required by the REP for this task Which operator      Operator 3 should perform 2nd check ANSWER KEY 178


Task # Task 3  Expected Dose 285 millirem 44 minutes Max Stay time before first admin hold point Continuous RP coverage or Stay time.
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER            DATE          REVISED                                COMMENTS 0            5/29/2007            6        New record 1            4/29/2009            6        Modified record to different area, different cues, and different answers.
RP coverage required by the REP for this task Operator 3 Which operator should perform 2 nd check   
REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
103. Vendor reference document upgrade 104. Plant modification (include number) 105. Procedure upgrade 106. Internal or External Agency Commitment (indicate item number) 107. Technical Specification Change (indicate amendment number) 108. Other (explain in comments) 179


ANSWER KEY
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:
 
You are the Control Room Supervisor in Unit 1. Operations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work.
SA 4  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  179  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 5/29/2007 6 New record 1 4/29/2009 6  Modified record to different area, different cues, and different answers.
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
 
consecutively in each revision.
103. Vendor reference document upgrade 104. Plant modification (include number) 105. Procedure upgrade 106. Internal or External Agency Commitment (indicate item number) 107. Technical Specification Change (indicate amendment number) 108. Other (explain in comments)
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 180  INITIATING CUE:
You are the Control Room Supervisor in Unit 1. Op erations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work.
Radiation Protection has informed you that they will be using REP 9- REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.
Radiation Protection has informed you that they will be using REP 9- REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.
The operator assigned to the job has a current year to date exposure of 664 mr.
The operator assigned to the job has a current year to date exposure of 664 mr.
It is estimated to take 15 minutes to complete the venting.
It is estimated to take 15 minutes to complete the venting.
Your task as the CRS is as follows:
Your task as the CRS is as follows:
Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics: Task # to be used to perform the job. How much dose is expected to be received by the operator Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded. RP coverage that is required for this task. Given the exposure of other operators in the table be low, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).
Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics:
* Task # to be used to perform the job.
* How much dose is expected to be received by the operator
* Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded.
* RP coverage that is required for this task.
* Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed.
(Assume it will take two minutes to perform the second check).
Note: this will not take the place of the pre-job brief with RP.
Note: this will not take the place of the pre-job brief with RP.
Operator Exposure history Other information 1 1489 mrem year to date 2 37 mrem this month Has declared she is attempting to become pregnant and has filled out a "Pre-Natal Dose Limit Statement".
Operator               Exposure history                         Other information 1           1489 mrem year to date 2             37 mrem this month         Has declared she is attempting to become pregnant and has filled out a Pre-Natal Dose Limit Statement.
3 420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.  
3             420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.
180


SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 181 Task # to be used to perform the job. How much dose is expected to be received by the operator?
SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Task # to be used to perform the job.
How much dose is expected to be received by the operator?
Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded.
Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded.
RP coverage that is required for this task.
RP coverage that is required for this task.
Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).  
Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).
181


SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 182 JPM BASIS INFORMATION TASK: 1240100202 Classify events requiring emergency plan implementation TASK STANDARD: Emergency Action Level (EAL) is identified and Site Area Emergency classified. K/A: 2.4.41 K/A RATING: RO:
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240100202 Classify events requiring emergency plan implementation TASK STANDARD: Emergency Action Level (EAL) is identified and Site Area Emergency classified.
2.9 SRO: 4.6 APPLICABLE POSITION(S):     SRO VALIDATION TIME: 15 minutes  
K/A: 2.4.41                                         K/A RATING:         RO:   2.9   SRO: 4.6 APPLICABLE POSITION(S):               SRO           VALIDATION TIME:           15 minutes


==REFERENCES:==
==REFERENCES:==
EPIP-01, Satellite Technical Suppor t Center Actions (rev 30) and EPIP-99, EPIP Standard Appendices (Rev 26) SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT       JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) No     APPROVAL Developed By: Alan Malley Date: 4/21/2009 Revised By: N/A Date: N/A Technical Review Operations Approval   E-Plan Review Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT       TESTING METHOD: SIMULATE   PERFORM       EVALUATION Examinee Name:
EPIP-01, Satellite Technical Support Center Actions (rev 30) and EPIP-99, EPIP Standard Appendices (Rev 26)
Date:   Evaluator Name:   Time to complete: Minutes GRADE (Circle  One) SAT / UNSAT    For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
SUGGESTED TESTING ENVIRONMENT:                   SIMULATOR             X     PLANT JPM TYPE Time Critical? (Yes/No)     Yes       Alternative Path? (Yes/No)       No APPROVAL Developed By:     Alan Malley                     Date:   4/21/2009 Revised By:       N/A                             Date:   N/A Technical Review                                   Operations Approval E-Plan Review                                     Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT:                 SIMULATOR                   PLANT TESTING METHOD:                             SIMULATE                   PERFORM EVALUATION Examinee Name:                                                     Date:
Evaluator Name:
Time to complete:                 Minutes         GRADE (Circle  One)   SAT / UNSATc c
For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.
PVAR # _____________
PVAR # _____________
182


SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 183 19. SIMULATOR SETUP:  
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
: 20. IC#: This JPM is designed to be given after the 2009 NRC Scenario 3 DDDD. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION  
: 19.     SIMULATOR SETUP:
: 51. N/A   EEEE. SPECIAL INSTRUCTIONS: This JPM is designed to be given after the 2009 NRC Scenario 3 FFFF. REQUIRED CONDITIONS: NONE GGGG. SIMULATOR EVALUATION PRE-CHECK Scenario 3 is complete.  
: 20. IC#: This JPM is designed to be given after the 2009 NRC Scenario 3 DDDD. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT             COMMAND                                   DESCRIPTION
: 19. SPECIAL TOOLS/EQUIPMENT:  
: 51.       N/A EEEE. SPECIAL INSTRUCTIONS:
: a. Copy of EPIP-01, Satellite Technical Support Center Actions  
* This JPM is designed to be given after the 2009 NRC Scenario 3 FFFF. REQUIRED CONDITIONS:
: b. Copy of EPIP-99, EPIP Standard Appendices
* NONE GGGG. SIMULATOR EVALUATION PRE-CHECK Scenario 3 is complete.
: 19. SPECIAL TOOLS/EQUIPMENT:
: a. Copy of EPIP-01, Satellite Technical Support Center Actions
: b. Copy of EPIP-99, EPIP Standard Appendices 183


SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 184 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
SPECIAL CONSIDERATIONS:
 
IN PLANT JPM's ONLY
IN PLANT JPM's ONLY Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment. Inform the control room staff of any discovered deficiencies. Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas. ALL JPM's You may use any source of information normally available.
* Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
INITIATING CUE:  
* Inform the control room staff of any discovered deficiencies.
 
* Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.
Based on plant conditions at the conclusion of the scenario, perform the two following tasks:  
ALL JPMs
: 1. List the Emergency Action Level that is CURRENTLY met.
* You may use any source of information normally available.
INITIATING CUE:
Based on plant conditions at the conclusion of the scenario, perform the two following tasks:
: 1. List the Emergency Action Level that is CURRENTLY met.
: 2. List the Classification of this event.
: 2. List the Classification of this event.
THIS IS A TIME CRITICAL JPM  
THIS IS A TIME CRITICAL JPM INFORMATION FOR EVALUATOR'S USE:
 
* Denotes Critical Step
INFORMATION FOR EVALUATOR'S USE:
* At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
* Denotes Critical Step At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM. Any step marked UNSAT requires comments. If this is the first JPM of the set then ensure the examinee has been briefed. Step sequence is not critical unless noted or will prevent achieving the task standard.
* Any step marked UNSAT requires comments.
SA 5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 185 Notify unit Shift Manager of in-plant JPM performance. Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed. Locked valves may be involved. No attempt will be made to actually operate any valves.
* If this is the first JPM of the set then ensure the examinee has been briefed.
SA 5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  186 JPM START TIME:
* Step sequence is not critical unless noted or will prevent achieving the task standard.
STEP CUE STANDARD 1.
184
* List the Emergency Action Level that is met.
The examinee refers to the Mode 1-4 classification chart and determines FA1 is the correct Emergency Action
 
Level (EAL).
Answer:  FA1 -  ANY loss or ANY Potential loss of EITHER Fuel Clad OR RCS due to RCS leakrate greater than available makeup by a loss of RCS subcooling to saturation (0 °F)


or RCS leak rate greater than charging capacity with Letdown
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam
* Notify unit Shift Manager of in-plant JPM performance.
* Performance of this JPM may require entry into areas with alarmed doors.          Security requirements must be observed.
* Locked valves may be involved. No attempt will be made to actually operate any valves.
185


isolated. START TIME ________________
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:
STEP                          CUE                    STANDARD
: 1.
* List the Emergency Action Level                        The examinee refers to the Mode 1-4 that is met.                                            classification chart and determines FA1 is the correct Emergency Action Level (EAL).
Answer: FA1 - ANY loss or ANY Potential loss of EITHER Fuel Clad OR RCS due to RCS leakrate greater than available makeup by a loss of RCS subcooling to saturation (0 °F) or RCS leak rate greater than charging capacity with Letdown isolated.
START TIME ________________
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
STEP CUE STANDARD 2.
STEP                           CUE                     STANDARD
* List the Classification of this event. Examinee use the Mode 1-4 classification chart to determines the  
: 2.
 
* List the Classification of this                         Examinee use the Mode 1-4 event.                                                  classification chart to determines the classification.
classification.
Answer: Alert STOP TIME _________________
Answer: Alert   STOP TIME _________________
Time should be less than 15 minutes from the time the cue is given until the event is classified.
Time should be less than 15 minutes from the time the cue is given until  
 
the event is classified.
SAT / UNSAT Comments (required for UNSAT):
SAT / UNSAT Comments (required for UNSAT):
JPM STOP TIME:
JPM STOP TIME:
NORMAL TERMINATION POINT  
NORMAL TERMINATION POINT 186


SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 187 ANSWER KEY  
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY
: 1. List the Emergency Action Level that is currently met.
: 1. List the Emergency Action Level that is currently met.
FA1 2. List the Classification of this event.
FA1
Alert  
: 2. List the Classification of this event.
Alert ANSWER KEY 187


ANSWER KEY
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION      REVISION        REASON NUMBER          DATE          REVISED                                COMMENTS 0          10/15/2009            6        Record Created REASON REVISED            Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
109. Vendor reference document upgrade 110. Plant modification (include number) 111. Procedure upgrade 112. Internal or External Agency Commitment (indicate item number) 113. Technical Specification Change (indicate amendment number) 114. Other (explain in comments) 188


SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 188  RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED  COMMENTS 0 10/15/2009 6 Record Created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered
SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:
Based on plant conditions at the conclusion of the scenario, perform the two following tasks:
: 1. List the Emergency Action Level that is CURRENTLY met.
: 2. List the Classification of this event.
THIS IS A TIME CRITICAL JPM Use this as your answer sheet.
CANDIDATE 189


consecutively in each revision.
Appendix       D                           Scenario Outline                               Form ES-D-1 Facility: PVNGS           Scenario No.:   __1             Op-Test No:       2009 Examiners:                                                   Operators:
109. Vendor reference document upgrade 110. Plant modification (include number) 111. Procedure upgrade 112. Internal or External Agency Commitment (indicate item number) 113. Technical Specification Change (indicate amendment number) 114. Other (explain in comments)
SA 5  PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam  189 INITIAL CONDITIONS INITIATING CUE:
Based on plant conditions at the conclusion of the scenario, perform the two following tasks:
: 1. List the Emergency Action Level that is CURRENTLY met. 2. List the Classification of this event.
THIS IS A TIME CRITICAL JPM Use this as your answer sheet.
CANDIDATE Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 190 of 248 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners:     Operators:
Initial Conditions: IC #100, (100% power, MOC).
Initial Conditions: IC #100, (100% power, MOC).
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralize r was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Norm al Shiftly Surveillances are complete. Risk Management Action Level is Green.
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.
Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Event No. Malf. No. Event Type* Event Description 1 None N CO/SRO Shift Condensate Demineralizers. 2 imf cmCNCV04CHNFIC243_2   I RO/SRO A seal injection controller will fail in automatic requiring the crew to take manual control of the controller. 3 imf cmCPCH03HCNA02A_6   imf cmCPCH03HCNA02C_6 C CO/SRO The A and C CEDM fans will trip requiring the CRS to enter 40AO-9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).
Event                 Malf. No.                 Event Type*                                 Event Description No.
4 imf mfRD02B R RO/CO/SRO (TS) CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.
1     None                                       N Shift Condensate Demineralizers.
Crew begins a 20% downpower. SR O enters LCO 3.1.5 Condition A and LCO 3.2.4 Condition A.
CO/SRO 2     imf cmCNCV04CHNFIC243_2                     I A seal injection controller will fail in automatic requiring the crew to RO/SRO take manual control of the controller.
5 imf mfTH06A C CO/SRO (TS) A Steam Generator Tube leak occu rs requiring the crew to enter 40AO-9ZZ02, Excessive RCS leakrate.
3     imf cmCPCH03HCNA02A_6                       C         The A and C CEDM fans will trip requiring the CRS to enter 40AO-imf cmCPCH03HCNA02C_6                    CO/SRO        9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).
6 imf mfRD02L mfRD12A mfRP04A mfRP04C M - ALL C - RO/SRO Another CEA slips into the core. Th is will cause a reactor trip signal but an ATWS will occur. This will require the crew to open the breakers supplying the CEDM MG sets. Critical Task - Crew will insert all CEAs.
4     imf mfRD02B                                 R CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.
7 mfRX01 I CO /SRO After the trip Tave will fail low requiring the CO to manually feed the SGs.
RO/CO/SRO Crew begins a 20% downpower. SRO enters LCO 3.1.5 Condition A (TS) and LCO 3.2.4 Condition A.
8 mmf mfTH06A M-ALL The SGTL will degrade on the trip.
5     imf mfTH06A                                 C A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO 40AO-9ZZ02, Excessive RCS leakrate.
The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.  
(TS) 6     imf mfRD02L                             M - ALL       Another CEA slips into the core. This will cause a reactor trip signal mfRD12A                                C - RO/SRO      but an ATWS will occur. This will require the crew to open the mfRP04A                                                breakers supplying the CEDM MG sets.
 
Critical Task - Crew will insert all CEAs.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End point  The scenario is terminated when the crew commences affected steam generator has been isolated or at the discretion of the lead examiner * (N)ormal,   (R)eactivity,   (I)nstrument,   (C)omponent,   (M)ajor Supplemental Turnover Plant conditions:
mfRP04C 7     mfRX01                                       I         After the trip Tave will fail low requiring the CO to manually feed the CO /SRO        SGs.
8     mmf mfTH06A                             M-ALL         The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End                                                             The scenario is terminated when the crew commences affected steam point                                                          generator has been isolated or at the discretion of the lead examiner
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
Appendix    D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 191 of 248 Risk Management Action Level is GREEN. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
NUREG-1021, Revision 9                         190 of 248
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
Note: The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 192 of 248 Turnover Plant conditions:
Appendix       D                           Scenario Outline                             Form ES-D-1 Risk Management Action Level is GREEN.
Train B is protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.
The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
Note:
The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.
NUREG-1021, Revision 9                           191 of 248
 
Appendix      D                            Scenario Outline                            Form ES-D-1 Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance. Risk Management Action Level is GREEN. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
Risk Management Action Level is GREEN.
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.  
Train B is protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.
The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
NUREG-1021, Revision 9                          192 of 248


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 193 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                             Form ES-D-2 Op-Test No: _2009_            Scenario No.: 1           Event No:   1 Event
_  Scenario No.:
1     Event No:   1 Event


== Description:==
== Description:==
Shift Condensate Demineralizers Time Position Applicant's Actions or Behavior T=0 CO Performs prerequisites: One NO and one RO to perform this Sections Condensate and Feedwater alighted to feed the SGs. Instrument air is available Service air is available. The service vessel to be placed has been rinsed within the past 12 hours. Informs chemistry demin configuration will be changed. Directs the demin operator to ensure the following valve SCN-V960F is open for the 'F' Demin Vessel. Opens the 'F' Demin Vessel outlet valves (SCN-UV-216) using handswitch SCN-HS-216A on B07. Verifies the STANDBY light goes out, The IN-SERVICE light illuminates, the red light illuminates and the green light goes out. Requests demin operator to monitor vessel flow and DP.
Shift Condensate Demineralizers Time       Position                           Applicants Actions or Behavior T=0         CO         Performs prerequisites:
Closes 'E' Demin Vessel Outlet valve (SCN-UV-0215) using handswitch SCN-HS-215A on B07. Verifies the STANDBY light illuminates, the IN-SERVICE light goes out, the green lights illuminates, the red lights go out, and indication that flow has  
* One NO and one RO to perform this Sections
 
* Condensate and Feedwater alighted to feed the SGs.
stopped through the service vessel. Requests demin operator to monitor vessel flow and DP.
* Instrument air is available
* Service air is available.
* The service vessel to be placed has been rinsed within the past 12 hours.
Informs chemistry demin configuration will be changed.
Directs the demin operator to ensure the following valve SCN-V960F is open for the F Demin Vessel.
Opens the F Demin Vessel outlet valves (SCN-UV-216) using handswitch SCN-HS-216A on B07.
Verifies the STANDBY light goes out, The IN-SERVICE light illuminates, the red light illuminates and the green light goes out.
Requests demin operator to monitor vessel flow and DP.
Closes E Demin Vessel Outlet valve (SCN-UV-0215) using handswitch SCN-HS-215A on B07.
Verifies the STANDBY light illuminates, the IN-SERVICE light goes out, the green lights illuminates, the red lights go out, and indication that flow has stopped through the service vessel.
Requests demin operator to monitor vessel flow and DP.
Directs demin operator to ensure SCN-V960E is closed.
Directs demin operator to ensure SCN-V960E is closed.
Directs demin operator to ensure SCN-V961E is open.  
Directs demin operator to ensure SCN-V961E is open.
193 of 248                      NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 194 of 248
Appendix D Operator Actions   Form ES-D-2 194 of 248 NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 195 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1           Event No:     2 Event
_  Scenario No.:
1     Event No:   2 Event


== Description:==
== Description:==
 
Seal Injection controller failure Time       Position                         Applicants Actions or Behavior T=7         RO       Evaluates alarm window 3A11A per 40AL-9RK3A.
Seal Injection controller failure Time Position Applicant's Actions or Behavior T=7 RO Evaluates alarm window 3A11A per 40AL-9RK3A. Determines a Lo flow condition exist for RCP 2A only (~7.7 gpm). Takes manual control of flow controller CHN-FIC-243 on B03 and adjusts flow to normal (~ 6.6 gpm).  
* Determines a Lo flow condition exist for RCP 2A only (~7.7 gpm).
 
* Takes manual control of flow controller CHN-FIC-243 on B03 and adjusts flow to normal (~ 6.6 gpm).
CRS May enter 40AO-9ZZ04, RCP Emergencies. Directs RO to take manual control of valve controller and restore flow to the normal band per 40AL-9RK3A , Secondary Priority Action 1.  
CRS       May enter 40AO-9ZZ04, RCP Emergencies.
 
Directs RO to take manual control of valve controller and restore flow to the normal band per 40AL-9RK3A, Secondary Priority Action 1.
Op-Test No: _2009
Op-Test No: _2009_          Scenario No.: 1           Event No:     3 Event
_  Scenario No.:
1     Event No:     3 Event


== Description:==
== Description:==
CEDM fans trip / Failure of Stby fans to auto start 195 of 248                        NUREG-1021, Revision 9


CEDM fans trip / Failure of Stby fans to auto start
Appendix D                     Operator Actions                               Form ES-D-2 Time     Position                     Applicants Actions or Behavior T=14       CO     Responds to alarms on B07 (Window 7A9B), determines that CEDM fans are not running.
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 196 of 248 Time Position Applicant's Actions or Behavior T=14 CO Responds to alarms on B07 (Window 7A9B), determines that CEDM fans are not running.
Uses the Alarm Response Procedure or direction from the CRS to start the B and D CEDM fans using handswitch HCB-HS-50 on B07.
Uses the Alarm Response Procedure or direction from the CRS to start the B and D CEDM fans using handswitch HCB-HS-50 on B07.
Evaluator Note: These standby fans h ave a two minute time delay before they should start, however, due to the fault, they will not auto start.
Evaluator Note: These standby fans have a two minute time delay before they should start, however, due to the fault, they will not auto start.
RO Responds to alarms on SESS panel (Window 6D). Addresses the alarm response procedure.  
RO     Responds to alarms on SESS panel (Window 6D). Addresses the alarm response procedure.
 
CRS   Evaluator Note: The crew may start the standby fans from the alarm response procedure on B07.
CRS
May implement Loss of HVAC procedure, 40AO-9ZZ20.
 
* Directs the CO to start the standby CEDM fans.
Evaluator Note: The crew may start the standby fans from the alarm response procedure on B07.
* May direct CO to verify normal containment parameters.
May implement Loss of HVAC procedure, 40AO-9ZZ20. Directs the CO to start the standby CEDM fans. May direct CO to verify normal containment parameters. May performs brief to address the failure and contingencies.
May performs brief to address the failure and contingencies.
Evaluator Note: There are no Tech Specs to address for this event.  
Evaluator Note: There are no Tech Specs to address for this event.
196 of 248                          NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 197 of 248 Op-Test No: _2009
Appendix   D                       Operator Actions                               Form ES-D-2 Op-Test No: _2009_        Scenario No.: 1               Event No:   4 Event
_  Scenario No.:
1     Event No:   4 Event


== Description:==
== Description:==
CEA 15 drops into the core Time      Position                          Applicants Actions or Behavior T=21        Crew    Responds to alarms on Board 3, determines that CEA 15 has dropped into the core.
CRS    Implement CEA Malfunction Abnormal Operating Procedure, 40AO-9ZZ11.
: 1. Checks that at least one CEA is deviating from its group by greater than 6.6 inches.
: 2. Verifies no CEA Reg Group is below the Transient Insertion Limit
: 3. Verifies Reactor power is not < 1%.
: 4. Ensures two or more CEAs are not deviating > 9.9 inches from their associated group.
: 5. Direct CEDMCS to Standby
: 6. Directs performance of Appendix E, Initial Actions.
: 7. Records CEA deviation time and Initial Power level.
: 8. Performs the following to start a power reduction within 10 minutes.
: a. Logs the start time for power reduction
: b. Directs the CO to lower turbine load to raise Tave 3&deg;F greater than Tref.
: 9. Determines that a 20% downpower is required.
: 10. Calculates the number of gallons of baric acid needed by using the STA reactivity worksheet. (~ 1000 gallons).
: 11. Directs the CO to lower turbine load to maintain Tave 3&deg;F greater than Tref.
: 12. Directs the RO to commence borating at a minimum rate of 25 gpm.
: 13. Determines the time required to perform the downpower using Appendix B.
: 14. When the requirements of Appendix B allow temperature to be lowered, the CRS directs the CO to maintain Tave/Tref mismatch + 3&deg;F.
: 15. Determines the ability to stabilize power at the target plateau using the Maneuvering Box Tools (This may have been discussed at the beginning of shift reactivity brief).
Enters LCO 3.1.5 Condition A. and LCO 3.2.4 Condition A.
Examiner Note - Step 22 of 40AO-9ZZ11 addresses TS. CRS may not get to address LCO.s 3.1.5 and 3.2.4 within the timing of the event. This can be followed up after the scenario.
RO    Places CEDMCS in Standby using the Mode Select switch on the CEDMCS panel (may be performed by CO)
Performs Appendix E actions (may be performed by CO):
: 1. Places Pressurizer in boron equalization
: a. Override and energize all pressurizer backup heaters:
RCA-HS-100-4          RCB-HS-100-5 RCN-HS-100-6          RCN-HS-100-7 RCN-HS-100-8          RCN-HS-100-9
: b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to 197 of 248                        NUREG-1021, Revision 9


CEA 15 drops into the core Time Position Applicant's Actions or Behavior T=21 Crew Responds to alarms on Board 3, determines that CEA 15 has dropped into the core. CRS Implement CEA Malfunction Abnormal Operating Procedure, 40AO-9ZZ11.
Appendix   D                           Operator Actions                             Form ES-D-2 Op-Test No: _2009_            Scenario No.: 1             Event No:    4 Event
: 1. Checks that at least one CEA is deviating from its group by greater than 6.6 inches. 2. Verifies no CEA Reg Group is below the Transient Insertion Limit
: 3. Verifies Reactor power is not < 1%.
: 4. Ensures two or more CEAs are not deviating > 9.9 inches from their associated group.
: 5. Direct CEDMCS to Standby
: 6. Directs performance of Appendix E, Initial Actions.
: 7. Records CEA deviation time and Initial Power level.
: 8. Performs the following to start a power reduction within 10 minutes.
: a. Logs the start time for power reduction
: b. Directs the CO to lower turbine load to raise Tave 3&deg;F greater than Tref. 9. Determines that a 20% downpower is required.
: 10. Calculates the number of gallons of baric acid needed by using the STA reactivity worksheet.  (~ 1000 gallons).
: 11. Directs the CO to lower turbine load to maintain Tave 3&deg;F greater than Tref. 12. Directs the RO to commence borating at a minimum rate of 25 gpm.
: 13. Determines the time required to perform the downpower using Appendix B.
: 14. When the requirements of Appendix B allow temperature to be lowered, the CRS directs the CO to maintain Tave/Tref mismatch +
3&deg;F. 15. Determines the ability to stabilize power at the target plateau using the Maneuvering Box Tools (This may have been discussed at the beginning of shift reactivity brief). Enters LCO 3.1.5 Condition A. and LCO 3.2.4 Condition A. Examiner Note - Step 22 of 40AO-9ZZ11 addresses TS. CRS may not get to address LCO.s 3.1.5 and 3.2.4 within the timing of the event. This can be followed up after the scenario.
RO Places CEDMCS in Standby using the Mode Select switch on the CEDMCS panel (may be performed by CO)
Performs Appendix E actions (may be performed by CO):
: 1. Places Pressurizer in boron equalization
: a. Override and energize all pressurizer backup heaters:
RCA-HS-100-4          RCB-HS-100-5 RCN-HS-100-6          RCN-HS-100-7 RCN-HS-100-8          RCN-HS-100-9
: b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 198 of 248 Op-Test No: _2009
_  Scenario No.:
1     Event No:    4 Event


== Description:==
== Description:==
 
CEA 15 drops into the core Time       Position                             Applicants Actions or Behavior 2220 psia.
CEA 15 drops into the core Time Position Applicant's Actions or Behavior 2220 psia.
Borates to the RCS as direct by the CRS.
Borates to the RCS as direct by the CRS. (basic steps the RO will perform)  
(basic steps the RO will perform)
: 1. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.  
: 1. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
: 2. Selects the "Target" makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2.  
: 2. Selects the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2.
: 3. Starts the boration as follows:  
: 3. Starts the boration as follows:
: a. Place CHN-HS-210 in the BORATE position.  
: a. Place CHN-HS-210 in the BORATE position.
: b. Depress the "Reset" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).  
: b. Depress the Reset pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
: c. Depress the "Start" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).  
: c. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
: d. Adjusts flow to the required flowrate (if > 40 gpm needed). May perform Appendix B as directed by the CRS.  
: d. Adjusts flow to the required flowrate (if > 40 gpm needed).
 
May perform Appendix B as directed by the CRS.
CO Lowers Turbine load using the Turbine Load Limit potentiometer on B06 to raise Tave greater than Tref by 3 &deg;F to maintain power within the limits of Appendix B.
CO         Lowers Turbine load using the Turbine Load Limit potentiometer on B06 to raise Tave greater than Tref by 3 &deg;F to maintain power within the limits of Appendix B.
May perform Appendix B as directed by the CRS.  
May perform Appendix B as directed by the CRS.
 
After ~5% load reduction, have the driver insert the next malfunction.
After ~5% load reduction, have the driver insert the next malfunction.
198 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 199 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1             Event No:     5 Event
_  Scenario No.:
1     Event No:   5 Event


== Description:==
== Description:==
 
Steam Generator Tube Leak Time       Position                           Applicants Actions or Behavior T=41         Crew     Receives alarms on RMS panel. Reports to the CRS that RU-142 is in alarm with SG #1 having the highest readings.
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior T=41 Crew Receives alarms on RMS panel. Reports to the CRS that RU-142 is in alarm with SG #1 having the highest readings. CRS Enters Excessive RCS Leakrate, 40AO-9ZZ02, Section 5. Examiner Note: The leakrate is small (~ 5gpm), but due to the down power, the crew may start the third charging pump and isolate letdown. It is not expected that the crew will trip the reactor.
CRS     Enters Excessive RCS Leakrate, 40AO-9ZZ02, Section 5.
IF pressurizer level is lowering, THEN ensure all available Charging Pumps are running. IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown.
Examiner Note: The leakrate is small (~ 5gpm), but due to the down power, the crew may start the third charging pump and isolate letdown. It is not expected that the crew will trip the reactor.
IF pressurizer level is lowering, THEN ensure all available Charging Pumps are running.
IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown.
IF ALL of the following conditions exist:
IF ALL of the following conditions exist:
* All available Charging Pumps are operating
* All available Charging Pumps are operating
* Letdown is isolated
* Letdown is isolated
* Pressurizer level is lowering THEN perform the following:  
* Pressurizer level is lowering THEN perform the following:
: a. Ensure that the Reactor is tripped.  
: a. Ensure that the Reactor is tripped.
: b. GO TO ONE of the following:
: b. GO TO ONE of the following:
* 40EP-9EO01, Standard Post Trip Actions
* 40EP-9EO01, Standard Post Trip Actions
* 40EP-9EO11, Lower Mode Functional Recovery Ensure the event is being classified.
* 40EP-9EO11, Lower Mode Functional Recovery Ensure the event is being classified.
IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.4.14, RCS Operational Leakage. The CRS should LCO 3.4.14 Condition 'b'. Direct Chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.
IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.4.14, RCS Operational Leakage. The CRS should LCO 3.4.14 Condition b.
Notify Radiation Protection that an RCS leak exists. Examiner Note: Due to the downpower being performed due to the slipped CEA, the crew will not be able to determine a leakrate, however, RU-142 gives the crew a leakrate based on RU readings. Determine the leakrate using ANY of the following: Appendix A, 15 Minute Leak Rate Calculation Appendix B, ERFDADS Leak Rate Determination 40ST-9RC02, ERFDADS (Preferred) Calculation of RCS Water Inventory 40ST-9RC05, Manual Calculation of RCS Water Inventory 40ST-9RC08, OAP (Backup) Calculation of RCS Water Inventory REFER TO Appendix F, Steam Generator Tube Leak Guidelines.
Direct Chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.
IF the plant will be shutdown, THEN PERFORM 40OP-9ZZ05, Power Operations. Perform Appendix C, Minimize Release to the Environment.
Notify Radiation Protection that an RCS leak exists.
Examiner Note: Due to the downpower being performed due to the slipped CEA, the crew will not be able to determine a leakrate, however, RU-142 gives the crew a leakrate based on RU readings.
Determine the leakrate using ANY of the following:
* Appendix A, 15 Minute Leak Rate Calculation
* Appendix B, ERFDADS Leak Rate Determination
* 40ST-9RC02, ERFDADS (Preferred) Calculation of RCS Water Inventory
* 40ST-9RC05, Manual Calculation of RCS Water Inventory
* 40ST-9RC08, OAP (Backup) Calculation of RCS Water Inventory REFER TO Appendix F, Steam Generator Tube Leak Guidelines.
IF the plant will be shutdown, THEN PERFORM 40OP-9ZZ05, Power Operations.
Perform Appendix C, Minimize Release to the Environment.
Perform 40DP-9ZZ14, Contaminated Water Management (would assign to another SRO in the unit or unaffected unit).
Perform 40DP-9ZZ14, Contaminated Water Management (would assign to another SRO in the unit or unaffected unit).
Direct an operator to perform Appendix D, Aligning Turbine Building Sumps to LRS. Direct Chemistry to sample the condensate and other connecting systems, including turbine building sumps for activity.
Direct an operator to perform Appendix D, Aligning Turbine Building Sumps to LRS.
IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.7.16, Secondary Specific Activity.  
Direct Chemistry to sample the condensate and other connecting systems, including turbine building sumps for activity.
IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.7.16, Secondary Specific Activity.
RO      Examiner Note: Due to the downpower being performed due to the slipped CEA, 199 of 248                      NUREG-1021, Revision 9


RO Examiner Note: Due to the downpower being performed due to the slipped CEA, Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 200 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1           Event No:     5 Event
_  Scenario No.:
1     Event No:   5 Event


== Description:==
== Description:==
 
Steam Generator Tube Leak Time       Position                           Applicants Actions or Behavior the crew will not be able to determine a leakrate, however, RU-141 and RU-142 gives the crew a leakrate based on RU readings.
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior the crew will not be able to determin e a leakrate, however, RU-141 and RU-142 gives the crew a leakrate based on RU readings.
Since a shutdown is required due to the SGTL and a downpower is in progress, the CRS may have the RO reset the totalizer on the makeup to continue the downpower.
Since a shutdown is required due to the SGTL and a downpower is in progress, the CRS may have the RO reset the totalizer on the makeup to continue the downpower.
However, this may not occur until later in the event, therefore it may not be observed (or the CRS may wait until after the 20% downpower is completed to reset for the downpower). Set the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y. Select the "Target" makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2. Continue the boration as follows:  
However, this may not occur until later in the event, therefore it may not be observed (or the CRS may wait until after the 20% downpower is completed to reset for the downpower).
: 1. Place CHN-HS-210 in the BORATE position. 2. Depress the "Reset" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion). 3. Depress the "Start" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion). May be asked to secure boration.  
* Set the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
 
* Select the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2.
CO Addresses RMS alarms and determines which monitors are in Alarm (RU-139, RU-142, RU-141, & RU-7). Reports highest reading in SG #1. Provides leakrate from  
* Continue the boration as follows:
 
: 1. Place CHN-HS-210 in the BORATE position.
RMS to the CRS as requested.
: 2. Depress the Reset pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
: 3. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
* May be asked to secure boration.
CO       Addresses RMS alarms and determines which monitors are in Alarm (RU-139, RU-142, RU-141, & RU-7). Reports highest reading in SG #1. Provides leakrate from RMS to the CRS as requested.
Secures SG blowdown as directed in the RMS alarm response procedure.
Secures SG blowdown as directed in the RMS alarm response procedure.
Performs Appendix C, Minimize Release to the Environment.  
Performs Appendix C, Minimize Release to the Environment.
: 1. Ensure ARN-HS-19, Post Filter Mode Select Switch, is in the "THRU FILTER MODE" by observing red i ndication on ARN-HS-19 on B07.  
: 1. Ensure ARN-HS-19, Post Filter Mode Select Switch, is in the THRU FILTER MODE by observing red indication on ARN-HS-19 on B07.
: 2. Select "OFF" on BOTH of the following switches: SGN-HS-1007, Valve 7 Mode Select SGN-HS-1008, Valve 8 Mode Select  
: 2. Select OFF on BOTH of the following switches:
: 3. Throttle opens CDN-HV-275, Demineralizer Water Feed to Condensate Service Header Valve using handswitch CDN-HS-275 on B04, to maintain 50 - 100 psig on CDN-PI-201.  
* SGN-HS-1007, Valve 7 Mode Select
: 4. Ensure that BOTH of the following Condensate Pump Overboard Valves are closed: CDN-HV-29 (Handswitch CDN-HS-29 on B05) CDN-HV-30 (Handswitch CDN-HS-30 on B05)
* SGN-HS-1008, Valve 8 Mode Select
Reduces turbine load as necessary to maintain primary temperature as directed by the CRS.  
: 3. Throttle opens CDN-HV-275, Demineralizer Water Feed to Condensate Service Header Valve using handswitch CDN-HS-275 on B04, to maintain 50 - 100 psig on CDN-PI-201.
: 4. Ensure that BOTH of the following Condensate Pump Overboard Valves are closed:
* CDN-HV-29 (Handswitch CDN-HS-29 on B05)
* CDN-HV-30 (Handswitch CDN-HS-30 on B05)
Reduces turbine load as necessary to maintain primary temperature as directed by the CRS.
200 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 201 of 248 Op-Test No: _2009
Appendix   D                     Operator Actions                   Form ES-D-2 Op-Test No: _2009_        Scenario No.: 1       Event No: 5 Event
_  Scenario No.:
1     Event No:   5 Event


== Description:==
== Description:==
Steam Generator Tube Leak Time      Position                    Applicants Actions or Behavior 201 of 248                NUREG-1021, Revision 9


Steam Generator Tube Leak Time Position Applicant's Actions or Behavior
Appendix   D                             Operator Actions                                 Form ES-D-2 Op-Test No: _2009_              Scenario No.: 1             Event No:     6 Event
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 202 of 248 Op-Test No: _2009
_  Scenario No.:
1     Event No:   6 Event


== Description:==
== Description:==
Trip initiator (2 nd CEA drops into the core) ATWS Time Position Applicant's Actions or Behavior T=57 Crew Recognizes another CEA has dropped into the core by alarms (on B04 and B05) and the CEAPDS monitor.
Trip initiator (2nd CEA drops into the core) ATWS Time       Position                               Applicants Actions or Behavior T=57         Crew       Recognizes another CEA has dropped into the core by alarms (on B04 and B05) and the CEAPDS monitor.
Recognizes that a Reactor Trip should have occurred by a ll 4 channels of bistable trip indication on PPS parame ter indications on B05 and/
Recognizes that a Reactor Trip should have occurred by all 4 channels of bistable trip indication on PPS parameter indications on B05 and/or first out annunciator indication on B04.
or first out annunciator indication on B04.  
CRS         Examiner Note: The SGTL will increase in size (200-300 gpm) which will cause the RCS pressure and level to begin trending down. Depending on when the reports are made, the RO may report pressure and level decreasing. This may cause the CRS to direct a manual initiation of SIAS/CIAS.
 
Implements procedure 40EP-9EO01, Standard Post Trip Actions.
CRS Examiner Note: The SGTL will increase in size (200-300 gpm) which will cause the RCS pressure and level to begin tr ending down. Depending on when the reports are made, the RO may report pressure and level decreasing. This may cause the CRS to direct a manual initiation of SIAS/CIAS.
: 1. Open the placekeeper and enter the EOP Entry Time.
Implements procedure 40EP-9EO01, Standard Post Trip Actions.  
: 2. Determine that Reactivity Control acceptance criteria are met by the following:
: 1. Open the placekeeper and enter the EOP Entry Time. 2. Determine that Reactivity Control acceptance criteria are met by the following:  
: a. Check that reactor power is dropping.
: a. Check that reactor power is dropping.  
: b. Check that start-up rate is negative.
: b. Check that start-up rate is negative.  
: c. Check that ALL full strength CEAs are inserted.
: c. Check that ALL full strength CEAs are inserted. Evaluator Note: The crew will have to open the B2 breakers for L03 and L10 on B01 to trip the reactor (using ha ndswitches NGN-HS-L03B2 and NGN-HS-L10B2 on B01). The CRS may direct this prior to getting the SPTA procedure. Critical Task - Crew will insert all CEAs.
Evaluator Note: The crew will have to open the B2 breakers for L03 and L10 on B01 to trip the reactor (using handswitches NGN-HS-L03B2 and NGN-HS-L10B2 on B01). The CRS may direct this prior to getting the SPTA procedure.
: 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following: a. Check that the Main Turbine is tripped.  
Critical Task - Crew will insert all CEAs.
: b. Check that the Main Generator output breakers are open.  
: 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
: c. Check that station loads have transfe rred to offsite electrical power such that BOTH of the following conditions are met:
: a. Check that the Main Turbine is tripped.
: b. Check that the Main Generator output breakers are open.
: c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:
* All vital and non-vital AC buses are powered
* All vital and non-vital AC buses are powered
* All vital and non-vital DC buses are powered 4. Determine that RCS Inventory Control acceptance criteria are met by the following: a. Check that Pressurizer level meets BOTH of the following:
* All vital and non-vital DC buses are powered
: 4. Determine that RCS Inventory Control acceptance criteria are met by the following:
: a. Check that Pressurizer level meets BOTH of the following:
* 10 - 65%
* 10 - 65%
* Trending as expected to 33 - 53% b. Check that the RCS is 24&deg;F or more subcooled.  
* Trending as expected to 33 - 53%
: b. Check that the RCS is 24&deg;F or more subcooled.
: c. Check that BOTH of the following are in service to all RCPs.
: c. Check that BOTH of the following are in service to all RCPs.
* Seal injection
* Seal injection
* Nuclear Cooling Water 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following: Pressurizer pressure is 1837 - 2285 psia Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
* Nuclear Cooling Water
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 203 of 248 Op-Test No: _2009
: 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
_  Scenario No.:
* Pressurizer pressure is 1837 - 2285 psia
1     Event No:   6 Event
* Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
202 of 248                        NUREG-1021, Revision 9
 
Appendix   D                           Operator Actions                                 Form ES-D-2 Op-Test No: _2009_              Scenario No.: 1             Event No:     6 Event


== Description:==
== Description:==
Trip initiator (2 nd CEA drops into the core) ATWS Time Position Applicant's Actions or Behavior 5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop. 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following: At least one RCP is operating Loop T is less than 10&deg;F RCS is 24&deg;F or more subcooled (Continued in next event)  
Trip initiator (2nd CEA drops into the core) ATWS Time       Position                             Applicants Actions or Behavior 5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.
 
