ML100690475
| 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 im pacts 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 est ablished 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 t he 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 ac tions 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 1 Record each occurrence of PZR Spray operation with a T greater than 200 F in the Reactor Logbook.
Operator notes this requirement for future action in this JPM.
Operator notes current temperatures for vapor phase, spray lines, and charging: determines
requirement is currently not applicable.
S U Comment:
Proc. Step TASK ELEMENT 3 STANDARD Grade 2 Ensure P-66B is operating within the limits of EOP Supplement 4.
Verifies P-66B flow is within EOP Supplement 4 S U Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 JUNE 2009 JPM: RO/SRO-I SYS A Proc. Step TASK ELEMENT 4 STANDARD Grade 3 Ensure open the following valves:
Charging Line Stop, CV-2111 (already open) Auxiliary Spray, CV-2117
Charging Pump Discharge to Train 2, MO-3072 HPSI Pump B Discharge to Train 2, CV-3018 Verifies or places hand switches in OPEN and verifies associated Green light OFF and Red
light ON.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 5 STANDARD Grade 4 Stop ALL Charging Pumps Candidate determines all three Charging Pumps are operating and have electrical power
available. Candidate will stop P-55A, P-55B, and P-55C.
S U 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 5 CLOSE the following valves:
Loop 1A, CV-2113
Loop 2A, CV-2115
Spray, CV-1057
Spray, CV-1059.
Places hand switches for CV-2113, CV-2115, CV-1057, and CV-1059 to CLOSE.
Verifies Green lights ON and Red lights OFF for all the above valves.
S U 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 6 Ensure open the following HPSI Train 1 valves: HPSI Train 1 Loop 1A, MO-3007
HPSI Train 1 Loop 1B, MO-3009
HPSI Train 1 Loop 2A, MO-3011
HSPI Train 1 Loop 2B, MO-3013 Verifies MO-3007, MO-3009, MO-3011, and MO-3013 Red lights ON and Green lights OFF.
S U Comment:
Proc. Step TASK ELEMENT 8 STANDARD Grade 7 CLOSE the following valves:
HPSI Train 2 Loop 2B, MO-3062
HPSI Train 2 Loop 2A, MO-3064
HPSI Train 2 Loop 1B, MO-3066
HSPI Train 2 Loop 1A, MO-3068 Places and holds hand switches for MO-3062, MO-3064, MO-3066, and MO-3068 to CLOSE
until Green lights ON and Red lights OFF.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 9 STANDARD Grade 8 Ensure HPSI flow of greater than or equal to 100 gpm to the Pressurizer through the
charging line is indicated on FIA-0212.
Operator checks flow is indicated on FIA-0212
greater than 100 gpm.
S U Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 2009 JPM: RO/SRO-I SYS A PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009 Proc. Step TASK ELEMENT 10 STANDARD Grade--- Candidate informs the CRS that the Hot Leg Injection using P-66B and split flow
has been established per EOP
Supplement 20 section 2.0.
CRS informed.
S U Comment:
END OF TASK
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 immedi ate 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 t he 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 ac tions 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 System procedure.
Candidate locates SOP-1A, Primary Coolant System. S U Comment:
Proc.Step TASK ELEMENT 2 STANDARD Grade--- Determine that Section 7.2.2.b.3 of SOP-1A should be used to alternate PZR Press
Controllers.
Reviews Section 7.2.2 PZR Press Control and
determines section 7.2.2.b.3 needs to be
performed.
S U 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 3.b Adjust output signal on PIC-0101A to match output signal on PIC-0101B.
Adjusts output signal on PIC-0101A to match
output signal on PIC-0101B for bumpless
transfer.
S U Comment:
Proc.Step TASK ELEMENT 5 STANDARD GradePALISADES NUCLEAR PLANT Page 4 of 10 JUNE 2009 JPM: RO/SRO-I SYS B 3.c Place Selector Switch 1/PRC-0101 to Channel 'A'.
Places Selector Switch 1/PRC-0101 to
Channel 'A'.
S U Evaluator: If asked, state th at AUTO CONTROL IS DESIRED.
CRITICAL STEP
Proc.Step TASK ELEMENT 6 STANDARD Grade 3.d.1 Ensure Pzr Htr Control Channel Selector Switch in CHAN A & B.
