ML16340B794: Difference between revisions

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(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
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NRC 2016-SIM01                            Revision: 0 Perform Emergency Boration During ATWS (ALT)
NRC 2016-SIM01                            Revision: 0 Perform Emergency Boration During ATWS (ALT)
NRC 2016-SIM01.doc                                                        Page 1 of 7
NRC 2016-SIM01.doc                                                        Page 1 of 7
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NRC 2016-Sim02                        Revision: 0 Establish Letdown In Accordance With 1-OHP-4023-SUP-015 NRC 2016-SIM02.doc                                                    Page 1 of 8
NRC 2016-Sim02                        Revision: 0 Establish Letdown In Accordance With 1-OHP-4023-SUP-015 NRC 2016-SIM02.doc                                                    Page 1 of 8


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NRC 2016-SIM03                            Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc                                                        Page 1 of 13
NRC 2016-SIM03                            Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc                                                        Page 1 of 13


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Unit 2 is responding to a SG Tube Rupture on SG 22. 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.
Unit 2 is responding to a SG Tube Rupture on SG 22. 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.
GENERAL STANDARDS/PRECAUTIONS Operator performs RCS Depressurization to Minimize Break Flow and Refill the Pressurizer using Aux Spray.
.
NRC 2016-SIM03                                  Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc                                                          Page 4 of 13
NRC 2016-SIM03                                  Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc                                                          Page 4 of 13


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NRC 2016-SIM04                        Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc                                                    Page 1 of 10
NRC 2016-SIM04                        Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc                                                    Page 1 of 10


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NRC 2016-SIM05                        Revision: 0 Place the West Main FW Pump In Service NRC 2016-SIM05.doc                                                  Page 1 of 6
NRC 2016-SIM05                        Revision: 0 Place the West Main FW Pump In Service NRC 2016-SIM05.doc                                                  Page 1 of 6


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NRC 2016-SIM06                            Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc                                                      Page 1 of 9
NRC 2016-SIM06                            Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc                                                      Page 1 of 9


OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure:    1-OHP-4023-E-0                Reactor Trip or Safety Injection 1-OHP-4023-SUP-004            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
OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure:    1-OHP-4023-E-0                Reactor Trip or Safety Injection 1-OHP-4023-SUP-004            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.
:
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-004 Phase B Isolation Checklist (HOLD)
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-004 Phase B Isolation Checklist (HOLD)
ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator - Cover PPC Screen With 2016-Sim06 Screen.
ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator - Cover PPC Screen With 2016-Sim06 Screen.
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NRC 2016-SIM07                          Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc                                                  Page 1 of 8
NRC 2016-SIM07                          Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc                                                  Page 1 of 8


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The US directs you to load the T11A Bus to the RCP bus in accordance with 1-OHP-4023-SUP-002, Attachment G.
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.
TASK STANDARDS Load the T11A Bus to the RCP Bus in accordance with 1-OHP-4023-SUP-002.
.
NRC 2016-SIM07                              Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc                                                      Page 3 of 8
NRC 2016-SIM07                              Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc                                                      Page 3 of 8


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NRC 2016-SIM08                        Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc                                                  Page 1 of 14
NRC 2016-SIM08                        Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc                                                  Page 1 of 14



Latest revision as of 21:46, 4 February 2020

DC Cook 2016 Proposed Operating Test CR-SIM JPMs
ML16340B794
Person / Time
Site: Cook  American Electric Power icon.png
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

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 10 MINUTES TITLE NUMBER AND NRC 2016-SIM01 TITLE: REVISION: 0 Perform Emergency Boration During ATWS (ALT)

Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM01 Revision: 0 Perform Emergency Boration During ATWS (ALT)

NRC 2016-SIM01.doc Page 1 of 7

OPERATIONS JPM REFERENCES/NRC KA/TASKS Response to Nuclear Power Procedure: 1-OHP-4023-FR-S.1 Generation/ATWS APE 024 A1.17 {3.9/3.9}

K/A Number:

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:

NRC 2016-SIM01 Revision: 0 Perform Emergency Boration During ATWS (ALT)

NRC 2016-SIM01.doc Page 2 of 7

OPERATIONS JPM 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 U1_RP03A U1_RP03B
3. Insert MALF RP10A and RP10B; Fail AUTO SI actuation U1_RP10A U1_RP10B
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)

ZGI43BAP2S_U1

7. Insert Override - ZGIRU20_U1 to IN (Maintains continuos rod motion in MANUAL)

ZGIRU20_U1

8. Insert Malf - U1_101BAP1 (Failure of the #1 BAP)

U1_101BAP1

9. Freeze simulator.

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NRC 2016-SIM01.doc Page 3 of 7

OPERATIONS JPM 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.

