ML111460567
| ML111460567 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/16/2010 |
| From: | Palagi B NRC/RGN-III/DRS/OLB |
| To: | |
| Shared Package | |
| ML102070508 | List: |
| References | |
| Download: ML111460567 (97) | |
Text
2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION AS-AD M I N ISTE RE D EXAM FI LES 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-O13J K/A: 004A4.18 Importance:
RO: 4.3 SRO: 4.1 WA Statement: Ability to manually operate and/or monitor in the control room:
Emergency borate valve Task Standard: All critical steps for Emergency Boration via Gravity Feed per SOP-2A, 4 have been completed within 15 minutes.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform X
Simulate
References:
EOP-1.O, Standard Post-Trip Actions SOP-2A, Chemical and Volume Control System Validation Time:
5 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010
JPM RO SYS A Tools/Equ ipmenVProcedu res Needed:
SOP-2A, "Chemical and Volume Control System," Attachment 14, "Emergency Manual Boration" Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
0 The Reactor has tripped and four full length Control Rods are not fully inserted.
Bus I D has a fault and is de-energized.
Bus I C is energized.
INITIATING CUES:
0 The Control Room Supervisor directs you to commence Emergency Boration per EOP-1.O, Immediate Action step 1.c.l.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM RO SYS A EVALUATOR NOTE: Emergency Boration is available by gravity feed only EVALUATOR CUE: Provide candidate a working copy of SOP-2A, Attachment 14 TASK ELEMENT I STANDARD Orade Proc.
WP Charging flow is verified greater than 33 gpm I
Att. 14, Ensure charging flow greater than 1.0 I33gprn Comment:
TASK ELEMENT 2 STANDARD Grade Proc.
Step I s u Determines that this step is not applicable I
If Bus 1 D is energized...
Comment:
If Bus 1C is energized, then, THEN ESTABLISH Gravity Feed PLACES handswitch for MO-2169 to open, (red light on, green light off)
Att. 14, 2.0b.l PLACES handswitch for MO-2170 to open, (red light on, green light off)
' OPEN M0-2169 and M0-21707 Boric Acid Tank Gravity Feed Isolation Valves.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 2010
JPM RO SYS A TASK ELEMENT 4 STANDARD Roc.
Step Grade Att. 14, 2.0b.2 Comment:
s u CLOSE CV-2155, Boric Acid Blender Outlet Control Valve CV-2155 verified CLOSED (red light off, green light on.)
TASK ELEMENT 5 STANDARD Grade Proc.
Step s u Att. 14, PLACES handswitch for MO-2087 to 2.0b.3 Valve CLOSE, (red light off, green light on).
Comment:
CLOSE MO-2087, VCT Outlet Isolation TASK ELEMENT 6 STANDARD Grade Proc.
Step Att. 14, Close MO-2160, SIRW Tank to I 2.0b.4 I 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-2160 position, report that MO-2160 I
is closed.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO SYS A TASK ELEMENT 7 STANDARD PrOC.
Step Grade Att. 14, If YO1 is not energized, THEN I 2.0b.5 I PERFORM the following:
STANDARD TASK ELEMENT 8 Proc.
step l s u l I Determines that this step is not applicable Grade Comment:
TASKELEMENT 9 STANDARD Proc.
Step Grade I s u l VERIFIES charging flow greater than 33 gpm on FIA-0212 I
VERIFY charging flow greater than Charging Line Flow Indicator Alarm 33 gpm as indicated by FIA-0212, na Comment:
s u Notify the Control Room Supervisor that emergency boration is in progress CRS notified PALISADES NUCLEAR PLANT END OF TASK Page 6 of 8 AUGUST 2010
JPM RO SYS A SIMULATOR OPERATOR INSTRUCTIONS Use any at power IC.
Insert malfunctions per the following table or use CAE file:
MALFUNCTION No. MALFUNCTION ET DELAY LOCATION RAMP VALUE RD16 Control rod stuck PIDRD02 5 (stuck)
ED04B Loss of Bus 1 D PIDEDOG True TITLE (select any 4 full length control rods)
Trip the Reactor Carry out EOP-I.O Immediate Actions.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
I (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Reactor has tripped and four full length Control Rods are not fully insetted.
Bus I D has a fault and is de-energized.
Bus I C is energized.
INITIATING CUES:
The Control Room Supervisor directs you to commence Emergency Boration per EOP-1.O, Immediate Action step 1.c.l.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO/SRO-I SYS B TITLE: SHIFT OPERATING CCW PUMPS CAN D I DATE:
EXAMINER:
JPM RO/SRO-I SYS B JOB PERFORMANCE MEASURE DATA PAGE Task:
Shift Operating Component Cooling Water Pumps Alternate Path: YES - CCW pump will trip when started. Alternate CCW pump must be manually started to maintain CCW cooling.
Facility JPM #: PL-OPS-CCW-001 J KIA:
008A2.0 1 I m po rtance:
RO:3.3 SRO:
3.6 WA Statement:
Ability to predict impacts of loss of CCW pump and correct, control, or mitigate the consequences.
Task Standard: P-52A P-52B in service Preferred Evaluation Location : Si mu lator X
In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
ONP-6.2, Loss of Component Cooling SOP-I 6, Component Cooling Water System Validation Time:
-1 5-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
mi nu tes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 9 AUGUST 2010
JPM RO/SRO-I SYS B
~
PALISADES NUCLEAR PLANT Tools/Equipment/Procedures Needed:
SOP-I 6, Component Cooling Water System ONP-6.2, Loss of Component Cooling Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
0 The Plant is at full power.
0 Both CCW Heat Exchangers are in operation.
CCW Pump P-52A is in service CCW Pumps P-52B and P-52C are in STANDBY.
INITIATING CUES:
The Control Room Supervisor directs you to shift operating CCW pumps per SOP-16, Section 7.3.6.
P-52C is to be started and P-52A and P-52B are to be left in STANDBY.
Page 3 of 9 AUGUST 2010
JPM RO/SRO-I SYS B EVALUATOR CUE: Provide candidate a working copy of SOP-16, section 7.3.6.
7.3.6.a Ptoc.Step TASK ELEMENT 1 STANDARD Grade I
s u Ensure LOCKED OPEN CCW pump P-52C suction and discharge valves.
Contacts A 0 to ensure MV-CC921 and MV-CC945 locked OPEN.
Proc.Step TASK ELEMENT 2 STANDARD Grade I
7.3.6.b Contacts A 0 to cycle MV-CC558 open and closed.
CUE:
s u Operate P-52C pump casing vent petcock to vent air from pump casing.
A 0 reports MV-CC558 cycled open and closed.
Comment:
ProcStep TASK ELEMENT 3 STANDARD Grade I
Both CCW Heat Exchangers in operation.
s u 7.3.6.c 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 E-54A AP is 6.6 psid.
E-54B AP is 6.8 psid.
following:
PALISADES NUCLEAR PLANT Page 4 of 9 AUGUST 201 0
JPM RO/SRO-I SYS B 7.3.6.d Proc.Step TASK ELEMENT 4 STANDARD Grade I
P-52C Handswitch taken to TRIP and amber IF the pump being started is in standby, THEN REMOVE the pump from standby by STBY extinguishes.
placing Control Switch to TRIP.
7.3.6.f Comment:
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 N/A since pump was started from Control Room.
I' Grade Proc.Step TASK ELEMENT 5 STANDARD 7m3.6'g P-52C CCW pump running. RED light above handswitch ON, GREEN light OFF.
7'3'6'e START selected CCW Pump.
s u P-52A has been stopped using handswitch.
RED light OFF, GREEN light ON.
STOP selected CCW Pump.
Comment:
Proc.Step TASK ELEMENT 6 STANDARD Grade I
.L Comment:
Proc.Step TASK ELEMENT 7 STANDARD Grade I
Comment:
EVALUATOR NOTE: P-52C will trip 5 seconds affer P-52A is secured. P-526 will not auto start on low pressure.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 201 0
JPM ROlSRO-I SYS B 4.1.a ProcStep TASK ELEMENT 8 STANDARD Grade I
- Checks CCW Surge Tank level to ensure Starts P-52A (or P-52B).
