ML13070A354
| ML13070A354 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/11/2013 |
| From: | Walton R NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| Download: ML13070A354 (108) | |
Text
NRC REGION III INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO SYS A TITLE: TERMINATE FROM EMERGENCY BORATION CANDIDATE:
EXAMINER:
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 2 of 8 OCTOBER 2012 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
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012 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.
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012 EVALUATOR CUE: Provide operator a Working Copy of EOP Supplement 40 and EOP-4.0 Step 22.
Proc. Step TASK ELEMENT 1 STANDARD Grade 2.0.1 Open Charging Pumps Suction From SIRWT Valve, MO-2160 MO-2160 handswitch taken to the open position (valve opens).
S U Comment:
EVALUATOR NOTE: MO-2160 will take a little time to stroke open.
CRITICAL STEP Proc. Step TASK ELEMENT 2 STANDARD Grade 2.0.2 Stop the Boric Acid Pumps.
P-56A P-56B P-56A AND P-56B handswitches to the trip position (Pumps off).
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade 2.0.3 Close the following valves:
Boric Acid Pump Feed Valve, MO-2140 Gravity Feed Valves MO-2169 MO-2170 MO-2140, MO-2169, and MO-2170 handswitches taken to the closed position (valves close)
S U Comment:
EVALUATOR NOTE: MO-2140, MO-2169, and MO-2170 will take a little time to stroke closed.
CRITICAL STEP
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 2.0.4 Ensure closed Charging Pumps Suction VCT Outlet Valve, MO-2087.
MO-2087 verified closed.
S U Comment:
Proc. Step TASK ELEMENT 5 STANDARD Grade 2.0.5 Operate each Charging Pump for at least five minutes.
Determines that all Charging pumps will be left in-service (given in initial conditions).
S U Comment:
EVALUATOR CUE: Inform Operator that five minutes have elapsed.
Proc. Step TASK ELEMENT 6 STANDARD Grade 2.0.6 WHEN each pump has been operated at least five minutes THEN.
Determines that all Charging pumps will be left in-service (given in initial conditions).
S U Comment:
EVALUATOR CUE: Inform Operator to leave all three Charging Pumps in service.
Proc. Step TASK ELEMENT 7 STANDARD Grade n/a EOP Supplement 40 is Signed, Dated/Timed EOP Supplement 40 Signed, Dated/Timed S U Comment:
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 8 STANDARD Grade n/a Notify CRS of the completion of EOP Supplement 40 CRS notified that EOP Supplement 40 complete S U Comment:
END OF TASK
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012 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
JPM SYSTEM A PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012 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 INITIAL LICENSE EXAM JOB PERFORMANCE MEASURE JPM: RO/SRO-I/SRO-U SYS B TITLE: PERFORM POST RAS ACTIONS CANDIDATE:
EXAMINER:
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 2 of 13 OCTOBER 2012 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
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 3 of 13 OCTOBER 2012 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.
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 4 of 13 OCTOBER 2012 EVALUATOR CUE: Provide candidate a Working Copy of EOP Supplement 42 and EOP-4.0 Step 52 Proc. Step TASK ELEMENT 1 STANDARD Grade 2.1.a WHEN SIRWT level lowers to below 2%,
THEN PERFORM ALL of the following
- a. ENSURE BOTH LPSI Pumps trip VERIFY P-67A tripped (red light OFF, green light ON).
AND VERIFY P-67B did not trip (red light ON, green light OFF).
S U Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade 2.1.a.1 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:
a) TRIP the operating LPSI Pump:
P-67B (152-111 CS)
Handswitch 152-111 CS TAKEN to TRIP position S U Comment:
EVALUATOR NOTE: Pump will not trip CRITICAL STEP
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 5 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 3 STANDARD Grade 2.1.a.1 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:
b) IF LPSI pump failed to trip using the previous step, THEN TRIP the operating LPSI pump at the bus:
152-111, Low Press Safety Inject Pump P-67B Breaker Directs Auxiliary Operator to TRIP P-67B locally at it breaker (152-111)
S U 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 2.1 c.iv 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 for at least 30 seconds after the following breaker is OPENED OPEN either of the following breakers supplying the bus 152-105, Station Power Trans 1-2 Breaker HOLD breaker 152-107 (D/G 1-1 To bus 1C) in TRIP and CONTINUE to hold in TRIP for at least 30 seconds after breaker 152-105 (Station Power Transf No 1-2 Bkr) is OPENED S U 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
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 6 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 5 STANDARD Grade 2.1.b CHECK OPEN BOTH Containment Sump Isolation Valves:
CV-3030 CV-3029 VERIFIED OPEN both Containment Sump Isolation valves:
CV-3030 (red light ON, green light OFF).
CV-3029 (red light ON, green light OFF).
S U Comment:
Proc. Step TASK ELEMENT 6 STANDARD Grade 2.1.c.
ENSURE CLOSED BOTH SIRWT Isolation Valves:
CV-3031 (Key: 149)
CV-3057 (Key: 150)
VERIFIED CLOSED both SIRWT Isolation valves:
CV-3031 (red light OFF, green light ON).
CV-3057 (red light OFF, green light ON).
S U Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade 2.1.d ENSURE CLOSED BOTH SI Pump Minimum Flow Stop Valves:
CV-3027 (Key: 28)
CV-3056 (Key 27)
VERIFIED CLOSED both SI Pump Minimum flow Stop Valves:
CV-3027 (red light OFF, green light ON).
CV-3056 (red light OFF, green light ON).
S U Comment:
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 7 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 8 STANDARD Grade 2.1.e ENSURE OPEN both CCW Hx Service Water Outlet valves:
CV-0826 CV-0823 VERIFIED OPEN both CCW Hx Service Water Outlet valves:
CV-0826 (red light ON, green light OFF).
CV-0823 (red light ON, green light OFF).
