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 ID)
CAN D 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, 4 have been completed within 15 minutes.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
EO P-I
.O, Standard Post-Tri p Act ions SOP-2A, Chemical and Volume Control System Validation Time:
5 minutes Time Critical:
YES (1 5 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 Manu a I Bora t i o n 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.
IN ITlAL CONDITIONS:
The Reactor has tripped and four full length Control Rods are pcJ 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 201 0
JPM: RO SYS A TASK ELEMENT 3 STANDARD Roc.
S@P TASK ELEMENT I STANDARD Grade Proc.
Step t
Grade I nla I Obtains correct procedure I SOP-2A, Attachment 14 is located Att. 14 2.0a I
If Bus 1 D is energized...
Determines that this step is not applicable s u Comment:
EVALUATOR NOTE: Emergency Boration is available by gravity feed only EVALUATOR CUE: Provide candidate a working copy of SOP-2A, Attachment 14 TASK ELEMENT 2 STANDARD Grade Proc.
Step Charging flow is verified greater than 33 gpm S U I
I Att. 14, I Ensure charging flow greater than 1.0 33 gpm
~ _ _ _ _
Comment:
Comment:
TASK ELEMENT 4 STANDARD Grade Proc.
Step If Bus I C is energized, then, THEN ESTABLISH Gravity Feed PLACES handswitch for MO-2169 to open, (red light on, green light off) s u Att. 14, 2.0b.l OPEN MO-2169 and MO-2170, Boric Acid Tank Gravity Feed Isolation Valves.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 201 0
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
TASK ELEMENT 6 Proc.
Step Comment:
STANDARD Grade Att. 14, 2.0b.2 s u CLOSE CV-2155, Boric Acid Blender Outlet Control Valve CV-2155 verified CLOSED (red light off, green light on.)
TASK ELEMENT 7 STANDARD Proc.
step Grade PALISADES NUCLEAR PLANT Att. 14, 2.0b.3 Page 5 of 9 s u CLOSE MO-2087, VCT Outlet Isolation Valve PLACES handswitch for MO-2087 to CLOSE, (red light off, green light on).
AUGUST 2010
JPM: RO SYS A TASK ELEMENT 9 STANDARD Proc.
Step Proe.
TASK ELEMENT 8 STANDARD Grade step Grade Close MO-2160, SlRW Tank to Charging Pumps Isolation I MO-2160 is verified CLOSED I s u 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.
Att. 14, If YO1 is not energized, THEN I 2.0b.5 I PERFORM the following:
l s u l I Determines that this step is not applicable Comment:
Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 201 0
JPM: RO SYS A TASK ELEMENT 11 STANDARD Proc.
Step Grade na END OF TASK s u Notify the Control Room Supervisor that emergency boration is in progress CRS notified PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 201 0
JPM: RO SYS A SI M U LATOR 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)
ED04B Loss of Bus I D PIDEDOG True (select any 4 full length control rods)
Trip the Reactor Carry out EOP-1.O Immediate Actions.
PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 201 0
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 1 D 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.
PALISADES NUCLEAR 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 CAN D I DATE:
EXAM1 NER:
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-001 J 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:
mi nu tes Performance Rating: SAT UNSAT Comments:
Examiner:
Signature PALISADES NUCLEAR PLANT Page 2 of 9 Date:
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.
IN ITlATl NG 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 STANDARD I
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.
I STANDARD Proc.step TASK ELEMENT 3 I
s u 7.3.6.a Comment:
Ensure LOCKED OPEN CCW pump P-52C suction and discharge valves.
Contacts A 0 to ensure MV-CC921 and MV-CC945 locked OPEN.
EVALUATOR CUE: A 0 reports MV-CC927 and MV-CC945 locked OPEN.
Grade 7.3.6.b Contacts A 0 to cycle MV-CC558 open and closed.
CUE: A 0 reports MV-CC558 cycled open and s u Operate P-52C pump casing vent petcock to vent air from pump casing.
closed.
Comment:
Proc.Step TASK ELEMENT 4 STANDARD Grade I
I I s u I Both CCW Heat Exchangers in operation.
Verify both CCW Heat Exchangers in operation.
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 201 0
JPM RO/SRO-I SYS B Comment:
~
Pr0c.S t e p TASK ELEMENT 5 STANDARD Grade I
t 7.3.6.d P-52C Handswitch taken to TRIP and amber STBY light extinguishes.
IF the pump being started is in standby, THEN REMOVE the pump from standby by placing Control Switch to TRIP.
Proc.Step TASK ELEMENT 6 STANDARD Grade I
ProcStep TASK ELEMENT 7 STANDARD I
P-52C CCW pump running. RED light above handswitch ON, GREEN light OFF.
7m3.6me Comment:
START selected CCW Pump.
Grade 7.3.6.f IF handswitch on breaker was used, THEN PLACE Control Room handswitch to "after close" to enable pump trip alarm scheme.
Operator determines this step to be NIA since pump was started from Control Room.
Proc.Step TASK ELEMENT 8 STANDARD Grade 7'3'6'g STOP selected CCW Pump.
P-52A has been stopped using handswitch.
s u RED light OFF, GREEN light ON.
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 7.3.6.h,i Proc.Step TASK ELEMENT 9 STANDARD Grade PRESS amber STANDBY button for pump to be placed in STANDBY.
CHECK amber STANDBY button linht ON.
s u Candidate determines this step is N/A from initial conditions.
CRS notified.
I Refers to ARP-7, window 67 and notifies CRS of P-52C trip and the need to reference ONP-6.2.
I s u 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 CC W pump.
ProcStep TASK ELEMENT I O STANDARD Grade I
I ONP-6.2
- Checks CCW Surge Tank level to IF less than 10 minutes has elapsed since loss of CCW, then start available CCW pumps as appropriate (based on suction supply).
- Verifies RED Light ON, GREEN light ensure adequate inventory.
Starts P-52A (or P-52B).
s u 4.1ma OFF.
