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Initial Exam 2008-301 Final Sim/In - Plant Job Performance Measure Worksheet
	ML101970310
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	; NRC/RGN-II
To:	; Carolina Power & Light Co
References
	50-261/08-301
	Download: ML101970310 (137)
	v • d • e

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Perform Rod Cluster Exercise lAW OST-011. 001 A2.11 4.4/4.7 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 01001100302 2008 NRC SIM a Simulated Performance:

Actual Performance:

x Classroom Simulator x Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

The plant is at 75% power.

OST-011, ROD CLUSTER CONTROL EXERCISE AND ROD POSITION INDICATION (Monthly) is being performed.

The prerequisites of Section 4 have been completed.

Task Standard:

Reactor has been manually tripped in response to a dropped rod. Required Materials:

OST-011, Rod Cluster Control Exercise and Rod Position Indication (Monthly)

General

References:

OST-011, Rod Cluster Control Exercise and Rod Position Indication (Monthly)

Handouts:

OST -011 , Section 8.1 Initiating Cue: You are to perform OST-011 commencing with Section 8.1 for Shutdown Bank "An rods. Time Critical Task: NO Validation Time:

18 minutes 2008 NRC SIM a NUREG 1021, Revision 9, Supplement 1

Appendix C 1. IC # 618. Job Performance Measure Worksheet SIMULATOR SETUP Form ES-C-1 3. When directed by the Chief Examiner, insert IMF CRF03A for Shutdown Bank "A" Rod N-7 to drop into the core during withdrawal.

4. OST-011 Prerequisites are signed off as complete.

2008 NRC SIM a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 11 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment: Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM a STARTTIME:

__ _ Reviews procedure and any required information.

OST -011, Section 8.1 is the required procedure to be performed.

Candidate may wish to review the prerequisites in Section 4. Record the initial Group Step counter height for Shutdown Bank "An. (Step 8.1.1) Candidate observes the proper group step counters and records 225 steps for Groups A and B. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Examiner's Note: Examiner's Cue: Comment: Performance Step: 4 Standard:

Examiner's Note: Comment: 2008 NRC SIM a Page 4 of 11 PERFORMANCE INFORMATION Form ES-C-1 If necessary to verify performance of Shutdown Bank A Demand Position Indication System prior to the required height change position of the test, THEN PERFORM the following:

Position the ROD BANK SELECTOR switch to the SBA position for Shutdown Bank "A". (Step 8.1.2.1) Candidate places the ROD BANK SELECTOR switch to the SBA position.

Performance of Shutdown Bank A Demand Position Indication System is required.

Using the IN-HOLD-OUT lever AND RTGB step counter indication, POSITION Shutdown Bank "A" rods in TWO steps. (Step 8.1.2.2) Candidate uses the IN-HOLD-OUT lever and inserts Shutdown Bank "A" rods from 225 steps to 223 steps. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Note: Comment: Performance Step: 6 Standard:

Examiner's Note: Comment: 2008 NRC SIM a Page 5 of 11 PERFORMANCE INFORMATION Form ES-C-1 Using the IN-HOLD-OUT lever, RETURN rods to the initial height as indicated on the operable step counter(s) for Shutdown Bank "A".(Step 8.1.2.3) Candidate uses the IN-HOLD-OUT lever and withdraws Shutdown Bank "A" rods from 223 steps to 225 steps. Check that Shutdown Bank "A" individual RPI indications on ERFIS have returned to their pre-test positions. (Step 8.1.2.4) Candidate checks that Shutdown Bank "A" RPI indications on ERFIS have returned to their pre-test positions.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 7 Standard:

Examiner's Note: Comment:

Performance Step: 8 Standard:

Examiner's Note: Comment:

Performance Step: 9 Standard:

Examiner's Note: Comment: 2008 NRC SIM a Page 6 of 11 PERFORMANCE INFORMATION Form ES-C-1 Record Initial Rod Heights from the RTGB (Steps), Initial Rod Heights from ERFIS (Inches). (Step 8.1.3)

Candidate records initial rod heights from the RTGB and ERFIS. Determine the required change in rod height based on current plant conditions. (Step 8.1.4) Plant is in Mode 1 . Rod height change is 19 steps. 225 -19 = 206 steps. Verify the ROD BANK SELECTOR switch in the SBA position for Shutdown Bank "A". (Step 8.1.5) Candidate re-positions switch to the SBA position.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 11 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 10 Using the IN-HOLD-OUT lever and RTGB Step Counter indication, position Shutdown Bank "A" rods to the required number of steps as dictated by plant conditions. (Step 8.1.6) Standard:

Candidate positions the IN-HOLD-OUT lever to IN position and inserts Shutdown Bank "A" 19 steps to 206 steps. Examiner's Note: APP-005-F3, APP-005-06 and APP-003-F4 will be received during the rod insertion.

Comment: Performance Step: 11 Record tested Rod Heights from the RTGB (Steps) and tested Rod Heights from ERFIS (Inches). (Step 8.1.7) Standard:

Candidate records Shutdown Bank "A" Rod Heights from RTGB (Steps) and Rod Heights from ERFIS (Inches).

Examiner's Note: Comment: 2008 NRC SIM a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 11 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 12 Using the IN-HOLD-OUT lever, return rods to the Initial Height (Steps) as indicated by the step counters. (Step 8.1.8) Standard:

Candidate positions the IN-HOLD-OUT lever to the OUT position and begins withdrawing Shutdown Bank "A" rods. Examiner's Note: Withdrawal shall NOT be the continuous 19 steps per Precaution 5.5.5. Booth Operator:

Insert malfunction IMF CRF03A to cause Rod N-7 to drop into the core AFTER the candidate starts the second withdrawal of the rods. Comment:

Performance Step: 13 Candidate diagnoses a dropped rod in Shutdown Bank "A". Standard:

Candidate determines a dropped rod has occurred in Shutdown Bank "A" by the following indications:

Rod Bottom Light for Rod N-7

Prompt drop in reactor power

APP-005-A3; PR DROPPED ROD

APP-005-C3; PR CHANNEL DEV

APP-005-F2; ROD BOTTOM ROD DROP Examiner's Note: Comment: 2008 NRC SIM a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 11 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 14 Stop withdrawal of Shutdown Bank "An rods. Standard:

Candidate releases IN-HOLD-OUT lever to the HOLD position.

Examiner's Note: Comment:

Performance Step: 15 Informs CRSS of need to trip reactor and initiates a manual reactor trip. (Based on Caution at the beginning of Section 8.1 and Precaution 5.5.4). Standard:

Informs CRSS and depresses either reactor trip pushbutton.

Examiner's Note: Comment: Termination:

STOP TIME: 2008 NRC SIM a Candidate verifies that reactor is tripped by Reactor Trip and Bypass breaker indication, Rod Bottom Lights, RPI indication, and Nuclear Flux decreasing.

END OF TASK Reactor has been manually tripped due to a dropped rod while in Individual Bank select mode. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 11 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM a Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM a NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM a Page 11 of 11 JPM CUE SHEET

The plant is at 75% power. Form ES-C-1

OST-011, ROD CLUSTER CONTROL EXERCISE AND ROD POSITION INDICATION (Monthly) is being performed.

The prerequisites of Section 4 have been completed.

You are to perform OST-011 commencing with Section 8.1 for Shutdown Bank "A" rods. NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Task No.: Fill a Safety Injection Accumulator lAW JPM No.: OP-202. 006 A4.01 4.1/3.9 006 A4.02 4.0/3.8 006 A 1.07 3.3/3.6 006 A1.13 3.5/3.7 NRC Examiner:

Date: Form ES-C-1 01006100101 2008 NRC SIM b Simulated Performance:

Actual Performance:

_.:....:X_

Plant x Classroom Simulator

---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

2008 NRC SIM b

The plant is operating at 100% RTP.

SI ACCUM C HilLa LVL (APP-002-E4) alarm has been received and actions have been reviewed by the RO.

OP-202, Section 8.2.1.1 Initial Conditions have been completed.

Refueling Water Purification is NOT in progress.

You are the Licensed Dedicated Operator referred to in OP-202.

Safety Injection Pump "A" has been walked down and pre-start checks are complete.

SI Accumulator "C" filled to reset the low level alarm without exceeding specified limits. OP-202, Revision 75, Section 8.2.1 OP-202, Revision 75, Section 8.2.1 NUREG 1021, Revision 9, Supplement 1

Appendix C Handouts:

Initiating Cue: Time Critical Task: Validation Time: 1. IC-611. Job Performance Measure Worksheet OP-202, Revision 75, Section 8.2.1 Form ES-C-1 The CRSS briefs and has directed you to fill SI Accumulator "C" to reset the low level alarm lAW OP-202, Section 8.2.1. NO 12 minutes SIMULATOR SETUP 2. NO SCN Required.

3. If IC-611 not available, reset simulator to IC-13 and drain SI Accumulator "C" to -61 %. 4. Ensure that Refueling Water Purification is NOT in progress.

5. Mark up OP-202, Section 8.2.1 with Initial Conditions Steps 8.2.1.1.a through 8.2.1.1.f.2 completed.

6. FREEZE the simulator until directed by the Chief Examiner to RUN. 2008 NRC SIM b NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 11 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

STARTTIME:

__ _ Examiner's Note: Performance Step: 1 Standard:

Comment:

Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM b The candidate may use ERFIS to monitor SI Accumulator "c" level. (ERFIS:QP ACCUM C) Check open SI-856A, SI PUMP RECIRC and SI-8568, SI PUMP RECIRC. Valves SI-856A and 8 checked OPEN. Verify the Control Power Defeat Switch for SI-869 is in the NORMAL position.

Locating NORMAL / DEFEAT key switch for SI-869 and placing the switch in the NORMAL position.

Key switch is located in the rear of the RTGB on the "ECCS VALVES CONTROL POWER DEFEAT PANEL."

When the key switch is selected to NORMAL, amber light above the key switch will ILLUMINATE.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Examiner's Note: Comment:

Performance Step: 4 Standard:

Examiner's Note: Comment: 2008 NRC SIM b Page 4 of 11 PERFORMANCE INFORMATION Form ES-C-1 If an SI actuation is received during filling, then immediately close the applicable SI Accumulator makeup valve and perform Step 8.2.1.2.m to restore the SI System lineup. Candidate acknowledges continuous action step in the event of an SI actuation.

Open SI-869, SI HOT LEG HDR. Valve SI-869 opened. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 5 Standard:

Examiner's Note: Comment: Performance Step: 6 Standard:

Examiner's Note: Comment: 2008 NRC SIM b Page 5 of 11 PERFORMANCE INFORMATION Start SI Pump "A". SI Pump "A" started. Neither SI has been run in the last 15 days. Form ES-C-1 When an SI Pump is started, APP-002-C3, BIT HDR HI PRESS will be received due to the cold leg header being pressurized by the SI Pump. This is an expected alarm and the BOP should be directed to review the APP. Listed below are APP-002-C3 actions:

Compare the indications on PI-943 and PI-934 to determine validity.

If the header high pressure is due to SI System testing, then do NOT perform actions to clear the high pressure until testing is complete or the operating SI Pump discharge valve is closed. At least 1 SI Pump Area Cooling unit is operating (HVH-6A or 68 or both). HVH-6A and/or 68 verified operating.