S U Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade 2.1.f ENSURE CLOSED both CCW Hx TCVs:
CV-0822 CV-0821 VERIFIED CLOSED both CCW Hx TCVs:
CV-0822 CV-0821 S U Comment:
EVALUATOR NOTE: Both CCW Hx TCVs indicate closed when green light is lit above HS-0828.
Proc. Step TASK ELEMENT 10 STANDARD Grade 2.1.g ENSURE HPSI Subcooling Alignment:
- 1) At least one Containment Spray Pump operating for each operating HPSI Pump VERIFIES one Containment Spray Pumps (P-54A) operating (red light ON, green light OFF).
AND VERIFIES one HPSI pump operating. (P-66A).
S U Comment:
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 8 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 11 STANDARD Grade 2.1.g ENSURE HPSI Subcooling Alignment:
- 2) VERIFY OPEN HPSI Subcooling Valve for any operating HPSI Pump CV-3071 VERIFIES OPEN CV-3071 (red light ON, green light OFF).
S U Comment:
Proc. Step TASK ELEMENT 12 STANDARD Grade 2.1.h IF any HPSI pump is operating with subcooling valve closed Determines that this step is not applicable.
S U Comment:
Proc. Step TASK ELEMENT 13 STANDARD Grade 2.1.i IF 2 or 3 Containment Spray Pumps are operating, THEN ENSURE both Containment Spray Valves are in the THROTTLE position.
Determines that this step is not applicable.
S U Comment:
Proc. Step TASK ELEMENT 14 STANDARD Grade 2.1.j IF one Containment spray valve is CLOSED AND one is throttled Determines that this step is not applicable.
S U Comment:
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 9 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 15 STANDARD Grade 2.1.k IF only one Containment Spray Pump is operating, THEN;
S U Comment:
Proc. Step TASK ELEMENT 16 STANDARD Grade 2.1.k IF only one Containment Spray Pump is operating, THEN;
- 2) PERFORM the following to close CV-3001, Containment Spray Valve:
a) PLACE HS-3001C to BYPASS HS-3001C PLACED in BYPASS.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 17 STANDARD Grade 2.1.k IF only one Containment Spray Pump is operating, THEN;
- 2) PERFORM the following to close CV-3001, Containment Spray Valve:
b) ENSURE CLOSED CV-3001 VERIFIES CV-3001 CLOSED (red light OFF, green light ON).
S U Comment:
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 10 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 18 STANDARD Grade 2.1.l IF either Containment Sump isolation valve failed to open, CV-3030 CV-3029 Determines that this step is not applicable.
S U Comment:
Proc. Step TASK ELEMENT 19 STANDARD Grade 2.1.m IF operation of additional spray pumps or HPSI pumps is desired Determines that this step is not applicable.
S U 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 2.1.o IF EITHER of the following exist:
ONLY P-54A Containment Spray Pump operating P-54A OFF THEN CROSSTIE ESS suction headers Determines that another Operator will monitor for this.
S U Comment:
EVALUATOR CUE: Cue Operator that another Operator will crosstie ESS headers.
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 11 of 13 OCTOBER 2012 Proc. Step TASK ELEMENT 22 STANDARD Grade 2.1.p INITIATE refill of the SIRW Tank.
Determines that another Operator will monitor for this.
S U Comment:
EVALUATOR CUE: Cue Operator that another Operator will refill SIRW Tank.
Proc. Step TASK ELEMENT 23 STANDARD Grade n/a NOTIFY the CRS that the post RAS actions have been completed.
CRS NOTIFIED that the post RAS actions have been completed.
S U Comment:
EVALUATOR CUE: Repeat back notification.
END OF TASK
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 12 of 13 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS SIMULATOR SETUP:
Use IC-17 Enter the following malfunctions and overrides:
Location Description Location Event Delay Ramp Final 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.
Perform pre RAS actions in EOP Supplement 42.
When SIRWT level reaches ~ 20%, then freeze simulator and take a snapshot.
JPM SYSTEM B PALISADES NUCLEAR PLANT Page 13 of 13 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 11 OCTOBER 2012 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
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 3 of 11 OCTOBER 2012 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.
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 4 of 11 OCTOBER 2012 EVALUATOR CUE: Provide candidate a working copy of SOP-1B, attachment 6.
Proc. Step TASK ELEMENT 1 STANDARD Grade 2.1a.1 PERFORM the following to OPEN MO-1042A, PZR Power Operated Relief Valve Isolation Valve.
ENSURE the following conditions:
- 1. HS-1042B, PZR to Quench Tank T-73 in CLOSE position.
HS-1042B checked in CLOSE position.
S U Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade 2.1a.2 ENSURE the following conditions:
- 2. MO-1042A, Power Relief Valve Isolation closed.
MO-1042A checked closed.
S U Comment:
Proc. Step TASK ELEMENT 3 STANDARD Grade 2.1a.3 ENSURE the following conditions:
- 3. PCS pressure control established:
SOP-1 2010 to 2100 psia PCS pressure checked between 2010 and 2100 psia S U Comment:
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 5 of 11 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 2.1b PLACE HS-1042B, PZR Quench Tank T-73 to OPEN for approximately 15 seconds, AND THEN PLACE to CLOSE, leaving handswitch in CLOSE position when complete.
HS-1042B placed to OPEN for approx.
15 seconds AND THEN HS-1042B placed to CLOSE, with handswitch left in CLOSE position.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade 2.1c 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 lights (indicates valve is 5% open, green position indication lamp is also lighted at this point).
- 2. PRV-1042B, Power Operated Relief opens.
HS-1042A operated intermittently until red light lights.
S U 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
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 6 of 11 OCTOBER 2012 EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 6 and 7.
Proc. Step TASK ELEMENT 6 STANDARD Grade ARP-8 The following alarms annunciate with PORV leaking:
- 1. EK-1373, SV AND/OR PORV OPEN, (Audible Acoustic Monitor alarm on back of Panel C-11A in alarm from FI-1042B Accelerometer (#4) Hi noise).