- Verifies RED Light ON, GREEN light OFF.
adequate inventory.
IF less than 10 minutes has elapsed since loss of CCW, then start available CCW pumps as appropriate (based on suction supply).
s u Refers to ARP'7, window 67 and notifies CRS of P-52C trip and the need to reference ONP-6.2.
CRS notified.
Proc.Step s u TASK ELEMENT 10 STANDARD Grade Comment:
EVALUATOR CUE:lf asked about any required actions for P-52A, role play and ask candidate what should be done. Candidate should state that ONP-6.2 should be entered and P-52A or P-52B should be manually started; agree and direct P-52A or P-526 started.
EXAMINER NOTE: Actual ONP entry is NOT required; CRS is directing use of ONP-6.2, 4.1.a step to start desired CCW pump.
EVALUATOR CUE: Provide candidate a working copy of ONP-6.2, page I.
7.3.6.hJ PRESS amber STANDBY button for pump to be placed in STANDBY.
CHECK amber STANDBY button light ON.
s u Candidate determines this step is N/A from initial conditions.
- = Not part of Critical Step PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO/SRO-I SYS B Proc.Step TASK ELEMENT I?
STANDARD Grade I
7.3.6.j Comment:
EVALUATOR CUE: When requested, as A 0 report:
E-54A Hx AP = 6.8 psid E54B Hx AP = 6.5 psid If required, adjust CCW Heat Exchanger AP OR CCW Pump discharge pressure.
Requests A 0 report on new CCW Hx Ensures CCW Heat Exchanger AP values are acceptable.
AP values.
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
0 0
Ensure CCW pump P-52A is running.
Ensure CCW Pump P-52B and P-52C in STANDBY INSERT MF CCO2C for CCW Pump P-52C with a 5 second time delay, assign to Insert Event Trigger 1 ZLOl P(46) = P-52A GREEN light Insert CC13B (P-52B fail to start) to ACTIVE Trigger I.
0 0
PALISADES NUCLEAR PLANT Page 8 of 9 AUGUST 201 0
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
IN ITlAL CONDITIONS:
The Plant is at full power.
Both CCW Heat Exchangers are in operation.
CCW Pump P-52A is in service CCW Pumps P-52B and P-52C are in STANDBY.
INITIATING CUES:
The Control Room Supervisor directs you to shift operating CCW pumps per SOP-16, Section 7.3.6.
P-52C is to be started and P-52A and P-52B are to be left in STANDBY.
PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO/SRO=I/SRO=U SYS C TITLE: OPEN MAIN STEAM ISOLATION VALVES AFTER REACTOR IS CRITICAL CAN D I DATE:
EXAMINER:
JPM: RO/SRO-VSRO-U SYS C JOB PERFORMANCE MEASURE DATA PAGE Task:
Open MSlVs Alternate Path: YES - One MSlV will not open requiring ADV operation to open.
Facility JPM #: PL-OPS-MSS-001 J K/A:
035K6.01 Importance:
RO:
3.2 SRO:
3.6 K/A Statement: Knowledge of the effect of a loss or malfunction of the following will have on the S/Gs: MSlVs Task Standard: Both MSlVs Open, MSlV bypasses closed, ADVs and TBV in AUTO Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
SOP-7, Main Steam System Validation Time: -
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 10 AUGUST 2010
Tools/Equipment/Procedures Needed:
SOP-7, "Main Steam System" Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
I 0
The reactor is critical with power at the POAH MSlV Bypass valves, MO-0501 and MO-0510, are open 0
Vacuum is established on the Main Turbine and the secondary plant is in the process of being started up INITIATING CUES:
The Control Room Supervisor directs you to open the MSlVs per SOP-7, starting at step 7.2.2.c.
I PALISADES NUCLEAR PLANT Page 3 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C EVALUATOR CUE: Provide candidate a working copy of SOP-7, section 7.2.2.
Proc. Step TASK ELEMENT 1 STANDARD Grade LATCH MSlV solenoid valves.
all MSlV solenoids in the turbine building and 'D' Candidate contacts Auxiliary Operator to latch bus area.
S U I
Comment:
SIM OPERATOR: Use MS36 on P&ID MS02, DO NOT latch 'A' MSlV (MS25) but report that it is complete.
Proc. Step TASK ELEMENT 2 STANDARD Grade I
Candidate determines that CV-0510, 'A' S/G I MSIV, did not open. Proceeds to step 7.2.2.e IF MSlVs opened after performance of Step 7.2.2~. THEN GO TO Step 7.2.211.
Comment:
EVALUATOR CUE: Role play as CRS and direct candidate to proceed to step 7.2.2.e, if asked.
e TASK ELEMENT 3 ENSURE CV-0511, Turbine Bypass to Condenser, remains CLOSED by performing the following:
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 A/S Isolation.
Has A 0 OPEN accumulator drain valve to bleed pressure from CV-0511 accumulator, THEN CLOSE the valve.
s u Comment:
SIM OPERATOR: Use MS35 on PIDMSO3 to close air supply to CV-0511, then notify as A 0 that air supply is closed and accumulator is bled down PALISADES NUCLEAR PLANT Page 4 of 10 AUGUST 201 0
JPM: RO/SRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 4 STANDARD Grade I
PERFORM the following notifications of Candidate informs CRS to notify Chemistry and f
I impending Steam Dump operation:
I to refer to ADMlN 4.00.
Comment:
EVALUATOR CUE: Notify Candidate that the Shift Engineer will perform this.
Proc. Step TASK ELEMENT 5 STANDARD Grade I
Candidate directs Auxiliary Operator to close the following valves in the ADV control cabinet:
CLOSE three of the four Steam Dump Air 9
Supplies for the MSlV to be opened, listed -
below:
s u MV-CA779 MV-CA780 MV-CA781 OR MV-CA782 Comment:
EVALUATOR NOTE: LCO 3.7.4.A is applicable. If candidate asks, notify them that the CRS will address LCO 3.7.4.
SIM OPERATOR: Use MS18, MSl9, MS20 (or MS21) on PID MSOI to close these valves PALISADES NUCLEAR PLANT Page 5 of 10 AUGUST 201 0
JPM: RO/SRO-I/SRO-U SYS C I
Grade Proc. Step TASK ELEMENT 6 STANDARD PLACE HIC-O780A, Steam Generator Candidate:
E-50B Steam Dump to MANUAL.
OPEN position to equalize DP across MSIV.
until MSIV CV-0510 opens.
s u Places HIC-0780A in Manual Operates manual output lever to open ADV hg OPERATE HIC-0780A toward 100%
Comment:
EVALUATOR NOTE: If candidate asks, inform them that the required notifications are made.
EVALUATOR NOTE: CV-0510 will latch when HIC-078OA reaches -25% output.
Proc. Step TASK ELEMENT 7 STANDARD Grade I
Proc. step TASK ELEMENT 8 STANDARD Grade I
I Candidate has A 0 open:
MV-CA779 Step 7.2.2g above.
MV-CA780 s u OPEN Steam Dump Air Supplies closed in MV-CA781 OR MV-CA782 Comment:
SIM OPERATOR: Use MS18, MS19, MS20 (or MS21) on PID MSOl to open the valves that were closed in Task Element #6.
PALISADES NUCLEAR PLANT Page 6 of 10 AUGUST 2010
JPM: ROlSRO-I/SRO-U SYS C Proc. Step TASK ELEMENT 9 STANDARD Grade I
Candidate determines this step is N/A because both MSIVs are now open.
IF both MSlVs did NOT open, THEN REPEAT Steps 7.2.29 through 7.2.2k for affected MSIV.
