Text

2009-11-Draft Operating Test
	ML101960320
Person / Time
Site:	Palo Verde
Issue date:	11/02/2009
From:	Garchow S; NRC Region 4
To:	;
References
	50-528/09-11, 50-529/09-11, 50-530/09-11
	Download: ML101960320 (275)
	v • d • e

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 1JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 2 1. SIMULATOR SETUP:

A. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

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: Copy of 40OP-9ZZ16, RCS Drain Operations Rev 66 Appendix D and E.

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 3 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 103'1" 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) Train "A" SDC flow is: Actual RCS level 0800 102 ft. 6 in. 4500 gpm ______________ 0815 101 ft. 10 in. 4000 gpm ______________

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 4 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.

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 5 JPM START TIME:

STEP CUE STANDARD 1.

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:

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 (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 6 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):

JPM STOP TIME:

NORMAL TERMINATION POINT

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 7

Increase in HUT level should be _____ 1.9 ( + 0.1 ft) _____ ft.

Time Indicated level from LG -752 (Train A) 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 8 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.

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)

RA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 9 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 103'1" 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) Train "A" SDC flow is: Actual RCS level 0800 102 ft. 6 in.

4500 gpm ______________ 0815 101 ft. 10 in.

4000 gpm ______________

CANDIDATE RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 10JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 11 2. SIMULATOR SETUP:

F. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

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 40DP-9OP02, Conduct of Shift Operations, Rev 46

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 12 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE: SPECIAL CONSIDERATIONS:

ALL JPM's You may use any source of information normally available. 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 03/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1.

Operator #1 can / cannot stand the position because ________________________________

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 13_____________________________________________________________________________. Operator #2 can / cannot stand the position because ________________________________ _____________________________________________________________________________.

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.

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 14 JPM START TIME:

STEP CUE STANDARD 1. Obtain 40DP-9OP02, Conduct of Shift Operations.

Obtain 40DP-9OP02, Conduct of Shift Operations. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

The examinee determines that #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 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months 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 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months . SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 15 ANSWER KEY

Operator #1 can / cannot stand the position because

(Circle one)

Operator #1 did not complete 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months 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 0.0167 hours 9.920635e-5 weeks 2.283e-5 months .

ANSWER KEY

RA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 16 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.

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)

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 17 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 03/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 18JPM BASIS INFORMATION TASK: 1290310301 Perform a Tech Review of a Permit TASK STANDARD: Tech Review a Permit and determine three errors and any actions to be taken 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 19 3. SIMULATOR SETUP:

K. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

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: 40DP-9OP29, Permit and Tagging Process Rev 35, Drawing 01-E-DWB-01 Drawing 01-M-DWP-02

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 20 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. Determine who should make the corrections to 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.

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 21 JPM START TIME:

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.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

Identifies three (3) errors on the permit. Examinee determines the following inaccuracies/inadequacies. Tag 2 is the wrong circuit breaker (breaker is for the "A" pump) Tag 5 has wrong position (OPEN) for the discharge valve. Tag 7 has right valve but wrong system DS. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Determines who should make the corrections to the permit.

Examinee returns Permit for correction to anyone (the person who performs the Tech Review cannot make the corrections.) SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 22 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.

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)

RA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 23 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. Determine who should make the corrections to the permit.

CANDIDATE CANDIDATE Power Block Permit and Tagging 40DP-9OP29 Page 50 of 66 Rev. 35 Appendix B Page 2 of 4 PERMIT FORM FACILITY NO. _____Unit 1____ PERMIT NO ____1-110909-1

______________

SYSTEM_____

DW_______ EQ I.D. _______

1M-DWN-P05B

_______ EQ DESCRIPTION Demin Water Pump B REASON FOR PERMIT: ____ Isolate the pump due to severe pump seal leak______________________ ________________________________________________________________________________________________________ ________________________________________________________________________________________________________ ________________________________________________________________________________________________________

EQUIP CONDITIONS REQUIRED FOR WORK (circle) SPECIAL INSTRUCTIONS De-energized Yes/No ________________________________________

Depressurized Yes/No ____________

None_______________________ Continuously Vented Yes/No ________________________________________ Drained Yes/No ________________________________________ Purged Yes/No ________________________________________ Isolated Yes/No ________________________________________

SWMS Search Yes/No ________________________________________

TSCCR Yes/No TSCCR No. ____N/A______________________

PREPARED BY:_______________________________________ EXT:_________

_ DATE:_________

_ TIME:_________ TAG PLACEMENT AUTHORIZED:______________________ EXT:_________

_ DATE:__________ TIME:_________ (responsible supervisor) EQ CONDITIONS ESTABLISHED:_______________________ EXT:_________

_ DATE:__________ TIME:_________ (operator) TAG REMOVAL AUTHORIZED:________________________ EXT:_________

_ DATE:__________ TIME:_________ (responsible supervisor) PERMIT CANCELLED:________________________________ EXT:_________

_ DATE:__________ TIME:_________ (responsible supervisor)

REQUESTOR/EXT (PRINT) WORK DOCUMENT SIGNATURE/DATE/TIME OPS - Unit 1 SM / X1206 N/A Tech Rev.__________________________ Authorized:_________________________ Accepted:___________________________

CANDIDATE Released:___________________________

FOR NRC EXAM ONLY CANDIDATE CANDIDATE Tag Assignment Sheet Unit No: __1____ Permit No: __1-110909-1 Page __1__ of __1__

TAG PLACEMENT TAG REMOVAL Tag No. Tag Color Equipment ID. Hang Order Component Position Placed By Verified By Restore Order Restore Position Restored By 1 Yellow 1J-DWN-HS29B, Handswitch for DWN-P05B 1

Breaker tagged 2 Red 1E-NHN-M1318, 480VAC Breaker for DWN-P05B 2 OPEN 3 Red 1P-DWN-V042 DWN-P05B Suct Valve 3 CLOSED 4 Red 1P-DWN-V043 DWN-P05B Recirc Valve 3 CLOSED 5 Red 1P-DWN-V051 DWN-P05B Disch Valve 3 OPEN 6 Yellow 1P-DWN-V353 DWN-P05B Vent Valve 4

Open as needed to vent 7 Yellow 1P-DSN-V355 DWN-P05B Drain Valve 4

Open as needed to drain

Special instructions on yellow tag

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 27JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 28 4. SIMULATOR SETUP:

P. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

Q. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

13. N/A 14. 15. 16. R. SPECIAL INSTRUCTIONS: None S. REQUIRED CONDITIONS: None 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: ____________________

5. SPECIAL TOOLS/EQUIPMENT: Survey map 75DP-9RP01 Radiation Exposure and Access Control Rev 16 Calculator

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 29 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 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 posting should this area have? Check only those that apply to the area you will need to access. 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. 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

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 30 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.

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 31 JPM START TIME:

STEP CUE STANDARD 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?

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. 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 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months ).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

What type of radiation posting should this are have? Check only those that apply to the area you will need to access.

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 32 STEP CUE STANDARD 3.

What are the requirements to enter this area? Check only those that apply to the area you will need to

access? Examinee should check the following: Continuous RP coverage or Stay Times. Briefing by RP Single PCs SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 33 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 Declared Fertile Woman.) ANSWER ___44 minutes or 0.73 hour8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months s_______________

2) What type of posting should this area have? Check only those that apply to the area you will need to access. 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. 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 34 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. 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)

RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 35 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.

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.

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 RA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 36 [e1]Comment [e1]:

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 37JPM BASIS INFORMATION TASK: 1290190102, Ensure Compliance with Tech Spec 1290600302, Ensure Performance of Operations Repetitive tasks TASK STANDARD: Interpret data, take actions, determine Tech Specs LCO Condition K/A: 2.1.25 K/A RATING: RO:

3.9 SRO: 4.2 K/A: 2.1.20 K/A RATING: RO:

4.6 SRO: 4.6 K/A: K/A RATING: RO:

SRO: APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

40DP-9OP06 (Rev 107) Operations Department Repetitive Task Program SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 08/09/2007 Revised By: Alan Malley Date: 04/22/2009 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 38 5. SIMULATOR SETUP:

U. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

V. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

17. N/A 18. 19. 20. W. SPECIAL INSTRUCTIONS: NONE X. REQUIRED CONDITIONS: NONE 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: ____________________

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 39 6. SPECIAL TOOLS/EQUIPMENT: Copy of Tech Specs Calculator Attached completed copy of Appendix EC003, up to step 16.0 with the following values:

o 1.0 inch change (decrease) in surge tank level o 195 minute elapsed time duration o 1.0 degree F change in temperature o Total leak rate (before adjustment) of 0.578 gph o Adjusted leak (incorrect value) of 0.588 gph 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 contam inated, airborne, or high radiation areas.

ALL JPM's You may use any source of information normally available.

INITIATING CUE:

You are the Control Room Supervisor in Unit 3. Given the following: Operations Repetitive task Appendix EC003 in progress, performed up to Step 16.0. Mode 1, 100% power

Your tasks for this JPM are to review Appendix EC003 including:

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 40 Identify (1) one error (Non-clerical, not typos) Take required actions, if any Determine any applicable LCO and condition. (Do NOT list any cascaded Tech Specs).

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 41 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 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 42 JPM START TIME:

STEP CUE STANDARD 1.