- 2. EK-0743, Pressurizer PWR Operated Relief Valve Discharge HI Temp (TIA-0106, Relief and Safety Valve Discharge Temp, reads up-scale).
Following alarms are acknowledged:
- 1. EK-1373, Operator Action: Refer to ONP-18: Follow Up Action: Check Acoustic Monitor Panel for open valve; Check TIA-0106 discharge temperature; Refer to ONP-23.1.
- 2. EK-0743, Operator Action: Refer to ONP-23.1; Follow Up Action: Evaluate desired position of MO-1042A; Refer to LCOs; Refer to ORM.
- 3. Acoustic Monitor Reset pushbutton pushed to silence audible Acoustic Monitor alarm (PORV MOV Block Valve must be closed, for alarm to clear).
S U Comment:
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.
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 7 of 11 OCTOBER 2012 Proc. Step TASK ELEMENT 7 STANDARD Grade ONP-18 or ONP-23.1 Power Relief Valve Isolation MO-1042A closed to isolate leaking PORV.
HS-1042A, Power Relief Valve Isolation placed in CLOSE position until MO-1042A red position indication lamp is OFF and green position indication lamp is ON.
S U Comment:
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 2.2a.1 PERFORM the following to OPEN MO-1043A, PZR Power Operated Relief Valve Isolation Valve.
ENSURE the following conditions:
- 1. HS-1043B, PZR to Quench Tank T-73 in CLOSE position.
HS-1043B checked in CLOSE position.
S U Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade 2.2a.2 ENSURE the following conditions:
- 2. MO-1043A, Power Relief Valve Isolation closed.
MO-1043A checked closed.
S U Comment:
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 8 of 11 OCTOBER 2012 Proc. Step TASK ELEMENT 10 STANDARD Grade 2.2a.3 ENSURE the following conditions:
- 3. PCS pressure control established:
SOP-1 2010 to 2100 psia PCS pressure checked between 2010 and 2100 psia S U Comment:
Proc. Step TASK ELEMENT 11 STANDARD Grade 2.2b PLACE HS-1043B, PZR Quench Tank T-73 to OPEN for approximately 15 seconds, AND THEN PLACE to CLOSE, leaving handswitch in CLOSE position when complete.
HS-1043B placed to OPEN for approx.
15 seconds AND THEN HS-1043B placed to CLOSE, with handswitch left in CLOSE position.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade 2.2c 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 lights (indicates valve is 5% open, green position indication lamp is also lighted at this point).
- 2. PRV-1043B, Power Operated Relief opens.
HS-1043A operated intermittently until red light lights.
S U Comment:
EVALUATOR NOTE: PORV does not open and stays closed and does not leak.
CRITICAL STEP
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 9 of 11 OCTOBER 2012 Proc. Step TASK ELEMENT 13 STANDARD Grade 2.2d IF PRV-1043B, Power Operated Relief opens AND then reseats, THEN repeat Step 2.2.c.
Determines that this step does not apply.
S U Comment:
Proc. Step TASK ELEMENT 14 STANDARD Grade 2.2e WHEN the following conditions exist,
- 1. MO-1043A, Power Relief Valve Isolation is 5% open (red position indication lamp lit).
- 2. PRV-1043B, Power Operated Relief is closed.
THEN FULLY OPEN MO-1043A, Power Relief Isolation.
MO-1043A to the full open position.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 15 STANDARD Grade n/a Notify the CRS that one PORV Block Valve is open.
CRS notified that one PORV Block Valve is open.
S U Comment:
END OF TASK
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 10 of 11 OCTOBER 2012 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, N2 tag next to VCT vent switch USE CAE or:
Location Description Delay Ramp Event Value Final Insert 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
JPM SYSTEM C PALISADES NUCLEAR PLANT Page 11 of 11 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012 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:
______ UNSAT ______
Comments:
Examiner: _______________________________
Date:
Signature
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
SOP-1A, Primary Coolant System 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.
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of SOP-1A, section 7.1.2.
Proc. Step TASK ELEMENT 1 STANDARD Grade o
WHEN starting P-50A, P-50B, or P-50C, THEN VERIFY the vibration indicator for the Primary Coolant Pump to be started indicates less then 2 mils.
Checks vibration monitor on Panel C-12 for P-50A vibration and verifies reading is < 2 mils.
S U Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade p
START the AC or DC Oil Lift Pump for the PCP(s) to be started as directed by the CRS:
Places P-80A hand switch to HAND and verifies red light LIT and green light OFF.
S U Comment:
EVALUATOR NOTE: P-80A started per Initiating Cue.
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade q
IF lift oil pressure interlock is NOT satisfied with one lift pump operating, THEN START the second Oil Lift Pump for the PCP to be started.
Verifies white light above P-50A hand switch is LIT and determines no need to start additional lift pump.
S U Comment:
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade r
IF lift oil pressure interlock is NOT satisfied with both Lift Pumps in operation, THEN NOTIFY Maintenance to prime the Lift Pumps.
Candidate determines this step is N/A.
S U Comment:
Proc. Step TASK ELEMENT 5 STANDARD Grade s
CHECK Annunciators EK-0937, EK-0938, EK-0939, "PRI COOLANT PUMP BACKSTOP OIL LOW FLOW," for pump(s) to be started NOT in alarm (Panel C-12).
Verifies alarm window EK-0937 is clear.
S U Comment:
Proc. Step TASK ELEMENT 6 STANDARD Grade t
VERIFY the PUMP START OIL PERMISSIVE white light illuminated for pump(s) to be started.
Verifies white PUMP START OIL PERMISSIVE light LIT for P-50A.
S U Comment:
Proc. Step TASK ELEMENT 7 STANDARD Grade u
WHEN oil lift pump(s) have been operating for at least two minutes, THEN START the selected Primary Coolant Pump.
After 2 or more minutes, places P-50A hand switch in START and verify red light LIT and green light OFF.