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NRC 2016-SIM01.doc Page 4 of 7

OPERATIONS JPM 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 BATP 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 next 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:

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NRC 2016-SIM01.doc Page 5 of 7

OPERATIONS JPM 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.

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NRC 2016-SIM01.doc Page 6 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.

Revision: 0 NRC 2016-SIM01.doc Page 7 of 7

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC2016-Sim02 TITLE: Establish Letdown In Accordance With 1-OHP- REVISION: 0 4023-SUP-015 (Alternate Path)

Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-Sim02 Revision: 0 Establish Letdown In Accordance With 1-OHP-4023-SUP-015 NRC 2016-SIM02.doc Page 1 of 8

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4023-SUP-015, R OPERATION OF NORMAL AND EXCESS LETDOWN Ability to (a) predict the impacts of the following K/A Number: SYS 004 A2.07 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 Place Letdown in Service 0030240101 Place Excess Letdown in Service TRAINING AIDS/TOOLS/EQUIPMENT None HANDOUTS Task Briefing Copy of 1-OHP-4023-SUP-015 procedure NRC 2016-Sim02 Revision: 0 Establish Letdown In Accordance With 1-OHP-4023-SUP-015 NRC 2016-SIM02.doc Page 2 of 8

OPERATIONS JPM 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 ZGI101QRV111_U1 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.

NRC 2016-Sim02 Revision: 0 Establish Letdown In Accordance With 1-OHP-4023-SUP-015 NRC 2016-SIM02.doc Page 3 of 8

OPERATIONS JPM 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-SUP-015. Recognize that normal letdown cannot be established and place Excess Letdown in service (Alternate Path).

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OPERATIONS JPM 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-111.

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:

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OPERATIONS JPM 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 established to seal water heat exchanger and the alignment has not been altered SAT: UNSAT:

STANDARD: (CS) Operator opens QCM-250/350 SAT: UNSAT:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

STANDARD: (CS) Operator opens 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.

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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.

Revision: 0 NRC 2016-SIM02.doc Page 8 of 8

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC 2016-SIM03 TITLE: Depressurize the RCS to Minimize Backflow/Refill REVISION: 0 the Pressurizer during SGTR (ALT)

Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

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OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 2-OHP-4023-E-3 Steam Generator Tube Rupture EPE 038 EA1.04 Ability to operate and monitor the following as they K/A Number:

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:

NRC 2016-SIM03 Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc Page 2 of 13

OPERATIONS JPM SIMULATOR/LAB SETUP

  • Initialize simulator to IC-737 (MODE 1 IC with the following Actions taken).
1. Ensure Aux Steam Loads are being supplied by Unit 1
2. IMF RC23B @ 40 causing a #22 SGTR of 400gpm. U2_RC23B
3. A SGTR in progress and ready to depressurize RCS
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_U2(2) == 1 or ZLONRV164_U2(2) == 1),

U2_PZR_Spray_op

b. MF RC15A & RC15B to 5% on Trigger 2 U2_RC15A U2_RC15B
6. Close PRZ PORV Block Valves NMO151 & NMO153, PORV NRV-151, Caution Tag NRV 151 & Block Closed for Leakage, Clearance Tag NRV-153 & NMO153
7. Insert Malfunction RC17B to 0% to fail NRV-152 closed &Global Malfunction101NMO153 U2_RC17B U2_EDPR25G Trg 1 - NMO151 to Open (ZGI101NMO151_U2 == 3), MF 101NMO151 U2 NMO151 to Open U2_EDPR22G
  • OOS Tag NRV & NMO 153, Caution Tag NRV & NMO 151
  • Freeze simulator.

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OPERATIONS JPM 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 22. 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.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

STANDARD: Operator determines that Normal Spray is available (Air to containment and RCPs 3/4 running)

SAT: UNSAT:

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OPERATIONS JPM 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:

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OPERATIONS JPM 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 NRC 2016-SIM03 Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc Page 7 of 13

OPERATIONS JPM 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.

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OPERATIONS JPM 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:

NRC 2016-SIM03 Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc Page 9 of 13

OPERATIONS JPM 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-251
  • QRV-200
  • QMO-200
  • QMO-201 SAT: UNSAT:

STANDARD: Operator closes normal spray valves.