Ensures Pzr Htr Control Channel Selector
Switch in CHAN A & B.
S U Comment:
Proc.Step TASK ELEMENT 7 STANDARD Grade 3.d.2 Ensure PIC-0101A setpoint set at desired PCS pressure.
Ensures PIC-0101A setpoint set to 2060 psia.
S U Comment:
Proc.Step TASK ELEMENT 8 STANDARD Grade 3.d.3 Adjust PIC-0101A output to match indicated Pzr Press (red pointer) with setpoint press (Blue pointer).
Adjusts PIC-0101A output to match indicated
Pzr Press (red pointer) with setpoint press (Blue pointer).
S U Comment:
Proc.Step TASK ELEMENT 9 STANDARD GradePALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009 JPM: RO/SRO-I SYS B PALISADES NUCLEAR PLANT Page 6 of 10 JUNE 2009 3.d.4 Depress the "A" pushbutton on PIC-0101A to place it in AUTO.
Depresses the "A" pushbutton on PIC-0101A to
place it in AUTO.
S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 10 STANDARD Grade 3.e Place the unselected controller in MANUAL with a 50% output signal.
Places PIC-0101B in MANUAL with a 50%
output signal.
S U 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
high. EK-0753 Pzr Press Off Normal Hi-Lo
alarm will also alert applicant of the
problem. Place PIC-0101A back to MANUAL and reduce
controller output to restore Pzr Press to 2060
psia. S U 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
JPM: RO/SRO-I SYS B Proc.Step TASK ELEMENT 12 STANDARD Grade---- Refers to ARP-4 window 53 and informs CRS of the problem with PIC-0101A.
ARP-4 referenced for EK-0753 and CRS
informed of the problem with PIC-0101A.
Candidate will inform CRS to refer to ONP-18, Pressurizer Pressure Control Malfunctions.
S U 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 3.b Adjust output signal on PIC-0101B to match output signal on PIC-0101A or desired
output. Adjusts output signal on PIC-0101B to desired
output. S U Comment:
Proc.Step TASK ELEMENT 15 STANDARD Grade 3.c Place selector switch 1/PRC-0101 to Channel 'B'.
Places selector switch 1/PRC-0101 to
Channel 'B'.
S U 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 3.d.1 PZR HTR Channel Selector Switch may be placed in CHAN B position.
Places PZR HTR Channel Selector Switch in
CHAN B or leaves in CHAN A & B.
S U 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 3.d.2 Ensure PIC-0101B setpoint set at desired PCS pressure.
Ensures PIC-0101B setpoint set at 2060 psia.
S U Comment:
Proc.Step TASK ELEMENT 18 STANDARD Grade 3.d.3 Adjust PIC-0101B output to match indicated Pzr Press (red pointer) with setpoint press (Blue pointer).
Adjusts PIC-0101B output to match indicated
Pzr Press (red pointer) with setpoint press (Blue pointer).
S U 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 3.d.4 Depress the "A" pushbutton on PIC-0101B to place it in AUTO.
Depresses the "A" pushbutton on PIC-0101B to
place it in AUTO.
S U 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 se cond 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 t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned 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 MS IVs 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 7.2.2.c LATCH MSIV solenoid valves. Candidate contacts Auxiliary Operator to latch all MSIV solenoids in the turbine building and 'D'
bus area.
S U 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 d IF MSIVs opened after performance of Step 7.2.2c, THEN GO TO Step 7.2.2q.
Candidate determines that CV-0510, 'A' S/G
MSIV, did not open. Proceeds to step 7.2.2.e S U Comment:
Evaluator: Role play as CRS and direct candida te 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 PALISADES NUCLEAR PLANT Page 5 of 10 JUNE 2009 Proc. Step TASK ELEMENT 4 STANDARD Grade e ENSURE CV-0511, Turbine Bypass to Condenser, remains CLOSED by
performing the following:
Candidate performs the following: ___ PLACEs PIC-0511, Turbine Bypass Valve Control to MANUAL. ___ Sets PIC-0511, Turbine Bypass Control Valve to CLOSE. ___ 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.