Evaluates data from Appendix EC003 and Independently verifies Adjusted leak rate. Examinee reviews the data and determines that the Adjusted leak rate is incorrect. (should be 0.68 gph) Note to Examiner: At step 15 the correct addition of 0.10 gpm should have been 0.678 gpm, not 0.588 (top row of blocks). SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

Determines Adjusted leak is >

0.63gph. Examinee reviews the data and determines that the leak rate exceeds 0.63 GPH and requires actions. (listed below in following steps)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Take Required actions for leak rate > .63 gph. Declare 'A' Train EC inoperable Examinee declares A Train EC Inoperable.

SAT / UNSAT Comments (required for UNSAT):

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 43 STEP CUE STANDARD 4. Initiate a PVAR for HVAC to quantify and investigate the leak rate. Another operator will generate a work mech.

Examinee accesses the appropriate work request screen and begins entering information. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 5. Notify the System (ext 6690) or Maintenance (ext 3541 or 1846)

Engineer. The System Engineer has been informed.

Examinee simulates calling one of the Engineers to report the results of the task performance. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 6.

Determines any applicable LCO and applicable actions. Examinee determines that entry into LCO 3.7.10 condition 'a' is required. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 44 ANSWER KEY

Error: 1. Leak rate is wrong at step 16. Should be .678 NOT .578 Action(s) to be taken:

1. Declare Train 'A' EC inoperable

2. Initiate a PVAR for HVAC to quantify and investigate the leak rate

3. Notify the System (ext 6690) or Maintenance (ext 3541 or 1846) Engineer.

EXAMINER NOTE: Action 2. and 3. are not required for satisfactory completion of this JPM (Examinee may just state perform step 17.2)

LCO and condition:

1. LCO 3.7.10 condition 'a' ANSWER KEY

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 45 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 001 08/09/2007 3 Updated JPM to match procedure 002 04/22/2009 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. 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)

SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 46 INITIAL CONDITIONS INITIATING CUE:

You are the Control Room Supervisor in Unit 3. Given the following: Operations Repetitive task Appendix EC003 in progress, performed up to Step 16.0. Mode 1, 100% power Your tasks for this JPM are to review Appendix EC003 including: Identify (1) one error (Non-clerical, not typos) Take required actions, if any Determine any applicable LCO and condition. (Do NOT list any cascaded Tech Specs). Use the table below to document your answers.

Error: 1. Action(s) to be taken:

LCO and condition:

CANDIDATE SA 1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 47 SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 04/22/08 48JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 49 6. SIMULATOR SETUP:

Z. IC#: N/A (May be performed in the simulator or classroom, NO setup required) AA. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

21. N/A 22. 23. 24. BB. SPECIAL INSTRUCTIONS: None CC. REQUIRED CONDITIONS: None 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 of Conduct of Shift Operations, 40DP-9OP02, Rev 46 TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 50SPECIAL CONSIDERATIONS:

ALL JPM's 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 Verde's 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 _________________ ___________________________________________________________________.

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 51 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 03/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1.

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 52 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 53 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 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 54 JPM START TIME:

STEP CUE STANDARD 1. Obtain 40DP-9OP02, Conduct of Shift Operations.

Obtain 40DP-9OP02, Conduct of Shift Operations. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

The examinee determines that #1 cannot stand the shift and the reason. The examinee states the following reason for operator #1 not being able to stand shift.

Operator #1 did not complete 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months 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 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 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months . SAT / UNSAT Comments (required for UNSAT):

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 55 STEP CUE STANDARD 4.

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).

The examinee determines that Unit 1 would not have the required number of 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. Either answer is acceptable. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 56 ANSWER KEY

1. Operator #1 can / cannot stand the position because

Operator #1 did not complete 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months 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 0.0167 hours 9.920635e-5 weeks 2.283e-5 months .

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 (3 rd Reactor Operator from Unit 3) to fill a reactor operator position in Unit #1.

Could call in another reactor operator to man Unit #1.

ANSWER KEY

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 57 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 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)

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 58 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 Verde's 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 _________________ ___________________________________________________________________.

CANDIDATE

SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 59 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 3. 02/12/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 02/13/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 2 02/14/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 2. 03/13/2009 Stood 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months shift as 3 rd Reactor Operator in Unit 3. 03/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 03/31/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 01/21/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 3 rd Reactor Operator in Unit 1. 02/25/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1. 02/26/2009 Stood 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as 2 nd Reactor Operator in Unit 1.

CANDIDATE SA 2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 60 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 61JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 62 7. SIMULATOR SETUP: EE. IC#: N/A FF. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

25. N/A 26. 27. 28. GG. SPECIAL INSTRUCTIONS: None HH. REQUIRED CONDITIONS: None 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 Tech Specs Copy of print 01-E-SIB-0001 Copy of 40OP-9PB01

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 63INFORMATION 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 JPM's You may use any source of information normally available.

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 64 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 (SIA-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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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) (if applicable)

Completion time(s) Enter TLCO condition(s) (if applicable) Completion time(s) 1315 Event 1 1427 Event 2 SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 65 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 66 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

Determine the applicable LCO(s) / TLCO(s) and completion times, if any for time 1315.

The examinee determines the applicable LCO is LCO 3.5.3 condition B and the completion time is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

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.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 67 ANSWER KEY

At time: Enter LCO condition(s) (if applicable)

Completion time(s) Enter TLCO condition(s) (if applicable)

Completion time(s) 1315 Event 1 LCO 3.5.3 condition B 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months N/A N/A 1427 Event 2 LCO 3.5.3 condition A 7 days TLCO 3.5.201 Condition A 7 days ANSWER KEY

SA 3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 68 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 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)

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 69 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 (SIA-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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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) (if applicable)

Completion time(s) Enter TLCO condition(s) (if applicable) Completion time(s) 1315 Event 1 1427 Event 2 CANDIDATE JPM BASIS INFORMATION SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/20/08 70 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 71 8. SIMULATOR SETUP:

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

29. N/A 30. 31. 32. LL. SPECIAL INSTRUCTIONS: None MM. REQUIRED CONDITIONS: None NN. 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: 75DP-9RP01, Radiation Exposure and Access Control REP# 9-9999Z Survey map of SDC HX room. Calculator

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 72INFORMATION 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 JPM's You may use any source of information normally available.

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 73 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.

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 74 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 75 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 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 76 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 received. (Based on the 15 minute stay time estimate given in the cue.)

Determines 285 mrem will be received. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Determine maximum stay time before the first administrative hold point is exceeded Determines that max stay time 44 minutes. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 4.

Determine RP Coverage requirements per the REP.

Determines that the REP will require continuous RP coverage or stay time. SAT / UNSAT Comments (required for UNSAT):

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 77 STEP CUE STANDARD 5.

Determine which operator will perform the Independent Verification Determines that the operator 3 will perform 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

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 78 ANSWER KEY

Task # Task 3 Expected Dose 285 millirem 44 minutes Max Stay time before first admin hold point Continuous RP coverage or Stay time.

RP coverage required by the REP for this task Operator 3 Which operator should perform 2 nd check

ANSWER KEY

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 79 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. 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)

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 80 INITIATING CUE:

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.

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 81 Task # Expected Dose Max Stay time before first admin hold point RP coverage required by the REP for this task Which operator should perform 2 nd check SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 82 Page 1 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS Location: ALL RCAs except Containment Job Scope: Perform Routine Operations tasks including: Tours, Inspections, Tagging, Valve Line-ups a nd Venting and Draining Limitations:

NO VHRA ENTRY NO Entry > 5,000 mREM/hr at 12 Inches. NO Containment Entry in Plant Modes 1-2 Survey Location Rose Rates (mRem/hr)

Contamination (dpm/100 Sq. cm)

Additional Information Survey or A/S ID # All areas (Excluding LHRAs)

*

Review current work area survey data

Locked High Radiation Areas (LHRAs) ** ** ** Work area dose rates as communicated in formal pre-job briefing and recorded in RP logbook. Page 2 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS Task SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 83 # Task / Job Evolution Dosimetry, Protective Clothing and Respiratory Requirements RP Coverage Requirements Pre-Job Brief Required 1 ROUTINE OPS TASKS - No contaminated system venting /

draining to include: HRA ENTRY RP AUTHORIZATION REQUIRED EPD CA entry - Full Set HCA / HPCA entry - Double Set Respirator Protection per TEDE ALARA Evaluation (attached as appropriate) Intermittent YES (For HRA entry) 2 OPS TASKS - Contaminated system venting / draining Hose Connect / Disconnect Vent / Drain to include: HRA ENTRY RP AUTHORIZATION REQUIRED EPD CA entry - Full Set HCA / HPCA entry - Double Set Respirator Protection per TEDE ALARA Evaluation (attached as appropriate) Intermittent RPL to determine RP coverage

for hose disconnect /

connect evolutions YES SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 84 (For HRA entry) Page 3 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS Task # Task / Job Evolution Dosimetry, Protective Clothing and Respiratory Requirements RP Coverage Requirements Pre-Job Brief Required 3 OPS TASKS (LHRAs) - includes contaminated system venting /

draining Hose Connect / Disconnect Vent / Drain Other tasks as authorized by RPL LHRA ENTRY FORMAL PJB AND RP AUTHORIZATION REQUIRED EPD CA entry - Full Set HCA / HPCA entry - Double Set Respirator Protection per TEDE ALARA Evaluation (attached as appropriate) Continuous YES 4 Hot Spot Flushing Hot Spot monitoring Connecting / Disconnecting hoses RP coverage Other tasks as authorized by RPL.