: 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
RO Examiner Note: The SGTL will increase in size which will cause the RCS pressure and level to begin trending dow
* At least one RCP is operating
: n. Depending on when the reports are made, the RO may report pressure and level decreasing.
* Loop T is less than 10&deg;F
May report Reactivity. Attempts to tr ip the reactor using B05 pushbuttons. May open NGN-L03B2 and NGN-L 10B2 using handswitches on B01 to de-energize the CEDM MG sets (This may be done by CO).  
* RCS is 24&deg;F or more subcooled (Continued in next event)
 
RO         Examiner Note: The SGTL will increase in size which will cause the RCS pressure and level to begin trending down. Depending on when the reports are made, the RO may report pressure and level decreasing.
Report the status of the Electric Plant (all buses are energized). Reports Pressurizer level and RCS subcooling.
May report Reactivity. Attempts to trip the reactor using B05 pushbuttons.
May open NGN-L03B2 and NGN-L10B2 using handswitches on B01 to de-energize the CEDM MG sets (This may be done by CO).
Report the status of the Electric Plant (all buses are energized).
Reports Pressurizer level and RCS subcooling.
Reports status of Seal injection and Nuclear Cooling to the RCPs.
Reports status of Seal injection and Nuclear Cooling to the RCPs.
Reports RCS pressure. Will stop one RCP in each loop when RCS pressure remains below the SIAS setpoint.
Reports RCS pressure. Will stop one RCP in each loop when RCS pressure remains below the SIAS setpoint.
Reports RCPs operating, loop T, and RCS subcooling. May report RCS Tc (usually done by the CO).
Reports RCPs operating, loop T, and RCS subcooling.
May report RCS Tc (usually done by the CO).
May report containment pressure and status of Radiation Monitoring.
May report containment pressure and status of Radiation Monitoring.
May report containment temperature and containment pressure.  
May report containment temperature and containment pressure.
CO          May report Reactivity when CEAs insert.
Reports status of the Main Turbine and Generator output breakers.
(Continued in next event) 203 of 248                          NUREG-1021, Revision 9


CO May report Reactivity when CEAs insert. Reports status of the Main Turbine and Generator output breakers.
Appendix   D                           Operator Actions                     Form ES-D-2 Op-Test No: _2009_              Scenario No.: 1           Event No: 6 Event
(Continued in next event)
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 204 of 248 Op-Test No: _2009
_  Scenario No.:
1     Event No:   6 Event


== Description:==
== Description:==
Trip initiator (2 nd CEA drops into the core) ATWS Time Position Applicant's Actions or Behavior  
Trip initiator (2nd CEA drops into the core) ATWS Time       Position                             Applicants Actions or Behavior 204 of 248                NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 205 of 248 Op-Test No: _2009
Appendix   D                             Operator Actions                               Form ES-D-2 Op-Test No: _2009_              Scenario No.: 1             Event No: 7 Event
_  Scenario No.:
1     Event No: 7 Event


== Description:==
== Description:==
Tave fails low Time Position Applicant's Actions or Behavior T=57 CO Reports SG levels and method of feed. The CO will have to take manual control of the Downcomer control valves (using the Downcomer Valve controllers SGN-FIK-113 and SGN-FIK-1123 or on the DFWCS screen) and feed the Steam Generators. Evaluator Note: CO does not need to diagnose the Tave failure May report RCS Tc. Reports SG pressure. SG pressures should be controlled by the SBCS in automatic.
Tave fails low Time       Position                               Applicants Actions or Behavior T=57         CO         Reports SG levels and method of feed. The CO will have to take manual control of the Downcomer control valves (using the Downcomer Valve controllers SGN-FIK-113 and SGN-FIK-1123 or on the DFWCS screen) and feed the Steam Generators.
Evaluator Note: CO does not need to diagnose the Tave failure May report RCS Tc.
Reports SG pressure. SG pressures should be controlled by the SBCS in automatic.
May report containment pressure and status of Radiation Monitoring.
May report containment pressure and status of Radiation Monitoring.
May report containment temperature and containment pressure.  
May report containment temperature and containment pressure.
 
CRS       (Continuing in the SPTAs)
CRS (Continuing in the SPTAs) 7. Determine that RCS Heat Removal acceptance criteria are met by the following: a. Check that at least one Steam Generator meets BOTH of the following conditions:
: 7. Determine that RCS Heat Removal acceptance criteria are met by the following:
: a. Check that at least one Steam Generator meets BOTH of the following conditions:
* Level is 35% WR or more
* Level is 35% WR or more
* Feedwater is restoring or maintaining level 45 - 60% NR Evaluator Note: Due to Tave failing low on the trip, the CO will have to take manual control of feedwater to feed the SGs. b. Check that Tc is 560 - 570&deg;F.  
* Feedwater is restoring or maintaining level 45 - 60% NR Evaluator Note: Due to Tave failing low on the trip, the CO will have to take manual control of feedwater to feed the SGs.
: c. Check that steam generator pressure is 1140 - 1200 psia.  
: b. Check that Tc is 560 - 570&deg;F.
: 8. Determine that Containment Isolation acceptance criteria are met by the following:  
: c. Check that steam generator pressure is 1140 - 1200 psia.
: a. Check that Containment pressure is less than 2.5 psig.  
: 8. Determine that Containment Isolation acceptance criteria are met by the following:
: b. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions: No valid containment area radiation monitor alarms or unexplained rise in activity No valid steam plant activity monitor alarms or unexplained rise in activity 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are me t by the following:  
: a. Check that Containment pressure is less than 2.5 psig.
: a. Check that containment temperature is less than 117&deg;F.  
: b. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
: b. Check that containment pressure is less than 2.5 psig. Diagnoses SGTR, enters 40EP-9EO04, Steam Generator Tube Rupture.  
* No valid containment area radiation monitor alarms or unexplained rise in activity
* No valid steam plant activity monitor alarms or unexplained rise in activity
: 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:
: a. Check that containment temperature is less than 117&deg;F.
: b. Check that containment pressure is less than 2.5 psig.
Diagnoses SGTR, enters 40EP-9EO04, Steam Generator Tube Rupture.
205 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 206 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                     Form ES-D-2 Op-Test No: _2009_              Scenario No.: 1       Event No: 7 Event
_  Scenario No.:
1     Event No: 7 Event


== Description:==
== Description:==
Tave fails low Time Position Applicant's Actions or Behavior  
Tave fails low Time       Position                         Applicants Actions or Behavior 206 of 248                NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 207 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1           Event No: 8 Event
_  Scenario No.:
1     Event No: 8 Event


== Description:==
== Description:==
SGTR Time      Position                          Applicants Actions or Behavior T=67        CRS      The CRS performs the following per 40EP-9EO04, Steam Generator Tube Rupture;
* Confirms the diagnosis of a SGTR by directing the performance of the SFSC, directing an operator to open the SG sample valves, and directing Chemistry to perform the abnormal occurrence checklist.
* Ensures the event is being classified. This is normally the task of the Shift Manager.
* Opens the placekeeper and enter the EOP entry time.
* If pressure drops below SIAS setpoint, directs an operator to check that SIAS is actuated.
* If SIAS has actuated, directs an operator to check HPSI and LPSI pumps started, and adequate SI flow per Appendix 2.
* If pressure remains below the SIAS setpoint, directs an operator to ensure one RCP is stopped in each loop.
* Directs an operator to monitor any operating RCP per Appendix 16.
Evaluator Note: The following two steps should have been done in the AOP for Excessive RCS leakrate
* Directs the CO to place the post filter blower in the THRU FILTER MODE.
* Directs the CO to place SBCS valves 1007 and 1008 in OFF.
Directs the CO to commence a cooldown to Th of less than 540 &deg;F using the SBCS and to perform the RCS cooldown log.
Evaluator Note: The CRS may hold a tailboard to discuss the operators responsibilities during the cooldown (cooldown, depressurize and reset MSIS setpoints)
* If steaming to atmosphere, informs Radiation Protection.
* Directs the RO to depressurize the RCS to <1135 psia, approximately equal to ruptured SG pressure, and within the P/T limits.
* Directs the RO to throttle HPSI when Safety Injection Throttle criteria are met.
* Directs the crew to reset the MSIS setpoints.
* Determines the most affected SG by verifying parameters.
* Directs Isolation of the Ruptured SG.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator 207 of 248                          NUREG-1021, Revision 9


SGTR   Time Position Applicant's Actions or Behavior T=67 CRS  The CRS performs the following per 40EP-9EO04, Steam Generator Tube Rupture;  Confirms the diagnosis of a SGTR by directing the performance of the SFSC, directing an operator to open the SG sample valves, and directing Chemistry to perform the abnormal occurrence checklist. Ensures the event is being classified. This is normally the task of the Shift Manager. Opens the placekeeper and enter the EOP entry time. If pressure drops below SIAS setpoint, directs an operator to check that SIAS is actuated. If SIAS has actuated, directs an operator to check HPSI and LPSI pumps started, and adequate SI flow per Appendix 2. If pressure remains below the SIAS setpoint, directs an operator to ensure one RCP is stopped in each loop. Directs an operator to monitor any operating RCP per Appendix 16. Evaluator Note:  The following two steps should have been done in the AOP for Excessive RCS leakrate  Directs the CO to place the post f ilter blower in the "THRU FILTER MODE."  Directs the CO to place SBCS valves 1007 and 1008 in "OFF." Directs the CO to commence a cooldown to T h of less than 540 &deg;F using the SBCS and to perform the RCS cooldown log. Evaluator Note:  The CRS may hold  a tailboard to discuss the operators responsibilities during the cooldown (cooldown, depressurize and reset MSIS
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1             Event No: 8 Event
 
setpoints)  If steaming to atmosphere, informs Radiation Protection. Directs the RO to depressurize the RCS to <1135 psia, approximately equal to ruptured SG pressure, and within the P/T limits. Directs the RO to throttle HPSI when Safety Injection Throttle criteria are met. Directs the crew to reset the MSIS setpoints. Determines the most affected SG by verifying parameters. Directs Isolation of the Ruptured SG. Critical Task - Initiate actions to cooldown and isolate the affected steam generator Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 208 of 248 Op-Test No: _2009
_  Scenario No.:
1     Event No: 8 Event


== Description:==
== Description:==
SGTR Time      Position                          Applicants Actions or Behavior RO      When pressure is < SIAS setpoint, ensures SIAS actuated and HPSI, LPSI pumps running. Verifies SIAS actuated and equipment is actuated by visually verifying equipment or checking SESS panel.
Trips one RCP in each loop when pressure remains below the SIAS setpoint using the handswitches on B04. (Trips 1A and 2A or trips 1B and 2B RCPs).
* RCP1A - handswitch RCN-HS-1
* RCP1B - handswitch RCN-HS-2
* RCP2A - handswitch RCN-HS-3
* RCP2B - handswitch RCN-HS-4 Monitors running RCP parameters per Appendix 16.
Depressurizes the RCS when directed using main sprays on B04 and/or aux sprays on B03.
* Main sprays - controller RCN-PIC-100 or RCN-PIK-100 in manual
* Aux Sprays - CHA-HS-205 and/or CHB-HS-203 Throttles HPSI when Safety Injection throttle criteria are met using the following handswitches on B03. Throttles HPSI one valve at a time.
Train A                            Train B SIA-HS-617                          SIB-HS-616 SIA-HS-627                          SIB-HS-626 SIA-HS-637                          SIB-HS-636 SIA-HS-647                          SIB-HS-646 Resets MSIS setpoints as the cooldown occurs as directed using the LO SG PRESS RESET pushbuttons on B05.
CO      May manually initiate SIAS/CIAS if directed by CRS.
Evaluator Note: The next two steps may have been performed during the Abnormal Operating Procedure for the SGTL.
Ensures post filter blower is in THRU FILTER MODE when directed using handswitch ARN-HS-19.
Places SBCS valves 1007 and 1008 are in OFF when directed using SGN-HS-1007 and SGN-HS-1008.
Performs a cooldown using SBCS (probably using SGN-PIK-1001, but any other SBCS valve is acceptable) to get Th less than 540 &deg;F when directed Resets MSIS setpoints using the LO SG PRESS SETPOINT RESET pushbuttons on B05 as the cooldown occurs as directed.
Isolates the affected SG when directed by ensuring the following are closed:
Component                            Handswitch - all on B06 unless noted otherwise.
ADV 184                              SGA-HIC-184A 208 of 248                        NUREG-1021, Revision 9


SGTR   Time Position Applicant's Actions or Behavior  RO When pressure is < SIAS setpoint, ensures SIAS actuated and HPSI, LPSI pumps running. Verifies SIAS actuated and equipment is actuated by visually verifying equipment or checking SESS panel.
Appendix   D                     Operator Actions                             Form ES-D-2 Op-Test No: _2009_          Scenario No.: 1         Event No: 8 Event
 
Trips one RCP in each loop when pressure remains below the SIAS setpoint using the handswitches on B04.  (Trips 1A and 2A or trips 1B and 2B RCPs). RCP1A - handswitch RCN-HS-1  RCP1B - handswitch RCN-HS-2  RCP2A - handswitch RCN-HS-3  RCP2B - handswitch RCN-HS-4 Monitors running RCP parameters per Appendix 16.
Depressurizes the RCS when directed using main sprays on B04 and/or aux sprays on B03. Main sprays - controller RCN-PIC-100 or RCN-PIK-100 in manual  Aux Sprays - CHA-HS-205 and/or CHB-HS-203 Throttles HPSI when Safety Injection throttle criteria are met using the following handswitches on B03. Throttles HPSI one valve at a time. 
 
Train A Train B SIA-HS-617 SIB-HS-616 SIA-HS-627 SIB-HS-626 SIA-HS-637 SIB-HS-636 SIA-HS-647 SIB-HS-646
 
Resets MSIS setpoints as the cooldown occurs as directed using the "LO SG PRESS RESET" pushbuttons on B05.
 
CO May manually initiate SIAS/CIAS if directed by CRS. Evaluator Note:  The next two steps may have been performed during the Abnormal Operating Procedure for the SGTL.
Ensures post filter blower is in "THR U FILTER MODE" when directed using handswitch ARN-HS-19.
 
Places SBCS valves 1007 and 1008 are in "OFF" when directed using SGN-HS-1007 and SGN-HS-1008.
Performs a cooldown using SBCS (probably using SGN-PIK-1001, but any other
 
SBCS valve is acceptable) to get T h less than 540 &deg;F when directed Resets MSIS setpoints using the "LO SG PRESS SETPOINT RESET" pushbuttons on B05 as the cooldown occurs as directed.
 
Isolates the affected SG when direct ed by ensuring the following are closed: Component Handswitch - all on B06 unless noted otherwise. ADV 184 SGA-HIC-184A Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 209 of 248 Op-Test No: _2009
_  Scenario No.:
1     Event No: 8 Event


== Description:==
== Description:==
SGTR Time      Position                        Applicants Actions or Behavior ADV 178                            SGB-HIC-178A MSIVs                              SGA-HS-251 or SGB-HS-253 (only need to push one button)
MSIV bypass                        Lights above SGA-HS-169A FWIVs                              SGA-HS-174C and SGB-HS-132C (need to push both buttons)
Downcomer valves                  SGA-HS-172 and SGB-HS-130 Blowdown Containment Isolations    SGA-HS-500P and SGB-HS-500Q (on B07)
Steam Trap Isolations              SGA-HS-1133 and SGB-HS-1135 SG Safety Valves                  LEDs above ADV controllers AF A Steam Supply                SGA-HS-134A AF A Feedwater Isolations        AFB-HS-34A and AFC-HS-36A Scenario Normal end point is when the SG is isolated.
209 of 248                      NUREG-1021, Revision 9


SGTR  Time Position Applicant's Actions or Behavior ADV 178 SGB-HIC-178A MSIVs SGA-HS-251 or SGB-HS-253 (only need to push one button) MSIV bypass Lights above SGA-HS-169A FWIVs SGA-HS-174C and SGB-HS-132C (need to push both buttons) Downcomer valves SGA-HS-172 and SGB-HS-130 Blowdown Containment Isolations SGA-HS-500P and SGB-HS-500Q (on B07) Steam Trap Isolations SGA-HS-1133 and SGB-HS-1135 SG Safety Valves LEDs above ADV controllers AF 'A' Steam Supply SGA-HS-134A AF 'A' Feedwater Isolations AFB-HS-34A and AFC-HS-36A
Appendix       D                           Scenario Outline                                   Form ES-D-1 Facility: PVNGS             Scenario No.:     3                 Op-Test No:         2009 Examiners:                                                       Operators:
 
Initial Conditions: IC # 101 (50% power, MOC)
Scenario Normal end point is when the SG is isolated.
Turnover: Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD. The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP. During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing. Maintenance is investigating at this time. The B MFP is tagged out. The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps. Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
 
Estimated return to service is 3 days. Train B is the protected train. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete.
Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 210 of 248 Facility: PVNGS Scenario No.: 3 Op-Test No: 2009 Examiners:     Operators:
Initial Conditions: IC # 101 (50% power, MOC) Turnover: Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD. The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the 'B' MFP. During the startup of the 'B' MFP it had high vibration and high temperature on the outboard pump bearing. Maintenance is investigating at this time. The 'B' MFP is tagged out. The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical mainte nance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps. Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Train B is the protected train. PC is NOT recircing the RWT. Normal Shiftly Surveilla nces are complete.
Risk Management Action Level is Green. Unit 2 is supplying the Aux Steam cross-tie header.
Risk Management Action Level is Green. Unit 2 is supplying the Aux Steam cross-tie header.
Event No. Malf. No. Event Type* Event Description 1 None N CO Swap stator cooling pumps. 2 doED ZLS037271DS_W1 doRP ZLSAAC01ALOP1_W1 mf AN_1A03D1 C CO/SRO (TS) The UV-1 LOV relay for PBA-S03 will fail requiring the crew to address the alarm response procedures and the CRS to address Tech  
Event                   Malf. No.                 Event Type*                                   Event Description No.
1                                                     N           Swap stator cooling pumps.
None CO 2       doED ZLS037271DS_W1                           C           The UV-1 LOV relay for PBA-S03 will fail requiring the crew to doRP ZLSAAC01ALOP1_W1                      CO/SRO          address the alarm response procedures and the CRS to address Tech mf AN_1A03D1                                (TS)          Specs.
3      cmTRRC03RCNPT100X_1                            C          RCN-PT-100X fails high requiring the crew to address the Alarm RO/SRO          Response procedure and select the unaffected channel.
4      cmBKED05NBNS02A_5                              C          Loss of NBN-S02 causing a loss of Turbine Cooling Water due to the CO/SRO          A Turbine Cooling failing to auto start. The CRS should address 40AO-9ZZ12, Degraded Electrical, 40AO-9ZZ03, Loss of Cooling water or the alarm response procedure to start the standby TC pump.
Other 4.16 kV loads will also be lost.
5        imf mfTH01B                                (TS)
A RCS leak will develop requiring the CRS to enter 40AO-9ZZ02, RO/SRO Excessive RCS leakrate.
6      imf mfTC13                                    M            Main Turbine Trip causes a reactor trip after a short time period due to imf mfMS16                                  ALL          failure of the SBCS Q.O. block circuitry (reactor trips on high pressurizer pressure).
7      imf cmTRMS02SGNPT1024_4                        I          After the reactor trips, a failure of Main Steam pressure transmitter CO/SRO          SGN-PT-1024 will require the CO to take manual actions to control heat removal with either the SBCS or ADVs.
8      mmf mfTH01B k:4 f:10                          M            RCS Leak degrades to a LOCA and one Containment Spray Pump imf cmMVRH03SIAUV672_6                      ALL          will fail to auto start while the other Containment Spray Header imf cmCPRH05SIBP03_5                          C          isolation will fail to open. HPSI B pump trips and the A DG does mmf mfTH01B f: 10                          RO/SRO          not come up to speed.
rfEG20                                                    Critical Task - Initiate Containment Spray flow.
9      imf mfED10A                                    C          After the CRS enters the LOCA procedure, a loss of PBA-S03 will RO/SRO          occur due to a fault on a SU transformer. This will cause a loss of the only running HPSI pump (other pump tripped when started). The CRS will transition to the FRP to restore power to PBA-S03.
Critical Task - Energize PBA-S03 from NBN-X04 to supply power to the A HPSI pump.
End                                                                The scenario is terminated when the PB bus is energized and HPSI has point                                                                started.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9                          210 of 248


Specs. 3 cmTRRC03RCNPT100X_1 C RO/SRO RCN-PT-100X fails high requiring the crew to address the Alarm Response procedure and select the unaffected channel. 4 cmBKED05NBNS02A_5 C CO/SRO  Loss of NBN-S02 causing a loss of Turbine Cooling Water due to the 'A' Turbine Cooling failing to auto start. The CRS should address 40AO-9ZZ12, Degraded Electrical, 40AO-9ZZ03, Loss of Cooling water or the alarm response procedure to start the standby TC pump.
Appendix       D                             Scenario Outline                             Form ES-D-1 Supplemental Turnover Plant conditions:
Other 4.16 kV loads will also be lost. 5  imf mfTH01B  (TS)
Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD.
RO/SRO A RCS leak will develop requiring the CRS to enter 40AO-9ZZ02, Excessive RCS leakrate. 6 imf mfTC13 imf mfMS16
Risk Management Action Level is Green.
 
Train B is protected equipment.
M ALL Main Turbine Trip causes a reactor trip after a short time period due to failure of the SBCS Q.O. block circuitry (reactor trips on high
PC is NOT recircing the RWT.
 
Unit 2 is supplying the Aux Steam cross-tie header.
pressurizer pressure). 7 imf cmTRMS02SGNPT1024_4 I CO/SRO After the reactor trips, a failure of Main Steam pressure transmitter SGN-PT-1024 will require the CO to take manual actions to control heat removal with either the SBCS or ADVs.
M ALL 8 mmf mfTH01B  k:4  f:10 imf cmMVRH03SIAUV672_6 imf cmCPRH05SIBP03_5 mmf mfTH01B f: 10
 
rfEG20 C RO/SRO RCS Leak degrades to a LOCA and one Containment Spray Pump will fail to auto start while the other Containment Spray Header isolation will fail to open. HPSI 'B' pump trips and the 'A' DG does not come up to speed. Critical Task - Initiate Containment Spray flow.
9 imf mfED10A C RO/SRO After the CRS enters the LOCA procedure, a loss of PBA-S03 will occur due to a fault on a SU transformer. This will cause a loss of the only running HPSI pump (other pump tripped when started). The CRS will transition to the FRP to restore power to PBA-S03. Critical Task - Energize PBA-S03 from NBN-X04 to supply power to the 'A' HPSI pump.
End point  The scenario is terminated when the PB bus is energized and HPSI has started. *  (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 211 of 248 Supplemental Turnover Plant conditions:
Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD. Risk Management Action Level is Green. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Equipment out of service:
Equipment out of service:
Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the 'B' MFP. During the startup of the 'B' MFP it had high vibration and high temperature on the outboard pump bearing. Maintenance is investigating at this time. The 'B' MFP is tagged out.
Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP.
During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing.
Maintenance is investigating at this time. The B MFP is tagged out.
Planned shift activities:
Planned shift activities:
Normal Shiftly surveillances are complete. The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.
Normal Shiftly surveillances are complete.
Note: The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.  
The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.
Note:
The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.
NUREG-1021, Revision 9                          211 of 248


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 212 of 248 Turnover Plant conditions:
Appendix       D                             Scenario Outline                             Form ES-D-1 Turnover Plant conditions:
Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD. Risk Management Action Level is Green. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD.
Risk Management Action Level is Green.
Train B is protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header.
Equipment out of service:
Equipment out of service:
Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the 'B' MFP. During the startup of the 'B' MFP it had high vibration and high temperature on the outboard pump bearing. Maintenance is investigating at this time. The 'B' MFP is tagged out.
Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP.
During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing.
Maintenance is investigating at this time. The B MFP is tagged out.
Planned shift activities:
Planned shift activities:
Normal Shiftly surveillances are complete. The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.  
Normal Shiftly surveillances are complete.
The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.
NUREG-1021, Revision 9                          212 of 248


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 213 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3           Event No:    1 Event
_  Scenario No.:
3   Event No:    1 Event


== Description:==
== Description:==
Swap Stator Cooling Pumps Time Position Applicant's Actions or Behavior T=0 CO Performs prerequisite - Stator Cooling System is in Operation with CEN-P01B running and CEN-P01A in standby.
Swap Stator Cooling Pumps Time       Position                           Applicants Actions or Behavior T=0         CO       Performs prerequisite - Stator Cooling System is in Operation with CEN-P01B running and CEN-P01A in standby.
Pushes CEN-HS-29B, Auto Start Test button until CEA-P01A starts as indicated by the amber light above the handswitch (CEN-HS-30) on B07.  
Pushes CEN-HS-29B, Auto Start Test button until CEA-P01A starts as indicated by the amber light above the handswitch (CEN-HS-30) on B07.
 
Places CEN-HS-30 to START Checks that the pump running red light is on.
Places CEN-HS-30 to START Checks that the pump running red light is on.
Stops CEN-P01B using handswitch CEN-HS-37.
Stops CEN-P01B using handswitch CEN-HS-37.
Pushes CEN-HS-29B, Auto Start Test button until CEA-P01B starts as indicated by the amber light above the handswitch (CEN-HS-37) on B07 Stops CEN-P01B using CEN-HS-37.
Pushes CEN-HS-29B, Auto Start Test button until CEA-P01B starts as indicated by the amber light above the handswitch (CEN-HS-37) on B07 Stops CEN-P01B using CEN-HS-37.
Checks discharge pressure is normal (~140 psig as read locally on CEN-PI-4).  
Checks discharge pressure is normal (~140 psig as read locally on CEN-PI-4).
 
Evaluator Note: The CRS may decide not to perform the auto start test of the B CE pump due to the problem with the terminal hot spot.
Evaluator Note: The CRS may decide not to perform the auto start test of the 'B' CE pump due to the problem with the terminal hot spot.  
CRS     Directs the CO to start the A Stator Cooling Water Pump and stop the B Stator Cooling Water Pump.
 
Evaluator Note: The CRS may decide not to perform the auto start test of the B CE pump due to the problem with the terminal hot spot.
CRS Directs the CO to start the 'A' Stator Cooling Water Pump and stop the 'B' Stator Cooling Water Pump.  
213 of 248                        NUREG-1021, Revision 9


Evaluator Note:  The CRS may decide not to perform the auto start test of the 'B' CE pump due to the problem with the terminal hot spot.
Appendix   D                         Operator Actions                             Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3           Event No:     2 Event
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 214 of 248 Op-Test No: _2009
_  Scenario No.:
3   Event No:   2 Event


== Description:==
== Description:==
PBA-S03 LOV relay 727-1 fails Time Position Applicant's Actions or Behavior T=10 RO Addresses Alarm on B01 using 41AL-1RK1A window 3D and performs the following: Determines alarm is not valid by observing PBA-S03 voltage indicator PBA-EI-S03. Determines that the 727-1 relay tripped by observing PBA-S03 undervoltage white indica ting lights on panel B01. Investigate the cause of the under voltage condition. Possible cause and indications of the condition include:
PBA-S03 LOV relay 727-1 fails Time       Position                         Applicants Actions or Behavior T=10         RO       Addresses Alarm on B01 using 41AL-1RK1A window 3D and performs the following:
o A low voltage condition on PBA-S03 o Excessive load on PBA Informs CRS that alarm response procedure states if an undervoltage relay is malfunctions, then place the undervoltage relay in 'Bypass". Informs the CRS to evaluate Tech Specs and to refer to the following LCOs: o 3.3.7 o 3.8.1 o 3.8.2
* Determines alarm is not valid by observing PBA-S03 voltage indicator PBA-EI-S03.
 
* Determines that the 727-1 relay tripped by observing PBA-S03 undervoltage white indicating lights on panel B01.
CRS Addresses Tech Specs and enters LCO 3.3.7 Condition 'A' which requires bypassing the channel within 1 hour.
* Investigate the cause of the undervoltage condition. Possible cause and indications of the condition include:
May refer to Control System drawing to determine which UV relay to bypass.  
o   A low voltage condition on PBA-S03 o   Excessive load on PBA
 
* Informs CRS that alarm response procedure states if an undervoltage relay is malfunctions, then place the undervoltage relay in Bypass.
Directs CO to place Train 'A' LOP1 rela y UV-1 in bypass (using 40OP-9SA01) at the BOP-ESFAS cabinet.  
* Informs the CRS to evaluate Tech Specs and to refer to the following LCOs:
o 3.3.7 o 3.8.1 o 3.8.2 CRS     Addresses Tech Specs and enters LCO 3.3.7 Condition A which requires bypassing the channel within 1 hour.
May refer to Control System drawing to determine which UV relay to bypass.
Directs CO to place Train A LOP1 relay UV-1 in bypass (using 40OP-9SA01) at the BOP-ESFAS cabinet.
CO      Places Train A UV-1 in bypass using 40OP-9SA01 by performing the following:
* Prerequisites o Ensures Applicable LCO has been reviewed (may mark this complete if CRS has discussed this).
o CRS Permission obtained (direction to do this is adequate) o Verifies redundant module in the other Train is not in bypass by a visual inspection of the Train B BOP-ESFAS Cabinet.
214 of 248                        NUREG-1021, Revision 9


CO Places Train 'A' UV-1 in bypass using 40OP-9SA01 by performing the following:  Prerequisites o Ensures Applicable LCO has been reviewed (may mark this complete if CRS has discussed this).
Appendix   D                       Operator Actions                             Form ES-D-2 Op-Test No: _2009_          Scenario No.: 3         Event No:    2 Event
o CRS Permission obtained (direction to do this is adequate) o Verifies redundant module in the other Train is not in bypass by a visual inspection of the Train B BOP-ESFAS Cabinet.
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 215 of 248 Op-Test No: _2009
_  Scenario No.:
3   Event No:    2 Event


== Description:==
== Description:==
PBA-S03 LOV relay 727-1 fails Time Position Applicant's Actions or Behavior Procedure o Ensures the sequencer is not in Auto Test by verifying the Manual half of the "Manual/Auto" button at the BOP-ESFAS cabinet is lit.
PBA-S03 LOV relay 727-1 fails Time       Position                       Applicants Actions or Behavior
o Performs a lamp test on Train 'A' BOP-ESFAS cabinet using the Lamp Test button.
* Procedure o Ensures the sequencer is not in Auto Test by verifying the Manual half of the Manual/Auto button at the BOP-ESFAS cabinet is lit.
o Determine the same relay on the redundant train module is NOT in bypass. o Place a checkmark by module to be placed in service in the procedure.
o Performs a lamp test on Train A BOP-ESFAS cabinet using the Lamp Test button.
o Bypass the UV-1 relay on Train 'A' BOP-ESFAS Cabinet by: Place Bypass key in key slot for UV-1 module Turn the key clockwise 1/4 turn or until the Bypass light comes on.
o Determine the same relay on the redundant train module is NOT in bypass.
o Requests Independent Verification of bypass.  
o Place a checkmark by module to be placed in service in the procedure.
o Bypass the UV-1 relay on Train A BOP-ESFAS Cabinet by:
Place Bypass key in key slot for UV-1 module Turn the key clockwise 1/4 turn or until the Bypass light comes on.
o   Requests Independent Verification of bypass.
215 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 216 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3           Event No:    3 Event
_  Scenario No.:
3   Event No:    3 Event


== Description:==
== Description:==
RCS controlling pressure (RCN-PT-100X) fails high.
RCS controlling pressure (RCN-PT-100X) fails high.
Time Position Applicant's Actions or Behavior T= 20 RO Receives alarms on B04 and addresses the Alarm Response Procedure 40AL-9RK4A (Windows 1B and 1A) Actions from Window 1B alarm response o Checks pressurizer pressure by observing RCN-PT-100X and 100Y on RCN-PR-100 o Selects the unaffected channel (Y) using handswitch RCN-HS-100 on B04.
Time       Position                         Applicants Actions or Behavior T= 20         RO       Receives alarms on B04 and addresses the Alarm Response Procedure 40AL-9RK4A (Windows 1B and 1A)
o Closes the heater breaker for the proportional heaters using the following handswitches: RCN-HS-100-1 RCN-HS-100-2 o Ensures ability to maintain pressu re with available heaters. Actions from Window 1A alarm response are the same as above.  
* Actions from Window 1B alarm response o   Checks pressurizer pressure by observing RCN-PT-100X and 100Y on RCN-PR-100 o   Selects the unaffected channel (Y) using handswitch RCN-HS-100 on B04.
 
o   Closes the heater breaker for the proportional heaters using the following handswitches:
CRS When RO reports failed instrument, dir ects the RO to select the unaffected Channel Y.
RCN-HS-100-1 RCN-HS-100-2 o   Ensures ability to maintain pressure with available heaters.
* Actions from Window 1A alarm response are the same as above.
CRS     When RO reports failed instrument, directs the RO to select the unaffected Channel Y.
Determines the affect of the failed instrument (affects the SBCS such that there will be bias from a high RCS pressure condition applied to the SBCS). This may be discussed by another member of the crew.
Determines the affect of the failed instrument (affects the SBCS such that there will be bias from a high RCS pressure condition applied to the SBCS). This may be discussed by another member of the crew.
If RCS pressure lowers to less than 2130 psia, the CRS should address Tech Spec 3.4.1 condition 'c'.
If RCS pressure lowers to less than 2130 psia, the CRS should address Tech Spec 3.4.1 condition c.
216 of 248                          NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 217 of 248 Op-Test No: _2009
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3           Event No:    4 Event
_  Scenario No.:
3   Event No:    4 Event


== Description:==
== Description:==
 
Loss of NBN-X02 Time       Position                             Applicants Actions or Behavior T=27         RO         The RO addresses alarms on B01 (Window 6C) (this may be done after the CO addresses the cooling water pumps due to manpower limitations).
Loss of NBN-X02 Time Position Applicant's Actions or Behavior T=27 RO The RO addresses alarms on B01 (Window 6C) (this may be done after the CO addresses the cooling water pumps due to manpower limitations).  
Refers CRS to 40AO-9ZZ12, Degraded Electrical.
 
CO         Addresses alarms on B07 (numerous windows)
Refers CRS to 40AO-9ZZ12, Degraded Electrical.  
Notices no Turbine Cooling Water Pump is running.
 
Starts the B TC pump (due to failure to auto start).
CO Addresses alarms on B07 (numerous windows) Notices no Turbine Cooling Water Pump is running.
Addresses the Normal chiller by starting the A Normal Chiller and restarting the B Normal Chiller (tripped due to low NC flow).
Starts the 'B' TC pump (due to failure to auto start).
CRS       Enters 40AO-9ZZ12, Degraded Electrical.
Addresses the Normal chiller by starting the 'A' Normal Chiller and restarting the  
Checks that all of the following pumps are operating as needed:
'B' Normal Chiller (tripped due to low NC flow).  
* Nuclear Cooling Water Pump A
 
* Turbine Cooling Water Pump A
CRS Enters 40AO-9ZZ12, Degraded Electrical. Checks that all of the following pumps are operating as needed: Nuclear Cooling Water Pump A Turbine Cooling Water Pump A Plant Cooling Water Pump A The crew notices that TC Pump A is not running and the CRS enters 40AO-9ZZ03, Loss of Cooling Water to start the TC A Pump (or the CO may use the alarm response procedure to start the pump).
* Plant Cooling Water Pump A The crew notices that TC Pump A is not running and the CRS enters 40AO-9ZZ03, Loss of Cooling Water to start the TC A Pump (or the CO may use the alarm response procedure to start the pump).
Addresses that the following have been lost:
Addresses that the following have been lost:
Condensate Pump C Heater Drain Pump A Normal Chiller C NC Pump B TC Pump B PW Pump B Directs the CO to address the Normal chillers by starting the 'A' Normal chiller and restarting the 'B' Normal Chiller (tripped due to low NC flow when the pumps shifted).  
Condensate Pump C Heater Drain Pump A Normal Chiller C NC Pump B TC Pump B PW Pump B Directs the CO to address the Normal chillers by starting the A Normal chiller and restarting the B Normal Chiller (tripped due to low NC flow when the pumps shifted).
217 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 218 of 248 Op-Test No: _2009
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:     5 Event
_  Scenario No.:
3     Event No:     5 Event


== Description:==
== Description:==
RCS Leak Time Position Applicant's Actions or Behavior T= 40 RO An operator discovers that the RCS leakrate is increasing by either observing ERFDADS leakrate number increasing, let down flow lowering, pressurizer level lowering, or by RU alarms.
RCS Leak Time       Position                             Applicants Actions or Behavior T= 40         RO       An operator discovers that the RCS leakrate is increasing by either observing ERFDADS leakrate number increasing, letdown flow lowering, pressurizer level lowering, or by RU alarms.
The Reactor Operator may start the standby charging pump if directed by the CRS. The Reactor Operator may isolate letdown if directed by the CRS. The Reactor Operator performs an RCS leakrate per Appendix B of 40AO-9ZZ02 by placing the VCT makeup in Manual a nd waiting for ERFDADS to calculate leakrate.  
The Reactor Operator may start the standby charging pump if directed by the CRS.
 
The Reactor Operator may isolate letdown if directed by the CRS.
CO Responds to RMS Alarms and informs CRS of actions/information. May monitor Containment sump levels using RDN-LI-410 and humidity /
The Reactor Operator performs an RCS leakrate per Appendix B of 40AO-9ZZ02 by placing the VCT makeup in Manual and waiting for ERFDADS to calculate leakrate.
CO       Responds to RMS Alarms and informs CRS of actions/information.
May monitor Containment sump levels using RDN-LI-410 and humidity /
temperature Yokogawa record 1JMNTJR001 (Both on B07).
temperature Yokogawa record 1JMNTJR001 (Both on B07).
May monitor Containment Pressu re using PPS indicators on B-05.  
May monitor Containment Pressure using PPS indicators on B-05.
 
