ML13070A468
| ML13070A468 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/12/2013 |
| From: | Walton R NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| Download: ML13070A468 (109) | |
Text
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO SYS A TITLE: TERMINATE FROM EMERGENCY BORATION CANDIDATE:
EXAMINER:
JPM SYSTEM A JOB PERFORMANCE MEASURE DATA PAGE Task: Align Charging Pump Suction to Safety Injection Refueling Water Tank Alternate Path: NO Facility JPM #: BANK K/A: 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: Emergency Boration secured with Charging Pump suction lined up to the SIRW Tank and all Charging Pumps operating.
Preferred Evaluation Location: Simulator __X__ In Plant _____
Preferred Evaluation Method: Perform __X__ Simulate _____
References:
EOP-4.0, Loss of Coolant Accident Recovery EOP Supplement 40, Charging Pump Suction Alignment 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 8 OCTOBER 2012
JPM SYSTEM A EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
EOP Supplement 40, Charging Pump Suction Alignment EOP-4.0, Loss of Coolant Accident Recovery, step 22.
Also see Simulator Operator Instructions (later 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 Loss of Coolant Accident has occurred
- SIS has occurred
- PCS boron concentration has been verified greater than the required concentration per EOP Supplement 35, Determination of Emergency Boration Requirements INITIATING CUES:
- During performance of EOP-4.0, Loss of Coolant Accident Recovery, Step 22, the Control Room Supervisor directs you to secure Emergency Boration per EOP Supplement 40 aligning Charging Pump suction to the SIRWT with all Charging Pumps left operating.
PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012
JPM SYSTEM A EVALUATOR CUE: Provide operator a Working Copy of EOP Supplement 40 and EOP-4.0 Step 22.
Proc. Step TASK ELEMENT 1 STANDARD Grade Open Charging Pumps Suction From MO-2160 handswitch taken to the open position 2.0.1 S U SIRWT Valve, MO-2160 (valve opens).
Comment:
EVALUATOR NOTE: MO-2160 will take a little time to stroke open.
CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade Stop the Boric Acid Pumps.
P-56A AND P-56B handswitches to the trip 2.0.2 P-56A S U position (Pumps off).
P-56B Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade Close the following valves:
Boric Acid Pump Feed Valve, MO-2140 MO-2140, MO-2169, and MO-2170 2.0.3 Gravity Feed Valves handswitches taken to the closed position S U (valves close)
MO-2169 MO-2170 Comment:
EVALUATOR NOTE: MO-2140, MO-2169, and MO-2170 will take a little time to stroke closed.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012
JPM SYSTEM A Proc. Step TASK ELEMENT 4 STANDARD Grade Ensure closed Charging Pumps Suction 2.0.4 MO-2087 verified closed. S U VCT Outlet Valve, MO-2087.
Comment:
Proc. Step TASK ELEMENT 5 STANDARD Grade Operate each Charging Pump for at least Determines that all Charging pumps will be left in-2.0.5 S U five minutes. service (given in initial conditions).
Comment:
EVALUATOR CUE: Inform Operator that five minutes have elapsed.
Proc. Step TASK ELEMENT 6 STANDARD Grade WHEN each pump has been operated at Determines that all Charging pumps will be left in-2.0.6 S U least five minutes THEN . service (given in initial conditions).
Comment:
EVALUATOR CUE: Inform Operator to leave all three Charging Pumps in service.
Proc. Step TASK ELEMENT 7 STANDARD Grade EOP Supplement 40 is Signed, n/a Dated/Timed EOP Supplement 40 Signed, Dated/Timed S U Comment:
PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012
JPM SYSTEM A Proc. Step TASK ELEMENT 8 STANDARD Grade Notify CRS of the completion of EOP n/a Supplement 40 CRS notified that EOP Supplement 40 complete S U Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012
JPM SYSTEM A SIMULATOR OPERATOR INSTRUCTIONS
- Use IC 17 (100% power)
- Enter malfunction RC04 at 100%
- Trip Reactor and carry out all EOP 1.0 immediate actions
- Place Letdown Orifice Stop valves to close
- Allow SIAS to occur automatically
- Allow at least 10% level reduction in each BAST PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012
JPM SYSTEM A CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A Loss of Coolant Accident has occurred
- SIS has occurred
- PCS boron concentration has been verified greater than the required concentration per EOP Supplement 35, Determination of Emergency Boration Requirements INITIATING CUES:
- During performance of EOP-4.0, Loss of Coolant Accident Recovery, Step 22, the Control Room Supervisor directs you to secure Emergency Boration per EOP Supplement 40 aligning Charging Pump suction to the SIRWT with all Charging Pumps left operating.
PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012
PALISADES INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS B TITLE: PERFORM POST RAS ACTIONS CANDIDATE:
EXAMINER:
JPM SYSTEM B JOB PERFORMANCE MEASURE DATA PAGE Task: Perform Post RAS actions in accordance with EOP Supplement 42 Alternate Path: NO Facility JPM #: BANK K/A: 013A4.03 Importance: RO: 4.5 SRO: 4.7 K/A Statement: Ability to manually operate and/or monitor in the control room: ESFAS initiation Task Standard: Post RAS actions complete Preferred Evaluation Location: Simulator __X__ In Plant _____
Preferred Evaluation Method: Perform __X__ Simulate _____
References:
EOP-4.0, Loss of Coolant Accident Recovery EOP Supplement 42, Pre and Post RAS Actions Validation Time: 30 minutes Time Critical: NO Candidate:
Time Start: ________ Time Finish: ________
Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______
Comments:
Examiner: _______________________________ Date: ______________
Signature PALISADES NUCLEAR PLANT Page 2 of 13 OCTOBER 2012
JPM SYSTEM B EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
- EOP-4.0, Loss of Coolant Accident Recovery, Step 52 Also see Simulator Operator Instructions (later 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.
- The Plant has been tripped and EOP-1.0, Standard Post Trip Actions, have been completed.
- EOP-4.0, Loss of Coolant Accident Recovery, has been entered.
- SIS and CHP have actuated.
- Pre-RAS actions have been taken per EOP Supplement 42.
- RAS is imminent.
INITIATING CUES:
- During performance of EOP-4.0 step 52, the Control Room Supervisor directs you to perform Post-RAS actions in accordance with EOP Supplement 42, step 2.0 when RAS occurs.
PALISADES NUCLEAR PLANT Page 3 of 13 OCTOBER 2012
JPM SYSTEM B EVALUATOR CUE: Provide candidate a Working Copy of EOP Supplement 42 and EOP-4.0 Step 52 Proc. Step TASK ELEMENT 1 STANDARD Grade VERIFY P-67A tripped (red light OFF, green light ON).
WHEN SIRWT level lowers to below 2%,
2.1.a THEN PERFORM ALL of the following AND S U
- a. ENSURE BOTH LPSI Pumps trip VERIFY P-67B did not trip (red light ON, green light OFF).
Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade WHEN SIRWT level lowers to below 2%,
THEN PERFORM ALL of the following
- a. ENSURE BOTH LPSI Pumps trip 2.1.a.1 1) IF any LPSI Pump failed to trip, Handswitch 152-111 CS TAKEN to TRIP position S U THEN PERFORM the following:
a) TRIP the operating LPSI Pump:
P-67B (152-111 CS)
Comment:
EVALUATOR NOTE: Pump will not trip CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 3 STANDARD Grade WHEN SIRWT level lowers to below 2%,
THEN PERFORM ALL of the following
- a. ENSURE BOTH LPSI Pumps trip
- 1) IF any LPSI Pump failed to trip, THEN PERFORM the following:
Directs Auxiliary Operator to TRIP P-67B locally 2.1.a.1 S U b) IF LPSI pump failed to trip using at it breaker (152-111) the previous step, THEN TRIP the operating LPSI pump at the bus:
152-111, Low Press Safety Inject Pump P-67B Breaker Comment:
EVALUATOR CUE: If contacted as AO to trip P-67B locally at its bus, cue that pump 67B will not trip.
Proc. Step TASK ELEMENT 4 STANDARD Grade For P-67B operating from off site power, SIMUTANEOUSLY PERFORM the following for the operating LPSI Pump:
HOLD 152-107, D/G 1-1 to Bus 1C in TRIP AND CONTINUE to hold in TRIP HOLD breaker 152-107 (D/G 1-1 To bus 1C) in for at least 30 seconds after the following TRIP and CONTINUE to hold in TRIP for at least 2.1 c.iv S U breaker is OPENED 30 seconds after breaker 152-105 (Station Power Transf No 1-2 Bkr) is OPENED OPEN either of the following breakers supplying the bus 152-105, Station Power Trans 1-2 Breaker Comment:
EVALUATOR NOTE: Bus 1C will de-energize and Diesel Generator 1-1 will auto start but its output breaker (152-107) will not close.
EVALUATOR CUE: If asked about tripping 1-1 D/G, cue that another Operator will trip the D/G.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 5 STANDARD Grade VERIFIED OPEN both Containment Sump CHECK OPEN BOTH Containment Sump Isolation valves:
Isolation Valves:
2.1.b
- CV-3030 (red light ON, green light OFF). S U CV-3030
- CV-3029 (red light ON, green light OFF).
CV-3029 Comment:
Proc. Step TASK ELEMENT 6 STANDARD Grade VERIFIED CLOSED both SIRWT Isolation ENSURE CLOSED BOTH SIRWT valves:
Isolation Valves:
2.1.c.
- CV-3031 (red light OFF, green light ON). S U CV-3031 (Key: 149)
- CV-3057 (red light OFF, green light ON).
CV-3057 (Key: 150)
Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade VERIFIED CLOSED both SI Pump Minimum flow ENSURE CLOSED BOTH SI Pump Stop Valves:
Minimum Flow Stop Valves:
2.1.d
- CV-3027 (red light OFF, green light ON). S U CV-3027 (Key: 28)
- CV-3056 (red light OFF, green light ON).
CV-3056 (Key 27)
Comment:
PALISADES NUCLEAR PLANT Page 6 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 8 STANDARD Grade VERIFIED OPEN both CCW Hx Service Water ENSURE OPEN both CCW Hx Service Outlet valves:
Water Outlet valves:
2.1.e
- CV-0826 (red light ON, green light OFF). S U CV-0826
- CV-0823 (red light ON, green light OFF).
CV-0823 Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade ENSURE CLOSED both CCW Hx TCVs: VERIFIED CLOSED both CCW Hx TCVs:
2.1.f CV-0822 CV-0822 S U CV-0821 CV-0821 Comment:
EVALUATOR NOTE: Both CCW Hx TCVs indicate closed when green light is lit above HS-0828.
Proc. Step TASK ELEMENT 10 STANDARD Grade VERIFIES one Containment Spray Pumps ENSURE HPSI Subcooling Alignment: (P-54A) operating (red light ON, green light OFF).
2.1.g 1) At least one Containment Spray Pump S U AND operating for each operating HPSI Pump VERIFIES one HPSI pump operating. (P-66A).
Comment:
PALISADES NUCLEAR PLANT Page 7 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 11 STANDARD Grade ENSURE HPSI Subcooling Alignment:
- 2) VERIFY OPEN HPSI Subcooling VERIFIES OPEN CV-3071 (red light ON, green 2.1.g S U Valve for any operating HPSI Pump light OFF).