I Comment:
Proc. Step TASK ELEMENT 10 STANDARD Grade I
I I Candidate has AO:
I I -
CLOSE CV-0511 accumulator drain valve I I CLOSE CV-0511 accumulator drain valve.
m, n OPEN MV-CA390, Turbine Bypass I CV-0511 AIS IsoI.
I OPEN MV-CA390, Turbine Bypass I -
CV-0511 AIS Isol.
Comment:
SIM OPERATOR: Use MS35 on PlDMSO3 to open air supply to CV-0517.
Proc. Step TASK ELEMENT I 1 STANDARD Grade I
RETURN HIC-0780A to AUTO or the AS FOUND position.
RETURN to Or the As controllers and verifying the 'A' button lights.
FOUND position.
Candidate places HIC-0780A and CV-0511 in AUTO by depressing the 'A' button on their s u O'
Comment:
EVALUATOR NOTE: If asked, inform candidate that PIC-0577 and HIC-078OA should be placed back in AUTO.
PALISADES NUCLEAR PLANT Page 7 of 10 AUGUST 2010
JPM: ROlSRO-VSRO-U SYS C CLOSE the following valves:
M0-0501 MSIV cv-0501 Bypass (MZ-3)
MO-0510, MSlV CV-0510 Bypass (MZ-2) q Proc. step TASK ELEMENT 12 STANDARD Grade I
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 Proo. Step TASK ELEMENT 13 STANDARD Grade I
Candidate informs the CRS that the MSlVs closed.
are open and the MSlV bypasses are CRS informed.
s u END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C SIMULATOR OPERATOR INSTRUCTIONS IC-I 2 Open MSlV Bypass Valves Close MSlVs Trip 'B' MFP, start P-8A Ensure Reactor Power is rods to approximately 41 "1 Insert the following triggers:
Trigger: 1 Event: ZA03F(62).gt.0.25 (ADV Controller reaches 25% output)
Action: irf ms25 latch (opens MSIV) 2% (limit for MSlV Bypass valves open)[insert Group 4 PALISADES NUCLEAR PLANT Page 9 of 10 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS C (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The reactor is critical with power at the POAH MSlV Bypass valves, MO-0501 and MO-0510, are open 0 Vacuum is established on the Main Turbine and the secondary plant is in the process of being started up INITIATING CUES:
The Control Room Supervisor directs you to open the MSlVs per SOP-7, starting at step 7.2.2.c.
PALISADES NUCLEAR PLANT Page 10 of 10 AUGUST 2010
NRC REGION TITLE:
INITIAL LICENSE JOB PERFORMANCE 111 EXAM MEASURE JPM:
ROISRO-I SYS D ALTERNATE PRESSURIZER LEVEL CONTROLLERS CANDIDATE:
EXAM I NER:
JPM RO/SRO-I SYS D j
WA: 01 1A4.01 Importance:
RO: 3.5 SRO: 3.2 JOB PERFORMANCE MEASURE DATA PAGE Task: Alternate Pressurizer Level Controllers Alternate Path: YES - A Pressurizer Level Controller cannot be placed in CASCADE mode requiring restoration of B Pressurizer Level Controller.
Facility JPM #: PL-OPS-PZR-OOGJ WA Statement: Ability to manually operate andlor monitor in the control room: Charging Pump and flow controls Task Standard: Candidate recognizes failure of A PZR level controller and shifts back to B PZR level controller per SOP-1A.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
SOP-I A, Primary Coolant System Validation Time:
15 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
mi nu tes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 15 AUGUST 2010
~
JPM RO/SRO-I SYS D Tools/Equipment/Procedures Needed: SOP-I A, "Primary Coolant System," section 7.2.1.f Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
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 15 AUGUST 2010
JPM RO/SRO-I SYS D EVALUATOR CUE: Provide candidate a working copy of SOP-1A section 7.2.l.f.
ProcStep TASK ELEMENT 1 STANDARD Grade I
I I If alternating..., then PLACE Charging Pumps Control Select Switches for P-55B P-55B Control Select Switch to MANUAL.
Charging Pump (43-12061Ss) and P-55c P-55C Control Select Switch to MANUAL.
Charging Pump (43-1 105/SS) to MANUAL. I s u Comment:
Proc.Step TASK ELEMENT 2 STANDARD Grade VERIFY controller to be selected in I
f-2 I MANUAL.
Comment:
I STANDARD Grade ProcStep TASK ELEMENT 3 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.
Adjusts output signal on LIC-0101A to match transfer.
f.3 output signal on LIC-0101 B for bumpless s u Comment:
PALISADES NUCLEAR PLANT Page 4 of 15 AUGUST 2010
JPM RO/SRO-I SYS D ProcStep TASK ELEMENT 4 STANDARD Grade I
Places Selector Switch I/LRC-O101 to I
f.4 I position for controller to be selected.
I Channel 'A'.
PLACE selector switch 1/LRC-0101 to Proc.Step TASK ELEMENT 5 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.
f'5 Comment:
EVALUATOR CUE: If asked, state that CASCADE CONTROL IS DESIRED.
NOTES: Operator must place the 'A' Level Controller to AUTO prior to going to CASCADE mode of operation.
SOP-IA, section 7.2.1.f.6 is for placing the controller to AUTO.
SOP-IA, section 7.2.1.f.7 is for placing the controller to CASCADE.
IT is permissible not to use step 7.2.1.f.6 to place the controller to AUTO.
The third substep in 7.2.1.f.7 is to place controller in AUTO.
IF Operator uses step 6 of SOP-1A section 7.2.l.f., go to Task Element 6.
If Operator NIA's step 6 of SOP-1A section 7.2.1.f, go to Task Element 9.
Proc.Step TASK ELEMENT 6 STANDARD Grade I
I IF the desired mode of operation is AUTO, I I
Charging and Letdown checked as being Letdown Orifice in service).
THEN PLACE the selected controller in AUTO as follows:
(a) VERIFY Charging and Letdown in operation as appropriate.
appropriate (one Charging Pump and one s u f'6'(a)
I I
I Comment:
PALISADES NUCLEAR PLANT Page 5 of 15 AUGUST 201 0
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 7 STANDARD Grade I
I IF the desired mode of operation is AUTO, THEN PLACE the selected controller in AUTO as follows:
A controller raise/lower pushbuttons adjusted I pointer).
I I
Comment:
Proc.Step TASK ELEMENT 8 STANDARD Grade I
IF the desired mode of operation is AUTO, Depresses the A pushbutton On LIC-0101A to THEN PLACE the selected controller in AUTO as follows:
(c) DEPRESS the A pushbutton on selected controller.
place it in AUTO and notes:
A AUTO light DOES NOT light s u f.6.(c)
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 By Level Controller two ways.
If Operator places selector switch IILRC-0101 to the B position, go to Task Element 12.
If Operator decides to swap back to the B Level Controller using SOP-IA, section 7.2.l.f, go to Task Element 13.
Either way to swap back to By Level Controller is acceptable.
PALISADES NUCLEAR PLANT Page 6 of 15 AUGUST 2010
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 9 STANDARD Grade I
\\
I IF the desired mode of operation is CASCADE, THEN PLACE the selected TYT-0200 TAVE signal verified.
I controller in CASCADE as follows:
I (a) VERIFY expected TAVE signal available f.7 (a)
I from selected TAVEnREF controller (use I TYT-0100, TYT-0200, or TI-01 IO).
s u Comment:
f.7 (b)
TASK ELEMENT 10 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 ( O F ) Pressurizer Level Program."
Comment:
CRlTlCAL STEP - only If polntershwere naB matched 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)
PALISADES NUCLEAR PLANT Page 7 of 15 AUGUST 2010
JPM ROlSRO-I SYS D ProcSCep TASK ELEMENT 11 STANDARD Grade 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:
f7 ()
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 By Level Controller two ways.
If Operator places selector switch IILRC-0101 to the B position, go to Task Element 12.
If Operator decides to swap back to the B Level Controller using SOP-IA, section 7.2.l.f, go to Task Element 13.
