ML111460567
| ML111460567 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML102070508 | List: |
| References | |
| Download: ML111460567 (97) | |
Text
2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION AS-AD MINISTERED EXAM FILES CONTROL ROOM JPMs
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROSYSA TITLE: EMERGENCY BORATE (WITHOUT BUS I D )
CANDIDATE:
EXAMINER:
JPM RO SYS A JOB PERFORMANCE MEASURE DATA PAGE Task: Initiate Emergency Boration In Accordance with SOP-2A Alternate Path: NO Facility JPM #: PL-OPS-CVC-O13J K/A: 004A4.18 Importance: RO: 4.3 SRO: 4.1 WA Statement: Ability to manually operate and/or monitor in the control room:
Emergency borate valve Task Standard: All critical steps for Emergency Boration via Gravity Feed per SOP-2A, Attachment 14 have been completed within 15 minutes.
Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform X - Simulate
References:
EOP-1.O, Standard Post-Trip Actions SOP-2A, Chemical and Volume Control System Validation Time: 5 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 8 AUGUST 2010
JPM RO SYS A Tools/EquipmenVProcedures Needed:
SOP-2A, "Chemical and Volume Control System," Attachment 14, "Emergency Manual Boration" 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:
0 The Reactor has tripped and four full length Control Rods are not fully inserted.
Bus I D has a fault and is de-energized.
Bus I C is energized.
INITIATING CUES:
0 The Control Room Supervisor directs you to commence Emergency Boration per EOP-1.O, Immediate Action step 1.c.l .
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM RO SYS A EVALUATOR NOTE: Emergency Boration is available by gravity feed only EVALUATOR CUE: Provide candidate a working copy of SOP-2A, Attachment 14 Proc.
TASK ELEMENT I STANDARD Orade WP Att. 14, Ensure charging flow greater than 1.0 I33gprn Comment:
I Charging flow is verified greater than 33 gpm Proc.
Step TASK ELEMENT 2 STANDARD Grade Comment:
If Bus 1D is energized.. .
I Determines that this step is not applicable I su If Bus 1C is energized, then , THEN PLACES handswitch for MO-2169 to open, ESTABLISH Gravity Feed (red light on, green light off)
Att. 14, 2.0b.l PLACES handswitchfor MO-2170 to open,
' OPEN M0-2169 and M0-21707 (red light on, green light off)
Boric Acid Tank Gravity Feed Isolation Valves.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
Step TASK ELEMENT 4 STANDARD Grade Att. 14, CLOSE CV-2155, Boric Acid Blender CV-2155 verified CLOSED (red light off, 2.0b.2 Outlet Control Valve green light on.)
su Comment:
Proc.
Step TASK ELEMENT 5 STANDARD Grade Att. 14, CLOSE MO-2087, VCT Outlet Isolation PLACES handswitch for MO-2087 to 2.0b.3 Valve CLOSE, (red light off, green light on).
su Comment:
Proc.
Step TASK ELEMENT 6 STANDARD Grade I Att. 14, 2.0b.4 I Close MO-2160, SIRW Tank to Charging Pumps Isolation I MO-2160 is verified CLOSED Isu Comment:
Evaluator Note: Operator should note that:
There is no position indication in the control room for MO-2160 due to bus 1D being de-energized.
MO-2160 can not be operated from the Control Room due to bus 1D being de-energized.
MO-2160 is normally closed I EVALUATOR CUE: If asked as A 0 to report MO-2160 position, report that MO-2160 is closed.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
Step TASK ELEMENT 7 STANDARD Grade I Att. 14, 2.0b.5 I If YO1 is not energized, THEN PERFORM the following:
I Determines that this step is not applicable lsul Comment:
Proc. Grade step TASK ELEMENT 8 STANDARD I Isul VERIFY charging flow greater than VERIFIES charging flow greater than 33 gpm 33 gpm as indicated by FIA-0212, on FIA-0212 Charging Line Flow Indicator Alarm Comment:
Proc. Grade Step TASKELEMENT 9 STANDARD Notify the Control Room Supervisor that na emergency boration is in progress CRS notified su END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO SYS A SIMULATOR OPERATOR INSTRUCTIONS Use any at power IC.
Insert malfunctions per the following table or use CAE file:
MALFUNCTION No. MALFUNCTION ET DELAY LOCATION RAMP VALUE TITLE RD16 Control rod stuck PIDRD02 5 (stuck)
(select any 4 full length control rods)
ED04B Loss of Bus 1D PIDEDOG True Trip the Reactor Carry out EOP-I .O Immediate Actions.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
I (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Reactor has tripped and four full length Control Rods are not fully insetted.
Bus I D has a fault and is de-energized.
Bus I C is energized.
INITIATING CUES:
The Control Room Supervisor directs you to commence Emergency Boration per EOP-1.O, Immediate Action step 1.c.l .
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS B TITLE: SHIFT OPERATING CCW PUMPS CANDIDATE:
EXAMINER:
JPM RO/SRO-I SYS B JOB PERFORMANCE MEASURE DATA PAGE Task: Shift Operating Component Cooling Water Pumps Alternate Path: YES - CCW pump will trip when started. Alternate CCW pump must be manually started to maintain CCW cooling.
Facility JPM #: PL-OPS-CCW-001J KIA: 008A2.0 1 Importance: RO:3.3 SRO: 3.6 WA Statement: Ability to predict impacts of loss of CCW pump and correct, control, or mitigate the consequences.
Task Standard: P-52A P-52B in service Preferred Evaluation Location: Simulator X In Plant Preferred Evaluation Method: Perform -X- Simulate
References:
ONP-6.2, Loss of Component Cooling SOP-I 6, Component Cooling Water System Validation Time: -1 5- 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 AUGUST 2010
JPM RO/SRO-I SYS B Tools/Equipment/Procedures Needed:
SOP-I 6, Component Cooling Water System ONP-6.2, Loss of Component Cooling 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:
0 The Plant is at full power.
0 Both CCW Heat Exchangers are in operation.
CCW Pump P-52A is in service CCW Pumps P-52B and P-52C are in STANDBY.
INITIATING CUES:
The Control Room Supervisor directs you to shift operating CCW pumps per SOP-16, Section 7.3.6.
P-52C is to be started and P-52A and P-52B are to be left in STANDBY.
~ PALISADES NUCLEAR PLANT Page 3 of 9 AUGUST 2010
JPM RO/SRO-I SYS B EVALUATOR CUE: Provide candidate a working copy of SOP-16, section 7.3.6.
Ptoc.Step TASK ELEMENT 1 I STANDARD Grade 7.3.6.a Ensure LOCKED OPEN CCW pump P-52C Contacts A 0 to ensure MV-CC921 and MV-suction and discharge valves. CC945 locked OPEN.
su Proc.Step TASK ELEMENT 2 I STANDARD Grade 7.3.6.b Contacts A 0 to cycle MV-CC558 open and Operate P-52C pump casing vent petcock closed.
to vent air from pump casing.
su CUE: A 0 reports MV-CC558 cycled open and closed.
Comment:
ProcStep TASK ELEMENT 3 I STANDARD Grade 7.3.6.c Verify both CCW Heat Exchangers in operation.
Both CCW Heat Exchangers in operation. su Comment:
NOTE: This info previously provided in Initial Conditions.
EVALUATOR CUE: If candidate asks for initial CCW Heat Exchanger AP give the following:
E-54A AP is 6.6 psid.
E-54B AP is 6.8 psid.
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 2010
JPM RO/SRO-I SYS B
. Proc.Step 7.3.6.d TASK ELEMENT 4 IF the pump being started is in standby, I STANDARD P-52C Handswitch taken to TRIP and amber Grade THEN REMOVE the pump from standby by STBY extinguishes.
placing Control Switch to TRIP.
Comment:
Proc.Step TASK ELEMENT 5 I' STANDARD P-52C CCW pump running. RED light above Grade 7'3'6'e START selected CCW Pump.
handswitch ON, GREEN light OFF.
Comment:
.L Proc.Step TASK ELEMENT 6 I STANDARD Grade 7.3.6.f IF handswitch on breaker was used, THEN PLACE Control Room handswitch Operator determines this step to be N/A since to "after close" to enable pump trip alarm pump was started from Control Room.
scheme.
Comment:
Proc.Step TASK ELEMENT 7 I STANDARD Grade 7m3.6'g P-52A has been stopped using handswitch.
STOP selected CCW Pump.