CV-3071 Comment:
Proc. Step TASK ELEMENT 12 STANDARD Grade IF any HPSI pump is operating with 2.1.h Determines that this step is not applicable. S U subcooling valve closed Comment:
Proc. Step TASK ELEMENT 13 STANDARD Grade IF 2 or 3 Containment Spray Pumps are operating, THEN ENSURE both 2.1.i Determines that this step is not applicable. S U Containment Spray Valves are in the THROTTLE position.
Comment:
Proc. Step TASK ELEMENT 14 STANDARD Grade IF one Containment spray valve is CLOSED 2.1.j Determines that this step is not applicable. S U AND one is throttled Comment:
PALISADES NUCLEAR PLANT Page 8 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 15 STANDARD Grade IF only one Containment Spray Pump is operating, THEN; 2.1.k VERIFIES one HPSI pump OPERATING (P-66A) S U
- 1) ENSURE only one HPSI Pump operating Comment:
Proc. Step TASK ELEMENT 16 STANDARD Grade IF only one Containment Spray Pump is operating, THEN; 2.1.k 2) PERFORM the following to close HS-3001C PLACED in BYPASS. S U CV-3001, Containment Spray Valve:
a) PLACE HS-3001C to BYPASS Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 17 STANDARD Grade IF only one Containment Spray Pump is operating, THEN; VERIFIES CV-3001 CLOSED (red light OFF, 2.1.k 2) PERFORM the following to close S U green light ON).
CV-3001, Containment Spray Valve:
b) ENSURE CLOSED CV-3001 Comment:
PALISADES NUCLEAR PLANT Page 9 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 18 STANDARD Grade IF either Containment Sump isolation valve failed to open, 2.1.l Determines that this step is not applicable. S U CV-3030 CV-3029 Comment:
Proc. Step TASK ELEMENT 19 STANDARD Grade IF operation of additional spray pumps or 2.1.m Determines that this step is not applicable. S U HPSI pumps is desired Comment:
EVALUATOR CUE: Cue Operator that no other pumps are desired to be placed in operation.
Proc. Step TASK ELEMENT 20 STANDARD Grade 2.1.n MONITOR for sump screen clogging. Sump screen MONITORED for clogging S U Comment:
EVALUATOR CUE: Cue Operator that another Operator will monitor for sump clogging.
Proc. Step TASK ELEMENT 21 STANDARD Grade IF EITHER of the following exist:
ONLY P-54A Containment Spray Pump operating Determines that another Operator will monitor for 2.1.o S U this.
P-54A OFF THEN CROSSTIE ESS suction headers Comment:
EVALUATOR CUE: Cue Operator that another Operator will crosstie ESS headers.
PALISADES NUCLEAR PLANT Page 10 of 13 OCTOBER 2012
JPM SYSTEM B Proc. Step TASK ELEMENT 22 STANDARD Grade Determines that another Operator will monitor for 2.1.p INITIATE refill of the SIRW Tank. S U this.
Comment:
EVALUATOR CUE: Cue Operator that another Operator will refill SIRW Tank.
Proc. Step TASK ELEMENT 23 STANDARD Grade NOTIFY the CRS that the post RAS actions CRS NOTIFIED that the post RAS actions have n/a have been completed. been completed.
S U Comment:
EVALUATOR CUE: Repeat back notification.
END OF TASK PALISADES NUCLEAR PLANT Page 11 of 13 OCTOBER 2012
JPM SYSTEM B SIMULATOR OPERATOR INSTRUCTIONS SIMULATOR SETUP:
- Use IC-17
- Enter the following malfunctions and overrides:
Final Location Description Location Event Delay Ramp Value RC01 Hot Leg Rupture PIDRC01 N/A 0 0 N/A KEY_155 P-67B trip on low level in SIRW Tank enable PNLC03 none 0 0 OFF P-67B-1 LPSI pump P-67B handswitch PNLC03 None 0 0 OFF P-67B-R P-67B red light PNLC03 none 0 0 ON P-67B-G P-67B green light PNLC03 none 0 0 OFF Take simulator out of freeze, reactor should automatically trip: carry out the following actions:
- Trip Main Feedwater Pumps.
- Trip all Primary Coolant Pumps.
- When SIRWT level reaches ~ 20%, then freeze simulator and take a snapshot.
PALISADES NUCLEAR PLANT Page 12 of 13 OCTOBER 2012
JPM SYSTEM B CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A large break LOCA has occurred.
- The plant has been tripped and EOP-1.0, Standard Post Trip Actions, have been completed.
- EOP-4.0, Loss of Coolant Accident Recovery, has been entered.
- SIS and CHP have actuated.
- Pre-RAS actions have been taken per EOP Supplement 42.
- RAS is imminent.
INITIATING CUES:
- During performance of EOP-4.0 step 52, the Control Room Supervisor directs you to perform Post-RAS actions in accordance with EOP Supplement 42, step 2.0 when RAS occurs.
PALISADES NUCLEAR PLANT Page 13 of 13 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS C TITLE: OPEN PORV BLOCK VALVES CANDIDATE:
EXAMINER:
JPM SYSTEM C JOB PERFORMANCE MEASURE DATA PAGE Task: Open PORV Block Valves Alternate Path: YES Facility JPM #: BANK K/A: 010A2.03 Importance: RO: 4.1 SRO: 4.2 K/A Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures.
Task Standard: At least one PORV placed in service per SOP-1B, Attachment 6.
Preferred Evaluation Location: Simulator __X__ In Plant _____
Preferred Evaluation Method: Perform __X__ Simulate _____
References:
SOP-1B, 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 11 OCTOBER 2012
JPM SYSTEM C EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
- SOP-1B, Attachment 6, Opening of PORV Isolation Valves
- GCL 9-1, Mode 3 525°F To Mode 4 Or Mode 5 Checklist
- ARP-8, Safeguards Safety Injection and Isolation Scheme EK-13 (EC-13),
Window 73
- ONP-23.1, Primary Coolant Leak
- ONP-18, Pressurizer Pressure Control Malfunctions Also see Simulator Operator Instructions (later 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 has been taken off-line, with the reactor tripped.
- P-8A Auxiliary Feedwater Pump is in service supplying feedwater to both S/Gs.
- GCL 9-1, Mode 3 525°F To Mode 4 Or Mode 5 Checklist, is complete through step 2.10.
INITIATING CUES:
The CRS directs you to open the PORV Isolation Valves, MO-1042A and MO-1043A, per SOP-1B, Primary Coolant System - Cooldown, attachment 6.
PALISADES NUCLEAR PLANT Page 3 of 11 OCTOBER 2012
JPM SYSTEM C EVALUATOR CUE: Provide candidate a working copy of SOP-1B, attachment 6.
Proc. Step TASK ELEMENT 1 STANDARD Grade PERFORM the following to OPEN MO-1042A, PZR Power Operated Relief Valve Isolation Valve.
HS-1042B checked in CLOSE position.
2.1a.1 ENSURE the following conditions: S U
- 1. HS-1042B, PZR to Quench Tank T-73 in CLOSE position.
Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade ENSURE the following conditions:
- 2. MO-1042A, Power Relief Valve MO-1042A checked closed.
2.1a.2 S U Isolation closed.
Comment:
Proc. Step TASK ELEMENT 3 STANDARD Grade ENSURE the following conditions:
PCS pressure checked between 2010 and 2.1a.3 3. PCS pressure control established: S U 2100 psia SOP-1 2010 to 2100 psia Comment:
PALISADES NUCLEAR PLANT Page 4 of 11 OCTOBER 2012
JPM SYSTEM C Proc. Step TASK ELEMENT 4 STANDARD Grade HS-1042B placed to OPEN for approx.
PLACE HS-1042B, PZR Quench Tank 15 seconds T-73 to OPEN for approximately 2.1b 15 seconds, AND THEN PLACE to AND THEN S U CLOSE, leaving handswitch in CLOSE HS-1042B placed to CLOSE, with handswitch position when complete.
left in CLOSE position.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade OPERATE HS-1042A, Power Relief Valve Isolation intermittently to the OPEN position until either of the following conditions is observed:
- 1. MO-1042A red position indication lamp HS-1042A operated intermittently until red light 2.1c S U lights (indicates valve is 5% open, green lights.
position indication lamp is also lighted at this point).
- 2. PRV-1042B, Power Operated Relief opens.
Comment:
EVALUATOR NOTE: After MO-1042A has a red light, associated PORV will start to leak by: this will result in alarms and associated ARP actions.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 11 OCTOBER 2012
JPM SYSTEM C EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 6 and 7.
Proc. Step TASK ELEMENT 6 STANDARD Grade Following alarms are acknowledged:
- 1. EK-1373, Operator Action: Refer to The following alarms annunciate with ONP-18: Follow Up Action: Check Acoustic PORV leaking: Monitor Panel for open valve; Check
- 1. EK-1373, SV AND/OR PORV OPEN, TIA-0106 discharge temperature; Refer to (Audible Acoustic Monitor alarm on ONP-23.1.
back of Panel C-11A in alarm from 2. EK-0743, Operator Action: Refer to ARP-8 FI-1042B Accelerometer (#4) Hi noise). S U ONP-23.1; Follow Up Action: Evaluate ARP-4 desired position of MO-1042A; Refer to
- 2. EK-0743, Pressurizer PWR Operated Relief Valve Discharge HI Temp LCOs; Refer to ORM.
(TIA-0106, Relief and Safety Valve
- 3. Acoustic Monitor Reset pushbutton pushed Discharge Temp, reads up-scale).
to silence audible Acoustic Monitor alarm (PORV MOV Block Valve must be closed, for alarm to clear).
Comment:
EVALUATOR CUE: Provide a working copy of ARP-8 Window 73 and ARP-4 Window 43 EVALUATOR CUE: If asked as CRS concerning ARP action to refer to ONP-18 or ONP-23.1, reply that you expect candidate to follow applicable procedures.
o Provide candidate a working copy of ONP-18 and/or ONP-23.1 as appropriate.
o EVALUATOR NOTE: ONP-18 step 4.3.c directs action to close PORV Isolation Valve for the PORV that is leaking. ONP-23.1 step 4.9.j.1 directs action to isolate the leak for any PCS leak that is located and can be isolated EVALUATOR CUE: If candidate begins to reference LCOs, tell them another Operator will reference Technical Specifications and the ORM (Operating Requirements Manual).
EVALUATOR CUE: If candidate asks about PCS leakrate, tell them it is in progress.
EVALUATOR CUE: If candidate asks about isolating Letdown, tell them NOT to isolate.
PALISADES NUCLEAR PLANT Page 6 of 11 OCTOBER 2012
JPM SYSTEM C Proc. Step TASK ELEMENT 7 STANDARD Grade HS-1042A, Power Relief Valve Isolation placed ONP-18 Power Relief Valve Isolation MO-1042A in CLOSE position until MO-1042A red position or S U closed to isolate leaking PORV. indication lamp is OFF and green position ONP-23.1 indication lamp is ON.
Comment:
EVALUATOR NOTE: The critical step criteria is that the PORV Isolation Valve is closed prior to SIAS (1605 psia).
CRITICAL STEP EVALUATOR CUE: If asked direction concerning performing procedure for the other PORV, direct them to perform the other PORV.