NUREG 1021, Revision 9, Supplement 1

Appendix C Note prior to Step 8.2.1.2.h

Performance Step: 7 Standard:

Examiner's Note: Comment: 2008 NRC SIM b Page 6 of 11 PERFORMANCE INFORMATION Form ES-C-1 NOTE: The following are pressure and level limits/alarms for the SI Accumulators:

High Pressure Alarm 646 psig

Normal Operating Pressure 630 psig

High Level Alarm 75 percent

Low Level Alarm 67 percent a. Open SI-851C, MAKEUP. b. Monitor the level and pressure of SI Accumulator "C". c. When desired level is obtained, then close SI-851 C. a. Valve SI-851C opened. b. Maintained>

614 psig and < 646 psig pressure limits as indicated on PI-929/931 and> 67% and < 75% level limits as indicated on U-928/930.

c. Valve SI-851 C closed. ITS limits for SI Accumulators:

Pressure of 600 -660 psig. Level of 61.5 -80.4%. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 8 Standard:

Examiner's Note: Comment: Performance Step: 9 Standard:

Examiner's Note: Comment: 2008 NRC SIM b Page 7 of 11 PERFORMANCE INFORMATION Stop the operating SI Pump Operating SI Pump stopped. Form ES-C-1 Verify both SI Pump Area Cooling units (HVH-6A and 68) are OFF Verifies HVH-6A and 68 are OFF. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 11 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 10 Close SI-869, 81 HOT LEG HDR Standard:

Valve SI-869 closed and independently verified closed. Examiner's Note: When an independent verification of Valve SI-869 is requested, inform the candidate that the valve has been independently verified closed. Comment:

Performance Step: 11 Place the Control Power Defeat switch for SI-869 in the DEFEAT position.

Standard:

Examiner's Cue: Examiner's Note: Comment: 2008 NRC SIM b Valve SI-869 control power switch has been positioned to DEFEAT. When an independent verification of SI-869 Control Power switch is requested, inform the candidate that the switch has been independently verified in the DEFEAT position.

When switch is positioned to DEFEAT position, amber light above the switch will extinguish.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 11 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 12 IF the Refueling Water Purification Pump was stopped in Step B.2.1.1.f, THEN perform the following:

Standard:

Examiner's Note: Comment: Terminating Cue: STOP TIME: 200B NRC SIM b

Open SFPC-B05B, RWST RETURN.

Start the Refueling Water Purification Pump. Candidate determines that the RWST purification was NOT in progress from the initial conditions and places Nt As in these steps. END OF TASK SI Accumulator "C" has been filled to clear the low level alarm. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 11 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM b Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM b NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM b Page 11 of 11 JPM CUE SHEET

The plant is operating at 100% RTP. Form ES-C-1

SI ACCUM C HIILO LVL (APP-002-E4) alarm has been received and actions have been reviewed by the RO.

OP-202, Section 8.2.1.1 Initial Conditions have been completed.

Refueling Water Purification is NOT in progress.

You are the Licensed Dedicated Operator referred to in OP-202.

Safety Injection Pump "A" has been walked down and pre-start checks are complete.

The CRSS briefs and has directed you to fill SI Accumulator "C" to reset the low level alarm lAW OP-202, Section 8.2.1. NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Isolate Ruptured S/G lAW PATH-2. 038 EK3.02 4.4/4.5 038 EA2.09 3.2/3.3 038 EA 1.11 3.8/3.9 038 EA 1.16 4.4/4.3 038 EA1.18 4.0/3.9 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 01000109605 2008 NRC SIM c Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant ------READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue: 2008 NRC SIM c

The plant was operating at 100% RTP.

RCS depressurization led to a Reactor Trip and Safety Injection.

S/G "A" has been identified as ruptured.

Grid location 8-6 (Maintain at least ONE S/G available for RCS Cooldown) of PATH-2 has just been reached.

Supplement G actions have NOT been completed.

S/G "A" is isolated per PATH-2 and Supplement N. PATH-2, Revision 17 and Supplement N, Revision 35. PATH-2, Revision 17 and Supplement N, Revision 35. None The CRSS directs you to completely isolate S/G "A" starting at PATH-2 grid location 8-6 (Ruptured S/G identified) in preparation for a rapid cooldown.

NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Time Critical Task: NO Validation Time: 20 minutes SIMULATOR SETUP 1. IC-614. 3. If IC-614 is not available, reset simulator to IC-13 and perform the following:

a. Override MSIV V1-3A to the OPEN position -IMF MSS03A f:FAIL_ TO_CLOSE.

b. Override MSIV V1-3A OPEN / CLOSED indication AS IS -lOR doMSSDD00498 f:OFF and lOR doMSSDD0049C f:ON. c. Insert 300 GPM tube rupture on S/G A -MFI SGN02A. d. Carry out actions of PATH-1 and PATH-2 until Step 8-6 is reached then FREEZE. 4. Ensure PATH-2 is marked up to Step 8-6. Have a copy of SUPPLEMENT N available for the operator to use and mark up. 2008 NRC SIM c NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 15 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

STARTTIME:

__ _ Performance Step: 1 Standard:

Examiner's Note: Comment:

Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM c Maintain at least one S/G available for RCS cooldown.

Operator identifies S/Gs "B" and "c" are available for RCS cooldown.

Verify ruptured Steam Line PORV setpoint at 1035 psig using status board. Operator adjusts potentiometer to 3.36, steam line PORV setpoint at 1035 psig, by comparing Status Board setpoint for S/G "A" PORV with potentiometer setting for RV1-1. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 3 Standard:

Examiner's Note: Comment: Performance Step: 4 Standard:

Examiner's Note: Comment: 2008 NRC SIM c Page 4 of 15 PERFORMANCE INFORMATION Form ES-C-1 Verify RCS temp less than 547 of prior to MSIV closure. Operator dumps steam to lower RCS temperature below 547 of using Steam Line PORVs or Condenser Steam Dumps.

Condenser Steam Dumps:

Take PC-464B to MANUAL and adjust valve position using UP or DOWN pushbuttons.

PC-464B in Automatic, adjust potentiometer to a lower setting to reduce RCS temperature.

Steam Line PORVs:

Adjust Potentiometer to OPEN or CLOSE PORV. Close ruptured S/G MSIV AND MSIV bypass. After RCS temperature less than 547 of, Operator attempts to close MSIV. MSIV will NOT close. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Note: Comment: Performance Step: 6 Standard:

Examiner's Note: Comment: 2008 NRC SIM c Page 5 of 15 PERFORMANCE INFORMATION Ruptured S/G MSIV AND MSIV Bypass Closed. Form ES-C-1 Operator responds NO, MSIV A will not close. Will transition to Supplement N to complete the isolation.

The Operator will go to Supplement N to address the alternate method of isolating the ruptured S/G. Supplement N Actions Verify BOTH Turbine Stop Valves CLOSED. (Step 1) Operator verifies BOTH Turbine Stop Valves indicate CLOSED on the RTGB. Turbine Stop and Bypass Valves were closed when the plant tripped. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 7 Standard:

Examiner's Note: Comment: Performance Step: 8 Standard:

Examiner's Note: Comment: 2008 NRC SIM c Page 6 of 15 PERFORMANCE INFORMATION Form ES-C-1 Verify ALL Condenser Steam Dump Valves CLOSED (Step 2) Operator closes the condenser dump isolation valves, and verifies that ALL valves indicate CLOSED (GREEN).

NE COND DUMP 1324A-1

NW COND DUMP 1324B-1

SE COND DUMP 1324A-2

W COND DUMP 1324B-3

SW COND DUMP 1324B-2 Condenser steam dump valves can be closed by placing PC-4648 in MAN and closing ALL valves OR place the Steam Dump Control to OFF. Verify ALL MSR Purge Valves CLOSED (Step 3) Operator verifies valves MS-V1-6-1 A, MS-V1-6-1 B, MS-V1-6-2A and MS-V1-6-2B are closed at the RTGB by observing green lights illuminated the MSR Purge isolation valves. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 9 Standard:

Examiner's Note: Comment:

Performance Step: 10 Standard:

Examiner's Note: Comment: 2008 NRC SIM c Page 7 of 15 PERFORMANCE INFORMATION Verify ALL MSR Shutoff Valves CLOSED (Step 4) Form ES-C-1 Operator verifies MS-V1-5-1 A, 1 B, 2A, & 2B valves are closed at the RTGB by observing green lights illuminated the MSR Shutoff isolation valves. Go To Step 6 to address the S/G "A" MSIV NOT closing. (Step 5) Verify the S/G "B" & "C" MSIVs CLOSED. (Step 6) Operator closes MSIVs V1-3B and V1-3C for S/Gs "B" & "C". NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 15 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 11 Verify steam supply valve to SDAFW pump from S/G "A" CLOSED. (Step 7) Standard:

Operator CLOSES V1-8A, Steam Shutoff and Goes to Step 14. Examiner's Cue: Examiner's Note: Comment:

Performance Step: 12 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC SIM c Dispatch an Operator to perform the following: (Step 14) a) Check BOTH the Turbine Stop Valve Bypass valves MS-297 & 298 CLOSED. b) Close Gland Seal Steam Supply Inlet Valve, GS-31. c) Close ALL Condenser Steam Dump Trap Isolation valves

MS-128, PRV-1324A-2, Trap T-67 Inlet

MS-133, PRV-1324A-1, Trap T-66 Inlet

MS-139, PRV-1324B-2, Trap T-69 Inlet

MS-145, PRV-1324B-1, Trap T-68 Inlet

MS-148, PRV-1324B-3, Trap T-70 Inlet Operator directs AO to close and / or verify the valves closed. When directed by operator, acknowledge request. Report that all valves are closed. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 15 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 13 Check ALL actions of Supplement N complete. (Step 15) Standard:

Operator informs CRSS that ALL actions of Supplement N are complete.

Examiner's Note: This completes the actions of Supplement N, the Operator should now resume PATH-2 at Step 8-8. Comment: Performance Step: 14 Use intact Steam Line PORVs for steam dump. Standard:

Operator uses intact steam line PORVs for steam dump (S/G '8' and 'C' only). Examiner's Note: Comment: Performance Step: 15 Ruptured S/G isolated from at least one intact S/G. Standard:

Operator answers YES, Ruptured S/G is isolated from at least one S/G. Examiner's Note: Comment: 2008 NRC SIM c NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 16 Standard:

Examiner's Note: Comment: Page 10 of 15 PERFORMANCE INFORMATION Form ES-C-1 WHEN ruptured S/G press decreases below 1035 psig THEN verify ruptured steam line PORV closed. Operator verifies PORV RV1-1 closed when S/G 'A' pressure less than 1035 psig. Performance Step: 17 IF MDAFW pump is not available, THEN maintain at least one S/G supply to SDAFW pump. Standard:

Operator verifies both MDAFW pumps available.

Examiner's Note: Comment: Performance Step: 18 Close ruptured S/G steam shutoff to SDAFW pump. Standard:

Operator verifies MS-V1-8A closed. Examiner's Note: Comment: 2008 NRC SIM c NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 15 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 19 Verify S/G blowdown isolation and sample valves closed. Standard:

Operator verifies S/G 'A' blowdown isolation and sample valves closed (FCV-1930 A&B, FCV-1933 A&B) by Phase A panel status light illuminated on RTGB. Examiner's Note: Phase A panel status light illuminates when all of the blowdown and sample isolation valves for S/G A are closed. Comment:

Performance Step: 20 Standard:

Booth Operator Note: Comment: 2008 NRC SIM c Candidate may use SPDS function for Containment to verify that all S/G Blowdown and Sample valves are closed. Locally close warmup steam supply from ruptured S/G to SDAFW pump. Operator dispatches an AO to locally close warmup steam supply from S/G 'A' to SDAFW pump. When directed by operator, acknowledge request. Close valve MS-20 by selecting Remote Function MSS047 (IRF MSS047 f:O). Report back that valve is closed. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 15 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 21 Locally close MSIV above and below seat drains from ruptured S/G. Standard:

These are locked valves that are part of the CV Integrity boundary in the steam lines and do not require local action to verify the valves are shut. These valves are normally locked closed and a dedicated operator is provided to close them in the event that an accident takes place. It is expected that if a valve has been opened the CRSS would be aware of it. The Operator may dispatch an AO to close MSIV MS-V1-3A above and below seat drains from S/G 'A'. Booth Operator Note: If directed by operator, acknowledge request. Report back valves closed. Comment: Performance Step: 22 Isolate feed flow to any ruptured S/G that is faulted unless needed for RCS cooldown.