S U 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 f PERFORM the following notifications of impending Steam Dump operation:
Candidate informs CRS to notify Chemistry and
to refer to ADMIN 4.00.
S U Comment:
Evaluator: Notify Candidate that the SE will perform this.
Proc. Step TASK ELEMENT 6 STANDARD Grade g CLOSE three of the four Steam Dump Air Supplies for the MSIV to be opened, listed
below: Candidate directs Auxiliary Operator to close the
following valves in the ADV control cabinet:
___ MV-CA779
___ MV-CA780
___ MV-CA781 OR MV-CA782 S U 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
JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 7 STANDARD Grade h, i PLACE HIC-0780A, Steam Generator E-50B Steam Dump to MANUAL.
OPERATE HIC-0780A toward 100%
OPEN position to equalize DP across
MSIV. Candidate: ___ Places HIC-0780A in Manual
___ Operates manual output lever to open ADV until MSIV CV-0510 opens.
S U 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 j WHEN MSIV opens, THEN PLACE HIC-0780A to CLOSE position.
Candidate Operates manual output lever to close ADV.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 9 STANDARD Grade k OPEN Steam Dump Air Supplies closed in Step 7.2.2g above.
Candidate has AO open:
___ MV-CA779
___ MV-CA780
___ MV-CA781 OR MV-CA782 S U 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 l IF both MSIVs did NOT open, THEN REPEAT Steps 7.2.2g through 7.2.2k for
affected MSIV.
Candidate determines this step is N/A because
both MSIVs are now open.
S U Comment:
Proc. Step TASK ELEMENT 11 STANDARD Grade m, n CLOSE CV-0511 accumulator drain valve.
OPEN MV-CA390, Turbine Bypass
CV-0511 A/S Isol.
Candidate has AO: ___ CLOSE CV-0511 accumulator drain valve
___ OPEN MV-CA390, Turbine Bypass CV-0511 A/S Isol.
S U Comment:
SIM OPERATOR: Use MS35 on PIDMS03 to open air supply to CV-0511.
CRITICAL STEP
Proc. Step TASK ELEMENT 12 STANDARD Grade o, p RETURN HIC-0780A to AUTO or the AS FOUND position.
RETURN PIC-0511 to AUTO or the AS FOUND position.
Candidate places HIC-0780A and CV-0511 in
AUTO by depressing the 'A' button on their
controllers and verifying the 'A' button lights.
S U Comment:
EVALUATOR NOTE: If asked, inform candida te 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 PALISADES NUCLEAR PLANT Page 8 of 10 JUNE 2009 Proc. Step TASK ELEMENT 13 STANDARD Grade q CLOSE the following valves:
- MO-0501, MSIV CV-0501 Bypass (MZ-3)
- MO-0510, MSIV CV-0510 Bypass (MZ-2)
Candidate closes MO-0501 and MO-0510 by holding switch in the CLOSE position until
associated Green light is ON and Red light is
OFF. S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 14 STANDARD Grade--- Candidate informs the CRS that the MSIVs are open and the MSIV bypasses are
closed. CRS informed.
S U Comment:
END OF TASK
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 f eatures/interlocks which provide for the following: Operation of CRDS controls fo r 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 Pu mp 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 PALISADES NUCLEAR PLANT Page 3 of 13 JUNE 2009 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 t he 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 ac tions 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.
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 7.1.2.a Ensure all rods of Group 'A' are withdrawn greater than or equal to 128 inches.
Candidate checks PPC (page 420) and/or
Panel C-02 display to verify Group 'A' rods are
above 128 inches.
S U Comment:
Proc.Step TASK ELEMENT 3 STANDARD Grade SOP-6 7.1.2.b Place Group Selector Switch to 'B' position.
Group Selector Switch placed in 'B' position.
S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 4 STANDARD Grade SOP-6 7.1.2.c Place Mode Selector Switch to MG (Manual Group) position.
Mode Selector Switch placed in MG position.
S U Comment:
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 13 JUNE 2009 JPM: RO/SRO-I/SRO-U SYS D PALISADES NUCLEAR PLANT Page 5 of 13 JUNE 2009 Proc.Step TASK ELEMENT 5 STANDARD Grade SOP-6 7.1.2.d Operate Raise-Lower Switch to RAISE position.