EVALUATOR NOTE: The same sequence as above will be repeated for the other PORV.
The following operation will NOT cause a PORV to leak.
Proc. Step TASK ELEMENT 8 STANDARD Grade PERFORM the following to OPEN MO-1043A, PZR Power Operated Relief Valve Isolation Valve.
HS-1043B checked in CLOSE position.
2.2a.1 ENSURE the following conditions: S U
- 1. HS-1043B, PZR to Quench Tank T-73 in CLOSE position.
Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade ENSURE the following conditions:
- 2. MO-1043A, Power Relief Valve MO-1043A checked closed.
2.2a.2 S U Isolation closed.
Comment:
PALISADES NUCLEAR PLANT Page 7 of 11 OCTOBER 2012
JPM SYSTEM C Proc. Step TASK ELEMENT 10 STANDARD Grade ENSURE the following conditions:
PCS pressure checked between 2010 and 2100
- 3. PCS pressure control established:
2.2a.3 psia S U SOP-1 2010 to 2100 psia Comment:
Proc. Step TASK ELEMENT 11 STANDARD Grade HS-1043B placed to OPEN for approx.
PLACE HS-1043B, PZR Quench Tank 15 seconds T-73 to OPEN for approximately 15 seconds, AND THEN PLACE to AND THEN 2.2b CLOSE, leaving handswitch in CLOSE S U HS-1043B placed to CLOSE, with handswitch position when complete.
left in CLOSE position.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade OPERATE HS-1043A, Power Relief Valve Isolation intermittently to the OPEN position until either of the following conditions is observed:
- 1. MO-1043A red position indication lamp HS-1043A operated intermittently until red light 2.2c lights (indicates valve is 5% open, green lights. S U position indication lamp is also lighted at this point).
- 2. PRV-1043B, Power Operated Relief opens.
Comment:
EVALUATOR NOTE: PORV does not open and stays closed and does not leak.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 8 of 11 OCTOBER 2012
JPM SYSTEM C Proc. Step TASK ELEMENT 13 STANDARD Grade IF PRV-1043B, Power Operated Relief opens AND then reseats, THEN repeat Determines that this step does not apply.
2.2d Step 2.2.c. S U Comment:
Proc. Step TASK ELEMENT 14 STANDARD Grade WHEN the following conditions exist,
- 1. MO-1043A, Power Relief Valve Isolation is 5% open (red position indication lamp lit).
2.2e 2. PRV-1043B, Power Operated Relief is MO-1043A to the full open position. S U closed.
THEN FULLY OPEN MO-1043A, Power Relief Isolation.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 15 STANDARD Grade Notify the CRS that one PORV Block Valve CRS notified that one PORV Block Valve is n/a is open. open. S U Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 OCTOBER 2012
JPM SYSTEM C SIMULATOR OPERATOR INSTRUCTIONS IC-11 MFPs tripped, P-8A, AFW Pump, inservice.
NOP and NOT (2060 psia, 532°F)
Banks of backup PZR heaters secured for reduced spray flow (GCL 9-1, step 2.8)
Two PCPs secured with associated PZR Spray Valves closed (GCL-9-1, Steps 2.9 and 2.10)
Double charging and letdown inservice.
Cover gas valved out to VCT, N 2 tag next to VCT vent switch USE CAE or:
Insert Location Description Delay Ramp Event Value Final Time Malfunctions:
(NONE)
RC 19 PORV Relief Valve Partially Lifts 5 Trigger 1 RC 20 PORV Relief Valve Partially Lifts 5 Trigger 2 Remotes:
(NONE)
Overrides:
(NONE)
Triggers:
Number Event Action Description 1 ZLO2P(16).and..not.et_array(2) 2 ZLO2P(19).and..not.et_array(1) set thkkarc20=1.0 3
4 PALISADES NUCLEAR PLANT Page 10 of 11 OCTOBER 2012
JPM SYSTEM C CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The Plant has been taken off-line, with the reactor tripped.
- P-8A Auxiliary Feedwater Pump is in service supplying feedwater to both S/Gs.
- GCL 9-1, Mode 3 525°F To Mode 4 Or Mode 5 Checklist, is complete through step 2.10.
INITIATING CUES:
The CRS directs you to open the PORV Isolation Valves, MO-1042A and MO-1043A, per SOP-1B, Primary Coolant System - Cooldown, attachment 6.
PALISADES NUCLEAR PLANT Page 11 of 11 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS D TITLE: START A PRIMARY COOLANT PUMP CANDIDATE:
EXAMINER:
JPM SYSTEM D JOB PERFORMANCE MEASURE DATA PAGE Task: Start a Primary Coolant Pump.
Alternate Path: YES Facility JPM #: BANK K/A: 003A4.06 Importance: RO: 2.9 SRO: 2.9 K/A Statement: Ability to manually operate and/or monitor in the control room: RCP parameters Task Standard: Primary Coolant Pump P-50A secured in response to indications of loss of cooling Preferred Evaluation Location: Simulator ___X___ In Plant _____
Preferred Evaluation Method: Perform ___X___ Simulate _____
References:
SOP-1A, Primary Coolant System ARP-5, Primary Coolant Pump Steam Generator and Rod Drives Scheme EK-09 (C-12)
Validation Time: 20 minutes Time Critical: NO Candidate:
Time Start: ________ Time Finish: ________
Performance Time: ________ minutes Performance Rating: SAT ______ UNSAT ______
Comments:
Examiner: _______________________________ Date: ______________
Signature PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012
JPM SYSTEM D EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
SOP-1A, Primary Coolant System, section 7.1.2 placekeep to step 7.1.2.o.
ARP-5, Primary Coolant Pump Steam Generator and Rod Drives Scheme EK-09 (C-12)
Also see Simulator Operator Instructions (later 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:
Primary Coolant Pumps P-50B, P-50C and P-50D are in service. The plant is in Hot Shutdown. Proper Shutdown margin has been verified. RPS Breakers 42-1 and 42-2 have been opened.
INITIATING CUES:
- During a plant hot shutdown outage, oil was added to P-50A oil reservoir. The CRS directs you to start PCP P-50A in accordance with SOP-1A, Section 7.1.2, starting at step 7.1.2.o.
- Testing of the lift system is NOT required.
- Use of P-80A, AC Oil Lift Pump, is desired.
PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012
JPM SYSTEM D EVALUATOR CUE: Provide candidate with a working copy of SOP-1A, section 7.1.2 (placekeep up to step 7.1.2.o)
Proc. Step TASK ELEMENT 1 STANDARD Grade WHEN starting P-50A, P-50B, or P-50C, THEN VERIFY the vibration indicator for Checks vibration monitor on Panel C-12 for o S U the Primary Coolant Pump to be started P-50A vibration and verifies reading is < 2 mils.
indicates less then 2 mils.
Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade START the AC or DC Oil Lift Pump for the Places P-80A hand switch to HAND and verifies p PCP(s) to be started as directed by the S U red light LIT and green light OFF.
CRS:
Comment:
EVALUATOR NOTE: P-80A started per Initiating Cue.
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade IF lift oil pressure interlock is NOT satisfied Verifies white light above P-50A hand switch is with one lift pump operating, THEN q LIT and determines no need to start additional S U START the second Oil Lift Pump for the lift pump.
PCP to be started.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012
JPM SYSTEM D Proc. Step TASK ELEMENT 4 STANDARD Grade IF lift oil pressure interlock is NOT satisfied with both Lift Pumps in operation, THEN r Candidate determines this step is N/A. S U NOTIFY Maintenance to prime the Lift Pumps.
Comment:
Proc. Step TASK ELEMENT 5 STANDARD Grade CHECK Annunciators EK-0937, EK-0938, EK-0939, "PRI COOLANT PUMP s BACKSTOP OIL LOW FLOW," for Verifies alarm window EK-0937 is clear. S U pump(s) to be started NOT in alarm (Panel C-12).
Comment:
Proc. Step TASK ELEMENT 6 STANDARD Grade VERIFY the PUMP START OIL Verifies white PUMP START OIL PERMISSIVE t PERMISSIVE white light illuminated for S U light LIT for P-50A.
pump(s) to be started.
Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade WHEN oil lift pump(s) have been operating After 2 or more minutes, places P-50A hand u for at least two minutes, THEN START the switch in START and verify red light LIT and S U selected Primary Coolant Pump. green light OFF.
Comment:
EVALUATOR CUE: Cue candidate that 2 minutes have elapsed.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012
JPM SYSTEM D Proc. Step TASK ELEMENT 8 STANDARD Grade v WHEN the following have occurred Candidate determines this is N/A S U Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade WHEN both of the following conditions exist:
After P-50A amps return to normal following the
- PCP amps return to normal operating starting amp surge and after two minutes have amps following the starting amp surge elapsed from the start of the PCP:
- Two minutes have elapsed from the w start of the PCP Places P-80A hand switch to AUTO S U THEN PERFORM the following: Verifies P-81A handswitch in AUTO
- 1. PLACE the DC Oil Lift Pump handswitches to AUTO. Verifies P-80A and P-81A red lights OFF and green lights LIT.
- 2. PLACE the AC Oil Lift Pump handswitches to AUTO.
Comment:
EVALUATOR NOTE: Depending on timing of the loss of cooling condition, this may not be completed.
SIMULATOR OPERATOR: During this time period, ensure EK-0931 alarms (insert Event Trigger #1 manually if required).
EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 10 through 13 Proc. Step TASK ELEMENT 10 STANDARD Grade Acknowledges alarm and refers to ARP-5:
ARP-5 EK-0931, Pri Coolant Pump P-50A CLG WTR Acknowledge cooling water low flow and LO Flow. S U EK-0931 high temp alarms and refer to ARP-5.
EK-0907 Prim Coolant Pump P-50A HI Temp Overload.
Comment:
EVALUATOR CUE: Provide a working copy of ARP-5 Window 31 PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012
JPM SYSTEM D Proc. Step TASK ELEMENT 11 STANDARD Grade ARP-5 Confirm rising PCP bearing temperatures Monitors P-50A temperature indications on by observing Panel C-11 recorder Panel C-11 recorder and determines S U EK-0931 LTVR-0901 indications for P-50A. temperatures rising at a rapid rate.
Comment:
EVALUATOR CUE: If notified as CRS of the condition, inform candidate to perform the appropriate actions.
CRITICAL STEP EVALUATOR CUE: If requested, provide candidate with a working copy of SOP-1A, section 7.1.4 (emergency shutdown).
Proc. Step TASK ELEMENT 12 STANDARD Grade SOP-1A 7.1.3.f Places hand switch on C-02 in TRIP and verifies Stop PCP P-50A. S U or red light OFF and green light LIT.
7.1.4.d Comment:
EVALUATOR NOTE: Procedure is NOT required to be in-hand for performance of this action.
CRITICAL STEP Proc. Step TASK ELEMENT 13 STANDARD Grade SOP-1A When at least five minutes have elapsed Places DC (P-81A) and AC (P-80A) Oil Lift 7.1.3.h since stopping P-50A, then stop oil lift Pump hand switches to OFF and verifies green S U or pumps. lights LIT and red lights OFF.
7.1.4.e Comment:
EVALUATOR CUE: Cue candidate that 5 minutes have elapsed.
PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012
JPM SYSTEM D Proc. Step TASK ELEMENT 14 STANDARD Grade Notifies CRS that P-50A is stopped due to loss N/A Inform CRS of status of CCW cooling and corresponding high S U temperatures.
Comment:
EVALUATOR CUE: If candidate asks about EM-04-08, STATE that another operator will perform this task.
END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012
JPM SYSTEM D SIMULATOR OPERATOR INSTRUCTIONS
- Reset to IC-11
- Trip reactor using Panel C-06 Reactor Trip Pushbutton.
- Trip PCP P-50A using SOP-1A section 7.1.4 (emergency shutdown)
- Reset all alarms.
- Wait at least 5 minutes to allow time for EK-0907 (P-50A HI Temp Overload) to alarm and perhaps reflash once (this is a normal post-stopping the PCP alarm: check all input TIAs for this alarm on Panel C-11 to ensure candidate will not be surprised by a reflash of this alarm prior to starting P-50A).
- Setup Event Trigger #1:
o Event = ZDI2P(126) (this is P-50A handswitch taken to CLOSE position)
- Place the following malfunction on Event Trigger #1:
o CC14 (PIDCC03), P-50A CCW Outlet Valve Position o Final Value = 0.0 o Delay Time = 30 seconds o Ramp Time = 30 seconds PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012
JPM SYSTEM D CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Primary Coolant Pumps P-50B, 50C and 50D are in service. The plant is in Hot Shutdown. Proper Shutdown margin has been verified. RPS Breakers 42-1 and 42-2 have been opened.
INITIATING CUES:
- During a plant hot shutdown outage, oil was added to P-50A oil reservoir. The CRS directs you to start PCP P-50A in accordance with SOP-1A, Section 7.1.2, starting at step 7.1.2.o.
- Testing of the lift system is NOT required.
- Use of P-80A, AC Oil Lift Pump, is desired.
PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS E TITLE: BYPASS MSIV CLOSURE CANDIDATE:
EXAMINER:
JPM SYSTEM E JOB PERFORMANCE MEASURE DATA PAGE Task: Bypass MSIV Closure Alternate Path: YES Facility JPM #: NEW K/A: 039A4.01 Importance: RO: 2.9 SRO: 2.8 K/A Statement: Ability to manually operate and/or monitor in the control room: Main steam supply valves.
Task Standard: Both MSIV Bypass Valves, MO-0501 and MO-0510, opened with S/G pressure less than 500 psia.
Preferred Evaluation Location: Simulator ___X___ In Plant _____
Preferred Evaluation Method: Perform ___X___ Simulate _____
References:
GOP-9, MODE 3 525°F to MODE 4 or MODE 5 Validation Time: 25 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 OCTOBER 2012
JPM SYSTEM E EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
GOP-9, MODE 3 525°F to MODE 4 or MODE 5 with GCL-9 completed through Step 3.6 and Step 2.15 circled but not slashed.
ARP-5, Primary Coolant Pump Steam Generator and Rod Drives Scheme EK-09 (C-12)
Also see Simulator Operator Instructions (later 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:
- Plant cooldown via the Turbine Bypass Valve, CV-0511, is in-progress per GOP-9, MODE 3 525°F to MODE 4 or MODE 5.
- S/G pressures are approximately 560 psia.
INITIATING CUES:
During performance of GOP-9, MODE 3 525°F to MODE 4 or MODE 5, the CRS directs you to block open the MSIVs per step 3.7 and ensure block is successful as S/G pressure continues to lower.
PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012
JPM SYSTEM E EVALUATOR CUE: Provide candidate with a working copy of GOP-9 with GCL-9 completed through Step 3.6 and Step 2.15 circled but not slashed.
Proc. Step TASK ELEMENT 1 STANDARD Grade WHEN 3 of 4 associated Steam Generator pressure sigmas indicate between 510 and 550 psia and the indicator is between alarm flags, THEN DEPRESS the HS/LPE-50A, BYPASS OF MSIV CLOSURE 3.7 associated pushbutton to bypass MSIV S U pushbutton depressed closure:
- HS/LPE-50A, BYPASS OF MSIV CLOSURE pushbutton Comment:
EVALUATOR NOTE: Alarm EK-0970, Steam Gen Valves Isolation Lockout, will alarm when at least one MSIV auto block signal has been blocked (i.e. blocking second MSIV does not change alarm status or cause it to reflash).
EVALUATOR NOTE: Candidate can perform Task Elements 1 and 2 in any order and may perform Task Element 3 as soon as alarm occurs.
Proc. Step TASK ELEMENT 2 STANDARD Grade WHEN 3 of 4 associated Steam Generator pressure sigmas indicate between 510 and 550 psia and the indicator is between alarm flags, THEN DEPRESS the HS/LPE-50B, BYPASS OF MSIV CLOSURE 3.7 associated pushbutton to bypass MSIV S U pushbutton depressed closure:
- HS/LPE-50B, BYPASS OF MSIV CLOSURE pushbutton Comment:
EVALUATOR NOTE: Alarm EK-0970, Steam Gen Valves Isolation Lockout, will alarm when at least one MSIV auto block signal has been blocked (i.e. blocking second MSIV does not change alarm status or cause it to reflash).
PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012
JPM SYSTEM E Proc. Step TASK ELEMENT 3 STANDARD Grade Acknowledge alarm EK-0970 and refer to Candidate acknowledges alarm on Panel C-02
S U ARP. and refers to ARP-5.
Comment:
EVALUATOR CUE: Provide a working copy of ARP-5 Window 70 EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 4 through 6 Proc. Step TASK ELEMENT 4 STANDARD Grade Determine that both MSIVs auto closed Candidate determines that both MSIVs have
when 2/4 S/G pressures on either S/G closed. S U went below 500 psia.
Comment:
EVALUATOR CUE: If candidate asks for direction on which procedure to use or action to take, then ask Candidate what they would suggest.
- Candidate Response: continue with cooldown using Turbine Bypass Valve (opening MSIV bypasses required for this) or Atmospheric Steam Dump Valves
- EVALUATOR Response: Use GOP-9 and continue the plant cooldown using CV-0511, Turbine Bypass Valve. Reopening of MSIVs is NOT desired CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade ENSURE OPEN both MSIV Bypass Valves: Candidate opens MSIV Bypass Valve 2.15 S U
- MO-0501, MSIV CV-0501 Bypass
- MO-0501
- MO-0510, MSIV CV-0510 Bypass Comment:
EVALUATOR NOTE: Candidate may use GOP-9 step 2.15 to complete this action (not required to meet Task Standard).
EVALUATOR NOTE: Candidate may close CV-0511 with PIC-0511 prior to opening the MSIV Bypass Valves.
EVALUATOR NOTE: Order in which candidate opens MSIV bypass valves is not critical.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012
JPM SYSTEM E Proc. Step TASK ELEMENT 6 STANDARD Grade ENSURE OPEN both MSIV Bypass Valves: Candidate opens MSIV Bypass Valve:
2.15 S U
- MO-0501, MSIV CV-0501 Bypass
- MO-0510
- MO-0510, MSIV CV-0510 Bypass Comment:
EVALUATOR NOTE: Candidate may use GOP-9 step 2.15 to complete this action (not required to meet Task Standard).
EVALUATOR NOTE: Candidate may close CV-0511 with PIC-0511 prior to opening the MSIV Bypass Valves.
EVALUATOR NOTE: Order in which candidate opens MSIV bypass valves is not critical.
CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade Notify CRS that both MSIV Bypass Valves are open due to inability to block auto N/A CRS notified. S U closure of MSIVs and cooldown has been reestablished.
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012
JPM SYSTEM E SIMULATOR OPERATOR INSTRUCTIONS
- Reset to IC-11.
- Insert override for zdi3p(174) to OFF (this is CV-0501-BYP, Bypass of MSIV Closure on Low SG Press, SG B Bypass pushbutton on Panel C-01).
- Trip the reactor.
- Fully open both MSIV Bypass Valves and then latch both MSIVs using remotes MS25 and MS36 on PID MS02.
- Commence a 60°/hr cooldown using CV-0511, TBV.
- Close both MSIV Bypass Valves.
- Annotate/perform other GOP-9 activities up to step 3.7.
- FREEZE when S/G pressures are approximately 560 psia and SNAP into a saved IC.
PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012
JPM SYSTEM E CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Plant cooldown via the Turbine Bypass Valve, CV-0511, is in-progress per GOP-9, MODE 3 525°F to MODE 4 or MODE 5.
- S/G pressures are approximately 560 psia.
INITIATING CUES:
During performance of GOP-9, MODE 3 525°F to MODE 4 or MODE 5, the CRS directs you to block open the MSIVs per step 3.7 and ensure block is successful as S/G pressure continues to lower.
PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS F TITLE: ALIGN CONTAINMENT AIR COOLERS CANDIDATE:
EXAMINER:
JPM SYSTEM F JOB PERFORMANCE MEASURE DATA PAGE Task: Alignment of Containment Air Coolers following fan maintenance Alternate Path: YES Facility JPM #: BANK K/A: 022A1.04 Importance: RO: 3.2 SRO: 3.3 K/A Statement: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Cooling water flow Task Standard: All four Containment Air Cooling System aligned per SOP-5. Third Service Water Pump started.
Preferred Evaluation Location: Simulator __X__ In Plant _____
Preferred Evaluation Method: Perform __X__ Simulate _____
References:
SOP-5, Containment Air Cooling 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 11 OCTOBER 2012
JPM SYSTEM F EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
- SOP-5, Containment Air Cooling, section 7.1.1.
Also see Simulator Operator Instructions (later 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 steady state 100% power.
- VHX-1 Cooling Fans V-1A and V-1B are OFF with Service Water isolated.
- VHX-4 Cooling Fans V-4A and V-4B are OFF with Service Water isolated.
- All CAC Outlet Bypass Valves are properly aligned per SOP-5, Containment Air Cooling, step 7.1.1.b.1 table.
INITIATING CUES:
The Control Room Supervisor has directed you to align the Containment Air Cooling System to its normal alignment per SOP-5, section 7.1.1 with all fans operating and all inlet and high capacity valves open.
PALISADES NUCLEAR PLANT Page 3 of 11 OCTOBER 2012
JPM SYSTEM F EVALUATOR CUE: Provide candidate with a working copy of SOP-5, section 7.1.1.
Proc.Step TASK ELEMENT 1 STANDARD Grade REFER TO Step 5.2.3 for guidance on Candidate refers to step 5.2.3 for guidance on 7.1.1.a S U Service Water Pump operation. SW pump operation.
Comment:
EVALUATOR CUE: Provide candidate with a working copy of SOP-5, section 5.2.3.
EVALUATOR CUE: If asked whether a third Service Water Pump should be started, state that, "If possible, operate with two Service Water Pumps."
EVALUATOR NOTE: Order of valve alignment and fan starts is not critical.
Proc.Step TASK ELEMENT 2 STANDARD Grade ENSURE control valves are positioned as
7.1.1 follows
CV-0869 is verified open. S U b.1 For VHX-4, verify open Inlet Valve CV-0869.
Comment:
EVALUATOR NOTE: Service Water Pump discharge pressure has been setup low and will lower further when CAC high capacity valves are opened.
