ML100690475

2009 Palisades Initial License Examination Administered Control Room JPMs

ML100690475
Person / Time
Site:	Palisades
Issue date:	05/25/2009
From:	Valos N Operations Branch III
To:	Entergy Nuclear Operations
References
Download: ML100690475 (79)

Text

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS A TITLE: HOT LEG INJECTION USING P-66B AND SPLIT FLOW CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I SYS A JOB PERFORMANCE MEASURE DATA PAGE Task: Establish Hot Leg Injection per in-use EOP Alternate Path: NO Facility JPM #: NEW K/A: 006A2.02 Importance: RO:3.9 SRO: 4.3 K/A Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: loss of flow path Task Standard: Hot Leg Injection flow established via HPSI Pump P-66B using EOP Supplement 20 split flow method.

Preferred Evaluation Location: Simulator _X__ In Plant ______

Preferred Evaluation Method: Perform _X__ Simulate ______

References:

EOP Supplement 20, Hot Leg Injection Via PZR EOP Supplement 4, HPSI and LPSI Flow Curves EOP-4.0, Loss of Coolant Accident Recovery Validation Time: __15__ minutes Time Critical: NO Candidate: ________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 JUNE 2009

JPM: RO/SRO-I SYS A EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

EOP Supplement 20, Hot Leg Injection Via PZR EOP Supplement 4, HPSI and LPSI Flow Curves Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

• Plant was tripped from 100% power.

• EOP-4.0 (Loss of Coolant Accident) has been entered.

• Conditions for initiating Hot Leg Injection per Step 60 are met.

• The normal path for Hot Leg Injection per Step 60 is not available due to HPSI Train 2 to Cold Leg Valve, MO-3080, being failed in the open position.

• HPSI Pump P-66A tripped after SIAS initiated and could not be restarted.

INITIATING CUES:

The CRS has directed you to establish hot leg injection using EOP Supplement 20 section 2.0, the HPSI Pump P-66B and split flow method.

PALISADES NUCLEAR PLANT Page 3 of 9 JUNE 2009

JPM: RO/SRO-I SYS A Proc. Step TASK ELEMENT 1 STANDARD Grade

--- Candidate locates EOP Supplement 20 EOP Supplement 20 is in hand S U Comment:

Evaluator: Provide candidate with a working copy of EOP Supplement 20 Proc. Step TASK ELEMENT 2 STANDARD Grade Operator notes this requirement for future action Record each occurrence of PZR Spray in this JPM.

1 operation with a T greater than 200°F in Operator notes current temperatures for vapor S U the Reactor Logbook. phase, spray lines, and charging: determines requirement is currently not applicable.

Comment:

Proc. Step TASK ELEMENT 3 STANDARD Grade Ensure P-66B is operating within the limits 2 Verifies P-66B flow is within EOP Supplement 4 S U of EOP Supplement 4.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 9 JUNE 2009

JPM: RO/SRO-I SYS A Proc. Step TASK ELEMENT 4 STANDARD Grade Ensure open the following valves:

Charging Line Stop, CV-2111 (already open)

Auxiliary Spray, CV-2117 Verifies or places hand switches in OPEN and 3 Charging Pump Discharge to Train 2, verifies associated Green light OFF and Red S U MO-3072 light ON.

HPSI Pump B Discharge to Train 2, CV-3018 Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade Candidate determines all three Charging Pumps are operating and have electrical power 4 Stop ALL Charging Pumps S U available. Candidate will stop P-55A, P-55B, and P-55C.

Comment:

EVALUATOR NOTE: Candidate may also place Auto/Manual switches on Panel C-12 to MANUAL (this is not required to meet Standard).

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade CLOSE the following valves:

Loop 1A, CV-2113 Places hand switches for CV-2113, CV-2115, CV-1057, and CV-1059 to CLOSE.

5 Loop 2A, CV-2115 S U Verifies Green lights ON and Red lights OFF for Spray, CV-1057 all the above valves.

Spray, CV-1059.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 9 JUNE 2009

JPM: RO/SRO-I SYS A Proc. Step TASK ELEMENT 7 STANDARD Grade Ensure open the following HPSI Train 1 valves:

HPSI Train 1 Loop 1A, MO-3007 Verifies MO-3007, MO-3009, MO-3011, and 6 S U HPSI Train 1 Loop 1B, MO-3009 MO-3013 Red lights ON and Green lights OFF.

HPSI Train 1 Loop 2A, MO-3011 HSPI Train 1 Loop 2B, MO-3013 Comment:

Proc. Step TASK ELEMENT 8 STANDARD Grade CLOSE the following valves:

HPSI Train 2 Loop 2B, MO-3062 Places and holds hand switches for MO-3062, 7 HPSI Train 2 Loop 2A, MO-3064 MO-3064, MO-3066, and MO-3068 to CLOSE S U until Green lights ON and Red lights OFF.

HPSI Train 2 Loop 1B, MO-3066 HSPI Train 2 Loop 1A, MO-3068 Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 9 STANDARD Grade Ensure HPSI flow of greater than or equal Operator checks flow is indicated on FIA-0212 8 to 100 gpm to the Pressurizer through the S U greater than 100 gpm.

charging line is indicated on FIA-0212.

Comment:

PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 2009

JPM: RO/SRO-I SYS A Proc. Step TASK ELEMENT 10 STANDARD Grade Candidate informs the CRS that the Hot Leg Injection using P-66B and split flow

--- CRS informed. S U has been established per EOP Supplement 20 section 2.0.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009

JPM: RO/SRO-I SYS A SIMULATOR OPERATOR INSTRUCTIONS

• Initialize to any at power IC.

• Enter malfunction SI01A (HPSI Pump P-66A fail) on PID SI02.

• Enter malfunction RC01 (Hot Leg Rupture) on PID RC01.

• Enter Overrride for MO-3080 to ON on PNL C-03.

• Trip the Reactor and carry out the immediate actions of EOP-1.0 actions (including tripping of MFW Pumps).

• Trip all Primary Coolant Pumps.

• Take P-66A handswitch to START (to give a red flag = attempt to restart provided in initiating cue.)

• Perform Pre-RAS Actions of EOP Supplement 42.

• Allow to run long enough to bring in RAS, then complete RAS verifications per EOP-4.0 Step 52 and EOP Supplement 42.

PALISADES NUCLEAR PLANT Page 8 of 9 JUNE 2009

JPM: RO/SRO-I SYS A CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• Plant was tripped from 100% power.

• EOP-4.0 (Loss of Coolant Accident) has been entered.

• Conditions for initiating Hot Leg Injection per Step 60 are met.

• The normal path for Hot Leg Injection per Step 60 is not available due to HPSI Train 2 to Cold Leg Valve, MO-3080, being failed in the open position.

• HPSI Pump P-66A tripped after SIAS initiated and could not be restarted.

INITIATING CUES:

The CRS has directed you to establish hot leg injection using EOP Supplement 20 section 2.0, the HPSI Pump P-66B and split flow method.

PALISADES NUCLEAR PLANT Page 9 of 9 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS B TITLE: SWAP PRESSURIZER PRESSURE CONTROL CHANNELS CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I SYS B JOB PERFORMANCE MEASURE DATA PAGE Task: Swap Pressurizer Pressure Control channels Alternate Path: YES Facility JPM #: 2005 NRC Exam K/A: 010A4.01 Importance: RO: 3.7 SRO: 3.5 K/A Statement: Ability to manually operate and/or monitor in the control room: PZR spray valve Task Standard: PIC-0101A placed in service; applicant recognizes failure of PIC-0101A and then switches back to PIC-0101B.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SOP-1A, Primary Coolant System ARP-4, Pressurizer Pressure Off Normal Hi-Lo Validation Time: 15 minutes Time Critical: NO Candidate: ________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 10 JUNE 2009

JPM: RO/SRO-I SYS B EXAMINER COPY ONLY Tools/Equipment/Procedures Needed: SOP-1A, section 7.2.2.b.3 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

• The plant is at steady state 100% power.