Raise-Lower Switch place in RAISE position.
S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 6 STANDARD Grade SOP-6 7.1.2.e Monitor Nuclear Instrumentation (NI) for response during rod movement.
NIs monitored as rods are moved.
S U Comment:
Evaluator Note: Group 'B' rods PIP/SPI diffe rence alarms on PPC are expected alarms as described by SOP-6 section 5.3.
Proc.Step TASK ELEMENT 7 STANDARD Grade SOP-6 7.1.2.f Stop movement of rods approximately every 33 inches (should not exceed 35 inches) of
rod movement.
Control Rod motion stopped prior to exceeding
35 inches of movement.
S U Comment:
Proc.Step TASK ELEMENT 8 STANDARD Grade SOP-6 7.1.2.f.1 WHEN rod motion has stopped, THEN OBSERVE proper reduction in startup rate.
Candidate observes SUR indication on Panel
C-02 and/or PPC.
S U Comment:
JPM: RO/SRO-I/SRO-U SYS D Proc.Step TASK ELEMENT 9 STANDARD Grade SOP-6 7.1.2.f.2 PERFORM Control Rod alignment verification Uses at least one of following methods to verify
all Group 'B' rods are within 2 inches of each
other: -TURN Rod Selector Switch for Group 'B' through all of its positions AND COMPARE
Control Rod positions. - Use the PPC Control Rod position indication for Group 'B' rods.
S U 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 SOP-6 7.1.2.d Continue Group 'B' withdrawal:
Operate Raise-Lower Switch to RAISE position.
Raise-Lower Switch place in RAISE position.
S U Comment:
EVALUATOR NOTE:
When Rod 18 is > 45 inches, it will become stuck.
CRITICAL STEP
Proc.Step TASK ELEMENT 11 STANDARD Grade SOP-6 7.1.2.e Monitor Nuclear Instrumentation (NI) for response during rod movement.
NIs monitored as rods are moved.
S U 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 Window 11 Alarm EK-0911 "Rod Position 4 Inches Deviation," Annunciates Control Rod motion stopped by releasing
Raise-Lower switch.
ARP-5 referenced for window 11 S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 13 STANDARD Grade ARP-5 Window 11 IDENTIFY affected Control Rod AND extent of its deviation.
On PPC display 411, Rod 18 identified OR
confirm on Panel C-02 by placing Group 'B'
Selector Switch to "18" S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 14 STANDARD Grade ARP-5 Window 11 COMPARE affected rod position with secondary rod position.
Verifies Rod 18 position is 4 inches lower than
remaining rods in Group 'B' using available
indications. Also notes that Rod 15 is more
than 2 inches different from remainder of
group. S U Comment:
Proc.Step TASK ELEMENT 15 STANDARD Grade ARP-5 Window 11 REPOSITION Control Rod in Manual Individual as necessary to clear alarm per
SOP-6 Refers to SOP-6, section 7.4.
S U 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 7.4.a REFER to Step 4.4.1 SOP-6 Step 4.4.1 reviewed.
S U 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 7.4.e PLACE Rod Selector Switch in the position for the rod to be moved.
Rod Selector Switch for Group 'B' placed in
position '18' S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 18 STANDARD Grade SOP-6 7.4.f TURN Group Selector Switch to the position for the group containing the rod to be
moved. Group Selector Switch placed in 'Group B'
position.
S U Comment:
Proc.Step TASK ELEMENT 19 STANDARD Grade SOP-6 7.4.g PLACE Mode Selector Switch to MI (Manual Individual) position.
Mode Selector Switch placed in 'MI' position.
S U 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 SOP-6 7.4.h Withdraw selected rod to clear 4-inch deviation alarm. ___ Operates ROD CONTROL joystick to
RAISE. ___ Rod 18 withdrawn to be within 2.0" of other Group 'B' rods. ___ Observes 4-Inch Deviation alarm clears.
S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 21 STANDARD Grade SOP-6 7.4.h Withdraw selected rod to level Rod 15. ___ Rod Selector Switch for Group 'B' placed in position '15' ___ Operates ROD CONTROL joystick to RAISE. ___ Rod 15 withdrawn to be within 2.0" of other Group 'B' rods.
