ML041700462
ML041700462 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 03/15/2004 |
From: | Bailey R American Electric Power Co |
To: | NRC/RGN-III |
References | |
50-315/OL04-301, 50-316/OL04-301 | |
Download: ML041700462 (135) | |
Text
NRC2004-Inp01 TITLE Locally Restore CR Ventilation per 01-OHP- REVISION 0 4025-R-14 PROGRAM NRC License Exam TIME 15 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-INP01 REVISION: 0 Locally Restore CR Ventilation per 01-OHP-4025-R-14 REFERENCES 01-OHP-4025-R-14 Rev. 2 Restore Control Room Ventilation TASKS Task: 0280250104 Align ESW to the Control Room Air Conditioning Air Handling Units K/A: APE 068 AA1.24 Ability to operate and/or monitor the Control Room re-accessability as applied to Control Room Evacuation.
K/A IMPORTANCE: RO: 3.0 SRO 3.6 EVALUATION SETTING In-Plant HANDOUTS Task Briefing Copy of 01-OHP-4025-R-14, Restore Control Room Ventilation ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3
TITLE: NRC2004-INP01 REVISION: 0 Locally Restore CR Ventilation per 01-OHP-4025-R-14 Task Objectives/Standards The North Control Room Ventilation is Running with ESW aligned for Cooling.
Task Briefing You are the Unit 1 AEO.
A small fire in the Unit 1 Control Room Control Panel has caused the Loss of Ventilation to the control room. The US has directed you to Restore the North Control Room Ventilation per 01-OHP-4025-R-14, Restore Control Room Ventilation, using R-14-2.
Page 3 of 3
TITLE: NRC2004-INP01 - Locally Restore CR Ventilation per 01-OHP-4025-R-14 REVISION: 0 General CUES:
- 1. Provide candidate copies of 01-OHP-4025-R-14
- 2. State all procedure prerequisites have been met.
ACTIONS:
Requests Control Room to Verify 1E ESW is in Service Cue: Control Room operator reports 1E ESW pump is in Service Verify Power to 1-AB-D-2C Cue: Operator reports 1-AB-D-2C has power.
Verify North Control Room Air Handling Unit - In Service Cue: North Air Handling Unit is LOUD & VIBRATING. (If asked, VDI-315 DP indicator reads 0.49)
Verify North Control Room Chiller Compressor - In Service Cue: Panel Switch in ON with RED indicator light NOT LIT {OR Compressor motor is WARM to touch}
Verify North Control Room Chiller Water Pump - In Service Cue: Panel Switch in RUN with GREEN indicator light LIT
{OR Pump motor is WARM to touch}
Operator informs control room of RNO actions Page of 4 Revision 0
TITLE: NRC2004-INP01 - Locally Restore CR Ventilation per 01-OHP-4025-R-14 REVISION: 0
{NOTE: Student MUST complete Att A prior to performing Step 5}
Place 1-PP-82N Control Switch in STOP position CUE: Switch is in the STOP position Place Compressor Control Switch in OFF position CUE: Switch is in the OFF position CT: Place valve 1DW-163N in the CLOSED position Cue: You feel movement, Movement has stopped.
Verify valve1DW-165N in the CLOSED position Cue: As found (Stem inserted)
CT: Place valve 1DW-166N in the CLOSED position Cue: You feel movement, Movement has stopped.
CT: Place valve 1ESW-169N in the CLOSED position Cue: You feel movement, Movement has stopped.
CT: Place valve 1ESW-170N in the CLOSED position Cue: You feel movement, Movement has stopped.
Verify valve1ESW-297 is in the CLOSED position Cue: As found (Stem inserted)
Page of 4 Revision 0
TITLE: NRC2004-INP01 - Locally Restore CR Ventilation per 01-OHP-4025-R-14 REVISION: 0 Verify valve 1ESW-276N is in the CLOSED position Cue: As found (Stem inserted)
CT: Place valve 1-ESW-296 in the OPEN position Cue: You feel movement, you feel resistance.
CT: Place valve 1-ESW-168N in the OPEN position Cue: You feel movement, you feel resistance.
CT: Place valve 1-ESW-171N in the OPEN position Cue: You feel movement, you feel resistance. You hear flow noise & feel vibration in piping CUE: Inlet/Bypass valves (1-VRV-315) stem indicates FULLY UP CUE: Acknowledge report that ESW flow initiated to North Control Room Air Handling Unit.
Page of 4 Revision 0
TITLE: NRC2004-INP01 - Locally Restore CR Ventilation per 01-OHP-4025-R-14 REVISION: 0 Checks that ventilation is restored.
Reports complete CUE: Acknowledge completion of R-14-2 to restore Unit 1 North Control Room Air Conditioning Unit to service.
Evaluator: JPM IS COMPLETE Page of 4 Revision 0
Task Briefing You are the Unit 1 AEO.
A small fire in the Unit 1 Control Room Control Panel has caused the Loss of Ventilation to the control room. The US has directed you to Restore the North Control Room Ventilation per 01-OHP-4025-R-14, Restore Control Room Ventilation, using R-14-2.
NRC2004-Inp01.doc Page 1 of 1
Alternate Path JPM NRC2004-Inp02 TITLE Locally Restore CRID Inverters per ECA-0.0 REVISION 0 PROGRAM NRC License Exam TIME 10 Minutes Revision 0:
New JPM written to validate local action required by EOP 1/2 OHP 4023 ECA-0.0 Modified for RO22 ILT Audit exam.
DATE:
DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NUMBER NRC2004-Inp02 REVISION: 0 AND TITLE:
Locally Restore CRID Inverters per ECA-0.0 References Procedure Number Proc Title 01-OHP 4023 ECA-0.0 Loss Of All AC Power 01-OHP-4021-082-008, Operation of CRID Power Supplies, Attachment 20, CRID 4 - Inverter to Normal Source UFSAR Section 8.3.3, 120 Volt AC Vital Instrument Bus System Design Basis Documents: DB-12-120V, 120 VAC System AEP Elementary Diagrams:
- 1. OP-1-12050, 120/208V AC Control Room Instrument Distribution Cabinets CRID-I Thru CRID IV, Engineered Safety System (Unit 1)
- 2. OP-1-98081, 120V AC Instrument Distribution Cab. CRID-II (Sheet 1 of 2)
- 3. OP-1-98082, 120V AC Instrument Distribution Cab. CRID-II (Sheet 2 of 2)
KA: KA Title APE 057 AA1.01 (3.7*/3.7) Loss of Vital AC Electrical Bus - Ability to Operate - Manual Inverter Swapping Task Number: Task Title 0820420104 Transfer CRID Power From the Alternate Source to the Inverter Evaluation Setting In Plant Handouts Task Briefing 01-OHP-4021-082-008 Attachment 20, CRID 4 - Inverter to Normal Source, pages 83 - 86 Attachments None Simulator Setup None - In Plant JPM Page 2 of 3
COURSE NUMBER NRC2004-Inp02 REVISION: 0 AND TITLE:
Locally Restore CRID Inverters per ECA-0.0 Task Objectives/Standards Terminal Objectives:
CRID 4 is powered from its normal source of power, (inverter)
Task Briefing Both Unit 1 Emergency Diesel Generators have failed and been declared INOPERABLE due to Zebra mussel fouling of the heat exchangers.
A loss of all AC Power occurs Power has been restored to T11A & T11B buses. The control room crew is at step 29 of 01-OHP 4023 ECA-0.0. When power was restored, CRID 4 transferred to its alternate source of power.
You have been called to the control room and directed to restore CRID 4 to the Normal Source of Power using Attachment 20, CRID 4 - Inverter to the Normal Source, of 01-OHP-4021-082-008.
Notify the control room when the task is complete.
Page 3 of 3
COURSE NUMBER NRC2004-Inp02 REVISION: 0 AND TITLE:
Locally Restore CRID Inverters per ECA-0.0 Operator checks the supply breaker ON.
(Located outside AB Battery Room)
Cue: Breaker is in the UP (ON) position Operator checks the input breaker ON.
Cue: Breaker is in the UP (ON) position Operator checks the Output Voltage and Frequency.