Either way to swap back to B Level Controller is acceptable.
ProcStep TASK ELEMENT 12 STANDARD Grade I
s u Place selector switch 1/LRC-0101 to position for controller to be selected.
Pressurizer Level Control Selector Switch 1/LRC-0101 placed to the B position.
Comment:
EVALUATOR CUE:
If CRS notified that 6 Level Controller is in service, CRS acknowledges.
NOTES: B Level Controller in service in already in CASCADE mode.
If Operator performed Task Element 12, go to Task Element 25.
PALISADES NUCLEAR PLANT Page 8 of 15 AUGUST 2010
Proc.Step TASK ELEMENT 14 STANDARD Grade I
VERIFY controller to be selected in MANUAL.
f.2 Depresses M pushbutton on LIC-0101B to place in MANUAL and notes:
s u M MANUAL light ON C CASCADE light OFF Comment:
I I
STANDARD Grade Proc.Step TASK ELEMENT 15 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 s u fm3 Comment:
I CRITtGAL STEP - only If outputs were not matched Proc.Step TASK ELEMENT 16 STANDARD Grade I
Pressurizer Level Control Selector Switch I f-4 I position for controller to be selected.
I 1 ILRC-0101 placed to the B position.
PLACE selector switch 1/LRC-0101 to I
PALISADES NUCLEAR PLANT Page 9 of 15 AUGUST 2010
JPM ROlSRO-I SYS D Proc.Step TASK ELEMENT 17 STANDARD Grade I
IF alternating controllers due to a malfunction of the previously selected channel, THEN PLACE the Pressurizer Heater Control Channel Selector Switch...
Operator MAY reposition Heater Control Channel Selector Switch to Channel 'B.'
fm5 s u Comment:
EVALUATOR CUES:
7 If asked, state that CASCADE CONTROL IS DESIRED.
2 If asked whether to swap Heater Control Channel Selector Switch, reply that this action is not required for this failure.
NOTES: Operator must place the 'By Level Controller to AUTO prior to going to CASCADE mode of operation.
SOP-IA, section 7.2.1.f.6 is for placing the controller to AUTO.
SOP-IA, section 7.2.1.f.7 is for placing the controller to CASCADE.
IT is permissible not to use step 7.2.1.f.6 to place the controller to AUTO.
The third substep in 7.2.1.f.7 is to place controller in AUTO.
IF Operator uses step 6 of SOP-1A section 7.2.l.f., go to Task Element 18.
If Operator NIA's step 6 of SOP-1A section 7.2.1.f, go to Task Element 21.
Charging and Letdown checked as being Letdown Orifice in service).
THEN PLACE the selected controller in AUTO as follows:
(a) VERIFY Charging and Letdown in operation as appropriate.
f'6'(a) appropriate (one Charging Pump and one s u I
Comment:
PALISADES NUCLEAR PLANT Page 10 of 15 AUGUST 2010
JPM RO/SRO-I SYS D PrOeStep TASK ELEMENT 19 STANDARD I
f.6.(b)
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 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).
I pointer).
I Comment:
s u ProcStep TASK ELEMENT 20 STANDARD Grade 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.
f.6.(c)
Comment:
Depresses the A pushbutton on LIC-0101 B to place it in AUTO and notes:
A AUTO light ON M MANUAL light OFF s u ProcStep TASK ELEMENT 21 STANDARD Grade I
I IF the desired mode of operation is I
I CASCADE, THEN PLACE the selected f.7 (a)
Comment:
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).
TYT-0200 TAVE signal verified.
PALISADES NUCLEAR PLANT Page 11 of 15 AUGUST 2010
JPM RO/SRO-I SYS D f.7 (b)
TASK ELEMENT 22 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 I O, 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) s u Comment:
NOTE: Pressurizer level setpoint determined by present Tave. Operator may refer to SOP-1A attachment IO, Tave Pressurizer Level Program.
CRITICAL STEP - only if pointers were not matched Proc.Step TASK ELEMENT 23 STANDARD Grade 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-0101B to place it in AUTO and notes:
A AUTO light ON M MANUAL light OFF.
f7 Comment:
s u Proc.Step TASK ELEMENT 24 STANDARD Grade f.7.(d)
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.
Depresses the C pushbutton pushed on LIC-0101 B to place it in CASCADE and notes:
A AUTO light OFF C CASCADE light ON s u Comment:
PALISADES NUCLEAR PLANT Page 12 of 15 AUGUST 2010
JPM RO/SRO-I SYS D Proc.Step TASK ELEMENT 25 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 - 5 5 ~
Control Select Switch to AUTO.
s u fm8 Comment:
Proc.Step TASK ELEMENT 26 STANDARD Grade I
PLACE the unselected controller in MANUAL, with a 50% output signal.
Operator recognizes A Level Controller is in MANUAL, places the output signal at 50%.
f9 Comment:
EVALUATOR CUE:
If Operator asks if A Level Controller should be left at current output signal, response is place a 50% output signal on the controller.
ProcStep TASK ELEMENT 27 STANDARD Grade I
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 13 of 15 AUGUST 2010
JPM ROISRO-I SYS D SIMULATOR OPERATOR INSTRUCTIONS 0
Reset to IC-17.
0 B Pressurizer Level Controller selected for service.
0 OVRD for LIC-0101A-AUT (A channel AUTO button in) to OFF 0
OVRD for LIC-0101A-MAN (A channel MANUAL button in) to ON PALISADES NUCLEAR PLANT Page 14 of 15 AUGUST 2010
JPM RO/SRO-I SYS D (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Its Friday Day-Shift and per the Plant Daily Schedule, Pressurizer Level Controllers need to be alternated.
INITIATING CUES:
The Control Room Supervisor directs you to alternate Pressurizer Level Controllers per SOP-I A, section 7.2.1.f., with the selected Pressurizer Level Controller in CASCADE.
PALISADES NUCLEAR PLANT Page 15 of 15 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM:
RO/SRO-I SYS E TITLE:
VENT NON4ONDENSIBLE GASES FROM THE REACTOR VESSEL HEAD CAN D I DATE :
EXAM I NER:
c
JPM RO/SRO-I SYS E JOBPERFORMANCEMEASURE DATA PAGE Task:
Alternate Path: NO.
Facility JPM #: PL-OPS-EOP-039J KIA:
007A3.01 Importance:
RO:2.7 SRO:
2.9 Vent Non-Condensible Gases from the Reactor Vessel Head WA Statement:
Ability to monitor automatic operation of the PRTS, including:
Components which discharge to the PRT.
Task Standard:
Non-condensible gases have been vented from Reactor Vessel Head to the Quench Tank.
Preferred Evaluation Location: Simulator -X-In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
EOP Supplement 26, "PCS Void Removal" Validation Time:
15 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
Performance Rating:
Comments:
minutes SAT UNSAT Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 201 0
JPM RO/SRO-I SYS E
~~~~
Tools/Equipment/Procedures Needed:
EOP Supplement 26, "PCS Void Removal" Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A large break LOCA has occurred 0
There are indications of non-condensable gases in the Reactor vessel head The Left Channel Hydrogen Monitor is in service I
INITIATING CUES:
You have been directed to vent the non-condensable gases from the Reactor vessel head, for five to ten minutes, using the preferred method in accordance with EOP Supplement 26, Section 3.0, step 1.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
EVALUATOR CUE: Provide candidate a working copy of EOP Supplement 26 Section 3.0.
Proc.Step TASK ELEMENT 1 STANDARD Grade I
s u 3.1.a Comment:
VALUATOR CUE: If candidate attempts to verify status using SOP-38, provide cue that this has already been performed.
Ensure at least one Hydrogen Monitor in operation.
Provided in Conditions.
3.1.c TASK ELEMENT 2 Open PRV-1072, Vent Path to Quench Tank (preferred method).
STANDARD Obtains Key 11 0.
Places HS-1072 to RESET and then to OPEN.