S U Comment:
Proc.Step TASK ELEMENT 22 STANDARD Grade SOP-6 7.4.i PLACE the Group Selector Switch to desired position.
Group Selector Switch placed in 'Group B'
position.
S U 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 7.4.j PLACE the Mode Selector Switch in MS (Manual Sequential) or as directed by the
Shift Manager.
Mode Selector Switch place in MG position S U 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 SOP-6 7.1.2.d Continue withdrawal of Group 'B' rods:
Operate Raise-Lower Switch to RAISE position.
Raise-Lower Switch place in RAISE position.
S U Comment:
CRITICAL STEP
Proc.Step TASK ELEMENT 25 STANDARD Grade SOP-6 7.1.2.e Monitor Nuclear Instrumentation (NI) for response during rod movement.
NIs monitored as rods are moved.
S U Comment:
Proc.Step TASK ELEMENT 26 STANDARD Grade SOP-6 7.1.2.f Stop movement of rods approximately every 33 inches (should not exceed 35 inches) of
rod movement.
Control Rod motion stopped prior to exceeding
35 inches of movement.
S U Comment:
PALISADES NUCLEAR PLANT Page 10 of 13 JUNE 2009 JPM: RO/SRO-I/SRO-U SYS D PALISADES NUCLEAR PLANT Page 11 of 13 JUNE 2009 Proc.Step TASK ELEMENT 27 STANDARD Grade SOP-6 7.1.2.f.1 WHEN rod motion has stopped, THEN OBSERVE proper reduction in startup rate.
Candidate observes SUR indication on Panel
C-02 and/or PPC.
S U Comment:
Proc.Step TASK ELEMENT 28 STANDARD Grade SOP-6 7.1.2.f.2 PERFORM Control Rod alignment verification Uses at least one of following methods to verify
all Group 'B' rods are within 2 inches of each
other: -TURN Rod Selector Switch for Group 'B' through all of its positions AND COMPARE
Control Rod positions. - Use the PPC Control Rod position indication for Group 'B' rods.
S U 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
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 Surv eillance 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, l oading, 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 t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned 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 C ontrol 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 n/a Operator obtains a copy of MO-7A-1, Section 5.6 MO-7A-1, Section 5.6 obtained
S U Comment:
Evaluator: Provide a working copy of MO-7A-1, Section 5.6.
Proc. Step TASK ELEMENT 2 STANDARD Grade 5.6.1 DETERMINE the Voltage Regulator Mode Select switch position from the table for the month -..
AND PERFORM the following:
Voltage Regulator Mode Select Switch Position is "AUTO" for month of January Operator determines that the Voltage Regulator Mode Select switch position is "AUTO".
S U 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 5.6.1a IF position is AUTO, THEN ENSURE Voltage Regulator Mode Select switch is in the AUTO position (location C-04 panel).
Voltage Regulator Mode Select switch is verified in AUTO position.
S U 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 5.6.1b.1 IF position is MANUAL, THEN PERFORM the following: -
Operator determines that this step is not applicable.
S U Comment:
Proc. Step TASK ELEMENT 5 STANDARD Grade 5.6.1b.2 IF the plant is in Mode 1, 2, 3, or 4, THEN PERFORM off-site source checks.
Operator determines that this step is not applicable.
S U Comment:
Proc. Step TASK ELEMENT 6 STANDARD Grade 5.6.2 DETERMINE the switch from the table for the performance month -. AND
PERFORM the Following:
Operator determines that the Field Rheostat switch on C-04 is to be used.
S U 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 5.6.2a Slowly raise generator voltage to between 2575 VAC and 2625 VAC on EVI-1107L, Local Volt Meter or as directed by the
System Engineer.
Operator adjusts generator voltage between 2575 VAC and 2625 VAC on EVI-1107L with the
Field Rheostat switch on C-04.
S U 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 generato r voltage, USE voltage indication on C-04 for the local voltage reading.