HRA ENTRY RP AUTHORIZATION REQUIRED SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 85 EPD CA entry - Full Set HCA / HPCA entry - Double Set Respirator Protection per TEDE ALARA Evaluation (attached as appropriate) Intermittent RPL to determine RP coverage

for hose disconnect /

connect evolutions YES (For HRA entry) Page 4 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS Task #

Task / Job Evolution Dosimetry, Protective Clothing and Respiratory Requirements RP Coverage Requirements Pre-Job Brief Required 5 Hot Spot Flushing (LHRAs) Hot Spot monitoring Connecting / Disconnecting hoses RP coverage Other tasks as authorized by RPL.

LHRA ENTRY FORMAL PJB AND RP AUTHORIZATION REQUIRED EPD CA entry - Full Set HCA / HPCA entry - Double Set SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 86 Respirator Protection per TEDE ALARA Evaluation (attached as appropriate) Continuous in LHRA YES Page 5 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS E.P.D. Settings Task

Minimum Dose Available Required for Entry Dose Alarm Dose Rate Alarm E.P.D.

Chirp Rate 1 25 mREM 25 mREM 500 mREM/hr One Chirp / 0.1 mREM 2 25 mREM 25 mREM 500 mREM/hr One Chirp / 0.1 mREM 3 50 mREM 50 mREM 1000 mREM/hr One Chirp / 0.1 mREM 4 25 mREM 25 mREM 500 mREM/hr One Chirp / 0.1 mREM 5 50 mREM 50 mREM 1000 mREM/hr One Chirp / 0.1 mREM Page 6 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS SPECIAL INSTRUCTIONS Contact RP prior to each RCA entry. Contact RP prior to opening any container in the RCA yard. Review current radiological survey data for work are prior to entry. EPD setpoints may be adjusted as determined prudent by RPL based on review of work plan and radiological conditions. RPL to document all setpoint adjustments in RP electronics. Half Set P.C.s may be worn for a C.A. entry as authorized by RP. RP may relax protective clothing requirements for minor tasks with low probability of personnel contamination (e.g. reach-in to contaminated area to wipe-up oil from pump skid).

SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 87 PREREQUISITES Prior to installing a hose connection and/or connecting a hose to contaminated system, both the hose connection and the hose shall be visibly marked as "Radioactive Material" (painting items purple is acceptable), or labeled, "Internal Contaminations". ALARA / ENGINEERING CONTROLS Securely connect drain/flush hoses at floor drain Stand by in low does "Cold Area" when not actively involved in job. RADIOLOGICAL HOLD POINTS Notify RP prior to and upon completion of connecting/disconnecting drain/vent lines to/from contaminated systems - RP authorization required. Notify RP prior to venting and draining contaminated systems. Notify RP prior to opening any package/container marked or labeled as "Radioactive material". Notify RP prior to obtaining any RadWaste samples. No LHRA Entry on task 1,2, or 4. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months decay time required prior to venting/draining any system containing fresh RCS water. RADIOLOGICAL SURVEILLANCE LHRA entry requires RPL notification. Entries greater than or equal to 1,000 mREM/hr at 12 inches requires RPL authorization. Anticipated Job exposure of greater than or equal to 0.100 man-Rem requires RP Leader concurrence. Page 7 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS RADIOLOGICAL SURVEILLANCE Monitor dose rates along the vent and drain pathway, note changes due to movement of hot spots. Verify the "as-left" radiological conditions following venting / draining operation. Hoses that become externally contaminated shall be segregated for either decon or exclusive use in CA's. Survey hoses and fittings prior to disconnecting. Ensure (direct hook-up) drain covers are installed prior to hose hook up, and removed at completion of job. RP Technicians entering an HPCA / HCA to perform RP monitoring tasks with low probability of personnel SA 4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 88 contamination may wear a modified Double Set consisting of a Full Set with outer shoe covers and gloves. Page 8 of 8 Radiation Exposure Permit 9-9999Z Job

Description:

OPERATIONS ROUT INE SHIFT TASKS Estimated Man-Hours: 36,285.0 / year Estimated Man-REM: 1.632 / year JHES Category 2 Yes Alara Review Required: Reg Guide 1.16 Category Operations and Surveillance No Rep Type Standing Job Recipe Available REP APPROVALS Rep prepared on: 6/17/2009 @ 13:00 , by Joe Rptech ALARA review on: 6/17/2009 @ 14:20 , by Joe Supervisor REP approved on 6/17/2009 @ 14:20 , by Joe Supervisor (RP Section Leader) REP TERMINATION REASON: REP Terminated on , by SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 89JPM 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: 2.4.40 K/A RATING: RO:

2.7 SRO: 4.5 K/A: 2.4.41 K/A RATING: RO:

2.9 SRO: 4.6 K/A: 2.4.44 K/A RATING: RO:

2.4 SRO: 4.4 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) No 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 90 9. SIMULATOR SETUP: OO. IC#: N/A (May be performed in the simulator or classroom, NO setup required)

PP. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

33. N/A 34. 35. 36. QQ. SPECIAL INSTRUCTIONS: NONE RR. REQUIRED CONDITIONS: NONE SS. 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: ____________________

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 91 10. SPECIAL TOOLS/EQUIPMENT: Copy of EPIP-01, Satellite Technical Support Center Actions Copy of EPIP-99, EPIP Standard Appendices 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 JPM's You may use any source of information normally available.

INITIATING CUE:

The following events are occurring in Unit 1: You are the Control Room Supervisor. The Shift Manager has fallen and broken his leg in the Turbine Building and cannot make it to the Control Room. Emergency Notification for his injury has been completed. Twenty (20) minutes ago the following events occurred: A turbine trip has occurred. Annunciator panels on B01, B02, B04, B05 and B06 are not working.

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 92 The plant computer is not working. Perform the three following tasks:

1. List who should be assigned to implement the Emergency Plan until relieved.

2. List the Emergency Action Level that is met.

3. List the Classification of this event.

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 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 93 JPM START TIME:

STEP CUE STANDARD 1.

List who is responsible for classifying the event. . The examinee may refer to Section 2.0 of EPIP-01 or may answer without reference.

Answer: An Emergency Coordinator qualified individual (not the CRS). The answer may (but not required) include order of preference: Unaffected Unit Shift Manager or another qualified Emergency Coordinator. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

List the Emergency Action Level that is met.

The examinee refers to the Mode 1-4 classification chart and determines MS6is the correct Emergency Action Level (EAL).

Answer: MS6 - Inability to monitor a significant transient in progress.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

List the Classification of this event. Examinee use the Mode 1-4 classification chart to determines the classification.

Answer: Site Area Emergency (SAE) SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 94 ANSWER KEY

1. List who should be assigned to implement the Emergency Plan until relieved. An Emergency Coordinator qualified individual (not the CRS). The answer may (but not required) include order of preference: Unaffected Unit Shift Manager or another qualified Emergency Coordinator.

2. List the Emergency Action Level that is met. MS6 - Inability to monitor a significant transient in progress.

3. List the Classification of this event. Site Area Emergency (SAE)

ANSWER KEY

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 95 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 0 4/21/2009 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. 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)

SA 5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 96 INITIAL CONDITIONS INITIATING CUE:

The following events are occurring in Unit 1: You are the Control Room Supervisor. The Shift Manager has fallen and broken his leg in the Turbine Building and cannot make it to the Control Room. Emergency Notification for his injury has been completed. Twenty (20) minutes ago the following events occurred: A turbine trip has occurred. Annunciator panels on B01, B02, B04, B05 and B06 are not working. The plant computer is not working. Perform the three following tasks:

1. List who should be assigned to implement the Emergency Plan until relieved.

2. List the Emergency Action Level that is met.

3. List the Classification of this event.

Use this as your answer sheet.

CANDIDATE JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 97JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 98 10. SIMULATOR SETUP: TT. IC#: N/A UU. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

37. N/A 38. 39. 40. VV. SPECIAL INSTRUCTIONS: NONE WW. REQUIRED CONDITIONS: NONE XX. 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: A copy of Appendix E of 40AO-9ZZ19, Rev 22 Pictures of the inside of a 4.16 kV breaker cubicle.

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 99 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. There has been a loss of offsite power. No automatic start and loading of the Emergency Diesel Generators, or load shed has occurred. The CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 9 to manually start and load the "B" Diesel Generator (another operator performed steps 1-8 to position disconnect switches). 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 contains a time critical element.

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 100 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.

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 101 JPM START TIME:

STEP CUE STANDARD 1.

Step 9 of Appendix E:

IF Diesel Generator B is NOT running, THEN start Diesel Generator B using DGB-HS-031, Emergency Start - Simulated LOP (DG B Control Panel). When examinee simulates pressing DGB-HS-31 provide the following

cue: Diesel Generator B is running. Examinee realizes DG is not running from the initiating CUE and attempts to start Diesel Generator B. DGB-HS-031 SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2. Step 10 of Appendix E: 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. Provide the following cues as the examinee looks at the appropriate instrument: DG "B" Voltage is 4220 VAC DG "B" speed is 600 rpm Examinee identifies indication on Diesel Generator control cabinet.