Verifies that PRV-1072 has opened (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 3 STANDARD I
Vent the Reactor Vessel Head by I -
Obtains Key 105.
Places HS-1067 to RESET and then opening ONE of the following valves for 5-1 0 minutes:
l-to OPEN.
0 PRV-1067 Verifies that PRV-1067 has opened (RED light is ON and GREEN light is OFF)*
-~
PRV-1068 OR -
Obtains Key 106.
Places HS-1068 to RESET and then Verifies that PRV-1068 has opened to OPEN.
(RED light is ON and GREEN light is OFF)*
Comment:
Note:
- not critical Use of either valve is acceptable.
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO/SRO-I SYS E TASK ELEMENT 5 STANDARD I
Secures Reactor Vessel Head venting by closing the appropriate valve which was opened:
0 PRV-1067 (RED light is OFF and GREEN light is Using Key 105 places HS-1067 to CLOSE.
Verifies that PRV-1067 has closed ON)*
OR PRV-1068 Using Key 106 places HS-1068 to I -
CLOSE.
Verifies that PRV-1068 has closed (RED light is OFF and GREEN light is ON)*
s u Comment:
- - not critical Proc.Step TASK ELEMENT 6 STANDARD Grade I
I 3.1.e I -
Using Key 109 places HS-1072 to CLOSE.
(RED light is OFF and GREEN light is ON)*
Ensure closed PRV-1072, Vent Path to Quench Tank.
Verifies that PRV-1072 has closed s u Comment:
- - not critical END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO/SRO-I SYS E SIMULATOR OPERATOR INSTRUCTIONS 0
Reset to IC-17.
0 0
Trip all PCPs.
0 0
INSERT MF RCOI (Large Break LOCA).
Place Left Train Hydrogen Monitor in-service per SOP-38.
Ensure Reactor Head Vent Header pressure (on Panel C-I 1A rear) has bled off.
PALISADES NUCLEAR PLANT Page 7 of 8 AUGUST 2010
JPM RO/SRO-I SYS E (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
A large break LOCA has occurred 0
There are indications of non-condensable gases in the Reactor vessel head The Left Channel Hydrogen Monitor is in service IN ITlATl NG CUES:
You have been directed to vent the non-condensable gases from the Reactor vessel head, for five to ten minutes, using the preferred method in accordance with EOP Supplement 26, Section 3.0, step 1.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS F TITLE:
PLACE A CONTAINMENT RADIATION MONITOR IN SERVICE CAN D I DATE :
EXAM I NER:
JPM RO/SRO-I/SRO-U SYS F JOBPERFORMANCEMEASURE DATA PAGE Task:
Alternate Path: YES - Operate light fails to illuminate when tested Facility JPM #: PL-OPS-RMS-004J WA:
072A4.01 Importance:
RO: 3.0 SRO: 3.3 Operate the Area Radiation Monitoring System 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:
- IO-minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 8 AUGUST 2010
Tools/Equipment/Procedures Needed:
SOP-39, Area Radiation Monitoring System, section 7.4.2 Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Plant is operating at full power.
0 I&C personnel have just completed maintenance on Containment Radiation Monitor RIA-I 805.
CL-39 for RIA-1805 has been completed INITIATING CUES:
The Control Room Supervisor directs you to place Containment Radiation Monitor, RIA-1805, in service per SOP-39, step 7.4.2.
Another operator will answer any front panel alarms.
PALISADES NUCLEAR PLANT Page 3 of 8 AUGUST 2010
JPM RO/SRO-VSRO-U SYS F 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 1 STANDARD Grade I
REFER TO Attachment 3, Checklist CL Candidate determines that this step is N/A per 39, "Area Monitors System Checklist."
I initial conditions.
I 7.4.2.a I Comment:
EVALUATOR CUE If asked, inform candidate that CL-39 has been completed for RIA-1805.
I Grade Proc. Step TASK ELEMENT 2 STANDARD I 7.4.2.b I CHECK operate light illuminated.
Operator recognizes that the OPERATE light is I not illuminated.
I Comment:
Proc. Step TASK ELEMENT 3 STANDARD Grade I
~~~~
Comment:
EVALUATOR CUE: Provide candidate a working copy of SOP-39, Attachment 2.
Proc. Step TASK ELEMENT 4 STANDARD Grade I
PRESS AND HOLD operate light.
Operate light pressed and held s u Comment:
PALISADES NUCLEAR PLANT Page 4 of 8 AUGUST 201 0
JPM RO/SRO-I/SRO-U SYS F Proc. Step I
Proc. Step TASK ELEMENT 5 STANDARD TASK ELEMENT 7 STANDARD Grade 4.1.b I
Operator verifies Orange and Red (Trip 1 and Trip 2) lights not illuminated for RIA-1806, 1807 CHECK other three monitors not tripped.
S U I and 1808.
Comment:
I Grade Proc. Step TASK ELEMENT 6 STANDARD RIA-1805 selector switch placed in CHECK I Dosition and released.
PLACE Selector Switch momentarily to CHECK position AND RELEASE.
s u Comment:
I 4.1.d I RELEASE operate light.
I Operate light is released I s u Comment:
Proc. Step 4.1.e TASK ELEMENT 8 RESET all alarms.
STANDARD Operator resets:
AMBER Trip 1 RED Trip 2 by depressing associated indicating light.
s u Comment:
PALISADES NUCLEAR PLANT Page 5 of 8 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS F Proc. Step TASK ELEMENT 9 STANDARD Grade 4.1.f Comment:
IF 'perate light still not THEN Operator determines this step is not applicable s u because Operate light is illuminated.
DECLARE the associated monitor inoperable AND REFER TO 4.2 below.
Proc. Step TASK ELEMENT 10 STANDARD Grade nla RESET all alarms.
Operator verifies all alarms reset.
s u Comment:
Operator informs Control Room Supervisor that Containment Radiation Monitor CRS Notified s u RIA-1 805 has been placed in service.
Grade Proc. Step TASK ELEMENT I 1 STANDARD 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.
7.4.2.6 Comment:
Proe. Step TASK ELEMENT 12 STANDARD Grade I
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 AUGUST 2010
JPM RO/SRO-VSRO-U SYS F SIMULATOR OPERATOR INSTRUCTIONS 0
Reset to any IC 0
0 Insert OR RIA-1805-G to OFF on Panel C-I 1 rear 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 7 of 8 AUGUST 2010
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
0 The Plant is operating at full power.
0 I&C personnel have just completed maintenance on Containment Radiation Monitor RIA-I 805.
CL-39 for RIA-I805 has been completed INITIATING CUES:
The Control Room Supervisor directs you to place Containment Radiation Monitor, RIA-I 805, in service per SOP-39, step 7.4.2.
Another operator will answer any front panel alarms.
PALISADES NUCLEAR PLANT Page 8 of 8 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS H TITLE: TEMPORARILY SECURE SHUTDOWN COOLING FLOW CAN D I DATE :
EXAMINER:
JPM: RO/SRO-I SYS H JOB PERFORMANCE MEASURE DATA PAGE Task:
Temporarily Secure Shutdown Cooling Flow Alternate Path: NO Facility JPM #: NEW WA: 005A4.01 Importance:
RO: 3.6 SRO: 3.4 K/A Statement: Ability to manually operate andlor monitor in the control room: Controls and indications for RHR pumps Task Standard: Shutdown Cooling secured per SOP-3 Preferred Evaluation Location: Simulator X In Plant Preferred Evaluation Method:
Perform
-X-Simulate
References:
Validation Time:
20 minutes Time Critical:
NO SOP-3, Safety Injection and Shutdown Cooling System Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 12 AUGUST 2010
Tools/Equipment/Procedures Needed:
0 SOP-3, "Safety Injection and Shutdown Cooling System, "sections 7.3.6 and 7.3.4 Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Plant is in the middle of a 45 day refueling outage.