RED light OFF, GREEN light ON.
su Comment:
EVALUATOR NOTE: P-52C will trip 5 seconds affer P-52A is secured. P-526 will not auto start on low pressure.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM ROlSRO-I SYS B ProcStep TASK ELEMENT 8 I STANDARD Grade Refers to ARP'7, window 67 and notifies CRS of P-52C trip and the need to CRS notified. su reference ONP-6.2.
Comment:
EVALUATOR CUE:lf asked about any required actions for P-52A, role play and ask candidate what should be done. Candidate should state that ONP-6.2 should be entered and P-52A or P-52B should be manually started; agree and direct P-52A or P-526 started.
EXAMINER NOTE: Actual ONP entry is NOT required; CRS is directing use of ONP-6.2, 4.1.a step to start desired CCW pump.
EVALUATOR CUE: Provide candidate a working copy of ONP-6.2, page I.
IF less than 10 minutes has elapsed since - *Checks CCW Surge Tank level to ensure adequate inventory.
4.1.a loss of CCW, then start available CCW pumps as appropriate (based on suction - Starts P-52A (or P-52B).
su supply). - *Verifies RED Light ON, GREEN light OFF.
- = Not part of Critical Step Proc.Step TASK ELEMENT 10 STANDARD Grade 7.3.6.hJ PRESS amber STANDBY button for pump to be placed in STANDBY. Candidate determines this step is N/A from initial conditions.
su CHECK amber STANDBY button light ON.
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO/SRO-I SYS B Proc.Step TASK ELEMENT I?
I STANDARD Grade 7.3.6.j If required, adjust CCW Heat Exchanger AP OR CCW Pump discharge pressure. Ensures CCW Heat Exchanger AP values are
- Requests A 0 report on new CCW Hx acceptable.
AP values.
Comment:
EVALUATOR CUE: When requested, as A 0 report:
E-54A Hx AP = 6.8 psid E54B Hx AP = 6.5 psid END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
JPM RO/SRO-I SYS B SIMULATOR OPERATOR INSTRUCTIONS 0 Reset to IC-I7 0 Ensure CCW pump P-52A is running.
0 Ensure CCW Pump P-52B and P-52C in STANDBY 0 INSERT MF CCO2C for CCW Pump P-52C with a 5 second time delay, assign to Trigger I.
0 Insert Event Trigger 1 ZLOl P(46) = P-52A GREEN light 0 Insert CC13B (P-52B fail to start) to ACTIVE PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITlAL CONDITIONS:
The Plant is at full power.
Both CCW Heat Exchangers are in operation.
CCW Pump P-52A is in service CCW Pumps P-52B and P-52C are in STANDBY.
INITIATING CUES:
The Control Room Supervisor directs you to shift operating CCW pumps per SOP-16, Section 7.3.6.
P-52C is to be started and P-52A and P-52B are to be left in STANDBY.
PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO=I/SRO=USYS C TITLE: OPEN MAIN STEAM ISOLATION VALVES AFTER REACTOR IS CRITICAL CANDIDATE:
EXAMINER:
JPM: RO/SRO-VSRO-U SYS C JOB PERFORMANCE MEASURE DATA PAGE Task: Open MSlVs Alternate Path: YES - One MSlV will not open requiring ADV operation to open.
Facility JPM #: PL-OPS-MSS-001J K/A: 035K6.01 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: MSlVs Task Standard: Both MSlVs Open, MSlV 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: 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 AUGUST 2010
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.
I INITIAL CONDITIONS:
0 The reactor is critical with power at the POAH MSlV Bypass valves, MO-0501 and MO-0510, are open 0 Vacuum is established on the Main Turbine and the secondary plant is in the process of being started up I
INITIATING CUES:
The Control Room Supervisor directs you to open the MSlVs per SOP-7, starting at step 7.2.2.c.
PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C EVALUATOR CUE: Provide candidate a working copy of SOP-7, section 7.2.2.
Proc. Step TASK ELEMENT 1 STANDARD Grade I
Candidate contacts Auxiliary Operator to latch LATCH MSlV solenoid valves. all MSlV solenoids in the turbine building and 'D' S U bus area.
Comment:
SIM OPERATOR: Use MS36 on P&ID MS02, DO NOT latch 'A' MSlV (MS25) but report that it is complete.
Proc. Step TASK ELEMENT 2 I STANDARD Grade IF MSlVs opened after performance of Step 7.2.2~.THEN GO TO Step 7.2.211. I Candidate determines that CV-0510, 'A' S/G MSIV, did not open. Proceeds to step 7.2.2.e Comment:
EVALUATOR CUE: Role play as CRS and direct candidate to proceed to step 7.2.2.e, if asked.
TASK ELEMENT 3 STANDARD 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. su performing the following: - Has A 0 Close MV-CA390, Turbine Bypass CV-0511 A/S Isolation.
- Has A 0 OPEN accumulator drain valve to bleed pressure from CV-0511 accumulator, THEN CLOSE the valve.
Comment:
SIM OPERATOR: Use MS35 on PIDMSO3 to close air supply to CV-0511, then notify as A 0 that air supply is closed and accumulator is bled down PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 4 I STANDARD Grade f I PERFORM the following notifications of impending Steam Dump operation: I Candidate informs CRS to notify Chemistry and to refer to ADMlN 4.00.
Comment:
EVALUATOR CUE: Notify Candidate that the Shift Engineer will perform this.
Proc. Step TASK ELEMENT 5 I STANDARD Grade Candidate directs Auxiliary Operator to close the following valves in the ADV control cabinet:
CLOSE three of the four Steam Dump Air 9 Supplies for the MSlV to be opened, listed - MV-CA779 su 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 address LCO 3.7.4.
SIM OPERATOR: Use MS18, MSl9, MS20 (or MS21) on PID MSOI to close these valves PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 6 I STANDARD Grade PLACE HIC-O780A, Steam Generator Candidate:
E-50B Steam Dump to MANUAL.
- Places HIC-0780A in Manual su hg OPERATE HIC-0780A toward 100%
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-078OA reaches -25% output.
Proc. Step TASK ELEMENT 7 STANDARD Grade I
Proc. step I
TASK ELEMENT 8 I STANDARD Grade Candidate has A 0 open:
OPEN Steam Dump Air Supplies closed in - MV-CA779 Step 7.2.2g above. - MV-CA780 su
- MV-CA781 OR MV-CA782 Comment:
SIM OPERATOR: Use MS18, MS19, MS20 (or MS21) on PID MSOl to open the valves that were closed in Task Element #6.
PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010
JPM: ROlSRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 9 I STANDARD Grade IF both MSlVs did NOT open, THEN Candidate determines this step is N/A because I REPEAT Steps 7.2.29 through 7.2.2k for both MSIVs are now open.
affected MSIV.
Comment:
Proc. Step TASK ELEMENT 10 I STANDARD Grade I
I CLOSE CV-0511 accumulator drain valve.
I Candidate has AO:
I - CLOSE CV-0511 accumulator drain valve I
I m,n I OPEN MV-CA390, Turbine Bypass CV-0511 AIS IsoI.
I- OPEN MV-CA390, Turbine Bypass CV-0511 AIS Isol. I Comment:
SIM OPERATOR: Use MS35 on PlDMSO3 to open air supply to CV-0517.
Proc. Step TASK ELEMENT I 1 I STANDARD Grade RETURN HIC-0780A to AUTO or the AS FOUND position. Candidate places HIC-0780A and CV-0511 in O'
RETURN to Or the As AUTO by depressing the 'A' button on their controllers and verifying the 'A' button lights.
su FOUND position.
Comment:
EVALUATOR NOTE: If asked, inform candidate that PIC-0577 and HIC-078OA should be placed back in AUTO.
PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010
JPM: ROlSRO-VSRO-U SYS C Proc. step TASK ELEMENT 12 I STANDARD Grade CLOSE the following valves: Candidate closes MO-0501 and MO-0510 by holding switch in the CLOSE position until q M0-0501 MSIV cv-0501Bypass (MZ-3) associated Green light is ON and Red light is su MO-0510, MSlV CV-0510 Bypass (MZ-2) OFF.
Proo. Step TASK ELEMENT 13 Candidate informs the CRS that the MSlVs I STANDARD Grade
--- are open and the MSlV bypasses are CRS informed. su closed.
END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C SIMULATOR OPERATOR INSTRUCTIONS IC-I 2 Open MSlV Bypass Valves Close MSlVs Trip 'B' MFP, start P-8A Ensure Reactor Power is 2% (limit for MSlV Bypass valves open)[insert Group 4 rods to approximately 41"1 Insert the following triggers:
Trigger: 1 Event: ZA03F(62).gt.0.25 (ADV Controller reaches 25% output)
Action: irf ms25 latch (opens MSIV)
PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The reactor is critical with power at the POAH MSlV Bypass valves, MO-0501 and MO-0510, are open 0 Vacuum is established on the Main Turbine and the secondary plant is in the process of being started up INITIATING CUES:
The Control Room Supervisor directs you to open the MSlVs per SOP-7, starting at step 7.2.2.c.
PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROISRO-I SYS D TITLE: ALTERNATE PRESSURIZER LEVEL CONTROLLERS CANDIDATE:
EXAMINER:
JPM RO/SRO-I SYS D JOB PERFORMANCE MEASURE DATA PAGE Task: Alternate Pressurizer Level Controllers Alternate Path: YES - A Pressurizer Level Controller cannot be placed in CASCADE mode requiring restoration of B Pressurizer Level Controller.
Facility JPM #: PL-OPS-PZR-OOGJ WA: 01 1A4.01 Importance: RO: 3.5 SRO: 3.2 j
WA Statement: Ability to manually operate andlor monitor in the control room: Charging Pump and flow controls Task Standard: Candidate recognizes failure of A PZR level controller and shifts back to B PZR level controller per SOP-1A.
Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform -X- Simulate
References:
SOP-I A, 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 15 AUGUST 2010
JPM RO/SRO-I SYS D
~
Tools/Equipment/Procedures Needed: SOP-I A, "Primary Coolant System," section 7.2.1 .f 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.
INITlAL CONDITIONS:
It's Friday Day-Shift and per the Plant Daily Schedule, Pressurizer Level Controllers need to be alternated.
INITIATING CUES:
The Control Room Supervisor directs you to alternate Pressurizer Level Controllers per SOP-I A, section 7.2.1 .f., with the selected Pressurizer Level Controller in CASCADE.
PALISADES NUCLEAR PLANT Page 3 of 15 AUGUST 2010
JPM RO/SRO-I SYS D EVALUATOR CUE: Provide candidate a working copy of SOP-1A section 7.2.l.f.
ProcStep TASK ELEMENT 1 I STANDARD Grade I If alternating.. ., then PLACE Charging Pumps Control Select Switches for P-55B I P-55B Control Select Switch to MANUAL.
su Charging Pump (43-12061Ss) and P-55c Charging Pump (43-1105/SS) to MANUAL. I P-55C Control Select Switch to MANUAL.
Comment:
Proc.Step TASK ELEMENT 2 STANDARD Grade I f-2 I VERIFY controller to be selected in MANUAL.
Comment:
ProcStep TASK ELEMENT 3 I STANDARD Grade Using the manual operating lever, ADJUST the output signal of the controller to be Adjusts output signal on LIC-0101A to match f.3 selected to match the output signal of the output signal on LIC-0101B for bumpless su currently selected controller or to desired transfer.
output.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 2010
JPM RO/SRO-I SYS D ProcStep TASK ELEMENT 4 I STANDARD Grade I f.4 I PLACE selector switch 1/LRC-0101 to position for controller to be selected. I Places Selector Switch I/LRC-O101 to Channel 'A'.
Proc.Step TASK ELEMENT 5 I STANDARD Grade IF alternating controllers due to a malfunction of the previously selected Operator recognizes that this step does not f'5 channel, THEN PLACE the Pressurizer su apply.
Heater Control Channel Selector Switch.. .
Comment:
EVALUATOR CUE: If asked, state that CASCADE CONTROL IS DESIRED.
NOTES: Operator must place the 'A' Level Controller to AUTO prior to going to CASCADE mode of operation.
SOP-IA, section 7.2.1.f.6 is for placing the controller to AUTO.
SOP-IA, section 7.2.1.f.7 is for placing the controller to CASCADE.
IT is permissible not to use step 7.2.1.f.6 to place the controller to AUTO.
The third substep in 7.2.1 .f.7 is to place controller in AUTO.
IF Operator uses step 6 of SOP-1A section 7.2.l.f., go to Task Element 6.
If Operator NIA's step 6 of SOP-1A section 7.2.1.f, go to Task Element 9.
Proc.Step TASK ELEMENT 6 I IF the desired mode of operation is AUTO, II STANDARD I
Grade THEN PLACE the selected controller in Charging and Letdown checked as being AUTO as follows:
f'6'(a) (a) VERIFY Charging and Letdown in appropriate (one Charging Pump and one su operation as appropriate. Letdown Orifice in service).
I I I Comment:
PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 2010
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 7 I STANDARD Grade I
IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows: A controller raise/lower pushbuttons adjusted I pointer). I I Comment:
Proc.Step TASK ELEMENT 8 I STANDARD Depresses the A pushbutton On LIC-0101A to Grade IF the desired mode of operation isAUTO, THEN PLACE the selected controller in place it in AUTO and notes:
AUTO as follows: A AUTO light DOES NOT light su f.6.(c)
(c) DEPRESS the A pushbutton on M MANUAL light stays ON selected controller. Determines that LIC will not shift to AUTO Comment:
EVALUATOR CUE: If Operator announces that Controller will not go into AUTO, CRS acknowledges.
EVALUATOR CUE: If Operator asks what should be done, ask them what should be done. When Operator responds to swap back, then direct them to proceed.
NOTES: Operator can swap back to the ByLevel Controller two ways.
If Operator places selector switch IILRC-0101 to the B position, go to Task Element 12.
If Operator decides to swap back to the B Level Controller using SOP-IA, section 7.2.l.f, go to Task Element 13.
Either way to swap back to ByLevel Controller is acceptable.
PALISADES NUCLEAR PLANT Page 6 of 15 AUGUST 2010
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 9 I STANDARD Grade
\
IF the desired mode of operation is CASCADE, THEN PLACE the selected I f.7 (a)
I controller in CASCADE as follows:
(a) VERIFY expected TAVE signal available I TYT-0200 TAVE signal verified. su I from selected TAVEnREF controller (use TYT-0100, TYT-0200, or TI-01IO). I Comment:
TASK ELEMENT 10 STANDARD IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
'A controller raise/lower pushbuttons adjusted (b) Using raise/lower pushbuttons, SLOWLY to match controller setpoint (blue pointer) to f.7 (b) ADJUST selected controller setpoint (blue Pressurizer level setpoint (red pointer). (blue pointer) to the Pressurizer level setpoint pointer moved to match red pointer) determined by present TAVE. Refer to Attachment 10, "TAVE ( O F ) Pressurizer Level Program."
Comment:
CRlTlCAL STEP only If polntershwere naB matched PALISADES NUCLEAR PLANT Page 7 of 15 AUGUST 2010
JPM ROlSRO-I SYS D ProcSCep TASK ELEMENT 11 I STANDARD Grade IF the desired mode of operation is Depresses the Apushbutton on LIC-0101A to CASCADE, THEN PLACE the selected place it in AUTO and notes:
controller in CASCADE as follows:
f7 ()
(c) DEPRESS the A pushbutton on the AAUTO light DOES NOT light su selected controller. M MANUAL light stays ON Determines that LIC will not shift to AUTO Comment:
EVALUATOR CUE: If Operator announces that Controller will not go into AUTO, CRS acknowledges.
EVALUATOR CUE: If Operator asks what should be done, ask them what should be done. When Operator responds to swap back, then direct them to proceed.
NOTES: Operator can swap back to the ByLevel Controller two ways.
If Operator places selector switch IILRC-0101 to the B position, go to Task Element 12.
If Operator decides to swap back to the B Level Controller using SOP-IA, section 7.2.l.f, go to Task Element 13.
Either way to swap back to B Level Controller is acceptable.
ProcStep TASK ELEMENT 12 I STANDARD Grade
Place selector switch 1/LRC-0101 to position for controller to be selected.
Pressurizer Level Control Selector Switch 1/LRC-0101 placed to the Bposition.
su Comment:
EVALUATOR CUE: If CRS notified that 6Level Controller is in service, CRS acknowledges.
NOTES: B Level Controller in service in already in CASCADE mode.
If Operator performed Task Element 12, go to Task Element 25.
PALISADES NUCLEAR PLANT Page 8 of 15 AUGUST 2010
Proc.Step TASK ELEMENT 14 I STANDARD Grade Depresses M pushbutton on LIC-0101B to place in MANUAL and notes:
VERIFY controller to be selected in su f.2 MANUAL. M MANUAL light ON C CASCADE light OFF Comment:
I Proc.Step TASK ELEMENT 15 I STANDARD Grade Using the manual lever, ADJUST the output Adjusts the slide bar to on the BPressurizer signal of the controller to be selected to Level Controller being swapped to, matching fm3 match the output signal of the currently its output signal to the in-service controllers su selected controller. output signal.