CRS       Evaluator Note: If the CRS decides to trip the reactor due to the leak, have the driver insert Event 6 before the crew trips the reactor.
CRS Evaluator Note: If the CRS decides to trip the reactor due to the leak, have the driver insert Event 6 before the crew trips the reactor. The CRS enters 40AO-9ZZ02, Excessive RCS Leakrate and performs the following:  
The CRS enters 40AO-9ZZ02, Excessive RCS Leakrate and performs the following:
: 1. Directs starting all available charging pumps if pressurizer level is lowering.  
: 1. Directs starting all available charging pumps if pressurizer level is lowering.
: 2. Direction isolate letdown if all charging pumps are running and pressurizer level is lowering.  
: 2. Direction isolate letdown if all charging pumps are running and pressurizer level is lowering.
: 3. If all charging pumps are running, letdown is isolated, and pressurizer level is lowering, direct a Reactor Trip.  
: 3. If all charging pumps are running, letdown is isolated, and pressurizer level is lowering, direct a Reactor Trip.
: 4. Ensure the event is being classified.
: 4. Ensure the event is being classified.
Evaluator note: The CRS should tell the Shift Manager to classify the event.  
Evaluator note: The CRS should tell the Shift Manager to classify the event.
: 5. Ensure compliance with LCO 3.4.14, RCS operation leakage. The CRS should enter condition 'A' of LCO 3.4.
: 5. Ensure compliance with LCO 3.4.14, RCS operation leakage. The CRS should enter condition A of LCO 3.4.14 (reduce leakage in 4 hours or be in Mode 3 in 6 hours and Mode 5 in 36 hours).
14 (reduce leakage in 4 hours or be in Mode 3 in 6 hours and Mode 5 in 36 hours).  
: 6. Directs chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.
: 6. Directs chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.  
: 7. Notifies RP that an RCS leak exists.
: 7. Notifies RP that an RCS leak exists.  
: 8. Directs the RO to determine the leakrate.
: 8. Directs the RO to determine the leakrate.
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 219 of 248 Op-Test No: _2009
218 of 248                        NUREG-1021, Revision 9
_  Scenario No.:
 
3     Event No:     5 Event
Appendix   D                       Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 3           Event No:     5 Event


== Description:==
== Description:==
RCS Leak Time Position Applicant's Actions or Behavior Evaluator note: Leakrate should be about 50 gpm. 9. Evaluate plant parameters to attempt to identify the source of the leakage.
RCS Leak Time       Position                         Applicants Actions or Behavior Evaluator note: Leakrate should be about 50 gpm.
: 10. Directs an operator to walkdown charging and letdown piping.  
: 9. Evaluate plant parameters to attempt to identify the source of the leakage.
: 11. Continue efforts to locat e and isolate the leak.  
: 10. Directs an operator to walkdown charging and letdown piping.
: 11. Continue efforts to locate and isolate the leak.
219 of 248                          NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 220 of 248 Op-Test No: _2009
Appendix   D                           Operator Actions                             Form ES-D-2 Op-Test No: _2009_              Scenario No.: 3         Event No:   6 Event
_  Scenario No.:
3   Event No:   6 Event


== Description:==
== Description:==
Main turbine trip.
Main turbine trip.
Time Position Applicant's Actions or Behavior T= 55 Crew Crew recognizes a Main Turbine trip has occurred. Crew may recognize that the SBCS did not quick open which results in a reactor trip. Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.  
Time       Position                           Applicants Actions or Behavior T= 55         Crew       Crew recognizes a Main Turbine trip has occurred.
 
Crew may recognize that the SBCS did not quick open which results in a reactor trip.
CRS May direct a manual reactor trip Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.  
Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.
CRS       May direct a manual reactor trip Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.
220 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 221 of 248 Op-Test No: _2009
Appendix   D                           Operator Actions                                 Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:     7 Event
_  Scenario No.:
3   Event No:   7 Event


== Description:==
== Description:==
Standard Post Trip Actions/ Failure of SGN-PT-1024.
Standard Post Trip Actions/ Failure of SGN-PT-1024.
Time Position Applicant's Actions or Behavior T= 55 CRS Directs the crew through the Standard Post Trip Actions (see next event for steps).
Time       Position                             Applicants Actions or Behavior T= 55         CRS       Directs the crew through the Standard Post Trip Actions (see next event for steps).
RO May report Reactivity (may be done by the CO). Will report the status of the Electric Pl ant. All vital and non-vital busses are energized Reports Pressurizer level and RCS subcooling.  
RO         May report Reactivity (may be done by the CO).
 
Will report the status of the Electric Plant. All vital and non-vital busses are energized Reports Pressurizer level and RCS subcooling.
Reports Seal injection and Nuclear Cooling Water available to the RCPs. Reports RCS pressure.
Reports Seal injection and Nuclear Cooling Water available to the RCPs.
Reports all RCPs operating, loop T, and RCS subcooling. May report RCS Tc (usually done by the CO).
Reports RCS pressure.
Reports all RCPs operating, loop T, and RCS subcooling.
May report RCS Tc (usually done by the CO).
May report containment pressure and status of Radiation Monitoring.
May report containment pressure and status of Radiation Monitoring.
May report containment temperature and containment pressure.  
May report containment temperature and containment pressure.
 
CO         May report Reactivity.
CO May report Reactivity. Reports status of the Main Turbine and Generator output breakers.
Reports status of the Main Turbine and Generator output breakers.
Reports SG levels and method of feed. Should be with MFPs in RTO.
Reports SG levels and method of feed. Should be with MFPs in RTO.
May report RCS Tc.  
May report RCS Tc.
Reports SG pressure. Due failure of SGN-PT0-1024, the CO will have to control SG pressure with the SBCS valves in manual (SGN-PIK-1001), the SBCS Master Controller in manual, or may use ADVs by giving the ADVs two permissive and using the controller below for the applicable ADV.
ADV 184                                SGA-HIC-184A ADV 178                                SGB-HIC-178A ADV 185                                SGB-HIC-185A ADV 179                                SGB-HIC-179A May report containment pressure and status of Radiation Monitoring.
May report containment temperature and containment pressure.
221 of 248                            NUREG-1021, Revision 9


Reports SG pressure. Due failure of S GN-PT0-1024, the CO will have to control SG pressure with the SBCS valves in manual (SGN-PIK-1001), the SBCS Master Controller in manual, or may use ADVs by giving the ADVs two permissive and using the controller below for the applicable ADV. ADV 184 SGA-HIC-184A ADV 178 SGB-HIC-178A ADV 185 SGB-HIC-185A ADV 179 SGB-HIC-179A May report containment pressure and status of Radiation Monitoring. May report containment temperature and containment pressure.
Appendix   D                         Operator Actions                                 Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:     8 Event
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 222 of 248 Op-Test No: _2009
_  Scenario No.:
3   Event No:   8 Event


== Description:==
== Description:==
RCS Leak degrades/Failure of Containment Spray/DG 'A' fails to reach rated speed/ HPSI B trips Time Position Applicant's Actions or Behavior T= 7 minutes after reactor trip Crew Notices RCS leak rate has increased dramatically.  
RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time     Position                           Applicants Actions or Behavior T= 7       Crew     Notices RCS leak rate has increased dramatically.
minutes after reactor trip RO      Secures RCPs on either CSAS or loss of subcooling.
Recognize that there is no Containment Spray flow after the Containment Spray Actuation Signal. The Train A CS valve fails to open and cannot be opened. The Train B CS pump fails to auto start.
Starts the Train B Containment Spray Pump using SIB-HS-6 on B02.
Critical Task - initiate CS flow.
May report DG A not running at rated speed after SIAS starts the DG. (The crew may attempt to override and raise the speed of the DG which will be unsuccessful.)
May report HPSI B has an 86 lockout (this may be done at end of SPTA briefing)
CO      Shifts SG pressure control to the ADVs if using the SBCS.
Shifts SG feed to Auxiliary Feedwater due to the MSIS.
AF A                      AF B                      AF N SGA-HS-134A                    AFB-HS-10                  AFA-HS-11 SGA-HS-138A                  AFB-HS-30A                  CTA-HS-1 AFA-HS-32A                  AFB-HS-31A                  CTA-HS-4 AFC-HS-36A                  AFB-HS-34A              SGN-FIK-1133 or AFA-HS-37A                  AFB-HS-35A                SGN-HS-1143 AFC-HS33A                                            SGN-FIK-1123 or SGN-HS-1145 CRS      Evaluator Note: These actions may vary depending on where the CRS is in the procedure when the RCS leakrate is increased. See actions at this section.
Implements procedure 40EP-9EO01, Standard Post Trip Actions.
: 1. Open the placekeeper and enter the EOP Entry Time.
: 2. Determine that Reactivity Control acceptance criteria are met by the following:
: a. Check that reactor power is dropping.
: b. Check that start-up rate is negative.
: c. Check that ALL full strength CEAs are inserted.
: 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
: a. Check that the Main Turbine is tripped.
: b. Check that the Main Generator output breakers are open.
: c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:
222 of 248                          NUREG-1021, Revision 9


RO Secures RCPs on either CSAS or loss of subcooling. Recognize that there is no Containment Spray flow after the Containment Spray Actuation Signal. The Train A CS valve fails to open and cannot be opened. The Train 'B' CS pump fails to auto start.
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:    8 Event
Starts the Train B Containment Spray Pump using SIB-HS-6 on B02. Critical Task - initiate CS flow. May report DG 'A' not running at rated speed after SIAS starts the DG.  (The crew may attempt to override and raise the speed of the DG which will be unsuccessful.) May report HPSI B has an 86 lockout (this may be done at end of SPTA briefing)
 
CO Shifts SG pressure contro l to the ADVs if using the SBCS. Shifts SG feed to Auxiliary Feedwater due to the MSIS. 
 
AF 'A' AF 'B' AF 'N' SGA-HS-134A AFB-HS-10 AFA-HS-11 SGA-HS-138A AFB-HS-30A CTA-HS-1 AFA-HS-32A AFB-HS-31A CTA-HS-4 AFC-HS-36A AFB-HS-34A AFA-HS-37A AFB-HS-35A SGN-FIK-1133 or SGN-HS-1143 AFC-HS33A  SGN-FIK-1123 or SGN-HS-1145
 
CRS Evaluator Note:  These actions may vary depending on where the CRS is in the procedure when the RCS leakrate is increased. See actions at this section. Implements procedure 40EP-9EO01, Standard Post Trip Actions.
: 1. Open the placekeeper and enter the EOP Entry Time. 2. Determine that Reactivity Control acceptance criteria are met by the following:
: a. Check that reactor power is dropping.
: b. Check that start-up rate is negative.
: c. Check that ALL full strength CEAs are inserted. 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following: a. Check that the Main Turbine is tripped.
: b. Check that the Main Generator output breakers are open.
: c. Check that station loads have transfe rred to offsite electrical power such that BOTH of the following conditions are met:
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 223 of 248 Op-Test No: _2009
_  Scenario No.:
3   Event No:    8 Event


== Description:==
== Description:==
RCS Leak degrades/Failure of Containment Spray/DG 'A' fails to reach rated speed/ HPSI B trips Time Position Applicant's Actions or Behavior
RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time     Position                               Applicants Actions or Behavior
* All vital and non-vital AC buses are powered
* All vital and non-vital AC buses are powered
* All vital and non-vital DC buses are powered 4. Determine that RCS Inventory Control acceptance criteria are met by the following: a. Check that Pressurizer level meets BOTH of the following:
* All vital and non-vital DC buses are powered
: 4. Determine that RCS Inventory Control acceptance criteria are met by the following:
: a. Check that Pressurizer level meets BOTH of the following:
* 10 - 65%
* 10 - 65%
* Trending as expected to 33 - 53% b. Check that the RCS is 24&deg;F or more subcooled.  
* Trending as expected to 33 - 53%
: b. Check that the RCS is 24&deg;F or more subcooled.
: c. Check that BOTH of the following are in service to all RCPs.
: c. Check that BOTH of the following are in service to all RCPs.
* Seal injection
* Seal injection
* Nuclear Cooling Water 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following: Pressurizer pressure is 1837 - 2285 psia Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
* Nuclear Cooling Water
5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop. 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following: At least one RCP is operating Loop T is less than 10&deg;F RCS is 24&deg;F or more subcooled 7. Determine that RCS Heat Removal acceptance criteria are met by the following: a. Check that at least one Steam Generator meets BOTH of the following conditions:
: 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
* Pressurizer pressure is 1837 - 2285 psia
* Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.
: 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
* At least one RCP is operating
* Loop T is less than 10&deg;F
* RCS is 24&deg;F or more subcooled
: 7. Determine that RCS Heat Removal acceptance criteria are met by the following:
: a. Check that at least one Steam Generator meets BOTH of the following conditions:
* Level is 35% WR or more
* Level is 35% WR or more
* Feedwater is restoring or maintaining level 45 - 60% NR b. Check that Tc is 560 - 570&deg;F.  
* Feedwater is restoring or maintaining level 45 - 60% NR
: c. Check that steam generator pressure is 1140 - 1200 psia. 8. Determine that Containment Isolation acceptance criteria are met by the following:  
: b. Check that Tc is 560 - 570&deg;F.
: c. Check that Containment pressure is less than 2.5 psig.  
: c. Check that steam generator pressure is 1140 - 1200 psia.
: d. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions: No valid containment area radiation monitor alarms or unexplained rise in activity No valid steam plant activity monitor alarms or unexplained rise in activity 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are me t by the following:
: 8. Determine that Containment Isolation acceptance criteria are met by the following:
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 224 of 248 Op-Test No: _2009
: c. Check that Containment pressure is less than 2.5 psig.
_  Scenario No.:
: d. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
3   Event No:    8 Event
* No valid containment area radiation monitor alarms or unexplained rise in activity
* No valid steam plant activity monitor alarms or unexplained rise in activity
: 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:
223 of 248                        NUREG-1021, Revision 9
 
Appendix   D                       Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3         Event No:    8 Event


== Description:==
== Description:==
RCS Leak degrades/Failure of Containment Spray/DG 'A' fails to reach rated speed/ HPSI B trips Time Position Applicant's Actions or Behavior  
RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time     Position                         Applicants Actions or Behavior
: a. Check that containment temperature is less than 117&deg;F.  
: a. Check that containment temperature is less than 117&deg;F.
: b. Check that containment pressure is less than 2.5 psig.
: b. Check that containment pressure is less than 2.5 psig.
When the LOCA gets large the CRS may repeat some SPTA steps. If time permits, may direct an operator to manually initiate a SIAS/CIAS/MSIS/ and or CSAS Directs RO to ensure proper SIAS actuation   Directs RO to stop RCPs on CSAS or loss of subcooling. Directs RO to isolate RCP seal bleedoff. Direct CO to shift feedwater to Auxiliary Feed and use ADVs to control SG pressure. Ensures adequate CS flow.
When the LOCA gets large the CRS may repeat some SPTA steps.
Diagnoses a LOCA and proceeds to 40EP-9EO03.  
* If time permits, may direct an operator to manually initiate a SIAS/CIAS/MSIS/ and or CSAS
* Directs RO to ensure proper SIAS actuation
* Directs RO to stop RCPs on CSAS or loss of subcooling.
* Directs RO to isolate RCP seal bleedoff.
* Direct CO to shift feedwater to Auxiliary Feed and use ADVs to control SG pressure.
* Ensures adequate CS flow.
Diagnoses a LOCA and proceeds to 40EP-9EO03.
224 of 248                        NUREG-1021, Revision 9


Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 225 of 248 Op-Test No: _2009
Appendix    D                         Operator Actions                                 Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:    9 Event
_  Scenario No.:
3     Event No:    9 Event


== Description:==
== Description:==
Loss of PBA-S03 Time Position Applicant's Actions or Behavior T= When the CRS enters the LOCA procedure Crew Recognizes a LOP has occurred by alarm on B05 and other plant indications.  
Loss of PBA-S03 Time     Position                           Applicants Actions or Behavior T= When       Crew       Recognizes a LOP has occurred by alarm on B05 and other plant indications.
the CRS enters the LOCA procedure RO            1. Determines that PBA-S03 has lost power.
: 2. Determines that his only running HPSI pump has lost power (this may be pointed out by another crew member).
: 3. CRS/RO may attempt to override and increase speed on the A DG. This will not be successful
: 4. Overrides and opens HPB-UV-2 on B02.
: 5. Places the B Hydrogen Analyzer in service.
: 6. Energizes PBA-S03 from NBN-S04 by closing breaker PBA-S03L using handswitch PBA-SS-S03K (Synch Switch) and PBA-II-S03K (breaker switch) when directed by the CRS.
: 7. Starts HPSI A using SIA-HS-1 or may wait for pump to start automatically.
CRS        Determines a loss of a safety function has occurred and transitions to the Functional Recovery Procedure.
: 1. Ensures the event is being classified
: 2. Enters the EOP entry time.
: 3. If pressurizer pressure remains below the SIA S setpoint, ensure one RCP is stopped in each loop or if < 24 &deg;F, ensure all RCPs are stopped.
: 4. If any RCPs are operating, directs the RO to perform Standard Appendix 16, RCP Trip Criteria.
: 5. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.
: 6. If CIAS has actuated, directs the RO to override and open HPB-UV-2 on B02.
: 7. Directs the RO to place the Hydrogen analyzers in service.
: 8. Identifies the success paths to be used to satisfy each safety function.
RC-1                                      HR-2 MVDC-1                                    CI-1 MVAC Jeopardized                      CTPC-2 IC Jeopardized                        CCGC-1 225 of 248                          NUREG-1021, Revision 9


RO 1. Determines that PBA-S03 has lost power.    
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 3             Event No:    9 Event
: 2. Determines that his only running HPSI pump has lost power (this may be pointed out by another crew member).
: 3. CRS/RO may attempt to override and increase speed on the 'A' DG. This will not be successful
: 4. Overrides and opens HPB-UV-2 on B02.
: 5. Places the 'B' Hydrogen An alyzer in service.
: 6. Energizes PBA-S03 from NBN-S04 by closing breaker PBA-S03L using handswitch PBA-SS-S03K (Synch Switch) and PBA-II-S03K (breaker
 
switch) when directed by the CRS.
: 7. Starts HPSI A using SIA-HS-1 or may wait for pump to start automatically.
 
CRS Determines a loss of a safety function has occurred and transitions to the Functional Recovery Procedure.
: 1. Ensures the event is being classified
: 2. Enters the EOP entry time.
: 3. If pressurizer pressure remains below the SIA S setpoint, ensure one RCP is stopped in each loop or if < 24 &deg;F, ensure all RCPs are stopped.
: 4. If any RCPs are operating, directs the RO to perform Standard Appendix 16, RCP Trip Criteria.
: 5. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.
: 6. If CIAS has actuated, directs the RO to override and open HPB-UV-2 on B02. 7. Directs the RO to place the Hy drogen analyzers in service.
: 8. Identifies the success paths to be used to satisfy each safety function. RC-1 HR-2 MVDC-1 CI-1 MVAC Jeopardized CTPC-2 IC Jeopardized CCGC-1 Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 226 of 248 Op-Test No: _2009
_  Scenario No.:
3     Event No:    9 Event


== Description:==
== Description:==
Loss of PBA-S03 Time Position Applicant's Actions or Behavior PC-3   9. Directs an operator to perform the Safety Function Status Check for those success paths in use.  
Loss of PBA-S03 Time       Position                           Applicants Actions or Behavior PC-3
: 10. Performs MVAC-1 (first jeopardized Safety Function) and directs the RO to close PBA-S03K to energize PBA-S03 from the train B ESF Transformer (NBN-X04).  
: 9. Directs an operator to perform the Safety Function Status Check for those success paths in use.
: 11. The CRS directs the RO to start the 'A' HPSI pump or may wait for HPSI to start automatically (~ 60 seconds after bus is powered). Critical Task - X-tie PB busses to restore HPSI.  
: 10. Performs MVAC-1 (first jeopardized Safety Function) and directs the RO to close PBA-S03K to energize PBA-S03 from the train B ESF Transformer (NBN-X04).
: 11. The CRS directs the RO to start the A HPSI pump or may wait for HPSI to start automatically (~ 60 seconds after bus is powered).
Critical Task - X-tie PB busses to restore HPSI.
End Point                Scenario Normal end point is when the HPSI A is started after PBA-S03 is energized.
226 of 248                          NUREG-1021, Revision 9


End Point  Scenario Normal end point is when the HPSI A is started after PBA-S03 is energized.  
Appendix      D                            Scenario Outline                              Form ES-D-1 Facility: PVNGS            Scenario No.:            4                Op-Test No:        2009 Examiners:                                                    Operators:
Initial Conditions: IC #100, (100% power, MOC).
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Train B is protected equipment. The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a Vibration Technician standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps.
Normal Shiftly Surveillances are complete. Risk Management Action Level is Yellow. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Event                  Malf. No.                  Event Type*                                Event Description No.
1      None                                          N Crew Shifts running Plant Cooling Water Pumps.
CO/SRO 2      imf cmTRCV19RCALT110X_4                      I The Train A Pressurizer Level Transmitter will fail. The crew should RO/SRO address the Alarm response procedure and select the Train B level (TS) transmitter. The CRS should address Tech Specs.
3      imf cmTRRX12SGCLT1123C_4                      I A SG level transmitter fails low. The crew addresses the alarm CO/SRO        response procedure and places the correct parameter in bypass. The (TS)        CRS addresses Tech Specs.
4      imf mfFW17B                                  C The B MFP will trip requiring the CRS to enter 40AO-9ZZ09, RO/CO/SRO RPCB (Loss of Feedpump).
5      imf mfFW15A                              M- ALL After the crew stabilizes power, the A MFP will experience high imf mfFW17A vibrations. The crew should address the alarm response procedure and determine they have to trip the reactor and trip the MFP.
6      imf mfRD03I                                  C        On the trip, two CEAs will stick out. This will require the crew to imf mfRD03M                              RO/SRO        borate.
7      imf mf FW21B                                  C        5 minutes into the SPTAs, the B AFW pump will trip. The CO imf mfFW23                                CO/SRO        should shift to the N AFW pump. If the examinee attempts to use AFA-P01 it will not come up to speed.
8      imf cmCPFW07AFNP01_3                        M          When the CRS enters the Reactor Trip procedure, AFN-P01 discharge ALL        pressure will degrade. The CRS should realize that a LOAF has occurred and transition to the FRP to feed the Steam Generators with the condensate pumps.
Critical Task - Take actions to align and initiate condensate to a steam generator.
End                                                              The scenario is terminated when the crew has established feed to one point                                                            SG with a condensate pump.
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH.
Normal Shiftly Surveillances are complete.
Risk Management Action Level is Yellow.
Train B is the protected equipment.
NUREG-1021, Revision 9                            227 of 248


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 227 of 248 Facility:  PVNGS  Scenario No.:  4  Op-Test No: 2009 Examiners:      Operators:
Appendix       D                             Scenario Outline                           Form ES-D-1 PC is NOT recircing the RWT.
Initial Conditions: IC #100, (100% power, MOC).
Unit 2 is supplying the Aux Steam cross-tie header.
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.
Train B is protected equipment. The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a Vibration Technician standing by at the pump to take vibrations on the 'A' PW pump. The area operator has been briefed and is standing by the PW pumps. Normal Shiftly Surveillances are complete. Risk Management Action Level is Yellow. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Event No. Malf. No. Event Type* Event Description 1 None N CO/SRO Crew Shifts running Plant Cooling Water Pumps. 2 imf cmTRCV19RCALT110X_4 I RO/SRO (TS) The Train A Pressurizer Level Transmitter will fail. The crew should address the Alarm response procedure and select the Train B level transmitter. The CRS should address Tech Specs. 3 imf cmTRRX12SGCLT1123C_4 I CO/SRO (TS) A SG level transmitter fails low. The crew addresses the alarm response procedure and places the correct parameter in bypass. The CRS addresses Tech Specs.
4 imf mfFW17B C RO/CO/SRO The 'B' MFP will trip requiring the CRS to enter 40AO-9ZZ09, RPCB (Loss of Feedpump).
5 imf mfFW15A imf mfFW17A M- ALL  After the crew stabilizes power, the 'A' MFP will experience high vibrations. The crew should address the alarm response procedure and determine they have to trip the reactor and trip the MFP.
6 imf mfRD03I imf mfRD03M C RO/SRO On the trip, two CEAs will stick out. This will require the crew to borate. 7 imf mf FW21B imf mfFW23 C CO/SRO 5 minutes into the SPTAs, the 'B" AFW pump will trip. The CO should shift to the 'N' AFW pump. If the examinee attempts to use AFA-P01 it will not come up to speed. 8 imf cmCPFW07AFNP01_3 M ALL When the CRS enters the Reactor Tr ip procedure, AFN-P01 discharge pressure will degrade. The CRS should realize that a LOAF has occurred and transition to the FRP to feed the Steam Generators with the condensate pumps. Critical Task - Take actions to align and initiate condensate to a steam generator.
End point  The scenario is terminated when the crew has established feed to one SG with a condensate pump. *  (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH. Normal Shiftly Surveillances are complete. Risk Management Action Level is Yellow. Train B is the protected equipment.
Appendix    D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 228 of 248 PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Equipment out of service:
Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Planned shift activities:
The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the 'A' PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.
The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.
Note: The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.  
Note:
The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.
NUREG-1021, Revision 9                            228 of 248


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 229 of 248 Supplemental Turnover Plant conditions:
Appendix       D                             Scenario Outline                           Form ES-D-1 Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH. Normal Shiftly Surveillances are complete. Risk Management Action Level is Yellow. Train B is the protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.
Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH.
Normal Shiftly Surveillances are complete.
Risk Management Action Level is Yellow.
Train B is the protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header.
Equipment out of service:
Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Planned shift activities:
The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the 'A' PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.  
The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.
NUREG-1021, Revision 9                            229 of 248


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 230 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                           Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4         Event No: 1 Event
_  Scenario No.:
4   Event No:   1 Event


== Description:==
== Description:==
Crew shifts running Plant Cooling Water Pumps.
Crew shifts running Plant Cooling Water Pumps.
Time Position Applicant's Actions or Behavior T=0 CO Starts PW pump A using PWN-HS-5 on B07. Directs AO to check pump running with no unusual noise or vibration.
Time       Position                           Applicants Actions or Behavior T=0         CO           Starts PW pump A using PWN-HS-5 on B07.
Directs AO to check pump running with no unusual noise or vibration.
Checks motor current decays to less than 137 amps.
Checks motor current decays to less than 137 amps.
Directs the AO to close PWN-HCV-12, PWN Pump B discharge valve When PWN-HCV-12 is closed, stops PW Pump B using PWN-HS-6.
Directs the AO to close PWN-HCV-12, PWN Pump B discharge valve When PWN-HCV-12 is closed, stops PW Pump B using PWN-HS-6.
Checks pressure alarm is clear and pressure returns to normal.  
Checks pressure alarm is clear and pressure returns to normal.
 
Directs AO to open PWN-HCV-12.
Directs AO to open PWN-HCV-12.
Directs AO to inspect PW Pump B to ensure no rotation.  
Directs AO to inspect PW Pump B to ensure no rotation.
230 of 248                    NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 231 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                     Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4         Event No: 1 Event
_  Scenario No.:
4   Event No:   1 Event


== Description:==
== Description:==
Crew shifts running Plant Cooling Water Pumps.
Crew shifts running Plant Cooling Water Pumps.
Time Position Applicant's Actions or Behavior  
Time       Position                           Applicants Actions or Behavior 231 of 248                NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 232 of 248 Op-Test No: _2009
Appendix   D                         Operator Actions                             Form ES-D-2 Op-Test No: _2009_          Scenario No.: 4           Event No:   2 Event
_  Scenario No.:
4   Event No:   2 Event


== Description:==
== Description:==
Train A Pressurizer Level instrument fails low Time      Position                          Applicants Actions or Behavior T=5          RO        Addresses the alarms on B04 (Windows 1A and 2B)
: 1. Verifies the controlling channel (RCA-LT-110X) has failed low
: 2. Selects Channel Y on RCN-HS-100 (Level Control Selector Channel X/Y) and RCN-HS-100-3 (Heater Control Selector Level Trip Channel X/Y)
: 3. Closes the proportional heater breakers by going to ON on handswitches RCN-HS-100-1 and RCN-HS-100-2.
CRS      Addresses Tech Specs:
Enters LCO 3.3.10 (Post Accident Monitoring) condition A and LCO 3.3.11 (Remote Shutdown Panel) condition A. Both require restoration of the function within 30 day.
232 of 248                      NUREG-1021, Revision 9


Train A Pressurizer Level instrument fails low Time Position Applicant's Actions or Behavior T=5 RO Addresses the alarms on B04 (Windows 1A and 2B)
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4             Event No:     3 Event
: 1. Verifies the controlling channel (RCA-LT-110X) has failed low
: 2. Selects Channel Y on RCN-HS-100 (Level Control Selector Channel X/Y) and RCN-HS-100-3 (Heater Control Selector
 
Level Trip Channel X/Y)
: 3. Closes the proportional heater breakers by going to "ON" on handswitches RCN-HS-100-1 and RCN-HS-100-2.
 
CRS Addresses Tech Specs: Enters LCO 3.3.10 (Post Accident Monitoring) condition 'A' and LCO 3.3.11 (Remote Shutdown Panel) condition 'A'. Both require restoration of the function within 30 day.
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 233 of 248 Op-Test No: _2009
_  Scenario No.:
4     Event No:     3 Event


== Description:==
== Description:==
SG #2 Channel C level transmitter failure Time Position Applicant's Actions or Behavior T=12 CO Addresses the alarm response procedure  
SG #2 Channel C level transmitter failure Time       Position                           Applicants Actions or Behavior T=12         CO       Addresses the alarm response procedure
: 1. Compares SG #2 level instrumentation and determines Channel C has failed low.  
: 1. Compares SG #2 level instrumentation and determines Channel C has failed low.
: 2. May recommend bypassing the aff ected channel to the CRS.  
: 2. May recommend bypassing the affected channel to the CRS.
: 3. May inform the CRS that Tech Specs 3.3.1, 3.3.5, 3.3.10 and 3.3.11 may be affected.  
: 3. May inform the CRS that Tech Specs 3.3.1, 3.3.5, 3.3.10 and 3.3.11 may be affected.
: 4. Bypasses the affected parameters (8, 18 and 19) as directed by the CRS.  
: 4. Bypasses the affected parameters (8, 18 and 19) as directed by the CRS.
CRS      Addresses Tech Specs
: 1. Enters LCO 3.3.1 (Reactor Protection System (RPS) Instrumentation -
Operating) condition A and LCO 3.3.5 (Engineered Safety Feature Actuation System (ESFAS) Instrumentation) condition A which both require bypassing or tripping the affected channel within 1 hour.
: 2. Refers to the bases for LCO 3.3.1 or LCO 3.3.5 to determine which instruments need to be bypassed.
Evaluator Note: LCO 3.3.10 is not applicable because it only requires 2 of the 4 channels and LCO 3.3.11 are not applicable for this channel because this is not a channel monitors at the Remote Shutdown panel.
: 3. Directs the CO to bypass Steam Generator #2 Level Low (RPS) and Steam Generator #1 and #2 Level Low (ESFAS) per the LCO bases.
233 of 248                        NUREG-1021, Revision 9


CRS Addresses Tech Specs
Appendix   D                           Operator Actions                                 Form ES-D-2 Op-Test No: _2009_              Scenario No.: 4             Event No:     4 Event
: 1. Enters LCO 3.3.1 (Reactor Protection System (RPS) Instrumentation - Operating) condition 'A' and LCO 3.3.5 (Engineered Safety Feature Actuation System (ESFAS) Instrumentation) condition 'A' which both require bypassing or tripping the affected channel within 1 hour.    
: 2. Refers to the bases for LCO 3.3.1 or LCO 3.3.5 to determine which instruments need to be bypassed. Evaluator Note:  LCO 3.3.10 is not applicable because it only requires 2 of the 4 channels and LCO 3.3.11 are not applicable for this channel because
 
this is not a channel monitors at the Remote Shutdown panel.
: 3. Directs the CO to bypass Steam Generator #2 Level Low (RPS) and Steam Generator #1 and #2 Level Low (ESFAS) per the LCO bases.
 
Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 234 of 248 Op-Test No: _2009
_  Scenario No.:
4   Event No:   4 Event


== Description:==
== Description:==
Trip of the B MFP Time      Position                              Applicants Actions or Behavior T=22        Crew        Addresses the alarms and diagnoses the trip of the B MFP.
CRS        Enters 40AO-9ZZ09 (RPCB-Loss of Feedpump) and performs the following:
: 1. Enters the AOP entry time
: 2. Checks that A RPCB - Loss of Feedpump has actuated and CEA subgroups 4, 5, and 22 have inserted.
: 3. Checks that Main Turbine Setback-Runback has lowered Main Turbine load to 65% or less.
: 4. Checks that no CEAs are deviating by greater than 6.6 inches if ANY CEA Reg Groups are below the Transient Insertion Limits.
: 5. May direct an operator to perform Appendix D, Status Check RPCB Loss of Feedpump (normally done by the STA).
: 6. Directs the CO to restore and maintain SG levels 45-60% NR.
: 7. Checks that RRS is adjusting CEAs to restore Tave/Tref + 3&deg;F.
: 8. If condenser hotwell level is less than 41 inches, directs an operator to restore level to 41 inches or more.
: 9. Directs an operator to remove RPCB from service by pushing the AUTO ACTUATE OUT OF SERVICE and the TEST RESET pushbuttons.
: 10. Directs the CO to perform a lamp test to ensure the LOAD LIMITING light illuminates.
: 11. Directs the CO to lower the load limit potentiometer until the LOAD LIMITING light comes on.
: 12. Directs CO to raise Speed Bias on the operating Main Feedwater Pump to zero or more
: 13. Directs an operator to place CEDMCS is Manual Sequential when CEA motion is only required for Xenon Buildup
: 14. Directs an operator to monitor ASI.
: 15. Directs an operator to start boron equalization of the pressurizer.
: 16. Directs the CO to adjust FWCS DP to stabilize feedwater (if necessary)
RO              1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by CO).
: 2. Checks for CEA deviation.
: 3. Checks that RRS is adjusting to maintain Tave/Tref + 3&deg;F.
: 4. Places CEDMCS in Manual Sequential using the CEDMCS Mode Select Switch on B04.
: 5. Commences Pressurizer Boron Equalization by performing the following:
234 of 248                          NUREG-1021, Revision 9


Trip of the 'B' MFP Time Position Applicant's Actions or Behavior T=22 Crew Addresses the alarms and diagnoses the trip of the 'B' MFP. CRS Enters 40AO-9ZZ09 (RPCB-Loss of Feedpump) and performs the following:
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_              Scenario No.: 4             Event No:   4 Event
: 1. Enters the AOP entry time
: 2. Checks that A RPCB - Loss of Feedpump has actuated and CEA subgroups 4, 5, and 22 have inserted.
: 3. Checks that Main Turbine Setback-Runback has lowered Main Turbine load to 65% or less.
: 4. Checks that no CEAs are deviating by greater than 6.6 inches if ANY CEA Reg Groups are below the Transient Insertion Limits.
: 5. May direct an operator to perform Appendix D, Status Check RPCB Loss of Feedpump (normally done by the STA).
: 6. Directs the CO to restore and maintain SG levels 45-60% NR.
: 7. Checks that RRS is adjusting CEAs to restore Tave/Tref +
3&deg;F. 8. If condenser hotwell level is less than 41 inches, directs an operator to restore level to 41 inches or more.
: 9. Directs an operator to remove RPCB from service by pushing the "AUTO ACTUATE OUT OF SERVICE" and the "TEST RESET" pushbuttons.
: 10. Directs the CO to perform a lamp test to ensure the "LOAD LIMITING" light illuminates.
: 11. Directs the CO to lower the load limit potentiometer until the "LOAD LIMITING" light comes on.
: 12. Directs CO to raise Speed Bias on the operating Main Feedwater Pump to zero or more
: 13. Directs an operator to place CEDMCS is "Manual Sequential" when CEA motion is only required for Xenon Buildup
: 14. Directs an operator to monitor ASI.
: 15. Directs an operator to start boron equalization of the pressurizer.
: 16. Directs the CO to adjust FWCS DP to stabilize feedwater (if necessary)
 
RO 1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by CO).
: 2. Checks for CEA deviation.
: 3. Checks that RRS is adjusting to maintain Tave/Tref +
3&deg;F. 4. Places CEDMCS in Manual Sequential using the CEDMCS Mode Select Switch on B04.
: 5. Commences Pressurizer Boron Equalization by performing the following:
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 235 of 248 Op-Test No: _2009
_  Scenario No.:
4   Event No:   4 Event


== Description:==
== Description:==
 
Trip of the B MFP Time       Position                             Applicants Actions or Behavior
Trip of the 'B' MFP Time Position Applicant's Actions or Behavior  
: a. Override and energize all pressurizer backup heaters:
: a. Override and energize all pressurizer backup heaters:
RCA-HS-100-4          RCB-HS-100-5 RCN-HS-100-6          RCN-HS-100-7 RCN-HS-100-8          RCN-HS-100-9  
RCA-HS-100-4          RCB-HS-100-5 RCN-HS-100-6          RCN-HS-100-7 RCN-HS-100-8          RCN-HS-100-9
: b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to 2220 psia.  
: b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to 2220 psia.
: 6. May perform Appendix D (Status Check of 40AO-9ZZ09)  
: 6. May perform Appendix D (Status Check of 40AO-9ZZ09)
: 7. May remove RPCB from service by pushing the "TEST RESET" and "AUTO-ACTUATE OOS" pushbuttons on the RPCB module on B04.  
: 7. May remove RPCB from service by pushing the TEST RESET and AUTO-ACTUATE OOS pushbuttons on the RPCB module on B04.
(May be done by CO)  
(May be done by CO)
CO              1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).
: 2. Ensures the Main Turbine Setback-Runback has reduced Main Turbine load to < 65% (~ 890 MWs).
: 3. Monitors SG levels to ensure they are restoring and maintaining 45-60% NR.
: 4. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).
: 5. Restore hotwell level to > 41 inches if necessary.
: 6. May remove RPCB from service by pushing the TEST RESET and AUTO-ACTUATE OOS pushbuttons on the RPCB module on B04.
(May be done by RO)
: 7. Performs a lamp test on the LOAD LIMITING light and then lowers the load limit potentiometer on B06 to cause the LOAD LIMITING light to come on.
: 8. Monitors ASI.
: 9. Ensures operating Feedpump bias is at zero at the FP Speed controller.
: 10. Ensures FWCS DP is maintaining feedwater steady.
235 of 248                        NUREG-1021, Revision 9


CO 1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).
Appendix   D                         Operator Actions                   Form ES-D-2 Op-Test No: _2009_              Scenario No.: 4       Event No: 4 Event
: 2. Ensures the Main Turbine Setback-R unback has reduced Main Turbine load to < 65% (~ 890 MWs).
: 3. Monitors SG levels to ensure they are restoring and maintaining 45-60% NR. 4. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).
: 5. Restore hotwell level to > 41 inches if necessary.
: 6. May remove RPCB from service by pushing the "TEST RESET" and "AUTO-ACTUATE OOS" pushbuttons on the RPCB module on B04.
(May be done by RO)
: 7. Performs a lamp test on the LOAD LIMITING light and then lowers the load limit potentiometer on B06 to cause the LOAD LIMITING light to come on.
: 8. Monitors ASI.
: 9. Ensures operating Feedpump bias is at zero at the FP Speed controller.
: 10. Ensures FWCS DP is maintaining feedwater steady.
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 236 of 248 Op-Test No: _2009
_  Scenario No.:
4   Event No:   4 Event


== Description:==
== Description:==
Trip of the B MFP Time      Position                        Applicants Actions or Behavior 236 of 248                NUREG-1021, Revision 9


Trip of the 'B' MFP Time Position Applicant's Actions or Behavior
Appendix   D                         Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4           Event No:     5 Event
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 237 of 248 Op-Test No: _2009
_  Scenario No.:
4   Event No:   5 Event


== Description:==
== Description:==
High Vibration on the A Main Feedpump (Trip initiator)
Time      Position                            Applicants Actions or Behavior T=35        CO        Addresses the high vibration alarm on B06.
: 1. Checks FWPT A vibration on recorder MTN-YR-301 on B07.
: 2. Checks FWPT A vibration on the plant computer.
: 3. Contacts vibration group to take local readings.
: 4. Directs an operator to check the FWPT A for vibration
: 5. When the vibration is greater than 5 mils and the AO reports the Feedpump is vibrating, informs the CRS that the alarm response directs a trip of the FWPT.
: 6. Trips the A MFP using the red trip pushbutton (FTN-HS-51) on B06.
CRS      When the CO reports that the alarm response directs a trip of the FWPT A, the CRS should direct a reactor trip and a trip of the FWPT A.
RO        Trips the reactor when directed by the CRS using the four RTSG breaker pushbuttons on B05 (SBA-HS-1, SBB-HS-2, SBC-HS-3, and SBD-HS-4).
237 of 248                        NUREG-1021, Revision 9


High Vibration on the 'A' Main Feedpump (Trip initiator)
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4             Event No:     6 Event
Time Position Applicant's Actions or Behavior T=35 CO  Addresses the high vibration alarm on B06.
: 1. Checks FWPT 'A' vibration on recorder MTN-YR-301 on B07.
: 2. Checks FWPT 'A' vibration on the plant computer.
: 3. Contacts vibration group to take local readings.
: 4. Directs an operator to check the FWPT A for vibration
: 5. When the vibration is greater than 5 mils and the AO reports the Feedpump is vibrating, informs the CRS that the alarm response directs a trip of the FWPT.
: 6. Trips the A MFP using the red trip pushbutton (FTN-HS-51) on B06.
 