S U Comment:
EVALUATOR CUE: Cue candidate that 2 minutes have elapsed.
CRITICAL STEP
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012 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 w
WHEN both of the following conditions exist:
PCP amps return to normal operating amps following the starting amp surge Two minutes have elapsed from the start of the PCP THEN PERFORM the following:
- 1. PLACE the DC Oil Lift Pump handswitches to AUTO.
- 2. PLACE the AC Oil Lift Pump handswitches to AUTO.
After P-50A amps return to normal following the starting amp surge and after two minutes have elapsed from the start of the PCP:
Places P-80A hand switch to AUTO Verifies P-81A handswitch in AUTO Verifies P-80A and P-81A red lights OFF and green lights LIT.
S U 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 ARP-5 EK-0931 Acknowledge cooling water low flow and high temp alarms and refer to ARP-5.
Acknowledges alarm and refers to ARP-5:
EK-0931, Pri Coolant Pump P-50A CLG WTR LO Flow.
EK-0907 Prim Coolant Pump P-50A HI Temp Overload.
S U Comment:
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 11 STANDARD Grade ARP-5 EK-0931 Confirm rising PCP bearing temperatures by observing Panel C-11 recorder LTVR-0901 indications for P-50A.
Monitors P-50A temperature indications on Panel C-11 recorder and determines temperatures rising at a rapid rate.
S U 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 or 7.1.4.d Stop PCP P-50A.
Places hand switch on C-02 in TRIP and verifies red light OFF and green light LIT.
S U 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 7.1.3.h or 7.1.4.e When at least five minutes have elapsed since stopping P-50A, then stop oil lift pumps.
Places DC (P-81A) and AC (P-80A) Oil Lift Pump hand switches to OFF and verifies green lights LIT and red lights OFF.
S U Comment:
EVALUATOR CUE: Cue candidate that 5 minutes have elapsed.
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 14 STANDARD Grade N/A Inform CRS of status Notifies CRS that P-50A is stopped due to loss of CCW cooling and corresponding high temperatures.
S U Comment:
EVALUATOR CUE: If candidate asks about EM-04-08, STATE that another operator will perform this task.
END OF TASK
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012 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
JPM SYSTEM D PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 8 OCTOBER 2012 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
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012 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.
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012 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 3.7 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 associated pushbutton to bypass MSIV closure:
HS/LPE-50A, BYPASS OF MSIV CLOSURE pushbutton HS/LPE-50A, BYPASS OF MSIV CLOSURE pushbutton depressed S U 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 3.7 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 associated pushbutton to bypass MSIV closure:
HS/LPE-50B, BYPASS OF MSIV CLOSURE pushbutton HS/LPE-50B, BYPASS OF MSIV CLOSURE pushbutton depressed S U 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).
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 3 STANDARD Grade Acknowledge alarm EK-0970 and refer to ARP.
Candidate acknowledges alarm on Panel C-02 and refers to ARP-5.
S U Comment:
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 when 2/4 S/G pressures on either S/G went below 500 psia.
Candidate determines that both MSIVs have closed.
S U Comment:
EVALUATOR CUE: If candidate asks for direction on which procedure to use or action to take, inform them to 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 2.15 ENSURE OPEN both MSIV Bypass Valves:
MO-0501, MSIV CV-0501 Bypass MO-0510, MSIV CV-0510 Bypass Candidate opens MSIV Bypass Valve MO-0501 S U 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
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 6 STANDARD Grade 2.15 ENSURE OPEN both MSIV Bypass Valves:
MO-0501, MSIV CV-0501 Bypass MO-0510, MSIV CV-0510 Bypass Candidate opens MSIV Bypass Valve:
MO-0510 S U 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 N/A Notify CRS that both MSIV Bypass Valves are open due to inability to block auto closure of MSIVs and cooldown has been reestablished.
CRS notified.
S U Comment:
END OF TASK
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012 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.
JPM SYSTEM E PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 11 OCTOBER 2012 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
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 3 of 11 OCTOBER 2012 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.
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 4 of 11 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of SOP-5, section 7.1.1.
Proc.Step TASK ELEMENT 1 STANDARD Grade 7.1.1.a REFER TO Step 5.2.3 for guidance on Service Water Pump operation.
Candidate refers to step 5.2.3 for guidance on SW pump operation.
S U 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 7.1.1 b.1 ENSURE control valves are positioned as follows:
For VHX-4, verify open Inlet Valve CV-0869.
CV-0869 is verified open.
S U 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 7.1.1 b.1 ENSURE control valves are positioned as follows:
For VHX-4, open High Capacity Outlet Valve CV-0867.
High Capacity Outlet Valve CV-0867 is opened.
S U Comment:
CRITICAL STEP
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 5 of 11 OCTOBER 2012 Proc.Step TASK ELEMENT 4 STANDARD Grade 7.1.1 b.1 ENSURE control valves are positioned as follows:
For VHX-1 verify Open Inlet Valve CV-0862.
Inlet Valve CV-0862 is verified open.
S U 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 7.1.1 b.1 ENSURE control valves are positioned as follows:
For VHX-1 open High Capacity Outlet Valve CV-0861.
High Capacity Outlet Valve CV-0861 is opened.
S U Comment:
EVALUATOR NOTE: This step may be performed AFTER Service Water Pump start.
CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade 5.2.3 Monitor Service Water Header pressure and determine that Service Water system pressure is < 50 psig.
Determines that the Standby Service Water Pump P-7C needs to be started because system pressure has lowered to < 50 psig.
May need to respond to alarms EK-0551 and EK-0557: Has AO investigate D/G local alarm boards.
S U Comment:
EVALUATOR CUE: When asked as AO report that D/G local alarm panels indicate low raw water pressure.
CRITICAL STEP
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 6 of 11 OCTOBER 2012 EVALUATOR NOTE: Alternate Path begins here and is covered in task elements 7 through 14 Proc.Step TASK ELEMENT 7 STANDARD Grade n/a Obtain SOP-15, Service Water System procedure, section 7.1.1.
