ML21034A625
| ML21034A625 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/03/2021 |
| From: | Gita Samaddar Division of Reactor Safety II |
| To: | |
| References | |
| Download: ML21034A625 (482) | |
Text
ML21034A625 Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: NRC 1 Op-Test No.: Draft Examiners: ___________________________ Operators: ____________________________
Initial Conditions: Reactor power is 2%.
Turnover: The BOP Operator is to swap Condensate Booster Pumps IAW 2OP-32. (C in service, A in standby). The OATC will raise power, 0GP-10, A2X Sequence, Step 10, is complete up to Item 165.
0GP-02 is complete up to Step 6.3.50.
Critical Task #1: Manually tie DG3 to E3 and/or DG4 to E4 before Station Blackout Procedure is entered.
Critical Task #2: Restore or maintain RPV level above LL4 using LP ECCS pumps before ED must be performed.
Event Malf. No. Event Type* Event No. Description N-BOP *Swap Condensate Booster Pumps 1
N-CRS OP-32 MS_IAMVDS0 C-BOP *Gland Seal Regulator Failure 2
1 C-CRS OP-26.1 R-ATC Raise Power using control rods 3
R-CRS GP-10, OP-07 C-ATC *Difficult to Move Rod 3a RD032M C-CRS AOP-02, OP-07 I-ATC *IRM Failure 4 NI018F I-CRS TS 3.3.1.1 C-BOP CSW Pump Trip, Standby Fails to Auto Start 5 CW036F C-CRS AOP-19, TS 3.7.2 EE009F M LOOP 6 DG006F C DGs fail to tie RSP, AOP-36.1, RVCP NB009F M LOCA ES016F C HPCI Aux Oil Pump Failure ES045F C All LP ECCS Fails to Auto start 7 ES046F ES043F ES044F Restore RPV water level SEP-09, LEP-01
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 SCENARIO DESCRIPTION
SUMMARY
Event Description With the unit at 2% power the crew will swap Condensate Booster Pumps IAW 2OP-32. C 1 will be placed in service, A to standby.
The steam seal regulator fails closed. Sealing steam pressure will lower causing alarm UA-02 2 (3-5) Steam Seal Regulator Press-Low. Crew will open the bypass valve to restore steam sealing pressure The crew will raise power by pulling control rods in preparation for placing the Mode 3 switch to RUN. Rod pulls will commence at Sequence A2X Step 10 Item 165 (18-15
@ 12).
When control rod 18-31 is selected for withdrawal, it will be stuck at position 12. 0AOP-02 may 3a be entered and 2OP-07, Section 6.3.2 actions are required to withdraw a difficult intermediate control rod. After raising drive water pressure the control rod will move.
While withdrawing control rods, IRM C will fail upscale causing a rod block and half scram.
SRO will address IRM A and C inoperability IAW TS 3.3.1.1. Once addressed, I&C will report 4 IRM A is ready to be returned to service following proper channel check. The crew will take the actions of the APP and bypass IRM C and reset the half scram.
A 4KV Bus E3 motor overload alarm will be received, followed by a CSW Pump A trip. CSW 5 Pump C will fail to auto start on low header pressure. The CRS will evaluate Tech Spec 3.7.2.
A Loss of Offsite Power and subsequent reactor scram on MSIV closure will occur. The CRS will direct entry RSP, RVCP, and AOP-36.1. The crew will perform scram immediate actions, maintain reactor pressure and level IAW RVCP, and perform applicable AOP-36.1 actions.
Coincident with the LOOP and scram, DG3 and DG4 will fail to close on their respective buses.
6 The crew will manually close the output breakers to energize buses E3 and E4.
When scram immediate actions are complete and the E-Buses are energized, the chief examiner may move to Event 7.
A LOCA signal (LL3, +45 inches, or 410 psig reactor pressure with 1.7# in the DW) will occur.
The LOCA will be greater than the flow capacities of RCIC / CRD (SEP-09) / SLC (LEP-01).
HPCI Aux Oil Pump will fail preventing HPCI operation. All LP ECCS systems will fail to auto 7 start, but can be manually started.
When LP ECCS has been started and level is greater than TAF and being returned to normal band the scenario may be terminated at the direction of the chief examiner.
BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2020 NRC SCENARIO 1, ES-D-2 Swap CBP, Gland Seal Reg Failure, Raise Power, Diff to Move Rod, IRM Failure, CSW Pump Trip, LOOP, DGs Fail to Tie, LOCA, HPCI AOP Failure, All LP ECCS Fails to Start, Restore Level REVISION 0 Developer: Bob Bolin Date: 5/5/20 Technical Review: S. Cotton Date: 6/18/20 Validators: Mike Long Date: 8/18/20 Mike Maricle Steve Hildebrandt Facility Representative: Rob Mehs Date: 9/15/20 Training Approval: Ed Rau Date: 9/16/20
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 96 REVISION
SUMMARY
0 Scenario developed for 2020 NRC Exam.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 3 of 96 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE .................................................................................................................. 4 2.0 SCENARIO DESCRIPTION
SUMMARY
.................................................................................. 5 3.0 CREW CRITICAL TASKS ........................................................................................................... 6 4.0 TERMINATION CRITERIA .......................................................................................................... 6 5.0 IMPLEMENTING REFERENCES .............................................................................................. 7 6.0 SETUP INSTRUCTIONS ............................................................................................................. 8 7.0 INTERVENTIONS....................................................................................................................... 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 14 ATTACHMENT 1 - Scenario quantitative Attribute Assessment ..................................................... 94 ATTACHMENT 2 - Shift Turnover ........................................................................................................ 96
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 4 of 96 1.0 SCENARIO OUTLINE Event Malf. No. Type* Event Description N-BOP *Swap Condensate Booster Pumps 1
N-CRS OP-32 MS_IAMVD C-BOP *Gland Seal Regulator Failure 2 S01 C-CRS OP-26.1 R-ATC Raise Power using control rods 3
R-CRS GP-10, OP-07 C-ATC *Difficult to Move Rod 3a RD032M C-CRS AOP-02, OP-07 I-ATC *IRM Failure 4 NI018F I-CRS TS 3.3.1.1 C-BOP CSW Pump Trip, Standby Fails to Auto Start 5 CW036F C-CRS AOP-19, TS 3.7.2 EE009F M LOOP 6 DG006F C DGs fail to tie RSP, AOP-36.1, RVCP NB009F M LOCA ES016F C HPCI Aux Oil Pump Failure ES045F C All LP ECCS Fails to Auto start 7 ES046F ES043F ES044F Restore RPV water level SEP-09, LEP-01
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 5 of 96 2.0 SCENARIO DESCRIPTION
SUMMARY
Event Description With the unit at 2% power the crew will swap Condensate Booster Pumps IAW 2OP-1 32. C will be placed in service, A to standby.
The steam seal regulator fails closed. Sealing steam pressure will lower causing 2 alarm UA-02 (3-5) Steam Seal Regulator Press-Low. Crew will open the bypass valve to restore steam sealing pressure The crew will raise power by pulling control rods in preparation for placing the Mode 3 switch to RUN. Rod pulls will commence at Sequence A2X Step 10 Item 165 (18-15
@ 12).
When control rod 18-31 is selected for withdrawal, it will be stuck at position 12.
0AOP-02 may be entered and 2OP-07, Section 6.3.2 actions are required to withdraw 3a a difficult intermediate control rod. After raising drive water pressure the control rod will move.
While withdrawing control rods, IRM C will fail upscale causing a rod block and half scram. SRO will address IRM A and C inoperability IAW TS 3.3.1.1. Once 4 addressed, I&C will report IRM A is ready to be returned to service following proper channel check. The crew will take the actions of the APP and bypass IRM C and reset the half scram.
A 4KV Bus E3 motor overload alarm will be received, followed by a CSW Pump A trip.
5 CSW Pump C will fail to auto start on low header pressure. The CRS will evaluate Tech Spec 3.7.2.
A Loss of Offsite Power and subsequent reactor scram on MSIV closure will occur.