Comment:
I CRITtGAL STEP - only If outputs were not matched Proc.Step TASK ELEMENT 16 I STANDARD Grade I f-4 I PLACE selector switch 1/LRC-0101 to position for controller to be selected. I Pressurizer Level Control Selector Switch 1ILRC-0101 placed to the B position.
I PALISADES NUCLEAR PLANT Page 9 of 15 AUGUST 2010
JPM ROlSRO-I SYS D Proc.Step TASK ELEMENT 17 IF alternating controllers due to a I STANDARD Grade malfunction of the previously selected Operator MAY reposition Heater Control fm5 channel, THEN PLACE the Pressurizer Channel Selector Switch to Channel 'B.'
su Heater Control Channel Selector Switch.. .
Comment:
EVALUATOR CUES:
7 If asked, state that CASCADE CONTROL IS DESIRED.
2 If asked whether to swap Heater Control Channel Selector Switch, reply that this action is not required for this failure.
NOTES: Operator must place the 'ByLevel Controller to AUTO prior to going to CASCADE mode of operation.
SOP-IA, section 7.2.1 .f.6 is for placing the controller to AUTO.
SOP-IA, section 7.2.1 .f.7 is for placing the controller to CASCADE.
IT is permissible not to use step 7.2.1.f.6 to place the controller to AUTO.
The third substep in 7.2.1 .f.7 is to place controller in AUTO.
IF Operator uses step 6 of SOP-1A section 7.2.l.f., go to Task Element 18.
If Operator NIA's step 6 of SOP-1A section 7.2.1 .f, go to Task Element 21.
THEN PLACE the selected controller in Charging and Letdown checked as being AUTO as follows:
f'6'(a)
(a) VERIFY Charging and Letdown in appropriate (one Charging Pump and one su Letdown Orifice in service).
operation as appropriate.
I Comment:
PALISADES NUCLEAR PLANT Page 10 of 15 AUGUST 2010
JPM RO/SRO-I SYS D PrOeStep TASK ELEMENT 19 IF the desired mode of operation is AUTO, I STANDARD THEN PLACE the selected controller in AUTO as follows: B controller raise/lower pushbuttons adjusted to match controller setpoint (blue pointer) to f.6.(b)
(b) Using raise/lower pushbuttons, ADJUST Pressurizer level setpoint (red pointer). (blue su selected controller setpoint (blue pointer) to pointer moved to match red pointer).
match indicated Pressurizer level (red I pointer). I Comment:
ProcStep TASK ELEMENT 20 STANDARD Grade IF the desired mode of operation is AUTO, Depresses the Apushbutton on LIC-0101B to THEN PLACE the selected controller in place it in AUTO and notes:
AUTO as follows:
f.6.(c)
AAUTO light ON su (c) DEPRESS the A pushbutton on M MANUAL light OFF selected controller.
Comment:
ProcStep TASK ELEMENT 21 I STANDARD Grade I I IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
I f.7 (a) TYT-0200 TAVE signal verified.
(a) VERIFY expected TAVE signal available from selected TAVE/TREF controller (use TYT-0100, TYT-0200, or TI-01 10).
Comment:
PALISADES NUCLEAR PLANT Page 11 of 15 AUGUST 2010
JPM RO/SRO-I SYS D TASK ELEMENT 22 STANDARD IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
B controller raise/lower pushbuttons adjusted (b) Using raise/lower pushbuttons, SLOWLY to match controller setpoint (blue pointer) to f.7 (b) ADJUST selected controller setpoint (blue Pressurizer level setpoint (red pointer). (blue su pointer) to the Pressurizer level setpoint pointer moved to match red pointer) determined by present TAVE. Refer to Attachment I O , TAVE (OF) Pressurizer Level Program.
Comment:
NOTE: Pressurizer level setpoint determined by present Tave. Operator may refer to SOP-1A attachment IO, Tave Pressurizer Level Program.
CRITICAL STEP only if pointers were not matched Proc.Step TASK ELEMENT 23 I STANDARD Grade IF the desired mode of operation is CASCADE, THEN PLACE the selected Depresses the A pushbutton on LIC-0101B to controller in CASCADE as follows: place it in AUTO and notes:
f7 (c) DEPRESS the A pushbutton on the A AUTO light ON su selected controller.
M MANUAL light OFF.
Comment:
Proc.Step TASK ELEMENT 24 STANDARD Grade IF the desired mode of operation is Depresses the C pushbutton pushed on CASCADE, THEN PLACE the selected LIC-0101B to place it in CASCADE and notes:
f.7.(d) controller in CASCADE as follows: su A AUTO light OFF (d) DEPRESS the C pushbutton on the selected controller. C CASCADE light ON Comment:
PALISADES NUCLEAR PLANT Page 12 of 15 AUGUST 2010
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 25 IF Charging Pumps P-55B and P-55C were I STANDARD Grade placed in MANUAL, THEN RETURN P-55B Control Select Switch to AUTO.
fm8 Charging Pumps Control Select Switches to su p-55~ Control Select Switch to AUTO.
AUTO.
Comment:
Proc.Step TASK ELEMENT 26 I STANDARD Grade PLACE the unselected controller in Operator recognizes A Level Controller is in f9 MANUAL, with a 50% output signal. MANUAL, places the output signal at 50%.
Comment:
EVALUATOR CUE: If Operator asks if A Level Controller should be left at current output signal, response is place a 50% output signal on the controller.
ProcStep TASK ELEMENT 27 I STANDARD Grade Notify CRS that Pressurizer Level CRS notified Pressurizer Level Controllers not Controllers were not alternated, with B alternated, B Level Controller in service.
Channel in service.
Comment:
EVALUATOR CUE: If notified, CRS acknowledges.
END OF TASK PALISADES NUCLEAR PLANT Page 13 of 15 AUGUST 2010
JPM ROISRO-I SYS D SIMULATOR OPERATOR INSTRUCTIONS 0 Reset to IC-17.
0 B Pressurizer Level Controller selected for service.
0 OVRD for LIC-0101A-AUT (A channel AUTO button in) to OFF 0 OVRD for LIC-0101A-MAN (A channel MANUAL button in) to ON PALISADES NUCLEAR PLANT Page 14 of 15 AUGUST 2010
JPM RO/SRO-I SYS D (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Its Friday Day-Shift and per the Plant Daily Schedule, Pressurizer Level Controllers need to be alternated.
INITIATING CUES:
The Control Room Supervisor directs you to alternate Pressurizer Level Controllers per SOP-I A, section 7.2.1 .f., with the selected Pressurizer Level Controller in CASCADE.
PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS E TITLE: VENT NON4ONDENSIBLE GASES FROM THE REACTOR VESSEL HEAD CANDIDATE:
EXAMINER:
c
JPM RO/SRO-I SYS E JOBPERFORMANCEMEASURE DATA PAGE Task: Vent Non-Condensible Gases from the Reactor Vessel Head Alternate Path: NO.
Facility JPM #: PL-OPS-EOP-039J KIA: 007A3.01 Importance: RO:2.7 SRO: 2.9 WA Statement: Ability to monitor automatic operation of the PRTS, including:
Components which discharge to the PRT.
Task Standard: Non-condensible gases have been vented from Reactor Vessel Head to the Quench Tank.
Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform -X- Simulate
References:
EOP Supplement 26, "PCS Void Removal" 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 8 AUGUST 2010
JPM RO/SRO-I SYS E
~~~~
Tools/Equipment/Procedures Needed:
EOP Supplement 26, "PCS Void Removal" 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:
A large break LOCA has occurred 0 There are indications of non-condensable gases in the Reactor vessel head The Left Channel Hydrogen Monitor is in service I INITIATING CUES:
You have been directed to vent the non-condensable gases from the Reactor vessel head, for five to ten minutes, using the preferred method in accordance with EOP Supplement 26, Section 3.0, step 1.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
EVALUATOR CUE: Provide candidate a working copy of EOP Supplement 26 Section 3.0.
Proc.Step TASK ELEMENT 1 I STANDARD Grade 3.1.a Ensure at least one Hydrogen Monitor su Provided in Conditions.
in operation.
Comment:
VALUATOR CUE: If candidate attempts to verify status using SOP-38, provide cue that this has already been performed.
TASK ELEMENT 2 STANDARD 3.1.c Obtains Key 110.
Places HS-1072 to RESET and then Open PRV-1072, Vent Path to Quench to OPEN. su Tank (preferred method). Verifies that PRV-1072 has opened (RED light is ON and GREEN light goes OFFY Comment:
- not critical PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM RO/SRO-I SYS E
- TASK ELEMENT 3 II - Obtains STANDARD Key 105.
