ML16340B794
| ML16340B794 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/02/2016 |
| From: | NRC/RGN-III |
| To: | Indiana Michigan Power Co, American Electric Power |
| Shared Package | |
| ML15274A375 | List: |
| References | |
| NRC 2016-SIM01 | |
| Download: ML16340B794 (76) | |
Text
NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 1 of 7 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 10 MINUTES NUMBER AND TITLE: NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) REVISION: 0 Examinee's Name: ____________________________________________ __________ Evaluator's Name: : ______________________________________________________
Date Performed: : _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts: : _____________________________________________________
Time to Complete: : _______________________________________________________
Comments:__________________________________________________________________
___________________________________________________________________________
___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 2 of 7 REFERENCES/NRC KA/TASKS Procedure:
1-OHP-4023-FR-S.1 Response to Nuclear Power Generation/ATWS K/A Number:
APE 024 A1.17 {3.9/3.9}
SYS 004 A2.14 {3.8/3.9}
K/A Imp.: RO: SRO: (See K/A Number)
Task Number:
EOP0870501 TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1-OHP-4023-FR-S.1 procedure ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
OPERATIONS JPM NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 3 of 7 SIMULATOR/LAB SETUP
- 1. Initialize simulator to IC
-740 (MODE 1 IC with the following Actions taken).
- 2. Insert MALF RP03A and RP03B, Fail Reactor Trip Breakers CLOSED
- 3. Insert MALF RP10A and RP10B; Fail AUTO SI actuation 4. Manually trip the Main Turbine
- 5. Perform Steps 1
- 4 of 01 OHP 4023-FR-S.1 and place rod control in MANUAL
- 6. Insert Override
- ZGI43BAP2S_U1 to SLOW (Maintains #2 BAP speed in SLOW)
- 7. Insert Override
- ZGIRU20_U1 to IN (Maintains continuos rod motion in MANUAL)
- 8. Insert Malf
- U1_101BAP1 (Failure of the #1 BAP)
- 9. Freeze simulator.
ZGI43BAP2S_U1 ZGIRU20_U1 U1_101BAP1 U1_RP03A U1_RP03B U1_RP10A U1_RP10B OPERATIONS JPM NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 4 of 7 EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING
You are the Reactor Operator. The crew has entered 1-OHP-4023-FR-S.1, Response to Power Generation/ATWS, due to a failure of the reactor to automatically or manually trip. The Balance Of Plant Operator is monitoring Rod Insertion.
INITIATING CUE The Unit Supervisor directs you to initiate Emergency Boration to the RCS in accordance with Step 5 of 1-OHP-4023-FR-S.1. GENERAL STANDARDS/PRECAUTIONS
Operator establishes the Emergency Boration flow from the Charging pumps aligned to the RWST with at least 170 gpm flow.
OPERATIONS JPM NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 5 of 7 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator verifies ONE CCP is running SAT: UNSAT: STANDARD: Operator attempts to start BOTH BAPs in Fast Speed NOTE: #1 BATP will Not Start, #2 BA TP Remains in SLOW Speed.
NOTE: AUTO SI did NOT actuate. Manual SI was NOT performed.
SAT: UNSAT:
STANDARD: Operator implements RNO action with SI NOT Actuated SAT: UNSAT: STANDARD:
Operator Opens at least ONE CCP suction from RWST valve (See nex t Page) SAT: UNSAT:
STANDARD: (CS) Operator OPENs RWST isolation valves IMO
-910 and/or IMO
-911 SAT: UNSAT:
STANDARD: (CS) Operator CLOSEs CCP suction valves QMO
-451 and/or QMO
-452 SAT: UNSAT:
STANDARD: (CS) Operator raises charging flow by adjusting QRV
-251 and/or QRV
-200 to obtain at least 170 gpm charging flow.
SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM01 Perform Emergency Boration During ATWS (ALT) Revision: 0 NRC 2016-SIM01.doc Page 6 of 7 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator verifies normal letdown flow in progress. (Letdown Flow
> 75 gpm) SAT: UNSAT:
STANDARD: Operator verifies PZR pressure is less than 2335 psig.
SAT: UNSAT:
TERMINATION CUE: This JPM is complete.
Revision: 0 NRC 2016-SIM01.doc Page 7 of 7 TASK BRIEFING You are the Reactor Operator. The crew has entered 1-OHP-4023-FR-S.1, Response to Power Generation/ATWS, due to a failure of the reactor to automatically or manually trip. The Balance Of Plant Operator is monitoring Rod Insertion.
The Unit Supervisor directs you to initiate Emergency Boration to the RCS in accordance with Step 5 of 1-OHP-4023-FR-S.1.
NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 1 of 8 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MINUTES NUMBER AND TITLE: NRC201 6-Sim02 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 (Alternate Path)
REVISION: 0 Examinee's Name: __________________________
__________________ __________
Evaluator's Name: : ______________________________________________________
Date Performed: : _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts: : _______
______________________________________________
Time to Complete: : _______________________________________________________
Comments:__________________________________________________________________
_____________________________________________________
______________________
___________________________________________________________________________
OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 2 of 8 REFERENCES/NRC KA/TASKS Procedure:
1-OHP-4023-SUP-015 , R OPERATION OF NORMAL AND EXCESS LETDOWN K/A Number:
SYS 004 A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5/ 43/5 / 45/3 / 45/5)
Isolation of letdown/makeup K/A Imp.: RO: 3.4 SRO: 3.7 Task Number:
0030020101 0030240101 Place Letdown in Service
Place Excess Letdown in Service TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1-OHP-4023-SUP-015 procedure OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 3 of 8 ATTACHMENTS None EVALUATION SETTINGS
Unit 1 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
SIMULATOR/LAB SETUP
- 1. Reset to IC 739 (IC 102 with an SI with ES-1.1 performed through Step 14) 2. Verify ZGI101QRV111 override to CLOSE EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING
You are the RO on Unit 1
. ZGI101QRV111_U1
OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 4 of 8 The unit has experienced a spurious Safety Injection. The crew has transitioned from E
-0 , Reactor Trip or Safety Injection, to ES-1.1 , SI Termination
.
The Unit Supervisor has requested that you place letdown in service in accordance with the 1-OHP-4023-SUP-015, OPERATION OF NORMAL AND EXCESS LETDOWN, per current procedure directions.
GENERAL STANDARDS/PRECAUTIONS Place CVCS letdown in service in accordance with 1
-OHP-4023-SU P-015. Recognize that normal letdown cannot be established and place Excess Letdown in service (Alternate Path).
OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 5 of 8 EXPECTED ACTIONS CUES/STANDARDS ("CS" Indicates Critical Standard)
STANDARD: Operator verifies air is available to containment SAT: UNSAT: Operator places QRV
-302 in the DIVERT position.
SAT: UNSAT: Operator verifies orifice isolation valves are closed (may give switches a 'green target' is desired)
SAT: UNSAT: Operator opens QCR-300/301 open.
SAT: UNSAT:
Operator resets and opens 1-CRV-470. SAT: UNSAT: STANDARD: (CS) Operator attempts to open QRV
-1 11. SAT: UNSAT:
NOTE: QRV-111 will not open.
CUE: If asked inform operator that Excess Letdown is desired.
STANDARD: (CS) Operator goes to Attachment A in accordance with Step 2 RNO due to failure of QRV
-111 to open
. SAT: UNSAT:
OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 6 of 8 EXPECTED ACTIONS CUES/STANDARDS ("CS" Indicates Critical Standard)
STANDARD: Operator verifies CCP suction is aligned as required.
CUE: If Required, Align CCP suction to the RWST.
SAT: UNSAT: STANDARD: Operator verifies Seal Injection Flow is 6
-12 gpm. SAT: UNSAT: STANDARD: Operator checks CCW aligned to Seal Water HX (May dispatch and operator or ask if the system is in normal alignment.
CUE: If Required, CCW flow wa previously establis hed to seal water heat exchanger and the alignment has not been altered SAT: UNSAT: STANDARD:
(CS) Operator opens QCM
-250/350 SAT: UNSAT:
OPERATIONS JPM NRC 201 6-Sim0 2 Establish Letdown In Accordance With 1
-OHP-4023-SUP-015 Revision: 0 NRC 2016-SIM02.doc Page 7 of 8 EXPECTED ACTIONS CUES/STANDARDS ("CS" Indicates Critical Standard)
STANDARD: (CS) Operator open s 2-CCR-460/462 SAT: UNSAT:
STANDARD: (CS) Operator Opens QRV
-113/114. SAT: UNSAT:
CUE: If asked, inform operator that excess letdown return will be aligned to the preferred flowpath.
STANDARD: Operator verifies QRV-171 in the VCT position SAT: UNSAT: STANDARD: (CS) Operator opens QRV-170 while maintaining excess letdown temperature less than 195°F.
SAT: UNSAT: When Excess Letdown is in Service, then TERMINATION CUE:
This JPM is complete.
Revision: 0 NRC 2016-SIM02.doc Page 8 of 8 Task Briefing You are the RO on Unit 1.
The unit has experienced a spurious Safety Injection. The crew has transitioned from E
-0, Reactor Trip or Safety Injection, to ES-1.1, SI Termination.
The Unit Supervisor has requested that you place letdown in service in accordance with the 1-OHP-4023-SUP-015, OPERATION OF NORMAL AND EXCESS LETDOWN, per current procedure directions.
NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 1 of 13 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MINUTES NUMBER AND TITLE: NRC 2016-SIM0 3 Depressurize the RCS to Minimize Backflow/Refill the Pressurizer during SGTR (ALT) REVISION: 0 Examinee's Name:
____________
________________________________ __________
Evaluator's Name:
- ______________________________________________________
Date Performed:
- _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts: : _____________________________________________________
Time to Complete:
- _______________________________________________________
Comments:__________________________________________________________________
_______________________________________
____________________________________
___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 2 of 13 REFERENCES/NRC KA/TASKS Procedure:
2-OHP-4023-E-3 Steam Generator Tube Rupture K/A Number:
EPE 038 EA1.04 Ability to operate and monitor the following as they apply to a SGTR:
PZR spray, to reduce coolant system pressure K/A Imp.: RO: 4.3 SRO: 4.1 Task Number:
EOP0070501 Control RCS Pressure and Inventory following a SGTR TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 2-OHP-4023-E-3, Steam Generator Tube Rupture - Steps 17-20 and Attachment B ATTACHMENTS
None EVALUATION SETTINGS Unit 2 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 3 of 13 SIMULATOR/LAB SETUP Initialize simulator to IC
-73 7 (MODE 1 IC with the following Actions taken).