The CRS will direct entry RSP, RVCP, and AOP-36.1. The crew will perform scram immediate actions, maintain reactor pressure and level IAW RVCP, and perform applicable AOP-36.1 actions. Coincident with the LOOP and scram, DG3 and DG4 6 will fail to close on their respective buses. The crew will manually close the output breakers to energize buses E3 and E4.
When scram immediate actions are complete and the E-Buses are energized, the chief examiner may move to Event 7.
A LOCA signal (LL3, +45 inches, or 410 psig reactor pressure with 1.7# in the DW) will occur. The LOCA will be greater than the flow capacities of RCIC / CRD (SEP-09)
/ SLC (LEP-01). HPCI Aux Oil Pump will fail preventing HPCI operation. All LP ECCS 7 systems will fail to auto start, but can be manually started.
When LP ECCS has been started and level is greater than TAF and being returned to normal band the scenario may be terminated at the direction of the chief examiner.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 96 3.0 CREW CRITICAL TASKS Critical Task #1 Manually tie DG3 to E3 and/or DG4 to E4 before Station Blackout Procedure is entered and within 15 minutes of the Loss of Offsite Power.
Critical Task #2 Restore and maintain RPV level above LL4 (-27.5 inches) using LP ECCS pumps before ED is performed.
4.0 TERMINATION CRITERIA When LP ECCS has been started and level is greater than TAF and being returned to normal band the scenario may be terminated at the direction of the chief examiner.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 7 of 96 5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.
Number Title 2OP-32 (6.3.6) Condensate and Feedwater System Operating Procedure 2OP-07 (6.1.1, 6.3.2) Reactor Manual Control System Operating Procedure 0GP-02 Approach To Criticality And Pressurization Of The Reactor 0GP-10 Rod Sequence Checkoff Sheets 2OP-26.1 (6.3.3) Gland Sealing Steam System Operating Procedure A-05, 2-4 IRM Upscale A-05, 3-4 IRM A Upscale/Inop A-05, 1-7 Reactor Auto Scram Sys A A-05, 4-7 Neut Mon Sys Trip A-05, 2-2 Rod Out Block UA-01, 1-8 Conv Hdr SW Pump A Trip UA-02, 3-5 Steam Seal Regulator Press-Low UA-17, 6-1 Bus E3 4KV Motor OVLD 0AOP-02.0 Control Rod Malfunction/Misposition 0AOP-19.0 Conventional Service Water System Failure 0AOP-36.1 Loss of Any 4160V buses or 480V E-Buses 2EOP-01-RSP Reactor Scram Procedure 2EOP-01-RVCP Reactor Vessel Control Procedure 0EOP-01-ED Emergency Depressurization Tech Specs Tech Specs
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 96 6.0 SETUP INSTRUCTIONS
- 1. PERFORM TAP-438, Establishing Simulator Exam Security.
- 2. RESET the Simulator to IC-05.
- 3. ENSURE the RWM rod sequence is set to A2.
- 4. ENSURE appropriate keys have blanks in switches.
- 6. ENSURE no rods are bypassed in the RWM.
- 7. VERIFY ERFIS and the Process Computer are updating in RUN (check clock time and selected points updating).
- 8. PLACE all SPDS displays to the Critical Plant Variable display (#100).
- 9. VERIFY Fireworks alarms are clear.
- 10. ENSURE hard cards, flow charts, panel gauges, indicators and recorders are cleaned up
- 11. ENSURE OP Aid Placards are updated as necessary.
- 12. VERIFY RHR Think Switches are GREEN FLAGGED
- 14. TAKE the SIMULATOR OUT OF FREEZE
- 15. ALIGN the plant as follows:
Manipulation
- 1. Ensure 2C Condensate Booster Pump is NOT in service.
- 2. Ensure 2A CSW Pump is in service and 2C CSW Pump is in standby
- 3. Bypass IRM A
- 4. Insert control rods through Step10, Item 165 of GP-10, Sequence A2X.
- 5. Raise reactor pressure to ~465 psig.
- 6. Verify level is stable
- 7. Verify drive water pressure is 275 psid.
- 16. LOAD Scenario File.
- 17. IF desired, take a SNAPSHOT and save into an available IC for later use.
- 18. PLACE a clearance on the following equipment.
Component Position IRM A Blue Tag
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- 19. INSTALL Protected Equipment signage and UPDATE RTGB placard as follows:
Protected Equipment ADHR, FPC Loop A, 2A Demin Xfer Pmp
- 20. ENSURE each Implementing References listed in Section 5 is intact and free of marks.
- 21. ENSURE all materials in the table below are in place and marked-up to the step identified.
Required Materials 0GP-10, A2X Sequence, Step 10, up to Item 165.
0GP-02 up to Step 6.3.50, with the exception of Step 6.3.46.
2OP-32, Section 6.3.6, Steps 1-10 completed.
- 22. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.
- 23. PROVIDE Shift Briefing sheet for the CRS.
- 24. CONDUCT exam pre-job brief with evaluation team IAW AD-TQ-ALL-0420, Conduct of Simulator Training and Evaluation.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 10 of 96 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Remote Function EE_LSHED4 - [LOCA LOAD SHED SEL SW, 2A CONDENSATE BOOSTER PUMP]
1 Remote Function EE_UTSHED4 - [UNIT TRIP LOAD SHED SEL SW, 2A COND BOOSTER PUMP]
2 Remote Function EE_LSHED6 - [LOCA LOAD SHED SEL SW, 2C CONDENSATE BOOSTER PUMP]
2 Remote Function EE_UTSHED6 - [UNIT TRIP LOAD SHED SEL SW, 2C COND BOOSTER PUMP]
3 Remote Function MS_IAMVDS01 - [MN STM TO SEALS VLV, MVD-S1]
4 Malfunction NI018F - [IRM C FAILS HI]
5 Malfunction CW027F - [CONV SW PUMP MOTOR WINDING FAULT]
6 Malfunction EE009F - [LOSS OF OFF-SITE POWER]
7 Remote Function SW_VHSW146L - [CONV SW TO RBCCW HXS V146]
8 Remote Function RP_IARPSA - [RESTART RPS MG SET A]
8 Remote Function RP_IAEPAMGA - [RPS M-G SET A EPA BKRS]
9 Remote Function RP_IAEPAMGB - [RPS M-G SET B EPA BKRS]
9 Remote Function RP_IARPSB - [RESTART RPS MG SET B]
10 Malfunction NB009F - [SMALL RECIRC PMP SUCT LINE RUPTURE]
11 Remote Function RD_RDSUCTF - [SUCTION FILTER ISOL VALVES]
11 Remote Function RD_RDDRIVF - [DRIVE WATER FILTER ISOL VALVES]
11 Remote Function RD_RDSUCTB - [SUCTION FILTER BYPASS VLV CO-V306]
12 Remote Function SL_IASLCTST - [SLC SUCT. LINEUP (NORM=SLC TNK / ALT=JUMPER HOSE)]
13 Remote Function EP_IACS993P - [DW CLR A & D OVERIDE - NORMAL/STOP]
13 Remote Function EP_IACS994P - [DW CLR B & C OVERIDE - NORMAL/STOP]
14 Remote Function EP_IAEOPJP2 - [DEFEAT RCIC LOW PRESS ISOL (SEP-10)]
15 Remote Function EP_IAEOPJ11 - [OPEN ALL DW COOLER BKRS (SEP-02)]