Comment:
- = Not part of Critical Step Proc.Step TASK ELEMENT 11 STANDARD Grade I
Comment:
I PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 201 0
JPM RO/SRO-I SYS B 7.3.6.j ProeStep TASK ELEMENT I 2 STANDARD Grade I
If required, adjust CCW Heat Exchanger AP OR CCW Pump discharge pressure.
- Requests A 0 report on new CCW Hx acceptable.
Ensures CCW Heat Exchanger AP values are AP values.
Comment:
EVALUATOR CUE: When requested, as A 0 report:
E-54A Hx AP = 6.8 psid E454B Hx AP = 6.5 psid PALISADES NUCLEAR PLANT END OF TASK 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 0 Insert Event Trigger 1 ZLOl P(46) = P-52A GREEN light 0 Insert CC13B (P-526 fail to start) to ACTIVE Trigger 1.
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 JPM:
RO/SRO-I/SRO-U SYS C TITLE: OPEN MAIN STEAM ISOLATION VALVES AFTER REACTOR IS CRITICAL CAN D I DATE:
EXAMINER:
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE
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-001 J 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 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 have on the S/Gs: MSlVs Validation Time: -
15-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Pe rfo r m a n ce Ti me :
Performance Rating:
SAT UNSAT Comments:
mi nu tes Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C Tools/Equ i pment/Procedu res 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 s u Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-7, section 7.2.2.
Proc. Step TASK ELEMENT 2 STANDARD Grade I
Candidate contacts Auxiliary Operator to latch all MSlV solenoids in the turbine building and 'D' bus area.
7.2.2.c LATCH MSlV solenoid valves.
S U 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 STANDARD Grade I
I s u Candidate determines that CV-0510, 'A' S/G I MSIV, did not open. Proceeds to step 7.2.2.e Step 7.2.2c, THEN GO TO Step 7.2.2q.
IF MSlVs opened after performance of 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
e Proc. Step TASK ELEMENT 5 STANDARD I
r TASK ELEMENT 4 Grade ENSURE CV-0511, Turbine Bypass to Condenser, remains CLOSED by performing the following:
PERFORM the following notifications of impending Steam Dump operation:
JPM: RO/SRO-VSRO-U SYS C Candidate informs CRS to notify Chemistry and to refer to ADMIN 4.00.
STANDARD Candidate performs the following:
PLACES PIC-051 1, Turbine Bypass Valve Control to MANUAL.
Sets PIC-051 1, Turbine Bypass Control Valve to CLOSE.
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 Proc. Step TASK ELEMENT 6 STANDARD I
Candidate directs Auxiliary Operator to close the following valves in the ADV control cabinet:
CLOSE three of the four Steam Dump Air Supplies for the MSlV to be opened, listed -
MV-CA779 below:
MV-CA780 g
MV-CA781 OR MV-CA782 Comment:
EVALUATOR NOTE: LCO 3.7.4.A is applicable. If candidate asks, notify them that the 4 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 STANDARD I
Grade PLACE HIC-O780A, Steam Generator E-50B Steam Dump to MANUAL.
OPERATE HIC-0780A toward 100%
OPEN position to equalize DP across MSIV.
j Candidate:
Places HIC-0780A in Manual Operates manual output lever to open ADV until MSlV CV-0510 opens.
s u I WHEN MSlV opens, THEN PLACE HIC-0780A to CLOSE position.
Candidate Operates manual output lever to close ADV.
s u OPEN Steam Dump Air Supplies closed in Step 7.2.2g above.
~~
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.
Candidate has A 0 open:
MV-CA779 MV-CA780 MV-CA781 OR MV-CA782 Proc. Step TASK ELEMENT 8 STANDARD Grade I
I STANDARD Grade Proc. Step TASK ELEMENT 9 s u 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 s u I Candidate determines this step is N/A because both MSIVs are now open.
REPEAT Steps 7.2.29 through 7.2.2k for IF both MSlVs did NOT open, THEN affected MSIV.
I Proc. Step TASK ELEMENT 11 STANDARD I
I Comment:
Grade m, n Candidate has AO:
CLOSE CV-0511 accumulator drain valve CLOSE CV-0511 accumulator drain valve.
OPEN MV-CA390, Turbine Bypass CV-0511 AIS Iso~.
OPEN MV-CA390, Turbine Bypass CV-0511 AIS IsoI.
Proc. Step TASK ELEMENT 'I2 STANDARD I
Grade EVALUATOR NOTE: If asked, inform candidate that PIC-057 7 and HIC-078OA should be placed back in AUTO.
O9 PALISADES NUCLEAR PLANT RETURN to Or the As Candidate places HIC-0780A and CV-0511 in FOUND position.
RETURN pic-051 to Or the As controllers and verifying the 'A' button lights.
FOUND position.
AUTO by depressing the 'A' button on their s u Page 7 of 10 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS C Proc. Step TASK ELEMENT 14 STANDARD Proc. Step TASK ELEMENT 13 STANDARD Grade I
Grade CLOSE the following valves:
M0-0501' MS'V cv-0501 Bypass (MZ-3)
MO-0510, MSlV CV-0510 Bypass (MZ-2)
Candidate closes MO-0501 and MO-0510 by holding switch in the CLOSE position until associated Green light is ON and Red light is OFF.
s u q
Comment:
CRS informed.
I Candidate informs the CRS that the MSlVs are open and the MSlV bypasses are I
--- I closed.
I s u I Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS C SIMULATOR OPERATOR INSTRUCTIONS IC-1 2 Open MSlV Bypass Valves Close MSlVs Trip B MFP, start P-8A Ensure Reactor Power is rods to approximately 41]
2% (limit for MSlV Bypass valves open)[insert Group 4 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 201 0
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 CAN D I DATE:
EXAM1 NER:
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:
mi nu tes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 16 AUGUST 2010
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.
IN ITlAL 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 16 AUGUST 2010
JPM: RO/SRO-I SYS D f2 ProcStep TASK ELEMENT 1 STANDARD Grade I
Verifies LIC-0101A is in MANUAL.
s u VERIFY controller to be selected in MANUAL.
I --- I Obtains correct procedure.
Candidate locates SOP-1 A, Primary Coolant I System.