NOTE: Time critical portion starts here. START Time ___________

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3. Step 11 of Appendix E:

Close breaker PBB-S04B, Diesel Generator PEB-G02, using the local control switch. Provide the following cue: The green light is "ON" and the red light is "OFF" on PBB-S04B.

Examinee simulates closing PBB-S04B by using the handswitch on the front of the breaker.

SAT / UNSAT Comments (required for UNSAT):

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 102 STEP CUE STANDARD 4. Step 11.1 of Appendix E: IF PBB-S04B did NOT close, THEN perform the following:

a. IF the breaker will be closed manually, THEN GO TO Step 12. of this appendix. Provide the following cue: The control room has directed you to close the breaker manually. 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.

Examinee goes to Step 12 of the appendix SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 5. Step 12 of Appendix E: IF breaker PBB-S04B, Diesel Generator PEB-G02, will be closed manually, THEN perform the following:

a. Check the closing spring indicates "CHGD".

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 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 103 STEP CUE STANDARD 6.

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.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 7.

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".

Another operator will complete this Appendix.

Examinee simulates closing PBB-S04B by using the handswitch on the front of the breaker.

NOTE: Time critical portion stops here.

STOP Time ___________

(Time should be less than 15 minutes from Start time). SAT / UNSAT Comments (required for UNSAT):

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 104 JPM STOP TIME:

NORMAL TERMINATION POINT

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 105 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.

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)

JP-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 106 INITIAL CONDITIONS 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 CRS directs you to complete Appendix E of 40AO-9ZZ19 beginning at step 9 to manually start and load the "B" Diesel Generator (another operator performed steps 1-8 to position disconnect switches). 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 contains a time critical element.

CANDIDATE JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 107JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 108 11. SIMULATOR SETUP: YY. IC#: N/A ZZ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

41. N/A 42. 43. 44. AAA. SPECIAL INSTRUCTIONS: NONE BBB.

REQUIRED CONDITIONS: NONE CCC.

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: Copy of 40EP-9EO10, Standard Appendices, Attachment 64-B, Rev 60 TASK CONDITIONS JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 109 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.

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 110 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.

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 111 JPM START TIME:

STEP CUE STANDARD 1. Step 1 of Attachment 64-B: Ensure Spray Pond Pump B is operating Spray Pond Pump B is running.

Examinee simulates calling control room for verification that SP Pump B is running.

SAT / UNSAT Comments (required for UNSAT):

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

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Step 3 of Attachment 64-B:

Perform the following: (EW Heat Exchanger B Room)

Close NCB-HCV-245, NC ISOLATION TO SFP HEAT EXCHANGER. NCB-HCV-245 stem lock is loosened. 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 112 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. 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. 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 113 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. 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". 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):

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 114 STEP CUE STANDARD Step 5 of Attachment 64-B:

Place NCN-FI-257, FPHX B OUTLET FLOWMETER, in service by performing the following:

Ensure the local equalizing valve is open.

The local equalizing valve will rotate freely in the closed 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-clockwise direction and has stopped moving. Close the equalizing valve.

The equalizing valve has been rotated clockwise and has stopped moving. 8.

Slowly open the local high side isolation valve The local high side isolation has been rotated in the counter-clockwise direction and has 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 115 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. 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):

JPM STOP TIME:

NORMAL TERMINATION POINT

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 116 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 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)

JP-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 117 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 JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 118JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 119 12. SIMULATOR SETUP: DDD. IC#: N/A EEE. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

45. N/A 46. 47. 48. FFF. SPECIAL INSTRUCTIONS: NONE GGG. REQUIRED CONDITIONS: NONE HHH. 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: ____________________

13. 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 120 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. 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.

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 121

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.

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 122 JPM START TIME:

STEP CUE STANDARD 1. Step 2. IF AFA-P01 will be used THEN perform the following: Adjust AFA-SK-52B, Auxiliary Feedwater Pump A Speed to minimum After the examinee simulates turning the speed potentiometer counter-clockwise 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 123 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. Wait 30 seconds and report the red light for SGA-UV-134 is on. 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 124 STEP CUE STANDARD When examinee looks at SG level transmitters provide the following

cue: Steam Generator Wide Range Levels are 30% WR. 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. 6.

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. Examine determines SG WR level and throttles open both SG Upstream valves. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 125 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 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)

JP-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 126 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 the 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 127JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 128 13. SIMULATOR SETUP:

III. 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) JJJ. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

49. 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. 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. When examinee directs AO to open bypass valves for 500S. (Valves are SGE-V293, SGE-V267, and SGE-VA33). The handswitch is taken to close to ensure the valve does not open when the malfunction is deleted. This ensures the examinee has to open the valve.

50. WHEN directed to close SGE-V293, SGE-V267, and SGE-VA33, wait a minute and report the valves closed.

51. 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.

KKK. SPECIAL INSTRUCTIONS: Reset to IC- 106 This JPM is set up to run with JS-2 for the 2009 NRC exam LLL. REQUIRED CONDITIONS: SG NR level approximately 65-75% NR. MMM. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Scenario "2009 JPM JS1" completed. 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: ____________________

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 129 14. 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:

A SGTR has occurred in SG #1. 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. If this is the first JPM of the set then ensure the examinee has been briefed.

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 130 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-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 131 JPM START TIME:

STEP CUE STANDARD 1. Step 1of Standard Appendix 33: Place SCN-HS-1, SG 1 Blowdown Path Selector in "OFF".

Examinee places SCN-HS-1 in "OFF". SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2.

Step 2 of Standard Appendix 33: Ensure SGA-UV-500P, SG 1 Common Upstream Isolation, is open. Examinee opens SGA-UV-500P.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Step 3 of Standard Appendix 33: 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: Select either valve. Examinee opens either SGE-HV-43 or SGE-HV-41.

SAT / UNSAT Comments (required for UNSAT):

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 132 STEP CUE STANDARD 4. Step 4 of Standard Appendix 33:

Check that SGB-UV-500Q is open. The examinee determines SGB-UV-500Q is closed and goes to the contingency step 4.1. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 5.

Step 4.1 of Standard Appendix 33:

Perform the following to open SGB-UV-500Q: a. Direct an operator to perform the following:

1) Unlock and open SGE-V293, "SGB-UV-500Q BYPASS HDR INLET ISOL VALVE"

2) Open SGE-V267, "SGB-UV-500Q BYPASS HDR 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 133 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 134 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%.

Examinee places SCN-HS-1 in "COND" and monitors SG level. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 135 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 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)

JS-1 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 136 INITIAL CONDITIONS INITIATING CUE:

A SGTR has occurred in SG #1. The CRS has directed you to reduce SG #1 level to 50% Narrow Range using Standard Appendix 33.

CANDIDATE JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 137JPM 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 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 138 14. SIMULATOR SETUP: NNN. IC#: 106 (For 2009 NRC exam only) OOO. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

52. None required PPP. SPECIAL INSTRUCTIONS: This is scheduled to run with JPM JS1 for the 2009 NRC exam. QQQ. REQUIRED CONDITIONS: Ensure Charging Pump B is NOT running RRR.

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: 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)

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 139 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.

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 140 Locked valves may be involved. No attempt will be made to actually operate any valves.

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 141 JPM START TIME:

STEP CUE STANDARD 1. Step 1 of Appendix 209: 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 closed NOTE: Examinee verifies Train B SDC is NOT in service and verifies SIB-UV-656 is closed.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2. Step 2 of Appendix 209:

IF it desired to align Charging Pump A, THEN perform the following:

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. 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

B). SAT / UNSAT Comments (required for UNSAT):

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 142 STEP CUE STANDARD 3. Step 3 of Appendix 209:

IF it desired to align Charging Pump B, THEN perform the following:

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: The area operator has completed Attachment 209-B.

Examinee ensures Charging Pump B in "PULL-TO-LOCK. Examinee directs an Area Operator to perform Attachment 209-B.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 4. Step 4 of Appendix 209:

IF it desired to align Charging Pump E, THEN perform the following:

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 B). SAT / UNSAT Comments (required for UNSAT):

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 143 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 examinee informs the CRS that Charging Pump B is aligned for Hot Leg Injection to HPSI Header B. SAT / UNSAT Comments (required for UNSAT):

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 144 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 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.

The examinee starts Charging Pump B. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 145 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON 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. 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)

JS-2 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 146 INITIAL CONDITIONS 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 147JPM 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: 04/17/2009 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 148 15. SIMULATOR SETUP: SSS. 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) TTT. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

53. None Required UUU. SPECIAL INSTRUCTIONS: This JPM is designed to run with JS-4 or JS-1 for the 2009 NRC exam. VVV. REQUIRED CONDITIONS: Ensure Charging Pump B is NOT running WWW. 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: Copy 40AO-9ZZ17, Inadvertent PPS Actuations, Appendix B If IC-103 is not available, then reset to IC-20 and manually initiate RAS on all four channels. 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) 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

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 149 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:

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.

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.

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 150 JPM START TIME:

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.

Examinee may perform lamp checks to ensure no other parameters are tripped. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2. Step 2 and 2.1 of Appendix B of 40AO-9ZZ17: 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. SAT / UNSAT Comments (required for UNSAT):

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 151 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 all four channels. (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 152 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. 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):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 153 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1 08/07/2009 6 Updated 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. 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)

JS-3 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 154 INITIAL CONDITIONS INITIATING CUE:

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-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 155JPM 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 Date: 04/17/2009 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 156 16. SIMULATOR SETUP: XXX. IC#: 103 (For 2009 NRC exam only) YYY. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

54. 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)

ZZZ. SPECIAL INSTRUCTIONS: This JPM is set to run with JS3 for the 2009 NRC exam AAAA. REQUIRED CONDITIONS: Containment pressure ~ 1.3 psig.