16 Trigger Command RFI:MS_IAMVDS01, 0,00:00:00,00:00:00 Trig # Trigger Text 16 K4506JN3 - [STM SEAL MVD-S2]
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 96 MALFUNCTIONS Malf Mult Current Target Rmp Description Actime Dactime Trig ID ID Value Value time RD012M 18-31 STUCK CONTROL ROD True True CONTROL ROD WITHDRAWAL RD032M 18-31 True True SLUGGISH NI018F IRM C FAILS HI False True 4 CONV SW PUMP MOTOR CW027F A False True 5 WINDING FAULT EE009F LOSS OF OFF-SITE POWER False True 6 DG OUTPUT BREAKER FAIL TO DG006F DG 3 True True AUTO CLOSE DG OUTPUT BREAKER FAIL TO DG006F DG 4 True True AUTO CLOSE SMALL RECIRC PMP SUCT LINE NB009F A 0.000 7.000 10 min 10 RUPTURE ES045F RHR A FAILURE TO AUTO START True True ES046F RHR B FAILURE TO AUTO START True True HPCI HYDRAULIC SYSTEM ES016F True True FAILURE CORE SPRAY A FAILURE TO AUTO ES043F True True START CORE SPRAY B FAILURE TO AUTO ES044F True True START
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 12 of 96 REMOTES Current Target Rmp Remf Id Mult Id Description Actime Trig Value Value time XA_IALPB102 AOG-XCV-102 LOCAL AUTO AUTO XA_IALPB142 AOG-XCV-142 LOCAL OPEN OPEN XA_IALPB147 AOG-XCV-147 LOCAL OPEN OPEN XA_IALPB148 AOG-XCV-148 LOCAL OPEN OPEN XA_IALPB143 AOG-XCV-143 LOCAL OPEN OPEN XA_IALPB141 AOG-XCV-141 LOCAL OPEN OPEN MS_VHCNV18L MECH VAC PMP A SUCTION VLV V16 SHUT SHUT MS_VHCNV19L MECH VAC PMP B SUCTION VLV V17 SHUT SHUT MS_IAGP1BYP LO COND VACUUM GP1 TRIP BYP NORMAL NORMAL CF_CFDFAUTO CFD B CFD E VALVE AUTO/MANUAL AUTO AUTO CF_CDDFAUTO CDD B CDD E VALVE AUTO/MANUAL AUTO AUTO CF_CFDFAUTO CFD C CFD E VALVE AUTO/MANUAL AUTO AUTO CF_CDDFAUTO CDD D CDD E VALVE AUTO/MANUAL AUTO AUTO CF_CDDMAUTO CDD MASTER AUTO/MANUAL AUTO AUTO CF_FCDDDMAN CDD B CDD E VALVE MANUAL DEMAND 21.7429 31 CF_CDDEVLV CDD B CDD E VALVE CONTROL SWITCH AUTO
- OPEN CF_CDDEVLV CDD D CDD E VALVE CONTROL SWITCH AUTO
- OPEN CF_CFDEVLV CFD A CFD E VALVE CONTROL SWITCH AUTO
- OPEN CF_CFDEVLV CFD B CFD E VALVE CONTROL SWITCH AUTO
- OPEN CF_CFDEVLV CFD C CFD E VALVE CONTROL SWITCH AUTO
- OPEN CF_IACFHIDP CFD BYP VLV RESET NORMAL RESET CF_CFDFAUTO CFD D CFD E VALVE AUTO/MANUAL AUTO AUTO CF_IAORCFD CFD OVERRIDE RESET NORMAL RESET LOCA LOAD SHED SEL SW, 2A EE_LSHED4 DISABLE ENABLE 1 CONDENSATE BOOSTER PUMP UNIT TRIP LOAD SHED SEL SW, 2A EE_UTSHED4 DISABLE ENABLE 1 COND BOOSTER PUMP LOCA LOAD SHED SEL SW, 2C EE_LSHED6 ENABLE DISABLE 2 CONDENSATE BOOSTER PUMP UNIT TRIP LOAD SHED SEL SW, 2C EE_UTSHED6 ENABLE DISABLE 2 COND BOOSTER PUMP MS_IAMVDS01 MN STM TO SEALS VLV, MVD-S1 -1 .200 3 SW_VHSW146L CONV SW TO RBCCW HXS V146 SHUT OPEN 7 RP_IAEPAMGA RPS M-G SET A EPA BKRS SET SET 00:02 8 RP_IARPSA RESTART RPS MG SET A NORMAL RESET 8 RP_IAEPAMGB RPS M-G SET B EPA BKRS SET SET 00:02 9 RP_IARPSB RESTART RPS MG SET B NORMAL RESET 9 RD_RDSUCTB SUCTION FILTER BYPASS VLV CO-V306 CLOSE OPEN 11 RD_RDSUCTF V307/309 SUCTION FILTER ISOL VALVES CLOSE OPEN 11
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 96 F020B/
RD_RDDRIVF DRIVE WATER FILTER ISOL VALVES CLOSE OPEN 11 F021B SLC SUCT. LINEUP (NORM=SLC TNK /
SL_IASLCTST NORMAL ALT 12 ALT=JUMPER HOSE)
EP_IAEOPJP2 DEFEAT RCIC LOW PRESS ISOL (SEP-10) OFF ON 14 EP_IAEOPJ11 OPEN ALL DW COOLER BKRS (SEP-02) ON OFF 15 DW CLR A & D OVERIDE -
EP_IACS993P NORMAL STOP 13 NORMAL/STOP DW CLR B & C OVERIDE -
EP_IACS994P NORMAL STOP 13 NORMAL/STOP PANEL OVERRIDES Position / Actual Override Rmp Tag ID Description Actime Dactime Trig Target Value Value time CONV HDR SW PMP C K4B41A AUTO ON OFF DISCH VLVS ANNUNCIATORS Override Window Description Tagname OVal AVal Actime Dactime Trig Type
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 96 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1: Swap of Condensate Booster Pumps (CBP)
Simulator Operator Actions Ensure Monitored Parameters is open and Variables are loaded.
Initiate Trigger 1 to ENABLE 2A CBP Unit Trip and LOCA Load Shed Selector Switches.
Initiate Trigger 2 to DISABLE 2C CBP Unit Trip and LOCA Load Shed Selector Switches Simulator Operator Role Play Acknowledge request to enable 2A CBP Unit Trip and LOCA Load Shed selector switches, after Sim Operator activates the trigger report that the action is complete.
Acknowledge request to disable 2C CBP Unit Trip and LOCA Load Shed selector switches, after Sim Operator activates the trigger report that the action is complete.
Acknowledge any requests for Radwaste actions.
Bus C Area is reported as clear if requested or if camera is checked.
Evaluator Notes Plant Response: 2C CBP is started and 2A CBP is secured Objectives: SRO - Directs BOP to swap Condensate Booster Pumps BOP - Swap Condensate Booster Pumps RO - Monitors the plant Success Path: Condensate Booster Pumps are swapped.
Event Termination: At the direction of the Chief Examiner, go to Event 2.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 15 of 96 EVENT 1: Swap of Condensate Booster Pumps (CBP)
Time Pos EXPECTED Operator Response NOTES SRO Conduct shift turnover shift briefing.
Direct CBPs to be swapped. (2OP-32, Section 6.3.6) 2C started and 2A secured.
Swap Condensate Booster Pumps IAW 2OP-32, Section 6.3.6 (see page 16 this guide):
Make a PA announcement for starting 2C Condensate Booster Pump and Securing 2A Condensate Booster Pump. Should also check that Bus C is clear of personnel, may state that they would use plant cameras.
BOP Performs 2OP-32, Section 6.3.6. Per the turnover, Steps 1-10 are complete.
Directs an AO to perform steps 12a and 12g, Unit Trip and LOCA Load Shed switches.
Directs Radwaste to perform steps 21 and 22.
ATC Monitors the plant
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 21 of 96 EVENT 2: Gland Seal Regulator Failure Simulator Operator Actions Initiate Trigger 3 to fail the Sealing Steam Regulator.
Simulator Operator Role Play Acknowledge any request for maintenance activities.
Evaluator Notes Plant Response: The steam seal regulator valve fails closed. Sealing steam pressure will lower causing alarm UA-02 (3-5) Steam Seal Regulator Press-Low. Crew will open the bypass valve to restore steam sealing pressure.