• Pressurizer Pressure Controller PIC-0101B is selected and is in AUTO.

• Pressurizer Pressure Controller PIC-0101A is in MANUAL at 50% demand.

INITIATING CUES:

The Control Room Supervisor has directed you to switch Pressurizer Pressure Controllers per SOP-1A for normal rotation of controllers.

PALISADES NUCLEAR PLANT Page 3 of 10 JUNE 2009

JPM: RO/SRO-I SYS B Proc.Step TASK ELEMENT 1 STANDARD Grade Obtain a copy of SOP-1A, Primary Coolant Candidate locates SOP-1A, Primary Coolant

--- S U System procedure. System.

Comment:

Proc.Step TASK ELEMENT 2 STANDARD Grade Determine that Section 7.2.2.b.3 of SOP-1A Reviews Section 7.2.2 PZR Press Control and

--- should be used to alternate PZR Press determines section 7.2.2.b.3 needs to be S U Controllers. performed.

Comment:

EVALUATOR: provide candidate working copy of SOP-1A section 7.2.2.b.3.

Proc.Step TASK ELEMENT 3 STANDARD Grade 3.a Verify controller to be selected in MANUAL. Verifies PIC-0101A is in MANUAL. S U Comment:

Proc.Step TASK ELEMENT 4 STANDARD Grade Adjusts output signal on PIC-0101A to match Adjust output signal on PIC-0101A to match 3.b output signal on PIC-0101B for bumpless S U output signal on PIC-0101B.

transfer.

Comment:

Proc.Step TASK ELEMENT 5 STANDARD Grade PALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009

JPM: RO/SRO-I SYS B Place Selector Switch 1/PRC-0101 to Places Selector Switch 1/PRC-0101 to 3.c S U Channel 'A'. Channel 'A'.

Evaluator: If asked, state that AUTO CONTROL IS DESIRED.

CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade Ensure Pzr Htr Control Channel Selector Ensures Pzr Htr Control Channel Selector 3.d.1 S U Switch in CHAN A & B. Switch in CHAN A & B.

Comment:

Proc.Step TASK ELEMENT 7 STANDARD Grade Ensure PIC-0101A setpoint set at desired 3.d.2 Ensures PIC-0101A setpoint set to 2060 psia. S U PCS pressure.

Comment:

Proc.Step TASK ELEMENT 8 STANDARD Grade Adjust PIC-0101A output to match indicated Adjusts PIC-0101A output to match indicated 3.d.3 Pzr Press (red pointer) with setpoint press Pzr Press (red pointer) with setpoint press S U (Blue pointer). (Blue pointer).

Comment:

Proc.Step TASK ELEMENT 9 STANDARD Grade PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009

JPM: RO/SRO-I SYS B Depress the "A" pushbutton on PIC-0101A Depresses the "A" pushbutton on PIC-0101A to 3.d.4 S U to place it in AUTO. place it in AUTO.

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 10 STANDARD Grade Place the unselected controller in MANUAL Places PIC-0101B in MANUAL with a 50%

3.e S U with a 50% output signal. output signal.

Comment:

NOTE: When PIC-0101B is placed in MANUAL control, after ~ 20 seconds, PIC-0101A output will slowly start to fail high (to 100% output). This will cause Pzr Press. to lower (sprays open, heaters to minimum.)

Proc.Step TASK ELEMENT 11 STANDARD Grade Applicant should recognize the failure by observing the output of PIC-0101A failing Place PIC-0101A back to MANUAL and reduce

---

high. EK-0753 Pzr Press Off Normal Hi-Lo controller output to restore Pzr Press to 2060 S U alarm will also alert applicant of the psia.

problem.

Comment:

EVALUATOR NOTE: Candidate may place 1/PRC-0101 back to Channel 'B'. This is acceptable. If so, proceed with JPM at Task Element 15.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009

JPM: RO/SRO-I SYS B Proc.Step TASK ELEMENT 12 STANDARD Grade ARP-4 referenced for EK-0753 and CRS Refers to ARP-4 window 53 and informs informed of the problem with PIC-0101A.

---

S U CRS of the problem with PIC-0101A. Candidate will inform CRS to refer to ONP-18, Pressurizer Pressure Control Malfunctions.

EVALUATOR: When informed to reference ONP-18, direct the operator to place PIC-0101B back in service in AUTO.

Proc.Step TASK ELEMENT 13 STANDARD Grade 3.a Verify PIC-0101B is in MANUAL. PIC-0101B is in MANUAL. S U Comment:

Proc.Step TASK ELEMENT 14 STANDARD Grade Adjust output signal on PIC-0101B to match Adjusts output signal on PIC-0101B to desired 3.b output signal on PIC-0101A or desired S U output.

output.

Comment:

Proc.Step TASK ELEMENT 15 STANDARD Grade Place selector switch 1/PRC-0101 to Places selector switch 1/PRC-0101 to 3.c S U Channel 'B'. Channel 'B'.

Evaluator: If asked, state that AUTO control is desired.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 7 of 10 JUNE 2009

JPM: RO/SRO-I SYS B Proc.Step TASK ELEMENT 16 STANDARD Grade PZR HTR Channel Selector Switch may be Places PZR HTR Channel Selector Switch in 3.d.1 S U placed in CHAN B position. CHAN B or leaves in CHAN A & B.

Comment:

Evaluator NOTE: Candidate may place switch in CHAN B or leave in CHAN A & B based on note preceding step 3.d.1.

Proc.Step TASK ELEMENT 17 STANDARD Grade Ensure PIC-0101B setpoint set at desired 3.d.2 Ensures PIC-0101B setpoint set at 2060 psia. S U PCS pressure.

Comment:

Proc.Step TASK ELEMENT 18 STANDARD Grade Adjust PIC-0101B output to match indicated Adjusts PIC-0101B output to match indicated 3.d.3 Pzr Press (red pointer) with setpoint press Pzr Press (red pointer) with setpoint press S U (Blue pointer). (Blue pointer).

Comment:

Evaluator NOTE: Correct performance of Task Element 18 or Task Element 19 is Critical. It is preferred to perform both.

CRITICAL STEP Proc.Step TASK ELEMENT 19 STANDARD Grade Depress the "A" pushbutton on PIC-0101B Depresses the "A" pushbutton on PIC-0101B to 3.d.4 S U to place it in AUTO. place it in AUTO.

Comment:

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 JUNE 2009

JPM: RO/SRO-I SYS B SIMULATOR OPERATOR INSTRUCTIONS

• Reset to IC-17.

• Build Event Trigger #1:

o Event ZDI2P(315), this is manual pushbutton on PIC-0101B Place RX05A (PIC-0101A failed high), 20 second time delay, on Event Trigger 1.

PALISADES NUCLEAR PLANT Page 9 of 10 JUNE 2009

JPM: RO/SRO-I SYS B CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• The plant is at steady state 100% power.

• Pressurizer Pressure Controller PIC-0101B is selected and is in AUTO.

• Pressurizer Pressure Controller PIC-0101A is in MANUAL at 50% demand.

INITIATING CUES:

The Control Room Supervisor has directed you to switch Pressurizer Pressure Controllers per SOP-1A for normal rotation of controllers.