I I Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-IA section 7.2.l.f.
I Proc.Step TASK ELEMENT 2 STANDARD Grade If alternating..., then PLACE Charging Pumps Control Select Switches for P-55B Charging Pump (43-1206ES) and P-55C Charging Pump (43-1 105/SS) to MANUAL.
f Comment:
P-55B Control Select Switch to MANUAL.
P-55C Control Select Switch to MANUAL.
s u I
Grade Proc.Step TASK ELEMENT 3 STANDARD Comment:
ProcStep TASK ELEMENT 4 STANDARD Grade I
Using the manual operating lever, ADJUST the output signal of the controller to be f.3 1 selected to match the output signal of the currently selected controller or to desired output.
Comment:
Adjusts output signal on LIC-0101A to match output signal on LIC-0101 B for bumpless transfer.
s u I CRITICAL STEP - only if outputs were not matched PALISADES NUCLEAR PLANT Page 4 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 5 STANDARD Grade I
s u PLACE selector switch I/LRC-0101 to position for controller to be selected.
Places Selector Switch 1 ILRC-0101 to Channel A.
f.4 ProcStep TASK ELEMENT 6 STANDARD Grade I
IF alternating controllers due to a malfunction of the previously selected channel, THEN PLACE the Pressurizer Heater Control Channel Selector Switch...
s u Operator recognizes that this step does not apply.
fS 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 ?
STANDARD Grade I
I IF the desired mode of operation is AUTO, I
Charging and Letdown checked as being appropriate (one Charging Pump and one Letdown Orifice in service).
THEN PLACE the selected controller in AUTO as follows:
(a) VERIFY Charging and Letdown in operation as appropriate.
fm6.(a) s u Comment:
PALISADES NUCLEAR PLANT Page 5 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proc.Step TASK ELEMENT 8 IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows:
match indicated Pressurizer level (red pointer).
Comment:
CRITICAL STEP - only if pointers were not matched STANDARD Grade A
controller raisehower pushbuttons adjusted to match controller setpoint (blue pointer) to Pressurizer level setpoint (red pointer). (blue pointer moved to match red pointer).
s u
- f. 6.( c)
TASK ELEMENT 9 STANDARD IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows:
(c) DEPRESS the A pushbutton on selected controller.
Depresses the A pushbutton on LIC-0101A to place it in AUTO and notes:
A AUTO light DOES NOT light M MANUAL light stays ON Determines that LIC will not shift to AUTO s u Comment:
EVALUATOR CUE:
EVALUATOR CUE:
If Operator announces that Controller will not go into AUTO, CRS acknowledges.
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 By Level 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 f.7 (a)
Comment:
TASK ELEMENT 10 IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(a) VERIFY expected TAVE signal available from selected TAVE/TREF controller (use TYT-0100, TYT-0200, or TI-01 IO).
STANDARD TYT-0200 TAVE signal verified.
f.7 (b)
Comment:
TASK ELEMENT I 1 IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(b) Using raise/lower pushbuttons, SLOWLY ADJUST selected controller setpoint (blue pointer) to the Pressurizer level setpoint determined by present TAVE. Refer to Attachment IO, "TAVE (OF) Pressurizer Level Program."
STANDARD
'A controller raise/lower pushbuttons adjusted to match controller setpoint (blue pointer) to Pressurizer level setpoint (red pointer). (blue pointer moved to match red pointer)
CRITIQIL STEP - only if pointers were not rn@tchssi PALISADES NUCLEAR PLANT Page 7 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D I
STANDARD Grade Proc.Step TASK ELEMENT 12 I
IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(c) DEPRESS the A pushbutton on the selected controller.
Depresses the A pushbutton on LIC-0101A to place it in AUTO and notes:
fm7 ()
A AUTO light DOES NOT light s u M MANUAL light stays ON Determines that LIC will not shift to AUTO Comment:
EVALUATOR CUE:
EVALUATOR CUE:
If Operator announces that Controller will not go into AUTO, CRS acknowledges.
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-0101 to the B position, go to Task Element 13.
If Operator decides to swap back to the By Level 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 STANDARD Grade I
Pressurizer Level Control Selector Switch I I/LRC-0101 placed to the B position.
Place selector switch l/LRC-0101 to Dosition for controller to be selected.
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 201 0
I JPM: RO/SRO-I SYS D ProcStep TASK ELEMENT 14 STANDARD Grade I
f If alternating..., then PLACE Charging Charging Pump (43-1206ES) and P-55C Charging Pump (43-1 105/SS) to MANUAL.
Pumps Control Select Switches for p-55B Recognizes that this step does not apply.
s u ProcStep TASK ELEMENT 15 STANDARD I
Grade place in MANUAL and notes:
M MANUAL light ON I
fm2 I s u I I Depresses M pushbutton on LIC-0101 B to I
I VERIFY controller to be selected in MANUAL.
I I
I 1
C CASCADE light OFF Comment:
f3 Proc.Step TASK ELEMENT 16 STANDARD Grade I
Using the manual lever, ADJUST the output signal of the controller to be selected to match the output signal of the currently selected controller.
output signal.
Adjusts the slide bar to on the B Pressurizer Level Controller being swapped to, matching its output signal to the in-service controllers f4 I CRITICAL STEP - snly if outputs were not matched s u PLACE selector switch 1/LRC-0101 to position for controller to be selected.
Pressurizer Level Control Selector Switch I/LRC-0101 placed to the B position.
Proc.Step TASK ELEMENT 17 STANDARD Grade I
PALISADES NUCLEAR PLANT Page 9 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Proc.Step TASK ELEMENT 18 STANDARD I
Grade fS 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.
Operator recognizes that this step does not apply. Operator MAY reposition Heater Control Channel Selector Switch to Channel B.
IF alternating controllers due to a malfunction of the previously selected channel, THEN PLACE the Pressurizer Heater Control Channel Selector Switch...
S U NOTES: Operator must place the By 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 19.
If Operator NIAs step 6 of SOP-1A section 7.2.1.f, go to Task Element 22.