Objectives: SRO - Direct actions for a loss of steam sealing pressure.
RO - Monitors the plant BOP - Perform actions for a loss of steam sealing pressure.
Success Path: Steam sealing pressure is restored above 1.5 psig.
Event Termination: At the direction of the Chief Examiner, go to Event 3.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 22 of 96 EVENT 2: Gland Seal Regulator Failure Time Pos EXPECTED Operator Response NOTES Acknowledge report of UA-02 (3-5) Steam Seal SRO Regulator Press-Low annunciator Direct opening bypass for Steam Seal Regulator IAW the APP or OP May conduct a brief (see Enclosure 1 on page 74 for format)
Reports UA-02 (3-5) Steam Seal Regulator BOP Press-Low annunciator and references APP.
IAW APP, (see page 23) Throttles open MVD-S2 (Steam Seal Byp Vlv) to maintain steam seal header pressure greater than 1.5 psig.
May reference 2OP-26.1 Section 6.3.3, Bypassing Steam Seal Feed Valve - Manual Operations, (see page 23) to throttle open MVD-S2 (Steam Seal Byp Vlv).
When Steam Seal Pressure is greater than 1.5 psig reports annunciator has cleared.
ATC Monitors the plant.
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 25 of 96 EVENT 3/3a: Raise Power Using Control Rods / Difficult to Move Control Rod Simulator Operator Actions When Drive Water d/P is raised to 300 psid, Delete stuck rod malfunction (RD012M).
Simulator Operator Role Play If asked as the RE, continuous rod withdrawal is allowed for moves to position 48.
If asked as the RE, report all thermal limits are within specifications.
Evaluator Notes Plant Response: Control rods will continue to be withdrawn IAW GP-10 Control rod 18-31 will not move until drive water pressure is raised to 300 psid IAW 2OP-07.
Objectives: SRO - Directs and monitor reactor power ascension with control rods Direct actions for a difficult to move control rod.
RO - Withdraw control rods to raise reactor power Perform 2OP-07 actions for difficult to move control rod Success Path: Control rods withdrawn to position 48, 18-31 by use of increased drive water d/P.
Event Termination: At the direction of the Chief Examiner/ Lead Evaluator, go to Event 4.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 26 of 96 EVENT 3/3a: Raise Power Using Control Rods / Difficult to Move Control Rod Time Pos EXPECTED Operator Response NOTES Directs RO to raise reactor power by withdrawing control rods IAW 0GP-10 Item 10 SRO Step 165.
(Continuous withdrawal allowed to position 48)
Directs RO to perform 2OP-07 for the difficult to move rod.
May direct AOP-02 (Control Rod malfunction) -
Notifies RE Directs 2OP-07 to move rod.
May conduct a brief (see Enclosure 1 on page 74 for format)
Monitor reactor plant parameters during BOP evolution.
Continues rod withdrawal per GP-10 IAW ATC guidance of 2OP-07.
Report A-5 3-3 SRM Period (This alarm may annunciate if a control rod is being withdrawn adjacent to one of the SRMs.)
Recognizes control rod 18-31 will not move.
Notifies SRO control rod 18-31 will not move.
Identifies 2OP-07, Reactor Manual Control System Operating Procedure, Section 6.3.2 (Control Rod Difficult to Withdraw, Control Rod NOT at Position 00) is required.
Continues rod withdrawal per GP-10 IAW guidance of 2OP-07.
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 42 of 96 EVENT 4: IRM Failure Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 4, to fail IRM C upscale Simulator Operator Role Play If contacted as the RE for IRM C inoperability, acknowledge request.
When IRM C inoperability has been addressed and by Lead Examiners direction, contact the control room as WCC SRO and report IRM A can be declared Operable following a satisfactory channel check. Once declared operable the off normal tag can be removed and the WCC will follow up with the paperwork.
Evaluator Notes Plant Response: The crew will continue raising power by pulling control rods in preparation for placing the Mode switch to RUN. IRM C will fail upscale causing a rod block and half scram.
Objectives: SRO - Determine Technical Specification application.
RO - Perform actions for IRM C failure Success Path: Declare IRM A operable by channel check and bypass IRM C.
Event Termination: Go to Event 5 at the direction of the Lead Evaluator.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 43 of 96 EVENT 4: IRM Failure Time Pos EXPECTED Operator Response NOTES SRO Directs APP reference.
Contacts I&C for IRM C failure.
May contact Shift Manager also.
References TS 3.3.1.1 and determines with IRMs A & C inoperable:
Condition A is applicable for Function 1a Required Action A.1 Place channel in trip is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or A.2 Place associated trip system in trip is required in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
May enter TRM 3.3 (Control Rod Block Instrumentation) Function 3 Condition A, Tracking LCO May conduct a brief (see Enclosure 1 on page 74 for format)
Evaluates IRM A operability following satisfactory channel check .
2OP-09, Attachment 4, 2.3.4 (Operability Guidance).
NOTE: WCC provides cue that IRM A can be declared operable after channel check is SAT.
Channel Check definition in the ESOMs Reactor Operator Daily Check Sheets. Channel Checks are a sufficient WO PMT for SRMs and IRMs at power unless a component failure is suspected in which case an I/V curve and TDR trace is desirable Directs IRM A channel check be performed.
Directs IRM C bypassed and reset of half scram BOP Monitors Plant
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 44 of 96 EVENT 4: IRM Failure Time Pos EXPECTED Operator Response NOTES ATC Determines IRM C failed upscale.
Responds and reports applicable alarms for IRM C failing upscale. A-05 1-7 REACTOR AUTO SCRAM SYS A 4-7 NEUT MON SYS TRIP 2-4 IRM UPSCALE 2-2 ROD OUT BLOCK 3-4 IRM A UPSCALE/INOP A-5 IRM A UPSCALE/INOP actions:
May reposition range switch for IRM C to bring indicated power to between 15 and 50 on the 0-125 scale.
May verify IRM C Drawer Selector switch (Control Panel H12-P606) is in OPERATE.
May notify CRS of Tech Spec applicability May inform CRS IRM C cannot be bypassed and half scram cannot be reset due to IRM A being bypassed.
Performs channel check of IRM A for operability.
Removes IRM A from Bypass Bypasses IRM C per APP guidance.
Resets half scram per APP guidance.
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 47 of 96 EVENT 5: CSW Pump Trip / Standby Auto Start Failure Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 5, to activate CSW Pump A trip Simulator Operator Role Play When asked as OAO to investigate, report 51 device actuation on all 3 phases after pump has tripped at breaker (AJ4) on E3.
If requested as I&C to investigate CSW Pump malfunctions, acknowledge the request.
Evaluator Notes Plant Response: E3 motor overload alarms and the CSW 2A trip alarms, and pump trips. CSW Pump 2C fails to auto start, can be manually started.
Objectives: SRO - Direct entry into AOP-19.0.
ATC - Monitors reactor plant parameters.
BOP - Take actions IAW 0AOP-19.0.
Success Path: CSW Pump A is tripped. CSW Pump C is started.
Event Termination: Go to Event 6 at the direction of the Lead Evaluator.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 48 of 96 EVENT 5: CSW Pump Trip / Standby Auto Start Failure Time Pos EXPECTED Operator Response NOTES Direct entry into AOP-19.0, Conventional SRO Service Water Failures May direct CSW Pump 2A tripped and CSW Pump 2C be started. (in any order)
Direct I&C to investigate CSW Pump 2A overcurrent and trip and failure of CSW Pump 2C to auto start Tech Spec 3.7.2 SW System and UHS Condition C.1 Verify the one OPERABLE CSW pump and one OPERABLE Unit 2 NSW pump are powered from separate 4.16 kV emergency buses Immediately.
and Condition C.2 Restore required CSW pump to OPERABLE Status within 7 days.
