ML111460149
| ML111460149 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML102070539 | List: |
| References | |
| Download: ML111460149 (109) | |
Text
r 2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION PROPOSED EXAM FILES PROPOSED CONTROL ROOM JPMs
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: ROSYSA TITLE: EMERGENCY BORATE (WITHOUT BUS I D )
CAND I DATE:
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-013J WA: 004A4.18 Importance: RO: 4.3 SRO: 4.1 K/A 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-I.O, Standard Post-Trip Act ions SOP-2A, Chemical and Volume Control System Validation Time: 5 minutes Time Critical: YES (15 minutes)
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 SYS A Tools/Equipment/Procedures Needed:
SOP-2A, "Chemical and Volume Control System," Attachment 14, "Emergency ManuaI Borat ion I' 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:
The Reactor has tripped and four full length Control Rods are p cJ fully inserted.
0 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.
This JPM is time critical. (Time limit will not be provided.)
Time will start upon the completion of communication for the Initiating Cue.
This JPM is Time Critical.
PALISADES NUCLEAR PLANT Page 3 of 9 AUGUST 2010
JPM: RO SYS A Proc.
Step TASK ELEMENT I STANDARD Grade t
I nla I Obtains correct procedure I SOP-2A, Attachment 14 is located I Comment:
EVALUATOR NOTE: Emergency Boration is available by gravity feed only EVALUATOR CUE: Provide candidate a working copy of SOP-2A, Attachment 14 Proc.
Step TASK ELEMENT 2 STANDARD Grade Att. 14, 1.0 I Ensure charging flow greater than 33 gpm I Charging flow is verified greater than 33 gpm I S U
~ _ _ _ _
Comment:
Roc.
TASK ELEMENT 3 STANDARD Grade S@P Att. 14 If Bus 1D is energized.. . Determines that this step is not applicable su 2.0a Comment:
Proc.
Step TASK ELEMENT 4 STANDARD Grade If Bus I C is energized, then , THEN ESTABLISH Gravity Feed PLACES handswitch for MO-2169 to open, Att. 14, (red light on, green light off) 2.0b.l .OPEN MO-2169 and MO-2170, Boric Acid Tank Gravity Feed su Isolation Valves.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 2010
ESTABLISH Gravity Feed (red light on, green light off)
.OPEN MO-2169 and MO-2170, Boric Acid Tank Gravity Feed I I Isolation Valves. I I Comment:
Proc.
Step TASK ELEMENT 6 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 Proc.
step TASK ELEMENT 7 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 PALISADESNUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM: RO SYS A Proe. TASK ELEMENT 8 STANDARD Grade step Close MO-2160, SlRW 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 EVALUATOR CUE: If asked as A 0 to report MO-2760 position, report that MO-2760 is closed.
Proc.
TASK ELEMENT 9 STANDARD Grade Step 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:
Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM: RO SYS A Proc.
Step TASK ELEMENT 11 STANDARD Grade Notify the Control Room Supervisor that na emergency boration is in progress CRS notified su END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 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 TITLE ET DELAY LOCATION RAMP VALUE RD16 Control rod stuck PIDRD02 5 (stuck)
(select any 4 full length control rods)
ED04B Loss of Bus I D PIDEDOG True Trip the Reactor Carry out EOP-1 .O Immediate Actions.
PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
JPM: RO SYS A (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The Reactor has tripped and four full length Control Rods are not fully inserted.
Bus 1D has a fault and is de-energized.
0 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 .
0 This JPM is time critical. (Time limit will not be provided.)
0 Time will start upon the completion of communication for the Initiating Cue.
This JPM is Time Critical.
PALISADESNUCLEAR PLANT Page 9 of 9 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS B TITLE: SHIFT OPERATING CCW PUMPS CANDIDATE:
EXAM1NER:
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. Third CCW pump must be manually started to maintain CCW.
Facility JPM #: PL-OPS-CCW-001J K/A: 008A2.01 Importance: RO: 3.3 SRO: 3.6 K/A Statement: Ability to predict impacts of loss of CCW pump and correct, control, or mitigate the consequences.
Task Standard: P-52A or P-52B running.
Preferred Evaluation Location: Simulator X In Plant Preferred Evaluation Method: Perform X - Simulate
References:
ONP-6.2, Loss of Component Cooling SOP-16, Component Cooling Water System Validation Time: -1 5- minutes Time Critical: NO 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 ROlSRO-I SYS B ToolslEquipmentlProcedures Needed:
SOP-I 6, Component Cooling Water System Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Plant is at full power.
0 Both CCW Heat Exchangers are in operation.
0 CCW Pump P-52A is in service 0 CCW Pumps P-52B and P-52C are in STANDBY.
INITlATlNG 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 ProcStep TASK ELEMENT 1 I STANDARD Grade Obtains correct procedure. I Locates and refers to SOP-16, Section 7.3.6. I s u Comment:
EVALUATOR CUE: Provide candidate a.working copy of SOP-76, section 7.3.6.
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 Comment:
EVALUATOR CUE: A 0 reports MV-CC927 and MV-CC945 locked OPEN.
I Proc.step TASK ELEMENT 3 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:
Proc.Step TASK ELEMENT 4 I STANDARD Grade Verify both CCW Heat Exchangers in operation.
I Both CCW Heat Exchangers in operation.
I Isu 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 Pr0c.Step TASK ELEMENT 5 IF the pump being started is in standby, I STANDARD Grade t
7.3.6.d P-52C Handswitch taken to TRIP and amber THEN REMOVE the pump from standby by STBY light extinguishes.
placing Control Switch to TRIP.
Comment:
~
Proc.Step TASK ELEMENT 6 I STANDARD P-52C CCW pump running. RED light above Grade 7m3.6me START selected CCW Pump.
handswitch ON, GREEN light OFF.
Comment:
ProcStep TASK ELEMENT 7 I STANDARD Grade 7.3.6.f IF handswitch on breaker was used, THEN PLACE Control Room handswitch Operator determines this step to be NIA since to "after close" to enable pump trip alarm pump was started from Control Room.
scheme.
Proc.Step TASK ELEMENT 8 STANDARD Grade P-52A has been stopped using handswitch.
7'3'6'g STOP selected CCW Pump.
RED light OFF, GREEN light ON.
su EVALUATOR NOTE: P-52C will trip 5 seconds after P-52A is secured. P-52B will not auto start on low pressure.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM RO/SRO-I SYS B Proc.Step TASK ELEMENT 9 STANDARD Grade I I Refers to ARP-7, window 67 and notifies CRS of P-52C trip and the need to CRS notified.
reference ONP-6.2. su Comment:
EVALUATOR CUE: If 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-52B 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.
ProcStep ONP-6.2 TASK ELEMENT I O I- STANDARD
- Checks CCW Surge Tank level to I
Grade IF less than 10 minutes has elapsed since ensure adequate inventory.