Cue: Output voltage indicates 120.; frequency indicates 59.8 Operator checks inverter Output and Input Breaker positions Cue: Breakers are in the UP (ON) position Operator checks the Alternate source light Cue: Alternate Source Supplying Load light is LIT Operator checks Manual Output Selector switch Cue: Switch is in the Normal Output position Operator checks the In Sync light Cue: In Sync light is NOT lit CT: Operator simulates placing the Manual Output Selector switch in the ALT Output position Cue: Manual Output switch is in the ALT OUTPUT position Page 1 of 3
COURSE NUMBER NRC2004-Inp02 REVISION: 0 AND TITLE:
Locally Restore CRID Inverters per ECA-0.0 CT: Operator simulates opening 1CRID-4-INV-CB4 Cue: Alt AC Input breaker is in the DOWN (OFF) position Operator requests MTI to adjust Inverter to 60Hz Cue: MTI has adjusted the frequency to 60HZ CT: Operator simulates closing 1CRID-4-INV-CB4 Cue: Alt AC Input breaker is in the UP (ON) position CT: Operator simulates placing the Manual Output Selector switch in the NORMAL Output position Cue: (When Operator returns to step 4.9)
IN SYNC light is lit.
CT: Operator checks the lockout light Cue: Auto Retransfer Lockout light is LIT CT: Operator simulates pressing the Auto Retransfer Reset Pushbutton Cue: Auto Retransfer Lockout light is OFF Operator simulates pressing the Inverter to load pushbutton Cue: Button is depressed. ALT Source to Load light is OFF &
Inverter Output Supplying Load light is ON Operator checks parameters of the CRID 4 inverter Cue: All Parameters are normal Cue: Control Room Reports Bus Voltage is normal EVALUATOR: This completes the JPM.
Page 2 of 3
COURSE NUMBER NRC2004-Inp02 REVISION: 0 AND TITLE:
Locally Restore CRID Inverters per ECA-0.0 FN1 FN2 PCBD ASSY TC NO. 2 Page 3 of 3
Task Briefing Both Unit 1 Emergency Diesel Generators have failed and been declared INOPERABLE due to Zebra mussel fouling of the heat exchangers.
A loss of all AC Power occurs Power has been restored to T11A & T11B buses. The control room crew is at step 29 of 01-OHP 4023 ECA-0.0. When power was restored, CRID 4 transferred to its alternate source of power.
You have been called to the control room and directed to restore CRID 4 to the Normal Source of Power using Attachment 20, CRID 4 - Inverter to the Normal Source, of 01-OHP-4021-082-008.
Notify the control room when the task is complete.
NRC2004-Inp02.doc Page 1 of 1
COURSE NUMBER NRC2004-Inp03 REVISION: 0 AND TITLE:
Shift TDAFP Suction to ESW NRC2004-Inp03 TITLE: Shift Turbine Driven Auxiliary Feed REVISION 0 Pump Suction to ESW :
PROGRAM NRC License Exam TIME: 15 minutes DATE:
DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NUMBER NRC2004-Inp03 REVISION: 0 AND TITLE:
Shift TDAFP Suction to ESW REFERENCES 02-OHP 4022.055.003, Rev. 6b Loss of Condensate to Auxiliary Feedwater Task Number: Task Title 0560230401 Align alternate suction sources to the AFW pumps.
KA: KA Title APE 054 AA1.01 (4.5/4.4) Loss of Main FW - Ability to operate AFW Controls, including the use of alternate AFW sources.
EVALUATION SETTING In Plant HANDOUTS Task Briefing Copy of 02-OHP-4022-055-003, Step 13 Page 2 of 3
COURSE NUMBER NRC2004-Inp03 REVISION: 0 AND TITLE:
Shift TDAFP Suction to ESW TASK OBJECTIVES/STANDARDS ESW has been aligned to the suction of the Unit 2 Turbine Driven Auxiliary Feed pump.
TASK BRIEFING You are an extra operator.
The Shift Manager directs you to locally align ESW to the Unit 2 Turbine Driven Auxiliary Feed pump in accordance with Step 13 of 2-OHP 4022.055.003, Loss of Condensate to Auxiliary Feedwater pumps.
You must manually open 2-WMO-753, ESW supply to TDAFW, since it has no power available.
Page 3 of 3
COURSE NUMBER NRC2004-Inp03 REVISION: 0 AND TITLE:
Shift TDAFP Suction to ESW General Feedback:
Valve full travel should be acknowledged by stating resistance is felt in that direction ACTIONS:
Operator breaks seal then closes 2-ESW-140.
Cue: You feel movement; you feel resistance.
CT: Operator breaks seal then opens 2-ESW-240.
Cue: You feel movement; you feel resistance.
CT: Operator pushes de-clutch lever in the direction of the arrow then releases the de-clutch lever.
CT: Operator opens 2-WMO-753 (turns hand-wheel Counter-clockwise.)
Cue: You feel movement; you feel resistance. Position indicator moves to the INLINE position.
The Operator checks over the auxiliary feed pump and informs the control room the pump is ready for a start.
Cue: Control room acknowledges that ESW is aligned to the TDAFP suction.
TERMINATION CUE: This JPM is Complete.
Page 1 of 1
Task Briefing You are an extra operator.
The Shift Manager directs you to locally align ESW to the Unit 2 Turbine Driven Auxiliary Feed pump in accordance with Step 13 of 2-OHP 4022.055.003, Loss of Condensate to Auxiliary Feedwater pumps.
You must manually open 2-WMO-753, ESW supply to TDAFW, since it has no power available.
NRC2004-Inp03.doc Page 1 of 1
NRC2004-Inp04 TITLE Local Control of RHR Valve for RCS Cooldown REVISION 0 PROGRAM NRC License Exam TIME 12 Minutes DATE:
DEVELOPING Name: S. Pettinger 01/18/04 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for REVISION: 0 AND TITLE: RCS Cooldown References 01-OHP-4025-LS-7, Rev 4a RCS Cooldown using RHR Task: APR0010604 Local Control of RHR and CVCS air operated regulating valves K/A CROSS
REFERENCE:
005 A2.04 K/A IMPORTANCE: RO 2.9 SRO 2.9 Evaluation Settings In Plant Simulation Unit 1 609 elevation of Aux Building Handouts Task Briefing for NRC2004-Inp04 Copy of 01-OHP-4025-LS-7-2, RCS Cooldown Using West RHR Train Attachments None Simulator Setup None Page 2 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for REVISION: 0 AND TITLE: RCS Cooldown Task Objectives/Standards Establish local control of RHR valves during RCS cooldown per 01-OHP-4025-LS-7, observing applicable precautions and limitations and procedural steps.
Task Briefing Unit 1 is in Mode 4 with a cooldown to cold shutdown in progress using the west train of RHR. A fire has prevented the remote operation of valve 1-IRV-320, 1W RHR HX Outlet Flow Control valve.
Control Air system is available.
The operators have implemented 01-OHP-4024-LS-7, RCS Cooldown using RHR.
The US directs you to perform the RNO actions of step 5 in LS-7-2 to allow local operation of 1-IRV-320 and report when complete.
No hazardous conditions have been identified in route to or at the local control station. No special tools are required to perform the task.
Page 3 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for RCS Cooldown REVISION: 0 AND TITLE:
General CUES:
Remote operation of 1-IRV-320 is unavailable Using provided procedure copy operator performs actions of RNO:
Operator locates local control station in Hallway by U-1 RHR HX rooms Operator locates hose for 1-IRV-320 & verifies number match CT: Operator (simulates) closes normal air supply valve (CA-2031)
CUE: You feel movement; You feel resistence CT: Operator (simulates) disconnects air hose from normal supply (quick disconnect)
CT: Operator (simulates) connects to emergency control air supply (quick disconnect)
CT: Operator (simulates) opens emergency control air supply valve (CA-2029)
CUE: You feel movement; You feel resistence Page 1 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for RCS Cooldown REVISION: 0 AND TITLE:
NOTE: Pressure regulator handwheel turns CLOCKWISE to raise pressure. Normally left in the full counter-clockwise position.
CUE: Pressure gauge reads ZERO psig (FULL OPEN)
Operator reports 1-IRV-320 is aligned for local operation.
CUE: Control Room directs you to cycle 1-IRV-320 closed, the open.