The SW System is considered OPERABLE when it has two OPERABLE CSW pumps (specifically the CSW 2A and CSW 2C pumps), three site NSW pumps (any combination of Unit 1 and Unit 2 NSW pumps), and an OPERABLE flow path capable of taking suction from the intake structure and transferring the water to the ECCS equipment and the DGs. For a CSW pump to be considered OPERABLE, it must be capable of supplying the CSW header and the NSW header.
May conduct a brief (see Enclosure 1 on page 74 for format)
ATC Monitors Plant
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 49 of 96 EVENT 5: CSW Pump Trip / Standby Auto Start Failure Time Pos EXPECTED Operator Response NOTES Dispatch AO to investigate UA-17, 6-1, 4KV BOP Motor Overload alarm.
When directed, announce and execute 0AOP-19.0, Conventional Service Water Failures Recognize/report trip alarm of CSW Pump 2A UA-01 (1-8).
Recognize failure of 2C CSW pump to auto-start and starts 2C CSW pump May also manually trip CSW Pump 2A and manually start CSW Pump 2C prior to trip.
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 53 of 96 EVENT 6: LOOP Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 6, to insert a LOOP If directed to align RBCCW to CSW cooling, wait 3 minutes and Initiate Trigger 7.
If directed to restart RPS MG sets, wait 4 minutes and insert the following as requested:
For RPS A Initiate Trigger 8 and/or for RPS B Initiate Trigger 9 Acknowledge fireworks, as needed Simulator Operator Role Play After reactor scram call as load dispatcher and report that crews are being dispatched to determine scope of work and a return to service time.
If requested to monitor DGs, acknowledge alarms on DG local Alarm Panel If directed to restart RPS MG sets, wait 4 minutes and inform Sim Operator to restart RPS then report actions complete.
If directed to align RBCCW to CSW cooling, wait 3 minutes and inform Sim Operator to align RBCCW to CSW cooling then report valve open.
If directed as RBAO to ensure BFIV latching mechanisms are disengaged, wait 3 minutes, then report latches are disengaged.
If requested, report that Unit One has no loads on E4/DG4 or E3/DG3 Evaluator Notes Plant Response: A Loss of Offsite Power and subsequent reactor scram on MSIV closure will occur.
The CRS will direct entry RSP, RVCP, and AOP-36.1. The crew will perform scram immediate actions, maintain reactor pressure and level IAW RVCP, and perform applicable AOP-36.1 actions. Coincident with the LOOP and scram, DG3 and DG4 will fail to close on their respective buses. The crew will manually close the output breakers to energize buses E3 and E4.
Objectives: SRO - Direct entry into AOP-36.1 and RVCP.
ATC - Performs reactor scram immediate operator actions.
BOP - Take actions IAW 0AOP-36.1.
Success Path: Reactor scram actions completed and 0AOP-36.1 actions being taken.
Event Termination: Go to Event 7 at the direction of the Lead Evaluator.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 54 of 96 EVENT 6: LOOP Time Pos EXPECTED Operator Response NOTES Enters RSP then Performs RVCP (due to no method of pressure control at this time).
- Direct pressure band
- Direct water level band Direct AOP-36.1 entry Calls WCC for UAT back feed Contacts Maintenance for failure of DG3 and DG4 to tie on their respective buses.
May conduct a brief (see Enclosure 1 on page 74 for format)
Announces reactor scram and performs Scram ATC Immediate Operator Actions.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 55 of 96 EVENT 6: LOOP Time Pos EXPECTED Operator Response NOTES Performs actions for RSP/RVCP as directed:
ATC /
- Control reactor pressure 300-500 psig BOP
- Control reactor water level 120 - 200 inches
- May perform SEP-09 to restart CRD Recognizes and reports failure of DGs to tie to their respective buses (failed auto action), then places respective DG synch. selector switch to ON and closes its DG output breaker.
DG 3 4 Synch Sw.
Output Breaker Manually tie DG3 to E3 and/or DG4 to E4 CRITICAL TASK #1 before Station Blackout Procedure is entered and within 15 minutes of the Loss of Offsite Power.
Performs AOP 36.1 Actions:
- Ensures pneumatics to DW
- Aligns 230Kv PCBs
- Calls for UAT back feed
- Places RCC on CSW
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 70 of 96 EVENT 7: LOCA / Start LP ECCS Pumps Simulator Operator Actions At the direction of the Chief Examiner, Initiate Trigger 10 to initiate a Recirc Pump suction line rupture. (If necessary, increase leak size to drive the crew to ED)
If asked to maximize CRD flow, Initiate Trigger 11. Inform Sim Role Player when completed.
If directed to position 2C12- F034 (chg wtr isol), modify RD_RDVF034 as necessary If requested to line up SLC for demin water injection, Initiate Trigger 12. Wait 5 minutes and report complete.
If directed to place drywell coolers to STOP, Initiate Trigger 13.
If requested to defeat RCIC low pressure isolation (SEP-10), Initiate Trigger 14.
If directed to trip all drywell cooler breakers, Initiate Trigger 15.
When directed by the lead evaluator, place the simulator in FREEZE DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Simulator Operator Role Play If asked to perform AO actions to maximize CRD flow, inform Sim Operator to initiate trigger
- 11. When complete, contact the control room and report the AO actions to maximize CRD flow IAW SEP-09 are complete.
If requested to line up SLC for demin water injection, inform Sim Operator to initiate trigger 12, wait 3 minutes and report demin water lined up.
If directed to place drywell coolers to STOP, inform Sim Operator to initiate trigger 13, wait 2 minutes and report coolers are stopped.
If requested to defeat RCIC low pressure isolation (SEP-10), inform Sim Operator to initiate trigger 14 and report completed.
If directed to trip all drywell cooler breakers wait 2 minutes, and initiate trigger 15 report breakers are tripped If dispatched to investigate HPCI AOP, report breaker is tripped (magnetics) and will not reset if attempted.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 71 of 96 Evaluator Notes Plant Response: A LOCA will occur. The LOCA will be greater than the flow capacities of RCIC / CRD /
SLC. The crew will maximize RCIC flow and implement LEP-01 for alternate cooling systems. Level will lower, when LOCA signal (LL3, +45 inches, or 410 psig reactor pressure with 1.7# in the DW) is reached all LP ECCS will fail to start, but can be manually started to restore level.
Objectives: SRO - Direct actions IAW RVCP.
OATC/BOP - Restore RPV water level to the designated band by starting LP ECCS Success Path: LP ECCS Pumps are started and reactor water level is being restored to the designated band.
Scenario Termination: When LP ECCS has been started and level is greater than TAF (-7.5 inches) and being returned to normal band the scenario may be terminated at the direction of the chief examiner.
Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluator/instructor.
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 72 of 96 EVENT 7: LOCA / Start LP ECCS Pumps Time Pos EXPECTED Operator Response NOTES Directs actions of RVCP:
- Direct water level band
- Direct reactor pressure band
- Directs ADS inhibited
- Directs the use of table 1 injection systems SRO
- Directs CRD flow maximization SEP-09
- Directs maximizing RCIC flow
- Directs injection using all available Table L-1 and L-2 systems
- Directs LEP-01, Alt cooling injection
- Direct level be restored Enters and directs actions of PCCP:
- Monitor and control Suppression Pool <95°F.
- Start available RHR Loops in Suppression pool Cooling as necessary to <95° F.
- Operate available drywell coolers
- Before Suppression Chamber press reaches 11.5 psig, Direct torus sprays per SEP-03.
- When suppression chamber exceeds 11.5 psig, direct drywell spray per SEP-02
- Confirm DWSIL in Safe Region
- Monitor PSP
- Monitor HCTL
2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 73 of 96 EVENT 7: LOCA / Start LP ECCS Pumps Time Pos EXPECTED Operator Response NOTES OATC/ Maximize CRD flow per SEP-09 BOP (Enclosure 2 on pages 75)
Ensure RCIC injection @ 500 gpm (Enclosure 3 on pages 79)
Inject demin water using SLC per LEP-01 (Enclosure 4 on pages 80)
When directed, Start torus spray per SEP-03 (Enclosure 5 on pages 81)
May dispatch AO to investigate trip of HPCI Aux Oil Pump (AOP)
When directed, Start drywell spray per SEP-02 (Enclosure 6 on pages 87)
When directed, maximize suppression pool cooling per OP-17 (Enclosure 7 on pages 90)
Recognize failure of LP ECCS Pumps to auto-start.