- 1. Ensure Aux Steam Loads are being supplied by Unit 1 2. IMF RC23 B @ 40 causing a #
2 2 SGTR of 400gpm.
- 4. Perform actions of E-0 and E-3 through step 16 as appropriate.
- 5. Trigger NRV
-163/164 to 5% open when either Red Light is lit.
- a. TRG 2 PZR Spray Open (ZLONRV163
_U 2(2) == 1 or ZLONRV16 4_U 2(2) == 1), b. MF RC15A & RC15B to 5%
on Trigger 2
-151, Caution Tag NRV 15 1 & Block Closed for Leakage, Clearance Tag NRV
-153 & NMO153
- 7. Insert Malfunction RC17B to 0% to fail NRV
-152 closed &Global Malfunction101NMO153 Trg 1 - NMO15 1 to Open (ZGI101NMO15 1_U 2 == 3), MF 101NMO151 OOS Tag NRV & NMO 15 3, Caution Tag NRV & NMO 15 1 Freeze simulator.
U2_EDPR25G U2 NMO151 to Open U2_PZR_Spray_op U2_EDPR22G U2_RC15A U2_RC15B U2_RC17B U2_RC23B OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 4 of 13 EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING
You are the RO in Unit
- 2. Unit 2 is responding to a SG Tube Rupture on SG 2 2. The cooldown is complete. The Unit Supervisor has requested that you implement Step 17 of 2-OHP-4023-E-3 to Depressurize the RCS to Minimize Break Flow and Refill the Pressurizer.
GENERAL STANDARDS/PRECAUTIONS Operator performs RCS Depressurization to Minimize Break Flow and Refill the Pressurizer using Aux Spray
. .
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 5 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator determines that Normal Spray is available (Air to containment and RCP s 3/4 running)
SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 6 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: (CS) Operator opens NRV
-163 and NRV
-164 with full demand. SAT: UNSAT:
NOTE: Spray Valves will only open 5% (Closed Indication on Control Panel after valve starts to open)
STANDARD: (CS) Operator determines that spray valves are not being effective in reducing RCS pressure, THEN goes to Step 18.
SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 7 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator may try to use PZR PORV SAT: UNSAT:
Operator may try to open NRV
-152, But the valve will not open. Operator may try to open NMO
-151, But the breaker for the valve will trip.
NOTE: Steps and Actions for 18.a RNO on page 9 of JPM
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 8 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator determines that NO PORVs are available SAT: UNSAT:
Operator may try to open NRV
-152, But the valve will not open.
Operator may try to open NMO
-151, But the breaker for the valve will trip.
CUE: If Required: If Operator tries to Open PORVs & discovers not available, Direct as US to perform Step 18.a RNO.
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 9 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
NOTE:Page 19 Step 18.a repeated for RNO Actions Required
STANDARD: Operator determines that Normal Spray is NOT available.
SAT: UNSAT:
STANDARD: Operator verifies that at least one SI and one CCP are in operation.
SAT: UNSAT: STANDARD: (CS) Operator transitions to Step 19.
SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 10 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: (CS) Operator resets and opens QMO
-225 and 226. SAT: UNSAT:
STANDARD: (CS) Operator closes BIT Inlet Valves.
SAT: UNSAT:
STANDARD: (CS) Operator verifies\opens the following valves:
QRV-2 51 QRV-200 QMO-200 QMO-201 SAT: UNSAT:
STANDARD: Operator closes normal spray valves.
SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 11 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: (CS) Operator opens QRV
-51. SAT: UNSAT:
STANDARD: (CS) Operator closes QRV
-61 and 62. SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 3 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR Revision: 0 NRC 2016-SIM03.doc Page 12 of 13 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: (CS) Operator depressurizes RCS until the conditions for Attachment B are met. (See Handout and/or table
) SAT: UNSAT:
STANDARD: Operator opens QRV
-61 and 62 SAT: UNSAT:
STANDARD: (CS) Operator stops spray flow when conditions of Attachment B are complete.
SAT: UNSAT: TERMINATION CUE: This JPM is complete.
Revision: 0 NRC 2016-SIM03.doc Page 13 of 13 Task Briefing You are the RO in Unit
- 22.
The cooldown is complete.
The Unit Supervisor has requested that you implement Step 17 of 2-OHP-4 023-E-3 to Depressurize the RCS to Minimize Break Flow and Refill the Pressurizer.
NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 1 of 10
OPERATIONS JPM TRAINING PROGRAM TITLE NRC 2016-SIM0 4 TIME: 20 MINUTES TITLE: Isolate ruptured steam generator (Alt)
REVISION: 0 Examinee's Name: _________________________________________
___ __________
Evaluator's Name:
- ______________________________________________________
Date Performed:
- _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts:
- ______________________
_______________________________
Time to Complete:
- _______________________________________________________
Comments:__________________________________________________________________
____________________________________________________________________
_______ ___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 2 of 10 REFERENCES/NRC KA/TASKS Procedure:
2-OHP-4023-E-3 STEAM GENERATOR TUBE RUPTURE K/A Number:
EPE.038.EA1.32 Isolation of a ruptured S/G K/A Imp.: RO: 4.6 SRO: 4.7 Task Number:
EOP0020501 Isolate ruptured Steam Generator(s).
TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 2-OHP-4023-E-3, Steam Generator Tube Rupture
, Step 3 Copy of 2-OHP-4023-E-3, Steam Generator Tube Rupture
, Attachment A (HOLD UNTIL REQUESTED) ATTACHMENTS None EVALUATION SETTINGS Unit 2 Simulator OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 3 of 10 SIMULATOR/LAB SETUP Reset to IC
-7 36 , with the following setup complete
- 1. Initialize simulator to MODE 1 IC.
- 2. Ensure Aux Steam Loads are being supplied by Unit 1 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. Close SG #
- 7. Freeze simulator.
EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING
You are an extra RO A reactor trip with SI occurred due to a Steam Generator Tube Rupture.
2-OHP-4023-E-0 and 2-OHP-4023-E-3 have been implemented.
2-OHP-4023-E-3 is still in progress. Steam Generator #
2 2 has been identified as the ONLY ruptured SG.
Auxiliary Feedwater has been isolated to SG #2 2 per 2-OHP-4023-E-0. The Unit Supervisor directs you to perform Step 3 of 2-OHP-4023-E-3 "Isolate Flow From Ruptured SG(s)."
GENERAL STANDARDS/PRECAUTIONS Examinee will perform E
-3 step to isolate a ruptured SG including RNO actions for failure of ruptured SG stop valve to close (Alternate path)
U2_RC23B U2_MS22B OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 4 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD:
CS Adjusts MRV-223 controller setpoint to 1040 psig SAT: UNSAT:
STANDARD: Operator checks MRV-223 CLOSED SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 5 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD:
CS Places MCM-221 to CLOSE SAT: UNSAT:
STANDARD: Verifies SG Blowdown Isolation Valve DCR-320 is CLOSED SAT: UNSAT:
STANDARD: Verifies SG Blowdown Sample Valve DCR-302 is CLOSED SAT: UNSAT:
STANDARD: Places SG Stop valve drain Valve DCR-407 to CLOSE SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 6 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Verifies DRV-407 is CLOSED SAT: UNSAT:
STANDARD:
Checks Steam Line Warming Valves MS-1 4 8 and MS-14 7 are CLOSED CUE: If asked, 2-MS-1 4 8 and 2-MS-14 7 are CLOSED SAT: UNSAT:
STANDARD:
Places SG Stop Valve Dump Valve MRV-221 to "Trip" CLOSE position (May also try to Trip MRV-222 Dump Valve) Identifies that MRV-220 did NOT CLOSE SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 7 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD CS: Places MRV
-211, MRV-231, and MRV-241 to "Trip" CLOSE position (To Close MRV-210, MRV-230, and MRV-240) (May use MRV-212, MRV-232, or MRV-242. The critical step is satisfied if all three stop valves are closed using either dump valve.
) SAT: UNSAT: STANDARD: Verifies SG stop valve dump valves (used above) are CLOSED (Placed in Neutral)
SAT: UNSAT:
STANDARD CS: Places Steam Dumps in "OFF" position SAT: UNSAT: CUE: When acknowledged, "The US directs you to perform Attachment A. The crew will continue on in this procedure."
NOTE: Provide E-3, Attachment A copy to examinee
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 8 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD:
Verifies that Aux Steam is supplied by Unit
- 1. CUE: Inform examinee that Unit 1 has taken over the Aux Steam Headers.
SAT: UNSAT:
STANDARD: Verify Main FW pump Steam Isolations ARV-11, ARV-12, (CS)ARV-13, and (CS)ARV-14 are CLOSED SAT: UNSAT:
STANDARD: Verify SG Lead Drain Pot Isolation valve DRV-407 is CLOSED SAT: UNSAT:
STANDARD: Verifies Feed Preheating Steam Supply valves
-
CLOSED MRV-501 and 502 MRV-601 and 602 CUE: If required, " MRV
-501, 502, 601, & 602 are locally verified closed."
SAT: UNSAT:
STANDARD: Verifies Reheater Isolation valves
- CLOSED MMO-431 and 432 M RV-411 and 412 SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM04 Isolate ruptured steam generator Revision: 0 NRC 2016-SIM04.doc Page 9 of 10 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Verifies Steam Dump valves
- CLOSED: URV-110, 120 and 130 URV-111, 124 and 135 URV-112, 125 and 136 SAT: UNSAT: STANDARD: Verifies Startup Air Ejectors Steam supply valve SMO-40 1 - CLOSED SAT: UNSAT: STANDARD CS: Places Turbine Sealing Steam Supply valves
- CLOSED: SRV-26 SRV-27 SAT: UNSAT: STANDARD: Verifies Main Steam Lead Drain valves
- CLOSED: DMO-4 25 , 4 26, 427 and 4 28 DMO-4 50 and 4 51 SAT: UNSAT:
STANDARD: Verifies Turbine Bypass Drain valves
-
CLOSED: DRV-40 5 DRV-40 6 SAT: UNSAT:
Examinee reports completion of Attachment A EVALUATOR:
JPM is COMPLETE
Revision: 0 NRC 2016-SIM04.doc Page 10 of 10 TASK BRIEFING:
You are an extra RO A reactor trip with SI occurred due to a Steam Generator Tube Rupture.
2-OHP-4023-E-0 and 2-OHP-4023-E-3 have been implemented.