0 P-67B is the LPSl Pump in service with PCS temperature approximately 108°F 0
Plant is in solid-plant pressure control: another Operator will control PCS pressure during this evolution Shutdown Cooling is expected to be secured for 30 minutes The maximum expected PCS heatup after Shutdown Cooling is secured is 20"F/hr PCS and Pressurizer parameters are being monitored via performance of PO-2, "PCS HeatuplCooldown Operations" All GOP-14 requirements are met for this evolution with all Management signoffs complete INITIATING CUES:
The Control Room Supervisor directs you to temporarily secure Shutdown Cooling flow per SOP-3, Section 7.3.6. You are further directed to have MO-3014, Loop 26 LPSl Injection Valve, to be the valve that is left in the throttled position when performing step 7.3.6.c.
PALISADES NUCLEAR PLANT Page 3 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H EVALUATOR CUE: Provide candidate a working copy of SOP-3, Section 7.3.6 7.3.6.a TASK ELEMENT I 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.
Comment:
STANDARD Given in the Initial Conditions TASK ELEMENT 2 1
7.3.6.b 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 Heatup/Cooldown Operations."
Comment:
STANDARD Grade Determines that this step is being met.
(PO-2 performance given in initial conditions) s u PALISADES NUCLEAR PLANT
~
Page 4 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 3 STANDARD I
Grade 7.3.6.c Prac. Step TASK ELEMENT 4 STANDARD Shutdown Cooling flow to approximately PERFORM Section 7.3.4 to reduce total 300 to 500 arm.
Branches to section 7.3.4 of SOP-3 I
Grade I s u 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 HeatuD/Cooldown ODerations."
target temperature, THEN ENSURE pcs Comment:
Evaluator provides a Working Copy of SOP-3, Section 7.3.4 EVALUATOR CUE: Another Operator will control PCS pressure during this evolution.
Determines that this step is being met.
s u (PO-2 performance given in initial conditions)
Proc. Step TASK ELEMENT 5 STANDARD 7.3.4.a Grade Proc. Step TASK ELEMENT 6 STANDARD Grade 7.3.4.b 7.3.4x Comment:
s u DETERMINE desired total Shutdown Cooling flow.
previous step 7.3.6.c).
Determines 300-500 gpm applies (from IF PCS level is greater than 643'4" 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)
I PALISADES NUCLEAR PLANT Page 5 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Pmn Step TASK ELEMENT 7 STANDARD Grade I
s u IF Shutdown Cooling flow is to be throttled below 2810 gpm,...
Determines that sub-steps 1, 2, and 3 do not apply.
7m3.4md Comment:
EVALUATOR CUE: CRS directs that sub-step 3 is not applicable for this evolution.
7.3.4.d TASK ELEMENT 8 IF Shutdown Cooling flow is to be throttled below 2810 gpm,...
- 4. IF PCS recirculation flow rate is less than the minimum required by Technical Specifications LCO 3.4.7, LCO 3.4.8, LCO 3.9.4, or LCO 3.9.5, THENCLOSEANDDANGERTAG MV-CVC2162, Primary Makeup Water Supply Stop within one hour.
STANDARD m Notifies CRS of need to Danger Tag MV-CVC2162.
s u Comment:
EVALUATOR CUE IF informed as CRS of need to hang Danger Tag on MV-CVC2162:
acknowledge and inform Operator that this was already completed by another operator during GOP-74.
Proc. Step TASK ELEMENT 9 STANDARD 7.3.4.d IF Shutdown Cooling flow is to be throttled below 2810 gpm,...
- 5. MAINTAIN General Operating Procedure GOP-14, "Shutdown Notifies CRS of need to maintain GOP-14 requirements.
I Cooling Operations," requirements. I Comment:
EVALUATOR CUE: IF informed as CRS of need to maintain GOP-74 requirements:
acknowledge.
PALISADES NUCLEAR PLANT Page 6 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H Proc. Step TASK ELEMENT 10 STANDARD Grade 7.3.4.e I
DETERMINE required status of..
Determines that maximum of one throttled/open LPSl Injection Valve applies. (per initiating cue this will be MO-3014) s u
~
~~~
Comment:
Checks FIC-0306 is in MANUAL.
7.3.4.f TASK ELEMENT 12 ADJUST Shutdown Cooling flow as follows:
- 2. SLOWLY OPERATE LPSl Injection Valves to establish status determined in Step 7.3.4e.
STANDARD SLOWLY operates each of the four LPSl Injection Valves (one at a time) until only one (MO-3014) LPSl Injection Valve is throttled open and SDC flow is 300 to 500 gpm.
0 MO-3010 closed 0
MO-3012 closed MO-3008 closed 0
MO-3014 throttled open s u Comment:
PALISADES NUCLEAR PLANT Page 7 of 12 AUGUST 201 0
JPM: RO/SRO-I SYS H Pmc. Step TASK ELEMENT 13 ADJUST Shutdown Coolina flow as follows:
- 3. BALANCE flow between in use LPSl Injection Loops to desired Total Shutdown Cooling flow determined in 7.3.4.f Comment:
STANDARD
- Grade, Determines this step is not applicable.
s u Proc, step TASK ELEMENT 14 ADJUST Shutdown Cooling flow as follows:
- 4. If necessary:
(a) THROTTLE CV-3025, SDC Hx Outlet to maintain desired 7.3.4.f Comment:
Determines this step is not applicable.
s u 7.3.4.f TASK ELEMENT 15 ADJUST Shutdown Coolina 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 Comment:
PALISADES NUCLEAR PLANT Page 8 of 12 AUGUST 201 0
JPM: RO/SRO-I SYS H Proc. Step 7.3.6.d TASK ELEMENT 16 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.
STANDARD 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 Comment:
EVALUATOR NOTE:
Procedure written for one person operation, this is a two person operation, it is not CRITICAL for the co-ordination from a JPM standpoint.
TASK ELEMENT 17 WHEN Total Shutdown Cooling flow has been reduced to approximately 300 to 500 gpm, THEN PERFORM the following:
- 2. CLOSE CV-3055, SDC Hx Inlet.
Comment:
STANDARD HS-3055A to CLOSE with key.
(Key may be removed or left in keyslot)
I been reduced to amroximatelv 300 to I
I 500 gpm, THEN PERFORM the following:
7.3.6.d I P-67B STOPPED I
- 3. STOP the operating LPSl Pump.
s u Comment:
PALISADES NUCLEAR PLANT Page 9 of 12 AUGUST 2010
Proc. Step TASK ELEMENT I 9 CRS NOTIFIED SDC temporarily secured NOTIFY the CRS that Shutdown Cooling has been temporarily secured per SOP-3, Section 7.3.6.
s u JPM: RO/SRO-I SYS H STANDARD Grade 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:
MO-3015
. MO-3016 MO-3189 MO-3198
. MO-3190 m MO-3199 0
Ensure Caution Tags on CV-3057 and CV-3031 PALISADES NUCLEAR PLANT Page 11 of 12 AUGUST 2010
JPM: RO/SRO-I SYS H (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is in the middle of a 45 day refueling outage.
0 P-67B is the LPSl Pump in service with PCS temperature approximately 108°F Plant is in solid-plant pressure control: another Operator will control PCS pressure during this evolution Shutdown Cooling is expected to be secured for 30 minutes The maximum expected PCS heatup after Shutdown Cooling is secured is 20"F/hr PCS and Pressurizer parameters are being monitored via performance of PO-2, "PCS Heatup/Cooldown Operations" All GOP-14 requirements are met for this evolution with all Management signoffs complete INITIATING CUES:
The Control Room Supervisor directs you to temporarily secure Shutdown Cooling flow per SOP-3, Section 7.3.6. You are further directed to have MO-3014, Loop 2B LPSl Injection Valve, to be the valve that is left in the throttled position when performing step 7.3.6.c.