BBBB. 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: Copy of 40OP-9CP01, Containment Purge System, Section 5.0, Rev 18

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 157 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 today's date from 0700 to 2400 and is approved.

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.

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 158 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-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 159 JPM START TIME:

STEP CUE STANDARD 1. Step 5.3.1 of 40OP-9CP01: Ensure IA-VB47, Instrument Air Supply valve to the Containment Power Access Purge Isolation Valve CP-UV4A is closed. After examinee directs AO to close IA-VB47 provide the following Cue: IA-VB47, Instrument Air Supply valve to the Containment Power Access Purge Isolation Valve CP-UV4A, is closed.

Examinee directs AO to verify IA-VB47 is closed.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2. Step 5.3.2 of 40OP-9CP01: Unlock and open IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43 per 40AC-0ZZ06.

After examinee directs AO to open IA-VB45 provide the following Cue: IA-VB45, Air Supply to CPB-UV-5B and CP-PV-43

, is open. (In simulator setup) Examinee directs AO to unlock and open IA-VB45.

SAT / UNSAT Comments (required for UNSAT):

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 160 STEP CUE STANDARD 3. Step 5.3.3 of 40OP-9CP01:

IF RU-34 is available, THEN perform BOTH of the following to place it in service:

1. Ensure CP-V024 (isolation between Power Access Purge Duct and RU-34) is open.

2. Ensure CV-V023 (isolation between Refueling Purge Duct and RU-34) is closed. After directions are given to the AO provide the following Cue: CP-V024, Isolation between Refueling Purge Duct and RU-34, is open CP-V023, isolation between Refueling Purge Duct and RU-34, is closed Examinee directs AO to open/check open CP-V024 and to close/check closed CP-V023.

SAT / UNSAT Comments (required for UNSAT):

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. After examinee directs Effluent Tech to very ST is current provide the following Cue: The Shiftly ST for RU-37 and RU-38 is current.

Examinee directs Effluent Tech to ensure ST is current. SAT / UNSAT Comments (required for UNSAT):

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 161 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):

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. 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.

The examinee initials this step and continues. SAT / UNSAT Comments (required for UNSAT):

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 162 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. Examinee N/As this step.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 9.

Step 5.3.8 of 40OP-9CP01:

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):

STEP CUE STANDARD 10. Step 5.3.9 of 40OP-9CP01: Ensure Damper CPN-M06 opens.

If the examinee sends an Area Operator to check the positions of M03 and/or M06 report the following as appropriate: 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. SAT / UNSAT Comments (required for UNSAT):

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 163 STEP CUE STANDARD 11.

Step 5.3.10 of 40OP-9CP01:

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.

NOTE: Per the note preceding this step, dual indication will be received on HS-4 because UV4A remains closed. SAT / UNSAT Comments (required for UNSAT):

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. 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):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 164 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON REVISED COMMENTS 1 03/10/2009 6 Updated 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. 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)

JS-4 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 165 INITIAL CONDITIONS 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.

CANDIDATE JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 166JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 167 17. SIMULATOR SETUP:

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

B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

55. None CCCC. SPECIAL INSTRUCTIONS: This JPM is set to run with JS6 for the 2009 NRC exam DDDD. 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 EEEE. 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: 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 JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 168 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: Reconnect and reset the Steam Bypass Control System.

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 169

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.

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 170 JPM START TIME:

STEP CUE STANDARD 1. Step 1 of Appendix C:

IF the SBCS needs to be reset, THEN perform steps 2.9 through 2.15. Examinee goes to step 2.0 to reconnect and reset SBCS.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 2. Step 2.1 of Appendix C: Check at least 1 "Not In Operate" light is lit on the SBCS test panel. Verifies both RED lights are lit.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 3.

Step 2.2 of Appendix C: 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 Panel). SAT / UNSAT Comments (required for UNSAT):

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 171 STEP CUE STANDARD 4. Step 2.3 of Appendix C: 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. Inform CUE: The power supply lights in SFN-CO3Y, nest 4, 5, 7 are not lit. 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 172 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 173 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 174 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 175 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. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 176 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 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)

JS-5 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 177 INITIAL CONDITIONS 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.

CANDIDATE JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam Revised 9/23/08 178JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 179 18. SIMULATOR SETUP:

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

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

FFFF. 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. GGGG. 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)

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 180 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. Pressurizer heaters are energized due to the expected pressurizer level deviation (+3%). 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.

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 181 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-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 182 JPM START TIME:

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 Requested: Letdown can not be restored Examinee should determine from Initiating Cue that letdown cannot be restored.

SAT / UNSAT Comments (required for UNSAT):

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):

STEP CUE STANDARD 3. Step 3 of Appendix C: Notify chemistry that the plant will be operated with letdown flow isolated.

Chemistry is notified of the status of letdown.

Examinee calls chemistry and informs them of the status of letdown. SAT / UNSAT Comments (required for UNSAT):

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 183 STEP CUE STANDARD 4. Step 4.a of Appendix C:

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.

The CRS will ensure compliance with LCO 3.4.9 if pressurizer level exceeds the Tech Spec limit. Examinee determines that pressurizer level is 56% and rising (or will exceed 56% shortly).

SAT / UNSAT Comments (required for UNSAT):

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 184 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 185 STEP CUE STANDARD 8.

Step 4.d of Appendix C: Place all charging pumps in pull to lock (PTL).

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 186 STEP CUE STANDARD 9. Step 5 of Appendix C: IF charging has been stopped, AND ANY of the following conditions exist: Pressurizer level is less than 53% Seal injection is needed THEN perform the following:

a. Open CHN-PDV-240

b. Start at least one Charging Pump c. Adjust CHN-PDIC-240 to 90- 135 psid and place in AUTO.

d. IF seal injection is needed, THEN restore seal injection. e. Operate charging as needed to maintain pressurizer level between 33 and 53%. The CRS has determined that Seal Injection is not needed at this time.

Examinee determines that pressurizer level is > 53%. Note: Examinee proceeds to procedure step 6 regarding VCT level after step is read/addressed. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 10. Step 6 of Appendix C:

IF VCT level needs to be lowered, THEN direct an Operator to perform

the following:

a. Open CHN-V117, VCT drain to the EDT (Blending Room, 120' of the Auxiliary Bldg.).

WHEN the desired level is reached, THEN close CHN-V117. The CRS has determined the VCT level does not need to be lowered.

NOTE: The operator may determine that VCT level needs to be lowered and take procedural action, or may ask CRS. Step should not be performed based on CUE. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 187 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 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)

JS-6 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 188 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. Pressurizer heaters are energized due to the expected pressurizer level deviation (+3%).

CANDIDATE JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 189JPM 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 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 190 19. SIMULATOR SETUP: HHHH. IC#: 105 (For 2009 NRC exam only)

IIII. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS EVENT COMMAND DESCRIPTION

57. None JJJJ. SPECIAL INSTRUCTIONS: This JPM is set to run with JS8 for the 2009 NRC exam. KKKK. REQUIRED CONDITIONS: NAN-S01 and NAN-S02 energized from the NAN-S03 and NAN-S04 respectively. LLLL. 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. SPECIAL TOOLS/EQUIPMENT: 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 49) 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)

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 191 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 h ave been performed.

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 192

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.

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 193 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:

Turn the Synchronizing Switch for NAN-S01 Supply Breaker, NAN-SS-S01A, to "ON" and check for proper synchronization.

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.

SAT / UNSAT Comments (required for UNSAT):

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 194 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 195 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 196 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 197 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):

JPM STOP TIME:

NORMAL TERMINATION POINT

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 198 RECORD OF REVISIONS REVISION NUMBER REVISION DATE REASON 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. 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)

JS-7 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 199 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 200JPM 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 / UNSAT For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation. PVAR # _____________

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 201 20. SIMULATOR SETUP:

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

B. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS: EVENT COMMAND DESCRIPTION 58. 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: ____________________

20. SPECIAL TOOLS/EQUIPMENT: Copy of 40AO-9ZZ17, Section 5.0, Rev 13 JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 202 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. The CRS directs you to respond to the inadvertent CSAS per 40AO-9ZZ17, Section 5.0.

THIS IS A TIME CRITICAL JPM.

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 203

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.

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 204 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 _______________ SAT / UNSAT Comments (required for UNSAT):

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. SAT / UNSAT Comments (required for UNSAT):

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 205 STEP CUE STANDARD 3.

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.

The examinee places the CS handswitch in stop to anti-pump the CS pump and verifies the pump

stops.

SAT / UNSAT Comments (required for UNSAT):

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 206 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.

Examinee verifies Seal injection is in service, therefore no action should be taken unless the candidate exceeds 10 minutes to restore NC to the RCPs. SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD 6.

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.