CT: Operator (simulates) adjusts pressure regulator for 1-IRV-320 to verify valve operation - CLOSE, then OPEN CUE: Control Room operator reports:
Page 2 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for RCS Cooldown REVISION: 0 AND TITLE:
-IRV-320 is full closed
- (At 0 - 3 psig) 1-IRV-320 is full open CUE: Control Room acknowledges 1-IRV-320 is open. US directs you to close 1-IRV-320.
Page 3 of 3
COURSE NUMBER NRC2004-Inp04 Local Control of RHR Valve for RCS Cooldown REVISION: 0 AND TITLE:
(Operator verified 1-IRV-320 functional in Step g. of RNO)
CUE: If asked, Another operator verified 1-IRV-320 is functional at the valve.
CT: Operator adjusts pressure regulator output to 15 psig and reports 1-IRV-320 is closed.
CUE: Control Room acknowledges 1-IRV-320 is closed.
JPM IS COMPLETE Page 4 of 3
TASK BRIEFING Unit 1 is in Mode 4 with a cooldown to cold shutdown in progress using the west train of RHR. A fire has prevented the remote operation of valve 1-IRV-320, 1W RHR HX Outlet Flow Control valve.
Control Air system is available.
The operators have implemented 01-OHP-4024-LS-7, RCS Cooldown using RHR.
The US directs you to perform the RNO actions of step 5 in LS-7-2 to allow local operation of 1-IRV-320 and report when complete.
No hazardous conditions have been identified in route to or at the local control station. No special tools are required to perform the task.
NRC2004-Inp04.doc Page 1 of 1
NRC2004-Inp04 TITLE Local Operation of U-1 SG PORVs (MRV-213 REVISION 0 and 243)
PROGRAM NRC License Exam TIME 10 Minutes DATE:
DEVELOPING Name: 10/10/03 INSTRUCTOR(S): Signature:
Page 1 of 3
TITLE: NRC2003-INP04 REVISION: 0 Local Operation of U-1 SG PORVs (MRV-213 and 243)
REFERENCES 1-OHP 4025.LS-4 Rev. 1 Steam Generator 1/4 Level Control Section LS-4-3 Steam Generator 1/4 PORV Control TASKS Task: 0510090504 Locally Operate Steam Generator PORVs K/A: APE 068 AA1.01 Control Room Evacuation - Ability to Operate S/G Atmospheric Relief Valve K/A IMPORTANCE: RO: 4.3 SRO 4.5 EVALUATION SETTING In-Plant HANDOUTS Task Briefing 01-OHP 4025.LS-4-3 ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3
TITLE: NRC2003-INP04 REVISION: 0 Local Operation of U-1 SG PORVs (MRV-213 and 243)
Task Objectives/Standards MRV-213 and MRV-243 (SG PORVs) have been locally opened.
TASK BRIEFING A loss of All AC power has occurred in Unit One. We are at the point where we are to depressurize intact S/G's to 200 psig.
The Unit 2 plant air compressor is tagged out for maintenance. The US directs you to line up to dump steam from #11 and #14 S/G's by using LS-4-3 of procedure 1-OHP-4025.LS-4.
US directs you to call him/her when you have opened #1 and #4 SG PORVs to 25%. You are the extra AEO.
Page 3 of 3
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 General CUES:
- 1. Provide candidate copy of 01-OHP-4025-LS-4
- 2. If asked, all procedure prerequisites have been met.
General Feedback:
Valve travel should be acknowledged by stating resistance is felt in that direction.
State that LS-3-3 is not complete.
Closes valve 12-CA-2341 Checks Isolation Valves Cue: 4 valves are open Checks 12-N-130 Cue: Valve is open Page 1 of 6 Revision 0
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 Checks 12-GPI-300 Cue: 12-GPI-300 indicates 1100#.
Verifies valves 12-N-132 and 12-N-135 are open Cue: Valves are full open Page 2 of 6 Revision 0
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 CT: Simulates opening valve 1-N-304 CT: Simulates opening valve 1-N-363 Checks Nitrogen Supply header Pressure Cue: Give indication at 1-GRV-354 outlet pressure gage that nitrogen pressure is 85 psig.
Page 3 of 6 Revision 0
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 CT: Simulates opening 1-N-308 CT: Simulates opening 1-N-307 Checks 1-MRV-213 and 1-MRV-214 Cue: Indication 0% for both controllers Page 4 of 6 Revision 0
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 CT: Simulates placing 1-MRV-213 and 1-MRV-243 to LOCAL position Cue: You feel the switch click into place.
Page 5 of 6 Revision 0
TITLE: NRC2003-INP04 - Local Operation of U-1 SG PORVs (MRV-213 and 243) REVISION: 0 CT: Simulates raising the output on 1-QR-78 Cue: You hear a loud flow noise coming from above you.
Give PORV 1-MRV-213 position on local controller.
CT: Simulates raising the output on 1-QR-81 Cue: You hear a loud flow noise coming from above you.
Give PORV 1-MRV-243 position on local controller.
Terminate JPM once report is made that the PORVs are opened Evaluator: JPM IS COMPLETE Page 6 of 6 Revision 0
Task Briefing A loss of All AC power has occurred in Unit One. We are at the point where we are to depressurize intact S/G's to 200 psig.
The Unit 2 plant air compressor is tagged out for maintenance. The US directs you to line up to dump steam from #11 and #14 S/G's by using LS-4-3 of procedure 1-OHP-4025.LS-4.
US directs you to call him/her when you have opened #1 and #4 SG PORVs to 25%. You are the extra AEO.
NRC2004-Inp04a.doc Page 1 of 1
NRC2004-Inp05 TITLE RCP Seal Injection via CVCS Cross-Tie to REVISION 0 Maintain Pressurizer Level PROGRAM NRC License Examination TIME 20 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/30/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level REFERENCES 1-OHP 4025.LS-6, rev. 2a RCS Make-Up, Seal Injection, And Boration With CVCS Cross-Tie TASKSs Task Number Task Title 0030560406 Cross-tie CVCS systems 0030530406 Establish charging flow to maintain PZR level K/A Number: 022 AA1.01 Ability to operate the CVCS letdown and charging as they apply to a Loss of Reactor Coolant Pump Makeup K/A IMPORTANCE: RO: 3.4 SRO: 3.3 EVALUATION SETTING In PlantUnit 1, Simulation only HANDOUTS Task Briefing Copy of 01-OHP 4025.LS-6-1, Seal Injection from CVCS Cross-Tie Copy of 01-OHP 4025.LS-6-2, PZR Level Control via CVCS Cross-Tie ATTACHMENTS None SIMULATOR SETUP None Page 2 of 3
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level TASK OBJECTIVES/STANDARDS CVCS crosstie operations in progress.
TASK BRIEFING Unit 1 has experienced a loss of all charging.
The Unit Supervisor directs you to establish Unit 1 RCP seal injection from Unit 2 in accordance with 1-OHP 4025.LS-6, beginning with LS-6-1 at step 1.
You are to accomplish this evolution by performing LS-6-1, Seal Injection from CVCS Cross-Tie, to establish supply from Unit 2, then performing LS-6-2, Pressurizer Level Control via CVCS Cross-Tie, through step 2 to establish seal injection flow.
Notify the control room when Unit 1 seal injection has been established.
Page 3 of 3
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level General Feedback;
- 1. Valve full travel should be acknowledged by stating Resistance is felt in that direction.
- 2. Discharge header crosstie valve position may be determined by observing the sliding pointer on the yoke of the valve. When the pointer is down at the bonnet, the valve is closed ACTIONS:
Operator verifies all valves are CLOSED.
Cue: All valves are as indicated. (Pointer is all the way in)
Page 1 of 4
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level Operator checks valve position CLOSED using placard.
{NOTE: Should use placard on stanchion by 12-QFI-201.}
Cue: Placard is correct OR valves are closed, if operator goes into pump rooms to verify position.
CT: Operator simulates cutting seal and opening valve.
Cue: You feel movement, you feel resistance.
Operator reports seal injection from CVCS Cross-Tie is aligned.
Cue: Control room acknowledges seal injection aligned via CVCS Cross-Tie and instructs you to continue with LS-6-2 and initiate CVCS Cross-Tie operations.