PALISADES NUCLEAR PLANT Page 10 of 10 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS C TITLE: OPEN MAIN STEAM ISOLATION VALVES AFTER REACTOR IS CRITICAL CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I/SRO-U SYS C JOB PERFORMANCE MEASURE DATA PAGE Task: Open MSIVs Alternate Path: One MSIV will not open requiring ADV operation to open Facility JPM #: 2007 CERT SRO JPM K/A: 035 K6.01 Importance: RO: 3.2 SRO: 3.6 K/A Statement: Knowledge of the effect of a loss or malfunction of the following will have on the S/Gs: MSIVs Task Standard: Both MSIVs Open, MSIV bypasses closed, ADVs and TBV in AUTO Preferred Evaluation Location: Simulator _X__ In Plant ______

Preferred Evaluation Method: Perform _X__ Simulate ______

References:

SOP-7, Main Steam System Validation Time: __15__ minutes Time Critical: NO Candidate: _________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-7, Main Steam System Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The reactor is critical with power at the POAH. MSIV Bypass valves, MO-0501 and MO-0510 are open. Vacuum is established on the Main Turbine and the secondary plant is in the process of being started up.

INITIATING CUES:

The CRS directs you to open the MSIVs per SOP-7, step 7.2.2.c.

PALISADES NUCLEAR PLANT Page 3 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 1 STANDARD Grade

--- Locate correct procedure Candidate locates SOP-7, section 7.2.2 S U Comment:

Evaluator: Provide candidate with a working copy of SOP-7, section 7.2.2.

Proc. Step TASK ELEMENT 2 STANDARD Grade Candidate contacts Auxiliary Operator to latch 7.2.2.c LATCH MSIV solenoid valves. all MSIV solenoids in the turbine building and 'D' S U bus area.

Comment:

SIM OPERATOR: Use MS36 on P&ID MS02, DO NOT latch 'A' MSIV (MS25) but report that it is complete.

CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade IF MSIVs opened after performance of Candidate determines that CV-0510, 'A' S/G d S U Step 7.2.2c, THEN GO TO Step 7.2.2q. MSIV, did not open. Proceeds to step 7.2.2.e Comment:

Evaluator: Role play as CRS and direct candidate to proceed to step 7.2.2.e, if asked.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 4 STANDARD Grade Candidate performs the following:

___ PLACEs PIC-0511, Turbine Bypass Valve Control to MANUAL.

ENSURE CV-0511, Turbine Bypass to ___ Sets PIC-0511, Turbine Bypass Control e Condenser, remains CLOSED by Valve to CLOSE. S U performing the following: ___ Has AO Close MV-CA390, Turbine Bypass CV-0511 A/S Isolation.

___ Has AO OPEN accumulator drain valve to bleed pressure from CV-0511 accumulator, THEN CLOSE the valve.

Comment:

SIM OPERATOR: Use MS35 on PIDMS03 to close air supply to CV-0511, then notify as AO that air supply is closed and accumulator is bled down Proc. Step TASK ELEMENT 5 STANDARD Grade PERFORM the following notifications of Candidate informs CRS to notify Chemistry and f S U impending Steam Dump operation: to refer to ADMIN 4.00.

Comment:

Evaluator: Notify Candidate that the SE will perform this.

Proc. Step TASK ELEMENT 6 STANDARD Grade Candidate directs Auxiliary Operator to close the following valves in the ADV control cabinet:

CLOSE three of the four Steam Dump Air g Supplies for the MSIV to be opened, listed ___ MV-CA779 S U below: ___ MV-CA780

___ MV-CA781 OR MV-CA782 Comment:

Evaluator NOTE: LCO 3.7.4.A is applicable. If candidate asks, notify them that the CRS will take care of this.

SIM OPERATOR: Use MS18, MS19, MS20 (or MS21) on PID MS01 to close these valves CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 7 STANDARD Grade PLACE HIC-0780A, Steam Generator Candidate:

E-50B Steam Dump to MANUAL.

___ Places HIC-0780A in Manual h, i OPERATE HIC-0780A toward 100% S U OPEN position to equalize DP across ___ Operates manual output lever to open ADV MSIV. until MSIV CV-0510 opens.

Comment:

Evaluator NOTE: If candidate asks, inform them that the required notifications are made.

Evaluator NOTE: CV-0510 will latch when HIC-0780A reaches ~25% output.

CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade WHEN MSIV opens, THEN PLACE Candidate Operates manual output lever to j S U HIC-0780A to CLOSE position. close ADV.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 9 STANDARD Grade Candidate has AO open:

OPEN Steam Dump Air Supplies closed in ___ MV-CA779 k S U Step 7.2.2g above. ___ MV-CA780

___ MV-CA781 OR MV-CA782 Comment:

SIM OPERATOR: Use MS18, MS19, MS20 (or MS21) on PID MS01 to open the valves that were closed in Task Element #6.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 10 STANDARD Grade IF both MSIVs did NOT open, THEN Candidate determines this step is N/A because l REPEAT Steps 7.2.2g through 7.2.2k for S U both MSIVs are now open.

affected MSIV.

Comment:

Proc. Step TASK ELEMENT 11 STANDARD Grade Candidate has AO:

CLOSE CV-0511 accumulator drain valve.

___ CLOSE CV-0511 accumulator drain valve m, n OPEN MV-CA390, Turbine Bypass S U CV-0511 A/S Isol. ___ OPEN MV-CA390, Turbine Bypass CV-0511 A/S Isol.

Comment:

SIM OPERATOR: Use MS35 on PIDMS03 to open air supply to CV-0511.

CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade RETURN HIC-0780A to AUTO or the AS FOUND position. Candidate places HIC-0780A and CV-0511 in o, p AUTO by depressing the 'A' button on their S U RETURN PIC-0511 to AUTO or the AS controllers and verifying the 'A' button lights.

FOUND position.

Comment:

EVALUATOR NOTE: If asked, inform candidate that PIC-0511 and HIC-0780A should be placed back in AUTO.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 7 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 13 STANDARD Grade CLOSE the following valves: Candidate closes MO-0501 and MO-0510 by holding switch in the CLOSE position until q

• MO-0501, MSIV CV-0501 Bypass (MZ-3) S U associated Green light is ON and Red light is

• MO-0510, MSIV CV-0510 Bypass (MZ-2) OFF.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 14 STANDARD Grade Candidate informs the CRS that the MSIVs

--- are open and the MSIV bypasses are CRS informed. S U closed.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C SIMULATOR OPERATOR INSTRUCTIONS IC-12 Open MSIV Bypass Valves Close MSIVs Trip 'B' MFP, start P-8A Ensure Reactor Power is < 2% (limit for MSIV Bypass valves open)[insert Group 4 rods to approximately 35]

Insert the following triggers:

Trigger: 1 Event: ZAO3F(62).gt.0.25 (ADV Controller reaches 25% output)

Action: irf ms25 latch (opens MSIV)

PALISADES NUCLEAR PLANT Page 9 of 10 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS C CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The reactor is critical with power at the POAH. MSIV Bypass valves, MO-0501 and MO-0510 are open. Vacuum is established on the Main Turbine and the secondary plant is in the process of being warmed up.

INITIATING CUES:

The CRS directs you to open the MSIVs per SOP-7 step 7.2.2.c.

PALISADES NUCLEAR PLANT Page 10 of 10 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS D TITLE: WITHDRAW SHUTDOWN GROUP CONTROL RODS CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I/SRO-U SYS D JOB PERFORMANCE MEASURE DATA PAGE Task: Withdraw Shutdown Group Control Rods Alternate Path: YES - 1 rod sticks during withdrawal Facility JPM #: NEW K/A: 001K4.13 Importance: SRO: 3.4 RO: 3.4 K/A Statement: Knowledge of CRDS design features/interlocks which provide for the following: Operation of CRDS controls for withdrawing lingering rods and transferring rods and rod groups.