3.1 .d Vent the Reactor Vessel Head by opening ONE of the following valves for 5-10 minutes:
0 PRV-1067 l- Places HS-1067 to RESET and then to OPEN.
- Verifies that PRV-1067 has opened (RED light is ON and GREEN light is OFF)*
-~
- Obtains Key 106.
PRV-1068
- Places HS-1068 to RESET and then to OPEN.
- Verifies that PRV-1068 has opened (RED light is ON and GREEN light is OFF)*
Comment:
Note: Use of either valve is acceptable.
- not critical PALISADESNUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO/SRO-I SYS E TASK ELEMENT 5 I STANDARD Secures Reactor Vessel Head venting - Using Key 105 places HS-1067 to by closing the appropriate valve which CLOSE.
was opened:
- Verifies that PRV-1067 has closed 0 PRV-1067 (RED light is OFF and GREEN light is ON)*
OR su PRV-1068 I Using Key 106 places HS-1068 to
- CLOSE.
- Verifies that PRV-1068 has closed (RED light is OFF and GREEN light is ON)*
Comment:
- - not critical I
Proc.Step TASK ELEMENT 6 I STANDARD Grade 3.1 .e I - Using Key 109 places HS-1072 to CLOSE.
Ensure closed PRV-1072, Vent Path to Quench Tank. - Verifies that PRV-1072 has closed su (RED light is OFF and GREEN light is ON)*
Comment:
- not critical END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO/SRO-I SYS E SIMULATOR OPERATOR INSTRUCTIONS 0 Reset to IC-17.
0 INSERT MF RCOI (Large Break LOCA).
0 Trip all PCPs.
0 Place Left Train Hydrogen Monitor in-service per SOP-38.
0 Ensure Reactor Head Vent Header pressure (on Panel C-I 1A rear) has bled off.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM RO/SRO-I SYS E (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A large break LOCA has occurred 0 There are indications of non-condensable gases in the Reactor vessel head The Left Channel Hydrogen Monitor is in service INITlATlNG CUES:
You have been directed to vent the non-condensable gases from the Reactor vessel head, for five to ten minutes, using the preferred method in accordance with EOP Supplement 26, Section 3.0, step 1.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS F TITLE: PLACE A CONTAINMENT RADIATION MONITOR IN SERVICE CANDI DATE:
EXAMINER:
JPM RO/SRO-I/SRO-U SYS F JOBPERFORMANCEMEASURE DATA PAGE Task: Operate the Area Radiation Monitoring System Alternate Path: YES - Operate light fails to illuminate when tested Facility JPM #: PL-OPS-RMS-004J WA: 072A4.01 Importance: RO: 3.0 SRO: 3.3 WA Statement: Ability to manually operate and/or monitor in the Control Room: Alarm and interlock setpoint checks and adjustments.
Task Standard: Green radiation monitor operate light for RIA-I 805 illuminated.
Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform -X- Simulate
References:
SOP-39, Area Radiation Monitoring System Validation Time: -I O - 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 8 AUGUST 2010
Tools/Equipment/Procedures Needed:
SOP-39, Area Radiation Monitoring System, 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 full power.
0 I&C personnel have just completed maintenance on Containment Radiation Monitor RIA-I 805.
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 8 AUGUST 2010
JPM RO/SRO-VSRO-U SYS F EVALUATOR CUE: Provide candidate a working copy of SOP-39, section 7.4.2.
Proc. Step TASK ELEMENT 1 I STANDARD Grade 7.4.2.a I REFER TO Attachment 3, Checklist CL 39, "Area Monitors System Checklist." I Candidate determines that this step is N/A per initial conditions. I Comment:
EVALUATOR CUE If asked, inform candidate that CL-39 has been completed for RIA-1805.
Proc. Step TASK ELEMENT 2 I STANDARD Grade I 7.4.2.b I CHECK operate light illuminated.
I Operator recognizes that the OPERATE light is not illuminated. I Comment:
Proc. Step TASK ELEMENT 3 IF operate light NOT illuminated, THEN I STANDARD Operator refers to Attachment 2 and locates Grade 7.4.2.c REFER TO Attachment 2, "System section 4.1 for Containment Radiation Monitors S U Malfunctions and Troubleshooting." Operate light not illuminated.
__ ~~~~
Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-39, Attachment 2.
Proc. Step TASK ELEMENT 4 I STANDARD Grade PRESS AND HOLD operate light. Operate light pressed and held su Comment:
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 5 I STANDARD I 4.1.b Comment:
CHECK other three monitors not tripped.
I Operator verifies Orange and Red (Trip 1 and Trip 2) lights not illuminated for RIA-1806, 1807 and 1808.
S U Proc. Step TASK ELEMENT 6 I STANDARD Grade PLACE Selector Switch momentarily to CHECK position AND RELEASE. I RIA-1805 selector switch placed in CHECK Dosition and released.
su I Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade 4.1 .d I RELEASE operate light. I Operate light is released Isu Comment:
Proc. Step TASK ELEMENT 8 STANDARD Operator resets:
AMBER Trip 1 4.1 .e RESET all alarms. su RED Trip 2 by depressing associated indicating light.
Comment:
PALISADESNUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 9 STANDARD Grade IF 'perate light stillnot THEN Operator determines this step is not applicable 4.1.f DECLARE the associated monitor because Operate light is illuminated.
su inoperable AND REFER TO 4.2 below.
Comment:
Proc. Step TASK ELEMENT 10 STANDARD Grade RESET all alarms. Operator verifies all alarms reset. su Comment:
Proc. Step TASK ELEMENT I 1 STANDARD Grade IF operate light still NOT illuminated, THEN DECLARE the associated monitor Operator determines this step is not applicable 7.4.2.6 inoperable. Refer to Attachment 2, because Operate light is illuminated.
"System Malfunctions and Troubleshooting.
Comment:
Proe. Step TASK ELEMENT 12 I STANDARD Grade Operator informs Control Room Supervisor nla that Containment Radiation Monitor CRS Notified su RIA-1805 has been placed in service.
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO/SRO-VSRO-U SYS F SIMULATOR OPERATOR INSTRUCTIONS 0 Reset to any IC 0 Insert OR RIA-1805-G to OFF on Panel C-I 1 rear 0 Create Event Trigger 1 as follows:
for Event .not.ZD14P(341).and.ZD14P(339) for Action dor RIA-I 805-G PALISADESNUCLEAR PLANT Page 7 of 8 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The Plant is operating at full power.
0 I&C personnel have just completed maintenance on Containment Radiation Monitor RIA-I 805.
CL-39 for RIA-I805 has been completed INITIATING CUES:
The Control Room Supervisor directs you to place Containment Radiation Monitor, RIA-I 805, in service per SOP-39, step 7.4.2.
Another operator will answer any front panel alarms.
PALISADESNUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS H TITLE: TEMPORARILY SECURE SHUTDOWN COOLING FLOW CANDIDATE:
EXAMINER:
JPM: RO/SRO-I SYS H JOB PERFORMANCE MEASURE DATA PAGE Task: Temporarily Secure Shutdown Cooling Flow Alternate Path: NO Facility JPM #: NEW WA: 005A4.01 Importance: RO: 3.6 SRO: 3.4 K/A Statement: Ability to manually operate andlor monitor in the control room: Controls and indications for RHR pumps Task Standard: Shutdown Cooling secured per SOP-3 Preferred Evaluation Location: Simulator X - In Plant Preferred Evaluation Method: Perform -X- Simulate
References:
SOP-3, Safety Injection and Shutdown Cooling System 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 12 AUGUST 2010
Tools/Equipment/Procedures Needed:
0 SOP-3, "Safety Injection and Shutdown Cooling System, "sections 7.3.6 and 7.3.4 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 the middle of a 45 day refueling outage.
0 P-67B is the LPSl Pump in service with PCS temperature approximately 108°F 0 Plant is in solid-plant pressure control: another Operator will control PCS pressure during this evolution Shutdown Cooling is expected to be secured for 30 minutes The maximum expected PCS heatup after Shutdown Cooling is secured is 20"F/hr PCS and Pressurizer parameters are being monitored via performance of PO-2, "PCS HeatuplCooldown Operations" All GOP-14 requirements are met for this evolution with all Management signoffs complete INITIATING CUES:
The Control Room Supervisor directs you to temporarily secure Shutdown Cooling flow per SOP-3, Section 7.3.6. You are further directed to have MO-3014, Loop 26 LPSl Injection Valve, to be the valve that is left in the throttled position when performing step 7.3.6.c.