CRS When the CO reports that the alarm response directs a trip of the FWPT A, the CRS should direct a reactor trip and a trip of the FWPT A.
 
RO Trips the reactor when directed by the CRS using the four RTSG breaker pushbuttons on B05 (SBA-HS-1, SBB-HS-2, SBC-HS-3, and SBD-HS-4).
 
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 238 of 248 Op-Test No: _2009
_  Scenario No.:
4     Event No:   6 Event


== Description:==
== Description:==
Standard Post Trip actions with 2 CEAs stuck out.
Standard Post Trip actions with 2 CEAs stuck out.
Time Position Applicant's Actions or Behavior T= 45 Crew The crew commences performance of the SPTAs. CO 1. Reports that power is lowering, negative startup rate and more than one CEA stuck out.  
Time       Position                             Applicants Actions or Behavior T= 45         Crew       The crew commences performance of the SPTAs.
: 2. Checks the Main Turbine is tripped and the generator output breakers are open. Evaluator note: Since the RO is starting a boration, the CRS may use the CO to continue with the SPTAs until the RO gets the boration started, therefore the following 6 steps may be completed by the CO until the RO takes over.  
CO             1. Reports that power is lowering, negative startup rate and more than one CEA stuck out.
: 3. Reports the status of the electric plant (may be performed by the RO) - all vital and non-vital busses are energized.  
: 2. Checks the Main Turbine is tripped and the generator output breakers are open.
: 4. Checks pressurizer level is 10-65% trending to 33-53%.  
Evaluator note: Since the RO is starting a boration, the CRS may use the CO to continue with the SPTAs until the RO gets the boration started, therefore the following 6 steps may be completed by the CO until the RO takes over.
: 5. Checks that the RCS is 24&deg;F or more subcooled.  
: 3. Reports the status of the electric plant (may be performed by the RO) -
: 6. Checks that Seal Injection and Nuclear Cooling water is available to all RCPs. 7. Checks RCS pressure 1837-2285 trending to 2225-2275 psia.  
all vital and non-vital busses are energized.
: 8. Determines Core Heat Removal is met by at least one RCP running, Loop T less than 10&deg;F, and RCS is 24&deg;F or more subcooled.  
: 4. Checks pressurizer level is 10-65% trending to 33-53%.
: 9. Uses AFB to feed the Steam Generators since both Main Feedwater pumps are tripped.  
: 5. Checks that the RCS is 24&deg;F or more subcooled.
: 10. Checks Tc is 560-570&deg;F.  
: 6. Checks that Seal Injection and Nuclear Cooling water is available to all RCPs.
: 11. Checks Steam Generator Pressure is 1140-1200 psia. Evaluator note: The following steps may be performed by the RO or CO.  
: 7. Checks RCS pressure 1837-2285 trending to 2225-2275 psia.
: 12. Checks Containment Pressure < 2.5 psig and checks RMS for alarm or trends. 13. Checks Containment temperature < 117&deg;F and Containment pressure < 2.5 psig. Evaluator Note: Due to the failure of RCN-PT-100X lowering the modulate signal, the SBCS will cycle valves when the permissive is automatically removed unless the CO takes manual control.  
: 8. Determines Core Heat Removal is met by at least one RCP running, Loop T less than 10&deg;F, and RCS is 24&deg;F or more subcooled.
: 9. Uses AFB to feed the Steam Generators since both Main Feedwater pumps are tripped.
: 10. Checks Tc is 560-570&deg;F.
: 11. Checks Steam Generator Pressure is 1140-1200 psia.
Evaluator note: The following steps may be performed by the RO or CO.
: 12. Checks Containment Pressure < 2.5 psig and checks RMS for alarm or trends.
: 13. Checks Containment temperature < 117&deg;F and Containment pressure <
2.5 psig.
Evaluator Note: Due to the failure of RCN-PT-100X lowering the modulate signal, the SBCS will cycle valves when the permissive is automatically removed unless the CO takes manual control.
RO        Commences boration of the RCS using Standard Appendix 103.
(basic steps the RO will perform)
: 4. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
: 5. Selects the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) (minimum 5000 gallons).
: 6. Starts the boration as follows:
: a. Place CHN-HS-210 in the BORATE position.
: b. Depress the Reset pushbutton - the left pushbutton on the 238 of 248                        NUREG-1021, Revision 9


RO Commences boration of the RCS using Standard Appendix 103. (basic steps the RO will perform)
Appendix   D                             Operator Actions                                 Form ES-D-2 Op-Test No: _2009_            Scenario No.: 4               Event No:    6 Event
: 4. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
: 5. Selects the "Target" makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) (minimum 5000 gallons).
: 6. Starts the boration as follows:
: a. Place CHN-HS-210 in the BORATE position.
: b. Depress the "Reset" pushbutton - the left pushbutton on the Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 239 of 248 Op-Test No: _2009
_  Scenario No.:
4     Event No:    6 Event


== Description:==
== Description:==
Standard Post Trip actions with 2 CEAs stuck out.
Standard Post Trip actions with 2 CEAs stuck out.
Time Position Applicant's Actions or Behavior totalizer/counter module (Micro-Motion).  
Time       Position                               Applicants Actions or Behavior totalizer/counter module (Micro-Motion).
: c. Depress the "Start" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion). When boration is started, he will continue with the SPTAs as noted in the CO actions above.  
: c. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
 
When boration is started, he will continue with the SPTAs as noted in the CO actions above.
CRS Implements procedure 40EP-9EO01, Standard Post Trip Actions.  
CRS       Implements procedure 40EP-9EO01, Standard Post Trip Actions.
: 1. Open the placekeeper and enter the EOP Entry Time. 2. Determines that Reactivity Control acceptance criteria are not met because of the stuck out CEAs and directs the RO to borate using Standard Appendix 103. 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following: a. Check that the Main Turbine is tripped.  
: 1. Open the placekeeper and enter the EOP Entry Time.
: b. Check that the Main Generator output breakers are open.  
: 2. Determines that Reactivity Control acceptance criteria are not met because of the stuck out CEAs and directs the RO to borate using Standard Appendix 103.
: c. Check that station loads have transfe rred to offsite electrical power such that BOTH of the following conditions are met:
: 3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
: a. Check that the Main Turbine is tripped.
: b. Check that the Main Generator output breakers are open.
: c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:
* All vital and non-vital AC buses are powered
* All vital and non-vital AC buses are powered
* All vital and non-vital DC buses are powered 4. Determine that RCS Inventory Control acceptance criteria are met by the following: a. Check that Pressurizer level meets BOTH of the following:
* All vital and non-vital DC buses are powered
: 4. Determine that RCS Inventory Control acceptance criteria are met by the following:
: a. Check that Pressurizer level meets BOTH of the following:
* 10 - 65%
* 10 - 65%
* Trending as expected to 33 - 53% b. Check that the RCS is 24&deg;F or more subcooled.  
* Trending as expected to 33 - 53%
: b. Check that the RCS is 24&deg;F or more subcooled.
: c. Check that BOTH of the following are in service to all RCPs.
: c. Check that BOTH of the following are in service to all RCPs.
* Seal injection
* Seal injection
* Nuclear Cooling Water 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following: Pressurizer pressure is 1837 - 2285 psia Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
* Nuclear Cooling Water
5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop. 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following: At least one RCP is operating Loop T is less than 10&deg;F RCS is 24&deg;F or more subcooled 7. Determine that RCS Heat Removal acceptance criteria are met by the following: a. Check that at least one Steam Generator meets BOTH of the Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 240 of 248 Op-Test No: _2009
: 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
_  Scenario No.:
* Pressurizer pressure is 1837 - 2285 psia
4     Event No:    6 Event
* Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.
5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.
: 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
* At least one RCP is operating
* Loop T is less than 10&deg;F
* RCS is 24&deg;F or more subcooled
: 7. Determine that RCS Heat Removal acceptance criteria are met by the following:
: a. Check that at least one Steam Generator meets BOTH of the 239 of 248                        NUREG-1021, Revision 9
 
Appendix   D                           Operator Actions                               Form ES-D-2 Op-Test No: _2009_              Scenario No.: 4           Event No:    6 Event


== Description:==
== Description:==
Standard Post Trip actions with 2 CEAs stuck out.
Standard Post Trip actions with 2 CEAs stuck out.
Time Position Applicant's Actions or Behavior following conditions:
Time       Position                               Applicants Actions or Behavior following conditions:
* Level is 35% WR or more
* Level is 35% WR or more
* Feedwater is restoring or maintaining level 45 - 60% NR. b. Checks that Tc is between 560 and 570&deg;F.  
* Feedwater is restoring or maintaining level 45 - 60% NR.
: c. Check that steam generator pressure is 1140 - 1200 psia.  
: b. Checks that Tc is between 560 and 570&deg;F.
: 8. Determine that Containment Isolation acceptance criteria are met by the following:  
: c. Check that steam generator pressure is 1140 - 1200 psia.
: e. Check that Containment pressure is less than 2.5 psig.  
: 8. Determine that Containment Isolation acceptance criteria are met by the following:
: f. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions: No valid containment area radiation monitor alarms or unexplained rise in activity No valid steam plant activity monitor alarms or unexplained rise in activity 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are me t by the following:  
: e. Check that Containment pressure is less than 2.5 psig.
: a. Check that containment temperature is less than 117&deg;F.  
: f. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
* No valid containment area radiation monitor alarms or unexplained rise in activity
* No valid steam plant activity monitor alarms or unexplained rise in activity
: 9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:
: a. Check that containment temperature is less than 117&deg;F.
: b. Check that containment pressure is less than 2.5 psig.
: b. Check that containment pressure is less than 2.5 psig.
Diagnoses a Reactor Trip.  
Diagnoses a Reactor Trip.
240 of 248                        NUREG-1021, Revision 9


Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 241 of 248 Op-Test No: _2009
Appendix     D                           Operator Actions                                 Form ES-D-2 Op-Test No: _2009_                Scenario No.: 4             Event No:    7 Event
_  Scenario No.:
4     Event No:    7 Event


== Description:==
== Description:==
Trip of 'B' AFW pump Time Position Applicant's Actions or Behavior If the CO uses AFN first, then go to event 8. T= 50 (~ 5 minutes into the SPTAs after CO reports feeding SGs) RO Receives a SESS alarm on AFW pump B and informs the CRS and CO.  
Trip of B AFW pump Time       Position                             Applicants Actions or Behavior If the CO uses AFN first, then go to event 8.
 
T= 50 (~ 5       RO         Receives a SESS alarm on AFW pump B and informs the CRS and CO.
CRS Directs the CO to use AFN-P01 to feed the SGs.  
minutes into the SPTAs after CO reports feeding SGs)
 
CRS         Directs the CO to use AFN-P01 to feed the SGs.
CO 1. Determines the AFW pump B has tripped on an 86 lockout.  
CO               1. Determines the AFW pump B has tripped on an 86 lockout.
: 2. Commences feeding the SGs with AFW pump N by performing the following:  
: 2. Commences feeding the SGs with AFW pump N by performing the following:
: a. Opening both suction valves for AFN-P01 using handswitches CTA-HS-1 and CTA-HS-2) on B06.  
: a. Opening both suction valves for AFN-P01 using handswitches CTA-HS-1 and CTA-HS-2) on B06.
: b. Taking manual control of the Downcomer Flow control valves (SGN-FIK-1113 and SGN-FIK-1123) and closing the flow valves or closing the Downcomer block valves (SGN-HS-
: b. Taking manual control of the Downcomer Flow control valves (SGN-FIK-1113 and SGN-FIK-1123) and closing the flow valves or closing the Downcomer block valves (SGN-HS-1142 and SGN-HS-1144)
 
: c. After the suction valves are open, starting AFN-P01 using handswitch AFA-HS-11.
1142 and SGN-HS-1144)  
: d. Start feeding the SGs by using the Downcomer flow controllers (SGN-FIK-1113 and SGN-FIK-1123) in manual or by using the Downcomer bypass valves (SGN-HS-1143 and SGN-HS-1145).
: c. After the suction valves are open, starting AFN-P01 using handswitch AFA-HS-11.  
Examiner Note: If the examinee attempts to use AFA-P01, it will not come up to speed (malfunction in the simulator setup).
: d. Start feeding the SGs by using the Downcomer flow controllers (SGN-FIK-1113 and SGN-FIK-1123) in manual or by using the Downcomer bypass valves (SGN-HS-1143 and  
Op-Test No: _2009_                Scenario No.: 4             Event No:    8 Event
 
SGN-HS-1145).
Examiner Note: If the examinee attempts to use AFA-P01, it will not come up to speed (malfunction in the simulator setup).  
 
Op-Test No: _2009
_  Scenario No.:
4     Event No:    8 Event


== Description:==
== Description:==
AFN-P01 discharge degrades.
AFN-P01 discharge degrades.
Time Position Applicant's Actions or Behavior T= after CRS enters CO 1. Notices that the feed to the SGs has degraded or stopped.  
Time       Position                             Applicants Actions or Behavior T= after       CO               1. Notices that the feed to the SGs has degraded or stopped.
CRS
: 2. Informs the CRS of a loss of all feed.
: 2. Informs the CRS of a loss of all feed.
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 242 of 248 Op-Test No: _2009
enters 241 of 248                          NUREG-1021, Revision 9
_  Scenario No.:
 
4     Event No:    8 Event
Appendix   D                       Operator Actions                                 Form ES-D-2 Op-Test No: _2009_        Scenario No.: 4             Event No:    8 Event


== Description:==
== Description:==
AFN-P01 discharge degrades.
AFN-P01 discharge degrades.
Time Position Applicant's Actions or Behavior Reactor Trip EOP Evaluator Note: See next page for continuance of CO actions after CRS enters the Functional Recovery Procedure..
Time       Position                         Applicants Actions or Behavior Reactor               Evaluator Note: See next page for continuance of CO actions after CRS enters Trip EOP              the Functional Recovery Procedure..
CRS Determines a loss of safety function has occurred and transitions to the Functional Recovery Procedure.  
CRS     Determines a loss of safety function has occurred and transitions to the Functional Recovery Procedure.
: 12. Ensures the event is being classified  
: 12. Ensures the event is being classified
: 13. Enters the EOP entry time.  
: 13. Enters the EOP entry time.
: 14. Directs the RO to perform Standard Appendix 16, RCP Trip Criteria.  
: 14. Directs the RO to perform Standard Appendix 16, RCP Trip Criteria.
: 15. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.  
: 15. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.
: 16. Directs the RO to place the Hy drogen analyzers in service.  
: 16. Directs the RO to place the Hydrogen analyzers in service.
: 17. Identifies the success paths to be used to satisfy each safety function.  
: 17. Identifies the success paths to be used to satisfy each safety function.
: a. RC-2 e. HR-1 Jeopardized
: a. RC-2                   e. HR-1 Jeopardized
: b. MVDC-1 f. CI-1 c. MVAC-1 g. CTPC-1 d. IC-1 h. CCGC-1 e. PC-1 18. Directs an operator to perform the Safety Function Status Check for those success paths in use.  
: b. MVDC-1                 f. CI-1
: 19. Proceed to HR-1 since it is the only jeopardized Safety Function.  
: c. MVAC-1                 g. CTPC-1
: 20. Directs the RO to stop all RCPs.  
: d. IC-1                   h. CCGC-1
: 21. Directs the CO to close all Blowdown Containment Isolation valves and SG sample valves.  
: e. PC-1
: 22. Directs the CO to perform Standard Appendix 44, FEEDING WITH THE CONDENSATE PUMPS.  
: 18. Directs an operator to perform the Safety Function Status Check for those success paths in use.
 
: 19. Proceed to HR-1 since it is the only jeopardized Safety Function.
CO When directed performs Standard Appendix 44, FEEDING WITH CONDENSATE PUMPS. 1. Selects a SG to feed (will probably discuss this with the CRS).  
: 20. Directs the RO to stop all RCPs.
: 21. Directs the CO to close all Blowdown Containment Isolation valves and SG sample valves.
: 22. Directs the CO to perform Standard Appendix 44, FEEDING WITH THE CONDENSATE PUMPS.
CO     When directed performs Standard Appendix 44, FEEDING WITH CONDENSATE PUMPS.
: 1. Selects a SG to feed (will probably discuss this with the CRS).
: 2. Open both Downcomer Isolation valves for the selected SG.
: 2. Open both Downcomer Isolation valves for the selected SG.
SG #1 selected SG #2 selected SGA-UV-172 SGA-UV-175 SGB-UV-130 SGB-UV-135  
SG #1 selected                         SG #2 selected SGA-UV-172                             SGA-UV-175 SGB-UV-130                             SGB-UV-135
: 3. Place the Downcomer Control valve in manual and close the Downcomer control valve.
: 3. Place the Downcomer Control valve in manual and close the Downcomer control valve.
SG #1 selected SG #2 selected SGN-FV-1113 SGN-FV-1123  
SG #1 selected                         SG #2 selected SGN-FV-1113                           SGN-FV-1123
: 4. If SG Downcomer Block valve will be used to feed the SG, open the Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 243 of 248 Op-Test No: _2009
: 4. If SG Downcomer Block valve will be used to feed the SG, open the 242 of 248                          NUREG-1021, Revision 9
_  Scenario No.:
 
4     Event No:   8 Event
Appendix   D                       Operator Actions                               Form ES-D-2 Op-Test No: _2009_        Scenario No.: 4             Event No:     8 Event


== Description:==
== Description:==
AFN-P01 discharge degrades.
AFN-P01 discharge degrades.
Time Position Applicant's Actions or Behavior Downcomer block valve SG #1 selected SG #2 selected SGN-HV-1142 SGN-HV-1144  
Time       Position                         Applicants Actions or Behavior Downcomer block valve SG #1 selected                         SG #2 selected SGN-HV-1142                           SGN-HV-1144
: 5. Close the Downcomer Bypass valve.
: 5. Close the Downcomer Bypass valve.
SG #1 selected SG #2 selected SGN-HV-1143 SGN-HV-1145  
SG #1 selected                       SG #2 selected SGN-HV-1143                           SGN-HV-1145
: 6. Fast close ALL Economizer FWIVs (both SGs) using pushbuttons.
: 6. Fast close ALL Economizer FWIVs (both SGs) using pushbuttons.
SGA-UV-174 SGA-UV-177 SGB-UV-132 SGB-UV-137  
SGA-UV-174                             SGA-UV-177 SGB-UV-132                             SGB-UV-137
: 7. If using the Downcomer Bypass Valve to feed the SG, ensure Downcomer Block Valve is closed.
: 7. If using the Downcomer Bypass Valve to feed the SG, ensure Downcomer Block Valve is closed.
SG #1 selected SG #2 selected SGN-HV-1142 SGN-HV-1144  
SG #1 selected                       SG #2 selected SGN-HV-1142                           SGN-HV-1144
: 8. Ensure one set or more of the HP f eedwater heater isolation valves are open. (HV-73 and HV-101 or HV-74 and HV-102)  
: 8. Ensure one set or more of the HP feedwater heater isolation valves are open. (HV-73 and HV-101 or HV-74 and HV-102)
: 9. Ensure both of the FWPTs are tripped.  
: 9. Ensure both of the FWPTs are tripped.
: 10. Check both FWPT Miniflow valves are closed (FWN-FV-1 and FWN-FV-2) 11. Ensure one or more of the FWPT Discharge valves are open (FWN-HV-31 and/or FWN-HV-32).  
: 10. Check both FWPT Miniflow valves are closed (FWN-FV-1 and FWN-FV-2)
: 12. Ensure one set or more of the LP F eedwater heater isolation valves are open (red lights lit on any of these handswitches - CDN-HS-214, CDN-HS-215, and/or CDN-HS-216).  
: 11. Ensure one or more of the FWPT Discharge valves are open (FWN-HV-31 and/or FWN-HV-32).
: 13. Ensures a condensate pump is running by observing red light on above any of the three handswitches (CDN-HS- 11, 12, or 13).  
: 12. Ensure one set or more of the LP Feedwater heater isolation valves are open (red lights lit on any of these handswitches - CDN-HS-214, CDN-HS-215, and/or CDN-HS-216).
: 14. IF RCS makeup is require then the CO will coordinates with the RO to start all available charging pumps, minimize letdown flow, Start one HPSI pump and open at least one HPSI Injection valve. The CO will probably discuss this step with the CRS.  
: 13. Ensures a condensate pump is running by observing red light on above any of the three handswitches (CDN-HS- 11, 12, or 13).
: 15. IF a MSIS or SIAS not initiated, lower the setpoints for the MSIS or SIAS as the cooldown and depressurization continues using the "LO SG PRESS SETPOINT RESET" and the "LO PXR PRESS SETPOINT  
: 14. IF RCS makeup is require then the CO will coordinates with the RO to start all available charging pumps, minimize letdown flow, Start one HPSI pump and open at least one HPSI Injection valve. The CO will probably discuss this step with the CRS.
: 15. IF a MSIS or SIAS not initiated, lower the setpoints for the MSIS or SIAS as the cooldown and depressurization continues using the LO SG PRESS SETPOINT RESET and the LO PXR PRESS SETPOINT RESET pushbuttons on B05. This will probably be done by both the RO and CO.
: 16. Perform Appendix 5, RCS and Pressurizer Cooldown Log.
: 17. Fast close the MSIVs on the selected SG using the pushbuttons on B06.
SG #1- SGA-HS-251 or SGB-HS-253 (only need to push one button)
SG #2- SGA-HS-250 or SGB-HS-252 (only need to push one button)
: 18. Lower the pressure in the affected SG to below the condensate pump discharge pressure using ADVs (SGA-HIC-184A, SGB-HIC-178A, SGB-HIC-185A, and/or SGA-HIC-179A) ion B06.
Evaluator Note: Per the Technical Guidelines for Standard Appendix 44, the 100&deg;F/hr cooldown rate may be exceeded during steam generator depressurization and subsequent refill with condensate. Re-establishing Feedwater o recover heat removal capabilities has priority over the 243 of 248                        NUREG-1021, Revision 9


RESET" pushbuttons on B05. This will probably be done by both the RO and CO.
Appendix  D                       Operator Actions                               Form ES-D-2 Op-Test No: _2009_          Scenario No.: 4             Event No:    8 Event
: 16. Perform Appendix 5, RCS and Pressurizer Cooldown Log.    
: 17. Fast close the MSIVs on the selected SG using the pushbuttons on B06. SG #1- SGA-HS-251 or SGB-HS-253 (only need to push one button) SG #2- SGA-HS-250 or SGB-HS-252 (only need to push one button)
: 18. Lower the pressure in the affected SG to below the condensate pump discharge pressure using ADVs (SGA-HIC-184A, SGB-HIC-178A, SGB-HIC-185A, and/or SGA-HIC-179A) ion B06. Evaluator Note: Per the Technical Guidelines for Standard Appendix 44, the 100&deg;F/hr cooldown rate may be ex ceeded during steam generator depressurization and subsequent refill with condensate. Re-establishing
 
Feedwater o recover heat removal capabilities has priority over the Appendix    D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 244 of 248 Op-Test No: _2009
_  Scenario No.:
4     Event No:    8 Event


== Description:==
== Description:==
AFN-P01 discharge degrades.
AFN-P01 discharge degrades.
Time Position Applicant's Actions or Behavior consequences of over cooling.  
Time       Position                         Applicants Actions or Behavior consequences of over cooling.
: 19. Maintain the non-selected SG pressure < 1200 psia.  
: 19. Maintain the non-selected SG pressure < 1200 psia.
: 20. If the selected steam generator is dry then maintain feed flow rate of <
: 20. If the selected steam generator is dry then maintain feed flow rate of <
1000 gpm.  
1000 gpm.
: 21. Initiates feed flow using the Downcomer Controllers or the Downcomer bypass valves. Critical Task: Take actions to align and initiate condensate to a steam generator.  
: 21. Initiates feed flow using the Downcomer Controllers or the Downcomer bypass valves.
 
Critical Task: Take actions to align and initiate condensate to a steam generator.
RO Performs Standard Appendix 16 for running RCPs. Stops all RCPs when directed by the CRS (using RCN-HS-1, 2, 3 and 4 on B04).  
RO     Performs Standard Appendix 16 for running RCPs.
 
Stops all RCPs when directed by the CRS (using RCN-HS-1, 2, 3 and 4 on B04).
Places the H 2 Analyzers in service when directed by the CRS (by using HP-HS-1, 2, 7, 8, 9A, and 10A on B02).
Places the H2 Analyzers in service when directed by the CRS (by using HP-HS-1, 2, 7, 8, 9A, and 10A on B02).
May operate Aux Sprays using CHA-HS-205 or CHB-HS-203 on B03)
May operate Aux Sprays using CHA-HS-205 or CHB-HS-203 on B03)
When the CO is ready to reduce the SG pressure for feed using condensate the RO may start available charging pumps (using handswitch CHA-HS216, CHA-HS-218A, and/or CHB-HS-217) minimize letdown using the PLCS master controller (RCN-LIC-110) on B04, start a HPSI pump (using handswitch SIA-HS-1 or SIB-HS-1), and open at least one HPSI injection valve when directed. Train A valves Train B vales SIA-HS-617  
When the CO is ready to reduce the SG pressure for feed using condensate the RO may start available charging pumps (using handswitch CHA-HS216, CHA-HS-218A, and/or CHB-HS-217) minimize letdown using the PLCS master controller (RCN-LIC-110) on B04, start a HPSI pump (using handswitch SIA-HS-1 or SIB-HS-1), and open at least one HPSI injection valve when directed.
 
Train A valves                             Train B vales SIA-HS-617                               SIB-HS-616 SIA-HS-627                                SIB-HS-626 SIA-HS-637                                SIB-HS-636 SIA-HS-647                                SIB-HS-646 The RO may assist resetting MSIS and SIAS setpoints during depressurization of the Steam Generator using the LO SG PRESS RESET pushbuttons on B05.
SIA-HS-627
The RO may assist controlling SG pressures while the CO performs standard Appendix 44.
 
End Point              The scenario may be stopped when feedwater is established to one SG using condensate.
SIA-HS-637
244 of 248                        NUREG-1021, Revision 9
 
SIA-HS-647 SIB-HS-616 SIB-HS-626 SIB-HS-636 SIB-HS-646  


The RO may assist resetting MSIS and SIAS setpoints during depressurization of the Steam Generator using the "LO SG PRESS RESET" pushbuttons on B05.
Appendix D Operator Actions    Form ES-D-2 245 of 248 NUREG-1021, Revision 9
The RO may assist controlling SG pressures while the CO performs standard Appendix 44.


End Point  The scenario may be stopped when feedwater is established to one SG using condensate.
Appendix       D                           Scenario Outline                               Form ES-D-1 Facility: PVNGS           Scenario No.:   __1             Op-Test No:       2009 Examiners:                                                   Operators:         (SRO)
 
(ATC/RO)
Appendix   D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 245 of 248 Appendix    D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 246 of 248 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners:           Operators: (SRO)
(CO/BOP)
          (ATC/RO)  
Initial Conditions: IC #100, (100% power, MOC). This is the as run scenario for one crew.
          (CO/BOP)
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.
Initial Conditions: IC #100, (100% power, MOC).
This is the as run scenario for one "crew".
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralize r was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Norm al Shiftly Surveillances are complete. Risk Management Action Level is Green.
Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Event No. Malf. No. Event Type* Event Description 1 None N CO/SRO Shift Condensate Demineralizers. 2 imf cmCNCV04CHNFIC243_2   I RO/SRO A seal injection controller will fail in automatic requiring the crew to take manual control of the controller. 3 imf cmCPCH03HCNA02A_6   imf cmCPCH03HCNA02C_6 C CO/SRO The A and C CEDM fans will trip requiring the CRS to enter 40AO-9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).
Event                 Malf. No.                 Event Type*                                 Event Description No.
4 imf mfRD02B R RO/CO/SRO (TS) CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.
1     None                                       N Shift Condensate Demineralizers.
Crew begins a 20% downpower. SR O enters LCO 3.1.5 Condition A and LCO 3.2.4 Condition A.
CO/SRO 2     imf cmCNCV04CHNFIC243_2                     I A seal injection controller will fail in automatic requiring the crew to RO/SRO take manual control of the controller.
5 imf mfTH06A C CO/SRO (TS) A Steam Generator Tube leak occu rs requiring the crew to enter 40AO-9ZZ02, Excessive RCS leakrate.
3     imf cmCPCH03HCNA02A_6                       C         The A and C CEDM fans will trip requiring the CRS to enter 40AO-imf cmCPCH03HCNA02C_6                    CO/SRO        9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).
6 imf mfRD02L mfRD12A mfRP04A mfRP04C M - ALL Another CEA slips into the core. Th is will cause a reactor trip signal but an ATWS will occur. This will require the crew to open the breakers supplying the CEDM MG sets. Critical Task - Crew will insert all CEAs.
4     imf mfRD02B                                 R CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.
7 mfRX01 I CO /SRO After the trip Tave will fail low requiring the CO to manually feed the SGs.
RO/CO/SRO Crew begins a 20% downpower. SRO enters LCO 3.1.5 Condition A (TS) and LCO 3.2.4 Condition A.
8 mmf mfTH06A M-ALL The SGTL will degrade on the trip.
5     imf mfTH06A                                 C A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO 40AO-9ZZ02, Excessive RCS leakrate.
The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.  
(TS) 6     imf mfRD02L                             M - ALL       Another CEA slips into the core. This will cause a reactor trip signal mfRD12A                                                but an ATWS will occur. This will require the crew to open the mfRP04A                                                breakers supplying the CEDM MG sets.
 
Critical Task - Crew will insert all CEAs.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End point  The scenario is terminated when the crew commences affected steam generator has been isolated or at the discretion of the lead examiner * (N)ormal,   (R)eactivity,   (I)nstrument,   (C)omponent,   (M)ajor Supplemental Turnover Plant conditions:
mfRP04C 7     mfRX01                                       I         After the trip Tave will fail low requiring the CO to manually feed the CO /SRO        SGs.
8     mmf mfTH06A                             M-ALL         The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End                                                             The scenario is terminated when the crew commences affected steam point                                                          generator has been isolated or at the discretion of the lead examiner
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 247 of 248 Risk Management Action Level is GREEN. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
NUREG-1021, Revision 9                          246 of 248
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
 
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
Appendix       D                           Scenario Outline                             Form ES-D-1 Risk Management Action Level is GREEN.
Note: The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.  
Train B is protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.
The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
Note:
The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.
NUREG-1021, Revision 9                          247 of 248


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 248 of 248 Turnover Plant conditions:
Appendix       D                           Scenario Outline                           Form ES-D-1 Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance. Risk Management Action Level is GREEN. Train B is protected equipment. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
Risk Management Action Level is GREEN.
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.  
Train B is protected equipment.
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.
Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.
The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
NUREG-1021, Revision 9                          248 of 248


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 1 of 3 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners:           Operators: (SRO)
Appendix     D                         Scenario Outline                           Form ES-D-1 Facility: PVNGS                 Scenario No.:   __1             Op-Test No:       2009 Examiners:                                               Operators:       (SRO)
          (ATC/RO)  
(ATC/RO)
          (CO/BOP)
(CO/BOP)
Initial Conditions: IC #100, (100% power, MOC).
Initial Conditions: IC #100, (100% power, MOC).
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green. Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.
Event No. Malf. No. Event Type* Event Description 1 None N CO/SRO Shift Condensate Demineralizers. 2 imf cmCNCV04CHNFIC243_2   I RO/SRO A seal injection controller will fail in automatic requiring the crew to take manual control of the controller. 3 imf cmCPCH03HCNA02A_6   imf cmCPCH03HCNA02C_6 C CO/SRO The A and C CEDM fans will trip requiring the CRS to enter 40AO-9ZZ25, Loss of HVAC to start the B and D fans (which  
The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.
Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.
Event               Malf. No.             Event Type*                               Event Description No.
1     None                                     N         Shift Condensate Demineralizers.
CO/SRO 2     imf cmCNCV04CHNFIC243_2                   I       A seal injection controller will fail in automatic requiring the RO/SRO      crew to take manual control of the controller.
3     imf cmCPCH03HCNA02A_6                   C         The A and C CEDM fans will trip requiring the CRS to enter 40AO-9ZZ25, Loss of HVAC to start the B and D fans (which imf cmCPCH03HCNA02C_6                CO/SRO      will fail to auto start).
4    imf mfRD02B                              R        CEA 15 drops completely into the core. Crew enters 40AO-RO/CO/SRO      9ZZ11. Crew begins a 20% downpower. SRO enters LCO 3.1.5 (TS)      Condition A and LCO 3.2.4 Condition A.
5    imf mfTH06A                              C        A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO      40AO-9ZZ02, Excessive RCS leakrate.
(TS) 6    imf mfRD02L                          M - ALL      Another CEA slips into the core. This will cause a reactor trip mfRD12A                                            signal but an ATWS will occur. This will require the crew to mfRP04A                                            open the breakers supplying the CEDM MG sets.
mfRP04C                                            Critical Task - Crew will insert all CEAs.
7    mfRX01                                    I        After the trip Tave will fail low requiring the CO to manually feed the SGs.
CO /SRO 8    mmf mfTH06A                          M-ALL        The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End                                                        The scenario is terminated when the crew commences affected point                                                      steam generator has been isolated or at the discretion of the lead examiner
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9                      1 of 3


will fail to auto start).
Appendix     D                       Scenario Outline                           Form ES-D-1 Supplemental Turnover Plant conditions:
4 imf mfRD02B R RO/CO/SRO (TS) CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11. Crew begins a 20% downpower. SRO enters LCO 3.1.5
 
Condition A and LCO 3.2.4 Condition A.
5 imf mfTH06A C CO/SRO (TS) A Steam Generator Tube leak occurs requiring the crew to enter 40AO-9ZZ02, Excessive RCS leakrate.
6 imf mfRD02L mfRD12A mfRP04A mfRP04C M - ALL  Another CEA slips into the core. This will cause a reactor trip signal but an ATWS will occur. This will require the crew to open the breakers supplying the CEDM MG sets.
Critical Task - Crew will insert all CEAs.
7 mfRX01 I CO /SRO After the trip Tave will fail low requiring the CO to manually feed the SGs.
8  mmf mfTH06A M-ALL The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.
Critical Task - Initiate actions to cooldown and isolate the affected steam generator End point  The scenario is terminated when the crew commences affected steam generator has been isolated or at the discretion of the lead examiner *  (N)ormal,  (R)eactivity,  (I)nstrument,  (C)omponent,  (M)ajor
 
Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 2 of 3  Supplemental Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance. Risk Management Action Level is GREEN. Train B is protected equipment.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
Risk Management Action Level is GREEN.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
Train B is protected equipment.
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
PC is NOT recircing the RWT.
Note: The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.  
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
Note:
The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.
NUREG-1021, Revision 9                      2 of 3


Appendix   D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 3 of 3  Turnover Plant conditions:
Appendix     D                       Scenario Outline                           Form ES-D-1 Turnover Plant conditions:
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.
The Emergency Seal Oil Pump is tagged out for emergent maintenance. Risk Management Action Level is GREEN. Train B is protected equipment.
The Emergency Seal Oil Pump is tagged out for emergent maintenance.
PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
Risk Management Action Level is GREEN.
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Planned shift activities:
Train B is protected equipment.
Normal, shiftly surveillances are complete. The crew needs to place the 'F' Condensate Demin in Service and remove the 'E' Condensate Demin from service. The 'F' Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.}}
PC is NOT recircing the RWT.
Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:
The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.
Planned shift activities:
Normal, shiftly surveillances are complete.
The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.
NUREG-1021, Revision 9                      3 of 3}}

Latest revision as of 01:54, 12 March 2020

2009-22-Final Operating Test
ML100880356
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 11/02/2009
From: Garchow S
NRC Region 4
To:
Arizona Public Service Co
References
50-528/09-301, 50-529/09-301, 50-530/09-301 50-528/09-301, 50-529/09-301, 50-530/09-301
Download: ML100880356 (267)
v • d • e


Text

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250440201 Perform Event Control Actions for a Control Room Fire TASK STANDARD: Diesel Generator B is running.

K/A: 4.2.068.AA1.10 K/A RATING: RO: 3.7 SRO: 3.9 K/A: 4.2.068.AA1.31 K/A RATING: RO: 3.9 SRO: 4.0 APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes

REFERENCES:

40AO-9ZZ19, Control Room Fire, Appendix E Rev 22 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 08/31/2004 Revised By: Alan Malley Date: 04/14/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X TESTING METHOD: SIMULATE X PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

1 Revised 9/23/08

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

1. SIMULATOR SETUP:

A. IC#: N/A B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

1. N/A 2.

3.

4.

C. SPECIAL INSTRUCTIONS:

  • NONE D. REQUIRED CONDITIONS:
  • NONE E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

2. SPECIAL TOOLS/EQUIPMENT:
  • Pictures of the inside of a 4.16 kV breaker cubicle.

2

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The control room has been evacuated due to a fire.
  • The B DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire).
  • The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Generator (another operator performed steps 1-9 to position disconnect switches and start the DG).
  • The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES).
  • Assume you have a portable lantern per Step 1 of Appendix E.

This JPM is time critical.

3

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

4

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 10 of Appendix E: Provide the following cues as the Examinee identifies indication on examinee looks at the appropriate Diesel Generator control cabinet.

Check that Both of the following instrument: NOTE: Time critical portion starts conditions for closing the DG Output here.

Breaker are met:

  • DG B Voltage is 4220
  • Diesel Generator B voltage is VAC START Time: ___________

3740 - 4580

  • DG B speed is 600 rpm
  • Diesel Generator B speed is approximately 600 rpm.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 11 of Appendix E: Provide the following cue: Examinee simulates closing PBB-S04B by using the handswitch on the Close breaker PBB-S04B, Diesel The green light is ON and the front of the breaker.

Generator PEB-G02, using the local red light is OFF on PBB-S04B.

control switch.

The white light is OUT on PBB-S04B.

SAT / UNSAT Comments (required for UNSAT):

5

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3. Step 11.1 of Appendix E: Provide the following cue: Examinee goes to Step 12 of the appendix IF PBB-S04B did NOT close, The control room has directed you THEN perform the following: to close the breaker manually.
a. IF the breaker will be closed Give the examinee the enclosed manually, THEN GO TO pictures and inform the examinee Step 12. of this appendix. that he/she does not need to open the switchgear door. Use the pictures to explain your actions.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 12 of Appendix E: Provide the following cue: Examinee goes to Step 12.1 of the appendix.

IF breaker PBB-S04B, Diesel The closing spring indicates Generator PEB-G02, will be closed DISCHGD.

manually, THEN perform the following: Alternate Path starts here.

a. Check the closing spring After examinee goes to step 12.1 indicates CHGD.
b. Press the MANUAL If asked:

CLOSE plunger for the breaker. The CRS directs you to close the breaker manually.