Standard:

Operator determines that the S/G 'A' is not faulted. Examiner's Note: Comment:

Performance Step: 23 When ruptured S/G level greater than 8% [18%] then isolate feed flow. Standard:

Operator checks level greater than 8% and isolates feed flow to S/G 'A' by closing V2-14A and V2-16A. Examiner's Note: Comment: 2008 NRC SIM c NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 24 Standard:

Booth Operator Note: Comment: Terminating Cue: STOP TIME: 2008 NRC SIM c Page 13 of 15 PERFORMANCE INFORMATION Form ES-C-1 Open breakers for any V1-8, V2-14, and V2-16 valve closed to isolate ruptured S/G. Operator contacts AO to open breakers for V1-8A, V2-14A and V2-16A. IRF EPSMCC5_189 f:RACK_OUT IRF EPSMCC10_262 f:RACK_OUT IRF EPSMCC10_264 f:RACK_OUT IRF EPSMCC9_255 f:RACK_OUT Note: Valve V2-16A has 2 power supplies, Normal and Emergency.

Ruptured SIG has been isolated lAW Supplement N. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 14 of 15 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM c Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM c NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM c Page 15 of 15 JPM CUE SHEET

The plant was operating at 100% RTP. Form ES-C-1

RCS depressurization led to a Reactor Trip and Safety Injection.

S/G "A" has been identified as ruptured.

Grid location 8-6 (Maintain at least ONE S/G available for RCS Cooldown) of PATH-2 has just been reached.

Supplement G actions have NOT been completed.

The CRSS directs you to completely isolate S/G "A" starting at grid location 8-6 (Maintain at least ONE S/G available for RCS Cooldown) of PATH-2 in preparation for a rapid cooldown.

NUREG 1021, Revision 9, Supplement 1

PERFORM SUPPLEMENT N FOR RUP.TURED S/G USE INTACT STEAM LINE PORVs FOR STEAM DUMP RUPTURED S/G ISOLATED FROM AT LEA,s-;.3I-O-si

.... ONE INTACT S/G NO VERIFY RUPTURED STEAM RUPTURED S/G MSIV MSIV BYPASS CLOSED YES AT WHEN RUPTURED S/G PRESS DECREASES BELOW 1035 PSIG THEN VERIFY RUPTURED STEAM LINE PORV . LOSED CLOSE RUPTURED S/G STEAM SHUTOFF TO SDAF'I' PUMP LOCALL Y CLOSE WARMUP STEAM SUPPLY FROM RUPTURED S/G TO SDAFW PUMP LOCALL Y CLOSE MSIV ABOVE AND BELOW SEAT DRAINS FROM RUP1URED S/G ISOLATE FEED FLOW TO ANY RUPTURED S/G THAT IS FAULTED UNLESS NEEDED FOR RCS COO DOWN OPEN BREAKERS FOR ANY V1-B, V2-14 V2-16 VALVE CLOSED TO ISOLATE RUPTURED S/G YES YES ANY S/G WITH UNCONTROLLED LEVEL INCREASE NO ANY S/G SAMPLE WITH HIGH ACTIVITY NO NO R-31A, B, AND C NO RAD LEVELS NORMAL YES R-19A, B, C R-15 RAD LEVELS NORMAL YES SEARCH FOR AND ATTEMPT TO IDENTIFY RUPTURED S/G EPP-Supplements INSTRUCTIONS SUPPLEMENTS CONTINUOUS USE Supplement N Rev. Page RESPONSE NOT OBTAINED Isolation of a Ruptured SIG From Intact SIGs (Page 1 of 5) erify BOTH Turbine Stop Valves

-CLOSED 35 72 Local operation of the Steam Dump valves below is via reverse acting handwheels.

ALL Condenser Steam Dump -CLOSED Yf6

NE COND DUMP (l324A-l)

NW COND DUMP (l324B-l)

SE COND DUMP (l324A -2) COND DUMP (l324B-3) COND DUMP (l324B-2)

ALL MSR PURGE Valves -* MS-Vl-6-1A

MS-Vl-6-1B

MS-Vl-6-2A

MS-Vl-6-2B of 89 EPP-Supplements INSTRUCTIONS SUPPLEMENTS CONTINUOUS USE Supplement N Rev. Page RESPONSE NOT OBTAINED Isolation of a Ruptured S/G From Intact S/Gs (Page 2 of 5) . . Verify ALL Valves -CLOSED

MS-Vl-5-1A

MS-Vl-5-1B

MS-Vl-5-2A

MS-Vl-5-2B This procedure is designed to handle ONLY one stuck open MSIV. Go To Appropriate Step From Following Table: STUCK MSIV !/sTEP -c..Yl-3A L :-/ Vl-3B Vl-3C The B & C

MSIV Vl-3B 9 12 S/G MSIVs -MSIV Vl-3C . erify Steam Supply Valve To -SDAFW Pump From S/G "A"-CLOSED Vl-8A, STEAM SHUTOFF To Step 14 35 73 of 89 EPP-Supplements INSTRUCTIONS SUPPLEMENTS CONTINUOUS USE Supplement N Rev. Page RESPONSE NOT OBTAINED Isolation of a Ruptured S/G From Intact S/Gs (Page 3 of 5) 9. Verify The A & C S/G MSIVs -CLOSED

MSIV Vl-3A

MSIV Vl-3C 10. Verify Steam Supply Valve To SDAFW Pump From S/G "B"-CLOSED

Vl-8B, STEAM SHUTOFF 11. Go To Step 14 12. Verify The A & B S/G MSIVs -CLOSED

MSIV Vl-3A

MSIV Vl-3B 13. Verify Steam Supply Valve To SDAFW Pump From S/G "C"-CLOSED

Vl-8C, STEAM SHUTOFF 35 74 of 89 Rev. 35 EPP-Supplements SUPPLEMENTS Page 75 of 89 INSTRUCTIONS RESPONSE NOT OBTAINED CONTINUOUS USE Supplement N Isolation of a Ruptured SIG From Intact SIGs (Page 4 of 5)

Actions:

BOTH the TURBINE STOP BYPASS Valves -CLOSED

MS-297

MS-298 Gland Seal Steam Supply GS-31, STEAM SUPPLY ALL Condenser Steam Trap Isolation Valves

MS-128, PRV-1324A-2 TRAP T-67 INLET

MS-133, PRV-1324A-1 TRAP T-66 INLET

MS -139, PRV-1324B-2 TRAP T-69 INLET

MS-145, PRV-1324B-1 TRAP T-68 INLET MS-148, PRV-1324B-3 TRAP T-70 INLET Actions Supplement N -a. Perform the following:

1) Verify ALL Governor valves are closed. 2) Contact Plant Operations Staff to intiate action to fail the valves closed. WHEN ALL actions have been completed, THEN notify the CRSS that Supplement N is complete.

IF an action can NOT be completed, THEN notify the CRSS of its status.

EPP-Supplements INSTRUCTIONS SUPPLEMENTS CONTINUOUS USE Supplement N Rev. Page RESPONSE NOT OBTAINED Isolation of a Ruptured S/G From Intact S/Gs (Page 5 of 5) tify The CRSS That Supplement Is Complete -END -35 76 of 89 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Manually Initiate Containment Spray lAW PATH-1. 026 A3.01 4.3/4.5 026 A4.01 4.5/4.3 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 01026100101 2008 NRC SIM d Simulated Performance:

Actual Performance:

_.:....:X_

Plant x Classroom Simulator

---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the RO.

The plant was operating at 100% RTP, 15 minutes ago an automatic Reactor Trip and Safety Injection was initiated.

PATH-1 has been implemented and is complete through grid location B-6, 'Restart Battery Chargers within 30 minutes of power loss using OP-601'.

Foldout "A" is in effect. Task Standard:

Containment Spray is manually aligned lAW PATH-1. Required Materials:

PATH-1, REACTOR TRIP AND SAFETY INJECTION, Rev. 18 General

References:

PATH-1, REACTOR TRIP AND SAFETY INJECTION, Rev. 18 Handouts:

PATH-1, REACTOR TRIP AND SAFETY INJECTION, Rev. 18 Initiating Cue: The CRSS has directed you to continue PATH-1 execution.

Time Critical Task: NO Validation Time: 10 minutes 2008 NRC SIM d NUREG 1021, Revision 9, Supplement 1

Appendix C 1. IC-61S. 2. SCN: 006_JPM_SS.

2008 NRC SIM d Job Performance Measure Worksheet SIMULATOR SETUP Form ES-C-1 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment:

Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM d CV pressure remained below 10 psig. Candidate checks CV pressure and determines it has NOT remained below 10 psig. Verify CV Spray initiated.

Identifies CV Spray has NOT been initiated.

NO CV Spray pumps are running, SI-880Al8/C/D are closed. The candidate may depress the CV Spray push buttons, but they will be unsuccessful.

The candidate may also return to Foldout "A" to stop RCPs due to low subcooling.

NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 3 Standard:

Examiner's Note: Comment: Performance Step: 4 Standard:

Examiner's Note: Comment: 2008 NRC SIM d Page 4 of 8 PERFORMANCE INFORMATION Form ES-C-1 Verify all CV Spray pumps running with valves properly aligned. Candidate attempts to start CV Spray Pumps "A" and "B", and open SI-845 and SI-880 valves. Candidate should recognize and report that CV Spray Pump "A" will NOT start. Acknowledge candidates report. Starting CV Spray Pump "8" and aligning "8" train valves satisfies the requirement of the JPM. Supplement 8 valves and required positions for CV Spray Train 8: SI-8448, PUMP 8 INLET -OPEN SI-8458, SAT DISCH -OPEN SI-845C, SAT THROTTLING

-THROTTLED TO -12 GPM SI-880C, PUMP 8 DISCH -OPEN SI-880D, PUMP 8 DISCH -OPEN Note: Opening either SI-880C or SI-880D will provide CV Spray flow path to the CV. Verify approximately 12 GPM spray additive tank flow. Candidate observes FI-949 indicates

-20 GPM and manually adjusts SI-845C until flow is -12 GPM. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 5 Standard:

Examiner's Note: Comment:

Performance Step: 6 Standard:

Examiner's Note: Comment: 2008 NRC SIM d Page 5 of 8 PERFORMANCE INFORMATION Verify Phase B isolation valves closed. Form ES-C-1 Candidate shuts Phase B isolation valves CCW-716A OR 716B, CCW-730, CCW-626 OR 735 and CVC-381 using RTGB control switches.

Only 1 of either CCW-716A or B is required for completion.

Only 1 of either CCW-626 or 735 is required for completion.

Supplement B valves that will close on a Phase B signal: CVC-381, SEAL WTR RTRN ISO FCV-626, THERM BAR FLOW CONT CC-735, THERM BAR OUT ISO CC-716A, CCW TO RCP ISO CC-716B, CCW TO RCP ISO CC-730, BRG OUTLET ISO MSIV AND MSIV BYPs Stop all RCPs. Candidate places all RCP control switches to STOP. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 7 Standard:

Examiner's Note: Comment: Performance Step: 8 Standard:

Examiner's Note: Comment: Termination:

STOP TIME: 2008 NRC SIM d Page 6 of 8 PERFORMANCE I N FORMATION Verify all MSIVs and MSIV Bypasses closed. Form ES-C-1 Candidate verifies all MSIVs and MSIV Bypasses closed by placing the control switches for the MSIVs to CLOSE. Locally open breaker for HVS-1 at MCC-5, CMPT 7 J within 60 minutes of SI initiation.