Task Standard: All Shutdown Group B Control Rods withdrawn 66 inches.

Preferred Evaluation Location: Simulator __X__ In Plant ______

Preferred Evaluation Method: Perform __X__ Simulate ______

References:

SOP-6, Reactor Control System ARP-5, Primary Coolant Pump Steam Generator and Rod Drives Scheme EK-09 (C-12)

Validation Time: __20___ minutes Time Critical: NO Candidate: ________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-6, Reactor Control System ARP-5, Primary Coolant Pump Steam Generator and Rod Drives Scheme Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Preparations for a critical approach are in progress per GOP-3, Mode 3 525°F To MODE 2. GOP-3 is completed through step 2.1.a.

INITIATING CUES:

The Control Room Supervisor has directed you to perform Section 7.1.2 of SOP-6, "Reactor Control System" for withdrawal of Shutdown Group B Control Rods. Section 7.1.1 has already been performed.

PALISADES NUCLEAR PLANT Page 3 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 1 STANDARD Grade

--- Obtains current procedure. Obtains and refers to SOP-6, Section 7.1.2. S U Comment:

Evaluator: Provide a working copy of SOP-6, section 7.1.2 to candidate.

Proc.Step TASK ELEMENT 2 STANDARD Grade SOP-6 Candidate checks PPC (page 420) and/or Ensure all rods of Group A are withdrawn Panel C-02 display to verify Group A rods are S U 7.1.2.a greater than or equal to 128 inches.

above 128 inches.

Comment:

Proc.Step TASK ELEMENT 3 STANDARD Grade SOP-6 Place Group Selector Switch to B position. Group Selector Switch placed in B position. S U 7.1.2.b Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 4 STANDARD Grade SOP-6 Place Mode Selector Switch to MG (Manual Mode Selector Switch placed in MG position. S U 7.1.2.c Group) position.

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 5 STANDARD Grade SOP-6 Operate Raise-Lower Switch to RAISE Raise-Lower Switch place in RAISE position. S U 7.1.2.d position.

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade SOP-6 Monitor Nuclear Instrumentation (NI) for NIs monitored as rods are moved. S U 7.1.2.e response during rod movement.

Comment:

Evaluator Note: Group B rods PIP/SPI difference alarms on PPC are expected alarms as described by SOP-6 section 5.3.

Proc.Step TASK ELEMENT 7 STANDARD Grade SOP-6 Stop movement of rods approximately every Control Rod motion stopped prior to exceeding 33 inches (should not exceed 35 inches) of S U 7.1.2.f 35 inches of movement.

rod movement.

Comment:

Proc.Step TASK ELEMENT 8 STANDARD Grade SOP-6 WHEN rod motion has stopped, THEN Candidate observes SUR indication on Panel S U 7.1.2.f.1 OBSERVE proper reduction in startup rate. C-02 and/or PPC.

Comment:

PALISADES NUCLEAR PLANT Page 5 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 9 STANDARD Grade Uses at least one of following methods to verify all Group B rods are within 2 inches of each other:

SOP-6 PERFORM Control Rod alignment -TURN Rod Selector Switch for Group B S U 7.1.2.f.2 verification through all of its positions AND COMPARE Control Rod positions.

- Use the PPC Control Rod position indication for Group B rods.

Comment:

EVALUATOR NOTE: IF candidate attempts to level Control Rod #15 after first 33-inch pull, as CRS inform them to follow procedure and not level rods until procedure criteria is met (i.e. more than 2 inches).

Proc.Step TASK ELEMENT 10 STANDARD Grade Continue Group B withdrawal:

SOP-6 Operate Raise-Lower Switch to RAISE Raise-Lower Switch place in RAISE position. S U 7.1.2.d position.

Comment:

EVALUATOR NOTE: When Rod 18 is > 45 inches, it will become stuck.

CRITICAL STEP Proc.Step TASK ELEMENT 11 STANDARD Grade SOP-6 Monitor Nuclear Instrumentation (NI) for NIs monitored as rods are moved. S U 7.1.2.e response during rod movement.

Comment:

PALISADES NUCLEAR PLANT Page 6 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 12 STANDARD Grade ARP-5 Control Rod motion stopped by releasing Alarm EK-0911 Rod Position 4 Inches Raise-Lower switch.

Window S U Deviation, Annunciates 11 ARP-5 referenced for window 11 Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 13 STANDARD Grade ARP-5 On PPC display 411, Rod 18 identified OR IDENTIFY affected Control Rod AND extent Window confirm on Panel C-02 by placing Group B S U of its deviation.

11 Selector Switch to 18 Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 14 STANDARD Grade Verifies Rod 18 position is 4 inches lower than ARP-5 remaining rods in Group B using available COMPARE affected rod position with Window indications. Also notes that Rod 15 is more S U secondary rod position.

11 than 2 inches different from remainder of group.

Comment:

Proc.Step TASK ELEMENT 15 STANDARD Grade ARP-5 REPOSITION Control Rod in Manual Window Individual as necessary to clear alarm per Refers to SOP-6, section 7.4. S U 11 SOP-6 Comment:

Evaluator: Provide candidate with a working copy of SOP-6, section 7.4 PALISADES NUCLEAR PLANT Page 7 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 16 STANDARD Grade SOP-6 REFER to Step 4.4.1 SOP-6 Step 4.4.1 reviewed. S U 7.4.a Comment:

NOTE: Step 7.4.b is not applicable; step 7.4.c and d have already been performed in ARP-5 actions.

Proc.Step TASK ELEMENT 17 STANDARD Grade SOP-6 PLACE Rod Selector Switch in the position Rod Selector Switch for Group B placed in S U 7.4.e for the rod to be moved. position 18 Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 18 STANDARD Grade SOP-6 TURN Group Selector Switch to the position Group Selector Switch placed in Group B for the group containing the rod to be S U 7.4.f position.

moved.

Comment:

Proc.Step TASK ELEMENT 19 STANDARD Grade SOP-6 PLACE Mode Selector Switch to MI (Manual Mode Selector Switch placed in MI position. S U 7.4.g Individual) position.

Comment:

NOTE: This deletes the stuck rod malfunction.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 8 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 20 STANDARD Grade

___ Operates ROD CONTROL joystick to RAISE.

SOP-6 Withdraw selected rod to clear 4-inch ___ Rod 18 withdrawn to be within 2.0" of S U 7.4.h deviation alarm. other Group B rods.

___ Observes 4-Inch Deviation alarm clears.

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 21 STANDARD Grade

___ Rod Selector Switch for Group B placed in position 15 SOP-6 ___ Operates ROD CONTROL joystick to Withdraw selected rod to level Rod 15. RAISE. S U 7.4.h

___ Rod 15 withdrawn to be within 2.0" of other Group B rods.

Comment:

Proc.Step TASK ELEMENT 22 STANDARD Grade SOP-6 PLACE the Group Selector Switch to Group Selector Switch placed in Group B S U 7.4.i desired position. position.

Comment:

PALISADES NUCLEAR PLANT Page 9 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 23 STANDARD Grade SOP-6 PLACE the Mode Selector Switch in MS (Manual Sequential) or as directed by the Mode Selector Switch place in MG position S U 7.4.j Shift Manager.

Comment:

EVALUATOR: If asked as Shift Manager: direct Mode Selector Switch be placed in the Manual Group (MG) position.

CRITICAL STEP Proc.Step TASK ELEMENT 24 STANDARD Grade Continue withdrawal of Group B rods:

SOP-6 Operate Raise-Lower Switch to RAISE Raise-Lower Switch place in RAISE position. S U 7.1.2.d position.