Page 2 of 4
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level Operator simulates establishing communication with the control room.
Cue: Control room communicator is online and standing by.
Cue: If asked, RCP Thermal Barrier cooling is in service.
CT: Operator (simulates) CLOSES 1-EPT-200 valve.
Cue: You feel movement, you feel resistance.
Page 3 of 4
TITLE: NRC2004-Inp05 REVISION: 0 RCP Seal Injection via CVCS Cross-Tie to Maintain Pressurizer Level Operator checks pressure indication on 12-QFI-201 at ZERO Cue: Gage indication is ZERO (0%)
CT: Operator simulates cutting seal and slowly opens valve 1-CS-535.
Cue: When monitored locally, RCP seal injection indicates 3 gpm per RCP.
CUE: IF asked, Pressurizer Level is stable Operator reports to the Main Control Room that CVCS crosstie operations are in progress Cue: Control Room acknowledges CVCS Cross-Tie flow established.
EVALUATOR: This completes the JPM.
Page 4 of 4
Task Briefing Unit 1 has experienced a loss of all charging.
The Unit Supervisor directs you to establish Unit 1 RCP seal injection from Unit 2 in accordance with 1-OHP 4025.LS-6, beginning with LS-6-1 at step 1.
You are to accomplish this evolution by performing LS-6-1, Seal Injection from CVCS Cross-Tie, to establish supply from Unit 2, then performing LS-6-2, Pressurizer Level Control via CVCS Cross-Tie, through step 2 to establish seal injection flow.
Notify the control room when Unit 1 seal injection has been established.
NRC2004-Inp05.doc Page 1 of 1
Alternate Path JPM NRC2004-Inp06 TITLE Perform Local DG Trip and Isolation REVISION 0 PROGRAM NRC License Exam TIME 17 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/23/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3 Revision 0
TITLE: NRC2004-Inp06 REVISION: 0 Perform Local Diesel Generator Trip and Isolation References 02-OHP-4025-LTI-3, Rev 0 Local Diesel Generator Trip and Isolation Task: 0320250604 Locally trip the Emergency Diesel Generator K/A: APE 068 AA1.31 Ability to operate and/or monitor the EDG as applied to Control Room Evacuation.
K/A IMPORTANCE: RO 3.9 SRO 4.0 Evaluation Setting In plant, Unit 2 591elevation CD DG room and 609 elevation 4KV room Handouts Task Briefing Copy of 02-OHP-4025-LTI-3, Local Diesel Generator Trip and Isolation Picture of the inside of a 4KV Breaker Control Power (Top) Cubicle Attachments None Simulator Setup None Page 2 of 3 Revision 0
TITLE: NRC2004-Inp06 REVISION: 0 Perform Local Diesel Generator Trip and Isolation Task Objectives/Standards Perform a local trip and isolation on Unit 2 CD Diesel Generator per 02-OHP-4025-LTI-3, observing applicable precautions and limitations and procedural steps.
Task Briefing Following a fire event on Unit 2, the 2CD Diesel Generator started but failed to load.
The US directs you to locally trip and isolate the 2CD Diesel Generator in accordance with 02-OHP-4025-LTI-3-2 (pages 5 and 6).
Page 3 of 3 Revision 0
TITLE: NRC2004-Inp06 REVISION: 0 Perform Local Diesel Generator Trip and Isolation GENERAL CUES:
2CD Diesel Generator started but failed to load after a fire event on Unit 2.
CT: Operator (simulates) depressing local EMERGENCY TRIP CUE: CD EDG is still Operating CT: Operator (Simulates) closing 2-DG-184C & 2-DG-186C CUE : Handwheel has stopped turning.
CT: Operator (Simulates) closing 2-DG-138C & 2-DG-144C CUE : Handwheel has stopped turning.
CT: Operator (Simulates) opening 2-DG-252C & 2-DG-254C CUE : Handwheel has stopped turning. Air is blowing from the drain valves and air receiver pressure is lowering to 0 psig.
CUE: 2 CD EDG has stopped running.
Page 1 of 2 Revision 0
TITLE: NRC2004-Inp06 REVISION: 0 Perform Local Diesel Generator Trip and Isolation NOTE: Operator leaves the 2CD DG room and proceeds to the 4KV Switchgear Room (609 TB)
NOTE: Operator (simulates) dons Full Flash Equipment EVALUATOR NOTE: Use attached picture (Inside of a 4KV Breaker Control Power (Top) Cubicle) to evaluate operators ability to locate control power fuses.
CT: Operator locates T21D8 breaker and (simulates) removes control power fuses CUE: Green lights OFF on front of breaker panel.
CT: Operator verifies breaker T21D8 tripped CUE: Breaker T21D8 green OPEN flag is showing.
CT: Operator locates T21C3 breaker and (simulates) removes control power fuses CUE: Green lights OFF on front of breaker panel.
CT: Operator verifies breaker T21C3 tripped CUE: Breaker T21C3 green OPEN flag is showing.
Reports task completed.
JPM IS COMPLETE.
Page 2 of 2 Revision 0
Task Briefing Following a fire event on Unit 2, the 2CD Diesel Generator started but failed to load.
The US directs you to locally trip and isolate the 2CD Diesel Generator in accordance with 02-OHP-4025-LTI-3-2 (pages 5 and 6).
NRC2004-Inp06.doc Page 1 of 1 Revision 0
NRC2004-SIM01 TITLE Perform Hot Shutdown Panel Pressurizer REVISION 0 Backup Heater Operability Test.
PROGRAM NRC License Exam TIME 10 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-SIM01 REVISION: 0 Perform Hot Shutdown Panel Pressurizer Backup Heater Operability Test.
REFERENCES 02-OHP-4030-214-049 Rev. 1a Hot Shutdown Panel Operability Test Pressurizer Backup heater Operability Test.
TASKS Task: 0021060201 Operate the Pressurizer backup Heaters from the HSD Panel K/A: SYS 010 A4.02 PZR Pressure Control System - Ability to operate Pressurizer Heaters.
K/A IMPORTANCE: RO: 3.6 SRO 3.4 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing Copy of 01-OHP-4030-214-049, Attachment 5, Pressurizer Backup Heater Operability Test ATTACHMENTS None SIMULATOR SETUP
- 1. Initialize simulator to IC 943
- 2. FREEZE the simulator.
Page 2 of 3
TITLE: NRC2004-SIM01 REVISION: 0 Perform Hot Shutdown Panel Pressurizer Backup Heater Operability Test.
Task Objectives Group C Pressurizer Heaters are transferred to the HSD panel, energized, and then Transferred back to Main CR operation.
Task Briefing You are an extra RO.
The US directs you to perform Step 4.1 of Attachment 5, Pressurizer Backup Heater Operability Test in 02-OHP-4030-214-049, Hot Shutdown panel Operability Test, and submit your results for review.
A Unit 2 Control Room operator is standing by to assist.
Page 3 of 3
TITLE: NRC2004-SIM01 - Perform Hot Shutdown Panel Pressurizer Backup Heater REVISION: 0 Operability Test.
General CUES:
- 1. Provide candidate copies of 02-OHP-4030-214-049 Attachment 5.
CUE: If asked, all procedure prerequisites have been met.
CUE: Evaluator will act as Control Room Communicator CUE: Plant Conditions are appropriate for conducting this test. Train B Heaters are in use in the Control Room.
Page 1 of 5 Revision 0
TITLE: NRC2004-SIM01 - Perform Hot Shutdown Panel Pressurizer Backup Heater REVISION: 0 Operability Test.
Requests Control Room Operator OPEN T21D9 Cue: T21D9 is Open CT: Places PZR HTRS CRC Transfer switch to HSD Operator verifies Annunciator 208 - Drop 49 is alarming CUE: If asked, Annunciator 208 - Drop 49 has alarmed.
CT: Places TR21D9 to CLOSE CT: Places GRC1 to CLOSE CT: Places GRC1 to TRIP and then NEUT CT: Places GRC2 to CLOSE CT: Places GRC2 to TRIP and then NEUT CT: Places GRC3 to CLOSE CT: Places GRC3 to TRIP and then NEUT Page 2 of 5 Revision 0
TITLE: NRC2004-SIM01 - Perform Hot Shutdown Panel Pressurizer Backup Heater REVISION: 0 Operability Test.