Candidate contacts AO to open breaker for HVS-1. JPM is complete when the candidate has established one Train of CV Spray and the Inside AO has been contacted to open the breaker for HVS-1. At least 1 train of CV Spray has been initiated.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM d Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM d NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM d Page 8 of 8 JPM CUE SHEET

You are the RO. Form ES-C-1

The plant was operating at 100% RTP, 15 minutes ago an automatic Reactor Trip and Safety Injection was initiated.

PATH-1 has been implemented and is complete through grid location B-6, 'Restart Battery Chargers within 30 minutes of power loss using OP-601 '.

Foldout "A" is in effect. The CRSS has directed you to continue PATH-1 execution.

NUREG 1021, Revision 9, Supplement 1

SUPPLEMENT M AUTOMATIC?

STEAM LINE YES ISOLATION REQUIRED NO VERIFlf BOTH EDGs RUNNING )K ( RESTART CHARGERS WIT IN 30 MIN OF POWER LOSS USING OP-501 )K /' CV PRESS REMAINED BELOW 10 PSIG /' AUTOMATIC NO / STEAM LINE ISOLATION

/ INITIATED

"-/' /' VERIFY ALL MSIVs AND '\

CLOSED: LOCALLY OPEN BREAKER FOR HVS-1, AT MCC-5 CMPT 7J WITHIN 60 MIN ,OF SIINITIATION X RCS PRESS YES / GREATER THAN 1350 PSIG [1250 PSIGJ NO /"' 1 VERIFY CV SPRAY INITIATED I VERIFY ALL CV SPRAY PUMPS RUNNING WITH VALVES "'--PROPERLY ALIGNED , ( VERIFY APPROXIMATELY 12 GPM SPRAY ADDITIVE TANK FLOW ( VERIFY PHASE B ISOLATION VALVES CLOSED 'I' l STOP ALL RCPs EPP-Supplements SUPPLEMENTS CONTINUOUS USE Supplement B Phase BAnd CV Spray Component Alignment (Page 1 of 1) Rev. Page establish Phase B Containment Isolation, verify the following valves -CLOSED Cooling

CVC-38l, SEAL WTR RTRN ISO

FCV-626, THERM BAR FLOW CONT

CC-735, THERM BAR OUT ISO

CC-7l6A, CCW TO RCP ISO

CC-7l6B, CCW TO RCP ISO

CC-730, BRG OUTLET ISO AND MSIV BYPs -CLOSED establish CV Spray, perform the following:

valves positioned as follows:

SI PUMP A INLET OPEN

SI-844B, PUMP B INLET -OPEN

S! 8'lSA, gAT DIgCH -OPEN

SI-845B, SAT DISCH -OPEN 35 20

SI-845C, SAT THROTTLING

-THROTTLED TO APPROXIMATELY 12 GPM .. S!. 880A, PUMP A DIbCH OPEN

SI 88GB, PUHP 0 11 DISCH OPEN .

SI-880C, PUMP B DISCH -OPEN

SI-880D, PUMP B DISCH -OPEN to procedure and step in effect. -END -of 89 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Perform a Post LOCA Cooldown and Depressurization lAW EPP-8. 063 K3.02 3.5/3.7 002 K1.08 4.5/4.6 00009 EA 1 .13 4.4/4.4 00009 EA2.15 3.3/3.4 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 01000102805 2008 NRC SIM e Simulated Performance:

Actual Performance:

X Classroom X Plant -"-'--Simulator

---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Plant was initially at 100% power.

RCS depressurization resulted in a Reactor Trip and Safety Injection.

PATH-1 has directed the crew to EPP-8, POST LOCA COOLDOWN AND DEPRESSURIZATION.

You are the Reactor Operator.

EPP-8 has been completed through Step 28.

CV Pressure is at its maximum value reached during the transient.

Task Standard:

SI Accumulators are either isolated or depressurized lAW EPP-8. Required Materials:

EPP-8, Revision 16, Post LOCA Cooldown and Depressurization.

General

References:

EPP-8, Revision 16, Post LOCA Cooldown and Depressurization.

Handouts:

EPP-8, Revision 16, Post LOCA Cooldown and Depressurization.

2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Initiating Cue: Time Critical Task: Validation Time: 1. IC # 612. Job Performance Measure Worksheet Form ES-C-1 The CRSS has directed you to continue with EPP-8 until the SI Accumulators have been isolated.

NO 17 minutes SIMULATOR SETUP 3. EPP-8 marked up as completed through Step 28. 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment: Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM e STARTTIME:

__ Determine if One SI Pump should be stopped: Check SI Pumps -Any Running (Step 29.a). Determines that 2 SI Pumps are running. Determine if One SI Pump should be stopped: Determine required RCS Subcooling from Table: Conditions: -3 Charging Pumps Running -NO RCPs running -2 SI Pumps Running Required RCS Subcooling is 70 [93] degrees F. Determines from table that required RCS Subcooling is 70 degrees F. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Examiner's Note: Comment: Performance Step: 4 Standard:

Examiner's Note: Comment:

Performance Step: 5 Standard:

Comment: 2008 NRC SIM e Page 4 of 13 PERFORMANCE INFORMATION Form ES-C-1 Check RCS Subcooling

-Less than required subcooling.

Determines that RCS subcooling is -149 degrees F which is more than the required sUbQooling. ( ,-, 1 Go To Step 29.1 If, , Check PZR level-Greater than 24% [45%]. Determines that PZR level is greater than required level. PZR is full. Stop one SI Pump. Candidate stops either SI Pump "A" or "C". NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 6 Standard:

Examiner's Note: Examiner's Cue: Comment: Performance Step: 7 Standard:

Examiner's Note: Comment: 2008 NRC SIM e Page 5 of 13 PERFORMANCE INFORMATION Check RCS pressure -Stable or Increasing.

Form ES-C-1 Determines that RCS pressure is decreasing due to stopping the SI Pump. Step 29.h RNO action will hold candidate until pressure is stable or increasing and then proceed back to Step 29.a. RCS pressure will stabilize at -1220 psig and should take -4 minutes to stabilize after the SI Pump is secured. After -1 minute has elapsed, inform the operator that RCS pressure is stable. Determine if One SI Pump should be stopped: Check SI Pumps -Any Running (Step 29.a) Determines that one SI Pump is running. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 8 Standard:

Examiner's Note: Comment:

Performance Step: 9 Standard:

Examiner's Note: Comment: 2008 NRC SIM e Page 6 of 13 PERFORMANCE INFORMATION Determine if One SI Pump should be stopped: Determine required RCS Subcooling from Table: Conditions: -3 Charging Pumps Running -NO RCPs running -1 SI Pump Running Required RCS Subcooling is 165 [191] degrees F. Form ES-C-1 Determines from table that required RCS Subcooling is 165 degrees F. Check RCS Subcooling

-Less than required subcooling.

Determines that RCS subcooling is -125 degrees F which is less than the required subcooling.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 13 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 10 Check RCS Hot Leg temperatures

-Less than 320 [300] degrees F. Standard:

Determines that RCS Hot Leg temperatures are -440 degrees F. Go To Step 32. ( M);) Examiner's Note: Comment: Performance Step: 11 Check SI Reinitiation Criteria as follows:

Check RCS Subcooling

-Greater than 35 [55] degrees F

Check PZR Level-Greater than 10% [32%] Standard:

Determines that both conditions are satisfied.

Examiner's Note: RCS Subcooling is 125 degrees F and PZR level is 100%. Comment: 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 13 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 12 Determine if SI Accumulators should be isolated:

Check RCS subcooling

-Less than 35 [55] degrees F Standard:

Determines that RCS subcooling is greater than specified.

! Go To Step 33.d. l Examiner's Note: RCS Subcooling is 125 degrees F. Comment:

Performance Step: 13 Check PZR Level-Greater than 10% [32%]. Standard:

Determines that PZR Level is greater than specified limits. Examiner's Note: PZR level is 100%. Comment: 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 13 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 14 Isolate SI Accumulators as follows: Standard:

Examiner's Note: Comment: Locally close the breakers for

SI-865C, ACCUMULATOR C DISCHARGE (MCC-5 CMPT 9F)

SI-865A, ACCUMULATOR A DISCHARGE (MCC-5 CMPT 14F)

SI-8658, ACCUMULATOR 8 DISCHARGE (MCC-6 CMPT 10J) Contacts the Inside and Outside AOs to close the breakers for the SI Accumulator Discharge Valves on MCC-5 and 6. The Inside and Outside AOs will communicate back to the Reactor Operator that the breakers are closed as requested.

Valves SI-865A1B/C will have RED open indication on the RTGB.

Performance Step: 15 Verify all ACCUM DISCHs -CLOSED. SI-865A, SI-8658, SI-865C. Standard:

Control switches are placed in the closed position.

Candidate should note that SI-865A and SI-8658 close but SI-865C has dual indication (RED and GREEN position lights ILLUMINATED)

Go To Step 34.b. RNO Examiner's Note: Comment: 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 13 PERFORMANCE INFORMATION

Performance Step: 16 Vent any unisolated accumulator as follows: Verify SI-855, ACC NITROGEN ISO, is closed. Standard:

Candidate determines that valve SI-855 is closed. Examiner's Note: Comment: Form ES-C-1

Performance Step: 17 Open the appropriate ACCUM VENT valve: SI-853C. Standard:

Candidate opens valve SI-853C to align SI Accumulator "c" to the vent path. Examiner's Note: Comment: 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 13 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 18 Open HIC-936, ACC VENT HDR FLOW. Standard:

Candidate opens HIC-936 by turning the valve potentiometer in the clockwise direction to open the valve and depressurize SI Accumulator "c" to the CV atmosphere.

Examiner's Note: APP-002-F4, SI ACCUM C HI/LO PRESS, will clear and come back in as the accumulator is depressurized.

Comment: Termination:

STOP TIME: 2008 NRC SIM e APP-036-C9, CV N2 HDR HI/LO PRESS, will be received when HIC-936 is opened. Once candidate notes that SI Accumulator "C" pressure is decreasing, examiner can terminate the JPM at his discretion.

END OF TASK SI Accumulators are isolated andlor depressurizing.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 13 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM e Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM e NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM e Page 13 of 13 JPM CUE SHEET

Plant was initially at 100% power. Form ES-C-1

RCS depressurization resulted in a Reactor Trip and Safety Injection.

PATH-1 has directed the crew to EPP-8, POST LOCA COOLDOWN AND DEPRESSURIZATION.

You are the Reactor Operator.

EPP-8 has been completed through Step 28.

CV Pressure is at its maximum value reached during the transient.

The CRSS has directed you to continue with EPP-8 until the SI Accumulators have been isolated.

NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Task No.: Remove N-44 from service lAW OWP-JPM No.: 011. 015 A4.02 3.9/3.9 015 A4.03 3.8/3.9 NRC Examiner:

Date: Form ES-C-1 01015100501 2008 NRC SIM f Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant ------READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

The plant is operating at 100% RTP.

No equipment is out of service.

I&C has requested a clearance on N-44 to replace the high voltage power supply.

This clearance and work scope will render the N-44 input to QPTR inoperable.

You are the BOP operator.

The CRSS has completed the required pre-job briefing.

QPTR meets the SR 3.2.4.2 requirement.