Comment:

CRITICAL STEP Proc.Step TASK ELEMENT 25 STANDARD Grade SOP-6 Monitor Nuclear Instrumentation (NI) for NIs monitored as rods are moved. S U 7.1.2.e response during rod movement.

Comment:

Proc.Step TASK ELEMENT 26 STANDARD Grade SOP-6 Stop movement of rods approximately every Control Rod motion stopped prior to exceeding 33 inches (should not exceed 35 inches) of S U 7.1.2.f 35 inches of movement.

rod movement.

Comment:

PALISADES NUCLEAR PLANT Page 10 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 27 STANDARD Grade SOP-6 WHEN rod motion has stopped, THEN Candidate observes SUR indication on Panel S U 7.1.2.f.1 OBSERVE proper reduction in startup rate. C-02 and/or PPC.

Comment:

Proc.Step TASK ELEMENT 28 STANDARD Grade Uses at least one of following methods to verify all Group B rods are within 2 inches of each other:

SOP-6 PERFORM Control Rod alignment -TURN Rod Selector Switch for Group B S U 7.1.2.f.2 verification through all of its positions AND COMPARE Control Rod positions.

- Use the PPC Control Rod position indication for Group B rods.

Comment:

EVALUATOR: Stop JPM when Group B reaches approximately 69 (i.e. after second 33-inch pull).

EVALUATOR: Inform candidate that task is complete.

END OF TASK PALISADES NUCLEAR PLANT Page 11 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-5.

Insert Shutdown Group B rods and part length rods to bottom of core using RD05B and RD05G. After these rods are fully inserted, then clear both malfunctions.

Ensure Dropped Rod alarm NOT on (May need to pull part length rods to 3.6")

Ensure Mode Select switch is in 'MS' position Setup Event Trigger 1:

Event: rdsr(18)>45 Place malfunction RD16-18-5 (PIDRC02) (=rod 18 stuck) on Event Trigger 1 Setup Event Trigger 2:

Event: ZDI2P(267) (this is Rod Control Mode Select Switch in MI position)

Action: dmf rd16-18 PALISADES NUCLEAR PLANT Page 12 of 13 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS D CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Preparations for a critical approach are in progress per GOP-3, Mode 3 525°F To MODE 2. GOP-3 is completed through step 2.1.a.

INITIATING CUES:

The Control Room Supervisor has directed you to perform Section 7.1.2 of SOP-6, "Reactor Control System" for withdrawal of Shutdown Group B Control Rods. Section 7.1.1 has already been performed.

PALISADES NUCLEAR PLANT Page 13 of 13 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS E TITLE: PERFORM A DIESEL GENERATOR (D/G)

VOLTAGE TEST ON 1-1 D/G CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I SYS E JOB PERFORMANCE MEASURE DATA PAGE Task: Perform Diesel Generator Surveillance MO-7A-1 and MO-7A-2 Alternate Path: NO Facility JPM #: PL-OPS-EDG-005J K/A: 064A4.06 Importance: RO: 3.9 SRO: 3.9 K/A Statement: Manual start, loading, and stopping of the ED/G Task Standard: 1-1 D/G Auto Voltage Regulator High and Low Limits verified.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

MO-7A-1, Emergency Diesel Generator 1-1 Validation Time: 10 minutes Time Critical: NO Candidate: ___________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 10 JUNE 2009

JPM: RO/SRO-I SYS E EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

MO-7A-1, Emergency Diesel Generator 1-1, Section 5.6 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

• Diesel Generator 1-1 running unloaded at 60 Hz.

• MO-7A-1, "Emergency Diesel Generator 1-1" is in progress; all steps up to 5.6 are completed.

• Month is January.

• Plant is in Mode 1.

• Auxiliary Operator is stationed at EC-22, Diesel Generator 1-1 Local Panel.

INITIATING CUES:

• During performance of MO-7A-1, the Control Room Supervisor directs you to perform Section 5.6 "Voltage Regulator Test."

PALISADES NUCLEAR PLANT Page 3 of 10 JUNE 2009

JPM: RO/SRO-I SYS E Proc. Step TASK ELEMENT 1 STANDARD Grade Operator obtains a copy of MO-7A-1, MO-7A-1, Section 5.6 obtained n/a Section 5.6 S U Comment:

Evaluator: Provide a working copy of MO-7A-1, Section 5.6.

Proc. Step TASK ELEMENT 2 STANDARD Grade DETERMINE the Voltage Regulator Mode Select switch position from the table for the month .. AND PERFORM the following: Operator determines that the Voltage Regulator 5.6.1 Mode Select switch position is AUTO. S U Voltage Regulator Mode Select Switch Position is AUTO for month of January Comment:

NOTE: The Voltage Regulator Mode Select switch position is determined by the Month of the test.

EVALUATOR: If asked as System Engineer what switch position to use, CUE that the procedure, MO-7A-1 is to be followed.

Proc. Step TASK ELEMENT 3 STANDARD Grade IF position is AUTO, THEN ENSURE Voltage Regulator Mode Select switch is verified Voltage Regulator Mode Select switch is in 5.6.1a in AUTO position. S U the AUTO position (location C-04 panel).

Comment:

EVALUATOR: If candidate places this switch in MANUAL, then this task element is a failed critical step.

PALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009

JPM: RO/SRO-I SYS E Proc. Step TASK ELEMENT 4 STANDARD Grade IF position is MANUAL, THEN PERFORM Operator determines that this step is not 5.6.1b.1 the following: applicable. S U Comment:

Proc. Step TASK ELEMENT 5 STANDARD Grade IF the plant is in Mode 1, 2, 3, or 4, THEN Operator determines that this step is not 5.6.1b.2 PERFORM off-site source checks. applicable. S U Comment:

Proc. Step TASK ELEMENT 6 STANDARD Grade DETERMINE the switch from the table for Operator determines that the Field Rheostat the performance month . AND 5.6.2 switch on C-04 is to be used. S U PERFORM the Following:

Comment:

NOTE: The Field Rheostat switch on C-04 is determined by the Month of the test.

EVALUATOR: If asked as System Engineer what switch to use, CUE The procedure, MO-7A-1 is to be followed.

PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009

JPM: RO/SRO-I SYS E Proc. Step TASK ELEMENT 7 STANDARD Grade Slowly raise generator voltage to between Operator adjusts generator voltage between 2575 VAC and 2625 VAC on EVI-1107L, 2575 VAC and 2625 VAC on EVI-1107L with the 5.6.2a Local Volt Meter or as directed by the S U Field Rheostat switch on C-04.

System Engineer.

Comment:

EVALUATOR: If asked as System Engineer what generator voltage limits to use, CUE that the procedure, MO-7A-1 is to be followed.

EVALUATOR: If asked as AO to report local generator voltage, USE voltage indication on C-04 for the local voltage reading.

CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade Recorded generator and field voltages (from RECORD generator voltage and field EC-22 panel:

voltage (location EC-22 panel)

Local Volt Meter (EVI-1107L) Volts: 2575 to 5.6.2b Local Volt Meter (EVI-1107L) Volts: ____ S U 2625 Field Voltage (EVI-1107DC) Volts: ____

Field Voltage (EVI-1107DC) Volts: __80V_

Comment:

EVALUATOR: If asked as AO to report local generator voltage, USE voltage indication on C-04 for the local voltage reading.

EVALUATOR: If asked as AO to report field voltage, REPORT: field voltage reads 80 V on EVI-1107DC.

PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009

JPM: RO/SRO-I SYS E Proc. Step TASK ELEMENT 9 STANDARD Grade Slowly lower generator voltage to between Operator adjusts generator voltage between 2275 VAC and 2325 VAC on EVI-1107L, 2275 VAC and 2325 VAC on EVI-1107L with the 5.6.2c Local Volt Meter or as directed by the S U Field Rheostat switch on C-04.