Locates SOP-15, Service Water System procedure.
S U 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 7.1.1.a IF starting the first Service Water Pump, THEN GO TO Section 7.1.5.
Candidate determines this step is N/A.
S U Comment:
Proc.Step TASK ELEMENT 9 STANDARD Grade SOP-15 7.1.1.b IF starting the third Service Water Pump, THEN NOTIFY Chemistry so that they can recalculate mixing basin discharge flow volume.
Notify Chemistry to recalculate Mixing Basin discharge flow volume.
S U Comment:
EVALUATOR CUE: CRS will notify Chemistry of P-7C start so they can recalculate mixing basin discharge flow volume.
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 7 of 11 OCTOBER 2012 Proc.Step TASK ELEMENT 10 STANDARD Grade SOP-15 7.1.1.c ENSURE OPEN associated pump discharge valve:
P-7C MV-SW104 Dispatch AO to check OPEN P-7C discharge valve MV-SW104.
S U Comment:
EVALUATOR (or Simulator Operator) CUE: "MV-SW104 is OPEN" Proc.Step TASK ELEMENT 11 STANDARD Grade SOP-15 7.1.1.d ENSURE motor oil levels normal.
Dispatch AO to check P-7C motor oil levels normal.
S U Comment:
EVALUATOR (or Simulator Operator) CUE: "P-7C Motor oil levels normal" Proc.Step TASK ELEMENT 12 STANDARD Grade SOP-15 7.1.1.e Remove P-7C from standby by placing Control Switch to TRIP.
P-7C Control Switch placed momentarily in TRIP until standby light extinguishes.
S U Comment:
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 8 of 11 OCTOBER 2012 Proc.Step TASK ELEMENT 13 STANDARD Grade SOP-15 7.1.1.f START desired pump from Control Room Handswitch (preferred) or using Handswitch on breaker.
P-7C control switch placed in START and released to mid-position.
S U 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 to > 50 psig.
Verify Service Water Header pressure rises to > 50 psig.
S U 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 7.1.1 b.2 ENSURE all available Containment Air Cooler Fans are operating:
For VHX-1 start fan V-1A (SOP-5).
V-1A is started.
S U Comment:
CRITICAL STEP
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 9 of 11 OCTOBER 2012 Proc.Step TASK ELEMENT 16 STANDARD Grade 7.1.1 b.2 ENSURE all available Containment Air Cooler Fans are operating:
For VHX-1 start fan V-1B (SOP-5)
V-1B is started.
S U Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 17 STANDARD Grade 7.1.1 b.2 ENSURE all available Containment Air Cooler Fans are operating:
For VHX-4 start fan V-4A (SOP-5)
V-4A is started.
S U Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 18 STANDARD Grade 7.1.1 b.2 ENSURE all available Containment Air Cooler Fans are operating:
For VHX-4 start fan V-4B (SOP-5)
V-4B is started.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 19 STANDARD Grade N/A Notify CRS that Containment Air Coolers are aligned with all High Capacity outlet valves open and all fans running.
CRS notified.
S U Comment:
END OF TASK
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 10 of 11 OCTOBER 2012 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}
JPM SYSTEM F PALISADES NUCLEAR PLANT Page 11 of 11 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 8 OCTOBER 2012 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:
______ UNSAT ______
Comments:
Examiner: _______________________________
Date:
Signature
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 3 of 8 OCTOBER 2012 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).
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 4 of 8 OCTOBER 2012 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 d.1 PUSH HIGH pushbutton on front of RIA-1049 and read current High Alarm Setpoint.
"High Alarm" push button on the front of RIA-1049 pushed and current high alarm setpoint is read as 2.70E3 CPM.
S U Comment:
Proc. Step TASK ELEMENT 2 STANDARD Grade d.2 PULL RIA-1049 out from the panel about six inches (6") to access the control buttons.
RIA-1049 pulled out from panel about 6 inches.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 3 STANDARD Grade d.3 VERIFY Function switch is set to 0 as seen on right side of switch.
Checks right side of Function Switch is set to 0.
S U Comment:
Proc. Step TASK ELEMENT 4 STANDARD Grade d.4 PRESS ENTER button to display High Alarm setpoint.
"Enter" button pressed and one digit blinking.
S U Comment:
CRITICAL STEP
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 5 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 5 STANDARD Grade d.5 SET the High Alarm setpoint by performing the following as necessary:
IF selecting another digit, THEN PRESS the DIGIT pushbutton.
IF changing the digit value, THEN PRESS the VALUE pushbutton until value desired for that digit is displayed.
Digit and Value pushbuttons manipulated as necessary to set the high alarm setpoint at 1.10E3.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 6 STANDARD Grade d.6(a)
WHEN entire display indicates desired trip setpoint, THEN:
(a) PRESS ENTER pushbutton.
Enter button pressed.
S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 7 STANDARD Grade d.6(b)
WHEN entire display indicates desired trip setpoint, THEN:
(b) PUSH monitor back into panel.
Monitor pushed back into panel.
S U Comment:
Proc. Step TASK ELEMENT 8 STANDARD Grade d.7 PRESS HIGH pushbutton on front of RIA-1049 to verify high alarm setpoint is correct.
High Alarm" push button pressed and 1.10E3 CPM trip setpoint verified.
S U Comment:
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 6 of 8 OCTOBER 2012 Proc. Step TASK ELEMENT 9 STANDARD Grade d.8 PRESS ALARM ACK button to clear any high alarms that may have come in.
Alarm Ack pushed and Alarms clear.
S U Comment:
Proc. Step TASK ELEMENT 10 STANDARD Grade N/A Notify the CRS that RIA-1049 High Alarm Setpoint is 1100 cpm.
CRS is notified.
S U Comment:
EVALUATOR CUE: As CRS, repeat back the notification.