Restore and maintain RPV level above LL4 CRITICAL TASK #2
(-27.5 inches) using LP ECCS pumps before ED is performed.
Manually starts 2A,2C,2B & 2D RHR Pumps and opens 2-E11-F015A(B)
Manually starts 2A & 2B CS Pumps and opens 2-E21-F005A(B)
Control injection flow to maintain RPV level as directed by the SRO.
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2020 NRC SCENARIO 1, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 94 of 96 ATTACHMENT 1 - Scenario quantitative Attribute Assessment Category Standard Scenario Content Total Malfunctions 5-8 9 Malfunctions after EOP 1-2 2 Entry Abnormal Events 2-4 3 Major Transients 1-2 2 EOPs Used 1-2 1 EOP Contingency 1-2 2 Crew Critical Tasks >2 2 Tech Specs 2 2 Instrument / Component 2 - ATC 2 Failures before Major 2 - BOP 2 Instrument / Component 2 3 Failures after Major Normal Operations 1 1 Reactivity manipulation 1 1
LOI SIMULATOR EVALUATION GUIDE LOI SIMULATOR EVALUATION GUIDE ATTACHMENT 2 - Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek J. Pierce B. Craig Manager: Manager:
Mode: 2 Rx Power: 2%
Plant Risk:
Green Current EOOS Risk Assessment is:
SFP Time to 45.7 hrs. Days Online: 0 days 200 Deg F:
IAW the reactivity plan the OATC is to raise power to 6-10% IAW GP-10, A2X sequence, Step 10, Item 165. Permission for continuous withdrawal has been granted for the rods going from 12-48.
Turnover: 0GP-02 completed up to Step 6.3.50, with the exception of Step 6.3.46.
IRM A is bypassed due to spurious spiking.
2OP-32, Section 6.3.6, Transferring to Standby Condensate Booster Pump, has been completed up to step 6.3.6.11.
Protected ADHR / FPC Loop A / Demin Transfer Pump.
Equipment:
The BOP operator will continue procedure to swap Condensate Booster Pumps (place CBP 2C in service and remove CBP 2A from service for Comments: maintenance).
After the CBP swap continue the power ascension.
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: NRC 2 Op-Test No.: Draft Examiners: ___________________________ Operators: ____________________________
Initial Conditions: Reactor power is ~90% due to rod shuffle. APRM 2 is bypassed. 1A NSW Pump is under clearance.
Turnover: The BOP Operator is to place 2A SJAE in full load IAW 2OP-30, Condenser Air Removal And Off-Gas Recombiner System. The OATC will raise power to ~97% using Recirc flow.
Critical Task #1: With a reactor scram required and the reactor not shutdown, insert control rods using one or more methods contained in 0EOP-01-LEP-02 to achieve reactor shutdown under all conditions.
Critical Task #2: With a reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.
Critical Task #3: During an ATWS, when conditions are met to deliberately lower RPV level, Terminate and Prevent (T/P) injection into the RPV (except for CRD/SLC/RCIC) from ECCS and Feedwater until conditions are met to re-establish injection.
Event Malf. No. Event Type* Event No. Description N-BOP *Place SJAE in Full Load 1
N-CRS 2OP-30 ZA761 *Accumulator Alarm (low pressure) 2 TS-CRS Q2BLIUAD TS 3.1.5 R-ATC Raise power 3
R-CRS 2OP-02, 0GP-12 C-ATC CRD Pump Trip due to high filter d/P 4 RD018F C-CRS 0AOP-02.0 C-BOP *Off Gas Filter d/P 5 ZUA343 C-CRS UA-03 (4-3), 2OP-30 C-ATC HPCI Logic Bus A Failure 6 ES013F C-CRS TS 3.5.1 C-BOP *Intake Blockage 7
C-CRS UA-01, 0AOP-37.1 RP005F M ATWS RP006F C *SLC Pump Trip 8
C *ARI Reset Failure RSP, ATWS, PCCP, LEP-02, LEP-03, RVCP
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 SCENARIO DESCRIPTION
SUMMARY
Event Description With reactor power at ~90% following a CRD sequence exchange, the crew will transfer both 1 SJAEs from half load to 2A SJAE in full load IAW 2OP-30 Section 6.3.1.
An accumulator alarm will annunciate, the ATC operator will dispatch the RB AO to investigate. The report will be that the accumulator is low pressure with a pressure of 930 2 psig. The SRO will evaluate TS 3.1.5. The RB AO will charge the accumulator IAW OP-08.
From an initial power of 90% RTP, the operating crew is directed to increase reactor power to 97%. Applicants will use 2OP-02, Section 6.1.3. Once reactor power reaches 97%,
3 the Chief Examiner can move to Event 4.
The CRD suction filter will clog which will trip the CRD pump. The OATC will (1) enter 0AOP-4 02.0, (2) dispatch an AO to swap CRD suction filters, and (3) restart the CRD pump.
The Off Gas Filter Hi d/P alarm will be received. The standby Off Gas filter will be placed in 5 service The ATC will respond to a blown HPCI logic power fuse IAW A-01 (5-5) HPCI LOGIC BUS A PWR FAILURE. HPCI will be manually isolated per the APP. The CRS will address T.S. 3.5.1 6 and TRM 3.6. After HPCI is isolated and the applicable TS is addressed, the chief examiner can move to Event 7.
An influx of gracilaria will cause UA-01 1-5. Shortly afterwards the CW Pump A will trip with alarms UA-01 2-5, 1-4, and 1-7. The crew will start the CW Pump C. After the standby pump 7 is started a total blockage of the traveling screens will occur requiring the crew to insert a manual scram.
Following initiation of the SCRAM, the crew is expected to enter and carry out actions in 2EOP-01-RSP. Expect the ATC operator to report ATWS conditions. Expect the crew to transition to 2EOP-01-ATWS with the BOP operator maintaining directed level/pressure bands.
The MSIV will close due to vacuum loss, the crew is expected to enter 0EOP-02-PCCP on torus temperature, and control pressure with SRVs. ADS will be inhibited (Critical task). The ATC operator will perform 0EOP-01-LEP-02 for control rod insertion. The ATC will inform the CRS of the failure of ARI to reset. Expect the CRS to direct terminate and prevent RPV 8 injection. (Critical Task to be performed to prevent exceeding HCTL). SLC Pumps will trip shortly after being started and LEP-03 will need to be performed. Rod insertion will continue IAW 0EOP-01-LEP-02 to lower power so as to not perform Emergency Depressurization on HCTL exceedance (0EOP-02-PCCP). When a level band is established IAW ATWS step RC/L-17, and at the direction of the lead evaluator, ARI will be fixed. The crew can reset the scram and insert all rods via manual scram. The CRS will transition from ATWS to RVCP and direct level restoration to the normal band. When all rods are inserted and level is being restored towards the normal band, the lead evaluator can terminate this scenario.
BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2020 NRC SCENARIO 2, ES-D-2 SJAE in Full Load, Accumulator Alarm, Raise Power, CRD Pump Trip, Off Gas Filter D/P, Intake Blockage, ATWS, SLC Pump Trip, ARI Reset Failure.