System Engineer.

Comment:

EVALUATOR: If asked as System Engineer what generator voltage limits to use, CUE that the procedure, MO-7A-1 is to be followed.

EVALUATOR: If asked as AO to report local generator voltage, USE voltage indication on C-04 for the local voltage reading.

CRITICAL STEP Proc. Step TASK ELEMENT 10 STANDARD Grade Recorded generator and field voltages (from RECORD generator voltage and field EC-22 panel:

voltage (location EC-22 panel)

Local Volt Meter (EVI-1107L) Volts: 2275 to 5.6.2d Local Volt Meter (EVI-1107L0 Volts: ____ S U 2325 Field Voltage (EVI-1107DC)n Volts: ____

Field Voltage (EVI-1107DC) Volts: __70V_

Comment:

EVALUATOR: If asked as AO to report local generator voltage, USE voltage indication on C-04 for the local voltage reading.

EVALUATOR: If asked as AO to report field voltage, REPORT: field voltage reads 70 V on EVI-1107DC.

PALISADES NUCLEAR PLANT Page 7 of 10 JUNE 2009

JPM: RO/SRO-I SYS E Proc. Step TASK ELEMENT 11 STANDARD Grade RAISE generator voltage to 2400 VAC Generator voltage raised to between 2390 VAC (2390 VAC - 2410 VAC) on EVI-1107L, and 2410 VAC on EVI-1107L with the Field 5.6.2e Local Volt Meter. Rheostat switch on C-04. S U Comment:

EVALUATOR: If asked as AO to report local generator voltage, USE voltage indication on C-04 for the local voltage reading.

CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade ENSURE Voltage Regulator Mode Select Voltage Regulator Mode Select switch verified switch is in AUTO position (location C-04 in the AUTO position panel).

5.6.3 S U Performed By: N/A Performed By: Signed, Time and Dated Verified By: Signed, Time and Dated Verified By: Signed, Time and Dated Comment:

EVALUATOR: Operator will not sign the Performed By line, the Verified By line will be signed (Voltage Selector switch in proper position and not manipulated)

Proc. Step TASK ELEMENT 13 STANDARD Grade Notify CRS that 1-1 D/G Voltage Regulator CRS notified that Section 5.6 of MO-7A-1 for Test has been completed per Section 5.6 of n/a Voltage Regulator Test Complete. S U MO-7A-1, for 1-1 D/G.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 JUNE 2009

JPM: RO/SRO-I SYS E SIMULATOR OPERATOR INSTRUCTIONS Any at power IC can be used.

Start EDG 1-1 in UNIT.

Clear Local Alarm guage board on PIDED08, using ED27.

PALISADES NUCLEAR PLANT Page 9 of 10 JUNE 2009

JPM: RO/SRO-I SYS E CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• Diesel Generator 1-1 running unloaded at 60 Hz.

• MO-7A-1, "Emergency Diesel Generator 1-1" is in progress; all steps up to 5.6 are completed.

• Month is January.

• Plant is in Mode 1.

• Auxiliary Operator is stationed at EC-22, Diesel Generator 1-1 Local Panel.

INITIATING CUES:

During performance of MO-7A-1, the Control Room Supervisor directs you to perform Section 5.6 "Voltage Regulator Test."

PALISADES NUCLEAR PLANT Page 10 of 10 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS F TITLE: PLACE A CONTAINMENT RADIATION MONITOR IN SERVICE CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I/SRO-U SYS F JOB PERFORMANCE MEASURE DATA PAGE Task: Operate the Area Radiation Monitoring System Alternate Path: YES - Operate light fails to illuminate when tested Facility JPM #: 2007 NRC SRO JPM K/A: 072A4.01 Importance: RO: 3.0 SRO: 3.3 K/A Statement: Ability to manually operate and/or monitor in the Control Room: Alarm and setpoint checks and adjustments.

Task Standard: Candidate recognizes that the radiation monitor operate light will not illuminate and refers to attachment 2 to troubleshoot the monitor.

Implementation of attachment 2 will restore the operate light.

Preferred Evaluation Location: Simulator _X_ In Plant ______

Preferred Evaluation Method: Perform _X_ Simulate ______

References:

SOP-39, Area Radiation Monitoring System Validation Time: _10_ minutes Time Critical: NO Candidate: _______________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-39 section 7.4.2 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

• The Plant is operating at 100% power.

• I&C Department has just completed maintenance on Containment Radiation Monitor RIA-1805.

• CL-39 for RIA-1805 has been completed INITIATING CUES:

The Control Room Supervisor directs you to place Containment Radiation Monitor, RIA-1805, in service per SOP-39, step 7.4.2.

Another operator will answer any front panel alarms.

PALISADES NUCLEAR PLANT Page 3 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 1 STANDARD Grade n/a Operator locates SOP-39, section 7.4.2 SOP-39, section 7.4.2 is located S U Comment:

Evaluator: Provide candidate with a working copy of SOP-39, section 7.4.2.

Proc. Step TASK ELEMENT 2 STANDARD Grade REFER TO Attachment 3, Checklist CL 39, Candidate determines that this step is N/A per 7.4.2.a S U "Area Monitors System Checklist." initial conditions.

Comment:

Evaluator: If asked, inform candidate that CL-39 has been completed for RIA-1805.

Proc. Step TASK ELEMENT 3 STANDARD Grade Operator recognizes that the OPERATE light is 7.4.2.b CHECK operate light illuminated. S U not illuminated.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade IF operate light NOT illuminated, THEN Operator refers to Attachment 2, section 4.1 for 7.4.2.c REFER TO Attachment 2, "System Containment Radiation Monitors Operate light S U Malfunctions and Troubleshooting." not illuminated.

Comment:

PALISADES NUCLEAR PLANT Page 4 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 5 STANDARD Grade 4.1.a PRESS AND HOLD operate light. Operate light pressed and held S U Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade Operator verifies Orange and Red (Trip 1 and 4.1.b CHECK other three monitors not tripped. Trip 2) lights not illuminated for RIA-1806, 1807 S U and 1808.

Comment:

Proc. Step TASK ELEMENT 7 STANDARD Grade PLACE Selector Switch momentarily to RIA-1805 selector switch placed in CHECK 4.1.c S U CHECK position AND RELEASE. position and released.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade 4.1.d RELEASE operate light. Operate light is released S U Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 9 STANDARD Grade Operator resets:

____ AMBER Trip 1 4.1.e RESET all alarms. S U

____ RED Trip 2 by depressing associated indicating light.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 10 STANDARD Grade IF operate light still not illuminated, THEN Operator determines this step is not applicable 4.1.f DECLARE the associated monitor S U because Operate light is illuminated.

inoperable AND REFER TO 4.2 below.

Comment:

Proc. Step TASK ELEMENT 11 STANDARD Grade 7.4.2.d RESET all alarms. Operator verifies all alarms reset. S U Comment:

Proc. Step TASK ELEMENT 12 STANDARD Grade IF operate light still NOT illuminated, THEN DECLARE the associated monitor Operator determines this step is not applicable 7.4.2.e inoperable. Refer to Attachment 2, S U because Operate light is illuminated.

"System Malfunctions and Troubleshooting.