4.1ma 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.
Comment:
- = Not part of Critical Step Proc.Step TASK ELEMENT 11 I STANDARD Grade 7.3.6.h,i 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 linht ON.
I Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO/SRO-I SYS B ProeStep TASK ELEMENT I 2 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 E454B 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 Secure any running CCW pumps so that ONLY 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 1.
0 Insert Event Trigger 1 ZLOl P(46) = P-52A GREEN light 0 Insert CC13B (P-526 fail to start) to ACTIVE PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The Plant is at full power.
0 Both CCW Heat Exchangers are in operation.
CCW Pump P-52A is in service 0 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.
0 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
~
I NRC REGION 111 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-VSRO-USYS 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 KIA: 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
JPM: RO/SRO-I/SRO-U SYS C Tools/Equ ipment/Procedures Needed:
SOP-7, "Main Steam System" Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The reactor is critical with power at the POAH. MSlV 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 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 Proc. step TASK ELEMENT 1 STANDARD Grade I --- Obtains correct procedure Candidate locates SOP-7, section 7.2.2 su Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-7, section 7.2.2.
Proc. Step TASK ELEMENT 2 I STANDARD Grade Candidate contacts Auxiliary Operator to latch 7.2.2.c 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.
Roc. Step TASK ELEMENT 3 I STANDARD Grade IF MSlVs opened after performance of Step 7.2.2c, THEN GO TO Step 7.2.2q. I Candidate determines that CV-0510, 'A' S/G MSIV, did not open. Proceeds to step 7.2.2.e Isu Comment:
EVALUATOR CUE: Role play as CRS and direct candidate to proceed to step 7.2.2.e, if asked.
CRBPlCAL STEP PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS C TASK ELEMENT 4 STANDARD Candidate performs the following:
- PLACESPIC-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.
performing the following: - Has A 0 Close MV-CA390, Turbine Bypass CV-0511 AIS 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 PlDMSO3 to close air supply to CV-0517, then notify as A 0 that air supply is closed and accumulator is bled down r
Proc. Step TASK ELEMENT 5 I STANDARD Grade PERFORM the following notificationsof Candidate informs CRS to notify Chemistry and impending Steam Dump operation: to refer to ADMIN 4.00.
Proc. Step TASK ELEMENT 6 I STANDARD Candidate directs Auxiliary Operator to close the following valves in the ADV control cabinet:
CLOSE three of the four Steam Dump Air 4
g Supplies for the MSlV to be opened, listed - MV-CA779 below: - MV-CA780
- MV-CA781 OR MV-CA782 Comment:
EVALUATOR NOTE: LCO 3.7.4.A is applicable. If candidate asks, notify them that the CRS will take care of this.
SIM OPERATOR: Use MS78, MS79, MS20 (or MS27) on PID MSO7 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 7 I STANDARD Grade PLACE HIC-O780A, Steam Generator Candidate:
E-50B Steam Dump to MANUAL.
- Places HIC-0780A in Manual su OPERATE HIC-0780A toward 100%
OPEN position to equalize DP across - Operates manual output lever to open ADV MSIV. until MSlV 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 8 I STANDARD Grade j
WHEN MSlV opens, THEN PLACE HIC-0780A to CLOSE position.
Candidate Operates manual output lever to close ADV.
su I Proc. Step TASK ELEMENT 9 I STANDARD Grade Candidate has A 0 open:
OPEN Steam Dump Air Supplies closed in - MV-CA779 Step 7.2.2g above.
su
- MV-CA780
- 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: RO/SRO-I/SRO-U SYS C Proc. step TASK ELEMENT I O STANDARD Grade I IsuI IF both MSlVs did NOT open, THEN Candidate determines this step is N/A because REPEAT Steps 7.2.29 through 7.2.2k for both MSIVs are now open.
affected MSIV. I Comment:
Proc. Step TASK ELEMENT 11 I Candidate has AO:
STANDARD Grade CLOSE CV-0511 accumulator drain valve.
m,n OPEN MV-CA390, Turbine Bypass - CLOSE CV-0511 accumulator drain valve CV-0511 AIS Iso~. - OPEN MV-CA390, Turbine Bypass CV-0511 AIS IsoI.
Proc. Step TASK ELEMENT 'I2 I STANDARD Grade RETURN to Or the As Candidate places HIC-0780A and CV-0511 in FOUND position.
O9 AUTO by depressing the 'A' button on their su RETURN pic-051 to Or the As controllers and verifying the 'A' button lights.
FOUND position.
EVALUATOR NOTE: If asked, inform candidate that PIC-057 7 and HIC-078OA should be placed back in AUTO.
PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS C Proc. Step TASK ELEMENT 13 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' MS'V cv-0501 Bypass (MZ-3) associated Green light is ON and Red light is su MO-0510, MSlV CV-0510 Bypass (MZ-2) OFF.
Comment:
Proc. Step TASK ELEMENT 14 STANDARD Grade I --- I Comment:
Candidate informs the CRS that the MSlVs are open and the MSlV bypasses are closed. I CRS informed.
IsuI END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS C SIMULATOR OPERATOR INSTRUCTIONS IC-12 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]
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:
The reactor is critical with power at the POAH. MSlV 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 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: ROlSRO-I SYS D TITLE: ALTERNATE PRESSURIZER LEVEL CONTROLLERS CANDIDATE:
EXAM1NER:
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 KIA: 01 1A4.01 Importance: RO: 3.5 SRO: 3.2 KIA Statement: Ability to manually operate and/or 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 16 AUGUST 2010
Tools/Equipment/Procedures Needed: SOP-IA, "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-IA, section 7.2.1 .f., with the selected Pressurizer Level Controller in CASCADE.
PALISADES NUCLEAR PLANT Page 3 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 1 I STANDARD Grade I --- I Obtains correct procedure.
I Candidate locates SOP-1A, Primary Coolant System. I I Comment:
I EVALUATOR CUE: Provide candidate a working copy of SOP-IA section 7.2.l.f.
Proc.Step TASK ELEMENT 2 STANDARD Grade If alternating.. ., then PLACE Charging P-55B Control Select Switch to MANUAL.
f Pumps Control Select Switches for P-55B Charging Pump (43-1206ES) and P-55C P-55C Control Select Switch to MANUAL.
su Charging Pump (43-1105/SS) to MANUAL.
Comment:
Proc.Step TASK ELEMENT 3 VERIFY controller to be selected in I STANDARD Grade f2 MANUAL.
Verifies LIC-0101A is in MANUAL. su Comment:
ProcStep f.3 Comment:
1 TASK ELEMENT 4 Using the manual operating lever, ADJUST the output signal of the controller to be selected to match the output signal of the currently selected controller or to desired output.
STANDARD Adjusts output signal on LIC-0101A to match output signal on LIC-0101B for bumpless transfer.