CRITICAL STEP
Proc. Step TASK ELEMENT 8 STANDARD Grade 5.6.2b RECORD generator voltage and field voltage (location EC-22 panel) Local Volt Meter (EVI-1107L) Volts: ____ Field Voltage (EVI-1107DC) Volts: ____
Recorded generator and field voltages (from EC-22 panel:
Local Volt Meter (EVI-1107L) Volts:
2575 to 2625 Field Voltage (EVI-1107DC) Volts:
__80V_ S U Comment:
EVALUATOR:
If asked as AO to report local generato r 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 5.6.2c Slowly lower generator voltage to between 2275 VAC and 2325 VAC on EVI-1107L, Local Volt Meter or as directed by the
System Engineer.
Operator adjusts generator voltage between 2275 VAC and 2325 VAC on EVI-1107L with the
Field Rheostat switch on C-04.
S U 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 generato r voltage, USE voltage indication on C-04 for the local voltage reading.
CRITICAL STEP
Proc. Step TASK ELEMENT 10 STANDARD Grade 5.6.2d RECORD generator voltage and field voltage (location EC-22 panel) Local Volt Meter (EVI-1107L0 Volts: ____ Field Voltage (EVI-1107DC)n Volts: ____
Recorded generator and field voltages (from EC-22 panel:
Local Volt Meter (EVI-1107L) Volts:
2275 to 2325 Field Voltage (EVI-1107DC) Volts:
__70V_ S U Comment:
EVALUATOR:
If asked as AO to report local generato r 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 PALISADES NUCLEAR PLANT Page 8 of 10 JUNE 2009 Proc. Step TASK ELEMENT 11 STANDARD Grade 5.6.2e RAISE generator voltage to 2400 VAC (2390 VAC - 2410 VAC) on EVI-1107L, Local Volt Meter.
Generator voltage raised to between 2390 VAC and 2410 VAC on EVI-1107L with the Field
Rheostat switch on C-04.
S U Comment:
EVALUATOR:
If asked as AO to report local generato r voltage, USE voltage indication on C-04 for the local voltage reading.
CRITICAL STEP
Proc. Step TASK ELEMENT 12 STANDARD Grade 5.6.3 ENSURE Voltage Regulator Mode Select switch is in AUTO position (location C-04 panel). Performed By: Signed, Time and Dated
Verified By: Signed, Time and Dated Voltage Regulator Mode Select switch verified in the AUTO position Performed By: N/A
Verified By: Signed, Time and Dated S U 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 n/a Notify CRS that 1-1 D/G Voltage Regulator Test has been completed per Section 5.6 of
MO-7A-1, for 1-1 D/G.
CRS notified that Section 5.6 of MO-7A-1 for Voltage Regulator Test Complete.
S U Comment:
END OF TASK
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 manua lly 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 t he 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 ac tions 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 7.4.2.a REFER TO Attachment 3, Checklist CL 39, "Area Monitors System Checklist." Candidate determines that this step is N/A per initial conditions.
S U Comment:
Evaluator: If asked, inform candidate that CL-39 has been completed for RIA-1805.
Proc. Step TASK ELEMENT 3 STANDARD Grade 7.4.2.b CHECK operate light illuminated.
Operator recognizes that the OPERATE light is not illuminated.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 4 STANDARD Grade 7.4.2.c IF operate light NOT illuminated, THEN REFER TO Attachment 2, "System Malfunctions and Troubleshooting." Operator refers to Attachment 2, section 4.1 for
Containment Radiation Monitors Operate light
not illuminated.
S U 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 4.1.b CHECK other three monitors not tripped.
Operator verifies Orange and Red (Trip 1 and Trip 2) lights not illuminated for RIA-1806, 1807
and 1808.
S U Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade 4.1.c PLACE Selector Switch momentarily to CHECK position AND RELEASE.
RIA-1805 selector switch placed in CHECK
position and released.
S U 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 4.1.e RESET all alarms.
Operator resets: ____ AMBER Trip 1
____ RED Trip 2
by depressing associated indicating light.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 10 STANDARD Grade 4.1.f IF operate light still not illuminated, THEN DECLARE the associated monitor
inoperable AND REFER TO 4.2 below.
Operator determines this step is not applicable
because Operate light is illuminated.
S U 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 7.4.2.e IF operate light still NOT illuminated, THEN DECLARE the associated monitor
inoperable. Refer to Attachment 2, "System Malfunctions and
Troubleshooting.