SAT / UNSAT Comments (required for UNSAT):

6

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

5.
  • Step 12.1.a-d of Appendix E: Provide the following cue: Examinee explains using the provided pictures how he/she would IF PBB-S04B will be closed The closing spring indicates manually charge the springs.

manually, AND the closing spring DISCHGD.

indicator does NOT indicate CHGD, THEN perform the Provide the following cues as the following to manually close the trainee simulates the steps.

breaker:

a. Obtain ALL of the a. The equipment has been Examinee simulates obtaining following equipment from obtained from the cabinet equipment from the cabinet located FPN-C02, Emergency by the door to the DC equipment Equipment Cabinet. room.
  • Ratchet
  • Extension
  • 5/8 inch socket
b. The 125 Vdc breaker is in The examinee opens the 125 V dc
b. Open the 125 Vdc control the OFF position. breaker.

power breaker.

c. Place the ratchet on the
c. The ratchet is on the stud. The examinee places the ratchet on charging spring motor the stud.

eccentric, hex charging stud (Right had side between the The examinee ratchets the stud to charging springs). d. The closing spring indicator obtain a CHGD indication.

d. Ratchet the hexed charging indicates CHGD.

stud clockwise to obtain a CHGD indication.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.
  • Step 12.1.e of Appendix E: Provide the following cue: Examinee simulates closing PBB-S04B by pressing the Manual Press the Manual CLOSE plunger The breaker position indicator Close Plunger.

for the breaker. reads CLOSED.

SAT / UNSAT Comments (required for UNSAT):

7

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

7.
  • Step 13.e of Appendix E: Provide the following cue: Examinee simulates closing PBB-S04C by using the handswitch on the Close breaker PBB-S04C, Essential The green light is OFF and the front of the breaker.

Spray Pond Pump SPB-P01. red light is ON.

NOTE: Time critical portion stops here.

STOP Time ___________

(Time should be less than 15 minutes Another operator will complete from Start time).

this Appendix.

This JPM is complete.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 8

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 1 08/31/04 3 Procedure removed direction to open PHB-M3209 and PHB-M3210.

2 09/08/2006 6 Changed cues for step 11 3 04/14/2009 6 Changed alternate path to DG breaker not closing.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade
2. Plant modification (include number)
3. Procedure upgrade
4. Internal or External Agency Commitment (indicate item number)
5. Technical Specification Change (indicate amendment number)
6. Other (explain in comments) 9

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • The control room has been evacuated due to a fire.
  • The B DG has been started per Appendix E of 40AO-9ZZ19 (Control Room Fire).
  • The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 10 to load the "B" Diesel Generator (another operator performed steps 1-9 to position disconnect switches and start the DG).
  • The CRS has waived the Electrical Protection Equipment requirements for this task per step 3.20.1 of 01DP-0IS13 (ELECTRICAL SAFE WORK PRACTICES).
  • Assume you have a portable lantern per Step 1 of Appendix E.

This JPM is time critical.

CANDIDATE 10

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240070004 Perform Auxiliary Operator Actions Per 40EP-9EO07, Loss Of Offsite Power TASK STANDARD: Align Train B EW to Spent Fuel Pool Cooling K/A: 4.2-062-AA1.03 K/A RATING: RO: 3.6 SRO: 3.6 K/A: 3.8-033-A2.02 K/A RATING: RO: 2.7 SRO: 3.0 APPLICABLE POSITION(S): AO/RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

40EP-9EO10 Standard Appendices, Appendix 64, Attachment 64-B, Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Mike Selland Date: 03/09/2006 Revised By: Alan Malley Date: 03/12/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X TESTING METHOD: SIMULATE X PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

11 Revised 9/23/08

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

2. SIMULATOR SETUP:

F. IC#: N/A G. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

5. N/A 6.

7.

8.

H. SPECIAL INSTRUCTIONS:

  • NONE I. REQUIRED CONDITIONS:
  • NONE J. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

3. SPECIAL TOOLS/EQUIPMENT:
  • Copy of 40EP-9EO10, Standard Appendices, Attachment 64-B, Rev 60 TASK CONDITIONS 12

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The plant has experienced a loss of offsite power and recovery is not expected soon.
  • The control room is currently performing steps from the Loss of Offsite Power EOP.
  • The CRS has directed you to perform the Area 3 actions from Attachment 64-B to align Train B EW to Spent Fuel Pool Cooling.
  • Another operator has been stationed at Essential Chiller B to perform required actions.
  • Permission has been granted to break 40AC-9ZZ06 locks as required.

13

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

14

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Attachment 64-B: Spray Pond Pump B is running. Examinee simulates calling control room for verification that Ensure Spray Pond Pump B is SP Pump B is running.

operating SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Attachment 64-B: EW Pump B is running. Examinee simulates calling control room for verification that Ensure Essential Cooling Water EW Pump B is running.

Pump B is operating.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Step 3 of Attachment 64-B: NCB-HCV-245 stem lock is Examinee simulates loosening valve loosened and ZZ06 lock is broken. stem lock.

Perform the following:

(EW Heat Exchanger B Room) NCB-HCV-245 has been rotated in Examinee simulates closing NCN-the clockwise direction and has HCV-245.

Close NCB-HCV-245, NC stopped moving.

ISOLATION TO SFP HEAT EXCHANGER. The position indication pointer is Note: Valve is located in EW heat indicating closed.

exchanger B room.

SAT / UNSAT Comments (required for UNSAT):

15

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4.
  • Continuation of step 3 of Attachment NCB-HCV-259 stem lock is Examinee simulates loosening valve 64-B: loosened and ZZ06 lock is broken. stem lock.

Close NCB-HCV-259, NC NCB-HCV-259 has been rotated in Examinee simulates closing NCN-ISOLATION FROM SFP HEAT the clockwise direction and has HCV-259.

EXCHANGER. stopped moving.

The position indication pointer is Note: Valve is located in EW heat indicating closed.

exchanger B room.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.
  • Continuation of step 3 of Attachment UNIT 3 ONLY: UNIT 3 ONLY:

64-B: EWB-HCV-68 stem lock is Examinee simulates loosening valve loosened and ZZ06 lock is broken. stem lock.

Open EWB-HCV-68, EW ISOLATION FROM SFP HEAT EWB-HCV-68 has been rotated in Examinee simulates unlocking and EXCHANGER. the counter-clockwise direction opening EWB-HCV-68 and has stopped moving.

The position indication pointer is indicating open. Note: Valve is located in EW heat exchanger B room.

SAT / UNSAT Comments (required for UNSAT):

16

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6.
  • Continuation of step 3 of Attachment EWB-HCV-134 stem lock is Examinee simulates loosening valve 64-B: loosened and ZZ06 lock is broken. stem lock.

Unlock and open EWB-HCV-134, EWB-HCV-134 has been rotated Examinee simulates unlocking and EW ISOLATION TO SFP HEAT in the counter-clockwise direction opening EWB-HCV-134 EXCHANGER. and has stopped moving.

Note: Valve is located in EW heat The position indication pointer is exchanger B room.

indicating open.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7. Step 4 of Attachment 64-B: Another operator has overridden Examinee simulates calling another and opened EWB-PCV-174 operator or the control room to open Direct an operator to perform the EWB-PCV-174.

following to override and open EWB-PCV-174 REFRIGERANT HEAD PRESSURE CONTROL VALVE.

Turn the Pilot Bypass Stem in he fully counter clockwise position.

SAT / UNSAT Comments (required for UNSAT):

17

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

8.
  • Step 5 of Attachment 64-B: Examinee simulates placing flow meter in service. Steps must be Place NCN-FI-257, FPHX B performed in the exact order listed to OUTLET FLOWMETER, in service be satisfactory.

by performing the following:

  • Ensure the local equalizing valve The local equalizing valve will Note: Flowmeter is located in Fuel is open. rotate freely in the closed Bldg 100 ft. on West side of direction, but only slightly open. stanchion South of PCHX A.
  • Open NCB-V113, NCN-FI-257 NCB-V113 has been rotated Root Isolation. counter-clockwise and has stopped moving.
  • Open NCB-V114, NCN-FI-257 NCB-V114 has been rotated Root Isolation. counter-clockwise and has stopped moving.
  • Open the local low side isolation The local low side isolation has valve. been rotated in the counter-clockwise direction and has stopped moving.
  • Close the equalizing valve. The equalizing valve has been rotated clockwise and has stopped moving.
  • Slowly open the local high side The local high side isolation has isolation valve been rotated in the counter-clockwise direction and has stopped moving.

If requested cue: Flow is currently at 1300 gpm on NCN-FI-257.

SAT / UNSAT Comments (required for UNSAT):

18

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

9.
  • Step 6 of Attachment 64-B: Flow is currently at 1300 gpm. Examinee simulates opening NCB-HCV-265. Examinee checks flow on Unlock and adjust NCB-HCV-265, After examinee simulates opening-NCN-FI-257.

FPHX B OUTLET ISOLATION, to NCB-HV-265, flow is at 1700 gpm.

obtain 1400-2400 gpm.

After examinee adjusts flow Note: Valve is in Fuel Bldg 100 ft at provide the following Cue: PC Heat Exchanger B outlet.

Another operator will complete the rest of Attachment 64-B.

This JPM is complete.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 19

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 001 02/10/06 3 Updated JPM to 40EP-9EO10 Rev 45. Updated cues.

002 02/24/06 6 Change cue for step 10 to coincide with plant indications.

Updated Validation time from 20 to 30 minutes.

003 03/09/06 6 Change cue in step 8. Included appropriate cues for NC/EW valves that have stem locks. Updated Validation time from 30 to 40 minutes. Editorial changes.

004 03/16/06 6 Updated step 5 cue to highlight that both U1 & U3 have stem locks on EWB-HCV-68. Added valve position indicator cue to step 6.

005 03/23/06 6 Updated step 5 cue to indicate that only U3 has the stem lock on EWB-HCV-68. Deleted step 12 and changed step 11cue to end the JPM with another operator performing the remaining steps.

006 03/12/2009 Updated to new format REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

7. Vendor reference document upgrade
8. Plant modification (include number)
9. Procedure upgrade
10. Internal or External Agency Commitment (indicate item number)
11. Technical Specification Change (indicate amendment number)
12. Other (explain in comments) 20

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • The plant has experienced a loss of offsite power and recovery is not expected soon.
  • The control room is currently performing steps from the Loss of Offsite Power EOP.
  • The CRS has directed you to perform the Area 3 actions from Attachment 64-B to align Train B EW to Spent Fuel Pool Cooling.
  • Another operator has been stationed at Essential Chiller B to perform required actions.
  • Permission has been granted to break 40AC-9ZZ06 locks as required.

CANDIDATE 21

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240023901 Perform operation of AFA-P01 at the Remote Shutdown Panel TASK STANDARD: Feeding the Steam Generators with AFA-P01 from the Remote Shutdown Panel K/A: 3.4-061-A3.01 K/A RATING: RO: 4.2 SRO: 4.2 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ18, Shutdown Outside the Control Room, Appendix E Auxiliary Feed Pumps Operation, Rev 7 SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 02/27/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT X TESTING METHOD: SIMULATE X PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

22 Revised 9/23/08

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

3. SIMULATOR SETUP:

K. IC#: N/A L. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

9. N/A 10.

11.

12.

M. SPECIAL INSTRUCTIONS:

  • NONE N. REQUIRED CONDITIONS:
  • NONE O. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

4. SPECIAL TOOLS/EQUIPMENT:
  • Copy of 40AO-9ZZ18, Shutdown Outside Control Room (Appendix E - Auxiliary Feed Pumps Operations), Rev 7 23

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • You are a reactor operator on crew.
  • The crew has implemented 40AO-9ZZ18, Shutdown Outside the Control Room to shutdown the unit.

24

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

25

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 2. After the examinee simulates NOTE: Examinee simulates turning turning the speed potentiometer the speed potentiometer in the IF AFA-P01 will be used THEN counter-clockwise provide the counter-clockwise direction until the perform the following:

following cue: dial is at minimum.

Adjust AFA-SK-52B, Auxiliary The potentiometer has stopped Feedwater Pump A Speed to moving and reads 0.

minimum SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • Continuation of Step 2: After the examinee simulates NOTE: Examinee simulates turning turning the speed control the speed control transfer switch left Place AFA-SK-52A, Speed Control handswitch to the REMOTE to the REMOTE SHUTDOWN Transfer, to the REMOTE SHUTDOWN position provide position.

SHUTDOWN position. the following cue:

The handswitch is pointing to the left.

SAT / UNSAT Comments (required for UNSAT):

26

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3.
  • Continuation of Step 2: After the examinee simulates Examinee simulates opening either turning handswitch for either SGA-UV-134 or SGA-UV-138.

Open one of the following Steam SGA-UV-134 or SGA-UV-138 Supply Valves provide the following cue for the appropriate valves:

  • SGA-UV-134
  • SGA-UV-138 The indication for SGA-UV-134(8)A red light is on. 30 seconds later the red light for SGA-UV-134 came on and both Green lights are off.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.
  • Continuation of Step 2: As the examinee goes to increase The examinee looks at the speed on the speed potentiometer indicator for AFA-P01 (AFA-SI-Adjust turbine speed using AFA-SK- provide the following cue: 52B) on the Remote Shutdown Panel 52B to ONE of the following: Unit 1 and 3 Cue: and adjusts the potentiometer to raise speed to 3590-3600 rpm in Unit 1 Unit 1 & 3 only -
  • Speed is now 3600 rpm and 3 or 3560-3570 in Unit 2..
  • 3590-3600 rpm Unit 2 only Unit 2 Cue:
  • 3560-3570 rpm
  • Speed is now 3560 rpm SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.
  • Continuation of Step 2: When the examinee takes the Examinee simulates placing the handswitches for AFA-UV-37 and handswitches for AFA-UV-37 and Open BOTH of the following AFW 36 to open provide the following AFA-UV-36 Pump A to Steam Generator cue:

Downstream Valves:

  • AFA-UV-37 The red lights for AFA-UV-37 and
  • AFA-UV-36 36 are on and the green lights are off.

SAT / UNSAT Comments (required for UNSAT):

27

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6.
  • Continuation of Step 2: When examinee looks at SG level Examine determines SG WR level transmitters provide the following and throttles open both SG Upstream Maintain steam generator levels 35-cue: valves.

80% WR with ANY of the following AFA Pump A to Steam Generator Steam Generator Wide Range Upstream Valves:: Levels are 30% WR.

  • AFA-UV-32 If asked the as found position of
  • AFA-UV-33 AFA-UV-23 and 33 are as indicated on the panel.

When the examine simulates jogging open AFA-UV-32 and 33 provide the following cue:

AFA-UV-32 red and green lights are on.

When examine looks at position indication for valves provide the following cue:

Valve position indicators read approximately _20_ % (depending on what operator says).

When examine looks at AF flow indicator provide the following cue:

The gauge indication is reading 350 gpm.

After feed is established provide the following cue:

Another operator will finish Appendix E.

This JPM is complete.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 28

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 2/27/09 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

13. Vendor reference document upgrade
14. Plant modification (include number)
15. Procedure upgrade
16. Internal or External Agency Commitment (indicate item number)
17. Technical Specification Change (indicate amendment number)
18. Other (explain in comments) 29

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • You are a reactor operator on crew.
  • The crew has implemented 40AO-9ZZ18, Shutdown Outside the Control Room to shutdown the unit.

CANDIDATE 30

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 0010030401 Perform a SG 1 (2) high rate blowdown to the main condenser.

TASK STANDARD: Use the high rate blowdown system to lower SG level K/A: 4.1 038 EA1.18 K/A RATING: RO: 4.0 SRO: 3.9 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

40EP-9EO10 Standard Appendices, Appendix 33 - Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 04/14/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

31 Revised 9/23/08

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

4. SIMULATOR SETUP:

P. If running JS1 and JS2 together reset to IC#: 106 (For 2009 NRC exam only)

If running JS1and JS3 together reset to IC# 110 (For 2009 NRC exam only)

Q. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

13. WHEN direct to open SGE-V293, SGE- When examinee directs AO to open bypass valves for V267, and SGE-VA33 perform the 500S. (Valves are SGE-V293, SGE-V267, and SGE-following: VA33).
  • Go to page WD6 and click on the The handswitch is taken to close to ensure the valve handswitch for 500Q. Use the does not open when the malfunction is deleted. This override to take the valve to close. ensures the examinee has to open the valve.

THEN

  • Delete the override for the handswitch above, THEN
  • dmf cmAVWD06SGBUV500Q_4 (listed under Comp Malfs on the header at the top of the simulator page)

THEN report the valves are open.

14. WHEN directed to close SGE-V293, SGE-V267, and SGE-VA33, wait a minute and report the valves closed.
15. WHEN directed to open SCN-V088, V099, V071, and V072, wait a few minutes and report the valves are open. These are opened in the simulator setup.

R. SPECIAL INSTRUCTIONS:

  • Reset to IC- 106
  • This JPM is set up to run with JS-2 and JS-3 for the 2009 NRC exam S. REQUIRED CONDITIONS:
  • SG NR level approximately 65-75% NR.

T. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

32

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

5. SPECIAL TOOLS/EQUIPMENT:
  • Copy of Standard Appendix 33 This scenario is set up in IC-106. If for some reason IC-106 is not available, reset to IC 6, use AF to fill SG#1 to approximately 70% NR and close all the Blowdown containment isolation valves. Then perform the following to open SCNV088 and SCNV071:
  • mrf rfWD29 OPEN
  • mrf rfWD30 OPEN
  • imf cmAVWD06SGBUV500Q_4 (mechanical Seizure of 500Q)

TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • Unit 1 is cooling down following a SGTR
  • SG #1 NR level is approximately 74%.
  • The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.

33

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

34

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1of Standard Appendix 33: Examinee places SCN-HS-1 in OFF.

Place SCN-HS-1, SG 1 Blowdown Path Selector in OFF.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • Step 2 of Standard Appendix 33: Examinee opens SGA-UV-500P.

Ensure SGA-UV-500P, SG 1 Common Upstream Isolation, is open.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Step 3 of Standard Appendix 33: If asked as CRS which valve to use Examinee opens either SGE-HV-43 provide the following cue: or SGE-HV-41.

Ensure that ONE of the following valves is open: Select either valve.

  • SGE-HV-43, SG 1 Hot Leg Isolation
  • SGE-HV-41, SG 2 Cold Leg Isolation SAT / UNSAT Comments (required for UNSAT):

35

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4. Step 4 of Standard Appendix 33: The examinee determines SGB-UV-500Q is closed and goes to the Check that SGB-UV-500Q is open.

contingency step 4.1.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.
  • Step 4.1 of Standard Appendix 33: Simulator Driver action required Examinee directs an operator to open at this time!!! SGE-V293, SGE-V267, and SGE-Perform the following to open SGB- VA33.

UV-500Q: Have the trainee use the radio to communicate with the Sim Driver. When the operator reports these

a. Direct an operator to perform the The driver will provide the cues for valves are open, the examinee opens following:

the valve positions. SGB-UV-500Q.

1) Unlock and open SGE-V293, SGB-UV-500Q BYPASS HDR INLET ISOL VALVE
2) Open SGE-V267, SGB-UV- After SGB-UV-500Q is open, the 500Q BYPASS HDR examinee directs the operator to OUTLET ISOL VALVE close SGE-V293, SGE-V267, and
3) Slowly open SGE-VA33, SGE-VA33.

SGB-UV-500Q BYPASS HEADER THROTTLE VALVE

b. Open SGB-UV-500Q, SG 1 Common Downstream Isolation
c. Direct an operator to close ALL of the following valves:
  • SGE-V293
  • SGE-V267
  • SGE-VA33 SAT / UNSAT Comments (required for UNSAT):

36

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6. Step 5 of Standard Appendix 33: (All valves have been positioned in Examinee directs an operator to open the simulator setup). the following valves:

Direct an operator to open ALL of

  • SCN-V088 the following valves:
  • SCN-V099
  • SCN-V088, SCN-HV-018C The sim driver will inform the
  • SCN-V071 OUTLET ISOLATION candidate that these valves are open.
  • SCN-V072 VALVE (S/G 1 HIGH RATE B/D TO CONDENSER)
  • SCN-V099, SCN-HV-018C INLET ISOLATION VALVE (S/G 1 HIGH RATE B/D TO CONDENSER)
  • SCN-V071, SCN-HV-018B OUTLET ISOLATION VALVE (S/G 1 ABNORMAL RATE B/D TO CONDENSER)
  • SCN-V072, SCN-HV-018B INLET ISOLATION VALVE (S/G 1 ABNORMAL RATE B/D TO CONDENSER)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7.
  • Step 6 of Standard Appendix 33: Examinee places SCN-HS-18 in HIGH RATE.

Place SCN-HS-18, SG 1 Blowdown Rate Selector in HIGH RATE.

SAT / UNSAT Comments (required for UNSAT):

37

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

8.
  • Step 7 of Standard Appendix 33: When examiner has seen level Examinee places SCN-HS-1 in decrease, provide the following COND and monitors SG level.

Maintain SG level by performing the cue:

following:

a. Place SCN-HS-1, SG 1 Blowdown Path Selector in Another operator will monitor SG COND.

level and secure blowdown at 50%.

b. WHEN SG 1 level reaches the desired level, THEN place SCH-HS-1, SG1 Blowdown Path Selector in OFF. This JPM is complete.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 38

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 04/14/2009 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

19. Vendor reference document upgrade
20. Plant modification (include number)
21. Procedure upgrade
22. Internal or External Agency Commitment (indicate item number)
23. Technical Specification Change (indicate amendment number)
24. Other (explain in comments) 39

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:

  • Unit 1 is cooling down following a SGTR
  • SG #1 NR level is approximately 74%.
  • The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.

CANDIDATE 40

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240001601 Perform LM-HPSI pump cold leg injection TASK STANDARD: Borate the RCS using Charging Pump through Hot leg Injection K/A: 4.2-024-AA1.09 K/A RATING: RO: 3.5 SRO: 3.5 K/A: 4.2-024-AA1.22 K/A RATING: RO: 3.2 SRO 3.2 APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

40EP-9EO10 - Standard Appendices, Appendix 209, LM-Charging Pump Hot Leg Injection Tran B HPSI, Rev 60 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 3/10/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

41 Revised 9/23/08

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

5. SIMULATOR SETUP:

U. IC#: 106 (For 2009 NRC exam only)

V. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

16. None required W. SPECIAL INSTRUCTIONS:
  • This is scheduled to run with JPM JS1 for the 2009 NRC exam.

X. REQUIRED CONDITIONS:

  • Ensure Charging Pump B is NOT running Y. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

6. SPECIAL TOOLS/EQUIPMENT:
  • Copy of 40EP-9EO10, Standard Appendices 209, LM-Charging Pump Hot Leg Injection Tran B HPSI.

If IC-106 is not available, reset to IC-6 and perform the following:

  • Depressurize RCS to ~ 250 psia
  • Shift to RCPs 1A and 1B running
  • Close SIB-UV-656 using the handswitch
  • Open SIB-UV-307 using the handswitch
  • Mrf crRH05SIBHV692_1 CLOSE (Closes the breaker for SIB-UV-692)
  • Open SIB-UV-692 using the handswitch
  • Open SIB-UV-322 using the handswitch
  • Mrf rfSI06 OPEN (opens SIV508)
  • Mrf rfCV26 OPEN (opens CH-756)
  • Mrf rvCV30 OPEN (opens CH-797) 42

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The plant is shutdown in Mode 5.
  • The CRS has entered the Lower Mode Functional Recovery Procedure.
  • Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the B Charging pump.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

43

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • Locked valves may be involved. No attempt will be made to actually operate any valves.

44

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix 209: NOTE: Examinee verifies Train B SDC is NOT in service and verifies Check BOTH of the following: SIB-UV-656 is closed.
  • SDC Train B is NOT is service
  • SIB-UV-656, Loop 2 to SDC LPSI pump B Suction Valve is closed SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Appendix 209: If needed cue: The CRS directed Examinee determines that Charging you to use Charging Pump B. Pump A will not be used (in IF it desired to align Charging Pump Initiating cue to use Charging Pump A, THEN perform the following:

B).

a. Place Charging Pump A in the PULL-TO-LOCK position.
b. Direct an operator to PERFORM Attachment 209-A, Charging Pump A Hot Leg Injection Train B HPSI.

SAT / UNSAT Comments (required for UNSAT):

45

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3. Step 3 of Appendix 209: After examinee directs an operator Examinee ensures Charging Pump B to Perform Attachment 209-B: in PULL-TO-LOCK.

IF it desired to align Charging Pump B, THEN perform the following: The area operator has completed Examinee directs an Area Operator

c. Place Charging Pump B in Attachment 209-B. to perform Attachment 209-B.

the PULL-TO-LOCK position.

  • Direct an operator to PERFORM Attachment 209-B, Charging Pump B Hot Leg Injection Train B HPSI.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 4 of Appendix 209: If needed cue: The CRS directed Examinee determines that Charging you to use Charging Pump B. Pump E will not be used (in IF it desired to align Charging Pump Initiating cue to use Charging Pump E, THEN perform the following:

B).

d. Place Charging Pump E in the PULL-TO-LOCK position.
  • Direct an operator to PERFORM Attachment 209-C, Charging Pump E Hot Leg Injection Train B HPSI SAT / UNSAT Comments (required for UNSAT):

46

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

5.
  • Step 5 of Appendix 209: The examinee closes SIB-HV-609, HPSI B Long Term Recirc, and WHEN ANY of the following are closes SIB-UV-332, SIT Fill Header complete:

Isolation.

  • Attachment 209-A
  • Attachment 209-B
  • Attachment 209-C THEN ensure BOTH of the following valves are closed:
  • SIB-HV-609, HPSI B Long Term Recirc
  • SIB-UV-332 SIT Fill Header Isolation SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6. Step 6 of Appendix 209: After the examinee informs the The examinee informs the CRS that Inform the CRS that the Charging CRS that Charging Pump B is Charging Pump B is aligned for Hot Pump(s) are aligned for Hot Leg aligned for Hot Leg Injection to Leg Injection to HPSI Header B.

Injection to HPSI Header B. HPSI Header B provide the following cue:

The CRS directs you to commence Hot Leg Injection.

SAT / UNSAT Comments (required for UNSAT):

47

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

7.
  • Step 7 of Appendix 209: The plaque on the board that The examinee opens SID-HV-331, WHEN directed by the CRS to references 40DP-9OP07 is informing HPSI B Long Term Recirc Throttle commence Hot Leg Injection, THEN the operator that a valve stroke Valve.

perform the following: surveillance must be done before Mode 4 once these valves have been

a. Open SID-HV-331, HPSI B moved.

Long Term Recirc Throttle Valve.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.
  • Step 7 of Appendix 209: After the examinee starts borating The examinee starts Charging Pump WHEN directed by the CRS to provide the following cue: B.

commence Hot Leg Injection, THEN perform the following: Another operator will continue with this Appendix.

b. Start the Charging Pump(s) aligned for Hot Leg This JPM is complete.

Injection.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 48

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 03/10/2009 6 JPM created.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

25. Vendor reference document upgrade
26. Plant modification (include number)
27. Procedure upgrade
28. Internal or External Agency Commitment (indicate item number)
29. Technical Specification Change (indicate amendment number)
30. Other (explain in comments) 49

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:

  • The plant is shutdown in Mode 5.
  • The CRS has entered the Lower Mode Functional Recovery Procedure.
  • Due to not having adequate Shutdown Margin, the CRS has directed you to perform Standard Appendix 209 to borate the RCS using the B Charging pump.

CANDIDATE 50

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250280201 Respond to an Inadvertent RAS TASK STANDARD: RAS reset K/A: 3.7 012 A4.02 K/A RATING: RO: 3.3 SRO: 3.4 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations, Rev 13 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 08/30/2005 Revised By: Alan Malley Date: 10/05/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

51 Revised 9/23/08

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

6. SIMULATOR SETUP:

Z. If running JS3 and JS4 together reset to IC#: 103 (For 2009 NRC exam only)

If running JS3 and JS1 together reset to IC# 110 (For 2009 NRC exam only)

AA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

17. None Required BB. SPECIAL INSTRUCTIONS:
  • This JPM is designed to run with JS-4 or JS-1 for the 2009 NRC exam.

CC. REQUIRED CONDITIONS:

  • Ensure Charging Pump B is NOT running DD. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

7. SPECIAL TOOLS/EQUIPMENT:
  • Copy 40AO-9ZZ17, Inadvertent PPS Actuations, Appendix B If IC-103 is not available, then reset to IC-20. Then perform the following:
  • imf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B)
  • imf cmSRRP01IRRASBD2_1 (fails the RAS relay)
  • imf RP06J1 (RAS Leg 1 blown fuse)

THEN

  • dmf cmTRCV07CHBLT203B_4 (failure of CHB-PT-203B)
  • dmf cmSRRP01IRRASBD2_1 (fails the RAS relay)
  • dmf RP06J1 (RAS Leg 1 blown fuse)
  • Override and close the Train B RAS Sump valves on B02.

The following lights should be lit:

  • The Channel B Lo RWT Level Trip and Pre-trip lights on B05 and at the PPS B cabinet
  • Flashing light for the Reset Actuation Trip Path 2 above the handswitch for the actuation path reset button on Channel B PPS Cabinet The following light should be out:
  • RAS Initiation light on B05 and Channel B PPS cabinet
  • Channel A RAS 2-4 leg actuation light at A PPS cabinet
  • Channel B RAS 1-3 and 2-4 actuation light at B PPS Cabinet 52

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

(For 100% power Initial Conditions)

  • Unit 1 is at 100% power.
  • An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
  • The power supply problem has been corrected.
  • The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.

(For low power Initial Conditions)

  • An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
  • All SDC valves have been realigned as needed for SDC.
  • The power supply problem has been corrected.
  • The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.

53

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

54

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix B of 40AO- Examinee marks step as N/A.

9ZZ17:

IF PPS-ESFAS actuation was caused by a failure to reset the SG or PZR Examinee may perform lamp checks Press variable setpoints during a to ensure no other parameters are controlled cooldown tripped.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 and 2.1 of Appendix B of The examinee determines channel B 40AO-9ZZ17: LO RWT LEVEL is LIT and resets the Channel B Trip Lamp by pushing Check the Trip lamps (B05) for the the reset pushbutton.

affected PPS-ESFAS actuation input parameters on all PPS channels satisfy ONE of the following:

  • NOT lit
  • Bypassed SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3. Step 3 of Appendix B of 40AO- RAS Initiation lamps (B05) are NOT 9ZZ17: lit, so examinee goes to contingency step 3.2.

Check the affected PPS-ESFAS actuation Initiation Relay lamps lit Step 3.1 should be marked N/A.

(B05) on all PPS channels.

SAT / UNSAT Comments (required for UNSAT):

55

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4.
  • Step 3.2 of Appendix B of 40AO- Examinee obtains RPS/ESFAS reset 9ZZ17: key and resets RAS initiation pathways on Channel B. (Places Perform the following for any de- keylock switch to UNLK position energized PPS-ESFAS Initiation and then pushes RAS reset Paths: pushbutton).
  • Reset the affected initiation path (PPS Cabinet)
  • Check the affected Initiation Signal lamps lit (PPS Status Panels above the PPS Cabinets).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. Step 4 of Appendix B of 40AO- The examinee determines RAS leg 1-9ZZ17: 3 and 2-4 are NOT lit.

Check the actuated PPS-ESFAS leg 1-3 and leg 2-4 lamps lit for PPS actuation signals A and B (PPS Status Panels above the PPS Cabinets).

SAT / UNSAT Comments (required for UNSAT):

56

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6.
  • Step 4.1 of Appendix B of 40AO- When this step is completed The examinee resets the RAS 9ZZ17: provide the following cue: actuation path in the A and B Aux Relay cabinets. Only Channel Perform the following: B needs to be reset.
  • Reset the actuation path for the RAS actuation (Aux Relay The CRS will have another EVALUATOR NOTE: Only one cabinet) operator complete the remainder pushbutton needs to be depressed in
  • Check the red ON light lit for of this procedure. each ESFAS Train Cabinet to the affected PPS-ESFAS completely reset the RAS initiation actuation (Aux Relay Cabinet). logic.

This JPM is complete. EVALUATOR NOTE: Only resetting the actuation path is critical for this step.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 57

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 1 08/07/2009 6 Updated format 2 10/05/2009 6 Incorporated comments from the NRC validation.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

31. Vendor reference document upgrade
32. Plant modification (include number)
33. Procedure upgrade
34. Internal or External Agency Commitment (indicate item number)
35. Technical Specification Change (indicate amendment number)
36. Other (explain in comments) 58

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

(For 100% power Initial Conditions)

  • Unit 1 is at 100% power.
  • An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
  • The power supply problem has been corrected.
  • The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.

CANDIDATE 59

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

(For low power Initial Conditions)

  • An inadvertent Recirc Actuation Signal (RAS) has occurred due to a power supply problem.
  • All SDC valves have been realigned as needed for SDC.
  • The power supply problem has been corrected.
  • The CRS directs you to take actions to reset the RAS Signal in accordance with 40AO-9ZZ17, Appendix B.

CANDIDATE 60

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 0500010401 Initiate a containment vent TASK STANDARD: Containment purge system in operation in the VENT mode.

K/A: 3.8 029 A2.03 K/A RATING: RO: 2.7 SRO: 3.1 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9CP01, Containment Purge System (Rev 18)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: John Dedon Date: 04/04/2004 Revised By: Alan Malley Date: 10/05/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

61 Revised 9/23/08

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

7. SIMULATOR SETUP:

EE. IC#: 103 (For 2009 NRC exam only)

FF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

18. If IC-103 is not available, the reset to IC-20 and perform the following:
  • Mrf rfCH04 OPEN (opens IA-BV45)
  • Mrf rfIP38 1.3 (puts containment pressure at 1.3 psig)

GG. SPECIAL INSTRUCTIONS:

  • This JPM is set to run with JS3 for the 2009 NRC exam HH. REQUIRED CONDITIONS:
  • Containment pressure ~ 1.3 psig.

II. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

8. SPECIAL TOOLS/EQUIPMENT:
  • Copy of 40OP-9CP01, Containment Purge System, Section 5.0, Rev 18 JJ. COMMUNICATIONS DURING JPM:

STEP COMMAND CUE 1 After examinee directs AO to close IA- IA-VB47, Instrument Air Supply valve to the VB47 provide the following Cue: Containment Power Access Purge Isolation Valve CP-UV4A, is closed. (In simulator setup) 2 After examinee directs AO to open IA- IA-VB45, Air Supply to CPB-UV-5B and CP-PV-VB45 provide the following Cue: 43, is open. (In simulator setup) 3 After examinee directs AO to

  • CP-V024, Isolation between Refueling open/check open CP-V024 and to Purge Duct and RU-34, is open close/check closed CP-V023.
  • CP-V023, isolation between Refueling Purge Duct and RU-34, is closed 4 If examinee asks Effluent Tech if ST for Shiftly Surveillance Test for RU-37 and RU-38 is RU-37 and RU-38 is current current.

10 If the examinee sends an Area Operator

  • M03 damper is closed to check the positions of M03 and/or
  • M06 damper is open M06 report the following as appropriate:

62

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System.
  • An area operator is standing by in the RCA to assist you.
  • RU-34 is available.
  • Authorization has been given to break ZZ06 locks as needed.
  • Venting of Containment is for pressure reduction
  • All prerequisites are complete.
  • The Effluent Release Permit is for todays date from 0700 to 2400 and is approved.
  • The shiftly Surveillance Test for RU-37 and RU-38 is current.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.

63

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

64

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 5.3.1 of 40OP-9CP01: Simulator driver will report IA-VB47 Examinee directs AO to verify IA-is closed VB47 is closed.

Ensure IA-VB47, Instrument Air Supply valve to the Containment Power Access Purge Isolation Valve CP-UV4A is closed.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 5.3.2 of 40OP-9CP01: Simulator driver will report IA- Examinee directs AO to unlock and VB45 is open. open IA-VB45.

Unlock and open IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43 per 40AC-0ZZ06.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3. Step 5.3.3 of 40OP-9CP01: Simulator driver will report CP-V024 Examinee directs AO to open/check is open and CP-V023 is closed.. open CP-V024 and to close/check IF RU-34 is available, THEN closed CP-V023.

perform BOTH of the following to place it in service:

2. Ensure CP-V024 (isolation between Power Access Purge Duct and RU-34) is open.
3. Ensure CP-V023 (isolation between Refueling Purge Duct and RU-34) is closed.

SAT / UNSAT Comments (required for UNSAT):

65

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4. Step 5.3.4 of 40OP-9CP01: If asked, the simulator driver will Examinee signs off this step from provide the cue that the ST for RU- information provided in the Initiating Direct the RMS/Effluents technician 37 and 38 is current. This info was CUE.

to ensure the Shiftly ST (per 74ST- in the initiating cue.

9SQ07) as required by SR 3.3.8.1 is current on RU37 and/or RU-38 prior to each system startup.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. Step 5.3.5 of 40OP-9CP01: The examinee N/As this step since the vent is for none of the reasons IF venting Containment to perform listed.

ANY of the following:

  • Section XI testing of CP valves
  • Starting Power Access Purge
  • Starting Refueling Purge
  • PAL testing per 73ST-9CL05, Containment Airlock Leakage Rate Test.

THEN notify security that Containment will be vented to less than +0.25 psig.

SAT / UNSAT Comments (required for UNSAT):

66

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6. NOTE before step 5.3.6 Provide this cue on the floor. The examinee may decide to set an An ERFDADS alarm may be ERFDADS alarm. If so, give the inserted to alarm at +0.3 psig to alert If examinee decides to set an cue. The examinee may decide to set the operator not to go below +0.25 ERFDADS alarm provide the an ERFDADS alarm. If so, give the psig. following Cue: Cue.

Another operator will set the ERFDADS alarm. The CRS directs you to continue with the procedure.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7. Step 5.3.6 of 40OP-9CP01: The examinee initials this step and continues.

IF venting Containment is only for pressure reduction, THEN do not vent less than +0.25 psig.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8. Step 5.3.7 of 40OP-9CP01: Examinee N/As this step.

IF venting Containment in support of PAL testing per 73ST-9CL05, Containment Airlock Leakage Rate Test, THEN vent Containment as close to 0.1 psig, as practical.

SAT / UNSAT Comments (required for UNSAT):

67

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

9.
  • Step 5.3.8 of 40OP-9CP01: The examinee places CPN-HS-1 to VENT.

Place CPN-HS-1, Containment Purge Mode Selector Switch, in the VENT position to start venting containment.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

10. Step 5.3.9 of 40OP-9CP01: If requested, the simulator driver will The examinee ensures CPN-M06 provide the following cue: opens.

Ensure Damper CPN-M06 opens.

  • M03 damper is closed This will cause dual indication for
  • M06 damper is open the position of M03/M06. The examinee may send an Area Operator to check the position locally.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11.
  • Step 5.3.10 of 40OP-9CP01: The examinee places CPA-HS-4 to the OPEN position.

Place CPA-HS-4, Containment Power Access Purge Upstream NOTE: Per the note preceding this Isolation Valve CP-UV4B to the step, dual indication will be received OPEN position. on HS-4 because UV4A remains closed.

SAT / UNSAT Comments (required for UNSAT):

68

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

12.
  • Step 5.3.11 of 40OP-9CP01: When the operator completes this The examinee places CPA-HS-5 to step provide the following cue: the OPEN position.