I Grade su I CRITICAL STEP - only ifoutputs were not matched PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 5 PLACE selector switch I/LRC-0101 to I STANDARD Places Selector Switch 1ILRC-0101 to Grade f.4 position for controller to be selected. Channel A.
su ProcStep TASK ELEMENT 6 I STANDARD Grade IF alternating controllers due to a malfunction of the previously selected Operator recognizes that this step does not fS 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-1A ,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 7.
If Operator NIAs step 6 of SOP-1A section 7.2.l.f, go to Task Element I O .
Proc.Step TASK ELEMENT ?
I IF the desired mode of operation is AUTO, II STANDARD Grade THEN PLACE the selected controller in Charging and Letdown checked as being AUTO as follows:
fm6.(a)
(a) VERIFY Charging and Letdown in appropriate (one Charging Pump and one su Letdown Orifice in service).
operation as appropriate.
Comment:
PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proc.Step TASK ELEMENT 8 STANDARD Grade IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows: Acontroller raisehower pushbuttons adjusted to match controller setpoint (blue pointer) to Pressurizer level setpoint (red pointer). (blue su pointer moved to match red pointer).
match indicated Pressurizer level (red pointer).
Comment:
CRITICAL STEP only if pointers were not matched TASK ELEMENT 9 STANDARD IF the desired mode of operation is AUTO, Depresses the A pushbutton on LIC-0101A to 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 13.
If Operator decides to swap back to the B Level Controller using SOP-IA, section 7.2.1 .f, go to Task Element 14.
Either way to swap back to B Level Controller is acceptable.
CRITICAL STEP (if Step F.? is NOT chosen}
PALISADES NUCLEAR PLANT Page 6 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D TASK ELEMENT 10 STANDARD IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
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 IO).
Comment:
TASK ELEMENT I 1 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 I O , "TAVE (OF) Pressurizer Level Program."
Comment:
CRITIQIL STEP only if pointers were not rn@tchssi PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proc.Step TASK ELEMENT 12 I STANDARD I
Grade IF the desired mode of operation is Depresses the A pushbutton on LIC-0101A to CASCADE, THEN PLACE the selected place it in AUTO and notes:
controller in CASCADE as follows:
fm7() A AUTO light DOES NOT light su (c) DEPRESS the A pushbutton on the 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 B Level Controller two ways.
If Operator places selector switch 1/LRC-0101to the B position, go to Task Element 13.
If Operator decides to swap back to the ByLevel Controller using SOP-IA, section 7.2.l.f go to Task Element 14.
Either way to swap back to B Level Controller is acceptable.
Proc.Step TASK ELEMENT 13 I STANDARD Grade Place selector switch l/LRC-0101 to Dosition for controller to be selected. I Pressurizer Level Control Selector Switch I/LRC-0101 placed to the B position.
Comment:
EVALUATOR CUE: If CRS notified that B Level Controller is in service, CRS acknowledges.
NOTES: B Level Controller in service in already in CASCADE mode.
If Operator performed Task Element 13, go to Task Element 26.
I PALISADES NUCLEAR PLANT Page 8 of 16 AUGUST 2010
I JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 14 I STANDARD Grade If alternating..., then PLACE Charging f Pumps Control Select Switches for p-55B Recognizes that this step does not apply. su Charging Pump (43-1206ES) and P-55C Charging Pump (43-1105/SS) to MANUAL.
ProcStep TASK ELEMENT 15 I STANDARD Grade I Depresses M pushbutton on LIC-0101B to I I II II s u 1I place in MANUAL and notes:
VERIFY controller to be selected in fm2 MANUAL. M MANUAL light ON I C CASCADE light OFF Comment:
Proc.Step TASK ELEMENT 16 I STANDARD Grade Using the manual lever, ADJUST the output Adjusts the slide bar to on the B Pressurizer signal of the controller to be selected to Level Controller being swapped to, matching f3 match the output signal of the currently its output signal to the in-service controllers selected controller. output signal.
I CRITICAL STEP - snly if outputs were not matched Proc.Step TASK ELEMENT 17 I STANDARD Grade PLACE selector switch 1/LRC-0101 to Pressurizer Level Control Selector Switch f4 position for controller to be selected. I/LRC-0101 placed to the B position.
su PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proc.Step TASK ELEMENT 18 STANDARD Grade I
IF alternating controllers due to a Operator recognizes that this step does not malfunction of the previously selected apply. Operator MAY reposition Heater Control S U fS channel, THEN PLACE the Pressurizer Channel Selector Switch to Channel B.
Heater Control Channel Selector Switch.. .
Comment:
EVALUATOR CUES:
1 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-1A , 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 19.
If Operator NIAs step 6 of SOP-1A section 7.2.1 .f, go to Task Element 22.
I Proc.Step TASK ELEMENT I 9 I IF the desired mode of oDeration is AUTO,.
II STANDARD Grade THEN PLACE the selected controller in Charging and Letdown checked as being AUTO as follows: su appropriate (one Charging Pump and one (a) VERIFY Charging and Letdown in Letdown Orifice in service).
operation as appropriate.
Comment:
PALISADES NUCLEAR PLANT Page 10 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D TASK ELEMENT 20 STANDARD Grade IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows: B controller raiselower 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 pointer). I Comment:
Proc.Step TASK ELEMENT 21 IF the desired mode of operation is AUTO, I STANDARD Grade Depresses the on LIc-olol to THEN PLACE the selected controller in place it in AUTO and notes:
AUTO as follows: su f.6.(c)
A AUTO light ON (c) DEPRESS the A pushbutton on M MANUAL light OFF selected controller.
Comment:
PALISADES NUCLEAR PLANT Page 11 of 16 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:
f.7 (a) TYT-0200 TAVE signal verified. su (a) VERIFY expected TAVE signal available from selected TAVE/TREF controller (use TYT-0100, TYT-0200, or TI-01 10).
Comment:
TASK ELEMENT 23 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 pointer) to the Pressurizer level setpoint pointer moved to match red pointer) determined by present TAVE. Refer to Attachment 10, TAVE (OF) Pressurizer Level Program.
Comment:
NOTE: Pressurizer level setpoint determined by present Tave. Operator may refer to SOP-I A attachment IO, Tave Pressurizer Level Program.
PALISADES NUCLEAR PLANT Page 12 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 24 I STANDARD Grade IF the desired mode of operation is CASCADE, THEN PLACE the selected Depresses the A pushbutton on LIC-01016to 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:
ProcStep TASK ELEMENT 25 IF the desired mode of operation is Depresses the C pushbutton pushed on CASCADE, THEN PLACE the selected LIC-01016 to place it in CASCADE and notes:
fa7.(d) controller in CASCADE as follows:
A AUTO light OFF su (d) DEPRESS the C pushbutton on the selected controller. C CASCADE light ON Comment:
ProcStep TASK ELEMENT 26 IF Charging Pumps P-55B and P-55C were I STANDARD Grade placed in MANUAL, THEN RETURN P-55B Control Select Switch to AUTO.
f.8 Charging Pumps Control Select Switches to su p-55c Control Select Switch to AUTO.