I Grade Proc.Step TASK ELEMENT I 9 STANDARD I
I IF the desired mode of oDeration is AUTO, I Charging and Letdown checked as being appropriate (one Charging Pump and one Letdown Orifice in service).
THEN PLACE the selected controller in AUTO as follows:
(a) VERIFY Charging and Letdown in operation as appropriate.
s u Comment:
PALISADES NUCLEAR PLANT Page 10 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D
- f. 6.( b)
Comment:
TASK ELEMENT 20 IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows:
(b) Using raise/lower pushbuttons, ADJUST selected controller setpoint (blue pointer) to match indicated Pressurizer level (red pointer).
STANDARD Grade B controller raiselower pushbuttons adjusted to match controller setpoint (blue pointer) to Pressurizer level setpoint (red pointer). (blue pointer moved to match red pointer).
s u I
Proc.Step TASK ELEMENT 21 STANDARD Grade I
IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows:
(c) DEPRESS the A pushbutton on selected controller.
Depresses the on LIc-olol to place it in AUTO and notes:
A AUTO light ON M MANUAL light OFF s u f.6.(c)
Comment:
PALISADES NUCLEAR PLANT Page 11 of 16 AUGUST 201 0
JPM: RO/SRO-I SYS D TASK ELEMENT 22 f.7 (a)
IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(a) VERIFY expected TAVE signal available from selected TAVE/TREF controller (use TYT-0100, TYT-0200, or TI-01 10).
Comment:
STANDARD TYT-0200 TAVE signal verified.
s u f.7 (b)
TASK ELEMENT 23 IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(b) Using raise/lower pushbuttons, SLOWLY ADJUST selected controller setpoint (blue pointer) to the Pressurizer level setpoint determined by present TAVE. Refer to 0, TAVE (OF) Pressurizer Level Program.
STANDARD B controller raise/lower pushbuttons adjusted to match controller setpoint (blue pointer) to Pressurizer level setpoint (red pointer). (blue pointer moved to match red pointer)
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 STANDARD I
Grade f7 ()
Depresses the A pushbutton on LIC-01016 to place it in AUTO and notes:
A AUTO light ON M MANUAL light OFF.
s u IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(c) DEPRESS the A pushbutton on the selected controller.
Comment:
ProcStep TASK ELEMENT 25 IF the desired mode of operation is CASCADE, THEN PLACE the selected controller in CASCADE as follows:
(d) DEPRESS the C pushbutton on the selected controller.
fa7.(d)
Depresses the C pushbutton pushed on LIC-0101 6 to place it in CASCADE and notes:
s u A AUTO light OFF C CASCADE light ON Comment:
ProcStep TASK ELEMENT 26 STANDARD Grade I
IF Charging Pumps P-55B and P-55C were placed in MANUAL, THEN RETURN Charging Pumps Control Select Switches to AUTO.
P-55B Control Select Switch to AUTO.
p-55c Control Select Switch to AUTO.
s u f.8 Comment:
PALISADES NUCLEAR PLANT Page 13 of 16 AUGUST 2010
JPM: RO/SRO-I SYS D Pro e. S ta p TASK ELEMENT 27 STANDARD Grade I
Operator recognizes A Level Controller is in I MANUAL, places the output signal at 50%.
I PLACE the unselected controller in MANUAL, with a 50% output signal.
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 con troller.
ProeStep TASK ELEMENT 28 STANDARD Grade CRS notified Pressurizer Level Controllers not alternated, B Level Controller in service.
Notify CRS that Pressurizer Level Controllers were not alternated, with B Channel in service.
Comment:
EVALUATOR CUE:
If notified, CRS acknowledges.
PALISADES NUCLEAR PLANT END OF TASK 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 (A channel 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.
IN ITlATl NG 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:
EXAM I NER:
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.
Non-condensible gases have been vented from Reactor Vesse Head to the Quench Tank.
Task Standard:
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/Procedu res 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 201 0
JPM RO/SRO-I SYS E Proc.Step TASK ELEMENT 1 STANDARD Grade I
--- I Obtains correct procedure.
I s u Refers to EOP Supplement 26,Section I 3.0.
Comment:
EVALUATOR CUE: Provide candidate a working copy of EOP Supplement 26 Section 3.0.
Proc.Step TASK ELEMENT 2 STANDARD Grade I
3.1.a Ensure at least one Hydrogen Monitor Provided in Conditions.
I in oDeration.
I I s u 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 3-1.c I Open PRV-1072, Vent Path to Quench Tank (preferred method).
STANDARD Grade Obtains Key 11 0.
Places HS-1072 to RESET and then Verifies that PRV-1072 has opened to OPEN.
(RED light is ON and GREEN light goes OFFY s u Comment:
- not critical PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM RO/SRO-I SYS E 3.1.d TASK ELEMENT 4 Vent the Reactor Vessel Head by opening ONE of the following valves for 5-10 minutes:
0 PRV-1067 STANDARD Obtains Key 105.
Places HS-1067 to RESET and then Verifies that PRV-1067 has opened to OPEN.
(RED light is ON and GREEN light is OFF)*
OR 0
PRV-1068 I -
Obtains Key 106.
Places HS-1068 to RESET and then I-to OPEN.
Verifies that PRV-1068 has opened (RED light is ON and GREEN light is OFF)*
Comment:
Note:
- not critical Use of either valve is acceptable.
s u Proc.Step TASK ELEMENT 5 STANDARD Grade I
I s u Vents Reactor Vessel Head for 5-10 I minutes.
After 5-10 minutes, secure Reactor Vessel Head venting.
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 STANDARD Secures Reactor Vessel Head venting by closing the appropriate valve which was opened:
PRV-1067 Using Key 105 places HS-1067 to Verifies that PRV-1067 has closed CLOSE.
(RED light is OFF and GREEN light is ON)*
0 PRV-1068 Comment:
- - not critical OR -
Using Key 106 places HS-1068 to Verifies that PRV-1068 has closed CLOSE.
(RED light is OFF and GREEN light is ON)*
s u 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
Trip all PCPs.
0 0
INSERT MF RCOI (Large Break LOCA)
Place Left Train Hydrogen Monitor in-service per SOP-38.