END OF TASK
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 7 of 8 OCTOBER 2012 SIMULATOR OPERATOR INSTRUCTIONS
- Any IC
- Ensure RIA-1049 high alarm setpoint is set at 2.70E3 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 = xxx-03 [xxx = use last three digits of current year]
Tank = T-91
% released = 10%
Volume released (gal) = 7300 Minimum required Dilution Water Pumps = 1 Minimum required Service Water Pumps = 2 Maximum permitted release rate (gpm) = 250 Authorization Shift Manager = any signature; Date = current date 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
JPM SYSTEM G PALISADES NUCLEAR PLANT Page 8 of 8 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 9 OCTOBER 2012 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
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 3 of 9 OCTOBER 2012 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.
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 4 of 9 OCTOBER 2012 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 7.2.5.a NOTIFY the RETS/REMP Supervisor or Duty Radiation Protection Supervisor to ensure requirements of Chemistry Procedure CH 6.27, "Containment Purge,"
are met.
RETS/REMP Supervisor or Duty HP notified S U Comment:
EVALUATOR CUE: Role play as CRS and notify candidate that RETS/REMP Supervisor has been informed.
Proc.Step TASK ELEMENT 2 STANDARD Grade 7.2.5.b ENSURE one Main Exhaust Fan operating.
V-6A V-6B Candidate verifies Main Exhaust Fan V-6A running on panel C-13.
S U Comment:
Proc.Step TASK ELEMENT 3 STANDARD Grade 7.2.5.c ENSURE the RGEM System is in operation.
Refer to System Operating Procedure SOP-38, "Gaseous Process Monitoring System," for RGEM System.
From Initiating Cue.
S U Comment:
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 5 of 9 OCTOBER 2012 Proc.Step TASK ELEMENT 4 STANDARD Grade 7.2.5.d ENSURE the following Test Tap Valves are LOCKED CLOSED AND CAPPED:
MV-VA506 MV-VA508 MV-VA505 Candidate calls Auxiliary Operator and directs the following valves be checked closed and capped:
MV-VA506 MV-VA508 MV-VA505 S U 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 7.2.5.e INSERT key AND OPEN the following Purge Supply and Exhaust Valves:
CV-1805 (key 272)
CV-1806 (key 274)
CV-1807 (key 275)
CV-1808 (key 277)
CV-1813 (key 273)
CV-1814 (key 276)
Key inserted and the following Purge Supply and Exhaust Valves opened and verifies associated Red light ON and Green light OFF:
CV-1805 (key 272) ____
CV-1806 (key 274) ____
CV-1807 (key 275) ____
CV-1808 (key 277) ____
CV-1813 (key 273) ____
CV-1814 (key 276) ____
S U Comment:
CRITICAL STEP Proc.Step TASK ELEMENT 6 STANDARD Grade 7.2.5.f RECORD in the SOMS Narrative Log the time the valves were opened.
Record the time the valves were opened in the Control Room Logbook.
S U Comment:
EVALUATOR CUE: Role play as CRS and inform candidate that these times have been logged.
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 6 of 9 OCTOBER 2012 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 annunciates.
Applicant refers to ARP-7, EK-1127, Main Exhaust Fan V-6A or B trip.
S U 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 ARP-7 ENSURE STARTED V-6A or V-6B, standby Main Exhaust Fan.
Candidate attempts to start V-6B and determines it will not start.
S U Comment:
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 7 of 9 OCTOBER 2012 Proc.Step TASK ELEMENT 10 STANDARD Grade ARP-7 IF neither Main Exhaust Fan can be started, THEN:
SUSPEND heavy load movements, core alterations and movement of irradiated fuel SECURE any Radioactive Waste Gas Batch per SOP-18A.
SHUTDOWN any Plant ventilation air flow per SOP-24.
Candidate stops Air Room Supply Fan V-46.
S U 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 ARP-7 Manually CLOSE all OPEN purge control valves opened in step 7.2.5.e:
CV-1805 (key 272)
CV-1806 (key 274)
CV-1807 (key 275)
CV-1808 (key 277)
CV-1813 (key 273)
CV-1814 (key 276)
Candidate closes all OPEN purge control valves and verifies associated Red light OFF and Green light ON: (Candidate may refer back to 7.2.5.e as a guide)
CV-1805 (key 272) ____
CV-1806 (key 274) ____
CV-1807 (key 275) ____
CV-1808 (key 277) ____
CV-1813 (key 273) ____
CV-1814 (key 276) ____
S U Comment:
EVALUATOR NOTE: Candidate may start securing other ventilation systems, but stop JPM when Containment Purge is isolated.
CRITICAL STEP END OF TASK
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 8 of 9 OCTOBER 2012 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
JPM SYSTEM H PALISADES NUCLEAR PLANT Page 9 of 9 OCTOBER 2012 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.
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 PALISADES NUCLEAR PLANT Page 2 of 10 OCTOBER 2012 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
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 3 of 10 OCTOBER 2012 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.
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 4 of 10 OCTOBER 2012 EVALUATOR CUE: Provide candidate with a working copy of SOP-7, Attachment 4.
Proc. Step TASK ELEMENT 1 STANDARD Grade 2.1 REFER TO table below to determine applicable Controller, Air Supply and Isolation Valve for Steam Dump being tested:
Candidate determines Controller, Air Supply and Isolation Valve for CV-0780.
S U 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 TAVE to approximately 534°F.
TAVE 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 2.3a For the Steam Dump Group being tested:
MANUALLY CLOSE the CV Isolation for the CV to be tested, THEN THROTTLE OPEN to the specified number of test turns.
Candidate directs Auxiliary Operator to close MV-MS104 and then throttle open 18.5 turns.
S U Comment:
EVALUATOR CUE: Acknowledge direction to AO and report MV-MS104 has been closed and then throttled open 18.5 turns.