AUTO.
Comment:
PALISADES NUCLEAR PLANT Page 13 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proe.Stap TASK ELEMENT 27 I STANDARD Grade PLACE the unselected controller in MANUAL, with a 50% output signal. I Operator recognizes A Level Controller is in MANUAL, places the output signal at 50%. I 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.
ProeStep TASK ELEMENT 28 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 14 of 16 AUGUST 2010
JPM: RO/SRO-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 (Achannel AUTO button in) to OFF OVRD for LIC-0101A-MAN (A channel MANUAL button in) to ON PALISADES NUCLEAR PLANT Page 15 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D
~~
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 Its Friday Day-Shift and per the Plant Daily Schedule, Pressurizer Level Controllers need to be alternated.
INITlATlNG 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 16 of 16 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS E TITLE: VENT NON-CONDENSIBLE GASES FROM THE REACTOR VESSEL HEAD CANDIDATE:
EXAMINER:
JPM RO/SRO-I SYS E JOB PERFORMANCE MEASURE DATA PAGE Task: Vent Non-Condensible Gases from the Reactor Vessel Head Alternate Path: NO.
Facility JPM #: PL-OPS-EOP-039J WA: 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 Vesse 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/Equ ipment/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. There are indications of non-condensible gases in the Reactor vessel head. The following Containment monitoring instruments are in service:
0 One (1) Hydrogen Monitor INITIATING CUES:
You have been directed to vent the non-condensible 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
JPM RO/SRO-I SYS E Proc.Step TASK ELEMENT 1 I STANDARD Grade
--- I Obtains correct procedure.
I Refers to EOP Supplement 26, Section 3.0. I su Comment:
EVALUATOR CUE: Provide candidate a working copy of EOP Supplement 26 Section 3.0.
Proc.Step TASK ELEMENT 2 I STANDARD Grade 3.1 .a I Ensure at least one Hydrogen Monitor in oDeration. I Provided in Conditions.
I su Comment:
EVALUATOR CUE: If candidate attempts to verify status using SOP-38, provide cue that this has already been performed.
Proc.Step TASK ELEMENT 3 STANDARD Grade 3-1.c I - 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 4 STANDARD 3.1 .d Vent the Reactor Vessel Head by - Obtains Key 105.
opening ONE of the following valves for 5-10 minutes:
- Places HS-1067 to RESET and then to OPEN.
0 PRV-1067
- Verifies that PRV-1067 has opened (RED light is ON and GREEN light is OFF)*
OR su I- Obtains Key 106.
I-0 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 Proc.Step TASK ELEMENT 5 I STANDARD Grade After 5-10 minutes, secure Reactor Vessel Head venting. I Vents Reactor Vessel Head for 5-10 minutes. Isu Comment:
EVALUATOR CUE: Five minutes have elapsed.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO/SRO-I SYS E
- 3.1 .e TASK ELEMENT 6 Secures Reactor Vessel Head venting STANDARD
- Using Key 105 places HS-1067 to by closing the appropriate valve which CLOSE.
was opened:
- Verifies that PRV-1067 has closed PRV-1067 (RED light is OFF and GREEN light is ON)*
OR su
- Using Key 106 places HS-1068 to CLOSE.
0 PRV-1068 - Verifies that PRV-1068 has closed (RED light is OFF and GREEN light is ON)*
Comment:
- - not critical Ensure closed PRV-1072, Vent Path to Quench Tank. Verifies that PRV-1072 has closed light is OFF and GREEN light is 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-I7 0 INSERT MF RCOI (Large Break LOCA)
Trip all PCPs.
0 Place Left Train Hydrogen Monitor in-service per SOP-38.
0 Ensures Reactor Head Vent Header pressure (on Panel C-I 1A rear) has bled off.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITlAL CONDITIONS:
A large break LOCA has occurred. There are indications of non-condensible gases in the Reactor vessel head. The following Containment monitoring instruments are in service:
0 One (1) Hydrogen Monitor INITIATING CUES:
You have been directed to vent the non-condensible 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-USYS F TITLE: PLACE A CONTAINMENT RADIATION MONITOR IN SERVICE CANDI DATE:
EXAM1NER:
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 #: PL-OPS-RMS-OO4J 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: 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/SRO-U SYS F 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:
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-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 AUGUST 2010
JPM: ROlSRO-VSRO-U SYS F Proc. Step TASK ELEMENT 1 STANDARD Grade Obtains correct procedure SOP-39, section 7.4.2 is located su Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-39, section 7.4.2.
Proc. Step TASK ELEMENT 2 REFER TO Attachment 3, Checklist CL I STANDARD Candidate determines that this step is N/A per Grade 7'4m2'a 39, "Area Monitors System Checklist." initial conditions.
Proc. Step TASK ELEMENT 3 I STANDARD Grade I 7.4.2.b I I
CHECK operate light illuminated.
I I
Operator recognizes that the OPERATE light is not illuminated.
Comment:
Proc Step TASK ELEMENT 4 I STANDARD Grade IF operate light NOT illuminated, THEN Operator refers to Attachment 2 and locates 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.
I I PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS F I
I Roc. step TASK ELEMENT 5 STANDARD Grade I 4.1.a I PRESS AND HOLD operate light. I Operate light pressed and held Isu I Comment:
Proc. Step TASK ELEMENT 6 I STANDARD Grade Operator verifies Orange and Red (Trip 1 and 4.1.b CHECK other three monitors not tripped. Trip 2) lights not illuminated for RIA-1806, 1807 S U and 1808.
Comment:
Proc, Step TASK ELEMENT 7 I STANDARD Grade PLACE Selector Switch momentarily to CHECK position AND RELEASE. I RIA-I805 selector switch placed in CHECK position and released.
Comment:
I Proc. Step TASK ELEMENT 8 I STANDARD Grade I 4.1 .d I RELEASE operate light. I Operate light is released Comment:
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 9 STANDARD Operator resets:
- AMBER Trip 1 4.1.e RESET all alarms.
- RED Trip 2 su by depressing associated indicating light.
Comment:
1 Proc. Step I
TASK ELEMENT 10 I STANDARD Grade IF 'perate light still not illuminated, 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 11 STANDARD Grade RESET all alarms. Operator verifies all alarms reset. su Comment:
Proc. Step TASK ELEMENT 12 IF operate light still NOT illuminated, I STANDARD Grade i THEN DECLARE the associated monitor Operator determines this step is not applicable 7.4.2.e inoperable. Refer to Attachment 2, because Operate light is illuminated.
"System Malfunctions and Troubleshooting.
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 13 STANDARD Grade Operator informs Control Room Supervisor nla that Containment Radiation Monitor CRS Notified su RIA-I 805 has been placed in service.