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)
IN ITlAL 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-U SYS F TITLE:
PLACE A CONTAINMENT RADIATION MONITOR IN SERVICE CAN D I DATE:
EXAM1 NER:
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:
mi nu tes 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 201 0
JPM: ROlSRO-VSRO-U SYS F 7'4m2'a Proc. Step TASK ELEMENT 1 STANDARD Grade REFER TO Attachment 3, Checklist CL 39, "Area Monitors System Checklist."
Candidate determines that this step is N/A per initial conditions.
Obtains correct procedure SOP-39, section 7.4.2 is located s u Comment:
7.4.2.c EVALUATOR CUE: Provide candidate a working copy of SOP-39, section 7.4.2.
IF operate light NOT illuminated, THEN REFER TO Attachment 2, "System Malfunctions and Troubleshooting."
Operator refers to Attachment 2 and locates section 4.1 for Containment Radiation Monitors S U Operate light not illuminated.
Proc. Step TASK ELEMENT 2 STANDARD Grade I
Proc. Step TASK ELEMENT 3 STANDARD Grade I
I 7.4.2.b I CHECK operate light illuminated.
Operator recognizes that the OPERATE light is I not illuminated.
I I
Comment:
Proc Step TASK ELEMENT 4 STANDARD Grade I
I I
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS F Roc. step I
TASK ELEMENT 5 STANDARD Grade I
I 4.1.a I PRESS AND HOLD operate light.
I Operate light pressed and held I s u I 4.1.b Comment:
Operator verifies Orange and Red (Trip 1 and Trip 2) lights not illuminated for RIA-1806, 1807 and 1808.
CHECK other three monitors not tripped.
S U Proc. Step TASK ELEMENT 6 STANDARD Grade I
Comment:
Proc, Step TASK ELEMENT 7 STANDARD Grade I
RIA-I 805 selector switch placed in CHECK I position and released.
PLACE Selector Switch momentarily to CHECK position AND RELEASE.
Comment:
I Proc. Step TASK ELEMENT 8 STANDARD Grade I
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 Proc. Step TASK ELEMENT 9 STANDARD I
Grade TASK ELEMENT 12 STANDARD i
Operator resets:
- AMBER Trip 1
- RED Trip 2 by depressing associated indicating light.
4.1.e RESET all alarms.
s u Comment:
7.4.2.e I
Grade Proc. Step TASK ELEMENT 10 STANDARD 1
I IF operate light still NOT illuminated, THEN DECLARE the associated monitor inoperable. Refer to Attachment 2, "System Malfunctions and Troubleshooting.
Operator determines this step is not applicable because Operate light is illuminated.
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.
s u inoperable AND REFER TO 4.2 below.
Comment:
Proc. Step TASK ELEMENT 11 STANDARD Grade RESET all alarms.
Operator verifies all alarms reset.
s u Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 13 STANDARD Grade nla s u Operator informs Control Room Supervisor that Containment Radiation Monitor RIA-I 805 has been placed in service.
CRS Notified Comment:
PALISADES NUCLEAR PLANT END OF TASK 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 201 0
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS G TITLE: DEPRESSURIZE PCS WHILE ON SHUTDOWN COOLING CAN D I DATE:
EXAM I NER:
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: 01 OAl.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 201 0
JPM: RO/SRO-I/SRO-U SYS G Proc. Step TASK ELEMENT 1 STANDARD Grade Locates correct procedure.
SOP-1 6, Section 7.1.2 obtained.
s u Comment:
EVALUATOR CUE: Provide candidate a Working Copy of SOP-7B, Section 7.7.2 Proc.Step TASK ELEMENT 2 STANDARD Grade I
I I NOTIFY Chemistry to sample the CVCS I
I for boron prior to securing the last charging Given in the Conditions I 7'1'2.a I pump so that VCT boron concentration is s u I known for startup.
I I
Comment:
TASK ELEMENT 3 WHEN depressurizing in Step 7.1.2c, THEN MONITOR for void formation.
Void formation is indicated by one or more of the following:
- 1. Indicated Charging and Letdown flows do not correspond.
- 3. RVLMS indicates voiding in the Reactor Vessel.
STANDARD Monitors the following during the next step:
Charging and Letdown flows Operable PCS temperatures RVLMS indication on Panel C-13 PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS G 7.1.2.c TASK ELEMENT 4 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 temperature from PCS less than or equal to 185°F)
THEN REDUCE PCS pressure by performing the following as directed by the CRS:
- 1. REDUCE PCS pressure using PIC-0202, Letdown Pressure Controller.
STANDARD Raises output on PIC-0202, Letdown Pressure Controller (slide bar to RIGHT = opens associated valve).
s u Comment:
7.1.2.d TASK ELEMENT 5 IF void formation is indicated, THEN RAISE PCS pressure as directed by CRS.
STANDARD Determines that a void exists via RVLMS indications.
Raises PCS pressure to band directed by CRS by:
Adjusts PIC-0202 (slide bar initially to LEFT to close associated valve) s u 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 STANDARD Grade I
REDUCE PCS pressure by performing the following as directed by the CRS:
- 2. STOP the remaining Charging Pump.
s u Stops Charging Pump P-55A when PCS pressure is below 100 psia.
7.1.2.c Comment:
IF void formation is indicated, THEN Comment:
STANDARD Determines that a void exists via RVLMS indications.
Raises PCS pressure to band directed by CRS by:
Starts one Charging Pump and Adjusts PIC-0202 (slide bar initially to LEFT to close associated valve) s u 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 s u na CRS NOTIFIED.
NOTIFY the CRS that PCS voids are no longer evident.