CT: Places TR21D9 to OPEN CT: Places PZR HTRS GRC Transfer switch to CTRL RM CUE: Annunciator 208 - Drop 49 has CLEARED.
CUE: Independent Verification of the Alarm is Completed CUE: Restore TR21PHC to its original position.
Operator closes TR21PHC breaker.
N/A these steps.
Page 3 of 5 Revision 0
TITLE: NRC2004-SIM01 - Perform Hot Shutdown Panel Pressurizer Backup Heater REVISION: 0 Operability Test.
N/A these steps.
Operator reviews Acceptance Criteria.
Page 4 of 5 Revision 0
TITLE: NRC2004-SIM01 - Perform Hot Shutdown Panel Pressurizer Backup Heater REVISION: 0 Operability Test.
Enters Test Start time.
Signs and Dates that test was completed Evaluator: JPM IS COMPLETE Page 5 of 5 Revision 0
Task Briefing You are an extra RO.
The US directs you to perform Step 4.1 of Attachment 5, Pressurizer Backup Heater Operability Test in 02-OHP-4030-214-049, Hot Shutdown panel Operability Test, and submit your results for review.
A Unit 2 Control Room operator is standing by to assist.
NRC2004-Sim01.doc Page 1 of 1
NRC2004-SIM02 TITLE Subcooling Margin Determination REVISION 0 PROGRAM NRC License Exam TIME 15 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination References 02-OHP-4023-SUP-001, Subcooling Margin Determination TASKS Task: 0020210505 Determine RCS subcooling with Adverse Containment APR0050601 Determine RCS subcooling K/A: EPE 0038 EA1.08 SGTR: Ability to monitor Core Cooling monitor K/A IMPORTANCE: RO: 3.7 SRO 3.8 Evaluation Setting Simulator Handouts Task Briefing 02-OHP-4023-SUP.001 Attachments None Simulator Setup
- 1. Initialize the Simulator to 943.
- 2. Insert the following overrides: (Fail Tsat/Psat readings to Subcooling Margin Monitor)
- IOV ZAOSATMTR_2 at 100%
- IOV ZAOSATMTR_4 at 100%
- 3. IMF CR0145 to 2250 Page 2 of 3
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination Task Objectives/Standards Correctly determines subcooling using 02-OHP-4023-SUP-001.
Task Briefing You are an extra RO.
A SGTR has occurred and the Unit Supervisor directs you to check subcooling using procedure 02-OHP-4023-SUP-001, Subcooling Margin Determination.
Page 3 of 3
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination General CUES:
If asked, all procedure prerequisites and previous steps have been have been met/performed.
Note: Values not provided for following steps as plant is cooling down. Enter values as candidate reads them.
CT: Uses 2-NPS-11_ to record lowest RCS Pressure.
RCS Pressure _____________ psig CT: Determines RCS Saturation temperature is _______
Records RCS Saturation temperature on Attachment 1 Page 1 of 4 Revision 0
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination CT: Accesses Screen TC MAP1 or TC MAP2 on PPC to Determine 5 Highest CETCs and records on Attachment 1 1 - _______ -________ oF 2 -________ -________ oF 3 -________ -________ oF 4 -________ -________ oF 5 -________ -________ oF CT: Calculates an average of _______o F CT: Adds 10 to reach an adjusted temperature of _____o F Records adjusted average CETC temperature on Attachment 1.
CT: Determines that Subcooling is - ______o F Records Subcooling on Attachment 1 Evaluator: JPM IS COMPLETE Page 2 of 4 Revision 0
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination For Reference ONLY Page 3 of 4 Revision 0
TITLE: NRC2004-SIM02 REVISION: 0 Subcooling Margin Determination For Reference ONLY Page 4 of 4 Revision 0
Task Briefing You are an extra RO.
A SGTR has occurred and the Unit Supervisor directs you to check subcooling using procedure 02-OHP-4023-SUP-001, Subcooling Margin Determination.
NRC2004-Sim02.doc Page 1 of 1
Alternate Path JPM NRC2004-SIM03 TITLE Isolate Ruptured Steam Generator REVISIO 0 N
PROGRAM NRC License Exam TIME 20 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator REFERENCES 02-OHP-4023-E-3 Rev. 10 Steam Generator Tube Rupture TASKS Task: EOP0020501 Isolate Ruptured Steam Generator K/A: EPE 038 EA1.32 SGTR - Isolation of Ruptured Steam Generator K/A IMPORTANCE: RO: 4.6 SRO 4.7 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing Copy of 02-OHP-4023-E-3, Steam Generator Tube Rupture ATTACHMENTS None SIMULATOR SETUP
- 2. Place simulator in RUN.
- 3. IMF MS22B @ 100 to Fail 2-MRV-220 OPEN
- 4. IMF RC23B @ 40 causing a #22 SGTR of 400gpm.
- 5. Perform actions of E-0 and E-3 through step 2 as appropriate.
- 6. Freeze simulator.
Page 2 of 3
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator TASK OBJECTIVES/STANDARDS
- Steam Generator #22 is isolated from Intact SGs and secondary systems.
TASK BRIEFING You are an extra RO A reactor trip with SI occurred due to a Steam Generator Tube Rupture. 02-OHP-4023-E-0 and 02-OHP-4023-E-3 have been implemented. 02-OHP-4023-E-3 is still in progress. Steam Generator #22 has been identified as the Only ruptured SG.
The Unit Supervisor directs you to perform Step 3 of 02-OHP-4023-E-3 Isolate Flow From Ruptured SG(s).
Page 3 of 3
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator CT: Adjusts 2-MRV-223 controller setpoint to 1040 psig Operator checks 2-MRV-223 CLOSED:
Page 1 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator el 215 Drop 22 is NOT Lit
- Position meter indicates 0%
Page 2 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator CT: Places 2-MCM-221 to CLOSE Verifies SG Blowdown Isolation Valve 2-DCR-320 is CLOSED Page 3 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator Verifies SG Blowdown Sample Valve 2-DCR-302 is CLOSED Places SG Stop valve drain Valve 2-DCR-407 to CLOSE Verifies 2-DRV-407 is CLOSED Checks Steam Line Warming Valves 2-MS-148 and 2-MS-147 are CLOSED CUE: If asked, 2-MS-147 and -148 are CLOSED.
{NOTE: Located in plant above the Unit 2 Lower Airlock}
Page 4 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator CT: Places SG Stop Valve 2-MRV-220 to Trip CLOSE position CT: Identifies that 2-MRV-220 did NOT CLOSE CT: Places 2-MRV-210, 2-MRV-230, and 2-MRV-240 to Trip CLOSE position CT: Places Steam Dumps in OFF position CUE: When acknowledged, The US directs you to perform Attachment A. The crew will continue on in this procedure.
NOTE: The Candidate should then locate and perform Attachment A Page 5 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator Verifies that Aux Steam is supplied by Unit 1.
CUE: Unit 1 reports that they are supplying Aux steam loads.
Verify Main FW pump Steam Isolations 2-ARV-11 and 2-ARV-12 are CLOSED Verifies 2-DRV-407 is CLOSED Verifies Feed Preheating Steam Supply valves - CLOSED Page 6 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator
-MRV-601
- 2-MRV-602 Verifies Reheater Isolation valves - CLOSED
- 2-MRV-431
- 2-MRV-432 CT: Operator CLOSES 2-MRV-411 and 412.
Page 7 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator Verifies Steam Dump valves - CLOSED:
Page 8 of 6
TITLE: NRC2004-SIM03 REVISION: 0 Isolate Ruptured Steam Generator URV-124
- 2-URV-130 2-URV-125
- 2-URV-140 2-URV-135
- 2-URV-111 2-URV-136 Verifies Startup Air Ejectors Steam supply valve - CLOSED:
- 2-SMO-401 CT: Places Turbine Sealing Steam Supply valves -
CLOSED:
- 2-SRV-26
- 2- SRV-27 Verifies Main Steam Lead Drain valves - CLOSED:
- 2-DMO-425 2-DMO-428
- 2-DMO-426 2-DMO-450
- 2-DMO-427 2-DMO-451 Verifies Turbine Bypass Drain valves - CLOSED:
- 2-DRV-405
- 2-DRV-406 EVALUATOR: JPM is COMPLETE Page 9 of 6
Task Briefing You are an extra RO A reactor trip with SI occurred due to a Steam Generator Tube Rupture. 02-OHP-4023-E-0 and 02-OHP-4023-E-3 have been implemented. 02-OHP-4023-E-3 is still in progress. Steam Generator #22 has been identified as the Only ruptured SG.