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
~ ~~
JPM: RO/SRO-I/SRO-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 PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
JPM: ROlSRO-I/SRO-U SYS F (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is operating at full power.
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 9 of 9 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS G TITLE: DEPRESSURIZE PCS WHILE ON SHUTDOWN COOLING CANDIDATE:
EXAMINER:
JPM: RO/SRO-I/SRO-U SYS G JOB PERFORMANCE MEASURE Task: Depressurize PCS While on Shutdown Cooling Alternate Path: YES - voiding occurs in reactor head during depressurization requiring operator to repressurize the PCS to eliminate voids.
Facility JPM #: NEW WA: 01OAl.07 Importance: RO: 3.7 SRO: 3.7 WA Statement: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: RCS pressure.
Task Standard: Reactor Vessel Head void removed.
Preferred Evaluation Location: Simulator -X- In Plant Preferred Evaluation Method: Perform X - Simulate
References:
SOP-I B, Primary Coolant System - Cooldown 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 8 AUGUST 2010
I I Tools/Equipment/Procedures Needed:
~
SOP-I B, Primary Coolant System - Cooldown, section 7.1.2 I 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 has just cooled down for a forced outage following a loss of offsite power and a natural circulation cooldown. Offsite power is in the process of being restored.
0 P-67B is the LPSl Pump in service.
0 Chemistry has sampled the CVCS for boron within the last 30 minutes.
INITIATING CUES:
The Control Room Supervisor directs you to depressurize the PCS while on Shutdown Cooling per SOP-I B, Section 7.1.2 using PIC-0202, Letdown Pressure Controller.
Secure Charging Pump P-55A when PCS pressure lowers to approximately 100 psia.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS G Proc. Step TASK ELEMENT 1 STANDARD Grade Locates correct procedure. SOP-16, Section 7.1.2 obtained. su Comment:
EVALUATOR CUE: Provide candidate a Working Copy of SOP-7B, Section 7.7.2 Proc.Step TASK ELEMENT 2 I STANDARD Grade I I NOTIFY Chemistry to sample the CVCS I I 7'1'2.a II pump so that VCT boron concentration is known for startup.
II for boron prior to securing the last charging Given in the Conditions I
su Comment:
TASK ELEMENT 3 STANDARD WHEN depressurizing in Step 7.1.2c, THEN MONITOR for void formation.
Void formation is indicated by one or more of the following: Monitors the following during the next step:
- 1. Indicated Charging and Letdown flows Charging and Letdown flows do not correspond. Operable PCS temperatures
- 2. Any operable PCS temperature RVLMS indication on Panel C-13 indication is less than 25°F subcooled.
- 3. RVLMS indicates voiding in the Reactor Vessel.
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS G
- TASK ELEMENT 4 STANDARD WHEN the following conditions are met:
at least 5 minutes have elapsed since stopping all PCPs all of shutdown cooling inventory AND the PCS will be at least 25°F subcooled when depressurized (shutdown cooling return Raises output on PIC-0202, Letdown Pressure 7.1.2.c temperature from PCS less than or equal Controller (slide bar to RIGHT = opens su to 185°F) associated valve).
THEN REDUCE PCS pressure by performing the following as directed by the CRS:
- 1. REDUCE PCS pressure using PIC-0202, Letdown Pressure Controller.
Comment:
TASK ELEMENT 5 STANDARD Determines that a void exists via RVLMS indications.
IF void formation is indicated, THEN Raises PCS pressure to band directed by CRS 7.1.2.d RAISE PCS pressure as directed by CRS. by: su Adjusts PIC-0202 (slide bar initially to LEFT to close associated valve)
Comment:
EVALUATOR CUE: If asked to provide a PCS pressure band: respond to raise PCS pressure until voiding is removed, but not greater than 250 psia.
NOTES: Operator can detect voids and eliminate voids two ways.
If Operator detects voids and restores pressure in Task Element 5, then go to Task Element 8.
If Operator does not detect voiding in Task Element 5, then go to Task Element 6.
Operator must complete either Task Element 5 7 successfully.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS G Proc. Step TASK ELEMENT 6 I STANDARD Grade REDUCE PCS pressure by performing the following as directed by the CRS: Stops Charging Pump P-55A when PCS 7.1.2.c pressure is below 100 psia.
su
- 2. STOP the remaining Charging Pump.
Comment:
STANDARD Determines that a void exists via RVLMS indications.
Raises PCS pressure to band directed by CRS IF void formation is indicated, THEN by: su Starts one Charging Pump and Adjusts PIC-0202 (slide bar initially to LEFT to close associated valve)
Comment:
EVALUATOR CUE: If asked to provide a PCS pressure band: respond to raise PCS pressure until voiding is removed, but not greater than 250 psia.
Proc. step TASK ELEMENT 8 STANDARD Grade NOTIFY the CRS that PCS voids are no na longer evident.
CRS NOTIFIED. su Comment:
NOTE: JPM may be ended when Candidate informs you that voids are no longer evident and Candidate has restored pressure to band directed by CRS.
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS G SIMULATOR OPERATOR INSTRUCTIONS 0 IC-2, Ready to Start PCPs 0 Open the following Swithyard Breakers:
31H9,29.H9,27H9,25H9,29F7,27R8.
0 Create the following triggers and overrides:
- 1. Create TRIGGER 1:
Event: RCPPZ.LT.200.0 [this is PCS pressure getting down to less than 200 psia]
- 2. Tie the following to TRIGGER 1:
LI-0101B-GI to OFF LI-0101B-R1 to ON LI-01OIA-R-1 to ON LI-0101A-GI to OFF
- 3. Create TRIGGERS 2, 3,4, and 5:
Event: et-array( I).and.RCPPZ.gt.202.0 [this is Trigger #I plus PCS pressure being restored to above 202 psia]
Action for Trigger 2: ior LI-0101B-GI Action for Trigger 3: ior LI-0101B-R1 Action for Trigger 4: ior LI-0101A-R1 Action for Trigger 5: ior LI-0101A-GI PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS G (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant has just cooled down for a forced outage following a loss of offsite power and a natural circulation cooldown. Offsite power is in the process of being restored.
P-67B is the LPSl Pump in service.
Chemistry has sampled the CVCS for boron within the last 30 minutes.
INITIATING CUES:
The Control Room Supervisor directs you to depressurize the PCS while on Shutdown Cooling per SOP-I B, Section 7.1.2 using PIC-0202, Letdown Pressure Controller.
Secure Charging Pump P-55A when PCS pressure lowers to approximately 100 psia.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO=lSYS H TITLE: TEMPORARILY SECURE SHUTDOWN COOLING FLOW CANDIDATE:
EXAMI NER:
~
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 WA Statement: Ability to manually operate and/or 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
ToolslEquipmentlProcedures 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:
A 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 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."