Proc.Step TASK ELEMENT 3 STANDARD Grade ENSURE control valves are positioned as
7.1.1 follows
High Capacity Outlet Valve CV-0867 is opened. S U b.1 For VHX-4, open High Capacity Outlet Valve CV-0867.
Comment:
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 11 OCTOBER 2012
JPM SYSTEM F Proc.Step TASK ELEMENT 4 STANDARD Grade ENSURE control valves are positioned as
7.1.1 follows
Inlet Valve CV-0862 is verified open. S U b.1 For VHX-1 verify Open Inlet Valve CV-0862.
Comment:
EVALUATOR NOTE: Will receive EDG Trouble Alarms on Panel C-11 after Service Water Pump start.
EVALUATOR NOTE: This step may be performed AFTER Service Water Pump start.
Proc.Step TASK ELEMENT 5 STANDARD Grade ENSURE control valves are positioned as
7.1.1 follows
High Capacity Outlet Valve CV-0861 is opened. S U b.1 For VHX-1 open High Capacity Outlet Valve CV-0861.
Comment:
EVALUATOR NOTE: This step may be performed AFTER Service Water Pump start.
CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade Determines that the Standby Service Water Pump P-7C needs to be started because Monitor Service Water Header pressure and system pressure has lowered to < 50 psig.
5.2.3 determine that Service Water system S U pressure is < 50 psig. May need to respond to alarms EK-0551 and EK-0557: Has AO investigate D/G local alarm boards.
Comment:
EVALUATOR CUE: When asked as AO report that D/G local alarm panels indicate low raw water pressure.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 11 OCTOBER 2012
JPM SYSTEM F EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 7 through 14 Proc.Step TASK ELEMENT 7 STANDARD Grade Obtain SOP-15, Service Water System Locates SOP-15, Service Water System n/a S U procedure, section 7.1.1. procedure.
Comment:
EVALUATOR CUE: Provide candidate with a working copy of SOP-15, section 7.1.1.
Proc.Step TASK ELEMENT 8 STANDARD Grade SOP-15 IF starting the first Service Water Pump, Candidate determines this step is N/A. S U 7.1.1.a THEN GO TO Section 7.1.5.
Comment:
Proc.Step TASK ELEMENT 9 STANDARD Grade IF starting the third Service Water Pump, SOP-15 THEN NOTIFY Chemistry so that they can Notify Chemistry to recalculate Mixing Basin S U 7.1.1.b recalculate mixing basin discharge flow discharge flow volume.
volume.
Comment:
EVALUATOR CUE: CRS will notify Chemistry of P-7C start so they can recalculate mixing basin discharge flow volume.
PALISADES NUCLEAR PLANT Page 6 of 11 OCTOBER 2012
JPM SYSTEM F Proc.Step TASK ELEMENT 10 STANDARD Grade ENSURE OPEN associated pump SOP-15 Dispatch AO to check OPEN P-7C discharge discharge valve: S U 7.1.1.c valve MV-SW104.
- P-7C MV-SW104 Comment:
EVALUATOR (or Simulator Operator) CUE: "MV-SW104 is OPEN" Proc.Step TASK ELEMENT 11 STANDARD Grade SOP-15 Dispatch AO to check P-7C motor oil levels ENSURE motor oil levels normal. S U 7.1.1.d normal.
Comment:
EVALUATOR (or Simulator Operator) CUE: "P-7C Motor oil levels normal" Proc.Step TASK ELEMENT 12 STANDARD Grade SOP-15 Remove P-7C from standby by placing P-7C Control Switch placed momentarily in S U 7.1.1.e Control Switch to TRIP. TRIP until standby light extinguishes.
Comment:
PALISADES NUCLEAR PLANT Page 7 of 11 OCTOBER 2012
JPM SYSTEM F Proc.Step TASK ELEMENT 13 STANDARD Grade SOP-15 START desired pump from Control Room P-7C control switch placed in START and Handswitch (preferred) or using Handswitch S U 7.1.1.f released to mid-position.
on breaker.
Comment:
SIMULATOR OPERATOR: Call in as AO and report that SW Pump P-7C local discharge pressure is 73 psig, and packing leakoff is not excessive. If asked, report that P-7C Basket Strainer DP is 4 psid.
EVALUATOR NOTE: EK-1144, P-7C Basket Strainer HI dP may alarm and then clear after pump start: candidate should reference ARP-7, but no actions are required.
CRITICAL STEP Proc.Step TASK ELEMENT 14 STANDARD Grade Verify Service Water Header pressure rises Verify Service Water Header pressure rises
--- S U to > 50 psig. to > 50 psig.
Comment:
EVALUATOR NOTE: Candidate will refer back to SOP-5, 7.1.1.b.2 to complete alignment of Containment Air Coolers.
Proc.Step TASK ELEMENT 15 STANDARD Grade ENSURE all available Containment Air 7.1.1 Cooler Fans are operating: V-1A is started. S U b.2 For VHX-1 start fan V-1A (SOP-5).
Comment:
CRITICAL STEP PALISADES NUCLEAR PLANT Page 8 of 11 OCTOBER 2012
JPM SYSTEM F Proc.Step TASK ELEMENT 16 STANDARD Grade ENSURE all available Containment Air 7.1.1 Cooler Fans are operating: V-1B is started. S U b.2 For VHX-1 start fan V-1B (SOP-5)
Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 17 STANDARD Grade ENSURE all available Containment Air 7.1.1 Cooler Fans are operating: V-4A is started. S U b.2 For VHX-4 start fan V-4A (SOP-5)
Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 18 STANDARD Grade ENSURE all available Containment Air 7.1.1 Cooler Fans are operating: V-4B is started. S U b.2 For VHX-4 start fan V-4B (SOP-5)
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 19 STANDARD Grade Notify CRS that Containment Air Coolers N/A are aligned with all High Capacity outlet CRS notified. S U valves open and all fans running.
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 9 of 11 OCTOBER 2012
JPM SYSTEM F SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-17.
Ensure P-7A and P-7B are in service, with P-7C in standby.
Stop V-1A, 1B, 4A, and 4B.
Close VHX-1 High Capacity Outlet, CV-0861.
Close VHX-4 High Capacity Outlet, CV-0867.
Insert SW leak: SW09 in at 50% (at setup).
Create Event Trigger 2: Event = zlo1p(26).and.zlo1p(32), Action - imf sw09 65
{this is for having the red lights on for CVs-0861 and 0867}
PALISADES NUCLEAR PLANT Page 10 of 11 OCTOBER 2012
JPM SYSTEM F CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The plant is operating at steady state 100% power.
- VHX-1 Cooling Fans V-1A and V-1B are OFF with Service Water isolated.
- VHX-4 Cooling Fans V-4A and V-4B are OFF with Service Water isolated.
- All CAC Outlet Bypass Valves are properly aligned per SOP-5, Containment Air Cooling, step 7.1.1.b.1 table.
INITIATING CUES:
The Control Room Supervisor has directed you to align the Containment Air Cooling System to its normal alignment per SOP-5, section 7.1.1 with all fans operating and all inlet and high capacity valves open.
PALISADES NUCLEAR PLANT Page 11 of 11 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS G TITLE: ADJUST RIA-1049 SETPOINT CANDIDATE:
EXAMINER:
JPM SYSTEM G JOB PERFORMANCE MEASURE DATA PAGE Task: Adjust RIA-1049 Alarm Setpoint Alternate Path: NO Facility JPM #: BANK K/A: 073A4.01 Importance: RO: 3.9 SRO: 3.9 K/A Statement: Ability to manually operate and/or monitor in the control room: Effluent release Task Standard: RIA-1049 high alarm set to 1100 cpm.
Preferred Evaluation Location: Simulator ___X___ In Plant _____
Preferred Evaluation Method: Perform ___X___ Simulate _____
References:
SOP-37, Process Liquid Monitor System Validation Time: 12 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 OCTOBER 2012
JPM SYSTEM G EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
SOP-37, Process Liquid Monitor System Also see Simulator Operator Instructions (later 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:
- Release Order, Form CH 6.21-3 (batch card) has been prepared. The following RE-1049 data has already been entered on this form:
o RE-1049 Check Source reading = 6.6 E6 o High alarm setpoint net cpm = 640 o RE-1049 background cpm = 460 o RIA-1049 alarm setpoint cpm = 1100
- Breaker 34 on Y-01 is closed.
- Attachment 3, Checklist 37, Table Digital Rate Meter Instruments for RIA-1049, Digital Rate Meter has been performed.
INITIATING CUES:
The CRS directs you to set up Radwaste Discharge Monitor, RIA-1049 High Alarm Setpoint using SOP-37 Section 7.2.3.d to a setpoint of 1100 cpm (hand candidate prepared Release Order).
PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012
JPM SYSTEM G EVALUATOR CUE: Provide candidate with a working copy of SOP-37, section 7.2.3.
EVALUATOR NOTE: Steps 7.2.3.a and 7.2.3.b are complete per initial conditions; Step 7.2.3.c is N/A.
Proc. Step TASK ELEMENT 1 STANDARD Grade PUSH HIGH pushbutton on front of "High Alarm" push button on the front of d.1 RIA-1049 and read current High Alarm RIA-1049 pushed and current high alarm S U Setpoint. setpoint is read as 2.70E3 CPM.
Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade PULL RIA-1049 out from the panel about d.2 six inches (6") to access the control RIA-1049 pulled out from panel about 6 inches. S U buttons.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade VERIFY Function switch is set to 0 as Checks right side of Function Switch is set d.3 S U seen on right side of switch. to 0.
Comment:
Proc. Step TASK ELEMENT 4 STANDARD Grade PRESS ENTER button to display High d.4 "Enter" button pressed and one digit blinking. S U Alarm setpoint.
Comment:
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012
JPM SYSTEM G Proc. Step TASK ELEMENT 5 STANDARD Grade SET the High Alarm setpoint by performing the following as necessary:
- IF selecting another digit, THEN Digit and Value pushbuttons manipulated as d.5 PRESS the DIGIT pushbutton. necessary to set the high alarm setpoint at S U
- IF changing the digit value, THEN 1.10E3.
PRESS the VALUE pushbutton until value desired for that digit is displayed.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade WHEN entire display indicates desired trip d.6(a) setpoint, THEN: Enter button pressed. S U (a) PRESS ENTER pushbutton.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade WHEN entire display indicates desired trip d.6(b) setpoint, THEN: Monitor pushed back into panel. S U (b) PUSH monitor back into panel.
Comment:
Proc. Step TASK ELEMENT 8 STANDARD Grade PRESS HIGH pushbutton on front of High Alarm" push button pressed and 1.10E3 d.7 RIA-1049 to verify high alarm setpoint is S U CPM trip setpoint verified.
correct.
Comment:
PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012
JPM SYSTEM G Proc. Step TASK ELEMENT 9 STANDARD Grade PRESS ALARM ACK button to clear any d.8 Alarm Ack pushed and Alarms clear. S U high alarms that may have come in.
Comment:
Proc. Step TASK ELEMENT 10 STANDARD Grade Notify the CRS that RIA-1049 High Alarm N/A CRS is notified. S U Setpoint is 1100 cpm.
Comment:
EVALUATOR CUE: As CRS, repeat back the notification.
END OF TASK PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012
JPM SYSTEM G SIMULATOR OPERATOR INSTRUCTIONS
- Any IC
- Ensure RIA-1049 high alarm setpoint is set at 2.61E3 cpm PRIOR TO performing this JPM and AFTER it is completed (as appropriate).