Operator determines this step is not applicable
because Operate light is illuminated.
S U 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 n/a Operator informs Control Room Supervisor that Containment Radiation Monitor
RIA-1805 has been placed in service.
CRS Notified S U 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 m onitor 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 t he 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 ac tions 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 maintenanc e 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 Wast e Gas System is lined up for operation per SOP-18A, as required by SOP-1A, 7.4.3.b.
PALISADES NUCLEAR PLANT Page 3 of 9 JUNE 2009 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 7.4.3.a NOTE: Waste Gas Surge Tank pressure should not exceed 18.5 psia during this
evolution. Lifting of RV-1111, Waste Gas
Surge Tank Relief is imminent if pressure
in the Waste Gas Surge Tank exceeds
18.5 psia.
STATION an Auxiliary Operator at C-40 Radwaste Panel to monitor T-67, Waste
Gas Surge Tank pressure and Waste Gas
Compressor operations Candidate reads NOTE
AO Stationed at C-40 per initial conditions S U 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 b ENSURE Waste Gas System lined up for operation. Refer to System Operating
Procedure SOP-18A, "Radioactive Waste
System - Gaseous." Per initial conditions S U Comment: SIM OPERATOR (as AO): Report that Waste Gas System is lined up.
PALISADES NUCLEAR PLANT Page 4 of 9 JUNE 2009 JPM: RO SYS G Proc. Step TASK ELEMENT 4 STANDARD Grade c, d NOTE: Waste Gas Surge Tank pressure will rise slightly when performing the next
two steps.
OPEN CV-1101, Containment Vent
Header Isolation.
OPEN CV-1102, Containment Vent Header Isolation.
Candidate reads note
Candidate positions switches for CV-1101 and CV-1102 to OPEN. Verifies Red light ON, Green light OFF S U Comment: SIM OPERATOR (as AO): Report that you understand WGST pressure will rise.
CRITICAL STEP
Proc. Step TASK ELEMENT 5 STANDARD Grade e CAUTION Waste Gas Surge Tank pressure will rise rapidly when performing the next step. The
Control Operator should be in constant communication with the Auxiliary Operator
to control pressure in the Waste Gas
Surge Tank during performance of the next
step. OPEN CV-0152, Quench Tank Vent.
Candidate reads caution and ensures he has the AO on the phone
Candidate takes CV-0152 to OPEN. Verifies Red light ON, Green light OFF.
S U 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 f IF Waste Gas Surge Tank pressure reaches approximately 18 psia, THEN
CLOSE CV-0152, Quench Tank Vent.
Candidate closes CV-0152 when AO informs
that WGST pressure is 18 psia.
S U 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 g REPEAT Steps e and f until PIA-0116, Quench Tank Pressure reaches 3 psig or
as directed by the CRS.
Candidate repeats steps e. and f. as necessary
to lower Quench Tank pressure to 6 psig.
S U Comment:
CRITICAL STEP
Proc. Step TASK ELEMENT 8 STANDARD Grade h ENSURE CLOSED CV-0152, Quench Tank Vent.
Candidate verifies Green light ON for CV-0152.
S U Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 2009 JPM: RO SYS G PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009 Proc. Step TASK ELEMENT 9 STANDARD Grade i, j CLOSE CV-1101, Containment Vent Header Isolation.
CLOSE CV-1102, Containment Vent Header Isolation Candidate positions handswitches for CV-1101
and CV-1102 to CLOSE and verifies Green light
ON, Red light OFF.
S U Comment:
Proc. Step TASK ELEMENT 10 STANDARD Grade k IF an Auxiliary Operator was stationed at C-40 Panel, THEN NOTIFY the Auxiliary
Operator the vent is complete Candidate notifies AO that vent is complete.
S U 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
6 psig. CRS notified S U Comment:
END OF TASK
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 maintenanc e 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 Wast e 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
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 t he 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 ac tions 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 Syste m" section 7.2.5. The CRS has also informed you that an AO has been brie fed and is standing by awaiting your instructions. The CRS also informs you t hat the RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.