REVISION 0 Developer: Bob Bolin Date: 05/21/20 Technical Review: S. Cotton Date: 06/18/20 Validators: Mike Long Date: 08/18/20 Mike Maricle Steve Hildebrandt Facility Representative: Rob Mehs Date: 09/15/20 Training Approval: Ed Rau Date: 09/16/20
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 89 REVISION
SUMMARY
0 Scenario developed for 2020 NRC Exam.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 3 of 89 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE .................................................................................................................. 4 2.0 SCENARIO DESCRIPTION
SUMMARY
.................................................................................. 5 3.0 CREW CRITICAL TASKS ........................................................................................................... 6 4.0 TERMINATION CRITERIA .......................................................................................................... 6 5.0 IMPLEMENTING REFERENCES .............................................................................................. 7 6.0 SETUP INSTRUCTIONS ............................................................................................................. 8 7.0 INTERVENTIONS....................................................................................................................... 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 12 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment ..................................................... 71 ATTACHMENT 2 - Shift Turnover ........................................................................................................ 89
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 4 of 89 1.0 SCENARIO OUTLINE Event Malf. No. Type* Event Description N-BOP *Place SJAE in Full Load 1
N-CRS 2OP-30 ZA761 *Accumulator Alarm (low pressure) 2 TS-CRS Q2BLIUAD TS 3.1.5 R-ATC Raise power 3
R-CRS 2OP-02, 0GP-12 C-ATC CRD Pump Trip due to high filter d/P 4 RD018F C-CRS 0AOP-02.0 C-BOP *Off Gas Filter d/P 5 ZUA343 C-CRS UA-03 (4-3), 2OP-30 C-ATC HPCI Logic Bus A Failure 6 ES013F C-CRS TS 3.5.1 C-BOP *Intake Blockage 7
C-CRS UA-01, 0AOP-37.1 RP005F M ATWS SL_IASLRA C *SLC Pump Trip 8 SL_IASLRB K2624A C *ARI Reset Failure RSP, ATWS, PCCP, LEP-02, LEP-03, RVCP
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 5 of 89 2.0 SCENARIO DESCRIPTION
SUMMARY
Event Description With reactor power at ~90% following a CRD sequence exchange, the crew will 1
transfer both SJAEs from half load to 2A SJAE in full load IAW 2OP-30 Section 6.3.1.
An accumulator alarm will annunciate, the ATC operator will dispatch the RB AO to investigate. The report will be that the accumulator is low pressure with a pressure of 2
930 psig. The SRO will evaluate TS 3.1.5. The RB AO will charge the accumulator IAW OP-08.
From an initial power of 90% RTP, the operating crew is directed to increase reactor 3 power to 97%. Applicants will use 2OP-02, Section 6.1.3. Once reactor power reaches 97%, the Chief Examiner can move to Event 4.
The CRD suction filter will clog which will trip the CRD pump. The OATC will (1) enter 4 0AOP-02.0, (2) dispatch an AO to swap CRD suction filters, and (3) restart the CRD pump.
The Off Gas Filter Hi d/P alarm will be received. The standby Off Gas filter will be 5
placed in service The ATC will respond to a blown HPCI logic power fuse IAW A-01 (5-5) HPCI LOGIC BUS A PWR FAILURE. HPCI will be manually isolated per the APP. The CRS will 6 address T.S. 3.5.1 and TRM 3.6.
After HPCI is isolated and the applicable TS is addressed, the chief examiner can move to Event 7.
An influx of gracilaria will cause UA-01 1-5 then 2-5. Shortly afterwards the CW Pump A will trip with alarms UA-01 1-4, and 1-7. The crew will start the CW Pump C. After 7
the standby pump is started a total blockage of the traveling screens will occur requiring the crew to insert a manual scram.
Following initiation of the SCRAM, the crew is expected to enter and carry out actions in 2EOP-01-RSP. Expect the ATC operator to report ATWS conditions. Expect the crew to transition to 2EOP-01-ATWS with the BOP operator maintaining directed level/pressure bands. The MSIV will close due to vacuum loss, the crew is expected to enter 0EOP-02-PCCP on torus temperature, and control pressure with SRVs. ADS will be inhibited (Critical task). The ATC operator will perform 0EOP-01-LEP-02 for control rod insertion. The ATC will inform the CRS of the failure of ARI to reset.
Expect the CRS to direct terminate and prevent RPV injection. (Critical Task to be 8 performed to prevent exceeding HCTL). SLC Pumps will trip shortly after being started and LEP-03 will need to be performed. Rod insertion will continue IAW 0EOP-01-LEP-02 to lower power so as to not perform Emergency Depressurization on HCTL exceedance (0EOP-02-PCCP). When a level band is established IAW ATWS step RC/L-17, and at the direction of the lead evaluator, ARI will be fixed. The crew can reset the scram and insert all rods via manual scram. (critical task) The CRS will transition from ATWS to RVCP and direct level restoration to the normal band. When all rods are inserted and level is being restored towards the normal band, the lead evaluator can terminate this scenario.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 89 3.0 CREW CRITICAL TASKS Critical Task #1 With a reactor scram required and the reactor not shutdown, insert control rods using one or more methods contained in 0EOP-01-LEP-02 to achieve reactor shutdown under all conditions prior to exceeding HCTL.
Critical Task #2 With a reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS prior to automatic initiation of ADS.
Critical Task #3 During an ATWS, when conditions are met to deliberately lower RPV level, Terminate and Prevent (T/P) injection into the RPV (except for CRD/SLC/RCIC) from ECCS and Feedwater until conditions are met to re-establish injection to prevent exceeding HCTL.
4.0 TERMINATION CRITERIA When all rods are inserted and level is being restored towards the normal band, the Chief Examiner can terminate this scenario.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 7 of 89 5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.
Number Title 2OP-30 (Section 6.3.1) Condenser Air Removal And Off-Gas Recombiner System UA-45 6-3 ICNDSR Cond Outlet Vlv CO-V17 Open A-07 6-1 CRD Accum Lo Press / Hi Level 0GP-12 Power Changes 2OP-02 (Section 6.1.3) Reactor Recirculation System Operating Procedure A-05, 6-1 CRD Pump Inlet Filter P High A-05, 3-1 CRD Pump 2A Lo Suct Press A-05, 5-1 CRD Pump 2B Lo Suct Press 0AOP-02.0 Control Rod Malfunction/Misposition UA-03 (4-3) Off Gas Filter Diff-High 2OP-30 (Section 6.3.3) Condenser Air Removal And Off-Gas Recombiner System A-01 (5-5) HPCI Logic Bus A Pwr Failure A-01 (6-4) HPCI Cond Storage Tnk Wtr Lvl Lo 2OP-19 High Pressure Coolant Injection System Operating Procedure UA-01 (1-5)(2-5)(3-5)(4-5) CW Screen A(B)(C)(D) Diff-High Or Stopped UA-01 (1-4) CW Screen Diff Hi-Hi UA-01 (1-7)(2-7)(3-7)(4-7) CW Pump A(B)(C)(D) Trip 0AOP-37.1 Intake Structure Blockages 2EOP-01-ATWS ATWS Procedure 2EOP-01-RSP Reactor Scram Procedure 0EOP-02-PCCP Primary Containment Control Procedure 0EOP-01-LEP-02 Alternate Control Rod Insertion 0EOP-01-LEP-03 Alternate Boron Injection 2EOP-01-RVCP Reactor Vessel Control Procedure
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 89 6.0 SETUP INSTRUCTIONS
- 1. PERFORM TAP-438, Establishing Simulator Exam Security.
- 2. RESET the Simulator to IC-13.
- 4. ENSURE appropriate keys have blanks in switches.
- 6. ENSURE no rods are bypassed in the RWM.
- 7. VERIFY ERFIS and the Process Computer are updating in RUN (check clock time and selected points updating).
- 8. PLACE all SPDS displays to the Critical Plant Variable display (#100).
- 9. VERIFY Fireworks alarms are clear.
- 10. ENSURE hard cards, flow charts, panel gauges, indicators and recorders are cleaned up
- 11. ENSURE OP Aid Placards are updated as necessary.
- 12. VERIFY RHR Think Switches are GREEN FLAGGED
- 14. TAKE the SIMULATOR OUT OF FREEZE
- 15. ALIGN the plant as follows:
Manipulation
- 1. Ensure Reactor power has been reduced to ~90% power using Recirc.
- 2. Ensure 2A SPE is in service.