PALISADES NUCLEAR PLANT Page 3 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H EVALUATOR CUE: Provide candidate a working copy of SOP-3, Section 7.3.6 TASK ELEMENT I STANDARD ENSURE the following:
- 1. PCS level greater than 623'-0".
- 2. Requirements of Step 5.1.2 and Technical Specifications LCO 3.4.7, LCO 3.4.8, LCO 3.9.4, or LCO 3.9.5, as applicable, are met.
7.3.6.a
- 3. PCS heatup rate and allowable outage Given in the Initial Conditions time determined. Refer to Section 7.3.7.
- 4. Requirements of General Operating Procedure GOP-14, "Shutdown Cooling Operations," are met.
- 5. Operations Superintendent approval to secure Shutdown Cooling flow has been obtained.
Comment:
TASK ELEMENT 2 STANDARD Grade IF PCS temperature will be changed more than five (5) degrees from the established target temperature, THEN ENSURE PCS Determines that this step is being met.
1 7.3.6.b and Pressurizer parameters are being su (PO-2 performance given in initial conditions) monitored. Refer to PO-2, "PCS Heatup/Cooldown Operations."
Comment:
PALISADES NUCLEAR PLANT Page 4 of 12 AUGUST 2010
~
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 3 I STANDARD Grade 7.3.6.c Comment:
PERFORM Section 7.3.4 to reduce total Shutdown Cooling flow to approximately 300 to 500 arm. I Branches to section 7.3.4 of SOP-3 I su Evaluator provides a Working Copy of SOP-3, Section 7.3.4 EVALUATOR CUE: Another Operator will control PCS pressure during this evolution.
Prac. Step TASK ELEMENT 4 STANDARD Grade IF PCS temperature will be changed more than five (5) degrees from the established target temperature, THEN ENSURE pcs Determines that this step is being met.
7.3.4.a and Pressurizer parameters are being su (PO-2 performance given in initial conditions) monitored. Refer to PO-2, "PCS HeatuD/Cooldown ODerations."
Proc. Step TASK ELEMENT 5 STANDARD Grade IF PCS level is greater than 643'4" AND any CRDM tool access flanges are Determines that this step does not apply.
7.3.4.b removed, THEN ENSURE personnel are clear of CRDM tool access flanges and (PCS level is given in initial conditions)
Reactor Cavity.
Comment:
I Proc. Step TASK ELEMENT 6 STANDARD Grade DETERMINE desired total Shutdown Determines 300-500 gpm applies (from 7.3.4x Cooling flow. previous step 7.3.6.c).
su PALISADES NUCLEAR PLANT Page 5 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Pmn Step TASK ELEMENT 7 I STANDARD Grade IF Shutdown Cooling flow is to be throttled Determines that sub-steps 1, 2, and 3 do not su 7m3.4md below 2810 gpm, ... apply.
Comment:
EVALUATOR CUE: CRS directs that sub-step 3 is not applicable for this evolution.
7.3.4.d TASK ELEMENT 8 IF Shutdown Cooling flow is to be throttled below 2810 gpm, ...
- 4. IF PCS recirculation flow rate is less than the minimum required by Technical Specifications LCO 3.4.7, LCO 3.4.8, LCO 3.9.4, or LCO 3.9.5, THENCLOSEANDDANGERTAG MV-CVC2162, Primary Makeup m STANDARD Notifies CRS of need to Danger Tag MV-CVC2162.
su Water Supply Stop within one hour.
Comment:
EVALUATOR CUE IF informed as CRS of need to hang Danger Tag on MV-CVC2162:
acknowledge and inform Operator that this was already completed by another operator during GOP-74.
Proc. Step TASK ELEMENT 9 STANDARD IF Shutdown Cooling flow is to be throttled below 2810 gpm, ...
Notifies CRS of need to maintain GOP-14 7.3.4.d 5. MAINTAIN General Operating requirements.
Procedure GOP-14, "Shutdown I Cooling Operations," requirements. I Comment:
EVALUATOR CUE: IF informed as CRS of need to maintain GOP-74 requirements:
acknowledge.
PALISADES NUCLEAR PLANT Page 6 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 10 STANDARD Grade I 7.3.4.e Comment:
DETERMINE required status of..
Determines that maximum of one throttled/open LPSl Injection Valve applies. (per initiating cue this will be MO-3014)
~
su
~~~
Checks FIC-0306 is in MANUAL.
TASK ELEMENT 12 STANDARD SLOWLY operates each of the four LPSl Injection Valves (one at a time) until only one (MO-3014) LPSl Injection Valve is throttled open ADJUST Shutdown Cooling flow as and SDC flow is 300 to 500 gpm.
follows:
7.3.4.f 2. SLOWLY OPERATE LPSl Injection 0 MO-3010 closed su Valves to establish status determined in Step 7.3.4e. 0 MO-3012 closed MO-3008 closed 0 MO-3014 throttled open Comment:
PALISADES NUCLEAR PLANT Page 7 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Pmc. Step TASK ELEMENT 13 STANDARD Grade, ADJUST Shutdown Coolina flow as follows:
- 3. BALANCE flow between in use 7.3.4.f LPSl Injection Loops to desired Total Determines this step is not applicable. su Shutdown Cooling flow determined in Comment:
Proc, step TASK ELEMENT 14 ADJUST Shutdown Cooling flow as follows:
- 4. If necessary:
7.3.4.f (a) THROTTLE CV-3025, SDC Determines this step is not applicable. su Hx Outlet to maintain desired Comment:
TASK ELEMENT 15 STANDARD ADJUST Shutdown Coolina flow as follows:
- 4. If necessary:
(b) THROTTLE FIC-0306 Output Determines this step is not applicable.
7.3.4.f signal to maintain desired flow through Shutdown Cooling Heat Branches back to section 7.3.6 of SOP-3 Exchangers.
Comment:
PALISADES NUCLEAR PLANT Page 8 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 16 STANDARD WHEN Total Shutdown Cooling flow has HIC-3025A MANUAL Slide Bar used to CLOSE been reduced to approximately 300 to (Slide bar taken to the left) CV-3025 500 gpm, THEN PERFORM the following:
7.3.6.d -
AND
- 1. CLOSE CV-3025, SDC Hx Outlet. CO-ORDINATES with the with Operator controlling PCS Pressure Comment:
EVALUATOR NOTE: Procedure written for one person operation, this is a two person operation, it is not CRITICAL for the co-ordination from a JPM standpoint.
TASK ELEMENT 17 STANDARD WHEN Total Shutdown Cooling flow has been reduced to approximately 300 to 500 gpm, THEN PERFORM the following: HS-3055A to CLOSE with key.
(Key may be removed or left in keyslot)
- 2. CLOSE CV-3055, SDC Hx Inlet.
Comment:
7.3.6.d I
I been reduced to amroximatelv 300 to 500 gpm, THEN PERFORM the following:
I I P-67B STOPPED su I 3. STOP the operating LPSl Pump.
Comment:
PALISADES NUCLEAR PLANT Page 9 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT I 9 STANDARD Grade NOTIFY the CRS that Shutdown Cooling has been temporarily secured per SOP-3, CRS NOTIFIED SDC temporarily secured su Section 7.3.6.
END OF TASK PALISADESNUCLEAR PLANT Page 10 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H SIMULATOR OPERATOR INSTRUCTIONS 0 IC-2, Ready to Start PCPs 0 Need Dedicated Operator to control PCS pressure during evolution (solid plant control) 0 Ensure TR-0351 S/D Cooling recorder in operation 0 Keys installed in the following MOVs:
MO-3015
. MO-3016 MO-3189 MO-3198
. MO-3190 m MO-3199 0 Ensure Caution Tags on CV-3057 and CV-3031 PALISADES NUCLEAR PLANT Page 11 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is in the middle of a 45 day refueling outage.
0 P-67B is the LPSl Pump in service with PCS temperature approximately 108°F Plant is in solid-plant pressure control: another Operator will control PCS pressure during this evolution Shutdown Cooling is expected to be secured for 30 minutes The maximum expected PCS heatup after Shutdown Cooling is secured is 20"F/hr PCS and Pressurizer parameters are being monitored via performance of PO-2, "PCS Heatup/Cooldown Operations" All GOP-14 requirements are met for this evolution with all Management signoffs complete INITIATING CUES:
The Control Room Supervisor directs you to temporarily secure Shutdown Cooling flow per SOP-3, Section 7.3.6. You are further directed to have MO-3014, Loop 2B LPSl Injection Valve, to be the valve that is left in the throttled position when performing step 7.3.6.c.