PALISADES NUCLEAR PLANT Page 12 of 12 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYSTEM I TITLE: SECURE FROM A WASTE GAS RELEASE CANDIDATE:
EXAM I NER:
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 WA Statement: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Isolation of waste gas release tanks Secure from Waste Gas Release Task Standard: T-68B Waste Gas Decay Tank release secured Preferred Evaluation Location: Simulator In Plant
-X-Preferred Evaluation Method:
Perform Simulate X
References:
Validation Time:
10 minutes Time Critical:
NO SOP-I 8A, Radioactive Waste System - Gaseous Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 6 AUGUST 2010
Tools/Equipment/Procedures Needed:
0 SOP-I 8A, "Radioactive Waste System - Gaseous, "Section 7.5 Also see Simulator Operator Instructions (last page of this document).
READ TO CANDIDATE DIRECTION TO CANDIDATE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
0 The Plant is at 48% power 0
T-68B Waste Gas Decay Tank batch release is in progress 0
It has been determined that the batch release must be secured INITIATING CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 3 of 6 AUGUST 2010
JPM: RO/SRO-I/SRO-U SYS I EVALUATOR CUE: Provide candidate a working copy of SOP-I8A, Section 7.5, step nn Proc. Step TASK ELEMENT 1 SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge
. MV-WG719, T-68A, B & C Outlet nn.1 Header Valves T-68NB/C:
Isolation STANDARD MV-WG719 CLOSED s u -
Comment:
EVALUATOR NOTE: Task Elements I and 2 can be performed in any order since they are bulleted substeps Proc. Step TASK ELEMENT 2 STANDARD Grade I
I I
I SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge
. MV-WG718A, T-I 01 A, B & C Outlet nn.1 Header Valves T-68NBIC:
MV-WG718A CLOSED Isolation Comment:
EVALUATOR NOTE: Task Elements 1 and 2 can be performed in any order since they are bulleted substeps Proc. Step TASK ELEMENT 3 CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
nn.2.a
.PLACE in CLOSE position HS-1123, Waste Gas Decay Tanks Discharge, at C-40 STANDARD 3 HS-1123 in CLOSE s u Comment:
EVALUATOR CUE: CV-1123 is closed, the green light is lit.
PALISADES NUCLEAR PLANT Page 4 of 6 AUGUST 2010
JPM: RO/SRO-VSRO-U SYS I Proc. Step TASK ELEMENT 4 STANDARD Grade I
nn.2.b CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
Gas Discharge To Stack HIC-1123 INDICATING 0 psi
.SET to zero (0) psi HIC-1123, Waste Comment:
EVALUATOR CUE: HIC-1123 indicates 0 psi s u -
Proc. Step nn.3 TASK ELEMENT 5 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-l120B, 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-11208) s u Proc. step TASK ELEMENT 6 STANDARD Grade I
I s u NOTIFY CRS that WGDT T-68B release CRS WGDT T-68B SECURED secured I
n/a I Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 5 of 6 AUGUST 2010
~
JPM: RO/SRO-I/SRO-U SYS I (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
The Plant is at 48% power 0
T-68B Waste Gas Decay Tank batch release is in progress 0
It has been determined that the batch release must be secured INITIATING CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-I8A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 6 of 6 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE
JPM: RO/SRO-I SYS J JOB PERFORMANCE MEASURE Task:
Establish/control alternate Auxiliary Feedwater methods IAW EOP Supplement 19 Alternate Path: YES - Turbine Driver K-8 is found to be unlatched and reset lever operation is required to complete task.
Facility JPM #: PL-OPS-ONP-OIOJ KIA: 061A2.04 Importance:
RO: 3.4 SRO: 3.8 WA Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct; control; or mitigate the consequences of those malfunctions or operations: pump failure or improper operation Task Standard: AFW Pump P-8B is operating with steam supplied via CV-0522BI K-8 Steam Supply from E-50A, in local control Preferred Evaluation Location: Simulator In Plant
-X-Preferred Evaluation Method:
Perform Simulate
-X-
References:
ONP-25.2, Alternate Safe Shutdown Procedure EOP Supplement 19, Alternate Auxiliary Feedwater Methods Validation Time:
15 minutes Time Critical:
NO Candidate:
Time Start:
Time Finish:
Performance Time:
minutes Performance Rating:
SAT UNSAT Comments:
Examiner:
Date:
Signature PALISADES NUCLEAR PLANT Page 2 of 11 AUGUST 201 0
JPM: RO/SRO-I SYS J I
READ TO CANDIDATE Tools/Equipment/Procedures Needed:
I DIRECTION TO CANDIDATE:
EOP Supplement 19, Alternate Auxiliary Feedwater Methods, section 4, P-8B Normal Steam Supply From A S/G including page 21 of supplement 19 I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
AFW flow control valves for P-8BI AFW Pump, have been verified closed.
Buses I C and 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.
PALISADES NUCLEAR PLANT Page 3 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J EVALUATOR CUE:Provide candidate a working copy of EOP Supplement I 9 I
Grade STANDARD Proc. Step TASK ELEMENT 1 OPEN HS-O522B, K-8 Normal Steam Supply, from one of the following prioritized locations...
4.0.1 Determines that this step is not applicable s u Comment:
I EVALUATOR CUE:lf asked if CV-0522B can be operated from either the Control Room or C-150 Panel, report that CV-05228 cannot be remotely operated Proc. Step TASK ELEMENT 2 STANDARD Grade CLOSE the following valves:
Simulates or describes CLOSING by turning the handwheel clockwise:
MV-CA377, air supply to CV-0522B s u
-MV-CA377, air supply to CV-0522B mMV-N2/268, nitrogen supply to CV-0522B 4m0.2.a MV-N2/268, nitrogen supply to CV-0522B Comment:
EVALUATOR CUE: The valves are closed Proc. Step TASK ELEMENT 3 STANDARD Grade I
MANUALLY CLOSE CV-O522B, 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 4.0.2.b.l manual override shaft Comment:
EVALUATOR CUE: Provide page 21 of EOP Supplement 19 EVALUATOR CUE: The coupling is unscrewed from the shaft NOTE: A ladder may be used to access the coupling PALISADES NUCLEAR PLANT Page 4 of 11 AUGUST 201 0
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 4 STANDARD MANUALLY CLOSE CV-O522B, K-8 Normal Steam Supply, as follows:
4.0-2-b-2.
TURN handwheel clockwise until the top of the actuator shaft is exposed sufficiently to engage the coupling Simulates or describes TURNING handwheel clockwise until manual override shaft is exposed Comment:
EVALUATOR CUE: The manual shaft is exposed s u Proc. Step TASK ELEMENT 5 STANDARD Grade I
INSERT the fork of the coupling all the way Simulates or describes INSERTING coupling all the way onto shaft onto actuator shaft 4m02b3 Comment:
NOTE: EOP Supplement 79, page 27 has a labeled diagram of CV-05226 EVALUATOR CUE: The coupling is all the way onto the shaft Proc. Step TASK ELEMENT 6 STANDARD Grade I I Simulates or describes REMOVING the lockwire I S U REMOVE lockwire from MV-FW356, CV-0522B Bonnet Isolation Comment:
EVALUATOR CUE: The lockwire is removed from MV-FW356, CV-05226 Bonnet Isolation PALISADES NUCLEAR PLANT Page 5 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 7 STANDARD Grade I
Simulates or describes OPENING MV-FW356 by TURNING handle 90 degrees (places it "in-line" with the turbine/piping).