2-OHP-4023-E-3 is still in progress. Steam Generator #
2 2 has been identified as the ONLY ruptured SG.
Auxiliary Feedwater has been isolated to SG #2 2 per 2-OHP-4023-E-0. The Unit Supervisor directs you to perform Step 3 of 2-OHP-4023-E-3 "Isolate Flow From Ruptured SG(s)."
NRC 2016-SIM0 5 Place the West Main FW Pump In Service Revision: 0 NRC 2016-SIM05.doc Page 1 of 6 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 10 MINUTES NUMBER AND TITLE: NRC 2016-SIM0 5 Place the West Main FW Pump In Service REVISION: 0 Examinee's Name: ____________________________________________ ________
__ Evaluator's Name: : ______________________________________________________
Date Performed: : _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts: : __________________________________
___________________
Time to Complete: : _______________________________________________________
Comments:__________________________________________________________________
___________________________________________________________________________
___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM0 5 Place the West Main FW Pump In Service Revision: 0 NRC 2016-SIM05.doc Page 2 of 6 REFERENCES/NRC KA/TASKS Procedure:
1-OHP-4021-055-003 PLACING A MAIN FEED PUMP IN SERVICE K/A Number:
SYS 059 K4.05
{2.5/2.8} SYS 059 A4.03
{2.9/2.9} K/A Imp.: RO: SRO: (See K/A Number)
Task Number:
0550110101 S tart a second Main Feedwater Pump TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1-OHP-4021-055-003 Attachment 4 ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
SIMULATOR/LAB SETUP
- 1. Initialize simulator to IC
-7 41 (MODE 1 IC with the following Actions taken).
- 2. Mode 1 IC around 55% power, with East MFP feeding the SGs and the West MFP rolling around 3650 RPM
- 3. Verify AC Auxiliary Oil Pump is running and that 2 control fluid pumps are running.
Sign off Attachment 4 through step 4.6.1
OPERATIONS JPM NRC 2016-SIM0 5 Place the West Main FW Pump In Service Revision: 0 NRC 2016-SIM05.doc Page 3 of 6 EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING
You are the Reactor Operator. The Unit supervisor has directed you to continue placing the West Main FW pump in Service from 1
-OHP-4021-055-003 Attachment 4 step 4.6.2 GENERAL STANDARDS/PRECAUTIONS
Operator places West Main FW Pump in DP control sharing load with the East Main FW Pump.
OPERATIONS JPM NRC 2016-SIM0 5 Place the West Main FW Pump In Service Revision: 0 NRC 2016-SIM05.doc Page 4 of 6 EXPECTED ACTIO NS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Operator stops West AC Auxiliary Pump 1-QT-301W and places in Auto SAT: UNSAT:
STANDARD: Operator Checks oil Pressures Stable and Alarm Clear CUE: Local pump bearing oil pressure (at PG
-9) is 16 Psig SAT: UNSAT:
STANDARD: Operator Checks Temperatures within Limits SAT: UNSAT: Normal oil temperature at outlet of coolers: 110-120°F Max. allowable oil temperature at outlet of coolers: 135
°F (1-SG-6, point 14; LTR
-11) Maximum allowable oil temperature at bearing outlet: 185
°F Maximum allowable turbine thrust bearing metal temperature (front/back): 230
°F (1-SG-6, point 3-4; TC-2-1) Maximum allowable turbine journal bearing metal temperature (HP/LP): 250
°F (1-SG-6, point 9
-10; TC-13-14) Maximum allowable pump outboard
-inboard radial bearing metal temperature: 200
°F (1-SG-6, point 23
-24; TTR-162-163) Maximum allowable pump thrust bearing oil drain temperature:
170°F (1-SG-6, point 22; TTR
-161) Maximum allowable pump journal bearing drain temperature:
190°F (1-SG-6, point 11/12; TTR
-TC-C/A-W) Maximum oil temperature rise through any Main Feed Pump or Turbine journal bearing: <50
°F STANDARD:
(CS) Operator enters a target speed and ramp rate and depresses GO on the HMI SAT: UNSAT:
STANDARD:
(CS) Operator places the WEST DP Control Pushbutton on HMI.
SAT: UNSAT:
STANDARD: Operator "Load Sharing Active" LIT on HMI.
SAT: UNSAT: Now SWP OPERATIONS JPM NRC 2016-SIM0 5 Place the West Main FW Pump In Service Revision: 0 NRC 2016-SIM05.doc Page 5 of 6 EXPECTED ACTIO NS CUES/STANDARDS ("
CS" Indicates Critical Standard)
CUE: If Required, "Auto Bias is Desired" STANDARD:
Operator verifies Auto Bias in service and verifies suction flows are match ed SAT: UNSAT:
TERMINATION CUE: This JPM is complete.