Reactor Engineering has been contacted to perform a Flux Map. Task Standard:

Power Range Channel NI-44 removed from service lAW OWP-011, NI-4. Required Materials:

OWP-011, NI-4 ERFIS Computer General

References:

OWP-011, NI-4 2008 NRC SIM f NUREG 1021, Revision 9 Appendix C Handouts:

Initiating Cue: Time Critical Task: Validation Time: 1.IC # 616. OWP-011, NI-4 Job Performance Measure Worksheet Form E8-C-1 You are directed by the CRSS to remove N-44 from service lAW OWP-011, NI-4. NO 10 minutes SIMULATOR SETUP 3. OP RO at RO ERFI8 terminal and OP BOP at BOP ERFI8 terminal.

2008 NRC 81M f NUREG 1021, Revision 9 Appendix C Page 3 of 10 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment: 2008 NRC SIM f STARTTIME:

__ Remove NI-44 from ERFIS scan: NIN0044A REMOVED NI-44 removed from ERFIS scan. Removal from scan can be performed by the following actions: Select F3 = MENU on the bottom of the ERFIS screen Select ADMIN (ADMINISTRATIVE FUNCTIONS MENU) Select DR (DEURES POINT FROMrrO SCAN OR ALARM) Select DELETE SCAN ENTER POINT ID Removal from scan can be performed by the following actions: If candidate knows the Turn On Code (TOC), he can type in DR and hit ENTER to go directly to the DR screen Select DELETE SCAN ENTER POINT ID APP-005-D6, Delta Flux Warning I Status will be received and a printout initiated for the CAOC Alarm Report. "CHANNEL #4 NOW OUT OF SERVICE with reading noted as 0000 ??" NUREG 1021, Revision 9 Appendix C

Performance Step: 2 Standard:

Examiner's Note: Comment: Performance Step: 3 Standard:

Examiner's Note: Comment: 2008 NRC SIM f Page 4 of 10 PERFORMANCE INFORMATION DROPPED ROD MODE switch: BYPASS. Form ES-C-1 On NI-44 drawer, NI-44 DROPPED ROD MODE switch selected to BYPASS. APP-005-D4, NIS TRIP/DROP ROD BYPASS will alarm when a Dropped Rod Mode switch is placed in BYPASS. DROPPED ROD BYPASS on the NI-44 drawer front will ILLUMINATE.

NIS ROD DROP BYPASS NI-44 Status Light: ILLUMINATED.

The candidate observes the NIS ROD DROP BYPASS NI-44 status light on RTGB Section B is illuminated.

NUREG 1021, Revision 9 Appendix C

Performance Step: 4 Standard:

Examiner's Note: Comment: Performance Step: 5 Standard:

Examiner's Note: Comment: 2008 NRC SIM f Page 5 of 10 PERFORMANCE INFORMATION Form ES-C-1 NI-44 OUT OF SERVICE TRIP SWITCH: TRIPPED. In the rear of NI-44 cabinet, the candidate positions the NI-44 OUT OF SERVICE TRIP SWITCH to the TRIPPED position. (Toggle switch in the UP position)

Operator determines that independent verification is not required due to the bistable status light is not illuminated prior to positioning the NI-44 OUT OF SERVICE TRIP SWITCH. This trips the 108% High Flux bistable for NI-44. Bistable light HI POW RANGE HI FLUX NC44R: ILLUMINATED.

The candidate determines that bistable light HI POW RANGE HI FLUX NC44R is illuminated on Bistable Status Panel B. APP-005-A4, PR SINGLE CH HI RANGE ALERT will be received when bistable is actuated.

OVERPOWER TRIP HIGH RANGE light on NI-44 drawer front will illuminate NUREG 1021, Revision 9 Appendix C

Performance Step: 6 Standard:

Examiner's Note: Comment:

Performance Step: 7 Standard:

Examiner's Note: Comment: 2008 NRC SIM f Page 6 of 10 PERFORMANCE INFORMATION ROD STOP BYASS switch: BYPASS PR 44. Form ES-C-1 On the Miscellaneous Control and Indication Panel, the candidate places the ROD STOP BYPASS switch to the BYPASS PR 44 position.

COMPARATOR CHANNEL DEFEAT switch: Select PR 44. On the Comparator and Rate drawer, the candidate places the COMPARATOR CHANNEL DEFEAT switch to select PR 44 position.

COMPARATOR DEFEAT light illuminates on the drawer above the switch. NUREG 1021, Revision 9 Appendix C

Performance Step: 8 Standard:

Examiner's Note: Comment:

Performance Step: 9 Standard:

Examiner's Note: Comment: 2008 NRC SIM f Page 7 of 10 PERFORMANCE INFORMATION DETECTOR CURRENT COMPARATOR Drawer: UPPER SECTION Switch: Select PR 44. Form ES-C-1 On the Detector Current Comparator drawer, the candidate selects PR 44 with the Upper Section switch. CHANNEL DEFEAT light for Upper Section illuminates when switch is selected out of NORMAL. DETECTOR CURRENT COMPARATOR Drawer: LOWER SECTION Switch: Select PR 44. On the Detector Current Comparator drawer, the candidate selects PR 44 with the Lower Section switch. CHANNEL DEFEAT light for Lower Section illuminates when switch is selected out of NORMAL. NUREG 1021, Revision 9 Appendix C Page 8 of 10 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 10 NI-44 INSTRUMENT POWER FUSES: REMOVED. Standard:

Candidate determines that this step is not required and N/As. Examiner's Cue: If candidate asks, inform him that I&C personnel will deenergize the drawer after AS FOUND readings are taken. Examiner's Note: This action is NtA if power is > P-10 or the reactor is in Modes 3 through 6 (ITS Table 3.3.1-1).

Comment:

Performance Step: 11 Bistable light LOW POW RANGE HI FLUX NC44P: ILLUMINATED.

Standard:

Candidate determines that this step can be signed or N/A'd. Examiner's Cue: Examiner's Note: Comment: Terminating Cue: STOP TIME: 2008 NRC SIM f This bistable is normally in the tripped condition (ILLUMINATED) at this power level. The candidate may sign for the step or Nt A the step. N-44 has been removed from service lAW OWP-011, NI-4. NUREG 1021, Revision 9 Appendix C Page 9 of 10 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM f Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Form ES-C-1 Examiner's Signature:

Date: -----------------------------

2008 NRC SIM f NUREG 1021, Revision 9 Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM f Page 10 of 10 JPM CUE SHEET

The plant is operating at 100% RTP.

No equipment is out of service. Form ES-C-1

I&C has requested a clearance on N-44 to replace the high voltage power supply.

This clearance and work scope will render the N-44 input to QPTR inoperable.

You are the BOP operator.

The CRSS has completed the required pre-job briefing.

QPTR meets the SR 3.2.4.2 requirement.

Reactor Engineering has been contacted to perform a Flux Map. You are directed by the CRSS to remove N-44 from service lAW OWP-011, NI-4. NUREG 1021, Revision 9 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Task No.: Respond to a Loss of CCW lAW AOP-JPM No.: 014. 008 K1.02 3.3/3.4 008 K3.03 4.1/4.2 026 AK3.03 4.0/4.2 NRC Examiner:

Date: Form ES-C-1 01000106705 2008 NRC SIM g Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant ------READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

The plant is operating at 100% power.

No equipment is out of service.

You are the Reactor operator.

Task Standard:

AOP-014 actions taken to ensure the RCPs are not damaged. Required Materials:

AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION, Revision 24 General

References:

APP-001-A4 AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION, Revision 24 Handouts:

None Initiating Cue: The CRSS is involved with a security situation and has told you to take the necessary actions for any alarm conditions that might arise. Time Critical Task: NO 2008 NRC SIM g NUREG 1021, Revision 9, Supplement 1

Appendix C Validation Time: 15 minutes 1. IC # 617 2. SCN: 006_JPM_S7 Job Performance Measure Worksheet SIMULATOR SETUP Form ES-C-1 3. On cue from the Chief Examiner, insert a 2000 GPM CCW piping rupture inside the CV. 2008 NRC SIM g NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 13 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment: Performance Step: 2 Standard:

Examiner's Note: Comment: 2008 NRC SIM g START TIME: __ _ Candidate refers to APP-001-A4.

Candidate observes rapidly lowering CCW Surge Tank level. Candidate takes recommended action from APP-001-A4 and enters AOP-014, CCW System Malfunction Implement The EALs. (Step 1) Candidate notifies supervision of EAL implementation.

Candidate is not responsible for implementing EALs NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Examiner's Note: Comment:

Performance Step: 4 Standard:

Examiner's Note: Comment:

Performance Step: 5 Standard:

Examiner's Note: Comment: 2008 NRC SIM g Page 4 of 13 PERFORMANCE INFORMATION Make PA Announcement For Procedure Entry. Form ES-C-1 Candidate makes announcement for AOP-014 entry using the PA system. Go To Appropriate Section For Indicated Malfunction. (Step 2) Candidate proceeds to Section A based on loss of CCW inventory.

Determine if pump cavitation is occurring or imminent:

Check Surge Tank Level < 5%. OR

Check CCW Pump Discharge Pressure (Local) AND Flow -WIDE OSCILLATIONS.

Candidate determines that CCW Surge Tank is < 5% level and that pump cavitation is imminent.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 6 Standard:

Examiner's Note: Comment:

Performance Step: 7 Standard:

Examiner's Note: Comment:

Performance Step: 8 Standard:

Examiner's Note: Comment: 2008 NRC SIM g Page 5 of 13 PERFORMANCE INFORMATION Check Reactor CRITICAL. (Step 2) Candidate determines that the Reactor is critical.

Verify the Reactor is Tripped. (Step 3) Form ES-C-1 Candidate depresses the Reactor Trip pushbutton to trip the Reactor and verify the Reactor is tripped. Stop ALL RCPs. (Step 4) Candidate stops ALL Reactor Coolant Pumps using the Control switches on the RTGB. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 9 Standard:

Examiner's Cue: Comment:

Performance Step: 10 Standard:

Examiner's Note: Comment: 2008 NRC SIM g Page 6 of 13 PERFORMANCE INFORMATION Form ES-C-1 Go To PATH-1 while continuing with this procedure. (Step 5) Candidate informs CRSS to enter PATH-1 while the Candidate continues in AOP-014. Cue or acknowledge the candidate that the CRSS and the BOP will continue in PATH-1 and the RO will continue in AOP-014. Lockout CCW Pumps:

Place AND hold all CCW Pump switches in STOP position.

Check APP-001-F5, CCW PMP LO PRESS, ILLUMINATED.

Release CCW Pump Switches.

Candidate places ALL CCW pump switches to STOP and holds them while verifying APP-001-F5 is illuminated.

The Candidate may ask and receive assistance from the BOP to hold one of the CCW Pump switches.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 11 Standard:

Examiner's Note: Comment:

Performance Step: 12 Standard:

Examiner's Note: Comment: 2008 NRC SIM g Page 7 of 13 PERFORMANCE INFORMATION Form ES-C-1 Dispatch Operator To Perform Attachment 3, CCW Leak Search, While Continuing With Procedure. (Step 11) Candidate contacts the AO to perform Attachment to identify the source of the leak. Check CV For CCW Break Using Control Room Indications. (Step 12.a) Candidate monitors ERFIS trends and CV WATER LEVEL (White Sump Lights) and determines that CV water level has increased.

CV Water level increase from -4.00 inches to 8 inches and stabilize.

Bottom white lights for CV Keyway Sump are illuminated.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 13 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 13 Check CV location of CCW break. (Step 12.b) Standard:

Candidate determines that CCW leak is in the CV. Examiner's Note: Comment: Performance Step: 14 Standard:

Examiner's Note: Comment: 2008 NRC SIM g Inform personnel performing leak search that the leak location is in the CV. (Step 12.c) Candidate informs AO performing leak search of leak in CV. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 13 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 15 Determine RCP alarm status. (Step 13) Standard:

Candidate recognizes that:

APP-001-B1, RCP BRG COOL WTR LO FLOW, is illuminated.