0 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 3 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H PALISADES NUCLEAR PLANT Page 4 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 1 STANDARD Grade Locates correct procedure SOP-3, Section 7.3.6 LOCATED su Comment:
I EVALUATOR CUE: Provide candidate a working copy of SOP-3, Section 7.3.6 I Proc. Step TASK I%EMENT 2 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.
- 3. PCS heatup rate and allowable outage 7m3.6ma Given in the Initial Conditions time determined. Refer to Section 7.3.7.
- 4. Requirementsof General Operating Procedure GOP-14, "Shutdown Cooling Operations," are met.
- 5. Operations Superintendent approval to secure Shutdown Cooling flow has been obtained.
Comment:
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.
7.3m6'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 5 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H P w . Step TASK ELEMENT 4 STANDARD Grade PERFORM Section 7.3.4 to reduce total 7.3.6.c Shutdown Cooling flow to approximately Branches to section 7.3.4 of SOP-3 su 300 to 500 gpm.
Comment:
Evaluator provides a Working Copy of SOP-3, Section 7.3.4 EVALUATOR CUE: Another Operator will control PCS pressure during this evolution.
TASK ELEMENT 5 STANDARD 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 (PO-2 performance given in initial conditions) monitored. Refer to PO-2, "PCS HeatuplCooldown Operations."
Comment:
IF PCS level is greater than 643'-0" AND any CRDM tool access flanges are Determines that this step does not apply.
7.3.4.b removed, THEN ENSURE personnel are su clear of CRDM tool access flanges and (PCS level is given in initial conditions)
Reactor Cavity.
Comment:
Proc. Step TASK ELEMENT 7 I STANDARD Grade 7.3.4.c DETERMINE desired total Shutdown Determines 300-500 gpm applies (from su Cooling flow. previous step 7.3.6.c).
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 8 I STANDARD Grade IF Shutdown Cooling flow is to be throttled Determines that sub-steps 1,2, and 3 do not su 7'3'4'd below 2810 gpm, ... apply.
Comment:
EVALUATOR CUE: CRS directs that sub-step 3 is not applicable for this evolution.
TASK ELEMENT 9 STANDARD IF Shutdown Cooling flow is to be throttled below 2810 gpm,. ..
- 4. IF PCS recirculation flow rate is less than the minimum required by Notifies CRS of need to Caution Tag 7.3.4.d Technical Specifications LCO 3.4.7, MV-CVC2 162.
LCO 3.4.8, LCO 3.9.4, or LCO 3.9.5, THEN CLOSE AND CAUTION TAG MV-CVC2162, Primary Makeup Water Supply Stop within one hour.
Comment:
EVALUATOR CUE IF informed as CRS of need to hang Caution Tag on MV-CVC2162:
acknowledge and inform Operator that this was already completed by another operator during GOP-14.
TASK ELEMENT I O 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 Comment:
EVALUATOR CUE: IF informed as CRS of need to maintain GOP-14 requirements:
acknowledge.
PALISADES NUCLEAR PLANT Page 7 of 12 AUGUST 2010
JPM: ROlSRO-I SYS H Proc. Step TASK ELEMENT 11 STANDARD Grade I I7.3.4.e DETERMINE required status of.. .
Determines that maximum of one throttled/open LPSl Injection Valve applies. (per initiating cue this will be MO-3014) lsul I Comment:
Proc. Step TASK ELEMENT 12 ADJUST Shutdown Cooling flow as I STANDARD Grade 7.3.4.f follows: Checks FIC-0306 is in MANUAL. su
- 1. ENSURE FIC-0306 is in MANUAL.
TASK ELEMENT 13 STANDARD Omde 7.3.4.f Comment:
ADJUST Shutdown Cooling flow as follows:
- 2. SLOWLY OPERATE LPSl injection Valves to establish status determined in SteP 7.3.4e.
I SLOWLY operates each of the four LPSl Injection Valves (one at a time) until only one (MO-3014) LPSl Injection Valve is throttled open and SDC flow is 300 to 500 gpm.
I follows: I I I 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:
PALISADES NUCLEAR PLANT Page 8 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H I
7.3.4.f follows:
- 4. If necessary:
(a) THROTTLE CV-3025, SDC I Determines this step is not applicable. su Hx Outlet to maintain desired I Comment:
TASK ELEMENT 16 STANDARD ADJUST Shutdown Cooling - flow as follows:
- 4. If necessary:
Determines this step is not applicable.
(b) THROTTLE FIC-0306 output 7.3.4.f signal to maintain desired flow su Branches back to section 7.3.6 of SOP-3 through Shutdown Cooling Heat Exchangers.
Comment:
Proc. Step TASK ELEMENT 17 STANDARD Grade 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 su
- 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.
PALISADES NUCLEAR PLANT Page 9 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H TASK ELEMENT 18 STANDARD Grade WHEN Total Shutdown Cooling flow has been reduced to approximately300 to 500 gpm, THEN PERFORM the following: HS-3025A to CLOSE with key.
7.3.6.d (Key may be removed or left in keyslot)
- 2. CLOSE CV-3055, SDC Hx Inlet.
Comment:
Proc. Step TASK ELEMENT I 9 WHEN Total Shutdown Cooling flowhas I STANDARD Grade been reduced to approximately 300 to 500 gpm, THEN PERFORM the following:
7.3.6.d P-67B STOPPED su I I 3. STOP the operating LPSl Pump.
Comment:
Proc. Step TASK ELEMENT 20 STANDARD Grade NOTIFY the CRS that Shutdown Cooling n/a has been temporarily secured per SOP-3, CRS NOTIFIED SDC temporarily secured su Section 7.3.6.
Comment:
END OF TASK PALISADES NUCLEAR 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 Keys installed in the following MOVs:
0 M0-3015 MO-3016
..MO-3189 MO-3198 MO-3190 0
.MO-3189 Ensure Caution Tags on CV-3057 and CV-3031 PALISADES NUCLEAR PLANT Page 11 of 12 AUGUST 2010
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JPM: RO/SRO-I SYS H (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A Plant is in the middle of a 45 day refueling outage.
P-67B is the LPSl Pump in service with PCS temperature approximately 108°F 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 28 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 I
I 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 7 AUGUST 2010
I 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:
The Plant is at 48% power 0 T-68B Waste Gas Decay Tank batch release is in progress 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-689, per SOP-I8A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 3 of 7 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I Proc. Step TASK ELEMENT 1 I STANDARD Grade I n/a I Obtain correct procedure. I SOP-I8A, Section 7.5, Step nn located Isu I I EVALUATOR CUE: Provide candidate a working copy of SOP-I8A, Section 7.5, step nn I 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-68AIBIC: MV-WG719 CLOSED MV-WG719, T-68A, B & C Outlet Isolation Comment:
EVALUATOR NOTE: Task Elements 2 and 3 can be performed in any order since they are bulleted substeps SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge nn.1 Header Valves T-68A/B/C: MV-WG718A CLOSED su
.MV-WG718A, T-IOIA, B & C Outlet Isolation Comment:
EVALUATOR NOTE: Task EIemenfs 2 and 3 can be performed in any order since they are bulleted substeps PALISADES NUCLEAR PLANT Page 4 of 7 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS I nn.2.a WGDT Discharge, as follows:
.PLACE in CLOSE position HS-1123, I HS-1123 in CLOSE su Waste Gas Decay Tanks Discharge, at C-40 Comment:
EVALUATOR CUE: CV-7723 is closed, the green light is lit.