SIMULATOR OPERATOR: INSERT SG12 (PIDMS01) Final Value to 50 (MV-MS104 being closed and then throttled open 18.5 turns)
CRITICAL STEP
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 5 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 4 STANDARD Grade 2.3b For the Steam Dump Group being tested:
CLOSE the Air Supply Isolation for the remaining Steam Dump in the group being tested.
Candidate directs Auxiliary Operator to close MV-CA782.
S U Comment:
EVALUATOR CUE: Acknowledge direction to NLO and report MV-CA782 has been closed.
SIMULATOR OPERATOR: INSERT MS21 (PIDMS01) to CLOSE for closing MV-CA782.
CRITICAL STEP Proc. Step TASK ELEMENT 5 STANDARD Grade 2.4a At C-33 Panel, perform the following:
PLACE appropriate Steam Dump Remote Controller to 0% OPEN AND MANUAL.
HIC-0780B verified to be 0% OPEN HIC-0780B placed in MANUAL (green light on, red light off).
- S U Comment:
CRITICAL STEP*
Proc. Step TASK ELEMENT 6 STANDARD Grade 2.4b At C-33 Panel, perform the following:
NOTIFY Control Operator to monitor Steam Dump position indication on C-01 Panel AND TIME Steam Dump stroke from CLOSED to OPEN position.
Control Operator notified.
S U Comment:
EVALUATOR CUE: Acknowledge request to Control Room Operator.
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 6 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 7 STANDARD Grade 2.4c At C-33 Panel, perform the following:
Using appropriate Steam Dump Remote Controller, STROKE the Steam Dump being tested fully OPEN and then CLOSED.
HIC-0780B manual operating lever operated to fully open and then close CV-0780.
S U 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 2.5 IF remaining Steam Dump in applicable group is to be tested, THEN PERFORM the following:
Candidate determines this step is N/A per initiating cue.
S U Comment:
Proc. Step TASK ELEMENT 9 STANDARD Grade 2.6 RETURN affected Steam Dump Remote Controller to AUTO.
HIC-0780A placed in AUTO.
S U Comment:
CRITICAL STEP
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 7 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 10 STANDARD Grade 2.6a FULLY OPEN the affected CV Isolation Valve closed in Step 2.3a.
Candidate directs Auxiliary Operator to fully open MV-MS104.
S U Comment:
EVALUATOR CUE: Acknowledge direction to NLO and report MV-MS104 has been fully opened.
SIMULATOR OPERATOR: INSERT SG12 (PIDMS01) Final Value to 100 for fully opening MV-MS104.
CRITICAL STEP Proc. Step TASK ELEMENT 11 STANDARD Grade 2.6b OPEN Air Supply closed in Step 2.3b.
Candidate directs Auxiliary Operator to open MV-CA782.
S U Comment:
EVALUATOR CUE: Acknowledge direction to NLO and report MV-CA782 has been opened.
SIMULATOR OPERATOR: INSERT MS21 (PIDMS01) Final Value to OPEN for reopening MV-CA782.
CRITICAL STEP Proc. Step TASK ELEMENT 12 STANDARD Grade 2.6c REPEAT Steps 2.3 through 2.4 for remaining Steam Dump in group.
Candidate determines this step is N/A.
S U Comment:
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 8 of 10 OCTOBER 2012 Proc. Step TASK ELEMENT 13 STANDARD Grade 2.6d REPORT results of Steam Dump testing to the System Engineer.
Candidate informs System Engineer either directly or by way of CRS.
S U Comment:
EVALUATOR CUE: Acknowledge report to System Engineer.
Proc. Step TASK ELEMENT 14 STANDARD Grade N/A CRS is notified that testing of CV-0780 has been completed.
CRS notified of operation.
S U Comment:
END OF TASK
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 9 of 10 OCTOBER 2012 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.
JPM SYSTEM I PALISADES NUCLEAR PLANT Page 10 of 10 OCTOBER 2012 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.
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:
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:
______ UNSAT ______
Comments:
Examiner: _______________________________
Date:
Signature
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.
EVALUATOR CUE: Provide candidate a working copy of ONP-20, section 4.4.2.
Proc. Step TASK ELEMENT 1 STANDARD Grade a.1 For D/G 1-1:
TRIP all breakers on Bus 1C electrically or mechanically.
Trips all breakers on 1C Bus electrically, by using the hand switch, or mechanically, using the mechanical trip plunger located bottom center of the breaker inside the cubicle.
S U 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 a.2 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 Bus 1C EXCEPT the following:
152-103, SW Pump P-7B 152-107, D/G 1-1 to Bus 1C 152-108, Station Power Trans EX-13 Feeder Breaker Simulates removing BRK CLOSING COIL FRN-R-2.5 and BRK CLOSE AND TRIP CIRCUIT 30A fuses for all breakers except 152-103, 152-107 and 152-108.
S U 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
Proc. Step TASK ELEMENT 3 STANDARD Grade a.3 OBTAIN Remote-Local-Transfer Switch Handles from the cubicle above 152-102, Dilution Water Pump P-40A.
Obtains RLTS handles from cubicle above breaker 152-102 S U Comment:
CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade a.4 Refer to Attachment 2, "Effects of Placing RLTS Switches in the Local Position," to review the effects of placing the D/G 1-1 Control Circuit RLTS Switches in the LOCAL position.
Reviews Attachment 2 for the effects of placing 1-1 Diesel Generator RLTS in the LOCAL position S U Comment:
EVALUATOR CUE: Provide attachment 2 at this time.
Proc. Step TASK ELEMENT 5 STANDARD Grade a.5 ISOLATE the D/G 1-1 Control Circuits by placing the Remote-Local-Transfer Switches on the D/G Exciter Control Panel (HS-C22-RLTS) and D/G 1-1 Engine Gauge Panel (HS-G20-RLTS) in the LOCAL position.
Simulates placing HS-C22-RLTS and HS-G20-RLTS to the LOCAL position S U Comment:
EVALUATOR CUE: HS-C22-RLTS and HS-G20-RLTS are in LOCAL position.