Place CPB-HS-5, Containment Power Access Purge Upstream Another operator will complete the NOTE: Per the note preceding this Isolation Valve CP-UV5B to the rest of this procedure. step, dual indication will be received OPEN position. on HS-4 because UV5A remains This JPM is complete. closed.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 69

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 1 03/10/2009 6 Updated format 2 10/05/2009 6 Incorporated comments from the NRC validation team REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

37. Vendor reference document upgrade
38. Plant modification (include number)
39. Procedure upgrade
40. Internal or External Agency Commitment (indicate item number)
41. Technical Specification Change (indicate amendment number)
42. Other (explain in comments) 70

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:

  • The CRS has directed you to initiate a normal containment vent in accordance with 40OP-9CP01, Containment Purge System.
  • An area operator is standing by in the RCA to assist you.
  • RU-34 is available.
  • Authorization has been given to break ZZ06 locks as needed.
  • Venting of Containment is for pressure reduction
  • All prerequisites are complete.
  • The Effluent Release Permit is for todays date from 0700 to 2400 and is approved.
  • The shiftly Surveillance Test for RU-37 and RU-38 is current.

CANDIDATE 71

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1140010401, lineup the steam bypass control system for normal operation TASK STANDARD: The not in operate lights are extinguished; SBCS abnormal alarm and SBCS condenser interlock alarms are reset.

K/A: 3.4-041-A4.08 K/A RATING: RO: 3.0 SRO: 3.1 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40OP-9SF05, Operation of Steam Bypass Control System (Rev 20)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: John Dedon Date: 11/18/2003 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

72 Revised 9/23/08

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

8. SIMULATOR SETUP:

A. IC#: 104 (For 2009 NRC exam only)

B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

19. None KK. SPECIAL INSTRUCTIONS:
  • This JPM is set to run with JS6 for the 2009 NRC exam LL. REQUIRED CONDITIONS:
  • The following RED LEDs will be lit at the SBCS test panel:

o Emergency Off o Both Condenser Interlocks o Both Not in Operate o AMI MM. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

9. SPECIAL TOOLS/EQUIPMENT:
  • On the SBCS Test panel:

o Press the Emergency Off pushbutton o Place the System Mode Selection switch to the TEST position

  • Place the SBCS Master Controller on B06 in Manual o Emergency Off o Both Condenser Interlocks o Both Not in Operate o AMI 73

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to:

74

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

75

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix C: Examinee marks this step N/A and goes to step 2.0 to reconnect and IF the SBCS needs to be reset, reset SBCS.

THEN perform steps 2.9 through 2.15.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2.1 of Appendix C: Verifies both RED lights are lit.

Check at least 1 Not In Operate light is lit on the SBCS test panel.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Step 2.2 of Appendix C: Examinee depresses the "EMERGENCY OFF" pushbutton Depress and release the (no change in status of SBCS Test "EMERGENCY OFF" pushbutton Panel).

on the SBCS test panel.

SAT / UNSAT Comments (required for UNSAT):

76

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4. Step 2.3 of Appendix C: When the examinee opens the door The examinee ensures the EMERG to the cabinet provide the OFF backlight is illuminated.

Ensure BOTH of the following: following CUE: The power supply lights in SFN-CO3Y, nest 4, 5, 7

  • Check the EMERG OFF NOTE: The power supply lights are are not lit.

backlight is illuminated. not modeled in the simulator so it is

  • Check that the power supply necessary to give the cue.

lights (-15,+15) in SFN-C03Y, nests 4, 5 and 7 are (These lights are not modeled in the not illuminated. simulator).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.
  • Step 2.4 of Appendix C: The examinee places the System Mode Select switch in Place the System Mode Selection "DISCONNECT".

switch in "DISCONNECT".

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.
  • Step 2.5 of Appendix C: The examinee depresses and releases Depress and release the Light and the LIGHT AND TIMER TEST Timer test button on the SBCS test pushbutton.

panel.

SAT / UNSAT Comments (required for UNSAT):

77

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

7. Step 2.6 of Appendix C: The NOT IN OPERATE lights 1 and Check that the Not In Operate 1 2 will extinguish then come back and 2 lights extinguish and then ON in 30 seconds.

come back on in approximately 30 seconds.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.
  • Step 2.7 of Appendix C: The examinee places the System Place the System Mode Selection Mode Selection Switch in switch in the Operate position on "OPERATE".

the SBCS Test Panel SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

9. Step 2.8 of Appendix C: The NOT IN OPERATE lights will Ensure that the Not In Operate 1 extinguish in 30 seconds.

and 2 lights extinguish in approximately 30 seconds.

SAT / UNSAT Comments (required for UNSAT):

78

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

10. Step 2.9 of Appendix C: The examinee ensures the SBCS Ensure that the SBCS Master Master Controller in "MANUAL" Controller is in the `Manual' mode mode with backlight illuminated.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11. Step 2.10 of Appendix C: The examinee ensures zero output on Ensure that the output of the SBCS SBCS controller.

Master Controller is zero.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

12.
  • Step 2.11 of Appendix C: Switch SGN-HS-1010 to "RESET" Take SGN-HS-1010 to RESET, to (spring return to neutral).

reset the SBCS emergency off.

NOTE: The following alarms should clear:

  • SBCS ABNORMAL
  • SBCS COND INTLK
  • NSSS SBCS RACK U POWER
  • NSSS SBCS RACK Y POWER SAT / UNSAT Comments (required for UNSAT):

79

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

13. Step 2.12 of Appendix C: Turb Bypass Demand Alarm is not in IF the Turb Bypass Demand Alarm alarm.

is received, THEN ensure that the output of the SBCS Master Controller is zero.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

14. Step 2.13 of Appendix C: Verify "SBCS ABNORMAL" alarm Ensure the `SBCS Abnormal' alarm clear.

(Window 6A16A) is clear if condenser pressure is less than 5 HgA.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

15. Step 2.14 of Appendix C: Verify "SBCS COND INTLK" alarm Ensure the SBCS COND INLK clear.

alarm (Window 6A16B) is clear.

SAT / UNSAT Comments (required for UNSAT):

80

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

16. Step 2.15 of Appendix C: Another operator will lineup the GO TO ONE of the following to SBCS.

place the BCS Master Controller in the desired mode of operation.

  • Section 4.3, Lineup of the This JPM is complete.

SBCS for Normal Operation.

  • Section 4.4, Shifting Master Controller Modes SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 81

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 2 04/16/2009 6 Changed format REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

43. Vendor reference document upgrade
44. Plant modification (include number)
45. Procedure upgrade
46. Internal or External Agency Commitment (indicate item number)
47. Technical Specification Change (indicate amendment number)
48. Other (explain in comments) 82

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS CANDIDATE INITIATING CUE:

The Steam Bypass Control System has been disconnected at the SBCS Test Panel. The CRS directs you to perform 40OP-9SF05, Operation of Steam Bypass Control System, Appendix C to:

CANDIDATE 83

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250370201, Perform actions for loss of letdown.

TASK STANDARD: All charging pumps are stopped and CHB-UV-255 closed K/A: 3.3.2-004-A2.07 K/A RATING: RO: 3.4 SRO: 3.7 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ05 Loss of Letdown (Rev 18)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 04/25/2007 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

84 Revised 9/23/08

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

9. SIMULATOR SETUP:

C. IC#: 104 D. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

20. Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.

NN. SPECIAL INSTRUCTIONS:

  • Place simulator in FREEZE.
  • Place simulator in RUN and acknowledge alarms.
  • Ensure the Pressurizer Pressure Master Controller is set at 2250 psia.
  • Provide Cue.
  • Place simulator in RUN.
  • This JPM is set to run with JS5 for the 2009 NRC exam.

A. REQUIRED CONDITIONS:

  • Letdown isolated, Letdown Control Valves in manual and closed, the normally running Charging Pump in PTL, Pressurizer level at 56% and rising. IC 104 has these conditions built in.
2. SPECIAL TOOLS/EQUIPMENT:
  • Copy of 40AO-9ZZ05, Loss of Letdown, Appendix C (Rev 18)
  • No Simulator Driver actions are required for this JPM.

OO. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

If IC-104 is not available, reset to IC-20 and perform the following:

  • Close CHB-UV-515 using the handswitch on B03
  • Allow Pzr Level to increase to 54%
  • Place the normally running Charging Pump in PTL imf cmAVCV04CHEFV244_4 (Mechanical seizure) 85

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The Unit is in mode 1.
  • Letdown was lost.
  • The CRS has determined that letdown can NOT be restored.
  • CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown.
  • The pressurizer is not in boron equalization.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.

86

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

87

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix C: If Requested: Letdown can not be Examinee should determine from restored Initiating Cue that letdown cannot be WHEN letdown can be restored, restored.

THEN GO TO Appendix A, Restoration of Letdown with a Pressurizer Steam Bubble.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Appendix C: Examinee determines Boron equalization is not in progress by IF Boron equalization is in progress, information provided in Initiating THEN STOP Boron equalization. Cue.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3. Step 3 of Appendix C: Chemistry is notified of the status Examinee calls chemistry and of letdown. informs them of the status of Notify chemistry that the plant will letdown.

be operated with letdown flow isolated.

SAT / UNSAT Comments (required for UNSAT):

88

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4. Step 4.a of Appendix C: The CRS will ensure compliance Examinee determines that pressurizer with LCO 3.4.9 if pressurizer level level is 56% and rising (or will WHEN the CRS determines seal exceeds the Tech Spec limit. exceed 56% shortly).

injection and charging are to be stopped, OR pressurizer level is 56%

or more and rising, THEN perform the following:

  • IF the unit is in Mode 1, 2 or 3, THEN ensure compliance with LCO 3.4.9, Pressurizer.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. Step 4.b of Appendix C: Examinee determines RCP controlled Bleedoff valves should be open and Ensure controlled Bleedoff is are open.

isolated on all standby RCPs prior to Seal 2 Outlet Temperature exceeding 250°F.

SAT / UNSAT Comments (required for UNSAT):

89

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6. Step 4.c of Appendix C: Examinee places the individual seal injection flow controllers in manual Close the seal injection flow control and adjusts the output TO 100% to valves. close the valves by using:

RCP 1(2) / A (B) SEAL INJECTION FLOW CONTROL CHN-FIC-241 THRU 244 Note:

  • These are reverse acting valves 100% output is full closed
  • This action may be performed by fully closing one valve at a time or partially closing each valve followed by full closure.

NOTE: ALTERNATE PATH. The flow control valve for RCP 2B (CHN-FIC-244) will not respond and will not close so the examinee should go to the contingency step and close CHB-HV-255.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7.
  • Step 4.c.1 of Appendix C: Examinee closes CHB-HV-255, Seal Injection Supply Header Isolation Close CHB-HV-255, Seal Injection Valve.

Supply Header Isolation Valve.

SAT / UNSAT Comments (required for UNSAT):

90

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

8.
  • Step 4.d of Appendix C: Another operator will complete Examinee places all charging pumps this appendix. in pull to lock (PTL) by using:

Place all charging pumps in pull to CHARGING PUMP 1 P01 lock (PTL).

  • CHA-HS-216 This JPM is complete. And CHARGING PUMP 3 P01
  • CHA-HS-218A CHB-HS-218 (no breaker therefore not required to go to PTL)

And CHARGING PUMP 2 P01 CHB-HS-217 (in PTL is setup)

NOTE: Critical nature of this step is that all running charging pumps are stopped.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 91

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 1 04/16/2009 6 Revised for format and procedure rev REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

49. Vendor reference document upgrade
50. Plant modification (include number)
51. Procedure upgrade
52. Internal or External Agency Commitment (indicate item number)
53. Technical Specification Change (indicate amendment number)
54. Other (explain in comments) 92

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • The Unit is in mode 1.
  • Letdown was lost.
  • The CRS has determined that letdown can NOT be restored.
  • CRS directs you to perform applicable steps of 40AO-9ZZ05, Loss of Letdown, Appendix C, Extended Operations Without Letdown.
  • The pressurizer is not in boron equalization.

CANDIDATE 93

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 0780031301, Transfer 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02 TASK STANDARD: Transfers 13.8KV bus S01 From 13.8KV Bus S03 to the Unit Auxiliary Transformer MAN-X02, Rev 50 K/A: 3.6-062-K1.04 K/A RATING: RO: 3.7 SRO: 4.2 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) 41AL-1RK1A, Panel B01A Alarm Responses (Rev 49)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 10/22/2003 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR X PLANT TESTING METHOD: SIMULATE PERFORM X EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

94

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

10. SIMULATOR SETUP:

PP. IC#: 105 (For 2009 NRC exam only)

QQ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

21. None RR. SPECIAL INSTRUCTIONS:
  • This JPM is set to run with JS8 for the 2009 NRC exam.

SS. REQUIRED CONDITIONS:

  • NAN-S01 and NAN-S02 energized from the NAN-S03 and NAN-S04 respectively.

TT. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

10. SPECIAL TOOLS/EQUIPMENT:
a. Copy of 40OP-9NA03, 13.8KV Electrical System (NA) (Rev 31) Section 4.8 and 4.9
  • Copy of 41AL-1RK1A, Panel B01A Alarm Responses (Rev 50) Window 18B If IC-105 is not available, reset to IC-20 and perform the following:
  • Transfer NAN-S01 and NAN-S02 to the Startup Transformers per 40OP-9NA03 per Sections 7.0 and 11.0.
  • imf cmBKED05NANS04B_1 (Auto Trip logic failure) 95

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers).
  • The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9.
  • All prerequisites have been performed.

96

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

97

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

Note: This JPM involves two procedure sections. The JPM starts at procedure section 4.8. If examinee goes to section 4.9 first, start at JPM step 7.

STEP CUE STANDARD

1.
  • From step 4.8.3.1 of 40OP-9NA03: Examinee places synchronizing switch NAN-SS-S01A to ON and Turn the Synchronizing Switch for verifies proper synchronization NAN-S01 Supply Breaker, NAN-SS- indicated by MAN-EI-002I, MAN-S01A, to ON and check for proper EI-002R and synchronizing scope at synchronization. the 12 oclock position.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • From step 4.8.3.2 of 40OP-9NA03: Examinee closes NAN-S01A using NAN-HS-S01A and checks red Close the NAN-S01 Supply breaker closed light illuminated.

NAN-S01A by turning handswitch NAN-HS-S01A to CLOSE.

SAT / UNSAT Comments (required for UNSAT):

98

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3. From step 4.8.3.3 of 40OP-9NA03: Examinee verifies NAN-S03B opens when NAN-HS-S01A is released by Check that the NAN-S03-NAN-S01 checking the green open light is Supply breaker, NAN-S03B, illuminated on NAN-HS-S03B.

automatically opens when handswitch NAN-HS-S01A is released.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. From step 4.8.3.4 of 40OP-9NA03: Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter Check that NAN-S01 voltage is NAN-EI-S01.

between 12.42KV - 14.49KV.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. From step 4.8.3.5 of 40OP-9NA03: Examinee places synchronizing switch, NAN-SS-S01A to OFF.

Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S01A to OFF.

SAT / UNSAT Comments (required for UNSAT):

99

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

6. From step 4.8.3.6 of 40OP-9NA03: Examinee determines that the related Startup Transformer is not supplying Perform the appropriate section of more than one unit and does not Appendix D - S/U Xfmr Winding perform Appendix D.

Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7.
  • From step 4.9.3.1 of 40OP-9NA03: Examinee places synchronizing switch NAN-SS-S02A to ON and Turn the Synchronizing Switch for verifies proper synchronization NAN-S02 Supply Breaker, NAN-SS- indicated by MAN-EI-002I, MAN-S02A to ON and check for proper EI-002R and synchronizing scope at synchronization. the 12 oclock position.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.
  • From step 4.9.3.2 of 40OP-9NA03: Examinee closes NAN-S02A using NAN-HS-S02A and checks red Close the NAN-S02 Supply Breaker closed light illuminated.

NAN-S02A by turning handswitch NAN-HS-S02A to CLOSE.

SAT / UNSAT Comments (required for UNSAT):

100

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

9.
  • From step 4.9.3.3 of 40OP-9NA03: If requested CUE: Understand that Examinee verifies NAN-S04B did NAN-SO4B did not open. NOT automatically open when Check that the NAN-S04-NAN-SO2 NAN-HS-S02A is released by Supply Breaker NAN-S04B, checking that the red closed light is automatically opens when still illuminated on NAN-HS-S04B.

handswitch NAN-HS-S02A is released. Note: Refers to alarm response procedure 41AL-1RK1A, window 1A18B. The examinee may not refer to this procedure, although he/she should.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

10.
  • From step 2 of Window 1A18B If examinee requests permission to Examinee manually opens NAN-Alarm Response Procedure: open S04B, CUE: Open breaker S04B using NAN-HS-S04B and NAN-S04B. checks green open light is IF the running breaker did not trip illuminated.

automatically when the oncoming breaker control switch was returned Note: The examinee may perform to the normal position, THEN trip this action without reference to the the running breaker. alarm response procedure. This is acceptable but not preferred.

SAT / UNSAT Comments (required for UNSAT):

101

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

11. From step 4.9.3.4 of 40OP-9NA03: Examinee verifies voltage between 12.42 and 14.49 KV on voltmeter Check that NAN-S02 voltage is NAN-EI-S02.

between 12.42KV - 14.49KV.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

12. From step 4.9.3.5 of 40OP-9NA03: Examinee places synchronizing switch, NAN-SS-S02A to OFF.

Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S02A to OFF.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

13. From step 4.9.3.6 of 40OP-9NA03: Examinee determines that the related Startup Transformer is not supplying Perform the appropriate section of more than one unit and does not Appendix D - S/U Xfmr Winding perform Appendix D.

Loading Guidance, if a related Startup Xfmr winding is supplying more than one unit.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 102

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS Rev 1 04/16/2009 6 Reformatted to new template and rewrote note.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

55. Vendor reference document upgrade
56. Plant modification (include number)
57. Procedure upgrade
58. Internal or External Agency Commitment (indicate item number)
59. Technical Specification Change (indicate amendment number)
60. Other (explain in comments) 103

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • The Unit's 13.8 kV buses (NAN-S01 and NAN-S02) are being supplied from offsite power (startup transformers).
  • The CRS directs you to transfer NAN-S01 and NAN-S02 to the Unit Auxiliary Transformer, MAN-X02, in accordance with 40OP-9NA03 sections 4.8 and 4.9.
  • All prerequisites have been performed.

CANDIDATE 104

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1250300301: Perform actions to restore equipment following inadvertent CSAS TASK STANDARD: Respond to an inadvertent CSAS on Train "B" K/A: 3.5 026 A2.03 K/A RATING: RO: 4.1 SRO: 4.4 K/A: K/A RATING: RO: SRO APPLICABLE POSITION(S): RO/SRO VALIDATION TIME: 15 minutes

REFERENCES:

40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations Rev 13 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 08/25/2005 Revised By: Alan Malley Date: 04/16/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

105 Revised 9/23/08

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

11. SIMULATOR SETUP:

A. IC#: 105 (For 2009 NRC exam only)

B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:

EVENT COMMAND DESCRIPTION

22. If IC-105 is not available, reset to IC-20 and perform the following:
  • imf RP06H1 (Blown fuse for CSAS B)
  • imf RP06H2 (Blown fuse for CSAS B)
  • Allow time for equipment to actuate
  • This JPM is set to run with JS7 during the 2009 NRC exam D. REQUIRED CONDITIONS:
  • Place simulator in FREEZE
  • Provide initiating cue to examinee
  • Place simulator in RUN E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

11. SPECIAL TOOLS/EQUIPMENT:

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPMs ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred.
  • THIS IS A TIME CRITICAL JPM.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

107

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

108

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. From step 1 of Section 5.0 of 40AO- If Requested: CSAS occurred at the The examinee notes the time of the 9ZZ17: current time. actuation.

Record the time of the CSAS Start Time _______________

Actuation. _________

Time critical evolution starts here.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. From step 2 of Section 5.0 of 40AO- Examinee determines SIAS has not 9ZZ17: actuated and N/As this step.

IF ANY Containment Spray Pump is running, AND BOTH of the following conditions exist:

SAT / UNSAT Comments (required for UNSAT):

109

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3.
  • From step 3 of Section 5.0 of 40AO- The examinee places the CS 9ZZ17: handswitch in stop to anti-pump the CS pump and verifies the pump IF ANY Containment Spray Pump is stops.

running, AND BOTH of the following conditions exist:

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.
  • From step 4 of Section 5.0 of 40AO- Examinee overrides and closes SIB-9ZZ17: UV-671.

Override and close all open Containment Spray Header Isolation Valves.

SAT / UNSAT Comments (required for UNSAT):

110

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

5. From step 5 of Section 5.0 of 40AO- Examinee verifies Seal injection is in 9ZZ17: service, therefore no action should be taken unless the candidate exceeds IF seal injection is in service, AND 10 minutes to restore NC to the cooling water is NOT restored to RCPs.

ANY operating RCP within 10 minutes of the initial loss, THEN perform the following:

a. Ensure the reactor is tripped.
b. Stop all of the RCPs.
c. Isolate controlled bleedoff.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.
  • From step 5 of Section 5.0 of 40AO- Upon completion of this step CUE: Examinee opens the following 9ZZ17: valves:

Another operator will complete Open ANY of the following as

  • NCB-UV-403, NCW Section 5.0.

needed to restore Nuclear Cooling Containment Upstream Return Water to Containment: Isolation Valve

  • NCA-UV-402, NCW
  • NCB-UV-401, NCW Containment Downstream This JPM is complete. Containment Upstream Supply Return Isolation Valve Isolation Valve
  • NCB-UV-403, NCW Note: The examinee should open Containment Upstream Return UV-403 first and then UV-401. If Isolation Valve UV-401 is opened first this is NOT a
  • NCB-UV-401, NCW failure.

Containment Upstream Supply Isolation Valve Record the time that the RCP Nuclear Cooling Water Low Flow alarms clear on B04: ___________

Time Critical steps end here. Time should be less than 10 minutes.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 111

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 001 10/12/2004 3 Revised to reflect procedure change to prevent pressurizer level from exceeding Tech Spec limit.

002 04/20/2005 6 Revised to make step 7 non-critical since no action is required.

003 4/25/2007 6 Enhancements to bring in line with procedure.

004 03/25/2209 6 Changed to new JPM format 005 04/16/2009 6 Changed to new format and to add procedure Revision No.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

61. Vendor reference document upgrade
62. Plant modification (include number)
63. Procedure upgrade
64. Internal or External Agency Commitment (indicate item number)
65. Technical Specification Change (indicate amendment number)
66. Other (explain in comments) 112

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

  • The plant is operating at 100% power and an inadvertent Train B CSAS has just occurred.
  • THIS IS A TIME CRITICAL JPM.

CANDIDATE 113

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1270130401 Implement reactor Coolant System Draining Operations TASK STANDARD: Determine amount of water drained and actual RCS level.

K/A: 2.1.25 K/A RATING: RO: 3.9 SRO: 4.2 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40OP-9ZZ16, RCS Drain Operations (Rev 66)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

114 Revised 9/20/08

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

12. SIMULATOR SETUP:

UU. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

VV. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

23. N/A 24.

25.

26.

WW. SPECIAL INSTRUCTIONS:

  • None XX. REQUIRED CONDITIONS:
  • None YY. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

12. SPECIAL TOOLS/EQUIPMENT:
a. Copy of 40OP-9ZZ16, RCS Drain Operations Rev 66 Appendix D and E.

115

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange level) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.

Unit 2 RCS level is currently 102 ft. 6 inches.

Train A Shutdown Cooling is in service.

The Steam Generator Nozzle dams are installed.

The CRS directs that you perform the following and record your answers in the table provided:

1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114 to 1031 Increase in HUT level should be ____________ ft.

AND

2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train A local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16.
  • Given the following information, determine and record the actual RCS level per Appendix D Section 5.0:

Time Indicated level from LG -752 Train A SDC Actual RCS level (Train A) flow is:

0800 102 ft. 6 in. 4500 gpm ______________

0815 101 ft. 10 in. 4000 gpm ______________

116

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

117

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.
  • The examinee determines the The examinee determines the level change in level in the HUT increase in the HUT by one of the following methods:
1. Uses the graph to determine the gallons of water drained from RCS is (93,800 - 70500 =

23300) 23300 gallons divided by 12,704 gallons / foot in the HUT

= a change of 1.834 ft OR

2. Uses the graph to determine directly that the change is HUT level is (7.4 - 5.5 = 1.9 ft) is 1.9 ft.

Acceptable answer 1.8 to 2.0 ft.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. The examinee determines the P The examinee determines the P is (inches) from the Unit 2 graph for approximately 28 inches (+ 2 inches).

a SDC flow of 4500 gpm.

SAT / UNSAT Comments (required for UNSAT):

118

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3.
  • The examinee adds indicated The examinee determines actual level level and P (inches) to for the 0800 reading is approximately determine actual level. 104 ft. 10 in. (+ 2 inches)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. The examinee determines the P The examinee determines the P is (inches) from the Unit 2 graph for approximately 22.5 inches (+ 2 inches).

a SDC flow of 4000 gpm.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.
  • The examinee adds indicated The examinee determines actual level is level and P (inches) to approximately 103 ft. 8.5 in. (+ 2 determine actual level. inches)

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 119

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Increase in HUT level should be _____ 1.9 ( + 0.1 ft) _____ ft.

Time Indicated level from LG - Train A Actual RCS level 752 (Train A) SDC flow is:

0800 102 ft. 6 in. 4500 gpm __104 ft 10 in ( + 2 inches) __

0815 101 ft. 10 in. 4000 gpm __103 ft 8.5 in ( + 2 inches) __

ANSWER KEY 120

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 04/17/2009 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

67. Vendor reference document upgrade
68. Plant modification (include number)
69. Procedure upgrade
70. Internal or External Agency Commitment (indicate item number)
71. Technical Specification Change (indicate amendment number)
72. Other (explain in comments) 121

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

You are a Reactor Operator in Unit 2 Unit 2 has drained the RCS from 114 foot (flange level) to 103 foot 1 inch (top of the hot leg) level to the Holdup Tank per 40OP-9ZZ16, RCS Drain Operations.

Unit 2 RCS level is currently 102 ft. 6 inches.

Train A Shutdown Cooling is in service.

The Steam Generator Nozzle dams are installed.

The CRS directs that you perform the following and record your answers in the table provided:

1. Use Appendix E of 40OP-9ZZ16 and determine what level increase should have occurred in the Holdup Tank (in Feet) during the drain of the RCS from 114 to 1031 Increase in HUT level should be ____________ ft.

AND

2. Coordinate with the Auxiliary Operator in Containment and monitor RCS level locally using the Train A local gage glass per Appendix D, Section 5.0 of 40OP-9ZZ16.
  • Given the following information, determine and record the actual RCS level per Appendix D Section 5.0:

Time Indicated level from LG -752 Train A SDC Actual RCS (Train A) flow is: level 0800 102 ft. 6 in. 4500 gpm _____________

0815 101 ft. 10 in. 4000 gpm _____________

CANDIDATE 122

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active and which operator can stand shift as a Reactor Operator.

K/A: 2.1.4 K/A RATING: RO: 3.3 SRO: 3.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40DP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

123 Revised 9/20/08

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

13. SIMULATOR SETUP:

ZZ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

AAA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

27. N/A 28.

29.

30.

BBB.SPECIAL INSTRUCTIONS:

  • None CCC.REQUIRED CONDITIONS:
  • None DDD. SIMULATOR EVALUATION PRE-CHECK
  • N/A
13. SPECIAL TOOLS/EQUIPMENT:
a. Copy of 40DP-9OP02, Conduct of Shift Operations, Rev 46 124

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE ON THE NEXT PAGE 125

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position. (Assume all medical and training requirements are met).

Operator #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.

01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

02/12/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

02/13/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

03/13/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

03/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

03/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

Operator #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

01/21/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

02/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

02/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

Operator #1 can / cannot stand the position because ________________________________

Operator #2 can / cannot stand the position because ________________________________

126

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

127

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Obtain 40DP-9OP02, Conduct of Obtain 40DP-9OP02, Conduct of Shift Shift Operations. Operations.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • The examinee determines that The examinee reviews the 40DP-9OP02 operator #1 cannot stand the shift and determines the following reason for and the reason. operator #1 not being able to stand shift.

Operator #1 did not complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> on shift because 12 of his/her hours were not on one shift.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • The examinee determines that The examinee reviews the 40DP-9OP02 operator #2 can stand the shift and determines the following reason for and the reason. operator #2 being able to stand shift.

Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 128

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Operator #1 can / cannot stand the position because :

(Circle one)

Operator #1 did not complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> on shift because 12 of his/her hours were not on one shift.

Operator #2 can / cannot stand the position because:

(Circle one)

Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

ANSWER KEY 129

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 04/17/2009 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

73. Vendor reference document upgrade
74. Plant modification (include number)
75. Procedure upgrade
76. Internal or External Agency Commitment (indicate item number)
77. Technical Specification Change (indicate amendment number)
78. Other (explain in comments) 130

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

Determine which of the following individuals (if any) can stand shift as an independent Reactor Operator on 04/04/2009 and state the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).

Operator #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.

01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

02/12/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

02/13/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

03/13/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

03/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

03/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

Operator #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

01/21/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

02/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

02/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

Operator #1 can / cannot stand the position because ________________________________________

(Circle one)

Operator #2 can / cannot stand the position because ________________________________________

(Circle one)

CANDIDATE 131

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290310301 Perform a Tech Review of a Permit TASK STANDARD: Tech Review a Permit and determine three errors with the permit.

K/A: 2.2.13 K/A RATING: RO: 4.1 SRO: 4.3 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40DP-9OP29, Permit and Tagging Process Rev 35, Drawings 01-E-DWB-01 & 01-M-DWP-02 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Tom Stahler Date: 05/03/2003 Revised By: Alan Malley Date: 05/19/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

132 Revised 9/20/08

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

14. SIMULATOR SETUP:

EEE. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

FFF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

31. N/A 32.

33.

34.

GGG. SPECIAL INSTRUCTIONS:

  • None HHH. REQUIRED CONDITIONS:
  • None III. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

14. SPECIAL TOOLS/EQUIPMENT:
  • Drawing 01-E-DWB-01
  • Drawing 01-M-DWP-02 133

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

Unit 1 is 100% power The B Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water.

Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.

The CRS has directed you to perform Tech Review of Permit 1-110909-1.

  • Identify three (3) errors (Non-clerical - not typos) on the permit.

INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

134

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Reviews Permit or Work Order to Examinee reviews Permit or Work Order determine scope of work to be and determines work scope to be replacing performed. gasket on 1P-DWN-V050.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • Identifies one (1) error on the permit. Examinee determines the following Tag 2 has the wrong circuit breaker inaccuracy/inadequacy.

identified.

  • Tag 2 is the wrong circuit breaker (breaker is for the A pump)

The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Identifies one (1) error on the permit. Examinee determines the following inaccuracy/inadequacy.

Tag 5 has the wrong position (open)

  • Tag 5 has wrong position (OPEN) for for the discharge valve.

the discharge valve.

The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

135

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4.
  • Identifies one (1) error on the permit. Examinee determines the following inaccuracy/inadequacy.

Tag 7 has the right valve number, but

  • Tag 7 has right valve number but the wrong system designator.

wrong system designator (DS).

The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 136

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 1 05/19/2009 6 Update format to new JPM format. Revise numbering for 2009 NRC exam.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

79. Vendor reference document upgrade
80. Plant modification (include number)
81. Procedure upgrade
82. Internal or External Agency Commitment (indicate item number)
83. Technical Specification Change (indicate amendment number)
84. Other (explain in comments) 137

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam CANDIDATE INITIATING CUE:

Unit 1 is 100% power The B Demineralized Water Pump (DWN-P05B) has a severe seal leak on the pump. The CRS has directed that the pump be isolated and a permit hung to prevent spilling water.

Permit 1-110909-1 was generated manually due to the Site Work Management System (SWMS) being down.

The CRS has directed you to perform Tech Review of Permit 1-110909-1.

  • Identify three (3) errors (Non-clerical - not typos) on the permit.

CANDIDATE 138

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine RP entry requirements to operate a valve.

K/A: 2.3.13 K/A RATING: RO: 3.4 SRO: 3.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

NGW01, Initial Radiation Worker Practices; 75DP-9RP01 Radiation Exposure and Access Control Rev 16 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 05/13/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

139 Revised 9/20/08

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

15. SIMULATOR SETUP:

JJJ. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

KKK. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

35. N/A 36.

37.

38.

LLL. SPECIAL INSTRUCTIONS:

  • None MMM. REQUIRED CONDITIONS:
  • None NNN. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

15. SPECIAL TOOLS/EQUIPMENT:
a. Survey map
b. 75DP-9RP01 Radiation Exposure and Access Control Rev 16
c. Calculator 140

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

  • Your dose exposure this year has been 664 mrem.
  • Unit 1 is coming out of a refueling outage.
  • Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
  • You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
  • Determine the following:
1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)

ANSWER ____________________

2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).

Radiation area High radiation area Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area

3) What are the requirements to enter this area? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).

Double PCs Single PCs Respirator Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry 141

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

142

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.
  • How many minutes Examinee reviews RP map and (MAXIMUM) can you stay in determines highest radiation reading is the area with the highest dose 1140 mr/hr since there is no other rate without exceeding Palo designation per note 1 on the map.

Verdes first administrative limit Examinee may refer to 75DP-9RP01 to per 75DP-9RP01? determine first administrative limit is 1.5 rem/yr. Since the examinee already has 664 mrem this year (per the cue) he/she may only receive 836 mrem for the rest of the year. In a radiation field of 1140 mrem/hr, the dose is 19mr/min, therefore 836 mrem/19 mrem/hr equals 44 minutes.

Answer: 44 minutes (or .73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • What type of radiation posting Examinee should check the following:

should this are have? Check only those that apply to the area you will

  • Contamination Area need to access.
  • Could include Radiation area, but this is not critical.

SAT / UNSAT Comments (required for UNSAT):

143

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

3.
  • What are the requirements to enter Examinee should check the following:

this area? Check only those that apply to the area you will need to

  • Continuous RP coverage or Stay Times.

access?

  • Briefing by RP
  • Single PCs SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 144

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY INITIATING CUE:

  • Your dose exposure this year has been 664 mrem.
  • Unit 1 is coming out of a refueling outage.
  • Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
  • You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
  • Determine the following:
1) How many minutes (MAXIMUM) can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)

ANSWER ___44 minutes or 0.73 hour8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />s_______________

2) What type of posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).

Radiation area High radiation area X Locked High Radiation area Very High Radiation area X Contamination area High Contamination area Airborne radiation area Hot particle area

3) What are the requirements to enter this area? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).

Double PCs X Single PCs Respirator X Briefing by RP Emergency Dosimetry Portable Dose Rate Meter X Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry ANSWER KEY 145

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 05/13/2009 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

85. Vendor reference document upgrade
86. Plant modification (include number)
87. Procedure upgrade
88. Internal or External Agency Commitment (indicate item number)
89. Technical Specification Change (indicate amendment number)
90. Other (explain in comments) 146

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

  • Your dose exposure this year has been 664 mrem.
  • Unit 1 is coming out of a refueling outage.
  • Restoration of the Train A Essential Cooling Water to the Shutdown Cooling heat exchanger (SDCHX) is in progress.
  • You are assigned the task of venting the EW side of the SDCHX through EWA-V020.
  • Determine the following:
1) How many minutes can you stay in the area with the highest dose rate without exceeding Palo Verdes first administrative limit per 75DP-9RP01? (Assume you are not a Declared Pregnant Woman or a Declared Fertile Woman.)

ANSWER ____________________________

2) What type of radiation posting should this area have? Check only those that apply to the area you will need to access to perform the venting (not all areas of the room).

Radiation area High radiation area Locked High Radiation area Very High Radiation area Contamination area High Contamination area Airborne radiation area Hot particle area

3) What are the requirements to enter this area? Check only those that apply to the area you will need to access perform the venting (not all areas of the room).

Double PCs Single PCs Respirator Briefing by RP Emergency Dosimetry Portable Dose Rate Meter Constant RP coverage with Dose Rate meter or Stay Time Telemetric Dosimetry CANDIDATE 147

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct shift operations TASK STANDARD: Determine if license is active and which operator can stand shift as a Reactor Operator. Determine if shift staffing is met K/A: 2.1.4 K/A RATING: RO: 3.3 SRO: 3.8 K/A: 2.1.5 K/A RATING: RO: 2.9 SRO: 3.9 APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes

REFERENCES:

40OP-9OP02, Conduct of Shift Operations, Rev 46 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 04/17/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

148 Revised 04/22/08

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

16. SIMULATOR SETUP:

OOO. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

PPP. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

39. N/A 40.

41.

42.

QQQ. SPECIAL INSTRUCTIONS:

  • None RRR.REQUIRED CONDITIONS:
  • None SSS. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

16. SPECIAL TOOLS/EQUIPMENT:
a. Copy of Conduct of Shift Operations, 40DP-9OP02, Rev 46 149

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

Given the attached history of 2 Licensed operators and the planned shift manning perform the following:

  • Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009.
  • State the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).
  • Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verdes staffing requirements. Assume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highlighted operators.

Use the following to document you answers

1. RO #1 can / cannot stand the position because ________________________________

(Circle one)

2. RO #2 can / cannot stand the position because _______________________________

(Circle one)

3. Staffing requirements are / are not met.

(Circle one)

4. If staffing requirements are not met, they can be met by _________________

150

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Operator License History RO #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.

01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

02/12/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

02/13/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

03/13/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

03/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

03/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

01/21/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

02/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

02/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

151

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position Unit 1 Unit 2 Unit 3 SM SRO SRO SRO CRS SRO SRO SRO STA STA STA STA Reactor Operator RO #1 RO #2 RO Control Operator RO RO RO 3rd Reactor Operator Vacant Vacant SRO Area 1 AO AO RO Area 2 AO AO AO Area 3 AO AO AO Area 4 AO AO AO Radwaste AO 152

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

153

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Obtain 40DP-9OP02, Conduct of Obtain 40DP-9OP02, Conduct of Shift Shift Operations. Operations.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • The examinee determines that #1 The examinee states the following cannot stand the shift and the reason for operator #1 not being able to reason. stand shift.

Operator #1 did not complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> on shift because 12 of his/her hours were not on one shift.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • The examinee determines The examinee states the following operator #2 can stand the shift reason for operator #2 being able to and the reason. stand shift.

Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

SAT / UNSAT Comments (required for UNSAT):

154

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

4.
  • Determine if staffing The examinee determines that Unit 1 requirements are met and what would not have the required number of actions would be necessary (if reactor operators.

any) to meet Palo Verdes staffing What could be done?

requirements (with the following crew manning list). Answer #1 Could move SRO (3rd Reactor Operator from Unit 3) to fill a reactor operator position in Unit #1.

Answer #2 Could call in another reactor operator to man Unit #1.

Either answer is acceptable.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 155

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY

1. Operator #1 can / cannot stand the position because :

Operator #1 did not complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> on shift because 12 of his/her hours were not on one shift.

2. Operator #2 can / cannot stand the position because:

Operator #2 received an Initial NRC license during the previous quarter so he/she is not required to complete 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

3. Staffing requirements are / are not met.

(Circle one)

4. If staffing requirements are not met, they can be met by: (Either answer acceptable)
  • Could move SRO or RO from Unit 3 to fill a reactor operator position in Unit #1.
  • Could call in another reactor operator to man Unit #1.

ANSWER KEY 156

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 04/17/2009 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

91. Vendor reference document upgrade
92. Plant modification (include number)
93. Procedure upgrade
94. Internal or External Agency Commitment (indicate item number)
95. Technical Specification Change (indicate amendment number)
96. Other (explain in comments) 157

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

Given the attached history of 2 Licensed operators and the planned shift manning perform the following:

  • Determine if each of the following individuals (if any) can stand shift as an independent Reactor Operator on the day of 04/04/2009.
  • State the reason why they can or cannot stand the position. (Assume all medical, training requirements, and overtime limitations are met).
  • Determine if staffing requirements are met and what actions (if any) would be necessary to meet Palo Verdes staffing requirements. Assume all operators except the two listed above are qualified to stand the position. Use the data from above to determine qualification of the highligh9+1ted operators.

Use the following to document you answers

1. RO #1 can / cannot stand the position because ________________________________

(Circle one)

2. RO #2 can / cannot stand the position because _______________________________

(Circle one)

3. Staffing requirements are / are not met.

(Circle one)

4. If staffing requirements are not met, they can be met by _________________

CANDIDATE 158

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Operator License History RO #1 12/21/2008 Operator taken off-shift to support the procedure upgrade project.