Proc. step TASK ELEMENT 5 I CLOSE Discharge Control Valve CV-1123, II .
STANDARD Grade nn.2.b I
I WGDT Discharge, as follows:
.SET to zero (0) psi HIC-1123, Waste Gas Discharge To Stack I
I HIC-1123 INDICATING 0 psi su Comment:
EVALUATOR CUE: HIC-I123 indicates 0 psi I
TASK ELEMENT 6 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 CLOSED mMV-CA352, I/A Isolation/ControlTo CV-1120B. T-68B Drain Valve (Opens MV-CA352 which opens CV-1120B)
Comment:
EVALUATOR CUE: one minute has elapsed.
PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 2010
JPM: RO/SRO-IISRO-U SYS I t
Roc. Step TASK ELEMENT 7 I STANDARD Grade I n'a I NOTIFY CRS that WGDT T-68B release secured I CRS WGDT T-68B SECURED Isu Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 7 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INIT1AL CONDIT1ONS:
The Plant is at 48% power T-68B Waste Gas Decay Tank batch release is in progress It has been determined that the batch release must be secured INIT1AT1NG CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step mm.
PALISADES NUCLEAR PLANT Page 7 of 7 AUGUST 2010
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NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS J TITLE: START AFW PUMP P-8B LOCALLY USING CV-0522B CANDIDATE:
EXAMI NER:
JPM: RO/SRO-I SYS J JOB PERFORMANCE MEASURE DATA PAGE 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-01OJ WA: 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-05226, K-8 Steam Supply from E-50AI 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 PALISADES NUCLEAR PLANT Page 2 of 11 AUGUST 2010
JPM: ROlSRO-I SYS J
~
Tools/Equipment/Procedures Needed:
I EOP Supplement 19, Alternate Auxiliary Feedwater Methods, section 4, P-8B Normal Steam Supply From A S/G including page 21 of supplement 19 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 AFW flow control valves for P-8BI AFW Pump, have been verified closed.
Buses 1C and 1D are NOT energized.
0 A Steam Generator steam and feed paths to both Steam Generators are available.
0 CV-0522BI K-8 Normal Steam Supply, is closed and cannot be operated from either the Control Room or C-I50 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 Proc. Step TASK ELEMENT 1 I STANDARD I
Grade I nla I Obtains correct procedure I EOP Supplement 19, Section 4.0 located I su I 1
Comment:
EVALUATOR CUE:Provide candidate a working copy of EOP Supplement 19 Proc. Step TASK ELEMENT 2 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-0522B cannot be remotely operated v
TASK ELEMENT 3 I STANDARD Grade 4.0.2.a CLOSE the following valves:
MV-CA377, air supply to CV-0522B MV-N2/268, nitrogen supply to Simulates or describes CLOSING by turning the hmdWhee1 clockwise:
su mMV-CA377, air supply to CV-0522B CV-05228 mMV-N2/268, nitrogen supply to CV-0522B Comment:
EVALUATOR CUE: The valves are closed PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 4 MANUALLY CLOSE CV-05226, K-8 I STANDARD Grade Steam Supply From E-50A, as follows: Simulates or describes UNSCREWING coupling su 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 I 9 EVALUATOR CUE: The coupling is unscrewed from the shaft NOTE: A ladder may be used to access the coupling Proc. Step TASK ELEMENT 5 STANDARD Grade MANUALLY CLOSE CV-05226, K-8 Normal Steam Supply, as follows?
Simulates or describes TURNING handwheel 4.0.2.b.2 ' TURN ha-~dwheelc~ockwiseuntil the clockwise until manual override shaft is exposed su top of the actuator shaft is exposed sufficiently to engage the coupling Comment:
EVALUATOR CUE: The manual shaft is exposed Proc. Step TASK ELEMENT 6 I STANDARD Grade NOTE: EOP Supplement 19, page 21 has a labeled diagram of CV-05228 PALISADES NUCLEAR PLANT Page 5 of 11 AUGUST 2010
~ JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 7 I STANDARD Grade REMOVE lockwire from MV-FW356, CV-0522B Bonnet Isolation I Simulates or describes REMOVING the lockwire I
Comment:
EVALUATOR CUE: The lockwire is removed from MV-FW356, CV-0522B Bonnet isolation I I Proc. Step TASK ELEMENT 8 I STANDARD Grade OPEN MV-FW356, CV-0522B Bonnet I Simulates or describes OPENING MV-FW356 by TURNING handle 90 degrees (places it in-line with the turbine/piping).
I EVALUATOR CUE: MV-FW356, CV-05225 Bonnet isolation handle is in line with the Proc. Step TASK ELEMENT 9 I STANDARD Grade Simulates or describes checking valve closed by CLOSE CV-O522B, K-8 Normal Steam 402b6 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-05225, report that it is closed PALISADES NUCLEAR PLANT Page 6 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc, Step TASK ELEMENT 10 STANDARD Grade CHECK Turbine Driver K-8 is latched as
, follows:
ENSURE the end of resetting level 4.0.2.c.l (knife edge) is in contact with the trip Determines that Turbine Driver is NOT RESET su level (can NOT slip a sheet of paper between),. Refer to Figure 1 (Page 20)
Comment:
NOTE: EOP Supplement 19, page 20 has a labeled diagram of CV-0522B trip linkage EVALUATOR CUE: The Knife edge of resetting lever is hanging down and not in contact with the hand trip lever
NOTE: Alternate Path begins here and is covered in task elements 11 and 12-------
Proc. Step TASK ELEMENT 11 I CHECK Turbine Driver K-8 is NOT I STANDARD Grade 4.0.2.c.2.a I
I latched, THEN RELATCH as follows:
. ENSURE CLOSED CV-O522B, K-8 Normal Steam Supply Simulates or describes verifying that CV-0522B is CLOSED Comment:
EVALUATOR CUE: If asked about the position of CV-O522B,report that it is closed Proc. Step TASK ELEMENT 12 STANDARD Grade 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 Auxiliary Reset lever until the lever is in contact S U Turbine Driver K-8 using the Auxiliary with the knife edge Reset lever Comment:
EVALUATOR CUE: The knife edge of resetting lever is in contact with the hand trip lever PALISADES NUCLEAR PLANT Page 7 of 11 AUGUST 201 0
JPM: RO/SRO-I SYS J f
Proc. Step TASK ELEMENT 13 I STANDARD Grade 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 Proc. Step
. TASK ELEMENT 14 I STANDARD Grade I I Simulates or describes OPENING MV-FW688, 4.0.2.d OPEN MV-FW688, PI-0590 root valve PI-0590 root valve by TURNING the handwheel S U counter clockwise Comment:
EVALUATOR CUE: Valve is open Proc, step TASK ELEMENT 15 I STANDARD Grade 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 counter clockwise S U PI-0521A I = PI-0521B I I Comment:
EVALUATOR CUE:Steam flow noise can be heard, CV-O522B, K-8 Normal Steam Supply indicates off its full closed position, and pressure on gauge is rising.