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-0101 B-R1 to ON LI-01 OIA-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-0101 B-GI Action for Trigger 3: ior LI-0101 B-R1 Action for Trigger 4: ior LI-0101 A-R1 Action for Trigger 5: ior LI-0101A-GI PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 201 0
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 201 0
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO=l SYS H TITLE: TEMPORARILY SECURE SHUTDOWN COOLING FLOW CAN D I DATE:
EXAM I 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:
Validation Time:
20 minutes Time Critical:
NO SOP-3, Safety Injection and Shutdown Cooling System Candidate:
Time Start:
Time Finish:
Performance Time:
mi n Utes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 12 AUGUST 201 0
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 201 0
PALISADES NUCLEAR PLANT Page 4 of 12 JPM: RO/SRO-I SYS H 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 s u Comment:
I EVALUATOR CUE: Provide candidate a working copy of SOP-3, Section 7.3.6 I
Proc. Step TASK I%EMENT 2 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 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.
7m3.6ma Comment:
STANDARD Given in the Initial Conditions IF PCS temperature will be changed more than five (5) degrees from the established and Pressurizer parameters are being monitored. Refer to PO-2, "PCS Heatup/Cooldown Operations."
target temperature, THEN ENSURE pcs Determines that this step is being met.
(PO-2 performance given in initial conditions) 7.3m6'b s u Comment:
PALISADES NUCLEAR PLANT Page 5 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H 7.3.4.c P w. Step TASK ELEMENT 4 STANDARD Grade s u DETERMINE desired total Shutdown Cooling flow.
previous step 7.3.6.c).
Determines 300-500 gpm applies (from 7.3.6.c PERFORM Section 7.3.4 to reduce total Shutdown Cooling flow to approximately 300 to 500 gpm.
Branches to section 7.3.4 of SOP-3 s u Comment:
Evaluator provides a Working Copy of SOP-3, Section 7.3.4 EVALUATOR CUE: Another Operator will control PCS pressure during this evolution.
7.3.4.a Comment:
TASK ELEMENT 5 IF PCS temperature will be changed more than five (5) degrees from the established target temperature, THEN ENSURE PCS and Pressurizer parameters are being monitored. Refer to PO-2, "PCS HeatuplCooldown Operations."
STANDARD Determines that this step is being met.
(PO-2 performance given in initial conditions) 7.3.4.b IF PCS level is greater than 643'-0" AND any CRDM tool access flanges are removed, THEN ENSURE personnel are clear of CRDM tool access flanges and Reactor Cavity.
Determines that this step does not apply.
(PCS level is given in initial conditions) s u Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade I
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 8 STANDARD I
Grade 7'3'4'd Comment:
EVALUATOR CUE: CRS directs that sub-step 3 is not applicable for this evolution.
s u IF Shutdown Cooling flow is to be throttled below 2810 gpm,...
apply.
Determines that sub-steps 1,2, and 3 do not 7.3.4.d TASK ELEMENT 9 IF Shutdown Cooling flow is to be throttled below 281 0 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, THEN CLOSE AND CAUTION TAG MV-CVC2162, Primary Makeup Water Supply Stop within one hour.
STANDARD Notifies CRS of need to Caution Tag MV-CVC2 1 62.
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 IF Shutdown Cooling flow is to be throttled below 2810 gpm,...
7.3.4.d
- 5. MAINTAIN General Operating Procedure GOP-14, "Shutdown Comment:
STANDARD Notifies CRS of need to maintain GOP-14 requirements.
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 7.3.4.e DETERMINE required status of...
I I
7.3.4.f Determines that maximum of one throttled/open LPSl Injection Valve applies. (per initiating cue this will be MO-3014) l s u l ADJUST Shutdown Cooling flow as follows:
Checks FIC-0306 is in MANUAL.
s u
- 1. ENSURE FIC-0306 is in MANUAL.
Comment:
I Proc. Step TASK ELEMENT 12 STANDARD Grade I
TASK ELEMENT 13 ADJUST Shutdown Cooling flow as follows:
7.3.4.f
- 2. SLOWLY OPERATE LPSl injection Valves to establish status determined in SteP 7.3.4e.
Comment:
STANDARD Omde SLOWLY operates each of the four LPSl Injection Valves (one at a time) until only one (MO-3014) LPSl Injection Valve is throttled open I
and SDC flow is 300 to 500 gpm.
I follows:
I 3* BALANCE flow between in use LPSl Injection Loops to desired Total Shutdown Cooling flow determined in Determines this step is not applicable.
I I
7.3.4.f s u
~
Comment:
PALISADES NUCLEAR PLANT Page 8 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H 7.3.4.f follows:
I I Determines this step is not applicable.
- 4. If necessary:
(a) THROTTLE CV-3025, SDC Hx Outlet to maintain desired I
s u Comment:
7.3.4.f Comment:
TASK ELEMENT 16 ADJUST Shutdown Cooling flow as follows:
- 4. If necessary:
(b) THROTTLE FIC-0306 output signal to maintain desired flow through Shutdown Cooling Heat Exchangers.
STANDARD Determines this step is not applicable.
Branches back to section 7.3.6 of SOP-3 s u Proc. Step TASK ELEMENT 17 STANDARD Grade WHEN Total Shutdown Cooling flow has been reduced to approximately 300 to 500 gpm, THEN PERFORM the following:
- 1. CLOSE CV-3025, SDC Hx Outlet.
7.3.6.d HIC-3025A MANUAL Slide Bar used to CLOSE (Slide bar taken to the left) CV-3025 AND CO-ORDINATES with the with Operator controlling PCS Pressure s u 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 7.3.6.d Comment:
TASK ELEMENT 18 WHEN Total Shutdown Cooling flow has been reduced to approximately300 to 500 gpm, THEN PERFORM the following:
- 2. CLOSE CV-3055, SDC Hx Inlet.
STANDARD Grade HS-3025A to CLOSE with key.
(Key may be removed or left in keyslot)
I Grade Proc. Step TASK ELEMENT I 9 STANDARD WHEN Total Shutdown Cooling flowhas been reduced to approximately 300 to 500 gpm, THEN PERFORM the following:
7.3.6.d I
- 3. STOP the operating LPSl Pump.