Comment:

PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 13 STANDARD Grade Operator informs Control Room Supervisor n/a that Containment Radiation Monitor CRS Notified S U RIA-1805 has been placed in service.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F SIMULATOR OPERATOR INSTRUCTIONS Reset to any IC Insert OR RIA-1805-G to off on panel C-11A rear Create Event Trigger 1 as follows:

for Event .not.ZDI4P(341).and.ZDI4P(339) for Action dor RIA-1805-G PALISADES NUCLEAR PLANT Page 8 of 9 JUNE 2009

JPM: RO/SRO-I/SRO-U SYS F CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• The Plant is operating at 100% power.

• I&C Department has just completed maintenance on Containment Radiation Monitor RIA-1805.

• CL-39 for RIA-1805 has been completed INITIATING CUES:

The Control Room Supervisor directs you to place Containment Radiation Monitor, RIA-1805, in service per SOP-39, step 7.4.2.

Another operator will answer any front panel alarms.

PALISADES NUCLEAR PLANT Page 9 of 9 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO SYS G TITLE: VENT THE QUENCH TANK TO THE WASTE GAS SURGE TANK CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO SYS G JOB PERFORMANCE MEASURE DATA PAGE Task: Vent Quench Tank Alternate Path: NO Facility JPM #: 2007 AUDIT SRO JPM K/A: 007A1.03 Importance: RO: 2.7 SRO: 2.9 K/A Statement: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS control including: Maintaining quench tank pressure Task Standard: Quench Tank pressure is 6 psig and Waste Gas Surge Tank pressure is maintained within limits.

Preferred Evaluation Location: Simulator _X__ In Plant ______

Preferred Evaluation Method: Perform _X__ Simulate ______

References:

SOP-1A, Primary Coolant System Validation Time: _15_ minutes Time Critical: NO Candidate: _______________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 JUNE 2009

JPM: RO SYS G EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-1A section 7.4.3 Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant is in MODE 1 full power. It is believed that there is a nitrogen leak into the Quench Tank. Quench Tank Pressure is currently 12 psig, and is rising very slowly (less than 1 psi per hour).

INITIATING CUES:

In preparation for troubleshooting and maintenance you are to vent the Quench Tank to the Waste Gas Surge Tank per SOP-1A, 7.4.3 to 6 psig. An Auxiliary Operator is stationed at Radwaste Panel C-40. The Waste Gas System is lined up for operation per SOP-18A, as required by SOP-1A, 7.4.3.b.

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JPM: RO SYS G Proc. Step TASK ELEMENT 1 STANDARD Grade

--- Locate SOP-1A Candidate locates SOP-1A, 7.4.3 S U Comment:

Evaluator: Provide a working copy of SOP-1A, Section 7.4.3.

Proc. Step TASK ELEMENT 2 STANDARD Grade NOTE: Waste Gas Surge Tank pressure should not exceed 18.5 psia during this Candidate reads NOTE evolution. Lifting of RV-1111, Waste Gas Surge Tank Relief is imminent if pressure in the Waste Gas Surge Tank exceeds 18.5 psia.

7.4.3.a S U STATION an Auxiliary Operator at C-40 Radwaste Panel to monitor T-67, Waste Gas Surge Tank pressure and Waste Gas AO Stationed at C-40 per initial conditions Compressor operations Comment:

Evaluator: Notify the candidate that you will not be role playing the AO. For communications with the AO, they must call them at Panel C-40.

SIM OPERATOR (as AO): Report that you are at Panel C-40 and will maintain WGST pressure <18.5 psia.

Proc. Step TASK ELEMENT 3 STANDARD Grade ENSURE Waste Gas System lined up for operation. Refer to System Operating b Per initial conditions S U Procedure SOP-18A, "Radioactive Waste System - Gaseous."

Comment:

SIM OPERATOR (as AO): Report that Waste Gas System is lined up.

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JPM: RO SYS G Proc. Step TASK ELEMENT 4 STANDARD Grade NOTE: Waste Gas Surge Tank pressure Candidate reads note will rise slightly when performing the next two steps.

c, d OPEN CV-1101, Containment Vent Candidate positions switches for CV-1101 and S U Header Isolation. CV-1102 to OPEN. Verifies Red light ON, OPEN CV-1102, Containment Vent Green light OFF Header Isolation.

Comment:

SIM OPERATOR (as AO): Report that you understand WGST pressure will rise.

CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade CAUTION Waste Gas Surge Tank pressure will rise Candidate reads caution and ensures he has rapidly when performing the next step. The the AO on the phone Control Operator should be in constant communication with the Auxiliary Operator e to control pressure in the Waste Gas S U Surge Tank during performance of the next step.

Candidate takes CV-0152 to OPEN. Verifies OPEN CV-0152, Quench Tank Vent. Red light ON, Green light OFF.

Comment:

SIM OPERATOR (as AO): Report that you are ready.

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 9 JUNE 2009

JPM: RO SYS G Proc. Step TASK ELEMENT 6 STANDARD Grade IF Waste Gas Surge Tank pressure Candidate closes CV-0152 when AO informs f reaches approximately 18 psia, THEN S U that WGST pressure is 18 psia.

CLOSE CV-0152, Quench Tank Vent.

Comment:

SIM OPERATOR (as AO): maintain constant communications:

• After CV-0152 is opened AND when EK-1368 (C-40 Off-Normal alarm) comes in, inform candidate that WGST pressure is 16.5 psia and rising. Continue to monitor WGST pressure on Instructor Station and inform candidate when pressure reaches 18 psia.

• Continue monitoring WGST pressure on Instructor Station after CV-0152 is closed and inform candidate when WGST pressure is 15 psia.

CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade REPEAT Steps e and f until PIA-0116, Candidate repeats steps e. and f. as necessary g Quench Tank Pressure reaches 3 psig or S U to lower Quench Tank pressure to 6 psig.

as directed by the CRS.

Comment:

CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade ENSURE CLOSED CV-0152, Quench h Candidate verifies Green light ON for CV-0152. S U Tank Vent.

Comment:

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JPM: RO SYS G Proc. Step TASK ELEMENT 9 STANDARD Grade CLOSE CV-1101, Containment Vent Header Isolation. Candidate positions handswitches for CV-1101 i, j and CV-1102 to CLOSE and verifies Green light S U CLOSE CV-1102, Containment Vent ON, Red light OFF.

Header Isolation Comment:

Proc. Step TASK ELEMENT 10 STANDARD Grade IF an Auxiliary Operator was stationed at k C-40 Panel, THEN NOTIFY the Auxiliary Candidate notifies AO that vent is complete. S U Operator the vent is complete Comment:

SIM OPERATOR (as AO): Report that you understand that vent is complete.

Proc. Step TASK ELEMENT 11 STANDARD Grade Candidate notifies CRS that vent is

--- complete and Quench Tank pressure is CRS notified S U 6 psig.

Comment:

END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009

JPM: RO SYS G SIMULATOR OPERATOR INSTRUCTIONS Any IC Create event trigger 2:

Event: 0 Action: set thksn2sup=26.0 Activate trigger 2 Raise Quench tank pressure to 12 psig utilizing CV-0150 and CV-1358 Monitor Waste Gas Surge Tank pressure when requested by:

o Start the Monitor program by clicking on "Monitor" on the instructor station control panel o Type "WPPPT67" into the input field and hit enter OR o Read WGST pressure on PIDWP01 PALISADES NUCLEAR PLANT Page 8 of 9 JUNE 2009

JPM: RO SYS G CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in MODE 1 full power. It is believed that there is a nitrogen leak into the Quench Tank. Pressure is currently at 12 psig, and is rising very slowly (less than 1 psi per hour).

INITIATING CUES:

In preparation for troubleshooting and maintenance you are to vent the Quench Tank to the Waste Gas Surge Tank per SOP-1A, 7.4.3 to 6 psig. An Auxiliary Operator is stationed at Radwaste Panel C-40. The Waste Gas System is lined up for operation per SOP-18A, as required by SOP-1A, 7.4.3.b.