CRITICAL STEP
Proc. Step TASK ELEMENT 6 STANDARD Grade a.6 ISOLATE the following Breaker Control Circuits by placing the following Remote-Local-Transfer Switches to the LOCAL position.
Breaker Service Remote-Local-Transfer Switch 152-107 D/G 1-1 HS-152-107RLTS 152-103 P-7B HS-152-103RLTS 152-108 Bus 13 HS-152-108RLTS Simulates placing HS-152-107 RLTS (Brkr.
152-107), HS-152-103 RLTS (Brkr. 152-103),
HS-152-108 RLTS (Brkr. 152-108) to the LOCAL position.
S U 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 a.7 REFER TO Attachment 3, "'C and 'D' Bus Fuse Designations," AND REMOVE the Close and Trip Circuit fuses from the following breakers:
152-103, SW Pump P-7B 152-107, D/G 1-1 to Bus 1C 152-108, Station Power Trans EX-13 Feeder Breaker Simulates removing the 30 AMP BREAKER CLOSE AND TRIP CIRCUIT fuses from breakers 152-107, 152-103, and 152-108 S U 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
Proc. Step TASK ELEMENT 8 STANDARD Grade a.8 IF breaker status lights are not illuminated after operating the Remote-Local-Transfer Switches, THEN PERFORM the following:
Determines step is not required because the breaker status lights are LIT for the breakers S U Comment:
EVALUATOR CUE: The breaker status lights are LIT.
Proc. Step TASK ELEMENT 9 STANDARD Grade a.9 (a)
(b)
START D/G 1-1 as follows:
PLACE Engine Control Switch on Local Gauge Board to START position momentarily.
REMOVE handle from Engine Control Switch.
Simulates placing local 1-1 DG Engine Control Switch to START and then removes handle from control switch S U 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
Proc. Step TASK ELEMENT 10 STANDARD Grade a.9 (c)
IF D/G 1-1 did not attempt to start after performing Step (a) above, THEN PRESS AND HOLD the Air Start Motor Solenoid Override pushbutton for at least five seconds.
Simulates depressing and holding for at least five seconds the Air Start Motor Solenoid Override pushbutton S U 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 a.9 (d)
(e)
IF D/G 1-1 did not start, THEN GO TO Section 4.5.
IF the D/G output voltage on any phase is greater than 2530 volts, OR less than 2070 volts, OR is erratic, THEN GO TO Section 4.7.1.
Operator determines that this step is not applicable because the Diesel Generator is running.
S U 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.
Proc. Step TASK ELEMENT 12 STANDARD Grade a.10 ENERGIZE Bus 1C by locally closing 152-107, D/G 1-1 to Bus 1C.
Simulates closing breaker 152-107 S U 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 a.12 Locally CLOSE 152-108, Station Power Trans EX-13 Feeder Breaker.
Simulates closing breaker 152-108 S U Comment:
EVALUATOR CUE: The red breaker status light is LIT and the green breaker status light is OFF.
CRITICAL STEP
Proc. Step TASK ELEMENT 15 STANDARD Grade a.13 CONTACT Control Room if available to verify Critical SW Header "B" pressure is greater than 42 psig. IF Control Room is unavailable, THEN ENSURE PI-1472, Diesel Generator Raw Water Pressure, greater than 25 psig.
Simulates closing breaker 152-108 S U 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
SIMULATOR OPERATOR INSTRUCTIONS NONE
Picture of a Typical 2400V Breaker Cubicle Fuse Arrangement
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.
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 PALISADES NUCLEAR PLANT Page 2 of 7 OCTOBER 2012 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
JPM SYSTEM K PALISADES NUCLEAR PLANT Page 3 of 7 OCTOBER 2012 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.
JPM SYSTEM K PALISADES NUCLEAR PLANT Page 4 of 7 OCTOBER 2012 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 nn.1 SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge Header Valves T-68A/B/C:
MV-WG719, T-68A, B & C Outlet Isolation Simulates closing MV-WG719 by turning handwheel clockwise S U 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 nn.1 SECURE from WGDT release as follows:
- 1. CLOSE appropriate Discharge Header Valves T-68A/B/C:
MV-WG718A, T-101A, B, C Outlet Isolation Simulates closing MV-WG718A by turning handwheel clockwise S U 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
JPM SYSTEM K PALISADES NUCLEAR PLANT Page 5 of 7 OCTOBER 2012 Proc. Step TASK ELEMENT 3 STANDARD Grade nn.2.a CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
PLACE in CLOSE position HS-1123, Waste Gas Decay Tanks Discharge, at C-40.
Simulates placing HS-1123 in CLOSE position S U Comment:
EVALUATOR CUE: CV-1123 green light is lit, red light if off.
CRITICAL STEP Proc. Step TASK ELEMENT 4 STANDARD Grade nn.2.b CLOSE Discharge Control Valve CV-1123, WGDT Discharge, as follows:
SET to zero (0) psi HIC-1123, Waste Gas Discharge To Stack.
Simulates turning HIC-1123 regulator valve counter-clockwise until zero (0) psi is indicated S U Comment:
EVALUATOR CUE: HIC-1123 indicates 0 psi Proc. Step TASK ELEMENT 5 STANDARD Grade nn.3 OPEN ONE of the following Drain Valves to Drain selected WGDT for one (1) minute, THEN CLOSE:
MV-CA352 Simulates opening MV-CA352 for one (1) minute by turning handwheel counter-clockwise and then simulates closing MV-CA352 by turning handwheel clockwise S U 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
JPM SYSTEM K PALISADES NUCLEAR PLANT Page 6 of 7 OCTOBER 2012 Proc. Step TASK ELEMENT 6 STANDARD Grade n/a NOTIFY CRS that T-68B, WGDT, release secured CRS notified release secured S U Comment:
END OF TASK
JPM SYSTEM K PALISADES NUCLEAR PLANT Page 7 of 7 OCTOBER 2012 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.