01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

02/12/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

02/13/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 2.

03/13/2009 Stood 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift as 3rd Reactor Operator in Unit 3.

03/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

03/31/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

RO #2 01/15/2009 Received a new NRC Reactor Operator License 01/20/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

01/21/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 3rd Reactor Operator in Unit 1.

02/25/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

02/26/2009 Stood 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift as 2nd Reactor Operator in Unit 1.

CANDIDATE 159

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam PLANNED SHIFT SCHEDULE TO DETERMINE MANNING Position Unit 1 Unit 2 Unit 3 SM SRO SRO SRO CRS SRO SRO SRO STA STA STA STA Reactor Operator RO #1 RO #2 RO Control Operator RO RO RO 3rd Reactor Vacant Vacant SRO Operator Area 1 AO AO RO Area 2 AO AO AO Area 3 AO AO AO Area 4 AO AO AO Radwaste AO CANDIDATE 160

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290190102 Ensure compliance with Tech Specs TASK STANDARD: Identify applicable LCO / LCO conditions and completion times.

K/A: 2.2.40 K/A RATING: RO: 3.4 SRO: 4.7 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes

REFERENCES:

Technical Specifications SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 04/23/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

161 Revised 9/20/08

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

17. SIMULATOR SETUP:

TTT. IC#: N/A UUU. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

43. N/A 44.

45.

46.

VVV. SPECIAL INSTRUCTIONS:

  • None WWW. REQUIRED CONDITIONS:
  • None XXX. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

17. SPECIAL TOOLS/EQUIPMENT:
a. Copy of Tech Specs
b. Copy of print 01-E-SIB-0001
c. Copy of 40OP-9PB01 162

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPM's ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

163

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

Given the following plant conditions in Unit 3 on the same day:

  • Unit 3 is at 100% power.

Event 1

  • At 1315 the area operator reports oil all over the floor of the B High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler.
  • Maintenance has investigated the B HPSI pump and determined it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair the oil leak.

Event 2

  • At 1427 a SESS alarm comes in for the A Low Pressure Safety Injection pump (SIA-P01).
  • The control room indication for the A LPSI pump breaker has been lost.
  • The area operator reports that all lights are off at the breaker for the A LPSI pump with the breaker open.

Determine any applicable LCO(s) and TLCO(s) and completion time(s).

(Assume Event 1 is still in progress when Event 2 occurs.)

Use the following to document your answers:

At time: Enter LCO condition(s) Completion Enter TLCO condition(s) Completion time(s) time(s)

(if applicable) (if applicable) 1315 Event 1 1427 Event 2 164

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

165

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.
  • The examinee refers to Tech The examinee determines the applicable Specs and the TRM (Technical LCO is LCO 3.5.3 condition B and the Requirements Manual). completion time is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • Determine the applicable LCO(s) The examinee determines the applicable

/ TLCO(s) and completion times, LCO is LCO 3.5.3 condition B and the if any for time 1315. completion time is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Determine the applicable LCO(s) The examinee determines the applicable

/ TLCO(s) and completion times, LCO is 3.5.3 condition A and the if any for time 1427 completion time is 7 days.

The examinee determines the applicable TLCO is 3.5.201 condition A and the completion time is 7 days.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 166

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY At time: Enter LCO Completion Enter TLCO Completion condition(s) time(s) condition(s) time(s)

(if applicable) (if applicable) 1315 LCO 3.5.3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> N/A N/A condition B Event 1 1427 LCO 3.5.3 7 days TLCO 3.5.201 7 days condition A Condition A Event 2 ANSWER KEY 167

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 04/23/2009 6 New record REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

97. Vendor reference document upgrade
98. Plant modification (include number)
99. Procedure upgrade 100. Internal or External Agency Commitment (indicate item number) 101. Technical Specification Change (indicate amendment number) 102. Other (explain in comments) 168

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

Given the following plant conditions in Unit 3 on the same day:

  • Unit 3 is at 100% power.

Event 1

  • At 1315 the area operator reports oil all over the floor of the B High Pressure Safety Injection (HPSI) pump (SIB-P02) room and no oil level indicated in pump bubbler.
  • Maintenance has investigated the B HPSI pump and determined it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair the oil leak.

Event 2

  • At 1427 a SESS alarm comes in for the A Low Pressure Safety Injection pump (SIA-P01).
  • The control room indication for the A LPSI pump breaker has been lost.
  • The area operator reports that all lights are off at the breaker for the A LPSI pump with the breaker open.

Determine any applicable LCO(s) and TLCO(s) and completion time(s).

(Assume Event 1 is still in progress when Event 2 occurs.)

Use the following to document your answers:

At time: Enter LCO condition(s) Completion Enter TLCO condition(s) Completion time(s) time(s)

(if applicable) (if applicable) 1315 Event 1 1427 Event 2 CANDIDATE 169

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1290020301 Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine exposure, stay time, develop Pre-Job Brief and determine who will provide a second check.

K/A: 2.3.13 K/A RATING: RO: 3.4 SRO: 3.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes

REFERENCES:

Technical Specifications SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Jordan Johnston Date: 5/29/2007 Revised By: Alan Malley Date: 4/29/2009 Technical Review Operations Approval E-Plan Review N/A Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

170 Revised 9/20/08

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

18. SIMULATOR SETUP:

YYY. IC#: N/A ZZZ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

47. N/A 48.

49.

50.

AAAA. SPECIAL INSTRUCTIONS:

  • None BBBB. REQUIRED CONDITIONS:
  • None CCCC. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

NA if Simulator setup not required Verified by: ____________________________ Date: ____________________

18. SPECIAL TOOLS/EQUIPMENT:
  • REP# 9-9999Z
  • Survey map of SDC HX room.
  • Calculator 171

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPM's ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

172

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

You are the Control Room Supervisor in Unit 1. Operations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work.

Radiation Protection has informed you that they will be using REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.

The operator assigned to the job has a current year to date exposure of 664 mr.

It is estimated to take 15 minutes to complete the venting.

Your task as the CRS is as follows:

Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics:

  • Task # to be used to perform the job.
  • How much dose is expected to be received by the operator
  • Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded
  • RP coverage that is required for this task.
  • Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).

Note: This will not take the place of the pre-job brief with RP.

Operator Exposure history Other information 1 1489 mrem year to date 2 37 mrem this month Has declared she is attempting to become pregnant and has filled out a Pre-Natal Dose Limit Statement.

3 420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.

173

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Task #

Expected Dose Max Stay time before first admin hold point Expected amount of RP coverage Which operator should perform 2nd check 174

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.
  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

175

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.
  • Determine Task. Examinee determines that Task 3 will be used.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • Determine expected dose to be Determines 285 mrem will be received.

received. (Based on the 15 minute stay time estimate given in the cue.)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.
  • Determine maximum stay time Determines that max stay time 44 minutes.

before the first administrative hold point is exceeded SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.
  • Determine RP Coverage Determines that the REP will require requirements per the REP. continuous RP coverage or stay time.

SAT / UNSAT Comments (required for UNSAT):

176

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam STEP CUE STANDARD

5.
  • Determine which operator will Determines that the operator 3 will perform perform the Independent Verification the independent verification because Operator 1 would exceed the first admin hold point and Operator 2 would exceed her dose limit due to declaring attempting to become pregnant. Only operator 3 would not exceed a dose limit of any type.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 177

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY Task # Task 3 Expected Dose 285 millirem Max Stay time 44 minutes before first admin hold point RP coverage Continuous RP coverage or Stay time.

required by the REP for this task Which operator Operator 3 should perform 2nd check ANSWER KEY 178

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 5/29/2007 6 New record 1 4/29/2009 6 Modified record to different area, different cues, and different answers.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

103. Vendor reference document upgrade 104. Plant modification (include number) 105. Procedure upgrade 106. Internal or External Agency Commitment (indicate item number) 107. Technical Specification Change (indicate amendment number) 108. Other (explain in comments) 179

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIATING CUE:

You are the Control Room Supervisor in Unit 1. Operations will be venting the EW supply to the Shutdown cooling heat exchanger in preparation for recovering the system from outage work.

Radiation Protection has informed you that they will be using REP 9- REP 9-9999Z for this job. The task will require an operator to vent the Shutdown cooling Heat Exchanger at valve EWA-V20.

The operator assigned to the job has a current year to date exposure of 664 mr.

It is estimated to take 15 minutes to complete the venting.

Your task as the CRS is as follows:

Given the REP and radiation survey map of the Train A Shutdown Cooling Heat Exchanger room, outline a pre-job brief covering the following topics:

  • Task # to be used to perform the job.
  • How much dose is expected to be received by the operator
  • Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded.
  • RP coverage that is required for this task.
  • Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed.

(Assume it will take two minutes to perform the second check).

Note: this will not take the place of the pre-job brief with RP.

Operator Exposure history Other information 1 1489 mrem year to date 2 37 mrem this month Has declared she is attempting to become pregnant and has filled out a Pre-Natal Dose Limit Statement.

3 420 mrem this month, and 720 mrem year to date Use the form on the next page to document your answers.

180

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Task # to be used to perform the job.

How much dose is expected to be received by the operator?

Max stay time for the operator above (in the 1140 mr/hr area) before the first administrative exposure hold point (per 75DP-9RP01) is exceeded.

RP coverage that is required for this task.

Given the exposure of other operators in the table below, determine which operator would be the best choice to perform an independent verification that EWA-V020 is closed after venting is completed. (Assume it will take two minutes to perform the second check).

181

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM BASIS INFORMATION TASK: 1240100202 Classify events requiring emergency plan implementation TASK STANDARD: Emergency Action Level (EAL) is identified and Site Area Emergency classified.

K/A: 2.4.41 K/A RATING: RO: 2.9 SRO: 4.6 APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

EPIP-01, Satellite Technical Support Center Actions (rev 30) and EPIP-99, EPIP Standard Appendices (Rev 26)

SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 4/21/2009 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review Training Approval Only required for Emergency Plan JPMs TESTING METHOD ACTUAL TESTING ENVIRONMENT: SIMULATOR PLANT TESTING METHOD: SIMULATE PERFORM EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSATc c

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

182

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

19. SIMULATOR SETUP:
20. IC#: This JPM is designed to be given after the 2009 NRC Scenario 3 DDDD. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION
51. N/A EEEE. SPECIAL INSTRUCTIONS:
  • This JPM is designed to be given after the 2009 NRC Scenario 3 FFFF. REQUIRED CONDITIONS:
  • NONE GGGG. SIMULATOR EVALUATION PRE-CHECK Scenario 3 is complete.
19. SPECIAL TOOLS/EQUIPMENT:
a. Copy of EPIP-01, Satellite Technical Support Center Actions
b. Copy of EPIP-99, EPIP Standard Appendices 183

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN PLANT JPM's ONLY

  • Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
  • Inform the control room staff of any discovered deficiencies.
  • Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contaminated, airborne, or high radiation areas.

ALL JPMs

  • You may use any source of information normally available.

INITIATING CUE:

Based on plant conditions at the conclusion of the scenario, perform the two following tasks:

1. List the Emergency Action Level that is CURRENTLY met.
2. List the Classification of this event.

THIS IS A TIME CRITICAL JPM INFORMATION FOR EVALUATOR'S USE:

  • Denotes Critical Step
  • At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
  • Any step marked UNSAT requires comments.
  • If this is the first JPM of the set then ensure the examinee has been briefed.
  • Step sequence is not critical unless noted or will prevent achieving the task standard.

184

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam

  • Notify unit Shift Manager of in-plant JPM performance.
  • Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.
  • Locked valves may be involved. No attempt will be made to actually operate any valves.

185

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.
  • List the Emergency Action Level The examinee refers to the Mode 1-4 that is met. classification chart and determines FA1 is the correct Emergency Action Level (EAL).

Answer: FA1 - ANY loss or ANY Potential loss of EITHER Fuel Clad OR RCS due to RCS leakrate greater than available makeup by a loss of RCS subcooling to saturation (0 °F) or RCS leak rate greater than charging capacity with Letdown isolated.

START TIME ________________

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.
  • List the Classification of this Examinee use the Mode 1-4 event. classification chart to determines the classification.

Answer: Alert STOP TIME _________________

Time should be less than 15 minutes from the time the cue is given until the event is classified.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT 186

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam ANSWER KEY

1. List the Emergency Action Level that is currently met.

FA1

2. List the Classification of this event.

Alert ANSWER KEY 187

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON NUMBER DATE REVISED COMMENTS 0 10/15/2009 6 Record Created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

109. Vendor reference document upgrade 110. Plant modification (include number) 111. Procedure upgrade 112. Internal or External Agency Commitment (indicate item number) 113. Technical Specification Change (indicate amendment number) 114. Other (explain in comments) 188

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam INITIAL CONDITIONS INITIATING CUE:

Based on plant conditions at the conclusion of the scenario, perform the two following tasks:

1. List the Emergency Action Level that is CURRENTLY met.
2. List the Classification of this event.

THIS IS A TIME CRITICAL JPM Use this as your answer sheet.

CANDIDATE 189

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners: Operators:

Initial Conditions: IC #100, (100% power, MOC).

Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.

Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.

Event Malf. No. Event Type* Event Description No.

1 None N Shift Condensate Demineralizers.

CO/SRO 2 imf cmCNCV04CHNFIC243_2 I A seal injection controller will fail in automatic requiring the crew to RO/SRO take manual control of the controller.

3 imf cmCPCH03HCNA02A_6 C The A and C CEDM fans will trip requiring the CRS to enter 40AO-imf cmCPCH03HCNA02C_6 CO/SRO 9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).

4 imf mfRD02B R CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.

RO/CO/SRO Crew begins a 20% downpower. SRO enters LCO 3.1.5 Condition A (TS) and LCO 3.2.4 Condition A.

5 imf mfTH06A C A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO 40AO-9ZZ02, Excessive RCS leakrate.

(TS) 6 imf mfRD02L M - ALL Another CEA slips into the core. This will cause a reactor trip signal mfRD12A C - RO/SRO but an ATWS will occur. This will require the crew to open the mfRP04A breakers supplying the CEDM MG sets.

Critical Task - Crew will insert all CEAs.

mfRP04C 7 mfRX01 I After the trip Tave will fail low requiring the CO to manually feed the CO /SRO SGs.

8 mmf mfTH06A M-ALL The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.

Critical Task - Initiate actions to cooldown and isolate the affected steam generator End The scenario is terminated when the crew commences affected steam point generator has been isolated or at the discretion of the lead examiner

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

NUREG-1021, Revision 9 190 of 248

Appendix D Scenario Outline Form ES-D-1 Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.

The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

Note:

The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.

NUREG-1021, Revision 9 191 of 248

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.

The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

NUREG-1021, Revision 9 192 of 248

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 1 Event

Description:

Shift Condensate Demineralizers Time Position Applicants Actions or Behavior T=0 CO Performs prerequisites:

  • One NO and one RO to perform this Sections
  • Instrument air is available
  • Service air is available.
  • The service vessel to be placed has been rinsed within the past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Informs chemistry demin configuration will be changed.

Directs the demin operator to ensure the following valve SCN-V960F is open for the F Demin Vessel.

Opens the F Demin Vessel outlet valves (SCN-UV-216) using handswitch SCN-HS-216A on B07.

Verifies the STANDBY light goes out, The IN-SERVICE light illuminates, the red light illuminates and the green light goes out.

Requests demin operator to monitor vessel flow and DP.

Closes E Demin Vessel Outlet valve (SCN-UV-0215) using handswitch SCN-HS-215A on B07.

Verifies the STANDBY light illuminates, the IN-SERVICE light goes out, the green lights illuminates, the red lights go out, and indication that flow has stopped through the service vessel.

Requests demin operator to monitor vessel flow and DP.

Directs demin operator to ensure SCN-V960E is closed.

Directs demin operator to ensure SCN-V961E is open.

193 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 194 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 2 Event

Description:

Seal Injection controller failure Time Position Applicants Actions or Behavior T=7 RO Evaluates alarm window 3A11A per 40AL-9RK3A.

  • Determines a Lo flow condition exist for RCP 2A only (~7.7 gpm).
  • Takes manual control of flow controller CHN-FIC-243 on B03 and adjusts flow to normal (~ 6.6 gpm).

CRS May enter 40AO-9ZZ04, RCP Emergencies.

Directs RO to take manual control of valve controller and restore flow to the normal band per 40AL-9RK3A, Secondary Priority Action 1.

Op-Test No: _2009_ Scenario No.: 1 Event No: 3 Event

Description:

CEDM fans trip / Failure of Stby fans to auto start 195 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Time Position Applicants Actions or Behavior T=14 CO Responds to alarms on B07 (Window 7A9B), determines that CEDM fans are not running.

Uses the Alarm Response Procedure or direction from the CRS to start the B and D CEDM fans using handswitch HCB-HS-50 on B07.

Evaluator Note: These standby fans have a two minute time delay before they should start, however, due to the fault, they will not auto start.

RO Responds to alarms on SESS panel (Window 6D). Addresses the alarm response procedure.

CRS Evaluator Note: The crew may start the standby fans from the alarm response procedure on B07.

May implement Loss of HVAC procedure, 40AO-9ZZ20.

  • Directs the CO to start the standby CEDM fans.
  • May direct CO to verify normal containment parameters.

May performs brief to address the failure and contingencies.

Evaluator Note: There are no Tech Specs to address for this event.

196 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 4 Event

Description:

CEA 15 drops into the core Time Position Applicants Actions or Behavior T=21 Crew Responds to alarms on Board 3, determines that CEA 15 has dropped into the core.

CRS Implement CEA Malfunction Abnormal Operating Procedure, 40AO-9ZZ11.

1. Checks that at least one CEA is deviating from its group by greater than 6.6 inches.
2. Verifies no CEA Reg Group is below the Transient Insertion Limit
3. Verifies Reactor power is not < 1%.
4. Ensures two or more CEAs are not deviating > 9.9 inches from their associated group.
5. Direct CEDMCS to Standby
6. Directs performance of Appendix E, Initial Actions.
7. Records CEA deviation time and Initial Power level.
8. Performs the following to start a power reduction within 10 minutes.
a. Logs the start time for power reduction
b. Directs the CO to lower turbine load to raise Tave 3°F greater than Tref.
9. Determines that a 20% downpower is required.
10. Calculates the number of gallons of baric acid needed by using the STA reactivity worksheet. (~ 1000 gallons).
11. Directs the CO to lower turbine load to maintain Tave 3°F greater than Tref.
12. Directs the RO to commence borating at a minimum rate of 25 gpm.
13. Determines the time required to perform the downpower using Appendix B.
14. When the requirements of Appendix B allow temperature to be lowered, the CRS directs the CO to maintain Tave/Tref mismatch + 3°F.
15. Determines the ability to stabilize power at the target plateau using the Maneuvering Box Tools (This may have been discussed at the beginning of shift reactivity brief).

Enters LCO 3.1.5 Condition A. and LCO 3.2.4 Condition A.

Examiner Note - Step 22 of 40AO-9ZZ11 addresses TS. CRS may not get to address LCO.s 3.1.5 and 3.2.4 within the timing of the event. This can be followed up after the scenario.

RO Places CEDMCS in Standby using the Mode Select switch on the CEDMCS panel (may be performed by CO)

Performs Appendix E actions (may be performed by CO):

1. Places Pressurizer in boron equalization
a. Override and energize all pressurizer backup heaters:

RCA-HS-100-4 RCB-HS-100-5 RCN-HS-100-6 RCN-HS-100-7 RCN-HS-100-8 RCN-HS-100-9

b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to 197 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 4 Event

Description:

CEA 15 drops into the core Time Position Applicants Actions or Behavior 2220 psia.

Borates to the RCS as direct by the CRS.

(basic steps the RO will perform)

1. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
2. Selects the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2.
3. Starts the boration as follows:
a. Place CHN-HS-210 in the BORATE position.
b. Depress the Reset pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
c. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
d. Adjusts flow to the required flowrate (if > 40 gpm needed).

May perform Appendix B as directed by the CRS.

CO Lowers Turbine load using the Turbine Load Limit potentiometer on B06 to raise Tave greater than Tref by 3 °F to maintain power within the limits of Appendix B.

May perform Appendix B as directed by the CRS.

After ~5% load reduction, have the driver insert the next malfunction.

198 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 5 Event

Description:

Steam Generator Tube Leak Time Position Applicants Actions or Behavior T=41 Crew Receives alarms on RMS panel. Reports to the CRS that RU-142 is in alarm with SG #1 having the highest readings.

CRS Enters Excessive RCS Leakrate, 40AO-9ZZ02, Section 5.

Examiner Note: The leakrate is small (~ 5gpm), but due to the down power, the crew may start the third charging pump and isolate letdown. It is not expected that the crew will trip the reactor.

IF pressurizer level is lowering, THEN ensure all available Charging Pumps are running.

IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown.

IF ALL of the following conditions exist:

  • All available Charging Pumps are operating
  • Letdown is isolated
  • Pressurizer level is lowering THEN perform the following:
a. Ensure that the Reactor is tripped.
b. GO TO ONE of the following:
  • 40EP-9EO11, Lower Mode Functional Recovery Ensure the event is being classified.

IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.4.14, RCS Operational Leakage. The CRS should LCO 3.4.14 Condition b.

Direct Chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.

Notify Radiation Protection that an RCS leak exists.

Examiner Note: Due to the downpower being performed due to the slipped CEA, the crew will not be able to determine a leakrate, however, RU-142 gives the crew a leakrate based on RU readings.

Determine the leakrate using ANY of the following:

  • Appendix A, 15 Minute Leak Rate Calculation
  • Appendix B, ERFDADS Leak Rate Determination
  • 40ST-9RC02, ERFDADS (Preferred) Calculation of RCS Water Inventory

IF the plant will be shutdown, THEN PERFORM 40OP-9ZZ05, Power Operations.

Perform Appendix C, Minimize Release to the Environment.

Perform 40DP-9ZZ14, Contaminated Water Management (would assign to another SRO in the unit or unaffected unit).

Direct an operator to perform Appendix D, Aligning Turbine Building Sumps to LRS.

Direct Chemistry to sample the condensate and other connecting systems, including turbine building sumps for activity.

IF the unit is in Mode 1 - 4, THEN ensure compliance with LCO 3.7.16, Secondary Specific Activity.

RO Examiner Note: Due to the downpower being performed due to the slipped CEA, 199 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 5 Event

Description:

Steam Generator Tube Leak Time Position Applicants Actions or Behavior the crew will not be able to determine a leakrate, however, RU-141 and RU-142 gives the crew a leakrate based on RU readings.

Since a shutdown is required due to the SGTL and a downpower is in progress, the CRS may have the RO reset the totalizer on the makeup to continue the downpower.

However, this may not occur until later in the event, therefore it may not be observed (or the CRS may wait until after the 20% downpower is completed to reset for the downpower).

  • Set the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
  • Select the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) as determined in step 7.3.1 or 7.3.2.
  • Continue the boration as follows:
1. Place CHN-HS-210 in the BORATE position.
2. Depress the Reset pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
3. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).
  • May be asked to secure boration.

CO Addresses RMS alarms and determines which monitors are in Alarm (RU-139, RU-142, RU-141, & RU-7). Reports highest reading in SG #1. Provides leakrate from RMS to the CRS as requested.

Secures SG blowdown as directed in the RMS alarm response procedure.

Performs Appendix C, Minimize Release to the Environment.

1. Ensure ARN-HS-19, Post Filter Mode Select Switch, is in the THRU FILTER MODE by observing red indication on ARN-HS-19 on B07.
2. Select OFF on BOTH of the following switches:
  • SGN-HS-1007, Valve 7 Mode Select
  • SGN-HS-1008, Valve 8 Mode Select
3. Throttle opens CDN-HV-275, Demineralizer Water Feed to Condensate Service Header Valve using handswitch CDN-HS-275 on B04, to maintain 50 - 100 psig on CDN-PI-201.
4. Ensure that BOTH of the following Condensate Pump Overboard Valves are closed:
  • CDN-HV-29 (Handswitch CDN-HS-29 on B05)
  • CDN-HV-30 (Handswitch CDN-HS-30 on B05)

Reduces turbine load as necessary to maintain primary temperature as directed by the CRS.

200 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 5 Event

Description:

Steam Generator Tube Leak Time Position Applicants Actions or Behavior 201 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 6 Event

Description:

Trip initiator (2nd CEA drops into the core) ATWS Time Position Applicants Actions or Behavior T=57 Crew Recognizes another CEA has dropped into the core by alarms (on B04 and B05) and the CEAPDS monitor.

Recognizes that a Reactor Trip should have occurred by all 4 channels of bistable trip indication on PPS parameter indications on B05 and/or first out annunciator indication on B04.

CRS Examiner Note: The SGTL will increase in size (200-300 gpm) which will cause the RCS pressure and level to begin trending down. Depending on when the reports are made, the RO may report pressure and level decreasing. This may cause the CRS to direct a manual initiation of SIAS/CIAS.

Implements procedure 40EP-9EO01, Standard Post Trip Actions.

1. Open the placekeeper and enter the EOP Entry Time.
2. Determine that Reactivity Control acceptance criteria are met by the following:
a. Check that reactor power is dropping.
b. Check that start-up rate is negative.
c. Check that ALL full strength CEAs are inserted.

Evaluator Note: The crew will have to open the B2 breakers for L03 and L10 on B01 to trip the reactor (using handswitches NGN-HS-L03B2 and NGN-HS-L10B2 on B01). The CRS may direct this prior to getting the SPTA procedure.

Critical Task - Crew will insert all CEAs.

3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
a. Check that the Main Turbine is tripped.
b. Check that the Main Generator output breakers are open.
c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:
  • All vital and non-vital AC buses are powered
  • All vital and non-vital DC buses are powered
4. Determine that RCS Inventory Control acceptance criteria are met by the following:
a. Check that Pressurizer level meets BOTH of the following:
  • 10 - 65%
  • Trending as expected to 33 - 53%
b. Check that the RCS is 24°F or more subcooled.
c. Check that BOTH of the following are in service to all RCPs.
  • Seal injection
  • Nuclear Cooling Water
5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
  • Pressurizer pressure is 1837 - 2285 psia
  • Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.

202 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 6 Event

Description:

Trip initiator (2nd CEA drops into the core) ATWS Time Position Applicants Actions or Behavior 5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.

6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
  • At least one RCP is operating
  • Loop T is less than 10°F
  • RCS is 24°F or more subcooled (Continued in next event)

RO Examiner Note: The SGTL will increase in size which will cause the RCS pressure and level to begin trending down. Depending on when the reports are made, the RO may report pressure and level decreasing.

May report Reactivity. Attempts to trip the reactor using B05 pushbuttons.

May open NGN-L03B2 and NGN-L10B2 using handswitches on B01 to de-energize the CEDM MG sets (This may be done by CO).

Report the status of the Electric Plant (all buses are energized).

Reports Pressurizer level and RCS subcooling.

Reports status of Seal injection and Nuclear Cooling to the RCPs.

Reports RCS pressure. Will stop one RCP in each loop when RCS pressure remains below the SIAS setpoint.

Reports RCPs operating, loop T, and RCS subcooling.

May report RCS Tc (usually done by the CO).

May report containment pressure and status of Radiation Monitoring.

May report containment temperature and containment pressure.

CO May report Reactivity when CEAs insert.

Reports status of the Main Turbine and Generator output breakers.

(Continued in next event) 203 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 6 Event

Description:

Trip initiator (2nd CEA drops into the core) ATWS Time Position Applicants Actions or Behavior 204 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 7 Event

Description:

Tave fails low Time Position Applicants Actions or Behavior T=57 CO Reports SG levels and method of feed. The CO will have to take manual control of the Downcomer control valves (using the Downcomer Valve controllers SGN-FIK-113 and SGN-FIK-1123 or on the DFWCS screen) and feed the Steam Generators.

Evaluator Note: CO does not need to diagnose the Tave failure May report RCS Tc.

Reports SG pressure. SG pressures should be controlled by the SBCS in automatic.

May report containment pressure and status of Radiation Monitoring.

May report containment temperature and containment pressure.

CRS (Continuing in the SPTAs)

7. Determine that RCS Heat Removal acceptance criteria are met by the following:
a. Check that at least one Steam Generator meets BOTH of the following conditions:
  • Level is 35% WR or more
  • Feedwater is restoring or maintaining level 45 - 60% NR Evaluator Note: Due to Tave failing low on the trip, the CO will have to take manual control of feedwater to feed the SGs.
b. Check that Tc is 560 - 570°F.
c. Check that steam generator pressure is 1140 - 1200 psia.
8. Determine that Containment Isolation acceptance criteria are met by the following:
a. Check that Containment pressure is less than 2.5 psig.
b. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
  • No valid containment area radiation monitor alarms or unexplained rise in activity
  • No valid steam plant activity monitor alarms or unexplained rise in activity
9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:
a. Check that containment temperature is less than 117°F.
b. Check that containment pressure is less than 2.5 psig.

Diagnoses SGTR, enters 40EP-9EO04, Steam Generator Tube Rupture.

205 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 7 Event

Description:

Tave fails low Time Position Applicants Actions or Behavior 206 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 8 Event

Description:

SGTR Time Position Applicants Actions or Behavior T=67 CRS The CRS performs the following per 40EP-9EO04, Steam Generator Tube Rupture;

  • Confirms the diagnosis of a SGTR by directing the performance of the SFSC, directing an operator to open the SG sample valves, and directing Chemistry to perform the abnormal occurrence checklist.
  • Ensures the event is being classified. This is normally the task of the Shift Manager.
  • Opens the placekeeper and enter the EOP entry time.
  • If pressure drops below SIAS setpoint, directs an operator to check that SIAS is actuated.
  • If SIAS has actuated, directs an operator to check HPSI and LPSI pumps started, and adequate SI flow per Appendix 2.
  • If pressure remains below the SIAS setpoint, directs an operator to ensure one RCP is stopped in each loop.
  • Directs an operator to monitor any operating RCP per Appendix 16.

Evaluator Note: The following two steps should have been done in the AOP for Excessive RCS leakrate

  • Directs the CO to place the post filter blower in the THRU FILTER MODE.
  • Directs the CO to place SBCS valves 1007 and 1008 in OFF.

Directs the CO to commence a cooldown to Th of less than 540 °F using the SBCS and to perform the RCS cooldown log.

Evaluator Note: The CRS may hold a tailboard to discuss the operators responsibilities during the cooldown (cooldown, depressurize and reset MSIS setpoints)

  • If steaming to atmosphere, informs Radiation Protection.
  • Directs the RO to depressurize the RCS to <1135 psia, approximately equal to ruptured SG pressure, and within the P/T limits.
  • Directs the RO to throttle HPSI when Safety Injection Throttle criteria are met.
  • Directs the crew to reset the MSIS setpoints.
  • Determines the most affected SG by verifying parameters.
  • Directs Isolation of the Ruptured SG.

Critical Task - Initiate actions to cooldown and isolate the affected steam generator 207 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 8 Event

Description:

SGTR Time Position Applicants Actions or Behavior RO When pressure is < SIAS setpoint, ensures SIAS actuated and HPSI, LPSI pumps running. Verifies SIAS actuated and equipment is actuated by visually verifying equipment or checking SESS panel.

Trips one RCP in each loop when pressure remains below the SIAS setpoint using the handswitches on B04. (Trips 1A and 2A or trips 1B and 2B RCPs).

  • RCP1A - handswitch RCN-HS-1
  • RCP1B - handswitch RCN-HS-2
  • RCP2A - handswitch RCN-HS-3
  • RCP2B - handswitch RCN-HS-4 Monitors running RCP parameters per Appendix 16.

Depressurizes the RCS when directed using main sprays on B04 and/or aux sprays on B03.

  • Main sprays - controller RCN-PIC-100 or RCN-PIK-100 in manual
  • Aux Sprays - CHA-HS-205 and/or CHB-HS-203 Throttles HPSI when Safety Injection throttle criteria are met using the following handswitches on B03. Throttles HPSI one valve at a time.

Train A Train B SIA-HS-617 SIB-HS-616 SIA-HS-627 SIB-HS-626 SIA-HS-637 SIB-HS-636 SIA-HS-647 SIB-HS-646 Resets MSIS setpoints as the cooldown occurs as directed using the LO SG PRESS RESET pushbuttons on B05.

CO May manually initiate SIAS/CIAS if directed by CRS.

Evaluator Note: The next two steps may have been performed during the Abnormal Operating Procedure for the SGTL.

Ensures post filter blower is in THRU FILTER MODE when directed using handswitch ARN-HS-19.

Places SBCS valves 1007 and 1008 are in OFF when directed using SGN-HS-1007 and SGN-HS-1008.

Performs a cooldown using SBCS (probably using SGN-PIK-1001, but any other SBCS valve is acceptable) to get Th less than 540 °F when directed Resets MSIS setpoints using the LO SG PRESS SETPOINT RESET pushbuttons on B05 as the cooldown occurs as directed.

Isolates the affected SG when directed by ensuring the following are closed:

Component Handswitch - all on B06 unless noted otherwise.

ADV 184 SGA-HIC-184A 208 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 1 Event No: 8 Event

Description:

SGTR Time Position Applicants Actions or Behavior ADV 178 SGB-HIC-178A MSIVs SGA-HS-251 or SGB-HS-253 (only need to push one button)

MSIV bypass Lights above SGA-HS-169A FWIVs SGA-HS-174C and SGB-HS-132C (need to push both buttons)

Downcomer valves SGA-HS-172 and SGB-HS-130 Blowdown Containment Isolations SGA-HS-500P and SGB-HS-500Q (on B07)

Steam Trap Isolations SGA-HS-1133 and SGB-HS-1135 SG Safety Valves LEDs above ADV controllers AF A Steam Supply SGA-HS-134A AF A Feedwater Isolations AFB-HS-34A and AFC-HS-36A Scenario Normal end point is when the SG is isolated.

209 of 248 NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 3 Op-Test No: 2009 Examiners: Operators:

Initial Conditions: IC # 101 (50% power, MOC)

Turnover: Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD. The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP. During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing. Maintenance is investigating at this time. The B MFP is tagged out. The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps. Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days. Train B is the protected train. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete.

Risk Management Action Level is Green. Unit 2 is supplying the Aux Steam cross-tie header.

Event Malf. No. Event Type* Event Description No.

1 N Swap stator cooling pumps.

None CO 2 doED ZLS037271DS_W1 C The UV-1 LOV relay for PBA-S03 will fail requiring the crew to doRP ZLSAAC01ALOP1_W1 CO/SRO address the alarm response procedures and the CRS to address Tech mf AN_1A03D1 (TS) Specs.

3 cmTRRC03RCNPT100X_1 C RCN-PT-100X fails high requiring the crew to address the Alarm RO/SRO Response procedure and select the unaffected channel.

4 cmBKED05NBNS02A_5 C Loss of NBN-S02 causing a loss of Turbine Cooling Water due to the CO/SRO A Turbine Cooling failing to auto start. The CRS should address 40AO-9ZZ12, Degraded Electrical, 40AO-9ZZ03, Loss of Cooling water or the alarm response procedure to start the standby TC pump.

Other 4.16 kV loads will also be lost.

5 imf mfTH01B (TS)

A RCS leak will develop requiring the CRS to enter 40AO-9ZZ02, RO/SRO Excessive RCS leakrate.

6 imf mfTC13 M Main Turbine Trip causes a reactor trip after a short time period due to imf mfMS16 ALL failure of the SBCS Q.O. block circuitry (reactor trips on high pressurizer pressure).

7 imf cmTRMS02SGNPT1024_4 I After the reactor trips, a failure of Main Steam pressure transmitter CO/SRO SGN-PT-1024 will require the CO to take manual actions to control heat removal with either the SBCS or ADVs.

8 mmf mfTH01B k:4 f:10 M RCS Leak degrades to a LOCA and one Containment Spray Pump imf cmMVRH03SIAUV672_6 ALL will fail to auto start while the other Containment Spray Header imf cmCPRH05SIBP03_5 C isolation will fail to open. HPSI B pump trips and the A DG does mmf mfTH01B f: 10 RO/SRO not come up to speed.

rfEG20 Critical Task - Initiate Containment Spray flow.

9 imf mfED10A C After the CRS enters the LOCA procedure, a loss of PBA-S03 will RO/SRO occur due to a fault on a SU transformer. This will cause a loss of the only running HPSI pump (other pump tripped when started). The CRS will transition to the FRP to restore power to PBA-S03.

Critical Task - Energize PBA-S03 from NBN-X04 to supply power to the A HPSI pump.

End The scenario is terminated when the PB bus is energized and HPSI has point started.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 210 of 248

Appendix D Scenario Outline Form ES-D-1 Supplemental Turnover Plant conditions:

Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD.

Risk Management Action Level is Green.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP.

During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing.

Maintenance is investigating at this time. The B MFP is tagged out.

Planned shift activities:

Normal Shiftly surveillances are complete.

The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.

Note:

The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.

NUREG-1021, Revision 9 211 of 248

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 has been at 50% power for the past 4 days. The core is at 250 EFPD.

Risk Management Action Level is Green.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

Alarm Window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

The unit had been in a SNOW outage and stopped the power increase due to a possible issue with the B MFP.

During the startup of the B MFP it had high vibration and high temperature on the outboard pump bearing.

Maintenance is investigating at this time. The B MFP is tagged out.

Planned shift activities:

Normal Shiftly surveillances are complete.

The crew is directed to shift the stator cooling water pumps after turnover to CEN-P01A running and CEN-P01B in standby to support electrical maintenance troubleshooting of a hot spot on the motor terminal connection of CEN-P01B. The Area Operator has been briefed and is standing by the stator cooling pumps.

NUREG-1021, Revision 9 212 of 248

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 1 Event

Description:

Swap Stator Cooling Pumps Time Position Applicants Actions or Behavior T=0 CO Performs prerequisite - Stator Cooling System is in Operation with CEN-P01B running and CEN-P01A in standby.

Pushes CEN-HS-29B, Auto Start Test button until CEA-P01A starts as indicated by the amber light above the handswitch (CEN-HS-30) on B07.

Places CEN-HS-30 to START Checks that the pump running red light is on.

Stops CEN-P01B using handswitch CEN-HS-37.

Pushes CEN-HS-29B, Auto Start Test button until CEA-P01B starts as indicated by the amber light above the handswitch (CEN-HS-37) on B07 Stops CEN-P01B using CEN-HS-37.

Checks discharge pressure is normal (~140 psig as read locally on CEN-PI-4).

Evaluator Note: The CRS may decide not to perform the auto start test of the B CE pump due to the problem with the terminal hot spot.

CRS Directs the CO to start the A Stator Cooling Water Pump and stop the B Stator Cooling Water Pump.

Evaluator Note: The CRS may decide not to perform the auto start test of the B CE pump due to the problem with the terminal hot spot.

213 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 2 Event

Description:

PBA-S03 LOV relay 727-1 fails Time Position Applicants Actions or Behavior T=10 RO Addresses Alarm on B01 using 41AL-1RK1A window 3D and performs the following:

  • Determines alarm is not valid by observing PBA-S03 voltage indicator PBA-EI-S03.
  • Determines that the 727-1 relay tripped by observing PBA-S03 undervoltage white indicating lights on panel B01.
  • Investigate the cause of the undervoltage condition. Possible cause and indications of the condition include:

o A low voltage condition on PBA-S03 o Excessive load on PBA

  • Informs CRS that alarm response procedure states if an undervoltage relay is malfunctions, then place the undervoltage relay in Bypass.
  • Informs the CRS to evaluate Tech Specs and to refer to the following LCOs:

o 3.3.7 o 3.8.1 o 3.8.2 CRS Addresses Tech Specs and enters LCO 3.3.7 Condition A which requires bypassing the channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

May refer to Control System drawing to determine which UV relay to bypass.

Directs CO to place Train A LOP1 relay UV-1 in bypass (using 40OP-9SA01) at the BOP-ESFAS cabinet.