PALISADES NUCLEAR PLANT Page 3 of 9 JUNE 2009 JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 1 STANDARD Grade N/A Obtain a copy of SOP-24, Ventilation and Air Conditioning System procedure.
Candidate obtains SOP-24, Ventilation and Air
Conditioning System procedure.
S U 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 7.2.5.a Notify the RETS/REMP Supervisor or Duty HP to ensure requirements of HP 6.14, Containment Purge, are met.
RETS/REMP Supervisor or Duty HP notified S U Comment:
Evaluator: Role play as CRS and notify candidate that RETS/REMP Supervisor has been informed.
Proc.Step TASK ELEMENT 3 STANDARD Grade 7.2.5.b Ensure one Main Exhaust Fan operating.
Candidate verifies Main Exhaust Fan V-6A running on panel C-13.
S U Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 JUNE 2009 JPM: RO/SRO-I SYS H PALISADES NUCLEAR PLANT Page 5 of 9 JUNE 2009 Proc.Step TASK ELEMENT 4 STANDARD Grade 7.2.5.c Ensure RGEM system is in operation per SOP-38, Gaseous Process Monitoring System. From Initiating Cue.
S U Comment:
Proc.Step TASK ELEMENT 5 STANDARD Grade 7.2.5.d Ensure the following Test Tap Valves are Locked Closed and capped:
MV-VA506 MV-VA508 MV-VA505 Ensure the following Test Tap Valves are Locked Closed and capped:
MV-VA506 MV-VA508 MV-VA505 S U 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 7.2.5.e INSERT key and OPEN the following Purge Supply and Exhaust Valves:
- CV-1805 (key 272)
- CV-1806 (key 274)
- CV-1807 (key 275)
- CV-1808 (key 277)
- CV-1813 (key 273)
- CV-1814 (key 276)
Key inserted and the following Purge Supply and Exhaust Valves opened and verifies
associated Red light ON and Green light OFF:
- CV-1805 (key 272) ____
- CV-1806 (key 274) ____
- CV-1807 (key 275) ____
- CV-1808 (key 277) ____
- CV-1813 (key 273) ____
- CV-1814 (key 276) ____
S U Comment:
CRITICAL STEP
JPM: RO/SRO-I SYS H Proc.Step TASK ELEMENT 7 STANDARD Grade 7.2.5.f Record the time the valves were opened in the Control Room Logbook.
Record the time the valves were opened in the
Control Room Logbook.
S U 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--- Main Exhaust V-6A trips.
Applicant refers to ARP-7, EK-1127, Main Exhaust Fan V-6A or B trip.
S U Comment:
Proc.Step TASK ELEMENT 10 STANDARD Grade ARP-7 ARP-7, EK-1127 directs starting the STANDBY Main Exhaust Fan V-6B.
Candidate attempts to start V-6B and
determines it will not start.
S U Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 JUNE 2009 JPM: RO/SRO-I SYS H PALISADES NUCLEAR PLANT Page 7 of 9 JUNE 2009 Proc.Step TASK ELEMENT 11 STANDARD Grade ARP-7 Per ARP-7, EK-1127, secure any radioactive waste gas batch per SOP-18A
and shutdown any plant ventilation air flow
per SOP-24.
Candidate stops Air Room Supply Fan V-46.
S U 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--- Manually CLOSE all OPEN purge control valves. The Applicant may use EOP Supplement 6, Containment Isolation as a
guide.
- CV-1805 (key 272)
- CV-1806 (key 274)
- CV-1807 (key 275)
- CV-1808 (key 277)
- CV-1813 (key 273)
- CV-1814 (key 276)
Candidate closes all OPEN purge control valves and verifies associated Red light OFF
and Green light ON. The Applicant may use
EOP Supplement 6, Containment Isolation as a
guide.
- CV-1805 (key 272) ____
- CV-1806 (key 274) ____
- CV-1807 (key 275) ____
- CV-1808 (key 277) ____
- CV-1813 (key 273) ____
- CV-1814 (key 276) ____
S U Comment:
Evaluator: Candidate may start securing other ventilation systems, but stop JPM when Containment Purge is isolated.
CRITICAL STEP
END OF TASK
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 Syste m" section 7.2.5. The CRS has also informed you that an AO has been brie fed 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