The Unit Supervisor directs you to perform Step 3 of 02-OHP-4023-E-3 Isolate Flow From Ruptured SG(s).
NRC2004-Sim03.doc Page 1 of 1
NRC2004-Sim04 TITLE Place Excess Letdown in Service REVISION 0 PROGRAM NRC License Exam TIME 10 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NRC2004-Sim04 REVISION: 0 NUMBER AND Place Excess Letdown in Service TITLE:
REFERENCES 02-OHP-4021-003-001 Rev. 22 Letdown, Charging and Seal Water Operation TASKS Task: 0030240101 Place Excess Letdown in Service K/A: 004 A4.06 Ability to manually operate and/or monitor in the control room Letdown isolation and flow control valves K/A IMPORTANCE: RO: 3.6 SRO 3.1 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing 02-OHP-4021-003-001, Attachment 6, Operating Excess Letdown ATTACHMENTS None SIMULATOR SETUP
- 1. Initialize simulator to any at power IC942
- 2. Reduce Normal Letdown to 75 GPM and stabilize PRZ Level.
- 3. FREEZE the simulator.
Page 2 of 3
COURSE NRC2004-Sim04 REVISION: 0 NUMBER AND Place Excess Letdown in Service TITLE:
Task Objectives/Standards Excess Letdown has been established and is being maintained within acceptable operating parameters.
Task Briefing You are the RO.
The US directs you to place Excess letdown in service per Attachment 6 of 02-OHP-4021-003-001, Letdown, Charging and Seal Water Operation, and establish excess letdown heat exchanger outlet temperature control between 140° F and 160° F. Normal letdown will be removed from service to repair a leaking letdown relief valve.
Page 3 of 3
COURSE NUMBER NRC2004-Sim04 - Place Excess Letdown in Service REVISION: 0 AND TITLE:
General CUES:
- 1. Provide candidate copies of 02-OHP-4021-003-001 Attachment 6
- 2. If asked, all procedure prerequisites have been met.
Operator may discuss caution note with US CUE: US is aware of caution note.
NOTE: Operator may verify CCW flow available prior to starting Step 4.1 (indication on Containment Vent Panel).
CUE: Normal letdown isolation was NOT pre-planned.
Operator verifies valves are OPEN.
CUE: Valve position is as indicated Page 1 of 2 Revision 0
COURSE NUMBER NRC2004-Sim04 - Place Excess Letdown in Service REVISION: 0 AND TITLE:
CT: Operator takes control switch for QRV-113 & 114 to OPEN.
{IF asked, CUE: Letdown to the VCT is desired.}
Operator verifies selector switch is in VCT position.
CT: Operator SLOWLY opens QRV-170 while maintaining outlet temperature between 140° F and 160° F (Maximum peak temperature less than 195° F)
CUE: Another operator will remove letdown from service.
Evaluator: JPM IS COMPLETE Page 2 of 2 Revision 0
Task Briefing You are the RO.
The US directs you to place Excess letdown in service per Attachment 6 of 02-OHP-4021-003-001, Letdown, Charging and Seal Water Operation, and establish excess letdown heat exchanger outlet temperature control between 140° F and 160° F. Normal letdown will be removed from service to repair a leaking letdown relief valve.
NRC2004-Sim04.doc Page 1 of 1
NRC2004-Sim05 TITLE Perform Hydrogen Recombiner Functional Test REVISION 0 PROGRAM NRC License Exam TIME 10 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NRC2004-Sim05 REVISION: 0 NUMBER AND Perform Hydrogen Recombiner Functional Test TITLE:
REFERENCES 02-OHP-4030-STP-013A Rev. 6 #2 (Train A) Electric Hydrogen Recombiner Functional Test TASKS Task: 0340230201 Perform Electric Hydrogen Recombiner Semi-annual Functional Test K/A: 028 A4.01 Ability to manually operate and/or monitor in the control room HRPS controls K/A IMPORTANCE: RO: 4.0 SRO 4.0 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing 02-OHP-4030-STP-013A, #2 (Train A) Electric Hydrogen Recombiner Functional Test ATTACHMENTS SIMULATOR SETUP
- 1. Initialize simulator to IC942.
- 2. FREEZE the simulator.
After the Hydrogen Recombiner is started use the following to raise indications when cued.
IOV 2AOH2TEMPB 12.8% for 256° F IOV 2AOH2TEMPB 21.5% for 430° F IOV 2AOH2TEMPB 29.5% for 490° F IOV 2AOH2TEMPB 38% for 760° F IOV 2AOH2TEMPB 46% for 920° F (if candidate does NOT Stop)
Page 2 of 3
COURSE NRC2004-Sim05 REVISION: 0 NUMBER AND Perform Hydrogen Recombiner Functional Test TITLE:
Task Objectives/Standards The #2 Hydrogen Recombiner is operating between 750° F and 850° F.
Task Briefing You are an extra RO.
The US directs you to perform surveillance test procedure 02-OHP-4030-STP-013A, #2 (Train A)
Electric Hydrogen Recombiner Functional Test. All prerequisites are met and have been verified satisfactory. A dedicated AEO has been stationed at the #2 Hydrogen Recombiner area.
Page 3 of 3
COURSE NUMBER NRC2004-Sim05 - Perform Hydrogen Recombiner Functional Test REVISION: 0 AND TITLE:
General CUES:
- 1. Provide candidate copies of 02-OHP-4030-STP-013A.
- 2. If asked, all procedure prerequisites have been met.
Hydrogen Recombiner #1 is Operable RWST system is Operable CUE: Instrument No. is SW01 and Next Due Cal. Date is 04/04/04.
Operator records thermocouple readings using selector switch.
CUE: An AEO is standing by at the #2 Hydrogen Recombiner.
CUE: AEO reports no personnel or obstructions in the vicinity of the #2 Hydrogen Recombiner.
Page 1 of 3 Revision 0
COURSE NUMBER NRC2004-Sim05 - Perform Hydrogen Recombiner Functional Test REVISION: 0 AND TITLE:
CT: Operator places 2-HR2 control switch in RUN, starts the stopwatch, and records start time.
{NOTE: Annunciator Panel 203 Drop 48 may come in -
adjust potentiometer to raise temperature}
CT: Operator slowly rotates HR2 potentiometer clockwise until 40 to 42 kW is indicated.
Operator records thermocouple readings every 15 minutes.
CUE: 15 minutes has elapsed.
(After initial readings have been taken have the simulator operator increase the temperature and then, cue 15 minutes have elapsed. Have the candidate record temperatures and power, then repeat until temperature is >750)
Operator records time, readings and power.
Page 2 of 3 Revision 0
COURSE NUMBER NRC2004-Sim05 - Perform Hydrogen Recombiner Functional Test REVISION: 0 AND TITLE:
When Thermocouple readings are >750° F Operator records current time.
CUE: Stop time = (Time 0 + 60 minutes).- (2 minutes)
Operator calculates time to reach 750° F is between 56 and 60 minutes.
CUE: You have been relieved by another operator.
Evaluator: JPM IS COMPLETE Page 3 of 3 Revision 0
Task Briefing You are an extra RO.
The US directs you to perform surveillance test procedure 02-OHP-4030-STP-013A, #2 (Train A)
Electric Hydrogen Recombiner Functional Test. All prerequisites are met and have been verified satisfactory. A dedicated AEO has been stationed at the #2 Hydrogen Recombiner area.