PALISADES NUCLEAR PLANT Page 12 of 12 AUGUST 2010
NRC REGION 111 -
INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYSTEM I TITLE: SECURE FROM A WASTE GAS RELEASE CANDIDATE:
EXAMINER:
JPM: RO/SRO-VSRO-U SYS I JOB PERFORMANCE MEASURE DATA PAGE Task: Secure from Waste Gas Release Alternate Path: NO Facility JPM #: PL-OPS-WGS-001J WA: 071K4.04 Importance: RO: 2.9 SRO: 3.4 WA Statement: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Isolation of waste gas release tanks Task Standard: T-68B Waste Gas Decay Tank release secured Preferred Evaluation Location: Simulator In Plant -X-Preferred Evaluation Method: Perform Simulate X -
References:
SOP-I 8A, Radioactive Waste System - Gaseous Validation Time: 10 minutes Time Critical: NO Candidate:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature PALISADESNUCLEAR PLANT Page 2 of 6 AUGUST 2010
Tools/Equipment/Procedures Needed:
0 SOP-I 8A, "Radioactive Waste System - Gaseous, "Section 7.5 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:
0 The Plant is at 48% power 0 T-68B Waste Gas Decay Tank batch release is in progress 0 It has been determined that the batch release must be secured INITIATING CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 3 of 6 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I EVALUATOR CUE: Provide candidate a working copy of SOP-I8A, Section 7.5, step nn Proc. Step TASK ELEMENT 1 STANDARD SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge nn.1 Header Valves T-68NB/C: MV-WG719 CLOSED su
. MV-WG719, T-68A, B & C Outlet Comment:
Isolation EVALUATOR NOTE: Task Elements I and 2 can be performed in any order since they are bulleted substeps Proc. Step TASK ELEMENT 2 I STANDARD Grade I SECURE from WGDT release as follows: I I
- 1. CLOSE appropriate Discharge nn.1 Header Valves T-68NBIC: MV-WG718A CLOSED
. MV-WG718A, T-I 01A, B & C Outlet Isolation Comment:
EVALUATOR NOTE: Task Elements 1 and 2 can be performed in any order since they are bulleted substeps Proc. Step nn.2.a TASK ELEMENT 3 CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
.PLACE in CLOSE position HS-1123, Waste Gas Decay Tanks Discharge, at C-40 3 STANDARD HS-1123 in CLOSE su Comment:
EVALUATOR CUE: CV-1123 is closed, the green light is lit.
PALISADES NUCLEAR PLANT Page 4 of 6 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS I Proc. Step TASK ELEMENT 4 CLOSE Discharge Control Valve CV-1123, I STANDARD Grade WGDT Discharge, as follows:
nn.2.b HIC-1123 INDICATING 0 psi su
.SET to zero (0) psi HIC-1123, Waste Gas Discharge To Stack Comment:
EVALUATOR CUE: HIC-1123 indicates 0 psi Proc. Step TASK ELEMENT 5 STANDARD OPEN ONE of the following Drain Valves to DRAIN selected WGDT for one (1) minute, THEN CLOSE: OPENS MV-CA352 for one (1) and then nn.3 mMV-CA352, I/A Isolation/Control To CLOSED su CV-l120B, T-68B Drain Valve (Opens MV-CA352 which opens CV-11208)
Comment:
EVALUATOR CUE: one minute has elapsed.
Proc. step TASK ELEMENT 6 I STANDARD Grade n/a I NOTIFY CRS that WGDT T-68B release secured I CRS WGDT T-68B SECURED Isu Comment:
END OF TASK PALISADESNUCLEAR PLANT Page 5 of 6 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I
~
(TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is at 48% power 0 T-68B Waste Gas Decay Tank batch release is in progress 0 It has been determined that the batch release must be secured INITIATING CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 6 of 6 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE
JPM: RO/SRO-I SYS J JOB PERFORMANCE MEASURE Task: Establish/control alternate Auxiliary Feedwater methods IAW EOP Supplement 19 Alternate Path: YES - Turbine Driver K-8 is found to be unlatched and reset lever operation is required to complete task.
Facility JPM #: PL-OPS-ONP-OIOJ KIA: 061A2.04 Importance: RO: 3.4 SRO: 3.8 WA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct; control; or mitigate the consequences of those malfunctions or operations: pump failure or improper operation Task Standard: AFW Pump P-8B is operating with steam supplied via CV-0522BI K-8 Steam Supply from E-50A, in local control Preferred Evaluation Location: Simulator In Plant -X-Preferred Evaluation Method: Perform Simulate -X-
References:
ONP-25.2, Alternate Safe Shutdown Procedure EOP Supplement 19, Alternate Auxiliary Feedwater Methods Validation Time: 15 minutes Time Critical: NO Candidate:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature PALISADESNUCLEAR PLANT Page 2 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Tools/Equipment/Procedures Needed:
EOP Supplement 19, Alternate Auxiliary Feedwater Methods, section 4, P-8B Normal Steam Supply From A S/G including page 21 of supplement 19 I READ TO CANDIDATE I 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:
AFW flow control valves for P-8BI AFW Pump, have been verified closed.
Buses I C and 1D are NOT energized.
ASteam Generator steam and feed paths to both Steam Generators are available.
CV-O522B, K-8 Normal Steam Supply, is closed and cannot be operated from either the Control Room or C-I 50 Panel.
INITIATING CUES:
During performance of ONP-25.2, Alternate Safe Shutdown Procedure, the CRS directs you to start P-8B locally using the Preferred Method of EOP Supplement 19 Section 4.0.
PALISADES NUCLEAR PLANT Page 3 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J EVALUATOR CUE:Provide candidate a working copy of EOP Supplement I 9 Proc. Step TASK ELEMENT 1 I STANDARD Grade OPEN HS-O522B, K-8 Normal Steam 4.0.1 Supply, from one of the following prioritized Determines that this step is not applicable su locations.. .
Comment:
EVALUATOR CUE:lf asked if CV-0522B can be operated from either the Control Room or C-150 Panel, report that CV-05228 cannot be remotely operated I Proc. Step TASK ELEMENT 2 STANDARD Grade CLOSE the following valves: Simulates or describes CLOSING by turning the MV-CA377, air supply to CV-0522B handwheel clockwise:
4m0.2.a
. MV-N2/268, nitrogen supply to CV-0522B
-MV-CA377, air supply to CV-0522B su mMV-N2/268, nitrogen supply to CV-0522B Comment:
EVALUATOR CUE: The valves are closed Proc. Step TASK ELEMENT 3 I STANDARD Grade MANUALLY CLOSE CV-O522B, K-8 Steam Supply From E-50A, as follows: Simulates or describes UNSCREWING coupling 4.0.2.b.l
. UNSCREW the coupling from the manual override shaft from shaft by turning coupling counter clockwise Comment:
EVALUATOR CUE: Provide page 21 of EOP Supplement 19 EVALUATOR CUE: The coupling is unscrewed from the shaft NOTE: A ladder may be used to access the coupling PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 4 STANDARD MANUALLY CLOSE CV-O522B, K-8 Normal Steam Supply, as follows:
4.0-2-b-2 . TURN handwheel clockwise until the top of the actuator shaft is exposed Simulates or describes TURNING handwheel clockwise until manual override shaft is exposed su sufficiently to engage the coupling Comment:
EVALUATOR CUE: The manual shaft is exposed Proc. Step TASK ELEMENT 5 I STANDARD Grade INSERT the fork of the coupling all the way Simulates or describes INSERTING coupling all 4m02b3 onto actuator shaft the way onto shaft Comment:
NOTE: EOP Supplement 79, page 27 has a labeled diagram of CV-05226 EVALUATOR CUE: The coupling is all the way onto the shaft Proc. Step TASK ELEMENT 6 I STANDARD Grade REMOVE lockwire from MV-FW356, CV-0522B Bonnet Isolation I Simulates or describes REMOVING the lockwire I S U Comment:
EVALUATOR CUE: The lockwire is removed from MV-FW356, CV-05226 Bonnet Isolation PALISADESNUCLEAR PLANT Page 5 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 7 I STANDARD Grade Simulates or describes OPENING MV-FW356 by OPEN MV-FW356, CV-0522B Bonnet TURNING handle 90 degrees (places it "in-line" S U 4.0.2.b.5 Isolation with the turbine/piping).