Revision: 0 NRC 2016-SIM05.doc Page 6 of 6 TASK BRIEFING You are the Reactor Operator. The Unit supervisor has directed you to continue placing the West Main FW pump in Service from 1
-OHP-4021-0 55-003 Attachment 4 step 4.6.2
NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 1 of 9 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 15 MINUTES NUMBER AND TITLE: NRC 2016 - SIM0 6 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A (Alt. Path with OHP
-4023-SUP-00 4 REVISION: 0 Examinee's Name:
____________________________________________ __________
Evaluator's Name:
- ______________________________________________________
Date Performed:
- _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts:
- _____________________________________________________
Time to Complete:
- _______________________________________________________
Comments:__________________________________________________________________
__________________________
_________________________________________________
___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 2 of 9 REFERENCES/NRC KA/TASKS Procedure:
1-OHP-4023-E-0 Reactor Trip or Safety Injection 1-OHP-4023-SUP-00 4 Phase B Isolation Checklist K/A Number:
SYS 103 A2.03 Ability to (a) predict the impacts of a Phase A and B isolation on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations K/A Imp.: RO: 3.5 SRO
- 3.8 Task Number:
0340030501 Verify Containment Isolation Phase B.
TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1-OHP-4023-E-0 Reactor Trip or Safety Injection Copy of 1-OHP-4023-SUP-00 4 Phase B Isolation Checklist (HOLD) ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator
- Cover PPC Screen With "201 6-Sim0 6 Screen."
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 3 of 9 SIMULATOR/LAB SETUP Reset to IC 738 with large break LOCA and loss of bus 1-AM-A and the following:
Insert Malfunctions RP1 6A & RP1 7A to cause a failure of Train A Auto/Manual Phase B Isolation Turn Power Off to 1-AM-A
Set RF for WCR 902 and WCR
-941 to Fail the valves open EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING Unit 1 has experienced a Large break LOCA with a loss of bus 1-AM-A You are the BOP.
The Unit Supervisor has requested that you verify Containment Isolation Phase B in accordance with E-0, Attachment A, Step 16
. GENERAL STANDARDS/PRECAUTIONS Verify completion of Containment Isolation Phas e B U1_SWR37 U1_RP16A U1_ED0820 ZLO101WCR941_U1[GRN]
U1_RP17A U1_SWR19 OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 4 of 9 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
CS: Operator recognizes that Containment Isolation Phase B, Train A did not actuate.
SAT: UNSAT:
Operator may attempt to manually actuate Containment Isolation Phase B, Train A and determines that it did not manually actuate.
SAT: UNSAT:
CS: Operator recognizes that Containment Isolation Phase B, Train A valves are still open and performs the RNO SAT: UNSAT:
Note: Five valves (CCM-452, CCM-454, CCM-459, WCR 902, and WCR-941) for Containment Isolation Phase B, Train B are also still open and will need to be isolated in SUP-00 4.
CUE: The PPC Containment Isolation Screen function is NOT available
- The Screen is frozen as indicated.
CS: Operator Implements SUP
-00 4. SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 5 of 9 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
Operator closes all Containment Isolation Phase B, Train A valves on the IV panel.
SAT: UNSAT:
NOTE: Only five valves are Critical Tasks associated with isolating containment due to Train B valves failing to close and Train A failure to actuate.
NOTE: CCM-452, CCM-454, CCM-459 have lost power due to 1-AM-A Loss and valves remain Open.
CS: Operator closes CCM
-458 SAT: UNSAT:
CS: Operator closes CCM-451 SAT: UNSAT:
CS: Operator closes CCM-453 SAT: UNSAT:
CS: Operator closes WCR-901 SAT: UNSAT: CS: Operator closes WCR-951 SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 6 of 9 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
Operator closes all Containment Isolation Phase A, Train B valves on the IV panel. SAT: UNSAT:
Operator attempts to close W CR-941. SAT: UNSAT:
NOTE: WCR-951 closure will isolate WCR
-941 flowpath.
NOTE: Only five valves are Critical Tasks associated with isolating containment due to Train B valves failing to close and Train A failure to actuate.
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 7 of 9 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
Operator attempts to close W CR-902. SAT: UNSAT:
NOTE: WCR-901 closure will isolate WCR
-902 flowpath.
NOTE: Only five valves are Critical Tasks associated with isolating containment due to Train B valves failing to close and Train A failure to actuate.
OPERATIONS JPM NRC 2016-SIM0 6 Verify Containment Isolation Phase B IAW OHP
-4023-E-0 Att. A Revision: 0 NRC 2016-SIM06.doc Page 8 of 9 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
NOTE: CCM-452, CCM-454, CCM-459 have lost power due to T11A Loss and valves remain Open. CCM
-451, CCM-453, CCM-458 Should have been previously Closed to complete this isolation.
Operator verifies at least 1 VALVE in each Flowpath has been closed. SAT: UNSAT:
NOTE: Only five valves are Critical Tasks associated with isolating containment due to Train B valves failing to close and Train A failure to actuate.
EVALUATOR:
"JPM IS COMPLETE."
Revision: 0 NRC 2016-SIM06.doc Page 9 of 9 Task Briefing Unit 1 has experienced a Large break LOCA with a loss of bus 1-AM-A You are the BOP.
The Unit Supervisor has requested that you verify Containment Isolation Phase B in accordance with E-0, Attachment A, Step 16.