NRC2004-Sim05.doc Page 1 of 1
Alternate Path JPM NRC2004 Sim06 TITLE Synchronize and Load 2AB DG REVISION 0 PROGRAM NRC License Exam TIME 20 Minutes DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR: Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
COURSE NUMBER NRC2004-Sim06 REVISION: 0 AND TITLE:
Synchronize and Load 2AB DG REFERENCES 02-OHP 4030-STP-027AB, Rev 19 AB Diesel Generator Operability Test (Train B) Attachment 1 Task: 0320180201: Perform EDG Operability Test (STP-027 AB/CD)
K/A CROSS
REFERENCE:
064 A4.06 K/A IMPORTANCE: RO 3.9 SRO 3.9 EVALUATION SETTINGS Simulator HANDOUTS NS02-05-HO-1 Task Brief Copy of Attachment 1 to 02-OHP-4030-STP-027AB with actions completed up to Step 4.18.
ATTACHMENTS
- 1. NONE SIMULATOR SETUP
- 1. Initialize simulator to IC942
- 2. Restore Summary File NRC04-Sim06
- Establish Trigger 1: linked to file TA11 POSITION {EG:CBTA11(3) == -1}
- Assign IOV ZAISSCAB 90 ramped over 2 mins to Trigger 1
- 3. Start 2AB DG using the RUN control switch
- 4. Adjust the DG speed to slightly less than 60 Hz NOTE: On each reset Check that DG2AB Start Gen and 69/4KV Voltmeter Selector is NOT in OFF.
Check that DG2AB Run and Bus T21A & T21B Voltmeter Selector is NOT in OFF Page 2 of 3
COURSE NUMBER NRC2004-Sim06 REVISION: 0 AND TITLE:
Synchronize and Load 2AB DG TASK OBJECTIVES/STANDARDS Synchronize and load the DG2AB to Bus T21A per 02-OHP-4030-STP-027AB.
Determine that a loss of Speed Control capability has occurred on the DG2AB, mitigate the condition by tripping or unloading and shutting down of the DG.
TASK BRIEFING You are an extra operator.
The crew is performing the slow start surveillance test on the 2AB Diesel Generator. Attachment 1 of 02-OHP-4030-STP-027AB has been completed through Step 4.17. A dedicated operator is stationed locally at the 2AB Diesel Generator and is in direct communication.
The US directs you to synchronize and load the 2AB Diesel Generator, starting at Step 4.18 of .
Page 3 of 3
COURSE NUMBER NRC2004-Sim06 REVISION: 0 AND TITLE:
Synchronize and Load 2AB DG GENERAL CUE:
The 2 AB DG has been slow speed started and all actions through step 4.17 have been completed. A dedicated operator has been stationed in the 2AB DG room.
CUE: Local operator is performing Steps 4.20 - 4.25 concurrently.
Operator places both Voltmeters to OFF position Page 1 of 2 Revision 0
COURSE NUMBER NRC2004-Sim06 REVISION: 0 AND TITLE:
Synchronize and Load 2AB DG CT: Operator places DG2AB 4KV CB T21A11 Synch Selector switch in MANUAL CT: Operator adjusts speed so the Synchroscope is rotating SLOWLY in the FAST direction.
Operator adjusts DG2AB run voltage is 2-3 volts higher than Bus T21A voltage.
CT: Operator closes DG2AB 4KV CB T21A11 control switch Operator verifies WHITE light permissive is LIT CT: Operator closes DG2AB Synchronize Master Close switch at 5 min to 12 oclock position.
Operator raises load to 900 -1100 kW (Uncontrolled rise noted)
CT: Operator takes action to unload/trip DG2AB by either:
- Emergency trip pushbutton Page 2 of 2 Revision 0
COURSE NUMBER NRC2004-Sim06 REVISION: 0 AND TITLE:
Synchronize and Load 2AB DG 11 Breaker, then shutdown using normal control switch/emergency trip pushbutton
- Trip open EDG and verify breaker trips CUE: US acknowledges tripping open the T21A11 breaker and stopping the DG OR tripping of the 2AB DG with the Emergency Trip Pushbutton.
EVALUATOR: JPM is COMPLETE Page 3 of 2 Revision 0
TASK BRIEFING You are an extra operator.
The crew is performing the slow start surveillance test on the 2AB Diesel Generator. Attachment 1 of 02-OHP-4030-STP-027AB has been completed through Step 4.17. A dedicated operator is stationed locally at the 2AB Diesel Generator and is in direct communication.
The US directs you to synchronize and load the 2AB Diesel Generator, starting at Step 4.18 of .
NRC2004-Sim06.doc Page 1 of 1
NRC2004-SIM07 TITLE: DILUTE THE RCS REVISION 0 TRAINING NRC License Exam TIME: 10 minutes PROGRAM DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3 Revision 0
TITLE: NRC2004-SIM07 REVISION: 0 Dilute the RCS.
REFERENCES 12-OHP 4021.005.001 Rev. 27 Boron Makeup System Operation TASKS Task: 0050090101 Dilute the RCS K/A: SYS 004 A4.12 CVCS - Ability to manually operate Boration/Dilution batch control K/A IMPORTANCE: RO: 3.3 SRO 3.8 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing 12-OHP-4021-005-001, Boron Makeup System Operation ATTACHMENTS None SIMULATOR SETUP
- 1. Initialize to IC941.
- 2. Freeze the simulator.
Page 2 of 3 Revision 0
TITLE: NRC2004-SIM07 REVISION: 0 Dilute the RCS.
TASK OBJECTIVES/STANDARDS When directed by the US, dilute the RCS by adding a specific quantity of primary water (+/- 10 gallons of desired value) to the RCS in accordance with the procedure and within a reasonable time.
Task Briefing You are the extra RO.
The following conditions exist:
- Unit is in Mode 3 preparing for startup.
- Makeup control set for auto.
- The makeup line is full of primary water.
The US directs you to add 100 gallons of primary water to the RCS in accordance with 02-OHP-4021-005-001 using Normal Dilute Mode.
You are to restore the blender alignment for Auto makeup.
Page 3 of 3 Revision 0
TITLE: NRC2004-SIM07 - Dilute the RCS. REVISION: 0 NOTE to Evaluator:
Student should proceed to step 4.4 Cue: Precautions and Limitations have been met.
Desired volume is given in the briefing and verified by SRO.
Places switch to STOP CT: Places switch to DILUTE CT: PW batch counter set to 100 gallons (using Pre A P/B)
PW flow can be set to any non-zero value.
CUE: If required, Acknowledge as US Expected Alarm CT: Places switch to START Verifies PW pump starts Verifies 2-QRV-422 Throttles Open Verifies 2-QRV-451 Opens CT: PW flow is stopped automatically or manually once 100 gallons (+/-10 gallons)
Page 1 of 2 Revision 0
TITLE: NRC2004-SIM07 - Dilute the RCS. REVISION: 0 Places switch to STOP Operator verifies controller QRV-400 & 451 in AUTO Operator verifies setpoint is set to 20.5 - 21.5 (1517 ppm)
CT:Places switch to AUTO CT:Places switch to START Reports that the dilution is complete and the blender is aligned for Auto CUE: Acknowledge completion of dilution TERMINATE JPM: This JPM is Complete Page 2 of 2 Revision 0
Task Briefing You are the extra RO.
The following conditions exist:
- Unit is in Mode 3 preparing for startup.
- Makeup control set for auto.
- The makeup line is full of primary water.
The US directs you to add 100 gallons of primary water to the RCS in accordance with 02-OHP-4021-005-001 using Normal Dilute Mode.
You are to restore the blender alignment for Auto makeup.
NRC2004-Sim07.doc Page 1 of 1 Revision 0
NRC2004-SIM08 TITLE Adjust Pressure in an SI Accumulator REVISIO 0 N
PROGRA NRC License Exam TIME 15 Minutes M
DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-SIM08 REVISION: 0 Adjust Pressure in an SI Accumulator REFERENCES 02-OHP 4021.008.006 Rev. 4a Adjusting Pressure in an Accumulator TASKS Task: 0080280101 Adjust accumulator pressure.
K/A: SYS 006 A1.13 ECCS - Ability to monitor changes associated with operating Accumulator Pressure.
K/A IMPORTANCE: RO: 3.5 SRO 3.7 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing ATTACHMENTS None SIMULATOR SETUP
- 1. Initialize to IC 941.
- 2. Place simulator in RUN.
- 3. Vent Accumulator #23 to below Notification Limit minimum pressure of 600 psig using IRV-132 and GRV-341 until Panel 206 Drop 23 reaches ~590 psig.