APP-001-B3, RCP A BEARING HI TEMP, is NOT illuminated.

APP-001-D3, RCP B BEARING HI TEMP, is NOT illuminated.

APP-001-F3, RCP C BEARING HI TEMP, is NOT illuminated.

Examiner's Note: Comment: Performance Step: 16 Check Reactor CRITICAL. (Step 14) Standard:

Candidate determines that the Reactor is NOT critical.

Examiner's Note: Comment: 2008 NRC SIM g NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 13 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 17 Verify Control Rods are Tripped. (Step 14.a RNO) Standard:

Candidate verifies ALL Control Rods are inserted.

Examiner's Note: Comment: Performance Step: 18 Stop ALL RCPs. (Step 14.b RNO) Standard:

Candidate verifies that ALL Reactor Coolant Pumps are stopped. Examiner's Note: Comment: 2008 NRC SIM g NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 19 Standard:

Examiner's Cue: Comment: Termination:

STOP TIME: 2008 NRC SIM g Page 11 of 13 PERFORMANCE INFORMATION Form ES-C-1 Close The Following Valves To Isolate CCW To The RCPs: (Step 18)

CC-716A, CCW TO RCP ISO

CC-716B, CCW TO RCP ISO

CC-730, BRG OUTLET ISO

CC-735, THERM BAR OUT ISO

FCV-626, THERM BAR FLOW CO NT Candidate uses RTGB switches to close the following valves:

CC-716A, CCW TO RCP ISO

CC-716B, CCW TO RCP ISO

CC-730, BRG OUTLET ISO

CC-735, THERM BAR OUT ISO

FCV-626, THERM BAR FLOW CONT CCW valves are closed to isolate CCW piping rupture in CV. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 13 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM 9 Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM g NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM g Page 13 of 13 JPM CUE SHEET

The plant is operating at 100% power.

No equipment is out of service.

You are the Reactor operator.

Form ES-C-1 The CRSS is involved with a security situation and has told you to take the necessary actions for any alarm conditions that might arise. NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Limit Radiation Exposure in Response to Radiation Alarm lAW AOP-005. 072 A 1.01 3.4/3.6 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 01000101405 2008 NRC SIM h Simulated Performance:

Actual Performance:

_.:...:X_

Plant x Classroom Simulator

---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue: 2008 NRC SIM h

The plant is at 100% power.

AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE, is being performed.

An unscheduled Containment entry is in progress to determine the leak location.

APP-036-L5, CV PERSONNEL HATCH DOOR OPEN, is ILLUMINATED.

Actions of AOP-005, Attachment 12, have been completed satisfactorily.

APP-036-D8, Revision 62 AOP-005, Revision 27 APP-036-D8, Revision 62 AOP-005, Revision 27 AOP-005, Revision 27 You are the Control Room Operator.

Respond to plant conditions.

NUREG 1021, Revision 9, Supplement 1

Appendix C Time Critical Task: NO Validation Time: 12 minutes 1. IC # 613. 2. SCN: 006_JPM_S3.

Job Performance Measure Worksheet SIMULATOR SETUP Form ES-C-1 3. Verify that the R-11/12 selector switch is in the CV position.

2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 14 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note: Comment: Performance Step: 2 Standard:

Examiner's Note: Comment: Performance Step: 3 Standard:

Examiner's Note: Comment: 2008 NRC SIM h START TIME: __ _ Locates proper procedure and required information.

Locates APP-036-D8, PROCESS MONITOR HI RAD. RR-1 Point #11 (R-12) is in alarm. Determine process channel in alarm condition.

Determines alarming channel is R-12, CV AIR AND PLANT VENT RADIOACTIVE GAS. I F the cause of the alarm is known to be the movement of radioactive material or is an expected alarm due to actions under operator control, THEN no further actions for this APP are required. (Step 1) (NO) The cause for the alarm is not known and personnel inside the CV are currently searching for the leak source. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 4 Standard:

Examiner's Note: Comment: Performance Step: 5 Standard:

Examiner's Note: Comment:

Performance Step: 6 Standard:

Examiner's Note: Comment: 2008 NRC SIM h Page 4 of 14 PERFORMANCE INFORMATION Form ES-C-1 Observe affected radiation monitor for radiation levels and evidence of short term spiking. (Step 2) (NO) R-12 is in high alarm and no appearance of short term spiking is noted. IF short term spiking is evidenced, THEN allow the indicated level to decrease prior to performing Step 4. (Step 3) No short term spiking is observed.

Determine if the alarm is valid by momentarily depressing the ALARM/RESET pushbutton for R-12 monitor (Step 4.4). Candidate depresses the RED ALARM/RESET pushbutton This action will cause the RED light and APP-036-DB to extinguish.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 7 Standard:

Examiner's Note: Comment: Performance Step: 8 Standard:

Examiner's Note: Comment: Performance Step: 9 Standard:

Examiner's Note: Comment: 200B NRC SIM h Page 5 of 14 PERFORMANCE INFORMATION Form ES-C-1 IF the alarm returns, THEN refer to AOP-005 (Step 4.5). APP-036-DB and the RED ALARM/RESET module on R-12 monitor returns, thus the alarm is valid. Make PA announcement for procedure entry into AOP-005 due to an R-12 alarm. Candidate makes PA announcement for AOP-005 entry due to R-12 alarm. Use non-performed attachments listed below for Radiation Monitors in alarm. Candidate selects Attachment 12 due to R-12 in alarm. NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 10 Check R-11/12 selector switch -SELECTED TO CV (Step 1). Standard:

Candidate locates selector switch on the Radiation Monitoring Panel and checks that the switch is selected to the CV position.

Examiner's Note: There is an illuminated white light above the switch that is labeled as CV. Comment: Performance Step: 11 Check RCS temperature

-Greater than 200 degrees F. Standard:

Unit is at 100% power. RCS Tavg is 575.9 degrees F. Examiner's Note: Comment: Performance Step: 12 Check EOP network procedures -IMPLEMENTED.

Standard:

Candidate determines that EOP procedures have NOT been implemented and proceeds to Step 5. Examiner's Note: Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 14 PERFORMANCE INFORMATION Performance Step: 13 Check personnel-IN CV. (Step 5) Form ES-C-1 Standard:

Determines that personnel are presently in CV from the initial conditions.

Examiner's Note: APP-036-L5, CV PERSONNEL HATCH DOOR OPEN, is illuminated.

Comment:

Performance Step: 14 Place VLC switch to EMERG position. (Step 6) Standard:

VLC switch placed in the EMERG position.

Examiner's Note: Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 14 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 15 Depress and Hold CV Evacuation Horn pushbutton for 15 seconds. (Step 7) Standard:

Depresses and holds CV evacuation horn pushbutton for 15 seconds Examiner's Note: Comment:

Performance Step: 16 Announce the following over Plant PA System: ATTENTION ALL PERSONNEL.

ATTENTION ALL PERSONNEL.

A HIGH RADIATION ALARM HAS BEEN RECEIVED ON CV VENT PROCESS MONITOR R-12. ALL NON-ESSENTIAL PERSONNEL EVACUATE CV UNTIL FURTHER NOTICE. (Step 8) Standard:

Announces condition requiring CV evacuation, stating that alarm is on R-12. Examiner's Note: Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 17 Repeat CV Evacuation announcement over PA System. (Step 9) Standard:

Candidate repeats announcement.

Examiner's Note: Comment: Performance Step: 18 Place VLC switch to NORM position. (Step 10) Standard:

Returns VLC switch to NORM position.

Examiner's Note: Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 19 Check Containment Ventilation Isolation valves closed. (Step 11) Standard:

Determines Containment Ventilation Isolation valves closed by valve position indication and/or status lights. Examiner's Note: Containment Ventilation Isolation Panel Status Lights will be pink with valves in the proper position.

Comment: Individual valves can be observed on the RTGB for position indication.

Amber lights lit for the CV Ventilation Isolation Signal Relay V-1 and V-2 on the bottom of the Radiation Monitoring Panel. CV Purge valves V12-6, V12-7, V12-8, V12-9 CV Pressure Reliefs V12-10, V12-11 CV Vacuum Reliefs V12-12, V12-13

Performance Step: 20 Place the following CV IODINE REMOVAL FAN control switches to PREPURGE position:

HVE-3 and HVE-4. (Step 12) Standard:

Places switches for HVE-3 and HVE-4 to PREPURGE position and verifies proper operation by fan and damper indication.

Examiner's Note: RTGB indications for HVE-3 and 4: Fans ON by RED lights illuminated and PREPURGE aligned by YELLOW lights illuminated.

Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 21 Request RC to perform a background radiation check at Radiation Monitors R-11 and R-12. (Step 13) Standard:

Contacts RC personnel to perform background checks at the radiation monitors.

Examiner's Cue: RC personnel will perform background radiation checks at R-11 and R-12. Comment: Performance Step: 22 Determine if Primary System leakage is occurring. (Step 14) Standard:

Determines that leakage is occurring.

Examiner's Note: Initial conditions stated entry had been made into AOP-016 to determine the location of the RCS leakage. Comment: Performance Step: 23 Go To the Main Body, Step 1 b, of this procedure. (Step 16) Standard:

Proceeds to Main Body, Step 1 b, of AOP-OOS. Examiner's Note: Comment: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 24 Use non-performed attachments listed below for radiation monitors in alarm -NONE to be addressed.

Standard:

R-12 attachment has already been addressed and there are no other Radiation monitors in alarm, thus none are remaining to be addressed.

Examiner's Note: Comment: Performance Step: 25 Implement the EALs. (Main Body, Step 2) Standard:

Informs the SSO of the need to implement the EALs. Examiner's Note: SSO acknowledges the information provided.

Comment: END OF TASK Termination:

AOP-005 actions for an R-12 alarm have been completed.

STOP TIME: 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C Page 13 of 14 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC SIM h Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC SIM h NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC SIM h Page 14 of 14 JPM CUE SHEET

The plant is at 100% power. Form ES-C-1

AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE, is being performed.

An unscheduled Containment entry is in progress to determine the leak location.

APP-036-LS, CV PERSONNEL HATCH DOOR OPEN, is ILLUMINATED.

You are the Control Room Operator.

Respond to plant conditions.

NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Task No.: Trip the Reactor from the Rod Drive MG JPM No.: Set Room 029 EA 1.11 3.9/4.1 029 EA1.12 4.1/4.0 NRC Examiner:

Date: Form ES-C-1 01311100906 2008 NRC In-Plant i Simulated Performance:

x Actual Performance:

Classroom

___ Simulator Plant ---x READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Initiating Cue: Time Critical Task: Validation Time: 2008 NRC IP i

You are the Inside AO.

Plant is operating at 100% RTP.

The Reactor cannot be tripped from the Control Room.

FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, is being implemented.

BOTH Rod Drive Motor Generator Circuit Breakers "A" and "B" are opened locally. FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, Rev. 17. FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, Rev. 17. The CRSS directs you to the Rod Drive MG Set Room to trip the following breakers:

Reactor Trip Breakers "A" and "B" and Rod Drive Motor Generator "A" and "B" Circuit Breakers.