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 1 of 8 NUMBER; NRC 2016-SIM0 7 TIME: 20 MINUTES TITLE: Restore RCP Bus 1A Power to Bus T11A REVISION: 0 Examinee's Name: ____________________________________________ __________
Evaluator's Name: : _________________________________________
_____________
Date Performed: : _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts: : _____________________________________________________
Time to Complete: : ________________________
_______________________________
Comments:__________________________________________________________________
___________________________________________________________________________
______________________________________________________________________
_____
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 2 of 8 REFERENCES/NRC KA/TASKS Procedure:
1-OHP 4023-SUP-002 Restoration of Reserve Power to 4KV Buses K/A Number:
SYS 062 A4.07 K/A Imp.: RO: 3.1 SRO: 3.1 Task Number:
EOP0390501 Restore Offsite Power to all AC buses using SUP 002. TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing sheet Copy of Attachment G of 1-OHP 4023-SUP-002 ATTACHMENTS None
EVALUATION SETTINGS
Unit 1 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
SIMULATOR/LAB SETUP
- 1. Reset to an IC
.738 2. Verify that T11A and T11B are fed from 1AB EDG.
- 3. Open CB12AB - TR101AB transformer breaker prior to/following Trip & Then Reclose (Must Also Close Unit 2 Breaker on Soft Panel)
.
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 3 of 8 EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING You are the extra operator.
The crew is recovering from a LOCA with a station blackout. The AB Emergency Buses are energized by the Emergency Diesel Generators. Offsite power has been restored to the AB RCP Buses.
The US directs you to load the T11A Bus to the RCP bus in accordance with 1
-OHP-4023-SUP-002, Attachment G.
TASK STANDARDS
Load the T11A Bus to the RCP Bus in accordance with 1
-OHP-4023-SUP-002. .
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 4 of 8 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Checks for lights, voltage, and/or amps on 4kV Bus 1A. SAT: UNSAT: STANDARD: Checks DG1AB running with Output Breaker to T11A closed.
SAT: UNSAT:
STANDARD: Places both Voltmeters to OFF position.
SAT: UNSAT:
STANDARD: CS: Places DG1AB 4KV CB T11A9 Synch Selector switch in MANUAL.
SAT: UNSAT:
STANDARD: CS: Adjusts DG1AB (START) voltage 2
-3 volts higher than Bus 1A (RUN) voltage.
SAT: UNSAT:
NOTE: Must use auto Voltage Adjust POT.
STANDARD: CS: Adjusts speed so the Synchroscope is rotating SLOWLY in the FAST direction.
SAT: UNSAT:
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 5 of 8 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: CS: Closes DG1AB 4KV CB T11A9 control switch at 11:00. SAT: UNSAT:
STANDARD: Verifies WHITE light permissive is LIT.
SAT: UNSAT:
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 6 of 8 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: CS: Places DG1AB Synchronize Master Close Switch in CLOSE at 11:00.
SAT: UNSAT:
STANDARD: Checks Breaker T11A9 CLOSED.
SAT: UNSAT:
Instructor Note:
Ann. 119, Drop 76, 4KV BUS T11A PARALLEL OPERATION, will alarm when both supply breakers are closed.
STANDARD: CS: Adjusts DG1AB load to greater than 0 kw. SAT: UNSAT:
STANDARD: CS: Places DG1AB 4KV CB T11A9 Synch Selector switch in OFF.
SAT: UNSAT: STANDARD: Adjusts DG1AB voltage as required.
SAT: UNSAT: STANDARD: CS: OPENS breaker T11A11.
SAT: UNSAT:
CUE: US acknowledges tripping open the T11A11 breaker.
NRC 2016-SIM07 Restore RCP Bus 1A Power to Bus T11A Revision: 0 NRC 2016-SIM07.doc Page 7 of 8 EXPECTED ACTIONS CUES/STANDARDS ("
CS" Indicates Critical Standard)
STANDARD: Recognized that Bus T11B is still energized by DG1AB and leaves DG1AB running.
SAT: UNSAT:
CUE: When a transition is made back to Supplement Body, Step 5, "JPM is COMPLE TE."
Revision: 0 NRC 2016-SIM07.doc Page 8 of 8 TASK BRIEFING You are the extra operator.
The crew is recovering from a station blackout. The AB Emergency Buses are energized by the Emergency Diesel Generators. Offsite power has been restored to the AB RCP Buses.
The US directs you to load the T11A Bus to the RCP bus in accordance with 1
-OHP-4023-SUP-002, Attachment G
.
NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 1 of 14 OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 3 0 MINUTES NUMBER AND TITLE: NRC 2016-SIM0 8 Perform Containment Pressure Relief REVISION: 0 Examinee's Name: ____________________________________________ __________
Evaluator's Name:
- ______________________________________________________
Date Performed:
- _______________________________________________________
Result (Circle One):
SAT / UNSAT Number of Attempts:
- _____________________________________________________
Time to Complete:
- _______________________________________________________
Comments:__________________________________________________________________
___________________________________________________________________________
___________________________________________________________________________
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 2 of 14 REFERENCES/NRC KA/TASKS Procedure:
OHP.4021.028.004 Operation of the Containment Pressure Relief System K/A Number:
SYS 029 A1.03 K/A Imp.: RO: 3.0 SRO 3.3: Task Number: 0280080101 Perform a Containment Pressure Relief.
TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1- OHP.4021.028.004 procedure ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator EVALUATION METHOD:
PERFORM: SIMULATE:
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 3 of 14 SIMULATOR/LAB SETUP
- 1. Reset the simulator to IC 741. 2. Place simulator in RUN.
- 3. MRF U12_CHR16 to 29.