SAT: UNSAT:

NRC 2016-SIM03 Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc Page 10 of 13

OPERATIONS JPM 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:

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OPERATIONS JPM 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.

NRC 2016-SIM03 Revision: 0 Depress. the RCS to Minimize Backflow/Refill the Pressurizer during SGTR NRC 2016-SIM03.doc Page 12 of 13

Task Briefing You are the RO in Unit 2.

Unit 2 is responding to a SG Tube Rupture on SG 22.

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.

Revision: 0 NRC 2016-SIM03.doc Page 13 of 13

OPERATIONS JPM TRAINING PROGRAM NRC 2016-SIM04 TIME: 20 MINUTES TITLE TITLE: Isolate ruptured steam generator (Alt)

REVISION: 0 Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM04 Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc Page 1 of 10

OPERATIONS JPM REFERENCES/NRC KA/TASKS 2-OHP-4023-E-3 STEAM GENERATOR TUBE RUPTURE Procedure:

EPE.038.EA1.32 Isolation of a ruptured S/G K/A Number:

K/A Imp.: RO: 4.6 SRO: 4.7 EOP0020501 Isolate ruptured Steam Generator(s).

Task Number:

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 NRC 2016-SIM04 Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc Page 2 of 10

OPERATIONS JPM SIMULATOR/LAB SETUP Reset to IC-736, 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: U2_MS22B
4. IMF RC23B @ 40 causing a #22 SGTR of 400gpm. U2_RC23B
5. Perform actions of E-0 and E-3 through step 2 as appropriate.
6. Close SG #22 FMOs if SG Level is >14%
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 #22 has been identified as the ONLY ruptured SG.

Auxiliary Feedwater has been isolated to SG #22 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)

NRC 2016-SIM04 Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc Page 3 of 10

OPERATIONS JPM 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:

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OPERATIONS JPM 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:

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

STANDARD: Verifies DRV-407 is CLOSED SAT: UNSAT:

STANDARD: Checks Steam Line Warming Valves MS-148 and MS-147 are CLOSED CUE: If asked, 2-MS-148 and 2-MS-147 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:

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OPERATIONS JPM 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 NRC 2016-SIM04 Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc Page 7 of 10

OPERATIONS JPM 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
  • MRV-411 and 412 SAT: UNSAT:

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OPERATIONS JPM 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-401 - 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-425, 426, 427 and 428
  • DMO-450 and 451 SAT: UNSAT:

STANDARD: Verifies Turbine Bypass Drain valves -

CLOSED:

  • DRV-405
  • DRV-406 SAT: UNSAT:

Examinee reports completion of Attachment A EVALUATOR: JPM is COMPLETE NRC 2016-SIM04 Revision: 0 Isolate ruptured steam generator NRC 2016-SIM04.doc Page 9 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 #22 has been identified as the ONLY ruptured SG.

Auxiliary Feedwater has been isolated to SG #22 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).

Revision: 0 NRC 2016-SIM04.doc Page 10 of 10

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 10 MINUTES TITLE NUMBER AND NRC 2016-SIM05 TITLE: REVISION: 0 Place the West Main FW Pump In Service Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM05 Revision: 0 Place the West Main FW Pump In Service NRC 2016-SIM05.doc Page 1 of 6

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4021-055-003 PLACING A MAIN FEED PUMP IN SERVICE SYS 059 K4.05 {2.5/2.8}

K/A Number:

SYS 059 A4.03 {2.9/2.9}

K/A Imp.: RO: SRO: (See K/A Number) 0550110101 Start a second Main Feedwater Pump Task Number:

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-741 (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 NRC 2016-SIM05 Revision: 0 Place the West Main FW Pump In Service NRC 2016-SIM05.doc Page 2 of 6

OPERATIONS JPM 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.

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OPERATIONS JPM EXPECTED ACTIONS 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:

SWP Now 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:

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OPERATIONS JPM EXPECTED ACTIONS 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 matched SAT: UNSAT:

TERMINATION CUE: This JPM is complete.