PALISADES NUCLEAR PLANT Page 8 of 11 AUGUST 2010
JPM: ROISRO-I SYS J Proc. Step TASK ELEMENT 16 I STANDARD Grade CHECK PI-0590 OR PI-0521B reading VERIFIES PI-0590 OR PI-0521B reading 4'0'2.e between 200 and 250 psig between 200 to 250 psig su EVALUATOR CUE: PI-0590 OR PI-0521B indicates 235 psis and stable Proc, Step TASK ELEMENT 17 STANDARD Grade Notify CRS that AFW Pump, P-8B is operating I CRS NOTIFIED that AFW Pump, P-8B is operating with CV-0522B opened manually Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 AUGUST 2010
JPM: ROISRO-I SYS J SIMULATOR OPERATOR INSTRUCTIONS 0 NIA PALISADES NUCLEAR PLANT Page 10 of 11 AUGUST 2010
I JPM: RO/SRO-I SYS J (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
AFW flow control valves for P-8B, 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 11 of 11 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS K TITLE: REDUCE STATION BATTERY #LOADING I
CANDIDATE:
EXAMINER:
JPM: RO/SRO-I/SRO-U SYS K JOB PERFORMANCE MEASURE DATA PAGE Task: Reduce Station Battery Loading Alternate Path: NO Facility JPM #: PL-OPS-EOP-021J WA: 063A1.01 Importance: RO: 2.5 SRO: 3.3 WA Statement: Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity I as it is affected by discharge rate.
Task Standard: Station Battery #I loading reduced to < I 57 amps.
Preferred Evaluation Location: Simulator In Plant -X-Preferred Evaluation Method: Perform Simulate -X-
References:
E0P-3.0, "Station Blackout Recovery" EOP Supplement 7, "Battery # I Load Stripping" Validation Time: -I O - minutes Time Critical: NO Candidate:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature I PALISADES NUCLEAR PLANT Page 2 of 9 AUGUST 2010
Tools/Equipment/Procedures Needed:
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EOP Supplement 7, Battery #I Load Stripping I 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:
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 not start.
INITIATING CUES:
During performance of EOP-3.0, Station Blackout Recovery, Step 19, the CRS directs you to ensure Station Battery #I discharge is within limits, per EOP Supplement 7.
PALISADES NUCLEAR PLANT Page 3 of 9 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS K Proc. Step TASK ELEMENT 1 I "
STANDARD Grade nla I Locate correct procedure EOP Supplement 7 is located I su Comment:
EVALUATOR CUE:Provide candidate a working copy of EOP Supplement 7 TASK ELEMIZNT 2 STANDARD MONITOR Station Battery No 1 loading using the dual range ammeter EAI-45 located at Panel D-13:
- a. For values greater than 200 amps, Operator reviews instructions for reading Station 1.0.1 use the outer scale on EAI-45 Battery No. 1 Ammeter.
su
- b. For values less than 200 amps, use the Lower Scale Reading push button and the inner scale on Comment:
EAI-45 TASK ELEMENT 3 STANDARD Operator RECORDS the following:
- 35 minutes ago from present time RECORD the following: - Present time
- a. Time of event initiation:
Operator determines bus loading for Station 1.0.2 b. Present Time: Battery No. 1 by: su
- c. Station Battery No 1 discharge - depressing Lower Scale Reading push current: EAI-45: button Amps
- reading inner scale of ammeter.
- Records 190 amps Comment:
EVALUATOR CUE:Use pointer and place on Station Battery No. I ammeter, AI-45, to indicate I90 AMPS out on inner scale.
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JPM: RO/SRO-I/SRO-U SYS K TASK ELEMENT 4 STANDARD Lc " '
DETERMINE the maximum acceptable Station Battery No 1 discharge current for time since event initiation:
Time Since Event AccePtable Operator determines the following maximum Current acceptable Station Battery No. 1 discharge 1.0.3 current is I157 amps 0 to 1 min. I 8 3 2 amps 1 to 11 min. S401 amps 11 to 30 min. 5 222 amps
> 30 min. I157 amps Comment:
TASK ELEMENT 5 IF Station Battery No 1 discharge current STANDARD 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 190 amps is not acceptable following steps, as necessary, to maintain 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 su 72-114 72-116 Panel Dl l-2 72-122 72-126 72-128 72-130 72-133 72-134 Comment:
VALUATOR CUE:lf candidates attempts to refer to drawing E-35 for valve failure modes, inform candidate that the Control Room has completed this.
VALUATOR 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 6 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 su
- 2) Station Battery No 1 discharge current: EAI-45: - Reads inner scale of ammeter amps RECORDS Battery No. 1 discharge current Comment:
EVALUATOR CUE:Use pointer and place on Station Battery No. I inner scale ammeter, AI-45, to indicate 170 AMPS out on inner scale.
TASK ELEMENT 7 STANDARD Grade IF Station Battery No 1 discharge current continues to be greater than the Operator performs the following:
- Determines that discharge current is still I I acceptable limits of Step 1.3, THEN OPEN 1'0'4.c the following breaker in Cable Spreading not acceptable su Room - Simulates OPENING breaker 72-17 on D-72-17 (D-10) 10 Comment:
EVALUATOR CUE:Provide cue that breaker indicates OFF. Battery discharge current should lower by approximately 40 amps.
Proc. 8tep TASK ELEMENT 8 STANDARD Grade 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 su button
- 2) Station Battery No 1 discharge current: EAI-45: - Reads inner scale of ammeter amps RECORDS Battery No. 1 discharge current EVALUATOR CUE:Use pointer and place on Station Battery No. 1 ammeter, AI-45, to indicate 135 AMPS out on inner scale.
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS K Proc. Step TASK ELEMENT 9 I STANDARD Grade IF Battery No discharge current 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
< 57 I amps PERFORM the following.. .
Comment:
Proc. step TASK ELEMENT 10 I STANDARD Grade nla 1 Operator informs Control Room that task is complete I Control Room informed Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS K SIMULATOR OPERATOR INSTRUCTIONS 0 N/A PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS K (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITlAL CONDITIONS:
0 All AC power is lost.
It is approximately 35 minutes after the loss of all AC power.
0 1-1 and 1-2 Diesel Generators will not 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