CH 6.21, Attachment 3, page 1 of 2.
In the first section of the form, fill in the following:
Batch = LRW-Today Tank = T-91
% released = 70%
Volume released (gal) = 51100 Minimum required Dilution Water Pumps = 1 Minimum required Service Water Pumps = 2 Maximum permitted release rate (gpm) = 250 Authorization Shift Manager = any signature; Date = today In the second section of the form, Control Room Operator pre-release section, fill in the following:
Check both DW pumps operating Check P-7A and P-7B SW pumps operating RE-1049 Check Source reading = 6.6 E6 High alarm setpoint net cpm = 640 RE-1049 background cpm = 460 RIA-1049 alarm setpoint cpm = 1100 Control Room Operator = any signature, Date = today PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012
JPM SYSTEM G CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Release Order, Form CH 6.21-3 (batch card) has been prepared. The following RE-1049 data has already been entered on this form:
o RE-1049 Check Source reading = 6.6 E6 o High alarm setpoint net cpm = 640 o RE-1049 background cpm = 460 o RIA-1049 alarm setpoint cpm = 1100
- Breaker 34 on Y-01 is closed.
- Attachment 3, Checklist 37, Table Digital Rate Meter Instruments for RIA-1049, Digital Rate Meter has been performed.
INITIATING CUES:
The CRS directs you to set up Radwaste Discharge Monitor, RIA-1049 High Alarm Setpoint using SOP-37 Section 7.2.3.d to a setpoint of 1100 cpm.
PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS H TITLE: INITIATE A CONTAINMENT PURGE CANDIDATE:
EXAMINER:
JPM SYSTEM H JOB PERFORMANCE MEASURE DATA PAGE Task: Initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System Alternate Path: YES Facility JPM #: 2009 NRC EXAM K/A: 029A2.03 Importance: RO: 2.7 SRO: 3.1 K/A Statement: Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Startup operations and the associated required valve lineups Task Standard: Initiate a Containment Purge. Subsequently terminate the Containment Purge based on plant ventilation fan status.
Preferred Evaluation Location: Simulator __X__ In Plant _____
Preferred Evaluation Method: Perform __X__ Simulate _____
References:
SOP-24, Ventilation and Air Conditioning System HP 6.14, Containment Purge SOP-38, Gaseous Process Monitoring System ARP-7, EK-1127, Main Exhaust Fan V-6A trip Validation Time: 20 minutes Time Critical: NO Candidate:
Time Start: ________ Time Finish: ________
Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______
Comments:
Examiner: _______________________________ Date: ______________
Signature PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012
JPM SYSTEM H EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
- SOP-24, Ventilation and Air Conditioning System, section 7.2.5
- ARP-7, Auxiliary Systems Scheme EK-11 (C-13), Window 27 Also see Simulator Operator Instructions (later 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 MODE 5 with the PCS vented to Containment.
- Control Room Supervisor has obtained a Batch Card for Containment.
- The RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.
INITIATING CUES:
The Control Room Supervisor has directed you to initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System section 7.2.5. The CRS has also informed you that an AO has been briefed and is standing by awaiting your instructions.
PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012
JPM SYSTEM H EVALUATOR CUE: Provide a working copy of SOP-24, Ventilation and Air Conditioning System, section 7.2.5.
EVALUATOR CUE: If candidate asks to see the Batch Card inform candidate that he doesn't need to see it, but to inform me of the start and stop times of the release so that it can be recorded.
Proc.Step TASK ELEMENT 1 STANDARD Grade NOTIFY the RETS/REMP Supervisor or Duty Radiation Protection Supervisor to 7.2.5.a ensure requirements of Chemistry RETS/REMP Supervisor or Duty HP notified S U Procedure CH 6.27, "Containment Purge,"
are met.
Comment:
EVALUATOR CUE: Role play as CRS and notify candidate that RETS/REMP Supervisor has been informed.
Proc.Step TASK ELEMENT 2 STANDARD Grade ENSURE one Main Exhaust Fan operating.
Candidate verifies Main Exhaust Fan V-6A 7.2.5.b
- V-6A S U running on panel C-13.
- V-6B Comment:
Proc.Step TASK ELEMENT 3 STANDARD Grade ENSURE the RGEM System is in operation.
Refer to System Operating Procedure 7.2.5.c From Initiating Cue. S U SOP-38, "Gaseous Process Monitoring System," for RGEM System.
Comment:
PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012
JPM SYSTEM H Proc.Step TASK ELEMENT 4 STANDARD Grade Candidate calls Auxiliary Operator and directs ENSURE the following Test Tap Valves are the following valves be checked closed and 7.2.5.d LOCKED CLOSED AND CAPPED: S U capped:
MV-VA506 MV-VA508 MV-VA505 MV-VA506 MV-VA508 MV-VA505 Comment:
EVALUATOR CUE: When candidate calls AO, role play as AO and report after approximately 2 minutes that MV-VA506, MV-VA508, and MV-VA505 are locked closed and capped.
Proc.Step TASK ELEMENT 5 STANDARD Grade Key inserted and the following Purge Supply INSERT key AND OPEN the following and Exhaust Valves opened and verifies Purge Supply and Exhaust Valves: associated Red light ON and Green light OFF:
- CV-1805 (key 272)
- CV-1805 (key 272) ____
- CV-1806 (key 274)
- CV-1806 (key 274) ____
7.2.5.e S U
- CV-1807 (key 275)
- CV-1807 (key 275) ____
- CV-1808 (key 277)
- CV-1808 (key 277) ____
- CV-1813 (key 273)
- CV-1813 (key 273) ____
- CV-1814 (key 276)
- CV-1814 (key 276) ____
Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade RECORD in the SOMS Narrative Log the Record the time the valves were opened in the 7.2.5.f S U time the valves were opened. Control Room Logbook.
Comment:
EVALUATOR CUE: Role play as CRS and inform candidate that these times have been logged.
PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012
JPM SYSTEM H Proc.Step TASK ELEMENT 7 STANDARD Grade 7.2.5.g START Air Room Purge Supply Fan V-46. Air Room Purge Supply Fan V-46 is started. S U Comment:
EVALUATOR NOTE: 10 seconds after Purge Supply Fan is started, the V-6A Main Exhaust Fan will TRIP, and V-6B Standby Fan will not start. This will require that the Containment Purge to be manually terminated.
CRITICAL STEP EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 8 through 11 Proc.Step TASK ELEMENT 8 STANDARD Grade Main Exhaust V-6A trips and EK-1127 Applicant refers to ARP-7, EK-1127, Main
--- S U annunciates. Exhaust Fan V-6A or B trip.
Comment:
EVALUATOR CUE: If told as CRS that Main Exhaust Fan has tripped, acknowledge.
EVALUATOR CUE: Provide a working copy of ARP-7 Window 27 Proc.Step TASK ELEMENT 9 STANDARD Grade ENSURE STARTED V-6A or V-6B, standby Candidate attempts to start V-6B and ARP-7 S U Main Exhaust Fan. determines it will not start.
Comment:
PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012
JPM SYSTEM H Proc.Step TASK ELEMENT 10 STANDARD Grade IF neither Main Exhaust Fan can be started, THEN:
SUSPEND heavy load movements, core alterations and movement of irradiated fuel ARP-7 Candidate stops Air Room Supply Fan V-46. S U SECURE any Radioactive Waste Gas Batch per SOP-18A.
SHUTDOWN any Plant ventilation air flow per SOP-24.
Comment:
EVALUATOR CUE: If asked, role play as SRO the following:
- No heavy load movements are in progress in the Containment or SFP
- No core alterations or movement of fuel is occurring in Containment or SFP
- No Waste Gas Decay Tank batches are in progress.
CRITICAL STEP Proc.Step TASK ELEMENT 11 STANDARD Grade Candidate closes all OPEN purge control Manually CLOSE all OPEN purge control valves and verifies associated Red light OFF valves opened in step 7.2.5.e: and Green light ON: (Candidate may refer back to 7.2.5.e as a guide)
- CV-1805 (key 272)
- CV-1805 (key 272) ____
- CV-1806 (key 274)
ARP-7
- CV-1806 (key 274) ____ S U
- CV-1807 (key 275)
- CV-1807 (key 275) ____
- CV-1808 (key 277)
- CV-1808 (key 277) ____
- CV-1813 (key 273)
- CV-1813 (key 273) ____
- CV-1814 (key 276)
- CV-1814 (key 276) ____
Comment:
EVALUATOR NOTE: Candidate may start securing other ventilation systems, but stop JPM when Containment Purge is isolated.
CRITICAL STEP END OF TASK PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012
JPM SYSTEM H SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-1 Ensure V-6A in service.
Create Event Trigger #1: Event: ZDI1P(524) [this is Purge Fan V-46 HS to CLOSE]
Place the following overrides on Panel PAL09M1 (C-13 left side) on Event Trigger #1 with a 10 second time delay:
V-6A-1, Main Exhaust V-6A Trip to ON V-6B-1, Main Exhaust V-6B Trip to ON PALISADES NUCLEAR PLANT Page 8 of 9 OCTOBER 2012
JPM SYSTEM H CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The Plant is in MODE 5 with the PCS vented to Containment.
- Control Room Supervisor has obtained a Batch Card for Containment.
- The RGEM system is in operation per SOP-38, Gaseous Process Monitoring System.
INITIATING CUES:
The Control Room Supervisor has directed you to initiate a Containment Purge per SOP-24, Ventilation and Air Conditioning System section 7.2.5. The Hot Side Auxiliary Operator has been briefed and is standing by awaiting your instructions.
PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I SYS I TITLE: TESTING OF ATMOSPHERIC STEAM DUMP VALVE CANDIDATE:
EXAMINER:
JPM SYSTEM I JOB PERFORMANCE MEASURE DATA PAGE Task: Testing of Atmospheric Steam Dump Valve Alternate Path: NO Facility JPM #: NEW K/A: 041A4.08 Importance: RO: 3.0 SRO: 3.1 K/A Statement: Ability to manually operate and/or monitor in the control room: Steam dump valves.
Task Standard: CV-0780, Atmospheric Steam Dump Valve tested per SOP-7.
Preferred Evaluation Location: Simulator ___X___ In Plant _____
Preferred Evaluation Method: Perform___X___ Simulate _____
References:
SOP-7, Main Steam System Validation Time: 30 minutes Time Critical: NO Candidate:
Time Start: ________ Time Finish: ________
Performance Time: ________ minutes Performance Rating: SAT______ UNSAT ______
Comments:
Examiner: _______________________________ Date: ______________
Signature PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012
JPM SYSTEM I EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
SOP-7, Main Steam System Also see Simulator Operator Instructions (later 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:
- GOP-2, MODE 5 TO MODE 3 525°F, has just been completed, with the Plant in MODE 3
- Reactor start-up preparations are in progress
- SOP-7, Main Steam System, step 7.2.1.h is being used to maintain Tave between 532°F and 535°F
- S/G levels are being maintained above 45%
INITIATING CUES:
The CRS directs you to test CV-0780, Atmospheric Steam Dump Valve, per SOP-7, , Test of Atmospheric Steam Dumps. The Secondary Auxiliary Operator has been briefed on this task and is awaiting your instructions.
PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012
JPM SYSTEM I EVALUATOR CUE: Provide candidate with a working copy of SOP-7, Attachment 4.
Proc. Step TASK ELEMENT 1 STANDARD Grade REFER TO table below to determine applicable Controller, Air Supply and Candidate determines Controller, Air Supply and 2.1 S U Isolation Valve for Steam Dump being Isolation Valve for CV-0780.
tested:
Comment:
EVALUATOR CUE: If asked, inform candidate that Tech Spec 3.7.4 has been reviewed.
Proc. Step TASK ELEMENT 2 STANDARD Grade 2.2 RAISE T AVE to approximately 534°F. T AVE verified to be approximately 534°F. S U Comment:
EVALUATOR CUE: If the Operator asks how to accomplish this, CRS response is that a separate Control Operator has completed this task and is stationed in the Control Room.
Proc. Step TASK ELEMENT 3 STANDARD Grade For the Steam Dump Group being tested:
MANUALLY CLOSE the CV Isolation for Candidate directs Auxiliary Operator to close 2.3a the CV to be tested, THEN THROTTLE S U MV-MS104 and then throttle open 18.5 turns.
OPEN to the specified number of test turns.
Comment:
EVALUATOR CUE: Have Candidate call AO (simulator operator).
SIMULATOR OPERATOR: Acknowledge direction to AO, then INSERT SG12 (PIDMS01)
Final Value to 50, then report MV-MS104 has been closed and then throttled open 18.5 turns.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012
JPM SYSTEM I Proc. Step TASK ELEMENT 4 STANDARD Grade For the Steam Dump Group being tested:
CLOSE the Air Supply Isolation for the Candidate directs Auxiliary Operator to close 2.3b S U remaining Steam Dump in the group being MV-CA782.
tested.
Comment:
EVALUATOR CUE: Have Candidate call AO (simulator operator).
SIMULATOR OPERATOR: Acknowledge direction to AO, then INSERT MS21 (PIDMS01) to CLOSE, then report MV-CA782 has been closed.
CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade At C-33 Panel, perform the following: HIC-0780B verified to be 0% OPEN 2.4a PLACE appropriate Steam Dump Remote HIC-0780B placed in MANUAL (green light on, S U Controller to 0% OPEN AND MANUAL. red light off).
- Comment:
CRITICAL STEP*
Proc. Step TASK ELEMENT 6 STANDARD Grade At C-33 Panel, perform the following:
NOTIFY Control Operator to monitor 2.4b Steam Dump position indication on C-01 Control Operator notified. S U Panel AND TIME Steam Dump stroke from CLOSED to OPEN position.
Comment:
EVALUATOR CUE: Acknowledge request to Control Room Operator.
PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012
JPM SYSTEM I Proc. Step TASK ELEMENT 7 STANDARD Grade At C-33 Panel, perform the following:
Using appropriate Steam Dump Remote HIC-0780B manual operating lever operated to 2.4c Controller, STROKE the Steam Dump S U fully open and then close CV-0780.
being tested fully OPEN and then CLOSED.
Comment:
EVALUATOR CUE: IF asked as Control Operator, report that CV-0780 fully opened in 5 seconds.
EVALUATOR CUE: IF asked as Control Operator, report that CV-0780 is fully closed.
CRITICAL STEP Proc. Step TASK ELEMENT 8 STANDARD Grade IF remaining Steam Dump in applicable Candidate determines this step is N/A per 2.5 group is to be tested, THEN PERFORM S U initiating cue.
the following:
Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade RETURN affected Steam Dump Remote 2.6 HIC-0780B placed in AUTO. S U Controller to AUTO.
Comment:
CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012
JPM SYSTEM I Proc. Step TASK ELEMENT 10 STANDARD Grade FULLY OPEN the affected CV Isolation Candidate directs Auxiliary Operator to fully 2.6a S U Valve closed in Step 2.3a. open MV-MS104.
Comment:
EVALUATOR CUE: Have Candidate call AO (simulator operator).
SIMULATOR OPERATOR: Acknowledge direction to AO, then INSERT SG12 (PIDMS01)
Final Value to 100, then report MV-MS104 has been fully opened.
CRITICAL STEP Proc. Step TASK ELEMENT 11 STANDARD Grade Candidate directs Auxiliary Operator to open 2.6b OPEN Air Supply closed in Step 2.3b. S U MV-CA782.
Comment:
EVALUATOR CUE: Have Candidate call AO (simulator operator).
SIMULATOR OPERATOR: Acknowledge direction to AO, then INSERT MS21 (PIDMS01)
Final Value to OPEN, then report MV-CA782 has been opened.
CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade REPEAT Steps 2.3 through 2.4 for 2.6c Candidate determines this step is N/A. S U remaining Steam Dump in group.
Comment:
Proc. Step TASK ELEMENT 13 STANDARD Grade REPORT results of Steam Dump testing to Candidate informs System Engineer either 2.6d S U the System Engineer. directly or by way of CRS.
Comment:
EVALUATOR CUE: Acknowledge report to System Engineer.
PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012
JPM SYSTEM I Proc. Step TASK ELEMENT 14 STANDARD Grade CRS is notified that testing of CV-0780 has N/A CRS notified of operation. S U been completed.
Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012
JPM SYSTEM I SIMULATOR OPERATOR INSTRUCTIONS
- All Control Rods are inserted.
- MSIVs are closed.
- Decay heat must be high enough to allow the PCS to heat up, adjust if necessary.
- Ensure Tave is maintained at approximately 534°F throughout the JPM.
PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012
JPM SYSTEM I CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- GOP-2, MODE 5 TO MODE 3 525°F, has just been completed, with the Plant in MODE 3
- Reactor start-up preparations are in progress
- SOP-7, Main Steam System, step 7.2.1.h is being used to maintain Tave between 532°F and 535°F
- S/G levels are being maintained above 45%
INITIATING CUES:
The CRS directs you to test CV-0780, Atmospheric Steam Dump Valve, per SOP-7, , Test of Atmospheric Steam Dumps. The Secondary Auxiliary Operator has been briefed on this task and is awaiting your instructions.
PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS J TITLE: ISOLATE AND LOCALLY START DIESEL GENERATOR 1-1 CANDIDATE:
EXAMINER:
JPM SYSTEM J JOB PERFORMANCE MEASURE DATA PAGE Task: Isolate and Locally Start D/G 1-1 Alternate Path: NO Facility JPM #: BANK K/A: 064A4.06 Importance: RO: 3.9 SRO: 3.9 K/A Statement: Ability to manually operate and/or monitor in the control room: Manual start, loading, and stopping of the ED/G Task Standard: 1-1 Diesel Generator is operating with SW Pump P-7B and Bus 13 energized.
Preferred Evaluation Location: Simulator ______ In Plant __X___
Preferred Evaluation Method: Perform ______ Simulate __X___
References:
ONP-25.2, Alternate Safe Shutdown Procedure ONP-20, Diesel Generator Manual Control Validation Time: 30 minutes Time Critical: NO Candidate:
Time Start: ________ Time Finish: ________
Performance Time: ________ minutes Performance Rating: SAT ______ UNSAT ______
Comments:
Examiner: _______________________________ Date: ______________
Signature PALISADES NUCLEAR PLANT Page 2 of 13 OCTOBER 2012
JPM SYSTEM J EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
ONP-25.2, Alternate Safe Shutdown Procedure ONP-20, Diesel Generator Manual Control, Attachment 3 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:
- Start-up Transformer 1-2 and Safeguards 1-1 Transformer are NOT available
- A fire in the Control Room damaged Bus 1C load shed circuits
- The fire in the Control Room also damaged 1-1 Diesel Generator control circuits
- The Control Room is NOT habitable
- 1-1 Diesel Generator is NOT operating.
INITIATING CUES:
During performance of ONP 25.2, "Alternate Safe Shutdown Procedure", the Shift Manager directs you to start 1-1 Diesel Generator, energize 1C Bus then close breakers 152-103 (starts SW Pump P-7B) and 152-108 (Bus 13) per ONP-20 section 4.4.2.
PALISADES NUCLEAR PLANT Page 3 of 13 OCTOBER 2012
JPM SYSTEM J EVALUATOR CUE: Provide candidate a working copy of ONP-20, section 4.4.2.
Proc. Step TASK ELEMENT 1 STANDARD Grade For D/G 1-1: Trips all breakers on 1C Bus electrically, by using the hand switch, or mechanically, using a.1 TRIP all breakers on Bus 1C electrically or S U the mechanical trip plunger located bottom mechanically. center of the breaker inside the cubicle.
Comment:
EVALUATOR CUE: As each breaker is opened electrically, the green and, if applicable, white breaker status lights are LIT and the red breaker status light is OFF.
EVALUATOR NOTE: As each breaker is opened mechanically, the breaker status flag reads OPEN.
CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade REFER TO Attachment 3, "'C' and 'D' Bus Fuse Designations," AND REMOVE Charging Motor Circuit Fuses AND Close and Trip Circuit Fuses for all breakers on Simulates removing BRK CLOSING COIL Bus 1C EXCEPT the following: FRN-R-2.5 and BRK CLOSE AND TRIP a.2 S U CIRCUIT 30A fuses for all breakers except 152-103, SW Pump P-7B 152-103, 152-107 and 152-108.
152-107, D/G 1-1 to Bus 1C 152-108, Station Power Trans EX-13 Feeder Breaker Comment:
EVALUATOR NOTE: Do not allow the student to open the cubicle door. A picture of the inside of a typical breaker is attached to this JPM. Have the student show which fuses would be removed and how they would be removed.
EVALUATOR CUE: Provide attachment 3 at this time and ask candidate:
What are the electrical safety requirements for performing this attachment? (IF the candidate cannot answer this question, THEN ask Where are these requirements located?)
Candidate answer (Critical): 100% natural fabric clothing (or EN-IS-123, Electrical Safety)
EVALUATOR CUE: The required breaker's fuses are removed (as each breaker fuse is removed).
EVALUATOR CUE: [after fuses removed] lights on breaker door are extinguished.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 4 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 3 STANDARD Grade OBTAIN Remote-Local-Transfer Switch Obtains RLTS handles from cubicle above a.3 Handles from the cubicle above 152-102, S U breaker 152-102 Dilution Water Pump P-40A.
Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade Refer to Attachment 2, "Effects of Placing RLTS Switches in the Local Position," to Reviews Attachment 2 for the effects of placing a.4 review the effects of placing the D/G 1-1 1-1 Diesel Generator RLTS in the LOCAL S U Control Circuit RLTS Switches in the position LOCAL position.
Comment:
EVALUATOR CUE: Provide attachment 2 at this time.
Proc. Step TASK ELEMENT 5 STANDARD Grade ISOLATE the D/G 1-1 Control Circuits by placing the Remote-Local-Transfer Switches on the D/G Exciter Control Panel Simulates placing HS-C22-RLTS and HS-G20-a.5 S U (HS-C22-RLTS) and D/G 1-1 Engine RLTS to the LOCAL position Gauge Panel (HS-G20-RLTS) in the LOCAL position.
Comment:
EVALUATOR CUES
- HS-C22-RLTS is in LOCAL position and red light is OFF
- HS-G20-RLTS is in LOCAL position.