YES 5 minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

EXAMINER'S NOTE: FRP-S.1, Steps 1 and 2 are immediate action steps and the AOs would be expected to execute these steps from memory without procedure in hand. START TIME: ___ _ Performance Step: 1 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP i These immediate action steps are represented by Steps 1, 2, 3 and 4 of this JPM, thus Steps 1 through 4 are time critical steps. TIME CRITICAL START TIME: ____ _ Trip Reactor Trip Breaker "A". Simulates tripping Reactor Trip Breaker "A" by depressing the trip button in the center of the breaker. As Found position of the breaker is CLOSED with RED CLOSED flag in the breaker status window. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker trip pushbutton in the center of the cubicle door has been pressed and the breaker RED CLOSED flag remains in the breaker's status window. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 2 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP i Page 3 of 8 PERFORMANCE INFORMATION Trip Reactor Trip Breaker "B". Form ES-C-1 Simulates tripping Reactor Trip Breaker "B" by depressing the trip button in the center of the breaker. As Found position of the breaker is CLOSED with RED CLOSED flag in the breaker status window. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker trip pushbutton in the center of the cubicle door has been pressed and the breaker RED CLOSED flag remains in the breaker's status window. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 3 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP i Page 4 of 8 PERFORMANCE INFORMATION Trip Motor Generator "A" Circuit Breaker. Form ES-C-1 Simulates tripping Motor Generator "A" Circuit Breaker. As Found position of the breaker is CLOSED with RED CLOSED flag in the breaker status window or indication on the MG Set panel has the RED light illuminated and the GREEN light extinguished.

BOTH Motor Generator Circuit Breakers "A" and "B" must be tripped locally for a success path in this JPM. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker trip pushbutton in the center of the cubicle door has been pressed and the breaker OPEN GREEN flag has appeared in the breaker's status window. Noise was heard as the breaker re-positioned.

OR The operator may choose to trip the breaker with the pistol grip switch on the MG Set panel. After locating and describing how the breaker would be tripped using the pistol grip switch, inform the candidate that the pistol grip switch has been taken to the TRIP position and the RED light is extinguished and the GREEN light is illuminated.

Noise was heard as the breaker re-positioned.

NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 4 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP i Page 5 of 8 PERFORMANCE INFORMATION Trip Motor Generator "B" Circuit Breaker. Form ES-C-1 Simulates tripping Motor Generator "B" Circuit Breaker. As Found position of the breaker is CLOSED with RED CLOSED flag in the breaker status window or indication on the MG Set panel has the RED light illuminated and the GREEN light extinguished.

BOTH Motor Generator Circuit Breakers "A" and "B" must be tripped locally for a success path in this JPM. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker trip pushbutton in the center of the cubicle door has been pressed and the breaker OPEN GREEN flag has appeared in the breaker's status window. Noise was heard as the breaker re-positioned.

OR The operator may choose to trip the breaker with the pistol grip switch on the MG Set panel. After locating and describing how the breaker would be tripped using the pistol grip switch, inform the candidate that the pistol grip switch has been taken to the TRIP position and the RED light is extinguished and the GREEN light is illuminated.

Noise was heard as the breaker re-positioned.

TIME CRITICAL STOP TIME: ____ _ NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Cue: Examiner's Note: Comment: Page 6 of 8 PERFORMANCE INFORMATION Form ES-C-1 Inform the Control Room that Motor Generator "A" and "B" Circuit Breakers have been tripped open and that Reactor Trip Breakers "A" and "B" would NOT open. Contacts the Control Room and reports that Motor Generator "A" and "8" Circuit Breakers have been tripped open and that Reactor Trip Breakers "A" and "B" would NOT open. As the CRSS, acknowledge the candidate's report. END OF TASK Termination:

Rod Drive MG Set Circuit Breakers "A" and "B" are tripped open. STOP TIME: 2008 NRC IP i NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC IP i Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC IP i NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC IP i Page 8 of 8 JPM CUE SHEET

You are the Inside AO.

Plant is operating at 100% RTP. Form ES-C-1

The Reactor cannot be tripped from the Control Room.

FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, is being implemented.

The CRSS directs you to the Rod Drive MG Set Room to trip the following breakers:

Reactor Trip Breakers "A" and "B" and Rod Drive Motor Generator "A" and "B" Circuit Breakers.

NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Task No.: Energize PZR Heaters from Emergency JPM No.: Busses (Turbine Building Actions) lAW EPP-21. 027 AA 1.05 3.3/3.2 056 AA 1.21 3.3/3.3 NRC Examiner:

Date: Form ES-C-1 04010100101 2008 NRC In-Plant j Simulated Performance:

x Actual Performance:

Classroom Simulator Plant x ------READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

2008 NRC IP j

The plant has experienced a loss of offsite AC power.

EOP Network has been implemented.

EPP-4, REACTOR TRIP RESPONSE, has directed the implementation of EPP-21, ENERGIZING PRESSURIZER HEATERS FROM EMERGENCY BUSSES.

You are the Outside AO.

Emergency Bus E-1 is powered by EDG "A".

You have been given Key # 69, "PZR Heater Breaker Arm Switch" and a set of large fuse pullers.

The breakers listed in Step # 3 cannot be verified open from the RTGB. Align breakers in preparation for energizing PZR Backup Heater Group A lAW EPP-21. EPP-21, ENERGIZING PRESSURIZER HEATERS FROM EMERGENCY BUSSES, Rev. 15. Key # 69 Large Fuse Pullers EPP-21, ENERGIZING PRESSURIZER HEATERS FROM EMERGENCY BUSSES, Rev. 15. NUREG 1021, Revision 9, Supplement 1

Appendix C Initiating Cue: Time Critical Task: Validation Time: 2008 NRC IP j Job Performance Measure Worksheet Form ES-C-1 The CRSS has directed you to perform the Turbine Building actions required to energize PZR Heaters from the emergency bus in accordance with EPP-21, Steps 3 through 6. NO 20 minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 10 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

START TIME: __ _ Performance Step: 1 Standard:

Examiner's Note: Examiner's Cue: Comment:

Performance Step: 2 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP j Obtain a copy of the appropriate procedure.

Candidate obtains copy of EPP-21 from the lAO office, WCC, Control Room or other valid location.

When candidate states they need to obtain a copy of EPP-21, ask him where to locate one. If correct, provide him with a copy of EPP-21. Verify OPEN SST-2A TO 480V SYSTEM BKR 52/1 B. (Step 3, First Bullet) Breaker 52/1 B opened by depressing the trip pushbutton in the center of the breaker cubicle door. As Found position of the breaker is CLOSED with RED CLOSED flag in the breaker status window. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker trip pushbutton in the center of the cubicle door has been pressed and the breaker OPEN GREEN flag has appeared in the breaker's status window. Noise was heard as the breaker re-positioned.

NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 3 Standard:

Examiner's Note: Examiner's Cue: Comment: Performance Step: 4 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP j Page 4 of 10 PERFORMANCE INFORMATION Form ES-C-1 Verify OPEN 480V BUS 1 MAIN BKR 52/2B. (Step 3, Second Bullet) Breaker 52/2B opened by depressing the trip pushbutton in the center of the breaker cubicle door. As Found position of the breaker is OPEN with GREEN OPEN flag in the breaker status window. Breaker indicates OPEN with GREEN flag in breaker status window. Verify OPEN 480V BUS 1-2A TIE BKR 52/5B. (Step 3, Third Bullet) Breaker 52/5B opened by depressing the trip pushbutton in the center of the breaker cubicle door. As Found position of the breaker is OPEN with GREEN OPEN flag in the breaker status window. Breaker indicates OPEN with GREEN flag in breaker status window. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Note: Examiner's Cue: Comment: Performance Step: 6 Standard:

Examiner's Note: Examiner's Cue: Comment: Page 5 of 10 PERFORMANCE INFORMATION Form ES-C-1 Verify OPEN 480V BUS E1 MAIN BKR 52/18B. (Step 3, Fourth Bullet) Breaker 52/18B opened by depressing the trip pushbutton located in the center of the breaker cubicle door. As Found position of the breaker is OPEN with GREEN OPEN flag in the breaker status window. Breaker indicates OPEN with GREEN flag in breaker status window. Obtain the following: (Step 4)

Key # 69 to PZR HEATER BKR ARM SWITCH

Large Fuse Pullers Obtain the key and large fuse pullers. Key and large fuse pullers were obtained during the initial conditions.

Ensure that the candidate is clear that the initial conditions provided the necessary materials.

NOTE: 4160V Breaker 52113 is locally opened by rotating the switch counterclockwise to the TRIP position and then pulled out to lock. 2008 NRC IP j NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 7 Standard:

Examiner's Note: Examiner's Cue: Comment: 2008 NRC IP j Page 6 of 10 PERFORMANCE INFORMATION Form ES-C-1 Locally open and Pull-To-Lock STATION SERVICE TRANSFORMER 2A and 2F BKR 52/13 (4160V Bus 2, CMPT-13). (Step 5) Breaker 52/13 opened by turning the breaker control switch counterclockwise to the TRIP position and placed in Pull-To-Lock (Located on 4160V Bus 2, CMPT -13). As Found position of the breaker is CLOSED with RED CLOSED indicator light illuminated on the breaker cubicle door. If candidate decides to look at the breaker by opening the cubicle door, the as found position of the breaker is CLOSED with RED CLOSED flag on the breaker status window. After the candidate locates and describes I simulates how the breaker would be tripped open, inform the candidate the breaker control switch has been rotated counterclockwise and the RED CLOSED indicator has extinguished and the GREEN OPEN indicator has illuminated.

Noise was heard as the breaker re-positioned.

NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 8 Standard:

Examiner's Note: 2008 NRC IP j Page 7 of 10 PERFORMANCE INFORMATION Perform the following: (Step 6) Form ES-C-1 a. Locally verify the following breakers at 480V Bus 1 -OPEN

Pressurizer Heater Backup Group A (CMPT-2C)

Feed to MCC-1 (CMPT-3A)

CV Polar Crane Power Supply (CMPT-3B)

Feed to PP-63 (CMPT -3C)

Construction Facilities Main Disconnect (CMPT-4B)

Spent Fuel Pit Cooling Pump B (CMPT-4C)

Condenser Vacuum Pump A (CMPT-5C)

b. Remove breaker control power fuses from Condenser Vacuum Pump A. (CMPT-5C)

a. All 480V Bus 1 breakers verified OPEN by checking for GREEN OPEN indication or by depressing the TRIP pushbutton in the center of the breaker cubicle door to place the breaker in the OPEN position.

b. Breaker door is opened and control power fuses are removed from Condenser Vacuum Pump A. (CMPT-5C)

As Found position of the following breakers is CLOSED with RED CLOSED indicator light illuminated on the breaker cubicle door: Feed to MCC-1 (CMPT-2C)

Feed to PP-63 (CMPT-3C)

Construction Facilities Main Disconnect (CMPT 4B) The remaining breaker positions may be OPEN or CLOSED, depending on whether they were operating for plant needs at the time of the loss of power. NUREG 1021, Revision 9, Supplement 1

Appendix C Examiner's Cue: Comment: Performance Step: 9 Standard:

Examiner's Note: Examiner's Cue: Comment: Page 8 of 10 PERFORMANCE INFORMATION Form ES-C-1 a. When the breakers are located, and the candidate has simulated pushing the TRIP pushbutton, inform the candidate that GREEN OPEN indication is visible. b. Once the candidate has determined and identified the proper 480V breaker cubicle to remove the control power fuses, present him with the breaker cubicle picture and allow him to identify the fuses and the removal process. When the fuses are identified, inform the candidate that they are removed. Inform the CRSS that the Turbine Building actions of EPP-21 , Steps 3 through 6 have been completed as directed.

Candidate contacts the Control Room and informs the CRSS that the Turbine Building portions of EPP-21 have been completed as directed.

CRSS acknowledges the report. END OF TASK Termination:

EPP-21 Steps 3 through 6 have been completed as directed.

STOP TIME: 2008 NRC IP j NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 10 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC IP i Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC IP j NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC IP j Page 10 of 10 JPM CUE SHEET Form ES-C-1

The plant has experienced a loss of offsite AC power.

EOP Network has been implemented.