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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 Revision: 0 NRC 2016-SIM05.doc Page 6 of 6

OPERATIONS JPM TRAINING PROGRAM INITIAL LICENSE TRAINING TIME: 15 MINUTES TITLE NUMBER AND NRC 2016 - SIM06 TITLE: Verify Containment Isolation Phase B IAW REVISION: 0 OHP-4023-E-0 Att. A (Alt. Path with OHP-4023-SUP-004 Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM06 Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc Page 1 of 9

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: 1-OHP-4023-E-0 Reactor Trip or Safety Injection 1-OHP-4023-SUP-004 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-004 Phase B Isolation Checklist (HOLD)

ATTACHMENTS None EVALUATION SETTINGS Unit 1 Simulator - Cover PPC Screen With 2016-Sim06 Screen.

NRC 2016-SIM06 Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc Page 2 of 9

OPERATIONS JPM SIMULATOR/LAB SETUP Reset to IC 738 with large break LOCA and loss of bus 1-AM-A and the following:

Insert Malfunctions RP16A & RP17A to cause a failure of Train A Auto/Manual Phase B Isolation U1_RP16A U1_RP17A Turn Power Off to 1-AM-A U1_ED0820 Set RF for WCR 902 and WCR-941 to Fail the valves open U1_SWR19 U1_SWR37 ZLO101WCR941_U1[GRN]

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 Phase B NRC 2016-SIM06 Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc Page 3 of 9

OPERATIONS JPM 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-004.

CUE: The PPC Containment Isolation Screen function is NOT available - The Screen is frozen as indicated.

CS: Operator Implements SUP-004.

SAT: UNSAT:

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OPERATIONS JPM 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:

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OPERATIONS JPM 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 WCR-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.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)

Operator attempts to close WCR-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.

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OPERATIONS JPM 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.

NRC 2016-SIM06 Revision: 0 Verify Containment Isolation Phase B IAW OHP-4023-E-0 Att. A NRC 2016-SIM06.doc Page 8 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.

Revision: 0 NRC 2016-SIM06.doc Page 9 of 9

NUMBER; NRC 2016-SIM07 TIME: 20 MINUTES TITLE: Restore RCP Bus 1A Power to Bus T11A REVISION: 0 Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM07 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 1 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 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 2 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 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 3 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 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 4 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 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 5 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 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 6 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 COMPLETE.

NRC 2016-SIM07 Revision: 0 Restore RCP Bus 1A Power to Bus T11A NRC 2016-SIM07.doc Page 7 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.

Revision: 0 NRC 2016-SIM07.doc Page 8 of 8

OPERATIONS JPM TRAINING PROGRAM TITLE INITIAL LICENSE TRAINING TIME: 30 MINUTES NUMBER AND NRC 2016-SIM08 TITLE:

Perform Containment Pressure Relief REVISION: 0 Examinees Name: ____________________________________________ __________

Evaluators Name: : ______________________________________________________

Date Performed: : _______________________________________________________

Result (Circle One): SAT / UNSAT Number of Attempts: : _____________________________________________________

Time to Complete: : _______________________________________________________

Comments:__________________________________________________________________

NRC 2016-SIM08 Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc Page 1 of 14

OPERATIONS JPM REFERENCES/NRC KA/TASKS Procedure: OHP.4021.028.004 Operation of the Containment Pressure Relief System K/A Number:

SYS029 A1.03 K/A Imp.: RO: SRO 3.0 3.3:

Task 0280080101 Perform a Containment Pressure Relief.

Number:

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:

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OPERATIONS JPM SIMULATOR/LAB SETUP

1. Reset the simulator to IC 741.
2. Place simulator in RUN.
3. MRF U12_CHR16 to 29.3 (barometric pressure)

U12_CHR16

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 REDUCED NRC 2016-SIM08 Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc Page 3 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (Critical Steps in bold-CS)

CUE: Containment pressure relief system absolute and charcoal filters are operable.

Standard: Candidate Reviews Precautions & Limitations SAT: UNSAT:

CUE: All radiation monitors are operable NRC 2016-SIM08 Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc Page 4 of 14

OPERATIONS JPM 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:

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OPERATIONS JPM 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.

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OPERATIONS JPM 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 is16-058 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:

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OPERATIONS JPM 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.

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OPERATIONS JPM 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.

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OPERATIONS JPM 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 NRC 2016-SIM08 Revision: 0 Perform Containment Pressure Relief NRC 2016-SIM08.doc Page 10 of 14

OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (Critical Steps in bold-CS)

NOTE: Included for information only.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (Critical Steps in bold-CS)

NOTE: Included for information only.

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OPERATIONS JPM EXPECTED ACTIONS CUES/STANDARDS (Critical Steps in bold-CS)

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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 Revision: 0 NRC 2016-SIM08.doc Page 14 of 14