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 failure. RECORD THE TIME THAT RCP LOW FLOW ALARMS CLEAR:

___________

NOTE: Must be less than 10 minutes from time recorded in step 1. SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 207 NORMAL TERMINATION POINT

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 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. 115. Vendor reference document upgrade 116. Plant modification (include number) 117. Procedure upgrade 118. Internal or External Agency Commitment (indicate item number) 119. Technical Specification Change (indicate amendment number) 120. Other (explain in comments)

JS-8 PVNGS JOB PERFORMANCE MEASURE 2009 NRC Exam 208 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 Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 209 of 275

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 210 of 275 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 Demineralize r 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 No. Malf. No. Event Type* Event Description 1 None N CO/SRO Shift Condensate Demineralizers. 2 imf cmCNCV04CHNFIC243_2 I RO/SRO After the crew performs the beginning of shift reactivity brief, 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).

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 - Isolate the affected steam generator End point The scenario is terminated when the affected steam generator has been isolated. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Supplemental Turnover Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 211 of 275 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 212 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 1 Event

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 213 of 275

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 214 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 2 Event

Description:

Seal Injection controller failure Time Position Applicant's Actions or Behavior T=7 RO Evaluates alarm window 3A11A per 40AL-9RK3A. Determines a Hi 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

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 215 of 275 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.

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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 216 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 4 Event

Description:

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.

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 Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 217 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 4 Event

Description:

CEA 15 drops into the core Time Position Applicant's 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 218 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 5 Event

Description:

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, 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-9EO01, Standard Post Trip Actions

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 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). 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, Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 219 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 5 Event

Description:

Steam Generator Tube Leak Time Position Applicant's 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 220 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 5 Event

Description:

Steam Generator Tube Leak Time Position Applicant's Actions or Behavior

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 221 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 6 Event

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.

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 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 222 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 6 Event

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°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)

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 223 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 6 Event

Description:

Trip initiator (2 nd CEA drops into the core) ATWS Time Position Applicant's Actions or Behavior

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 224 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 7 Event

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. 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 225 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 7 Event

Description:

Tave fails low Time Position Applicant's Actions or Behavior

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 226 of 275 Op-Test No: _2009

_ Scenario No.: 1 Event No: 8 Event

Description:

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 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 T h 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 - Cooldown and Isolate the most affected SG.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 227 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 8 Event

Description:

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. 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 T h 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 Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 228 of 275Op-Test No: _2009

_ Scenario No.: 1 Event No: 8 Event

Description:

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

Scenario Normal end point is when the SG is isolated.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 229 of 275 Facility: PVNGS Scenario No.: 2 Op-Test No: 2009 Examiners: Operators:

Initial Conditions: IC #102, (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 pressurizer was placed in boron equalization last shift. Chemistry has verified that the boron differential between the pressurizer and the RCS is 2 ppm. The first evolution the crew needs to complete is to remove the pressurizer from boron equalization. The second action the crew needs to complete is to shutdown the 'A' DG. The 'A' DG is running and ha s run at full load for 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The surveillance test is complete with the exception of shutting down the 'A' DG. The Area Operator has been briefed and is standing by with a copy of the procedure. PC is NOT recircing the RWT. Normal Shiftly Surveillances a re complete. Risk Management Action Level is Green. Train B is protected equipment. Unit 2 is supplying the Aux Steam cross-ti e header. Event No. Malf. No. Event Type* Event Description 1 None N RO/SRO Remove the pressurizer from boron equalization. 2 mfEG06A C RO/SRO (TS) The crew will start a normal shutdown of DG 'A'. The DG will trip before the crew can complete the shutdown. The CRS addresses

Tech Specs. 3 cmTRRX09RCBPDT125B_4 I CO/SRO (TS) SG DP transmitter failure Channel B fails low. The crew will address the alarm response procedure and bypass the parameter within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The CRS will address Tech Specs.

4 mfMC01A C - ALL Condenser vacuum will begin to degrade. The CRS will enter 40AO-9ZZ07 and commence a downpower to stabilize vacuum. Once a downpower is started, vacuum will recover. 5 mfNI02B k:4 mfNI02A k:4 I CO/SRO A failure of control channel 2 will occur. The CRS enters 40AO-9ZZ16, RRS Malfunctions to select the unaffected channel at the RRS test panel 6 mfMS01D mfED08A mfED08B M RO/CO/SRO C-ALL A steam leak in containment will occur causing a reactor trip. The crew may trip manually before the automatic trips initiate. On the trip, the fast bus transfer for the 13.8 kV non-class buses will fail. 7 cmCPSI01SIAP02_6 cmCPSI01SIBP02_5 C RO/SRO HPSI A trips on an 86 lockout and HPSI B fails to auto start Critical Task - initiate safety injection flow 8 cmBSRP01BSSG1DPHIAT_1 cmBSRP01BSSG1DPHIBT_1 cmBSRP01BSSG1DPHICT_1 cmBSRP01BSSG1DPHIDT_1 C CO/SRO Failure of the SG 1 > SG 2 DP lockout Critical Task - secure feeding the faulted SG End point The scenario is terminated when the crew stabilizes RCS temperature, the 'B' HPSI pump is started, and AF to the faulted SG is isolated. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 230 of 275 Supplemental Turnover Plant conditions:

Unit 1 has been at 100% power for the past 150 days. The core is presently at 250 EFPD. Risk Management Action Level is GREEN. Normal, shiftly surveillances are complete. 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 pressurizer was placed in boron equalization last shift. Chemistry has verified that the boron differential between the pressurizer and the RCS is 2 ppm. The first evolution the crew needs to complete is to remove the pressurizer from boron equalization. The second action the crew needs to complete is to shutdown the 'A' DG. The 'A' DG is running and has run at full load for 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The surveillance test is complete with the exception of shutting down the 'A' DG. The Area Operator has been briefed and is standing by with a copy of the procedure. 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 Operator Actions Form ES-D-2 NUREG-1021, Revision 9 231 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 1___

Event

Description:

Removing the pressurizer from boron equalization.

Time Position Applicant's Actions or Behavior T=0 RO De-energizes the pressurizer backup heater using handswitches RCA-HS-100-4, RCB-HS-100-5, and RCN-HS-100-6,7,8, and 9 Raises the setpoint on RCN-PIC-100, Pressurizer Pressure Controller to approximately 2250 psia.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 232 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 1___

Event

Description:

Removing the pressurizer from boron equalization.

Time Position Applicant's Actions or Behavior

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 233 of 275 Op-Test No: _2009

_ Scenario No.: 2 Event No: 2___

Event

Description:

Shutdown of the 'A' DG following performance of a surveillance test with DG trip on GENERATOR DIFFERENTIAL after first load reduction Time Position Applicant's Actions or Behavior T=7 RO The Reactor Operator will start shutting down DG 'A' per 40OP-9DG01.

1. Reduce DG 'A' load per Appendix N. Reduces load to 3.6 to 4.4 MWs for 5 minutes using the Diesel Generator Speed Switch (PEA-SC-G01) on B01. Evaluator Note: Every load change requires staying at the new load for 5 minutes, therefore after the first load reduction, have the driver insert the trip of DG 'A' (Key 1). Informs the CRS of the DG trip and addresses the alarm response procedure.

o Checks that DG 'A' tripped as indicated by a lit STOP light on DGA-HS-1.

o Checks that DG 'A' output breaker PBA-S03B is open as indicated on PEA-HS-S03B.

o Directs an operator to investigate the cause of the trip a the control cabinet and take action per the local alarm response procedure.

CRS The CRS declares DG 'A' inoperable and addresses Tech Specs.

1. Enters LCO 3.8.1 condition 'B' and performs the following: Directs an operator to perform 41ST-1ZZ02, Inoperable Power Sources Action Statement within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . (This satisfies performing S.R.3.8.1.1 from condition B). Verifies no redundant equipment on the other train is inoperable (This is addressed by 41ST-1ZZ02)

Another LCO action is also to determine the other DG is not inoperable due to common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The CRS may not address this at this time due to not knowing what caused the DG to trip at this time. (This will be addressed by 41ST-1ZZ02.)

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 234 of 275 Op-Test No: _2009

_ Scenario No.: 2 Event No: 3___

Event

Description:

SG DP transmitter failure Channel B fails low Time Position Applicant's Actions or Behavior T= 20 CO The CO responds to alarms on panel B05

1. Addresses the alarm response procedure for window 12C. Verifies normal SG 2 D/P on B05 indicators RCA-PDI-125A, RCB-PDI-125B, RCC-PDI-125C and RCD-PDI-125D. The CO determines that instrument RCB-PDI-125B has failed low. Contact I&C prior to placing channel in bypass (The CRS may perform this step). Bypasses parameter 15 by unlocking the bypass compartment on PPS panel B behind panel B06 and pushing the bypass button for parameter 15.

CRS CRS addresses Tech Specs

1. Enters LCO 3.3.1 condition 'A' and performs the following: Directs an operator to bypass the SG #2 DP (parameter 15) on PPS. (This should occur after I&C tell the control room that they cannot get a tech to the control room for 90 minutes).

.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 235 of 275 Op-Test No: _2009

_ Scenario No.: 2 Event No: 4___

Event

Description:

Condenser vacuum degrades Time Position Applicant's Actions or Behavior T= 28 Crew Evaluator Note: It will take approximately 2.5 minutes from when the malfunction is entered until the first alarm.

Receives Condenser A-B Differential Pressure Hi alarm on B05.