3" (barometric pressure)
- 4. Verify Lower Containment pressure at ~ 0.16
-.20 psig. 5. Verify Check Source NOT Failed For VRS 1100, VRS 1200, ERS
-1300, ERS-1400, VRS-1500 Channels EVALUATOR INSTRUCTIONS
- 1. Ensure simulator setup is complete
- 2. Brief the operator (May be performed by giving out Task Briefing Sheet)
- 3. Announce start of the JPM
- 4. Perform evolution
- 5. At completion of evolution, announce the JPM is complete.
- 6. Document evaluation performance.
TASK BRIEFING Unit 1 is operating at 100% power. Containment pressure has risen due to previous problems associated with containment cooling. Pressure is +0.18 psig and the Unit Supervisor directed that containment pressure be reduced in accordance with 1-OHP 4021-028-004, Operation of the Containment Pressure Relief System There are no abnormal RCS leak rates. All radiation monitors are operable. Containment pressure relief system absolute and charcoal filters are operable.
Initiating cue: The Unit Supervisor has directed you to relieve containment pressure to 0.00 psig in accordance with 1
-OHP 4021-028-004, Operation of the Containment Pressure Relief System GENERAL STANDARDS/PRECAUTIONS CONTAINMENT PRESSURE IS REDUCEDU12_CHR16 OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 4 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") C UE: Containment pressure relief system absolute and charcoal filters are operable.
Standard: Candidate Reviews Precautions & Limitations SAT: UNSAT: C UE: All radiation monitors are operable
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 5 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") Information in this note is typically reviewed and discussed in task briefing.
NOTE: Not part of JPM.
CUE: None of the planned evolution activities are scheduled during the time we will be performing the pressure relief.
{NOTE: JPM starts here.}
STANDARD: Operator verifies that all listed monitors are functioning properly SAT: UNSAT: CUE: If asked, AEO reports that 1-VFS-1521 is operating within the Normal range.
STANDARD: Operator determines that ALL channels are OPERABLE SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 6 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") N/A N/A
NOTE: This is typically reviewed and discussed as part of the task briefing.
CUE: Shift Manager deems NONE of these actions as necessary."
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 7 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") NOTE: Data is recorded on Section A of Data Sheet 1 (FYI Page 13 of JPM)
STANDARD: Enter Next CPR number CUE: Next Containment Pressure Relief Number is 1 6-058 SAT: UNSAT: STANDARD: Record Vent Flow from 1-VFR-1510 or 1-VFR-315 on recorder 1-MR-54 and circles source SAT: UNSAT:
STANDARD: Record Containment Pressure SAT: UNSAT:
STANDARD: Record Radiation Monitor readings SAT: UNSAT: STANDARD: Perform Source Check on 1-ERS-1305 SAT: UNSAT: STANDARD: Perform Source Check on 1-ERS-1405 SAT: UNSAT: STANDARD: CS Verify all Trip block switches in NORMAL SAT: UNSAT:
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 8 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS")
STANDARD: Initial Data Sheet 1 SAT: UNSAT: N/A
CUE: If Required, Audible alarm is Available N/A NOTE: These contingencies may be reviewed by the Operator. They will be used later in this JPM and are repeated when appropriate.
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 9 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS")
CUE: If asked, 1-VFC-207 Containment Pressure Relief Flow controller is set at 500 cfm.
STANDARD:
CS Places 1-VCR-107 to OPEN.
SAT: UNSAT:
STANDARD:
CS Places 1-VCR-207 to OPEN and holds.
SAT: UNSAT: CUE: After VCR-107 and VCR
-207 are open, "US directs you to start HV
-CPR-1, CNTMT Pressure Relief Vent Unit."
STANDARD:
CS 1-HV-CPR-1 Fan switch is placed in START.
SAT: UNSAT: N/A STANDARD: Operator records start time in Section B SAT: UNSAT: CUE: The Control Room Log Entry Has been completed.
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 10 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") CUE: "The Desired Pressure has been Reached" STANDARD:
CS Operator places 1-HV-CPR-1 fan to STOP SAT: UNSAT: NA STANDARD:
CS Operator places 1-VCR-107 to CLOSE SAT: UNSAT: STANDARD:
CS Operator places 1-VCR-207 to CLOSE SAT: UNSAT: STANDARD: Operator records stop time SAT: UNSAT: STANDARD: Operator Places TRIP/BLOCK Switches to BLOCK SAT: UNSAT: STANDARD: Operator records information on Data Sheet 2 setpoint SAT: UNSAT: EVALUATOR:
JPM is COMPLETE
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 11 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") NOTE: Included for information only.
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 12 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS") NOTE: Included for information only.
OPERATIONS JPM NRC 2016-SIM0 8 Perform Containment Pressure Relief Revision: 0 NRC 2016-SIM08.doc Page 13 of 14 EXPECTED ACTIONS CUES/STANDARDS ("Critical Steps in bold
-CS")
Revision: 0 NRC 2016-SIM08.doc Page 14 of 14 Unit 1 is operating at 100% power. Containment pressure has risen due to previous problems associated with containment cooling. Pressure is +0.18 psig and the Unit Supervisor directed that containment pressure be reduced in accordance with 1
-OHP 4021-028-004, Operation of the Containment Pressure Relief System There are no abnormal RCS leak rates. All radiation monitors are operable. Containment pressure relief system absolute and charcoal filters are operable.
Initiating cue:
The Unit Supervisor has directed you to relieve containment pressure to 0.00 psig in accordance with 1
-OHP 4021-028-004, Operation of the Containment Pressure Relief System