CO Places Train A UV-1 in bypass using 40OP-9SA01 by performing the following:

  • Prerequisites o Ensures Applicable LCO has been reviewed (may mark this complete if CRS has discussed this).

o CRS Permission obtained (direction to do this is adequate) o Verifies redundant module in the other Train is not in bypass by a visual inspection of the Train B BOP-ESFAS Cabinet.

214 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 2 Event

Description:

PBA-S03 LOV relay 727-1 fails Time Position Applicants Actions or Behavior

  • Procedure o Ensures the sequencer is not in Auto Test by verifying the Manual half of the Manual/Auto button at the BOP-ESFAS cabinet is lit.

o Performs a lamp test on Train A BOP-ESFAS cabinet using the Lamp Test button.

o Determine the same relay on the redundant train module is NOT in bypass.

o Place a checkmark by module to be placed in service in the procedure.

o Bypass the UV-1 relay on Train A BOP-ESFAS Cabinet by:

Place Bypass key in key slot for UV-1 module Turn the key clockwise 1/4 turn or until the Bypass light comes on.

o Requests Independent Verification of bypass.

215 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 3 Event

Description:

RCS controlling pressure (RCN-PT-100X) fails high.

Time Position Applicants Actions or Behavior T= 20 RO Receives alarms on B04 and addresses the Alarm Response Procedure 40AL-9RK4A (Windows 1B and 1A)

  • Actions from Window 1B alarm response o Checks pressurizer pressure by observing RCN-PT-100X and 100Y on RCN-PR-100 o Selects the unaffected channel (Y) using handswitch RCN-HS-100 on B04.

o Closes the heater breaker for the proportional heaters using the following handswitches:

RCN-HS-100-1 RCN-HS-100-2 o Ensures ability to maintain pressure with available heaters.

  • Actions from Window 1A alarm response are the same as above.

CRS When RO reports failed instrument, directs the RO to select the unaffected Channel Y.

Determines the affect of the failed instrument (affects the SBCS such that there will be bias from a high RCS pressure condition applied to the SBCS). This may be discussed by another member of the crew.

If RCS pressure lowers to less than 2130 psia, the CRS should address Tech Spec 3.4.1 condition c.

216 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 4 Event

Description:

Loss of NBN-X02 Time Position Applicants Actions or Behavior T=27 RO The RO addresses alarms on B01 (Window 6C) (this may be done after the CO addresses the cooling water pumps due to manpower limitations).

Refers CRS to 40AO-9ZZ12, Degraded Electrical.

CO Addresses alarms on B07 (numerous windows)

Notices no Turbine Cooling Water Pump is running.

Starts the B TC pump (due to failure to auto start).

Addresses the Normal chiller by starting the A Normal Chiller and restarting the B Normal Chiller (tripped due to low NC flow).

CRS Enters 40AO-9ZZ12, Degraded Electrical.

Checks that all of the following pumps are operating as needed:

  • Nuclear Cooling Water Pump A
  • Turbine Cooling Water Pump A
  • Plant Cooling Water Pump A The crew notices that TC Pump A is not running and the CRS enters 40AO-9ZZ03, Loss of Cooling Water to start the TC A Pump (or the CO may use the alarm response procedure to start the pump).

Addresses that the following have been lost:

Condensate Pump C Heater Drain Pump A Normal Chiller C NC Pump B TC Pump B PW Pump B Directs the CO to address the Normal chillers by starting the A Normal chiller and restarting the B Normal Chiller (tripped due to low NC flow when the pumps shifted).

217 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 5 Event

Description:

RCS Leak Time Position Applicants Actions or Behavior T= 40 RO An operator discovers that the RCS leakrate is increasing by either observing ERFDADS leakrate number increasing, letdown flow lowering, pressurizer level lowering, or by RU alarms.

The Reactor Operator may start the standby charging pump if directed by the CRS.

The Reactor Operator may isolate letdown if directed by the CRS.

The Reactor Operator performs an RCS leakrate per Appendix B of 40AO-9ZZ02 by placing the VCT makeup in Manual and waiting for ERFDADS to calculate leakrate.

CO Responds to RMS Alarms and informs CRS of actions/information.

May monitor Containment sump levels using RDN-LI-410 and humidity /

temperature Yokogawa record 1JMNTJR001 (Both on B07).

May monitor Containment Pressure using PPS indicators on B-05.

CRS Evaluator Note: If the CRS decides to trip the reactor due to the leak, have the driver insert Event 6 before the crew trips the reactor.

The CRS enters 40AO-9ZZ02, Excessive RCS Leakrate and performs the following:

1. Directs starting all available charging pumps if pressurizer level is lowering.
2. Direction isolate letdown if all charging pumps are running and pressurizer level is lowering.
3. If all charging pumps are running, letdown is isolated, and pressurizer level is lowering, direct a Reactor Trip.
4. Ensure the event is being classified.

Evaluator note: The CRS should tell the Shift Manager to classify the event.

5. Ensure compliance with LCO 3.4.14, RCS operation leakage. The CRS should enter condition A of LCO 3.4.14 (reduce leakage in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />).
6. Directs chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist.
7. Notifies RP that an RCS leak exists.
8. Directs the RO to determine the leakrate.

218 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 5 Event

Description:

RCS Leak Time Position Applicants Actions or Behavior Evaluator note: Leakrate should be about 50 gpm.

9. Evaluate plant parameters to attempt to identify the source of the leakage.
10. Directs an operator to walkdown charging and letdown piping.
11. Continue efforts to locate and isolate the leak.

219 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 6 Event

Description:

Main turbine trip.

Time Position Applicants Actions or Behavior T= 55 Crew Crew recognizes a Main Turbine trip has occurred.

Crew may recognize that the SBCS did not quick open which results in a reactor trip.

Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.

CRS May direct a manual reactor trip Evaluator Note: There is only a short time period between the Turbine Trip and the automatic trip on High Pressurizer pressure; therefore the CRS may not have time to direct a manual reactor trip.

220 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 7 Event

Description:

Standard Post Trip Actions/ Failure of SGN-PT-1024.

Time Position Applicants Actions or Behavior T= 55 CRS Directs the crew through the Standard Post Trip Actions (see next event for steps).

RO May report Reactivity (may be done by the CO).

Will report the status of the Electric Plant. All vital and non-vital busses are energized Reports Pressurizer level and RCS subcooling.

Reports Seal injection and Nuclear Cooling Water available to the RCPs.

Reports RCS pressure.

Reports all RCPs operating, loop T, and RCS subcooling.

May report RCS Tc (usually done by the CO).

May report containment pressure and status of Radiation Monitoring.

May report containment temperature and containment pressure.

CO May report Reactivity.

Reports status of the Main Turbine and Generator output breakers.

Reports SG levels and method of feed. Should be with MFPs in RTO.

May report RCS Tc.

Reports SG pressure. Due failure of SGN-PT0-1024, the CO will have to control SG pressure with the SBCS valves in manual (SGN-PIK-1001), the SBCS Master Controller in manual, or may use ADVs by giving the ADVs two permissive and using the controller below for the applicable ADV.

ADV 184 SGA-HIC-184A ADV 178 SGB-HIC-178A ADV 185 SGB-HIC-185A ADV 179 SGB-HIC-179A May report containment pressure and status of Radiation Monitoring.

May report containment temperature and containment pressure.

221 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 8 Event

Description:

RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time Position Applicants Actions or Behavior T= 7 Crew Notices RCS leak rate has increased dramatically.

minutes after reactor trip RO Secures RCPs on either CSAS or loss of subcooling.

Recognize that there is no Containment Spray flow after the Containment Spray Actuation Signal. The Train A CS valve fails to open and cannot be opened. The Train B CS pump fails to auto start.

Starts the Train B Containment Spray Pump using SIB-HS-6 on B02.

Critical Task - initiate CS flow.

May report DG A not running at rated speed after SIAS starts the DG. (The crew may attempt to override and raise the speed of the DG which will be unsuccessful.)

May report HPSI B has an 86 lockout (this may be done at end of SPTA briefing)

CO Shifts SG pressure control to the ADVs if using the SBCS.

Shifts SG feed to Auxiliary Feedwater due to the MSIS.

AF A AF B AF N SGA-HS-134A AFB-HS-10 AFA-HS-11 SGA-HS-138A AFB-HS-30A CTA-HS-1 AFA-HS-32A AFB-HS-31A CTA-HS-4 AFC-HS-36A AFB-HS-34A SGN-FIK-1133 or AFA-HS-37A AFB-HS-35A SGN-HS-1143 AFC-HS33A SGN-FIK-1123 or SGN-HS-1145 CRS Evaluator Note: These actions may vary depending on where the CRS is in the procedure when the RCS leakrate is increased. See actions at this section.

Implements procedure 40EP-9EO01, Standard Post Trip Actions.

1. Open the placekeeper and enter the EOP Entry Time.
2. Determine that Reactivity Control acceptance criteria are met by the following:
a. Check that reactor power is dropping.
b. Check that start-up rate is negative.
c. Check that ALL full strength CEAs are inserted.
3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
a. Check that the Main Turbine is tripped.
b. Check that the Main Generator output breakers are open.
c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:

222 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 8 Event

Description:

RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time Position Applicants Actions or Behavior

  • All vital and non-vital AC buses are powered
  • All vital and non-vital DC buses are powered
4. Determine that RCS Inventory Control acceptance criteria are met by the following:
a. Check that Pressurizer level meets BOTH of the following:
  • 10 - 65%
  • Trending as expected to 33 - 53%
b. Check that the RCS is 24°F or more subcooled.
c. Check that BOTH of the following are in service to all RCPs.
  • Seal injection
  • Nuclear Cooling Water
5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
  • Pressurizer pressure is 1837 - 2285 psia
  • Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.

5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.

6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
  • At least one RCP is operating
  • Loop T is less than 10°F
  • RCS is 24°F or more subcooled
7. Determine that RCS Heat Removal acceptance criteria are met by the following:
a. Check that at least one Steam Generator meets BOTH of the following conditions:
  • Level is 35% WR or more
  • Feedwater is restoring or maintaining level 45 - 60% NR
b. Check that Tc is 560 - 570°F.
c. Check that steam generator pressure is 1140 - 1200 psia.
8. Determine that Containment Isolation acceptance criteria are met by the following:
c. Check that Containment pressure is less than 2.5 psig.
d. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
  • No valid containment area radiation monitor alarms or unexplained rise in activity
  • No valid steam plant activity monitor alarms or unexplained rise in activity
9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:

223 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 8 Event

Description:

RCS Leak degrades/Failure of Containment Spray/DG A fails to reach rated speed/ HPSI B trips Time Position Applicants Actions or Behavior

a. Check that containment temperature is less than 117°F.
b. Check that containment pressure is less than 2.5 psig.

When the LOCA gets large the CRS may repeat some SPTA steps.

  • If time permits, may direct an operator to manually initiate a SIAS/CIAS/MSIS/ and or CSAS
  • Directs RO to ensure proper SIAS actuation
  • Directs RO to stop RCPs on CSAS or loss of subcooling.
  • Directs RO to isolate RCP seal bleedoff.
  • Direct CO to shift feedwater to Auxiliary Feed and use ADVs to control SG pressure.
  • Ensures adequate CS flow.

Diagnoses a LOCA and proceeds to 40EP-9EO03.

224 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 9 Event

Description:

Loss of PBA-S03 Time Position Applicants Actions or Behavior T= When Crew Recognizes a LOP has occurred by alarm on B05 and other plant indications.

the CRS enters the LOCA procedure RO 1. Determines that PBA-S03 has lost power.

2. Determines that his only running HPSI pump has lost power (this may be pointed out by another crew member).
3. CRS/RO may attempt to override and increase speed on the A DG. This will not be successful
4. Overrides and opens HPB-UV-2 on B02.
5. Places the B Hydrogen Analyzer in service.
6. Energizes PBA-S03 from NBN-S04 by closing breaker PBA-S03L using handswitch PBA-SS-S03K (Synch Switch) and PBA-II-S03K (breaker switch) when directed by the CRS.
7. Starts HPSI A using SIA-HS-1 or may wait for pump to start automatically.

CRS Determines a loss of a safety function has occurred and transitions to the Functional Recovery Procedure.

1. Ensures the event is being classified
2. Enters the EOP entry time.
3. If pressurizer pressure remains below the SIA S setpoint, ensure one RCP is stopped in each loop or if < 24 °F, ensure all RCPs are stopped.
4. If any RCPs are operating, directs the RO to perform Standard Appendix 16, RCP Trip Criteria.
5. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.
6. If CIAS has actuated, directs the RO to override and open HPB-UV-2 on B02.
7. Directs the RO to place the Hydrogen analyzers in service.
8. Identifies the success paths to be used to satisfy each safety function.

RC-1 HR-2 MVDC-1 CI-1 MVAC Jeopardized CTPC-2 IC Jeopardized CCGC-1 225 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 3 Event No: 9 Event

Description:

Loss of PBA-S03 Time Position Applicants Actions or Behavior PC-3

9. Directs an operator to perform the Safety Function Status Check for those success paths in use.
10. Performs MVAC-1 (first jeopardized Safety Function) and directs the RO to close PBA-S03K to energize PBA-S03 from the train B ESF Transformer (NBN-X04).
11. The CRS directs the RO to start the A HPSI pump or may wait for HPSI to start automatically (~ 60 seconds after bus is powered).

Critical Task - X-tie PB busses to restore HPSI.

End Point Scenario Normal end point is when the HPSI A is started after PBA-S03 is energized.

226 of 248 NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: 4 Op-Test No: 2009 Examiners: Operators:

Initial Conditions: IC #100, (100% power, MOC).

Turnover: Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days. Train B is protected equipment. The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a Vibration Technician standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps.

Normal Shiftly Surveillances are complete. Risk Management Action Level is Yellow. PC is NOT recircing the RWT. Unit 2 is supplying the Aux Steam cross-tie header.

Event Malf. No. Event Type* Event Description No.

1 None N Crew Shifts running Plant Cooling Water Pumps.

CO/SRO 2 imf cmTRCV19RCALT110X_4 I The Train A Pressurizer Level Transmitter will fail. The crew should RO/SRO address the Alarm response procedure and select the Train B level (TS) transmitter. The CRS should address Tech Specs.

3 imf cmTRRX12SGCLT1123C_4 I A SG level transmitter fails low. The crew addresses the alarm CO/SRO response procedure and places the correct parameter in bypass. The (TS) CRS addresses Tech Specs.

4 imf mfFW17B C The B MFP will trip requiring the CRS to enter 40AO-9ZZ09, RO/CO/SRO RPCB (Loss of Feedpump).

5 imf mfFW15A M- ALL After the crew stabilizes power, the A MFP will experience high imf mfFW17A vibrations. The crew should address the alarm response procedure and determine they have to trip the reactor and trip the MFP.

6 imf mfRD03I C On the trip, two CEAs will stick out. This will require the crew to imf mfRD03M RO/SRO borate.

7 imf mf FW21B C 5 minutes into the SPTAs, the B AFW pump will trip. The CO imf mfFW23 CO/SRO should shift to the N AFW pump. If the examinee attempts to use AFA-P01 it will not come up to speed.

8 imf cmCPFW07AFNP01_3 M When the CRS enters the Reactor Trip procedure, AFN-P01 discharge ALL pressure will degrade. The CRS should realize that a LOAF has occurred and transition to the FRP to feed the Steam Generators with the condensate pumps.

Critical Task - Take actions to align and initiate condensate to a steam generator.

End The scenario is terminated when the crew has established feed to one point SG with a condensate pump.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH.

Normal Shiftly Surveillances are complete.

Risk Management Action Level is Yellow.

Train B is the protected equipment.

NUREG-1021, Revision 9 227 of 248

Appendix D Scenario Outline Form ES-D-1 PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.

Note:

The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.

NUREG-1021, Revision 9 228 of 248

Appendix D Scenario Outline Form ES-D-1 Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is at 250 EFPH.

Normal Shiftly Surveillances are complete.

Risk Management Action Level is Yellow.

Train B is the protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration tech standing by at the pump to take vibrations on the A PW pump. The area operator has been briefed and is standing by the PW pumps. The area operator also has an approved Confined Space Entry form.

NUREG-1021, Revision 9 229 of 248

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 1 Event

Description:

Crew shifts running Plant Cooling Water Pumps.

Time Position Applicants Actions or Behavior T=0 CO Starts PW pump A using PWN-HS-5 on B07.

Directs AO to check pump running with no unusual noise or vibration.

Checks motor current decays to less than 137 amps.

Directs the AO to close PWN-HCV-12, PWN Pump B discharge valve When PWN-HCV-12 is closed, stops PW Pump B using PWN-HS-6.

Checks pressure alarm is clear and pressure returns to normal.

Directs AO to open PWN-HCV-12.

Directs AO to inspect PW Pump B to ensure no rotation.

230 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 1 Event

Description:

Crew shifts running Plant Cooling Water Pumps.

Time Position Applicants Actions or Behavior 231 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 2 Event

Description:

Train A Pressurizer Level instrument fails low Time Position Applicants Actions or Behavior T=5 RO Addresses the alarms on B04 (Windows 1A and 2B)

1. Verifies the controlling channel (RCA-LT-110X) has failed low
2. Selects Channel Y on RCN-HS-100 (Level Control Selector Channel X/Y) and RCN-HS-100-3 (Heater Control Selector Level Trip Channel X/Y)
3. Closes the proportional heater breakers by going to ON on handswitches RCN-HS-100-1 and RCN-HS-100-2.

CRS Addresses Tech Specs:

Enters LCO 3.3.10 (Post Accident Monitoring) condition A and LCO 3.3.11 (Remote Shutdown Panel) condition A. Both require restoration of the function within 30 day.

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Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 3 Event

Description:

SG #2 Channel C level transmitter failure Time Position Applicants Actions or Behavior T=12 CO Addresses the alarm response procedure

1. Compares SG #2 level instrumentation and determines Channel C has failed low.
2. May recommend bypassing the affected channel to the CRS.
3. May inform the CRS that Tech Specs 3.3.1, 3.3.5, 3.3.10 and 3.3.11 may be affected.
4. Bypasses the affected parameters (8, 18 and 19) as directed by the CRS.

CRS Addresses Tech Specs

1. Enters LCO 3.3.1 (Reactor Protection System (RPS) Instrumentation -

Operating) condition A and LCO 3.3.5 (Engineered Safety Feature Actuation System (ESFAS) Instrumentation) condition A which both require bypassing or tripping the affected channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. Refers to the bases for LCO 3.3.1 or LCO 3.3.5 to determine which instruments need to be bypassed.

Evaluator Note: LCO 3.3.10 is not applicable because it only requires 2 of the 4 channels and LCO 3.3.11 are not applicable for this channel because this is not a channel monitors at the Remote Shutdown panel.

3. Directs the CO to bypass Steam Generator #2 Level Low (RPS) and Steam Generator #1 and #2 Level Low (ESFAS) per the LCO bases.

233 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 4 Event

Description:

Trip of the B MFP Time Position Applicants Actions or Behavior T=22 Crew Addresses the alarms and diagnoses the trip of the B MFP.

CRS Enters 40AO-9ZZ09 (RPCB-Loss of Feedpump) and performs the following:

1. Enters the AOP entry time
2. Checks that A RPCB - Loss of Feedpump has actuated and CEA subgroups 4, 5, and 22 have inserted.
3. Checks that Main Turbine Setback-Runback has lowered Main Turbine load to 65% or less.
4. Checks that no CEAs are deviating by greater than 6.6 inches if ANY CEA Reg Groups are below the Transient Insertion Limits.
5. May direct an operator to perform Appendix D, Status Check RPCB Loss of Feedpump (normally done by the STA).
6. Directs the CO to restore and maintain SG levels 45-60% NR.
7. Checks that RRS is adjusting CEAs to restore Tave/Tref + 3°F.
8. If condenser hotwell level is less than 41 inches, directs an operator to restore level to 41 inches or more.
9. Directs an operator to remove RPCB from service by pushing the AUTO ACTUATE OUT OF SERVICE and the TEST RESET pushbuttons.
10. Directs the CO to perform a lamp test to ensure the LOAD LIMITING light illuminates.
11. Directs the CO to lower the load limit potentiometer until the LOAD LIMITING light comes on.
12. Directs CO to raise Speed Bias on the operating Main Feedwater Pump to zero or more
13. Directs an operator to place CEDMCS is Manual Sequential when CEA motion is only required for Xenon Buildup
14. Directs an operator to monitor ASI.
15. Directs an operator to start boron equalization of the pressurizer.
16. Directs the CO to adjust FWCS DP to stabilize feedwater (if necessary)

RO 1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by CO).

2. Checks for CEA deviation.
3. Checks that RRS is adjusting to maintain Tave/Tref + 3°F.
4. Places CEDMCS in Manual Sequential using the CEDMCS Mode Select Switch on B04.
5. Commences Pressurizer Boron Equalization by performing the following:

234 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 4 Event

Description:

Trip of the B MFP Time Position Applicants Actions or Behavior

a. Override and energize all pressurizer backup heaters:

RCA-HS-100-4 RCB-HS-100-5 RCN-HS-100-6 RCN-HS-100-7 RCN-HS-100-8 RCN-HS-100-9

b. Lower the setpoint on RCNPIC-100, Pressurizer Pressure Controller to 2220 psia.
6. May perform Appendix D (Status Check of 40AO-9ZZ09)
7. May remove RPCB from service by pushing the TEST RESET and AUTO-ACTUATE OOS pushbuttons on the RPCB module on B04.

(May be done by CO)

CO 1. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).

2. Ensures the Main Turbine Setback-Runback has reduced Main Turbine load to < 65% (~ 890 MWs).
3. Monitors SG levels to ensure they are restoring and maintaining 45-60% NR.
4. May check that RPCB has occurred with subgroups 4, 5, and 22 inserted (may be done by RO).
5. Restore hotwell level to > 41 inches if necessary.
6. May remove RPCB from service by pushing the TEST RESET and AUTO-ACTUATE OOS pushbuttons on the RPCB module on B04.

(May be done by RO)

7. Performs a lamp test on the LOAD LIMITING light and then lowers the load limit potentiometer on B06 to cause the LOAD LIMITING light to come on.
8. Monitors ASI.
9. Ensures operating Feedpump bias is at zero at the FP Speed controller.
10. Ensures FWCS DP is maintaining feedwater steady.

235 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 4 Event

Description:

Trip of the B MFP Time Position Applicants Actions or Behavior 236 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 5 Event

Description:

High Vibration on the A Main Feedpump (Trip initiator)

Time Position Applicants Actions or Behavior T=35 CO Addresses the high vibration alarm on B06.

1. Checks FWPT A vibration on recorder MTN-YR-301 on B07.
2. Checks FWPT A vibration on the plant computer.
3. Contacts vibration group to take local readings.
4. Directs an operator to check the FWPT A for vibration
5. When the vibration is greater than 5 mils and the AO reports the Feedpump is vibrating, informs the CRS that the alarm response directs a trip of the FWPT.
6. Trips the A MFP using the red trip pushbutton (FTN-HS-51) on B06.

CRS When the CO reports that the alarm response directs a trip of the FWPT A, the CRS should direct a reactor trip and a trip of the FWPT A.

RO Trips the reactor when directed by the CRS using the four RTSG breaker pushbuttons on B05 (SBA-HS-1, SBB-HS-2, SBC-HS-3, and SBD-HS-4).

237 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 6 Event

Description:

Standard Post Trip actions with 2 CEAs stuck out.

Time Position Applicants Actions or Behavior T= 45 Crew The crew commences performance of the SPTAs.

CO 1. Reports that power is lowering, negative startup rate and more than one CEA stuck out.

2. Checks the Main Turbine is tripped and the generator output breakers are open.

Evaluator note: Since the RO is starting a boration, the CRS may use the CO to continue with the SPTAs until the RO gets the boration started, therefore the following 6 steps may be completed by the CO until the RO takes over.

3. Reports the status of the electric plant (may be performed by the RO) -

all vital and non-vital busses are energized.

4. Checks pressurizer level is 10-65% trending to 33-53%.
5. Checks that the RCS is 24°F or more subcooled.
6. Checks that Seal Injection and Nuclear Cooling water is available to all RCPs.
7. Checks RCS pressure 1837-2285 trending to 2225-2275 psia.
8. Determines Core Heat Removal is met by at least one RCP running, Loop T less than 10°F, and RCS is 24°F or more subcooled.
9. Uses AFB to feed the Steam Generators since both Main Feedwater pumps are tripped.
10. Checks Tc is 560-570°F.
11. Checks Steam Generator Pressure is 1140-1200 psia.

Evaluator note: The following steps may be performed by the RO or CO.

12. Checks Containment Pressure < 2.5 psig and checks RMS for alarm or trends.
13. Checks Containment temperature < 117°F and Containment pressure <

2.5 psig.

Evaluator Note: Due to the failure of RCN-PT-100X lowering the modulate signal, the SBCS will cycle valves when the permissive is automatically removed unless the CO takes manual control.

RO Commences boration of the RCS using Standard Appendix 103.

(basic steps the RO will perform)

4. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.
5. Selects the Target makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) (minimum 5000 gallons).
6. Starts the boration as follows:
a. Place CHN-HS-210 in the BORATE position.
b. Depress the Reset pushbutton - the left pushbutton on the 238 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 6 Event

Description:

Standard Post Trip actions with 2 CEAs stuck out.

Time Position Applicants Actions or Behavior totalizer/counter module (Micro-Motion).

c. Depress the Start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).

When boration is started, he will continue with the SPTAs as noted in the CO actions above.

CRS Implements procedure 40EP-9EO01, Standard Post Trip Actions.

1. Open the placekeeper and enter the EOP Entry Time.
2. Determines that Reactivity Control acceptance criteria are not met because of the stuck out CEAs and directs the RO to borate using Standard Appendix 103.
3. Determine that Maintenance of Vital Auxiliaries acceptance criteria are met by the following:
a. Check that the Main Turbine is tripped.
b. Check that the Main Generator output breakers are open.
c. Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:
  • All vital and non-vital AC buses are powered
  • All vital and non-vital DC buses are powered
4. Determine that RCS Inventory Control acceptance criteria are met by the following:
a. Check that Pressurizer level meets BOTH of the following:
  • 10 - 65%
  • Trending as expected to 33 - 53%
b. Check that the RCS is 24°F or more subcooled.
c. Check that BOTH of the following are in service to all RCPs.
  • Seal injection
  • Nuclear Cooling Water
5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following:
  • Pressurizer pressure is 1837 - 2285 psia
  • Pressurizer pressure is trending as expected to 2225 - 2275 psia 5.2 IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated.

5.3 IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop.

6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following:
  • At least one RCP is operating
  • Loop T is less than 10°F
  • RCS is 24°F or more subcooled
7. Determine that RCS Heat Removal acceptance criteria are met by the following:
a. Check that at least one Steam Generator meets BOTH of the 239 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 6 Event

Description:

Standard Post Trip actions with 2 CEAs stuck out.

Time Position Applicants Actions or Behavior following conditions:

  • Level is 35% WR or more
  • Feedwater is restoring or maintaining level 45 - 60% NR.
b. Checks that Tc is between 560 and 570°F.
c. Check that steam generator pressure is 1140 - 1200 psia.
8. Determine that Containment Isolation acceptance criteria are met by the following:
e. Check that Containment pressure is less than 2.5 psig.
f. REFER TO Appendix 7, List of EOP Radiation Monitors and check BOTH of the following conditions:
  • No valid containment area radiation monitor alarms or unexplained rise in activity
  • No valid steam plant activity monitor alarms or unexplained rise in activity
9. Determine that Containment Temperature, Pressure, and Combustible Gas Control acceptance criteria are met by the following:
a. Check that containment temperature is less than 117°F.
b. Check that containment pressure is less than 2.5 psig.

Diagnoses a Reactor Trip.

240 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 7 Event

Description:

Trip of B AFW pump Time Position Applicants Actions or Behavior If the CO uses AFN first, then go to event 8.

T= 50 (~ 5 RO Receives a SESS alarm on AFW pump B and informs the CRS and CO.

minutes into the SPTAs after CO reports feeding SGs)

CRS Directs the CO to use AFN-P01 to feed the SGs.

CO 1. Determines the AFW pump B has tripped on an 86 lockout.

2. Commences feeding the SGs with AFW pump N by performing the following:
a. Opening both suction valves for AFN-P01 using handswitches CTA-HS-1 and CTA-HS-2) on B06.
b. Taking manual control of the Downcomer Flow control valves (SGN-FIK-1113 and SGN-FIK-1123) and closing the flow valves or closing the Downcomer block valves (SGN-HS-1142 and SGN-HS-1144)
c. After the suction valves are open, starting AFN-P01 using handswitch AFA-HS-11.
d. Start feeding the SGs by using the Downcomer flow controllers (SGN-FIK-1113 and SGN-FIK-1123) in manual or by using the Downcomer bypass valves (SGN-HS-1143 and SGN-HS-1145).

Examiner Note: If the examinee attempts to use AFA-P01, it will not come up to speed (malfunction in the simulator setup).

Op-Test No: _2009_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicants Actions or Behavior T= after CO 1. Notices that the feed to the SGs has degraded or stopped.

CRS

2. Informs the CRS of a loss of all feed.

enters 241 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicants Actions or Behavior Reactor Evaluator Note: See next page for continuance of CO actions after CRS enters Trip EOP the Functional Recovery Procedure..

CRS Determines a loss of safety function has occurred and transitions to the Functional Recovery Procedure.

12. Ensures the event is being classified
13. Enters the EOP entry time.
14. Directs the RO to perform Standard Appendix 16, RCP Trip Criteria.
15. Ensures the SG sample valves are open and directs chemistry to perform the Abnormal Occurrence Checklist.
16. Directs the RO to place the Hydrogen analyzers in service.
17. Identifies the success paths to be used to satisfy each safety function.
a. RC-2 e. HR-1 Jeopardized
b. MVDC-1 f. CI-1
c. MVAC-1 g. CTPC-1
d. IC-1 h. CCGC-1
e. PC-1
18. Directs an operator to perform the Safety Function Status Check for those success paths in use.
19. Proceed to HR-1 since it is the only jeopardized Safety Function.
20. Directs the RO to stop all RCPs.
21. Directs the CO to close all Blowdown Containment Isolation valves and SG sample valves.
22. Directs the CO to perform Standard Appendix 44, FEEDING WITH THE CONDENSATE PUMPS.

CO When directed performs Standard Appendix 44, FEEDING WITH CONDENSATE PUMPS.

1. Selects a SG to feed (will probably discuss this with the CRS).
2. Open both Downcomer Isolation valves for the selected SG.

SG #1 selected SG #2 selected SGA-UV-172 SGA-UV-175 SGB-UV-130 SGB-UV-135

3. Place the Downcomer Control valve in manual and close the Downcomer control valve.

SG #1 selected SG #2 selected SGN-FV-1113 SGN-FV-1123

4. If SG Downcomer Block valve will be used to feed the SG, open the 242 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicants Actions or Behavior Downcomer block valve SG #1 selected SG #2 selected SGN-HV-1142 SGN-HV-1144

5. Close the Downcomer Bypass valve.

SG #1 selected SG #2 selected SGN-HV-1143 SGN-HV-1145

6. Fast close ALL Economizer FWIVs (both SGs) using pushbuttons.

SGA-UV-174 SGA-UV-177 SGB-UV-132 SGB-UV-137

7. If using the Downcomer Bypass Valve to feed the SG, ensure Downcomer Block Valve is closed.

SG #1 selected SG #2 selected SGN-HV-1142 SGN-HV-1144

8. Ensure one set or more of the HP feedwater heater isolation valves are open. (HV-73 and HV-101 or HV-74 and HV-102)
9. Ensure both of the FWPTs are tripped.
10. Check both FWPT Miniflow valves are closed (FWN-FV-1 and FWN-FV-2)
11. Ensure one or more of the FWPT Discharge valves are open (FWN-HV-31 and/or FWN-HV-32).
12. Ensure one set or more of the LP Feedwater heater isolation valves are open (red lights lit on any of these handswitches - CDN-HS-214, CDN-HS-215, and/or CDN-HS-216).
13. Ensures a condensate pump is running by observing red light on above any of the three handswitches (CDN-HS- 11, 12, or 13).
14. IF RCS makeup is require then the CO will coordinates with the RO to start all available charging pumps, minimize letdown flow, Start one HPSI pump and open at least one HPSI Injection valve. The CO will probably discuss this step with the CRS.
15. IF a MSIS or SIAS not initiated, lower the setpoints for the MSIS or SIAS as the cooldown and depressurization continues using the LO SG PRESS SETPOINT RESET and the LO PXR PRESS SETPOINT RESET pushbuttons on B05. This will probably be done by both the RO and CO.
16. Perform Appendix 5, RCS and Pressurizer Cooldown Log.
17. Fast close the MSIVs on the selected SG using the pushbuttons on B06.

SG #1- SGA-HS-251 or SGB-HS-253 (only need to push one button)

SG #2- SGA-HS-250 or SGB-HS-252 (only need to push one button)

18. Lower the pressure in the affected SG to below the condensate pump discharge pressure using ADVs (SGA-HIC-184A, SGB-HIC-178A, SGB-HIC-185A, and/or SGA-HIC-179A) ion B06.

Evaluator Note: Per the Technical Guidelines for Standard Appendix 44, the 100°F/hr cooldown rate may be exceeded during steam generator depressurization and subsequent refill with condensate. Re-establishing Feedwater o recover heat removal capabilities has priority over the 243 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 Op-Test No: _2009_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicants Actions or Behavior consequences of over cooling.

19. Maintain the non-selected SG pressure < 1200 psia.
20. If the selected steam generator is dry then maintain feed flow rate of <

1000 gpm.

21. Initiates feed flow using the Downcomer Controllers or the Downcomer bypass valves.

Critical Task: Take actions to align and initiate condensate to a steam generator.

RO Performs Standard Appendix 16 for running RCPs.

Stops all RCPs when directed by the CRS (using RCN-HS-1, 2, 3 and 4 on B04).

Places the H2 Analyzers in service when directed by the CRS (by using HP-HS-1, 2, 7, 8, 9A, and 10A on B02).

May operate Aux Sprays using CHA-HS-205 or CHB-HS-203 on B03)

When the CO is ready to reduce the SG pressure for feed using condensate the RO may start available charging pumps (using handswitch CHA-HS216, CHA-HS-218A, and/or CHB-HS-217) minimize letdown using the PLCS master controller (RCN-LIC-110) on B04, start a HPSI pump (using handswitch SIA-HS-1 or SIB-HS-1), and open at least one HPSI injection valve when directed.

Train A valves Train B vales SIA-HS-617 SIB-HS-616 SIA-HS-627 SIB-HS-626 SIA-HS-637 SIB-HS-636 SIA-HS-647 SIB-HS-646 The RO may assist resetting MSIS and SIAS setpoints during depressurization of the Steam Generator using the LO SG PRESS RESET pushbuttons on B05.

The RO may assist controlling SG pressures while the CO performs standard Appendix 44.

End Point The scenario may be stopped when feedwater is established to one SG using condensate.

244 of 248 NUREG-1021, Revision 9

Appendix D Operator Actions Form ES-D-2 245 of 248 NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners: Operators: (SRO)

(ATC/RO)

(CO/BOP)

Initial Conditions: IC #100, (100% power, MOC). This is the as run scenario for one crew.

Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.

Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.

Event Malf. No. Event Type* Event Description No.

1 None N Shift Condensate Demineralizers.

CO/SRO 2 imf cmCNCV04CHNFIC243_2 I A seal injection controller will fail in automatic requiring the crew to RO/SRO take manual control of the controller.

3 imf cmCPCH03HCNA02A_6 C The A and C CEDM fans will trip requiring the CRS to enter 40AO-imf cmCPCH03HCNA02C_6 CO/SRO 9ZZ25, Loss of HVAC to start the B and D fans (which will fail to auto start).

4 imf mfRD02B R CEA 15 drops completely into the core. Crew enters 40AO-9ZZ11.

RO/CO/SRO Crew begins a 20% downpower. SRO enters LCO 3.1.5 Condition A (TS) and LCO 3.2.4 Condition A.

5 imf mfTH06A C A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO 40AO-9ZZ02, Excessive RCS leakrate.

(TS) 6 imf mfRD02L M - ALL Another CEA slips into the core. This will cause a reactor trip signal mfRD12A but an ATWS will occur. This will require the crew to open the mfRP04A breakers supplying the CEDM MG sets.

Critical Task - Crew will insert all CEAs.

mfRP04C 7 mfRX01 I After the trip Tave will fail low requiring the CO to manually feed the CO /SRO SGs.

8 mmf mfTH06A M-ALL The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.

Critical Task - Initiate actions to cooldown and isolate the affected steam generator End The scenario is terminated when the crew commences affected steam point generator has been isolated or at the discretion of the lead examiner

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

NUREG-1021, Revision 9 246 of 248

Appendix D Scenario Outline Form ES-D-1 Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.

The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

Note:

The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.

NUREG-1021, Revision 9 247 of 248

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance.

Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.

The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

NUREG-1021, Revision 9 248 of 248

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2009 Examiners: Operators: (SRO)

(ATC/RO)

(CO/BOP)

Initial Conditions: IC #100, (100% power, MOC).

Turnover: Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance (estimated return to service is 3 days). The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service.

The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by. PC is NOT recircing the RWT. Normal Shiftly Surveillances are complete. Risk Management Action Level is Green.

Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-tie header.

Event Malf. No. Event Type* Event Description No.

1 None N Shift Condensate Demineralizers.

CO/SRO 2 imf cmCNCV04CHNFIC243_2 I A seal injection controller will fail in automatic requiring the RO/SRO crew to take manual control of the controller.

3 imf cmCPCH03HCNA02A_6 C The A and C CEDM fans will trip requiring the CRS to enter 40AO-9ZZ25, Loss of HVAC to start the B and D fans (which imf cmCPCH03HCNA02C_6 CO/SRO will fail to auto start).

4 imf mfRD02B R CEA 15 drops completely into the core. Crew enters 40AO-RO/CO/SRO 9ZZ11. Crew begins a 20% downpower. SRO enters LCO 3.1.5 (TS) Condition A and LCO 3.2.4 Condition A.

5 imf mfTH06A C A Steam Generator Tube leak occurs requiring the crew to enter CO/SRO 40AO-9ZZ02, Excessive RCS leakrate.

(TS) 6 imf mfRD02L M - ALL Another CEA slips into the core. This will cause a reactor trip mfRD12A signal but an ATWS will occur. This will require the crew to mfRP04A open the breakers supplying the CEDM MG sets.

mfRP04C Critical Task - Crew will insert all CEAs.

7 mfRX01 I After the trip Tave will fail low requiring the CO to manually feed the SGs.

CO /SRO 8 mmf mfTH06A M-ALL The SGTL will degrade on the trip. The CRS will diagnose a SGTR at the completion of the SPTAs. The crew performs a cooldown and isolates the affected Steam Generator.

Critical Task - Initiate actions to cooldown and isolate the affected steam generator End The scenario is terminated when the crew commences affected point steam generator has been isolated or at the discretion of the lead examiner

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3

Appendix D Scenario Outline Form ES-D-1 Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

Note:

The crew will walk down the control boards and assume the shift and then perform a reactivity brief prior to the commencement of the evaluation.

NUREG-1021, Revision 9 2 of 3

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD.

The Emergency Seal Oil Pump is tagged out for emergent maintenance.

Risk Management Action Level is GREEN.

Train B is protected equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header Equipment out of service:

The alarm window on Board 6 is due to the Emergency Seal Oil Pump being tagged out for emergent maintenance. Estimated return to service is 3 days.

Planned shift activities:

Normal, shiftly surveillances are complete.

The crew needs to place the F Condensate Demin in Service and remove the E Condensate Demin from service. The F Condensate Demineralizer was rinsed right before turnover. The Demin operator has been briefed and is standing by.

NUREG-1021, Revision 9 3 of 3

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