Page 2 of 3
TITLE: NRC2004-SIM08 REVISION: 0 Adjust Pressure in an SI Accumulator Task Objectives The Candidate has successfully adjusted accumulator pressure to 620 psig (610 - 630 psig) in accordance with procedure.
Task Briefing
- 23 SI accumulator pressure is outside the notification limits.
The US has directed you to raise #23 SI accumulator pressure to 620 psig using 02-OHP 4021.008.006, Adjusting Pressure In An Accumulator.
Nitrogen with a pressure of > 700 psig is available as per 12-OHP-4021-030-001. GRV-313, Nitrogen Supply to Accumulator Tanks Pressure Regulating Valve is set at 675 psig. The GRV-313 bypass should not be used.
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TITLE: NRC2004-SIM08 - Adjust Pressure in an SI Accumulator REVISION: 0 General:
Initial conditions are checked.
NOTE: This information is provided in JPM briefing.
CUE: (As Indicated by initial) - Nitrogen has been verified available per 12-OHP-4021-030-001.
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TITLE: NRC2004-SIM08 - Adjust Pressure in an SI Accumulator REVISION: 0 CUE: Precautions and Limitations have been met.
CT: Places 2-IRV-132 to OPEN CT: Operator informs US that Accumulator #23 must be declared INOPERABLE CUE: US Acknowledges that #23 Accumulator is INOPERABLE and has entered it in the Log.
Verifies that GRV-313 is set at desired pressure.
CUE: GRV-313 is set at 700 psig (desired pressure)
CT: Places 2-GCR-314 Control Switch to OPEN Monitors Acc. #23 pressure CT: When Acc #23 pressure is 620 psig, Places 2-GCR-314 Control Switch to CLOSE CT: Places 2-IRV-132 to CLOSE N/A Page 2 of 3
TITLE: NRC2004-SIM08 - Adjust Pressure in an SI Accumulator REVISION: 0 N/A Operator verifies final accumulator pressure is 620 psig (610 - 630 psig).
Report is made to the US that accumulator is at desired pressure and it may be declared OPERABLE TERMINATE JPM is COMPLETE NOTE: If report is made prior to restoring the local valve lineup, the JPM should still be terminated.
Page 3 of 3
Task Briefing
- 23 SI accumulator pressure is outside the notification limits.
The US has directed you to raise #23 SI accumulator pressure to 620 psig using 02-OHP 4021.008.006, Adjusting Pressure In An Accumulator.
Nitrogen with a pressure of > 700 psig is available as per 12-OHP-4021-030-001. GRV-313, Nitrogen Supply to Accumulator Tanks Pressure Regulating Valve is set at 675 psig. The GRV-313 bypass should not be used.
NRC2004-Sim08.doc Page 1 of 1 Revision 0
NRC2004-SIM09 TITLE Respond to a Traveling Screen DP Alarm REVISIO 0 N
PROGRA NRC License Exam TIME 25 Minutes M
DATE:
DEVELOPING Name: S. Pettinger 10/22/03 INSTRUCTOR(S): Signature:
OPERATIONS REVIEW: Name:
Signature:
Page 1 of 3
TITLE: NRC2004-SIM09 REVISION: 0 Respond to a traveling Screen DP Alarm REFERENCES 02-OHP 4024-223 (Drop 18) Rev. 9 ANNUNCIATOR #223 Response: Circulating Water 12-OHP-4022-057-001 Rev. 1a Screen House Forebay Degraded Condition TASKS Task: 0570270101 Monitor Screen wash System Operation K/A: SYS 075 A2.01 CW - ability to predict and correct consequences of Loss of Intake structure.
K/A IMPORTANCE: RO: 3.0 SRO 3.2 EVALUATION SETTING Unit 2 Simulator HANDOUTS Task Briefing 02-OHP 4024-223 (Drop 18) ANNUNCIATOR #223 Response: Circulating Water 12-OHP-4022-057-001 Screen House Forebay Degraded Condition ATTACHMENTS None SIMULATOR SETUP
- 1. Initialize to any Mode 3 IC.
- 2. Place simulator in RUN.
- 3. IMF CW03B 50 (50% = 0-24>4.5 causes traveling screens to operate)
- 4. IRF CWR12 64 (Lake water temp set at 64° F for pump reduction determination)
- 5. IOR AN23(017) ALARM OFF (Defeat Forebay Level Low-Low alarm)
Page 2 of 3
TITLE: NRC2004-SIM09 REVISION: 0 Respond to a traveling Screen DP Alarm Task Objectives The Candidate has successfully operated the Traveling screens by ensuring they are all running in high speed and has Shutdown the #21 and #22 CW pumps in accordance with procedures.
Task Briefing You are an extra operator.
The US has directed you to monitor and respond to any standing or incoming alarms on the Circulating Water (CW) Panel Page 3 of 3
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 General:
Initial conditions are checked.
NOTE: This information is provided in JPM briefing.
Identifies Annunciator and consults this ARP Verifies all Unit 2 Traveling Screens are in Operation.
Contacts Unit 1 to Confirm start of Screens and Pumps CUE: All Unit 1 Screens are operating in slow Speed. The North screen wash pump is operating.
Page 1 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Places All screens to FAST CUE: Spray pattern is effective Identifies that DP is NOT lowering and transitions to 12-OHP-4022-057-001.
Page 2 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Notifies Unit 1 to enter 12-OHP-4022-057-001 CUE: Unit 1 has entered 12-OHP-4022-057-001 Page 3 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Dispatch Operators to monitor for debris intrusion CUE: Operators are assisting in screen monitoring and cleanup. Screens are operating properly but there is a large influx of fish.
N/A - This is Unit 2 CUE: (If required) Unit 1 has dispatched an Operator to Start the backup air compressor.
CT: Identifies that DP is Less than 25 and transitions to Step 5.
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 N/A N/A Step 4 is NOT required.
Page 5 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 CT: Checks Screen DP and determines that it is > 15 inches. If NO, then proceed to Step 6.
{NOTE: Malfunction severity will require performance of Step 5 to complete JPM.}
Determines that 4 CW pumps are operating on Unit 2 With plant shutdown, the maximum power limit has no Impact (2 pumps at highest lake temperature allows 61% power)
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Plant is shutdown and so less than Maximum allowed power.
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Throttles Main Waterbox outlets to raise pressure 3-4 psig.
Selects CW pump #21 or #22 for Shutdown (both pumps will eventually be shutdown - These steps will be repeated)
CT: Place CW pump 21 (22) Control Switch in NEUTRAL CT: Place CW pump 21 (22) Discharge Valve to CLOSE and Place Pump Control Switch in STOP when Discharge valve is fully closed.
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Check Vacuums stable Determines that Screen DP is >6 Returns to Step 5b. to stop second CW pump.
{NOTE: Terminate JPM when both CW pumps #21 and #22 are stopped.}
THIS JPM is COMPLETE Page 9 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator verifies Screen P is <10 OR NOT ALL Circ water pumps are stopped & goes to Step 7.
Page 10 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator verifies Panel 223, Drop 17 is NOT LIT Page 11 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator asks local AEO to report on ICE around screens.
CUE: Local AEO reports NO ICE on the screens.
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator places ALL available screens in RUN Operator verifies at least ONE screen wash pump running.
Operator directs local AEO to place running screen wash pump strainer in continuous backwash.
CUE: Local AEO reports running screen wash pump strainer is in continuous backwash.
Page 13 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator verifies Panel 223, Drop 12 annunciator NOT LIT Page 14 of 16
TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator verifies screen wash pressure is greater than 100 psig.
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TITLE: NRC2004-SIM09 - Respond to a traveling Screen DP Alarm REVISION: 0 Operator verifies screen P is <4.5; IF NO, then performs RNO
- Places ALL available screens in HIGH speed Operator calls local AEO to verify NO screen carryover occurring.
CUE: Local AEO reports NO screen carryover occurring.
Operator verifies screen P is LOWERING; IF NO, then returns to Step 5.c Page 16 of 16
Task Briefing You are an extra operator.
The US has directed you to monitor and respond to any standing or incoming alarms on the Circulating Water (CW) Panel NRC2004-Sim09.doc Page 1 of 1 Revision 0