I P-67B STOPPED s u Comment:
Proc. Step TASK ELEMENT 20 STANDARD Grade NOTIFY the CRS that Shutdown Cooling has been temporarily secured per SOP-3, Section 7.3.6.
n/a CRS NOTIFIED SDC temporarily secured s u Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 10 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H SIMULATOR OPERATOR INSTRUCTIONS 0
0 0
0 IC-2, Ready to Start PCPs Need Dedicated Operator to control PCS pressure during evolution (solid plant control)
Ensure TR-0351 S/D Cooling recorder in operation Keys installed in the following MOVs:
. M0-3015
. MO-3016
. MO-3189
. MO-3198 MO-3190
. MO-3189 0
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:
Alternate Path: NO Facility JPM #: PL-OPS-WGS-001 J WA: 071K4.04 Importance:
RO: 2.9 SRO: 3.4 Secure from Waste Gas Release 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 nn.1 Proc. Step TASK ELEMENT 1 STANDARD Grade I
SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge
. MV-WG718A, T-IOIA, B & C Outlet Header Valves T-68A/B/C:
MV-WG718A CLOSED Isolation I n/a I Obtain correct procedure.
I SOP-I8A, Section 7.5, Step nn located I s u I I EVALUATOR CUE: Provide candidate a working copy of SOP-I8A, Section 7.5, step nn I Proc. Step TASK ELEMENT 2 STANDARD Grade I
I SECURE from WGDT release as follows: I I
- 1. CLOSE appropriate Discharge MV-WG719, T-68A, B & C Outlet nn.1 Header Valves T-68AIBIC:
MV-WG719 CLOSED Isolation Comment:
EVALUATOR NOTE: Task Elements 2 and 3 can be performed in any order since they are bulleted substeps s u 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 I
WGDT Discharge, as follows:
.PLACE in CLOSE position HS-1123, Waste Gas Decay Tanks Discharge, at C-40 HS-1123 in CLOSE Comment:
EVALUATOR CUE: CV-7723 is closed, the green light is lit.
s u Proc. step TASK ELEMENT 5 STANDARD Grade I
I CLOSE Discharge Control Valve CV-1123, I.
HIC-1123 INDICATING 0 psi I
WGDT Discharge, as follows:
I
.SET to zero (0) psi HIC-1123, Waste nn.2.b I
Gas Discharge To Stack I
s u I
Comment:
EVALUATOR CUE: HIC-I123 indicates 0 psi nn.3 TASK ELEMENT 6 OPEN ONE of the following Drain Valves to DRAIN selected WGDT for one (1) minute, THEN CLOSE:
mMV-CA352, I/A Isolation/Control To CV-1120B. T-68B Drain Valve Comment:
EVALUATOR CUE: one minute has elapsed.
STANDARD OPENS MV-CA352 for one (1) and then CLOSED (Opens MV-CA352 which opens CV-1120B)
PALISADES NUCLEAR PLANT Page 5 of 7 AUGUST 2010
JPM: RO/SRO-IISRO-U SYS I Roc. Step TASK ELEMENT 7 STANDARD I
t Grade I s u NOTIFY CRS that WGDT T-68B release CRS WGDT T-68B SECURED I n'a I secured I
Comment:
PALISADES NUCLEAR PLANT END OF TASK Page 6 of 7 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I PALISADES NUCLEAR PLANT
~~
(TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
IN IT1 AL CON DIT1 ONS:
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 IN IT1 AT1 NG CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step mm.
Page 7 of 7 AUGUST 2010
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 CAN D I DATE:
EXAM I 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-01 OJ 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 1 C and 1 D 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 STANDARD Grade I
I I nla I Obtains correct procedure I EOP Supplement 19, Section 4.0 located I s u I OPEN HS-O522B, K-8 Normal Steam locations...
Supply, from one of the following prioritized 1
Comment:
EVALUATOR CUE:Provide candidate a working copy of EOP Supplement 19 Determines that this step is not applicable s u Proc. Step TASK ELEMENT 2 STANDARD Grade I
4.0.1 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 4.0.2.a v
TASK ELEMENT 3 STANDARD Grade I
CLOSE the following valves:
Simulates or describes CLOSING by turning the hmdWhee1 clockwise:
- MV-CA377, air supply to CV-0522B MV-N2/268, nitrogen supply to s u mMV-CA377, air supply to CV-0522B mMV-N2/268, nitrogen supply to CV-0522B CV-05228 Comment:
EVALUATOR CUE: The valves are closed PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J MANUALLY CLOSE CV-05226, K-8 Normal Steam Supply, as follows?
' TURN ha-~dwheel c~ockwise until the top of the actuator shaft is exposed sufficiently to engage the coupling Proc. Step TASK ELEMENT 4 STANDARD Grade I
Simulates or describes TURNING handwheel clockwise until manual override shaft is exposed 4.0.2.b.l MANUALLY CLOSE CV-05226, K-8 Steam Supply From E-50A, as follows:
. UNSCREW the coupling from the Simulates or describes UNSCREWING coupling from shaft by turning coupling counter clockwise manual override shaft s u 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 4.0.2.b.2 s u Comment:
EVALUATOR CUE: The manual shaft is exposed Proc. Step TASK ELEMENT 6 STANDARD Grade I
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 I
Grade TASK ELEMENT 7 STANDARD I
I Simulates or describes REMOVING the lockwire REMOVE lockwire from MV-FW356, CV-0522B Bonnet Isolation 402b6 Comment:
EVALUATOR CUE: The lockwire is removed from MV-FW356, CV-0522B Bonnet isolation Simulates or describes checking valve closed by TURNING handwheel in the clockwise direction S U (given in the initial conditions)
CLOSE CV-O522B, K-8 Normal Steam Supply, using the handwheel I
I Proc. Step TASK ELEMENT 8 STANDARD Grade I
Simulates or describes OPENING MV-FW356 by TURNING handle 90 degrees (places it in-line I with the turbine/piping).