PALISADES NUCLEAR PLANT Page 9 of 9 JUNE 2009

NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS H TITLE: INITIATE A CONTAINMENT PURGE CANDIDATE: _____________________________________________

EXAMINER: _____________________________________________

JPM: RO/SRO-I SYS H JOB PERFORMANCE MEASURE DATA PAGE Task: Initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System Alternate Path: YES Facility JPM #: 2005 NRC JPM K/A: 029A2.03 Importance: RO:2.7 SRO: 3.1 K/A Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Startup operations and the associated required valve lineups Task Standard: Initiate a Containment Purge. Subsequently terminate the Containment Purge based on plant ventilation fan status.

Preferred Evaluation Location: Simulator __X__ In Plant _____

Preferred Evaluation Method: Perform __X__ Simulate _____

References:

SOP-24, Ventilation and Air Conditioning System HP 6.14, Containment Purge SOP-38, Gaseous Process Monitoring System ARP-7, EK-1127, Main Exhaust Fan V-6A trip Validation Time: __20___ minutes Time Critical: NO Candidate: ________________________________________________________

Time Start: ________ Time Finish: ________

Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______

Comments:

Examiner: _______________________________ Date: ______________

Signature PALISADES NUCLEAR PLANT Page 2 of 9 JUNE 2009

JPM: RO/SRO-I SYS H EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:

SOP-24, section 7.2.5.

Also see Simulator Operator Instructions (last page of this document).

READ TO CANDIDATE DIRECTION TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The plant is in MODE 5 with the PCS vented to Containment.

INITIATING CUES:

The Control Room Supervisor has directed you to initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System section 7.2.5. The CRS has also informed you that an AO has been briefed and is standing by awaiting your instructions. The CRS also informs you that the RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.

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JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 1 STANDARD Grade Obtain a copy of SOP-24, Ventilation and Candidate obtains SOP-24, Ventilation and Air N/A S U Air Conditioning System procedure. Conditioning System procedure.

Comment:

Evaluator: When applicant indicates where to find a current copy of procedure provide a copy of SOP-24, Ventilation and Air Conditioning System procedure.

Evaluator: If candidate asks to see the Batch Card inform candidate that he doesn't need to see it, but to inform me of the start and stop times of the release so that it can be recorded.

Proc.Step TASK ELEMENT 2 STANDARD Grade Notify the RETS/REMP Supervisor or Duty 7.2.5.a HP to ensure requirements of HP 6.14, RETS/REMP Supervisor or Duty HP notified S U Containment Purge, are met.

Comment:

Evaluator: Role play as CRS and notify candidate that RETS/REMP Supervisor has been informed.

Proc.Step TASK ELEMENT 3 STANDARD Grade Candidate verifies Main Exhaust Fan V-6A 7.2.5.b Ensure one Main Exhaust Fan operating. S U running on panel C-13.

Comment:

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JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 4 STANDARD Grade Ensure RGEM system is in operation per 7.2.5.c SOP-38, Gaseous Process Monitoring From Initiating Cue. S U System.

Comment:

Proc.Step TASK ELEMENT 5 STANDARD Grade Ensure the following Test Tap Valves are Ensure the following Test Tap Valves are 7.2.5.d Locked Closed and capped: Locked Closed and capped: S U MV-VA506 MV-VA508 MV-VA505 MV-VA506 MV-VA508 MV-VA505 Comment:

EVALUATOR: When candidate calls AO, role play as AO and report after approximately 2 minutes that MV-VA506, MV-VA508, and MV-VA505 are locked closed and capped.

Proc.Step TASK ELEMENT 6 STANDARD Grade Key inserted and the following Purge Supply INSERT key and OPEN the following Purge and Exhaust Valves opened and verifies Supply and Exhaust Valves: associated Red light ON and Green light OFF:

• CV-1805 (key 272)

• CV-1805 (key 272) ____

• CV-1806 (key 274)

• CV-1806 (key 274) ____

7.2.5.e S U

• CV-1807 (key 275)

• CV-1807 (key 275) ____

• CV-1808 (key 277)

• CV-1808 (key 277) ____

• CV-1813 (key 273)

• CV-1813 (key 273) ____

• CV-1814 (key 276)

• CV-1814 (key 276) ____

Comment:

CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 9 JUNE 2009

JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 7 STANDARD Grade Record the time the valves were opened in Record the time the valves were opened in the 7.2.5.f S U the Control Room Logbook. Control Room Logbook.

Comment:

Evaluator: Role play as CRS and inform candidate that these times have been logged.

Proc.Step TASK ELEMENT 8 STANDARD Grade 7.2.5.g START Air Room Purge Supply Fan V-46. START Air Room Purge Supply Fan V-46. S U Comment:

NOTE: After Purge Supply Fan is started, the V-6A Main Exhaust Fan will TRIP, and V-6B Standby Fan will not start. This will require that the Containment Purge be manually terminated.

CRITICAL STEP Proc.Step TASK ELEMENT 9 STANDARD Grade Applicant refers to ARP-7, EK-1127, Main

--- Main Exhaust V-6A trips. S U Exhaust Fan V-6A or B trip.

Comment:

Proc.Step TASK ELEMENT 10 STANDARD Grade ARP-7, EK-1127 directs starting the Candidate attempts to start V-6B and ARP-7 S U STANDBY Main Exhaust Fan V-6B. determines it will not start.

Comment:

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JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 11 STANDARD Grade Per ARP-7, EK-1127, secure any radioactive waste gas batch per SOP-18A ARP-7 Candidate stops Air Room Supply Fan V-46. S U and shutdown any plant ventilation air flow per SOP-24.

Comment:

Evaluator: If asked, role play as SRO and state that no heavy load movements are in progress in the Containment or SFP and that no core alterations or movement of fuel is occurring in Containment or SFP.

CRITICAL STEP Proc.Step TASK ELEMENT 12 STANDARD Grade Candidate closes all OPEN purge control Manually CLOSE all OPEN purge control valves and verifies associated Red light OFF valves. The Applicant may use EOP and Green light ON. The Applicant may use Supplement 6, Containment Isolation as a EOP Supplement 6, Containment Isolation as a guide.

guide.

• CV-1805 (key 272)

• CV-1805 (key 272) ____

---

• CV-1806 (key 274) S U

• CV-1806 (key 274) ____

• CV-1807 (key 275)

• CV-1807 (key 275) ____

• CV-1808 (key 277)

• CV-1808 (key 277) ____

• CV-1813 (key 273)

• CV-1813 (key 273) ____

• CV-1814 (key 276)

• CV-1814 (key 276) ____

Comment:

Evaluator: Candidate may start securing other ventilation systems, but stop JPM when Containment Purge is isolated.

CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009

JPM: RO/SRO-I SYS H SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-1 Ensure V-6A in service.

Create Event Trigger #1: Event: ZDI1P(524) [this is Purge Fan V-46 HS to CLOSE]

Place the following overrides on Panel PAL09M1 (C-13 left side) on Event Trigger #1 with a 10 second time delay:

V-6A-1, Main Exhaust V-6A Trip to ON V-6B-1, Main Exhaust V-6B Trip to ON PALISADES NUCLEAR PLANT Page 8 of 9 JUNE 2009

JPM: RO/SRO-I SYS H CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in MODE 5 with the PCS vented to Containment.

INITIATING CUES:

The Control Room Supervisor has directed you to initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System section 7.2.5. The CRS has also informed you that an AO has been briefed and is standing by awaiting your instructions. The CRS also informs you that the RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.

PALISADES NUCLEAR PLANT Page 9 of 9 JUNE 2009