EVALUATOR NOTE: There are no indicating lights for HS-G20-RLTS.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 6 STANDARD Grade ISOLATE the following Breaker Control Circuits by placing the following Remote-Local-Transfer Switches to the LOCAL position. Simulates placing HS-152-107 RLTS (Brkr.
152-107), HS-152-103 RLTS (Brkr. 152-103),
a.6 S U Breaker Service Remote-Local-Transfer Switch HS-152-108 RLTS (Brkr. 152-108) to the 152-107 D/G 1-1 HS-152-107RLTS LOCAL position.
152-103 P-7B HS-152-103RLTS 152-108 Bus 13 HS-152-108RLTS Comment:
EVALUATOR CUE: Hand switch is in the LOCAL position (as each hand switch is place in the LOCAL position)
CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade REFER TO Attachment 3, "'C and 'D' Bus Fuse Designations," AND REMOVE the Simulates removing the 30 AMP BREAKER Close and Trip Circuit fuses from the CLOSE AND TRIP CIRCUIT fuses from following breakers: breakers 152-107, 152-103, and 152-108 a.7 S U 152-103, SW Pump P-7B 152-107, D/G 1-1 to Bus 1C (One set of fuses, right side, is removed from 152-108, Station Power Trans EX-13 each breaker)
Feeder Breaker Comment:
EVALUATOR NOTE: Do not allow the student to open the cubicle door. A picture of the inside of a typical breaker is attached to this JPM. Have the student show which fuses would be removed.
EVALUATOR CUE: 30 AMP BREAKER CLOSE AND TRIP CIRCUIT fuse is removed (as each fuse is removed).
EVALUATOR NOTE: Electrical safety requirements are identical to Task Element 2.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 8 STANDARD Grade IF breaker status lights are not illuminated Determines step is not required because the a.8 after operating the Remote-Local-Transfer S U breaker status lights are LIT for the breakers Switches, THEN PERFORM the following:
Comment:
EVALUATOR CUE: The breaker status lights are LIT.
Proc. Step TASK ELEMENT 9 STANDARD Grade START D/G 1-1 as follows:
PLACE Engine Control Switch on Local Simulates placing local 1-1 DG Engine Control a.9 (a) Gauge Board to START position Switch to START and then removes handle S U (b) momentarily.
from control switch REMOVE handle from Engine Control Switch.
Comment:
EVALUATOR CUE: 1-1 DG control switch is in START, engine is NOT running and did NOT attempt to start.
EVALUATOR CUE: IF candidate asks for any readings on the Diesel Generator to verify that it is operating, cue the operator that the reading indicates engine is not running.
(Speed: 0 RPM, Frequency: 0 Hz, Voltage: 0 kilovolts)
CRITICAL STEP PALISADES NUCLEAR PLANT Page 7 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 10 STANDARD Grade IF D/G 1-1 did not attempt to start after performing Step (a) above, THEN PRESS Simulates depressing and holding for at least a.9 (c) AND HOLD the Air Start Motor Solenoid five seconds the Air Start Motor Solenoid S U Override pushbutton for at least five Override pushbutton seconds.
Comment:
EVALUATOR NOTE: If the candidate places the control switch to STOP after performing step a.9(a), then the diesel will not develop proper voltage. Cue that voltage is zero volts.
EVALUATOR CUE: 1-1 DG Air Start Motor Solenoid Override pushbutton has been depressed for more than 5 seconds, and diesel engine is running.
EVALUATOR CUE: IF candidate asks for any readings on the diesel generator to verify that is operating, cue the operator that the reading indicated is correct for normal unloaded conditions. (Speed: 900 RPM, Frequency: 60 Hz, Voltage: 2400 volts)
EVALUATOR NOTE: Alarms on local panel are ENGINE TROUBLE and LOW RAW WATER PRESSURE. Alarms do NOT reset if reset button depressed.
CRITICAL STEP Proc. Step TASK ELEMENT 11 STANDARD Grade IF D/G 1-1 did not start, THEN GO TO Section 4.5.
Operator determines that this step is not a.9 (d) IF the D/G output voltage on any phase is applicable because the Diesel Generator is S U (e) greater than 2530 volts, OR less than 2070 running.
volts, OR is erratic, THEN GO TO Section
4.7.1. Comment
EVALUATOR NOTE: If the candidate placed the DG control switch to STOP after attempting to start for the first time and candidate attempts to go to section 4.7.1 after cue that voltage is zero, provide CUES as appropriate that voltage does not recover when performing this step. The only action that will recover voltage is placing the DG control switch to START and then letting go.
PALISADES NUCLEAR PLANT Page 8 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 12 STANDARD Grade ENERGIZE Bus 1C by locally closing a.10 Simulates closing breaker 152-107 S U 152-107, D/G 1-1 to Bus 1C.
Comment:
EVALUATOR CUE: The red breaker status light is LIT and the green breaker status light is OFF.
CRITICAL STEP Proc. Step TASK ELEMENT 13 STANDARD Grade a.11 Locally CLOSE 152-103, SW Pump P-7B. Simulates closing breaker 152-103 S U Comment:
EVALUATOR CUE: Thermal/Hydraulic Shock Prevention actions have been completed.
EVALUATOR CUE: The red breaker status light is LIT and the green breaker status light is OFF.
CRITICAL STEP Proc. Step TASK ELEMENT 14 STANDARD Grade Locally CLOSE 152-108, Station Power a.12 Simulates closing breaker 152-108 S U Trans EX-13 Feeder Breaker.
Comment:
EVALUATOR CUE: The red breaker status light is LIT and the green breaker status light is OFF.
CRITICAL STEP PALISADES NUCLEAR PLANT Page 9 of 13 OCTOBER 2012
JPM SYSTEM J Proc. Step TASK ELEMENT 15 STANDARD Grade CONTACT Control Room if available to verify Critical SW Header "B" pressure is greater than 42 psig. IF Control Room is a.13 Simulates closing breaker 152-108 S U unavailable, THEN ENSURE PI-1472, Diesel Generator Raw Water Pressure, greater than 25 psig.
Comment:
EVALUATOR CUE: When candidate attempts to read PI-1472, use pen to indicate a reading of 60 psig.
EVALUATOR CUE: After candidate validates Raw Water pressure, end the JPM.
END OF TASK PALISADES NUCLEAR PLANT Page 10 of 13 OCTOBER 2012
JPM SYSTEM J SIMULATOR OPERATOR INSTRUCTIONS NONE PALISADES NUCLEAR PLANT Page 11 of 13 OCTOBER 2012
JPM SYSTEM J Picture of a Typical 2400V Breaker Cubicle Fuse Arrangement PALISADES NUCLEAR PLANT Page 12 of 13 OCTOBER 2012
JPM SYSTEM J CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Start-up Transformer 1-2 and Safeguards 1-1 Transformer are NOT available.
- A fire in the Control Room damaged Bus 1C load shed circuits.
- The fire in the Control Room also damaged 1-1 Diesel Generator control circuits.
- The Control Room is NOT habitable.
- 1-1 DG is NOT operating.
INITIATING CUES:
During performance of ONP 25.2, "Alternate Safe Shutdown Procedure," the Shift Manager directs you to start 1-1 Diesel Generator, energize 1C Bus and close breakers 152-103 (SW Pump P-7B) and 152-108 (Bus 13) per ONP-20, section 4.4.2.
PALISADES NUCLEAR PLANT Page 13 of 13 OCTOBER 2012
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS K TITLE: SECURE FROM A WASTE GAS RELEASE CANDIDATE:
EXAMINER:
JPM SYSTEM K JOB PERFORMANCE MEASURE DATA PAGE Task: Secure from Waste Gas Release Alternate Path: NO Facility JPM #: 2010 NRC EXAM K/A: 071K4.04 Importance: RO: 2.9 SRO: 3.4 K/A 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-18A, Radioactive Waste System - Gaseous 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 OCTOBER 2012
JPM SYSTEM K EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
- SOP-18A, Radioactive Waste System - Gaseous 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
- 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-68B, per SOP-18A, Section 7.5, step nn.
PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012
JPM SYSTEM K EVALUATOR NOTE: Prior to starting System K JPM Task Elements, ask the Candidate to locate Panel C-33, Redundant Safety Injection Panel (Panel that was used in Simulator for System I JPM).
Proc. Additional TASK ELEMENT for STANDARD Grade Step System I JPM (2012 NRC Exam Only)
Locate Panel C-33, Redundant Safety Injection Panel. Candidate locates Panel C-33. S U Comment:
CRITICAL STEP RWP INFORMATION FOR 2012 NRC EXAM:
RWP 2012-005, Task 2 PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012
JPM SYSTEM K EVALUATOR CUE: Provide candidate a working copy of SOP-18A, Section 7.5 place kept through step mm.
Proc. Step TASK ELEMENT 1 STANDARD Grade SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge Header Valves Simulates closing MV-WG719 by turning nn.1 S U T-68A/B/C: handwheel clockwise
- MV-WG719, T-68A, B & C Outlet Isolation Comment:
EVALUATOR NOTE: Task Elements 1 and 2 can be performed in any order since they are bulleted substeps EVALUATOR CUE: MV-WG719 handwheel cannot be turned any further clockwise CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge Header Valves Simulates closing MV-WG718A by turning nn.1 S U T-68A/B/C: handwheel clockwise
- MV-WG718A, T-101A, B, C Outlet Isolation Comment:
EVALUATOR NOTE: Task Elements 1 and 2 can be performed in any order since they are bulleted substeps EVALUATOR CUE: MV-WG718A handwheel cannot be turned any further clockwise CRITICAL STEP PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012
JPM SYSTEM K Proc. Step TASK ELEMENT 3 STANDARD Grade CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
nn.2.a Simulates placing HS-1123 in CLOSE position S U PLACE in CLOSE position HS-1123, Waste Gas Decay Tanks Discharge, at C-40.
Comment:
EVALUATOR CUE: CV-1123 green light is lit, red light if off.
CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows: Simulates turning HIC-1123 regulator valve nn.2.b S U SET to zero (0) psi HIC-1123, Waste counter-clockwise until zero (0) psi is indicated Gas Discharge To Stack.
Comment:
EVALUATOR CUE: HIC-1123 indicates 0 psi Proc. Step TASK ELEMENT 5 STANDARD Grade OPEN ONE of the following Drain Valves Simulates opening MV-CA352 for one (1) to Drain selected WGDT for one (1) minute by turning handwheel counter-clockwise nn.3 minute, THEN CLOSE: S U and then simulates closing MV-CA352 by MV-CA352 turning handwheel clockwise Comment:
EVALUATOR NOTE: Opening MV-CA352 opens CV-1120B.
EVALUATOR CUES:
- 1. MV-CA352 handwheel cannot be turned any further counter-clockwise
- 2. one minute has elapsed
- 3. MV-CA352 handwheel cannot be turned any further clockwise CRITICAL STEP PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012
JPM SYSTEM K Proc. Step TASK ELEMENT 6 STANDARD Grade NOTIFY CRS that T-68B, WGDT, release n/a secured CRS notified release secured S U Comment:
END OF TASK PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012
JPM SYSTEM K CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 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 INITIATING CUES:
The CRS has directed you to secure from the batch release of T-68B, per SOP-18A, Section 7.5, Step nn.
PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012