OPEN MV-FW356, CV-0522B Bonnet I
EVALUATOR CUE: MV-FW356, CV-05225 Bonnet isolation handle is in line with the Proc. Step TASK ELEMENT 9 STANDARD Grade I
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 4.0.2.c.l CHECK Turbine Driver K-8 is latched as ENSURE the end of resetting level
, follows:
(knife edge) is in contact with the trip level (can NOT slip a sheet of paper between),. Refer to Figure 1 (Page
- 20)
Determines that Turbine Driver is NOT RESET s u 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 STANDARD Grade I
I CHECK Turbine Driver K-8 is NOT latched, THEN RELATCH as follows:
I. ENSURE CLOSED CV-O522B, K-8 4.0.2.c.2.a I
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:
4.0-2-c-2-b
= RESET the overspeed trip lever on Turbine Driver K-8 using the Auxiliary Reset lever Simulates or describes PULLING UP on the Auxiliary Reset lever until the lever is in contact with the knife edge S U 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 STANDARD Grade I
CHECKS room for personnel s u CLEAR personnel from the Auxiliary Feedwater Pump room na Comment:
EVALUATOR CUE: There are no other personnel in the Auxiliary Feedwater Pump room I
Grade Proc. Step TASK ELEMENT 14 STANDARD PI-0590 root valve by TURNING the handwheel Simulates or describes OPENING MV-FW688, counter clockwise S U I
4.0.2.d OPEN MV-FW688, PI-0590 root valve I
Comment:
EVALUATOR CUE: Valve is open Proc, step TASK ELEMENT 15 STANDARD Grade I
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 PI-0521A with the hand operator by TURNING handwheel counter clockwise S U 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 STANDARD Grade I
4'0'2.e EVALUATOR CUE: PI-0590 OR PI-0521B indicates 235 psis and stable s u CHECK PI-0590 OR PI-0521 B reading between 200 and 250 psig VERIFIES PI-0590 OR PI-0521 B reading between 200 to 250 psig Proc, Step TASK ELEMENT 17 STANDARD Grade CRS NOTIFIED that AFW Pump, P-8B is I operating with CV-0522B opened manually Notify CRS that AFW Pump, P-8B is operating Comment:
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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 1 D 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.
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NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS K TITLE:
REDUCE STATION BATTERY #I LOADING CAN D I DATE:
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-021 J 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 as it is affected by discharge rate.
I 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 :
E 0 P-3.0, "Stat ion Blackout Recovery" EOP Supplement 7, "Battery # I Load Stripping" Validation Time:
- IO-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/Equ i pment/Procedu res Needed:
~
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.
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JPM: RO/SRO-VSRO-U SYS K Proc. Step TASK ELEMENT 1 STANDARD Grade I "
nla I Locate correct procedure EOP Supplement 7 is located I s u Comment:
EVALUATOR CUE: Provide candidate a working copy of EOP Supplement 7
1.0.1 Comment
TASK ELEMIZNT 2 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, use the outer scale on EAI-45
- b. For values less than 200 amps, use the Lower Scale Reading push button and the inner scale on EAI-45 STANDARD Operator reviews instructions for reading Station Battery No. 1 Ammeter.
s u 1.0.2 TASK ELEMENT 3 RECORD the following:
- a. Time of event initiation:
- b. Present Time:
- c. Station Battery No 1 discharge current: EAI-45:
Amps STANDARD Operator RECORDS the following:
35 minutes ago from present time Present time Operator determines bus loading for Station Battery No. 1 by:
depressing Lower Scale Reading push button reading inner scale of ammeter.
Records 190 amps s u 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 Lc
1.0.3 Comment
TASK ELEMENT 4 DETERMINE the maximum acceptable Station Battery No 1 discharge current for time since event initiation:
Time Since Event AccePtable Current 0 to 1 min.
1 to 11 min.
11 to 30 min.
> 30 min.
I 8 3 2 amps S401 amps 5 222 amps I
157 amps STANDARD Operator determines the following maximum acceptable Station Battery No. 1 discharge current is I 157 amps 1.0.4.a TASK ELEMENT 5 IF Station Battery No 1 discharge current is greater than, or will be greater than, the limits of Step 1.3, THEN PERFORM the following steps, as necessary, to maintain discharge current within acceptable limits:
OPEN the following breakers in the Cable Spreading Room:
Panel D11-1 72-107 72-113 72-114 72-116 Panel Dl l-2 72-122 72-126 72-128 72-130 72-133 72-134 STANDARD Operator performs the following:
Determines that discharge current of 190 amps is not acceptable Simulates OPENING breakers on panels D11-1 and Dll-2.
s u 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 WHEN the above breakers are open, THEN RECORD the following:
- 1) Time:
- 2) Station Battery No 1 discharge current: EAI-45:
amps 1.0.4.b Operator performs the following:
RECORDS present time Depresses Lower Scale Reading push Reads inner scale of ammeter button RECORDS Battery No. 1 discharge current s u 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 IF Station Battery No 1 discharge current continues to be greater than the acceptable limits of Step 1.3, THEN OPEN the following breaker in Cable Spreading Room 1'0'4.c 72-17 (D-10)
Comment:
STANDARD Grade I
I Operator performs the following:
Determines that discharge current is still Simulates OPENING breaker 72-1 7 on D-not acceptable 10 s u EVALUATOR CUE:Provide cue that breaker indicates OFF. Battery discharge current should lower by approximately 40 amps.
Proc. 8tep TASK ELEMENT 8 STANDARD Grade WHEN the above breaker is open, THEN RECORD the following:
- 1) Time:
- 2) Station Battery No 1 discharge current: EAI-45:
amps 1.0.4.d Operator performs the following:
RECORDS present time Depresses Lower Scale Reading push button Reads inner scale of ammeter RECORDS Battery No. 1 discharge current s u EVALUATOR CUE:Use pointer and place on Station Battery No. 1 ammeter, AI-45, to indicate 135 AMPS out on inner scale.
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JPM: RO/SRO-I/SRO-U SYS K 1'0'4'e Proc. Step TASK ELEMENT 9 STANDARD Grade I
IF Battery No discharge current Operator determines that this step is N/A because Battery No. 1 discharge current is s u continues to be greater than the acceptable limits of Step 1.3, THEN PERFORM the following...
<I 57 amps Comment:
Proc. step TASK ELEMENT 10 STANDARD Grade I
Operator informs Control Room that task Control Room informed is complete I
nla 1
Comment:
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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)
IN ITlAL 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.
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