EPP-4, REACTOR TRIP RESPONSE, has directed the implementation of EPP-21, ENERGIZING PRESSURIZER HEATERS FROM EMERGENCY BUSSES.

You are the Outside AO.

Emergency Bus E-1 is powered by EDG "A".

You have been given Key # 69, "PZR Heater Breaker Arm Switch" and a set of large fuse pullers.

The breakers listed in Step # 3 cannot be verified open from the RTGB. The CRSS has directed you to perform the Turbine Building actions required to energize PZR Heaters from the emergency bus in accordance with EPP-21 , Steps 3 through 6. NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Manually Start EDG Using Air Start Solenoids 064 A3.01 4.1/4.0 056 AK3.02 4.4/4.7 056 AA2.14 4.4/4.6 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 04064100901 2008 NRC In-Plant k Simulated Performance:

x Actual Performance:

Classroom Simulator Plant X ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Inside AO.

The unit has experienced a total loss of onsite and offsite power.

EPP-1, LOSS OF ALL AC POWER, has been implemented.

Emergency Diesel Generator "B" is out of service for scheduled maintenance to replace the fuel oil filters.

Emergency Diesel Generator "A" failed to start. Task Standard:

Start EDG "A" locally and energize 480V Bus E-1 Required Materials:

EPP-1, Revision 38 General

References:

EPP-1, Revision 38 Initiating Cue: The CRSS has dispatched you to perform EPP-1, starting at Step 10.b. RNO. Time Critical Task: NO Validation Time: 12 minutes 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Cue: Comment:

Performance Step: 2 Standard:

Examiner's Cue: Comment: 2008 NRC IP k STARTTIME:

__ Place the EDG Control Switch in the LOCAL position.

Candidate locates and simulates placing the EDG "A" LOCAL / REMOTE CONTROL switch in the LOCAL position.

EDG "A" LOCAL I REMOTE CONTROL switch is rotated to the LOCAL position and the Local Control WHITE light is ILLUMINATED.

Depress the Local Engine START pushbutton.

Candidate simulates depressing the Local Engine START pushbutton on the EDG "A" Engine Control Panel. EDG "A" does NOT start. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 3 Standard:

Examiner's Cue: Comment:

Performance Step: 4 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 3 of 8 PERFORMANCE INFORMATION Form ES-C-1 If the affected EDG did NOT start from the Engine Control Panel, Then perform the following at the EDG Hand Start valves: Remove the locking pin from the Hand Start valves Lock Bar and remove the Lock Bar. Candidate simulates removing the locking pin from the Hand Start valves Lock Bar and removing the Lock Bar from valves DA-41 and DA-42. Locking pin from the Hand Start valves Lock Bar is removed and the Lock Bar from valves DA-41 and DA-42 is removed. If the affected EDG did NOT start from the Engine Control Panel, Then perform the following at the EDG Hand Start valves: Pull down and hold either of the EDG Hand Start valves until the EDG starts:

DA-41

DA-42 Candidate selects one of the Hand Start valves and simulates pulling down on the handle until the EDG starts. EDG "A" has started and is running at 900 RPM. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Note: Comment: Performance Step: 6 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 4 of 8 PERFORMANCE INFORMATION If either EDG has started, Then Go To Step 11. Form ES-C-1 EDG "A" started and candidate proceeds to Step 11 . Check either Emergency Bus E-1 or E-2 -ENERGIZED.

Candidate observes indication on the EDG "A" Generator Control Panel and notes that 480V Bus E-1 is NOT energized.

GENERATOR AC VOLTS indicates 480 Volts. EMERGENCY BUS AC VOLTS indicates 0 Volts. NORMAL BUS AC VOLTS INDICATES 0 Volts. GENERATOR HERTZ indicates 60 Hz. If candidate requests information from the Control Room, inform him that neither Emergency Bus is energized.

NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 7 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 5 of 8 PERFORMANCE INFORMATION Verify the following for any running EDG: Form ES-C-1

EMERG GEN VOLTS -APPROXIMATELY 480 VOLTS. AND

BRKR 52/17B, EMERG DG A TO BUS E1 -CLOSED. Candidate observes that EDG "A" GENERATOR AC VOLTS indicates

-480 Volts. Candidate closes EDG "A" Output breaker at the EDG Generator Control Panel by placing EDG OUTPUT BKR 52/17B control switch to the CLOSE position.

Indications on the EDG Generator Control panel include Generator AC Volts, Emergency Bus AC Volts and Normal Bus AC Volts. Inform candidate that EDG Generator AC Volts is 480 Volts. Inform candidate that breaker 52117B indication has the GREEN OPEN light illuminated and the RED CLOSED light extinguished when the breaker control switch is located. Inform candidate that breaker 52117B indication has the RED CLOSED light illuminated and the GREEN OPEN light extinguished when the breaker control switch is placed in the closed position.

Generator AC KW indicates 400 KW. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 8 Standard:

Examiner's Cue: Comment: Page 6 of 8 PERFORMANCE INFORMATION Form ES-C-1 If either Emergency Bus is energized, Then Go To Step 12. 480V Bus E-1 is energized at 480 Volts with EDG "A" supplying the bus. Inform the candidate that EMERGENCY BUS AC VOLTS indicates 480 Volts and that Emergency Bus E-1 is energized.

END OF TASK Termination:

EDG "A" started and 480V Bus E-1 energized.

STOP TIME: 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC IP k Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC IP k Page 8 of 8 JPM CUE SHEET

You are the Inside AO. Form ES-C-1

The unit has experienced a total loss of onsite and offsite power.

EPP-1, LOSS OF ALL AC POWER, has been implemented.

Emergency Diesel Generator "8" is out of service for scheduled maintenance to replace the fuel oil filters.

Emergency Diesel Generator "A" failed to start. The CRSS has dispatched you to perform EPP-1, starting at Step 10.b. RNa. NUREG 1021, Revision 9, Supplement 1

Appendix C Facility:

Task Title: KJA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure Worksheet HB ROBINSON Manually Start EDG Using Air Start Solenoids 064 A3.01 4.1/4.0 056 AK3.02 4.4/4.7 056 AA2.14 4.4/4.6 Task No.: JPM No.: NRC Examiner:

Date: Form ES-C-1 04064100901 2008 NRC In-Plant k Simulated Performance:

x Actual Performance:

Classroom Simulator Plant x ------READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

You are the Inside AO.

The unit has experienced a total loss of onsite and offsite power.

EPP-1, LOSS OF ALL AC POWER, has been implemented.

Emergency Diesel Generator "B" is out of service for scheduled maintenance to replace the fuel oil filters.

Emergency Diesel Generator "A" failed to start. Task Standard:

Start EDG "An locally and energize 480V Bus E-1 Required Materials:

EPP-1, Revision 38 General

References:

EPP-1, Revision 38 Initiating Cue: The CRSS has dispatched you to perform EPP-1, starting at Step 10.b. RNO. Time Critical Task: NO Validation Time: 12 minutes 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Cue: Comment:

Performance Step: 2 Standard:

Examiner's Cue: Comment: 2008 NRC IP k START TIME: __ Place the EDG Control Switch in the LOCAL position.

Candidate locates and simulates placing the EDG "A" LOCAL / REMOTE CONTROL switch in the LOCAL position.

EDG "A" LOCAL I REMOTE CONTROL switch is rotated to the LOCAL position and the Local Control WHITE light is ILLUMINATED.

Depress the Local Engine START pushbutton.

Candidate simulates depressing the Local Engine START pushbutton on the EDG "A" Engine Control Panel. EDG "A" does NOT start. NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 3 Standard:

Examiner's Cue: Comment:

Performance Step: 4 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 3 of 8 PERFORMANCE INFORMATION Form ES-C-1 If the affected EDG did NOT start from the Engine Control Panel, Then perform the following at the EDG Hand Start valves: Remove the locking pin from the Hand Start valves Lock Bar and remove the Lock Bar. Candidate simulates removing the locking pin from the Hand Start valves Lock Bar and removing the Lock Bar from valves DA-41 and DA-42. Locking pin from the Hand Start valves Lock Bar is removed and the Lock Bar from valves DA-41 and DA-42 is removed. If the affected EDG did NOT start from the Engine Control Panel, Then perform the following at the EDG Hand Start valves: Pull down and hold either of the EDG Hand Start valves until the EDG starts:

DA-41

DA-42 Candidate selects one of the Hand Start valves and simulates pulling down on the handle until the EDG starts. EDG "A" has started and is running at 900 RPM. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 5 Standard:

Examiner's Note: Comment: Performance Step: 6 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 4 of 8 PERFORMANCE INFORMATION If either EDG has started, Then Go To Step 11. Form ES-C-1 EDG "A" started and candidate proceeds to Step 11. Check either Emergency Bus E-1 or E-2 -ENERGIZED.

Candidate observes indication on the EDG "A" Generator Control Panel and notes that 480V Bus E-1 is NOT energized.

GENERATOR AC VOLTS indicates 480 Volts. EMERGENCY BUS AC VOLTS indicates 0 Volts. NORMAL BUS AC VOLTS INDICATES 0 Volts. GENERATOR HERTZ indicates 60 Hz. If candidate requests information from the Control Room, inform him that neither Emergency Bus is energized.

NUREG 1021, Revision 9, Supplement 1

Appendix C

Performance Step: 7 Standard:

Examiner's Cue: Comment: 2008 NRC IP k Page 5 of 8 PERFORMANCE INFORMATION Verify the following for any running EDG: Form ES-C-1

EMERG GEN VOLTS -APPROXIMATELY 480 VOLTS. AND

BRKR 52/17B, EMERG DG A TO BUS E1 -CLOSED. Candidate observes that EDG "A" GENERATOR AC VOLTS indicates

-480 Volts. Candidate closes EDG "A" Output breaker at the EDG Generator Control Panel by placing EDG OUTPUT BKR 52/17B control switch to the CLOSE position.

Indications on the EDG Generator Control panel include Generator AC Volts, Emergency Bus AC Volts and Normal Bus AC Volts. Inform candidate that EDG Generator AC Volts is 480 Volts. Inform candidate that breaker 52/17B indication has the GREEN OPEN light illuminated and the RED CLOSED light extinguished when the breaker control switch is located. Inform candidate that breaker 52/17B indication has the RED CLOSED light illuminated and the GREEN OPEN light extinguished when the breaker control switch is placed in the closed position.

Generator AC KW indicates 400 KW. NUREG 1021, Revision 9, Supplement 1

Appendix C Performance Step: 8 Standard:

Examiner's Cue: Comment: Page 6 of 8 PERFORMANCE INFORMATION Form ES-C-1 If either Emergency Bus is energized, Then Go To Step 12. 480V Bus E-1 is energized at -480 Volts with EDG "A" supplying the bus. Inform the candidate that EMERGENCY BUS AC VOLTS indicates 480 Volts and that Emergency Bus E-1 is energized.

END OF TASK Termination:

EDG "A" started and 480V Bus E-1 energized.

STOP TIME: 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC IP k Examinee's Name: Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -----------------------------

Form ES-C-1 2008 NRC IP k NUREG 1021, Revision 9, Supplement 1

Appendix C INITIAL CONDITIONS:

INITIATING CUE: 2008 NRC IP k Page 8 of 8 JPM CUE SHEET

You are the Inside AO. Form ES-C-1

The unit has experienced a total loss of onsite and offsite power.

EPP-1, LOSS OF ALL AC POWER, has been implemented.

Emergency Diesel Generator "8" is out of service for scheduled maintenance to replace the fuel oil filters.

Emergency Diesel Generator "A" failed to start. The CRSS has dispatched you to perform EPP-1, starting at Step 10.b. RNa. NUREG 1021, Revision 9, Supplement 1

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