S U OPEN MV-FW356, CV-0522B Bonnet Isolation 4.0.2.b.5 Comment:
EVALUATOR CUE: MV-FW356, CV-0522B Bonnet Isolation handle is in line with the tubing Proc. Step TASK ELEMENT 8 STANDARD Grade Simulates or describes checking valve closed by TURNING handwheel in the clockwise direction S U (given in the initial conditions)
CLOSE CV-O522B, K-8 Normal Steam Supply, using the handwheel 4'0'2'bA Comment:
EVALUATOR CUE: If asked about the position of CV-O522B, report that it is closed Proc. Step TASK ELEMENT 9 STANDARD Orade I
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 level (can NOT slip a sheet of paper between),. Refer to Figure 1 (Page Determines that Turbine Driver is NOT RESET S U Comment:
EVALUATOR CUE: Provide EOP Supplement 79, page 20 EVALUATOR CUE: The Knife edge of resetting lever is hanging down and not in contact with the hand trip lever
I--
NOTE: Alternate Path begins here and is covered in task elements 10 and 11-------
PALISADES NUCLEAR PLANT Page 6 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 10 STANDARD Grade I
CHECK Turbine Driver K-8 is NOT latched, THEN RELATCH as follows:
Simulates or describes verifying that CV-05228 4.0.2.c.2.a ENSURE CLOSED CV-05228, K-8 is Normal Steam Supply s u Comment:
EVALUATOR CUE: If asked about the position of CV-O522B, report that it is closed Proc. step TASK ELEMENT 11 STANDARD CHECK Turbine Driver K-8 is NOT latched, THEN RELATCH as follows:
Simulates or describes PULLING UP on the Auxiliary Reset lever Until the lever iS in Contact with the knife edge 4.0.2.c.2.b RESET the overspeed trip lever on Turbine Driver K-8 using the Auxiliary Reset lever s u Comment:
EVALUATOR CUE: The knife edge of resetting lever is in contact with the hand trip lever Proc. Step TASK ELEMENT 12 STANDARD Orade 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 PALISADES NUCLEAR PLANT Page 7 of 11 AUGUST 201 0
JPM: RO/SRO-I SYS J Proc. Step TASK ELEMENT 13 STANDARD Grade I
4.0.2.d Simulates or describes OPENING MV-FW688, PI-0590 root valve by TURNING the handwheel l s u l I counter clockwise OPEN MV-FW688, PI-0590 root valve Comment:
EVALUATOR CUE: Valve is open 4.0.2.e TASK ELEMENT 14 SLOWLY THROTTLE OPEN CV-0522B to maintain between 200 and 250 psig steam pressure on any of the following:
. PI-0590
. PI-0521A PI-0521 B STANDARD Simulates or describes OPENING CV-0522B with the hand operator by TURNING handwheel counter clockwise s u Comment:
EVALUATOR CUE:Steam flow noise can be heard, CV-0522B, K-8 Normal Steam Supply indicates off its full closed position, and pressure on gauge is rising.
Proc. Step TASK ELEMENT 15 STANDARD Grade I
l s u l VERIFIES PI-0590 OR PI-0521 B reading 4'0m2me I between 200 and 250 psig I between 200 to 250 psig CHECK PI-0590 OR PI-0521 B reading Comment:
EVALUATOR CUE: PI-0590 OR PI-05216 indicates 235 psis and stable PALISADES NUCLEAR PLANT Page 8 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J
a Proc. Step TASK ELEMENT 16 STANDARD Grade I
s u Notify CRS that AFW Pump, P-8B is operating CRS NOTIFIED that AFW Pump, P-8B is operating with CV-0522B opened manually END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 AUGUST 201 0
JPM: RO/SRO-I SYS J SIMULATOR OPERATOR INSTRUCTIONS 0
N/A PALISADES NUCLEAR PLANT Page 10 of 11 AUGUST 2010
JPM: RO/SRO-I SYS J
~
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
AFW flow control valves for P-8BI AFW Pump, have been verified closed.
Buses 1 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.
PALISADES NUCLEAR PLANT Page 11 of 11 AUGUST 2010
NRC REGION 111 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE I
JPM: RO/SRO-l/SRO-U SYS K TITLE:
REDUCE STATION BATTERY #I LOADING CANDIDATE:
EXAM I NER:
JPM RO/SRO-VSRO-U SYS K JOB PERFORMANCE MEASURE
~
Task:
Reduce Station Battery Loading Alternate Path: NO Facility JPM #: PL-OPS-EOP-021 J K/A:
063A1.01 Importance:
RO:
2.5 SRO:
3.3 K/A Statement: Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate.
Task Standard: Station Battery #I loading reduced to 30 min.
S 832 amps 1401 amps 2 222 amps I
157 amps STANDARD Operator determines the following maximum acceptable Station Battery No. 1 discharge current is I 157 amps P
1.0.4.a TASK ELEMENT 4 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 D11-2 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 poJ acceptable Simulates OPENING breakers on panels D11-1 and Dll-2.
Comment:
EVALUATOR CUE:lf candidate attempts to refer to drawing E-35 for valve failure modes, EVALUATOR CUE:As each breaker is opened, cue operator that breaker indicates OFF.
inform candidate that the Control Room has completed this.
Battery discharge current will lower by only 2 or 3 amps for each breaker.
PALISADES NUCLEAR PLANT Page 5 of 9 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS K Proc. Step TASK ELEMENT 5 1.0.4.b WHEN the above breakers are open, THEN RECORD the following:
- 1) Time:
- 2) Station Battery No 1 discharge current: EAI-45:
amps STANDARD Operator performs the following:
RECORDS present time Depresses Lower Scale Reading push button I
Reads inner scale of ammeter RECORDS Battery No. 1 discharge current Comment:
EVALUATOR CUE:lf candidate pushes inner scale pushbutton, then use pointer and place on Station Battery No. 1 ammeter, EA/-45, to indicate 170 AMPS out on inner scale.
place on Station Battery No. I ammeter, AI-45, to indicate 170 AMPS out on outer scale.
EVALUATOR CUE:lf candidate does NOT push inner scale pushbutton, use pointer and Proc. Step TASK ELEMENT 6 1.0.4.c 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 72-1 7 (D-I 0)
Operator performs the following:
Determines that discharge current is still Simulates OPENING breaker 72-17 on D-not acceptable s u 10 Comment:
EVALUATOR CUE: Provide cue that breaker indicates OFF. Battery discharge current should lower by approximately 40 amps.
PALISADES NUCLEAR PLANT Page 6 of 9 AUGUST 2010
JPM RO/SRO-I/SRO-U SYS K IF Battery No discharge current continues to be greater than the acceptable limits of Step 1.3, THEN PERFORM the following...
1.0.4.e Proc. Step TASK ELEMENT 7 STANDARD Operator determines that this step is N/A because Battery No. 1 discharge current is s u
<I 57 amps 1.0.4.d Operator informs Control Room that task is complete nla WHEN the above breaker is open, THEN RECORD the following:
- 1) Time:
- 2) Station Battery No 1 discharge current: EAI-45:
amps s u Control Room informed Operator performs the following:
RECORDS present time Depresses Lower Scale Reading push Reads inner scale of ammeter button RECORDS Battery No. 1 discharge current Comment:
EVALUATOR CUE:lf candidate pushes -
inner scale pushbutton, then use pointer and place on Station Battery No. I ammeter, EA/-45, to indicate 135 AMPS out on inner scale.
place on Station Battery No. 1 ammeter, EA/-45, to indicate 135 AMPS out on outer scale.
EVALUATOR CUE:lf candidate does NOT push inner scale pushbutton, use pointer and Proc. step TASK ELEMENT 8 STANDARD Grade I
Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade I
~~
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 AUGUST 2010
0 N/A PALISADES NUCLEAR PLANT JPM RO/SRO-VSRO-U SYS K SIMULATOR OPERATOR INSTRUCTIONS Page 8 of 9 AUGUST 201 0
JPM RO/SRO-VSRO-U SYS K I
(TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
IN ITlAL CONDITIONS:
All AC power is lost It is approximately 35 minutes after the loss of all AC power 1-1 and 1-2 Diesel Generators will poJ start INITIATING CUES:
During performance of EOP-3.0, Electrical Emergency Recovery, Step 19, the CRS directs you to ensure Station Battery #I discharge is within limits per EOP Supplement 7.
PALISADES NUCLEAR PLANT Page 9 of 9 AUGUST 2010