Comment:
EVALUATOR CUE: MV-FW356, CV-0522B Bonnet Isolation handle is in line with the tubing Proc. Step TASK ELEMENT 8 STANDARD Grade Simulates or describes checking valve closed by CLOSE CV-O522B, K-8 Normal Steam 4'0'2'bA TURNING handwheel in the clockwise direction S U Supply, using the handwheel (given in the initial conditions)
Comment:
EVALUATOR CUE: If asked about the position of CV-O522B, report that it is closed Proc. Step TASK ELEMENT 9 I STANDARD Orade CHECK Turbine Driver K-8 is latched as follows:
4.0.2.c.l
. ENSURE the end of resetting level (knife edge) is in contact with the trip Determines that Turbine Driver is NOT RESET S U level (can NOT slip a sheet of paper between),. Refer to Figure 1 (Page Comment:
EVALUATOR CUE: Provide EOP Supplement 79, page 20 EVALUATOR CUE: The Knife edge of resetting lever is hanging down and not in contact with the hand trip lever
I-- NOTE: Alternate Path begins here and is covered in task elements 10 and 11-------
PALISADES NUCLEAR PLANT Page 6 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 10 I STANDARD Grade CHECK Turbine Driver K-8 is NOT latched, THEN RELATCH as follows: Simulates or describes verifying that CV-05228 4.0.2.c.2.a su ENSURE CLOSED CV-05228, K-8 is Normal Steam Supply Comment:
EVALUATOR CUE: If asked about the position of CV-O522B, report that it is closed Proc. step TASK ELEMENT 11 STANDARD CHECK Turbine Driver K-8 is NOT latched, THEN RELATCH as follows: Simulates or describes PULLING UP on the 4.0.2.c.2.b .RESET the overspeed trip lever on Turbine Driver K-8 using the Auxiliary Auxiliary Reset lever Until the lever iS in Contact with the knife edge su Reset lever Comment:
EVALUATOR CUE: The knife edge of resetting lever is in contact with the hand trip lever Proc. Step TASK ELEMENT 12 I STANDARD Orade CLEAR personnel from the Auxiliary na Feedwater Pump room CHECKS room for personnel su Comment:
EVALUATOR CUE: There are no other personnel in the Auxiliary Feedwater Pump room PALISADES NUCLEAR PLANT Page 7 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 13 I STANDARD Grade 4.0.2.d Comment:
OPEN MV-FW688, PI-0590 root valve I Simulates or describes OPENING MV-FW688, PI-0590 root valve by TURNING the handwheel counter clockwise lsul EVALUATOR CUE: Valve is open TASK ELEMENT 14 STANDARD SLOWLY THROTTLE OPEN CV-0522B to maintain between 200 and 250 psig steam pressure on any of the following: Simulates or describes OPENING CV-0522B 4.0.2.e . PI-0590 with the hand operator by TURNING handwheel su
. PI-0521A counter clockwise
. PI-0521B Comment:
EVALUATOR CUE:Steam flow noise can be heard, CV-0522B, K-8 Normal Steam Supply indicates off its full closed position, and pressure on gauge is rising.
Proc. Step TASK ELEMENT 15 I STANDARD Grade I CHECK PI-0590 OR PI-0521B reading 4'0m2me between 200 and 250 psig I VERIFIES PI-0590 OR PI-0521B reading between 200 to 250 psig lsul Comment:
EVALUATOR CUE: PI-0590 OR PI-05216 indicates 235 psis and stable PALISADES NUCLEAR PLANT Page 8 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 16 I STANDARD Grade Notify CRS that AFW Pump, P-8B is CRS NOTIFIED that AFW Pump, P-8B is
a operating operating with CV-0522B opened manually su END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J SIMULATOR OPERATOR INSTRUCTIONS 0 N/A PALISADESNUCLEAR PLANT Page 10 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J
~
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
AFW flow control valves for P-8BI AFW Pump, have been verified closed.
Buses 1C and 1D are NOT energized.
A Steam Generator steam and feed paths to both Steam Generators are available.
CV-O522B, K-8 Normal Steam Supply, is closed and cannot be operated from either the Control Room or C-I 50 Panel.
INITIATING CUES:
During performance of ONP-25.2, Alternate Safe Shutdown Procedure, the CRS directs you to start P-8B locally using the Preferred Method of EOP Supplement 19 Section 4.0.
PALISADES NUCLEAR PLANT Page 11 of 11 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE I
JPM: RO/SRO-l/SRO-U SYS K TITLE: REDUCE STATION BATTERY #ILOADING CANDIDATE:
EXAMINER:
JPM RO/SRO-VSRO-U SYS K JOB PERFORMANCE MEASURE
~
Task: Reduce Station Battery Loading Alternate Path: NO Facility JPM #: PL-OPS-EOP-021J K/A: 063A1.01 Importance: RO: 2.5 SRO: 3.3 K/A Statement: Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate.
Task Standard: Station Battery #I loading reduced to 30 min. I157 amps Comment:
TASK ELEMENT 4 STANDARD P
IF Station Battery No 1 discharge current Operator performs the following:
is greater than, or will be greater than, the limits of Step 1.3, THEN PERFORM the
- Determines that discharge current of following steps, as necessary, to maintain 190 amps is poJ acceptable discharge current within acceptable limits:
OPEN the following breakers in the Cable Spreading Room:
Panel D11-1 - Simulates OPENING breakers on panels 72-107 D11-1 and D l l - 2 .
1.0.4.a 72-113 72-114 72-116 Panel D11-2 72-122 72-126 72-128 72-130 72-133 72-134 Comment:
EVALUATOR CUE:lf candidate attempts to refer to drawing E-35 for valve failure modes, inform candidate that the Control Room has completed this.
EVALUATOR CUE:As each breaker is opened, cue operator that breaker indicates OFF.
Battery discharge current will lower by only 2 or 3 amps for each breaker.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS K Proc. Step TASK ELEMENT 5 STANDARD Operator performs the following:
WHEN the above breakers are open, THEN RECORD the following: - RECORDS present time
- 1) Time: - Depresses Lower Scale Reading push 1.0.4.b button
- 2) Station Battery No 1 discharge Comment:
current: EAI-45:
amps
- Reads inner scale of ammeter RECORDS Battery No. 1 discharge current I EVALUATOR CUE:lf candidate pushes inner scale pushbutton, then use pointer and place on Station Battery No. 1 ammeter, EA/-45, to indicate 170 AMPS out on inner scale.
EVALUATOR CUE:lf candidate does NOT push inner scale pushbutton, use pointer and place on Station Battery No. I ammeter, AI-45, to indicate 170 AMPS out on outer scale.
Proc. Step TASK ELEMENT 6 IF Station Battery No 1 discharge current Operator performs the following:
continues to be greater than the acceptable limits of Step 1.3, THEN OPEN - Determines that discharge current is still 1.0.4.c the following breaker in Cable Spreading not acceptable su Room - Simulates OPENING breaker 72-17 on D-72-17 (D-I 0) 10 Comment:
EVALUATOR CUE:Provide cue that breaker indicates OFF. Battery discharge current should lower by approximately 40 amps.
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS K Proc. Step TASK ELEMENT 7 STANDARD Operator performs the following:
WHEN the above breaker is open, THEN RECORD the following: - RECORDS present time 1.0.4.d
- 1) Time: - Depresses Lower Scale Reading push button
- 2) Station Battery No 1 discharge current: EAI-45: - Reads inner scale of ammeter amps RECORDS Battery No. 1 discharge current Comment:
EVALUATOR CUE:lf candidate pushes inner scale pushbutton, then use pointer and place on Station Battery No. I ammeter, EA/-45, to indicate 135 AMPS out on inner scale.
EVALUATOR CUE:lf candidate does NOT push inner scale pushbutton, use pointer and place on Station Battery No. 1 ammeter, EA/-45, to indicate 135 AMPS out on outer scale.
Proc. step IF TASK ELEMENT 8 Battery No discharge current I STANDARD Grade Operator determines that this step is N/A continues to be greater than the 1.0.4.e acceptable limits of Step 1.3, THEN because Battery No. 1 discharge current is su
<I57 amps PERFORM the following.. .
Comment:
Proc. Step TASK ELEMENT 9 Operator informs Control Room that task I STANDARD Grade nla is complete Control Room informed su
~~
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
JPM RO/SRO-VSRO-U SYS K SIMULATOR OPERATOR INSTRUCTIONS 0 N/A PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
I JPM RO/SRO-VSRO-U SYS K (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITlAL CONDITIONS:
All AC power is lost It is approximately 35 minutes after the loss of all AC power 1-1 and 1-2 Diesel Generators will poJ start INITIATING CUES:
During performance of EOP-3.0, Electrical Emergency Recovery, Step 19, the CRS directs you to ensure Station Battery #I discharge is within limits per EOP Supplement 7.
PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010