CRS Enters 40AO-9ZZ07. Loss of Condenser Vacuum

1. Performs the diagnostic flow chart and goes to Section 4.0.

2. Directs an operator to have AO ensure seal water on the Condenser Expansion Joints (Dog bone seals), the vacuum breakers, and the Steam packing Exhauster Condenser drain.

3. Directs an operator to have the AOs checks for sources of possible loss of vacuum. 4. Directs the CO to ensure all Air Removal Pumps are in operation.

5. May direct the CO to open all the suction valves for the 'D' Air Removal pump. 6. Determines the magnitude of a power reduction (minimum of 5%) and the rate to reduce power.

7. Calculates the reactivity needed to reduce power by boration (1000 gallons per 10%) or CEA insertion (9 inches per 1%). Evaluator Note: The procedure gives the CRS the option of using CEAs or boration. He may use either or a combination of both.

8. Directs the RO to begin boration (if boration is used)

9. Directs the CO to reduce power by lowering turbine load.

10. Directs CO to maintain Tavg/Tref mismatch 5°F or less. Evaluator Note: Once the crew has downpowered about 5% have the driver delete the malfunction to simulate correcting the condenser vacuum leak.

11. Stops the power reduction.

CO Addresses the alarm response for CNDS SYS TRBL on B05, Window 14A by: Verify alarm validity May manually start standby vacuum pump P01D. Addresses condenser vacuum on B06 and reports vacuum in Shell A degrading. Starts the 'D' AR pump (handswitch ARN-HS-28 on B07) and opens suction valves (using ARN-HS-14m 15 and/or 16 on B07) as directed by the CRS. Reduces turbine load using the "LOAD LIMIT" potentiometer on B06 as directed by the CRS.

Stabilizes power when the leak is repaired by not reducing Turbine load any further except for temperature adjustment if needed due to boron already added.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 236 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 4___

Event

Description:

Condenser vacuum degrades Time Position Applicant's Actions or Behavior RO Performs a boration if directed by the CRS or monitors CEA position if CEAs are used to reduce power in automatic. (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) as determined in step 7.3.1 or 7.3.2.

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 totalizer/counter module (Micro-Motion).

c. Depress the "Start" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion). If the CRS directs a manual CEA insertion, the RO will insert CEAs using the Insert/

Withdraw switch on the CEDM panel. Monitors Reactor power using ERFDADS and/or B06 indications as turbine load is reduced.

Monitors Tavg/Tref mismatch using meter on B04.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 237 of 275 Op-Test No: _2009

_ Scenario No.: 2 Event No: 5___

Event

Description:

Failure of control channel 1 Time Position Applicant's Actions or Behavior T= 46 Crew The crew responds to alarms on B04 and B06. The crew addresses the alarm response procedures for 4A10B and 6A6B). The crew determines that Control Channel #1 has failed low. CRS Enters 40AO-9ZZ16, RRS Malfunctions

1. Directs an operator to place CEDMCS in a position other than Auto Sequential (CRS should direct which position he wants the switch in). Evaluator Note: The RRS malfunction direct the CRS to put the CEDM switch out of AUTO SEQUENTIAL. The alarm response procedures direct the board operator to put the switch in MANUAL SEQUENTIAL, so there may be some discussion about which position to select.

2. Determines the impact of the failed instrument.

1. AMI on 5% deviation

2. DFWCS deviation on 8% - uses canned value of 60% power.

3. Directs an operator to select the unaffected instrument at the RRS test panel (behind B05)

4. Directs an operator to check Tavg/Tref mismatch is 3°F or less (this may take a minute or so until the rate of change decays)

5. Directs an operator to place CEDMCS in the desired mode.

CO Addresses the alarm response procedures. When directed, places CEDMCS in the mode using the CEDM Mode Select Switch on B04 as directed by the CRS (this may be performed by the RO) When directed selects the unaffected channel at the RRS test panel using the " N1 Select" switch.

When directed places CEDMCS in the mode directed by the CRS. Addresses the DFWCS alarm response procedure and places Control Channel one in "Maintenance" and removes the ATUN LOCKOUT using the DFWCS digital

screen. RO May select CEDMCS using the Mode Select Switch on B04 as directed by the CRS.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 238 of 275 Op-Test No: _2009

_ Scenario No.: 2 Event No: 6, 7, and 8 Event

Description:

Trip initiator (ESD in containment)

Time Position Applicant's Actions or Behavior T= 56 Crew Crew receives alarms on B07 for high temperature and humidity in containmant.. The reactor trips automatically. The crew performs the SPTAs. Evaluator Note: On the trip a failure of the fast bus transfer of NAN-S01 and NAN-S02 (13.8kV non-class busses) will occur.

RO

EVENT 7 May report Reactivity (may be done by the CO). Will report a loss of NAN-S01/S02 and NBN-S01/S02 when asked the status of the Electric Plant. Reports Pressurizer level decreasing and RCS subcooling increasing.

Reports Seal injection available to the RCPs, but no Nuclear Cooling Water. Addresses the blue plaque on B04 and closes the seal Bleedoff valves from the RCPs. Since a LOOP has occurred, the RO will have to use the containment isolation valves (CHB-HS-505 and CHA-HS-506 on B03) with the relief isolation (CHN-HS-507 on B03) to isolate seal bleedoff. Reports RCS pressure decreasing. Ensures SIAS actuated.

Notices no HPSI running (A pump tripped on an 86 Lockout and the B pump failed to auto start) and starts the B HPSI pump using SIB-HS-1 on B02.

Critical Task: Ensure adequate Safety Injection flow Reports no RCPs operating, loop T, and RCS subcooling. May report RCS Tc (usually done by the CO).

May report containment pressure increasing and no alarms or trends on the Radiation Monitoring Panel (may be done by the CO) May report containment temperature increasing and containment pressure increasing (may be done by the CO). Evaluator note: Depending on how long the scenario runs, the RO may have to reclose CHN-UV-507, Bleedoff Relief Isolation due to it failing open because CSAS isolated air to containment. This is not necessary to see to complete the scenario.

CO EVENT 8 May report Reactivity. Reports status of the Main Turbine and Generator output breakers. May report RCS Tc. Reports SG levels and method of feed.

Reports indications of a faulted SG #2 into containment due to low pressure and level dropping rapidly on SG #2. CO does not feed SG #2 due to the fault in containment.

When AFAS occurs, the DP lockout will fail, allowing AF to flow to SG #2. The CO should override and stop feeding SG #2. Critical Task: When AFAS DP is failed, secure feeding faulted SG. Stabilizes RCS temperature by using the lowest RCS Tc when rebound occurs to lookup the saturation pressure for that temperature and lower the non-faulted SG to that pressure using ADVs.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 239 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 6, 7, and 8 Event

Description:

Trip initiator (ESD in containment)

Time Position Applicant's Actions or Behavior After the ESD procedure is entered the CO performs the following: Ensures that the affected SG is isolated by verifying all of the following valves are

closed: Component Handswitch - all on B06 unless noted otherwise. ADV 184 SGA-HIC-184A 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 isolation 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 from SG 2 SGA-HS-138A AF 'A' Feedwater Isolations for SG 2 AFB-HS-33A and AFC-HS-37A 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 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:

A Loss of NAN-S01/S02 and NBN-S01/S02 has occurred 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% (Pressurizer level is lowering due to the ESD) b. Check that the RCS is 24°F or more subcooled. (Subcooling is increasing due to the ESD) c. Check that BOTH of the following are in service to all RCPs.

Seal injection

Nuclear Cooling Water - (NC is not available so the CRS should direct the RO to address the blue plaque on B04). 5. Determine that RCS Pressure Control acceptance criteria are met by BOTH of the following: Pressurizer pressure is 1837 - 2285 psia Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 240 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 6, 7, and 8 Event

Description:

Trip initiator (ESD in containment)

Time Position Applicant's Actions or Behavior Pressurizer pressure is trending as expected to 2225 - 2275 psia (if pressure is going high, the CRS should direct the RO to use Auxiliary Sprays to control RCS pressure due to the loss of power). 5.2 WHEN 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 (This is not applicable due tot the loss of power.) 6. Determine that Core Heat Removal acceptance criteria are met by ALL of the following: At least one RCP is operating - No RCPs are running due to loss of power. 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 (SG #2 level is lowering rapidly)

Directs CO to not feed faulted SG. b. Checks that Tc is between 560 and 570°F.

c. Check that steam generator pressure is 1140 - 1200 psia. Due to MSIS actuated, the CRS should tell the CO to stabilize temperature when dryout is reached in the faulted SG. CO should be using Aux Feed to feed SG #1 only. 8. Determine that Containment Isolation acceptance criteria are met by the following:

c. Check that Containment pressure. Since Containment pressure is > 3 psig, directs an operator to ensure that CIAS has been initiated

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:

a. Check that containment temperature is less than 117°F.

b. Check that containment pressure is less than 2.5 psig. Since containment pressure is > 8.5 psig, he directs the RO to ensure CSAS actuated and at least one Containment Spray header flow is > 4350 gpm. Diagnoses an Excess Steam Demand. Enters 40EP-9EO05, Excess Steam Demand Confirms the diagnosis Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 241 of 275Op-Test No: _2009

_ Scenario No.: 2 Event No: 6, 7, and 8 Event

Description:

Trip initiator (ESD in containment)

Time Position Applicant's Actions or Behavior Directs chemistry to perform Abnormal Occurrence Checklist Ensures the event is being classified (by instructing SM to classify the event). Opens the placekeeper and enters the EOP entry time.

Directs an operator to ensure SIAS has actuated and HPSI and LPSI pumps have started There is adequate SI flow. Directs the RO to shift charging pump suction to the RWT using Appendix 10 or to the SFP using Appendix 11.

Determines SG #2 is the most affect Steam Generator Isolates the Steam Generator #2. No action should be necessary to isolate the SG if the CO has already closed the Aux Feedwater valves to SG #2.

Normal termination point is when the 'B' HPSI has been started, RCS temperature is stabilized and the affected SG is isolated.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 242 of 275 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. 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 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 Specs. 3 cmTRRC03RCNPT100X_1 C RO/SRO RCN-PT-100X fails low requiring the crew to address the Alarm Response procedure and select the unaffected channel. 4 imf mfCPTP04TCNP01A_6 C CO/SRO The 'A' Turbine Cooling water pump will trip with a failure of the standby pump to auto start. This will require the crew to address 40AO-9ZZ03, Loss of Cooling Water or the alarm response procedure to start the standby TC pump.

5 imf mfTH01B (TS) RO/SRO A RCS leak will develop requiring the CRS to enter 40AO-9ZZ02, Excessive RCS leakrate. 6 imf mfTC13 imf mfMS16 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 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 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. 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 9 243 of 275 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 244 of 275Op-Test No: _2009

_ Scenario No.: 3 Event No: 1 Event

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. 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).

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 245 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 2 Event

Description:

PBA-S03 LOV relay 727-1 fails Time Position Applicant's Actions or Behavior T=0 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 246 of 275Op-Test No: _2009

_ Scenario No.: 3 Event No: 2 Event

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.

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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 247 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 3 Event

Description:

RCS controlling pressure (RCN-PT-100X) fails low Time Position Applicant's Actions or Behavior T= 10 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 no bias from a high RCS pressure condition applied to the SBCS). This may be discussed by another member of the crew.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 248 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 4 Event

Description:

Turbine Cooling Water pump trip Time Position Applicant's Actions or Behavior T=17 CO The CO addresses alarms on B07.

1. Determines the 'A' TC pump has tripped and the 'B' TC pump did not auto start. 2. Recommends starting the 'B' TC pump.

3. Starts the 'B' TC pump when directed by the CRS using TCN-HS-22 on B07. 4. Places TC 'A' pump in the Pull-to-Lock position per the Alarm Response Procedure.

CRS The CRS may enter 40AO-9ZZ03, Loss of Cooling water or may direct the CO to address the alarm response procedure to start the standby TC pump.

May direct area operator to investigate cause of trip of TC pump.

May direct area operator to ensure proper operation of running TC pump.

Op-Test No: _2009

_ Scenario No.: 3 Event No: 5 Event

Description:

RCS Leak Time Position Applicant's Actions or Behavior T= 25 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 performs an RCS leakrate per Appendix B of 40AO-9ZZ02 Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 249 of 275Op-Test No: _2009

_ Scenario No.: 3 Event No: 5 Event

Description:

RCS Leak Time Position Applicant's Actions or Behavior 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 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Mode 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ).

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. Evaluator note: Leakrate should be about 17 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 250 of 275Op-Test No: _2009

_ Scenario No.: 3 Event No: 5 Event

Description:

RCS Leak Time Position Applicant's Actions or Behavior

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 251 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 6 Event

Description:

Main turbine trip.

Time Position Applicant's Actions or Behavior T= 35 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 252 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 7 Event

Description:

Standard Post Trip Actions/ Failure of SGN-PT-1024.

Time Position Applicant's Actions or Behavior T= 35 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) or may use ADVs. 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 NUREG-1021, Revision 9 253 of 275 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 Applicant's Actions or Behavior T= 7 minutes after reactor trip Crew Notices RCS leak rate has increased dramatically.

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 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 transferred to offsite electrical power such that BOTH of the following conditions are met:

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 254 of 275Op-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 Applicant's 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:

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:

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 255 of 275Op-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 Applicant's 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.

Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 256 of 275 Op-Test No: _2009

_ Scenario No.: 3 Event No: 9 Event

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.

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 Appendix D Operator Actions Form ES-D-2 NUREG-1021, Revision 9 257 of 275Op-Test No: _2009

_ Scenario No.: 3 Event No: 9 Event

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.

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.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 258 of 275 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. Aux Feed Pump 'A' is out of service for work to repair a leak on the discharge check valve (AFA-V016). Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . LCO 3.7.5 condition 'A' and 'B' have been entered. 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 C CO/SRO 5 minutes into the SPTAs, the 'B" AFW pump will trip. The CO should shift to the 'N' AFW pump. 8 imf cmCPFW07AFNP01_3 M ALL When the CO starts AFN, it will have degraded discharge pressure. 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 - 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

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 259 of 275 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 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. Aux Feed Pump 'A' is out of service for work to repair a leak on the discharge check valve (AFA-V016). Expected back in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . LCO 3.7.5 condition 'A' and 'B' have been entered. . Planned shift activities:

.The crew is directed to shift running Plant Cooling Water pumps immediately after turnover due to a vibration 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.

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 9 260 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 1 Event

Description:

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. 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.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 261 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 1 Event

Description:

Crew shifts running Plant Cooling Water Pumps.

Time Position Applicant' s Actions or Behavior

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 262 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 2 Event

Description:

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)

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 Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 263 of 275 Op-Test No: _2009

_ Scenario No.: 4 Event No: 3 Event

Description:

SG #2 Channel C level transmitter failure Time Position Applicant' s 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 264 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 4 Event

Description:

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:

2. Enters the AOP entry time

3. Checks that A RPCB - Loss of Feedpump has actuated and CEA subgroups 4, 5, and 22 have inserted.

4. Checks that Main Turbine Setback-Runback has lowered Main Turbine load to 65% or less.

5. Checks that no CEAs are deviating by greater than 6.6 inches if ANY CEA Reg Groups are below the Transient Insertion Limits.

6. May direct an operator to perform Appendix D, Status Check RPCB Loss of Feedpump (normally done by the STA).

7. Directs the CO to restore and maintain SG levels 45-60% NR.

8. Checks that RRS is adjusting CEAs to restore Tave/Tref +

3°F. 9. If condenser hotwell level is less than 41 inches, directs an operator to restore level to 41 inches or more. 10. Directs an operator to remove RPCB from service by pushing the "AUTO ACTUATE OUT OF SERVICE" and the "TEST RESET" pushbuttons. 11. Directs the CO to perform a lamp test to ensure the "LOAD LIMITING" light illuminates. 12. Directs the CO to lower the load limit potentiometer until the "LOAD LIMITING" light comes on. 13. Directs CO to raise Speed Bias on the operating Main Feedwater Pump to zero or more 14. Directs an operator to place CEDMCS is "Manual Sequential" when CEA motion is only required for Xenon Buildup 15. Directs an operator to monitor ASI. 16. Directs an operator to start boron equalization of the pressurizer. 17. 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:

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 265 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 4 Event

Description:

Trip of the 'B' MFP Time Position Applicant' s 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.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 266 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 4 Event

Description:

Trip of the 'B' MFP Time Position Applicant' s Actions or Behavior

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 267 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 5 Event

Description:

High Vibration on the 'A' Main Feedpump (Trip initiator)

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 Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 268 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 6 Event

Description:

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.

2. Checks the Main Turbine is tripped and the generator output breakers are closed. 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.

RO Commences boration of the RCS using Standard Appendix 103. (basic steps the RO will perform)

7. Sets the desired boric acid makeup flow rate on the Foxboro controller, CHN-FIC-210Y.

8. Selects the "Target" makeup volume (gallons) on the boric acid makeup flow totalizer/counter CHN-FQIS-210Y (Micro-Motion) (minimum 5000 gallons).

9. 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).

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 269 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 6 Event

Description:

Standard Post Trip actions with 2 CEAs stuck out.

Time Position Applicant' s Actions or Behavior

c. Depress the "Start" pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion). Critical Task: Commence boration. 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 Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 270 of 275 Op-Test No: _2009

_ Scenario No.:

4 Event No: 6 Event

Description:

Standard Post Trip actions with 2 CEAs stuck out.

Time Position Applicant' s 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:

g. Check that Containment pressure is less than 2.5 psig.

h. 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.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 271 of 275 Op-Test No: _2009

_ Scenario No.: 4 Event No: 7 Event

Description:

Trip of 'B' AFW pump Time Position Applicant' s Actions or Behavior If the CO uses AFN first, then go to event 7. 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.

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).

Op-Test No: _2009

_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicant' s Actions or Behavior Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 272 of 275 Op-Test No: _2009

_ Scenario No.: 4 Event No: 8 Event

Description:

AFN-P01 discharge degrades.

Time Position Applicant' s Actions or Behavior T= after CRS enters Reactor Trip EOP CO 1. Notices that the feed to the SGs has degraded or stopped.

2. Informs the CRS of a loss of all feed.

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.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 273 of 275 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 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) 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-HV-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)

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 274 of 275 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 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: Establish feedwater to the SG using condensate pumps.

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). 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 SIA-HS-627 SIA-HS-637 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. The RO may assist controlling SG pressures while the CO performs standard Appendix 44.

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 275 of 275

End Point The scenario may be stopped when feedwater is established to one SG using condensate.

ML101960320

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