- 3. Ensure CW Pumps A&B are running
- 4. Null DVM
- 5. Bypass APRM 2
- 16. LOAD Scenario File.
- 17. IF desired, take a SNAPSHOT and save into an available IC for later use.
- 18. PLACE a clearance on the following equipment.
Component Position APRM 2 Blue Tag
- 19. INSTALL Protected Equipment signage and UPDATE RTGB placard as follows:
Protected Equipment
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- 20. VERIFY 0ENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-13 is in place.
- 21. ENSURE each Implementing References listed in Section 5 is intact and free of marks.
- 22. ENSURE all materials in the table below are in place and marked-up to the step identified.
Required Materials Mark up of 2OP-30, Section 6.3.1, completed up to step 3.
0GP-12, Power Changes, Section 6.2 completed up to Step 43.
- 23. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.
- 24. PROVIDE Shift Briefing sheet for the CRS.
- 25. CONDUCT exam pre-job brief with evaluation team IAW AD-TQ-ALL-0420, Conduct of Simulator Training and Evaluation.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 10 of 89 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Annunciator ZA761 - [CRD ACCUM LO PRESS/HI LEVEL]
1 DO Override Q2BLIUAD - [ACCUM-ROD DISPLAY]
2 Trigger Command dod:q2bliuad 3 Trigger Command and:za761 4 Malfunction RD018F [A] - [CRD PUMP SUCTION FILTER PLUGGED]
5 Remote Function RD_RDSUCTF [A V305/308] - [SUCTION FILTER ISOL VALVES]
5 Remote Function RD_RDSUCTF [B V307/309] - [SUCTION FILTER ISOL VALVES]
6 Annunciator ZUA343 - [OFF-GAS FILTER DIFF HIGH]
7 Malfunction ES014F - [INADVERTANT HPCI SYS INITIATION]
7 Malfunction ES013F - [HPCI LOGIC BUS A AUTO START FAILS]
8 Remote Function HP_ZVHP041M - [SUPP SUCTION VLV E41-F041]
9 Remote Function HP_ZVHP042M - [TORUS SUCTION VLV E41-F042]
10 Malfunction CW015F - [CW SCREEN HI DELTA P]
11 Remote Function SL_IASLRA - [2A SLC PUMP MOTOR BKR]
12 Remote Function SL_IASLRB - [2B SLC PUMP MOTOR BKR]
13 Remote Function EP_IAEOPJP1 - [BYPASS LL-3 GROUP I ISOL (SEP-10)]
14 Malfunction RP005F - [AUTO SCRAM DEFEAT]
15 Trigger Command and:zua343 Trig # Trigger Text 11 !K2119NWD - Not [S/B LIQ PUMP A & B]
15 QK214RRZ - [AOG SYS ISOL HCV-101 RED]
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 89 MALFUNCTIONS Malf Mult Current Target Rmp Description Actime Dactime Trig ID ID Value Value time CRD PUMP SUCTION FILTER RD018F A 0.000 100.0 01:00 4 PLUGGED HPCI LOGIC BUS A AUTO START ES013F False True 7 FAILS INADVERTANT HPCI SYS ES014F False True 7 INITIATION CW015F CW SCREEN HI DELTA P 0.000 60.0 10 NI032F APRM 2 APRM FAILS LO True True RP009F ATWS 2 True True RP005F AUTO SCRAM DEFEAT False True 14 REMOTES Current Target Rmp Remf Id Mult Id Description Actime Trig Value Value time RD_RDSUCTF A V305/308 SUCTION FILTER ISOL VALVES OPEN CLOSE 0:00:05 5 RD_RDSUCTF B V307/309 SUCTION FILTER ISOL VALVES CLOSE OPEN 5 HP_ZVHP041M SUPP SUCTION VLV E41-F041 ON OFF 8 HP_ZVHP042M TORUS SUCTION VLV E41-F042 ON OFF 9 SL_IASLRA 2A SLC PUMP MOTOR BKR CLOSE OPEN 11 SL_IASLRB 2B SLC PUMP MOTOR BKR CLOSE OPEN 12 BYPASS LL-3 GROUP I ISOL (SEP-EP_IAEOPJP1 OFF ON 13 10)
PANEL OVERRIDES Position / Actual Override Rmp Tag ID Description Actime Dactime Trig Target Value Value time Q2BLIUAD ACCUM-ROD DISPLAY ON/OFF OFF ON 1 K2624A CS-5562 ARI RESET OFF OFF ANNUNCIATORS Override Window Description Tagname OVal AVal Actime Dactime Trig Type CRD ACCUM LO PRESS/HI 6-1 ZA761 ON ON OFF 1 LEVEL 4-3 OFF-GAS FILTER DIFF HIGH ZUA343 ON ON OFF 6
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 12 of 89 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1: Placing 2A SJAE in Full Load Simulator Operator Actions Ensure Monitored Parameters is open and Variables are loaded.
NOTE Event 2 can be performed as the BOP Operator is performing this Event.
Simulator Operator Role Play If contacted as TBAO to remain available for valve or breaker problems, acknowledge request If contacted for status of service air injection, report it is not aligned to SJAE 2B.
If contacted as E&C provide name (Jerry Johnson), if contacted to perform sampling acknowledge request.
If contacted as I&C, provide name (James Sparks), acknowledge request for jumpers to be removed. After a minute report jumpers have been removed and verified.
If contacted report WCC will establish a supplemental check.
Evaluator Notes Plant Response: 2B SJAE operating at half load will be S/D and 2A SJAE operating at half load will be in full load.
Objectives: SRO - Direct BOP operator to place 2A SJAE in full load, secure Off Gas Train B.
RO - Monitor plant parameters.
BOP - Place 2A SJAE in full load, secures Off Gas Train B.
Success Path: 2A SJAE is placed in full load IAW 2OP-30 Section 6.3.1.
Event Termination: When Step 8 of section 6.3.1 (depressing Off Gas Train B Master Switch Off/Reset pushbutton) is complete and at the direction of the Chief Examiner, go to Event 2 or 3 as applicable.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 89 EVENT 1: Placing 2A SJAE in Full Load Time Pos EXPECTED Operator Response NOTES SRO Conduct shift turnover shift briefing.
Directs BOP operator to place 2A SJAE in full SRO load IAW 2OP-30 SRO May conduct a brief (see Enclosure 1 page 71)
May contact TB AO to remain available to BOP respond to any valve or breaker problems Performs 2OP-30 Section 6.3.1
- Depresses 2-OG-CS-4290, Off Gas Train A Full Load pushbutton NOTE: UA-45 6-3 will alarm when the full load pushbutton is depressed. Applicant should diagnose that this is normal until the BOP Off Gas Train B Off button is depressed and the CO-V17 closes.
- Verifies valves
- Monitors SJAE Off-Gas rad monitors
- Secures Off Gas train B
- Direct Chemistry to perform surveillance for SR 3.7.5.1 ATC Monitors plant parameters
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 20 of 89 EVENT 2: Accumulator Alarm Simulator Operator Actions At the direction of the lead evaluator, Insert Trigger 1 to actuate the accumulator alarm and light.
When directed to re-charge the accumulator, Initiate Trigger 2 to delete the accumulator light and Initiate Trigger 3 to delete the accumulator alarm.
NOTE This event can be performed as the BOP Operator is performing Event 1.
Simulator Operator Role Play When dispatched as RB AO, report CRD 18-31 indicates low pressure condition. The pressure gauge is reading 930 psig.
If directed to re-charge accumulator acknowledge request. After Tech Specs have been addressed and Sim Operator has deleted alarm report accumulator is re-charged with pressure reading 980 psig.
Evaluator Notes Plant Response: Receives alarm for accumulator 18-31. SRO will declare the Accumulator INOP or the Control Rod scram time slow due to low pressure IAW TS 3.1.5. The AO will re-charge the accumulator.
Objectives: SRO - Declare accumulator INOP due to low pressure condition.
RO - Direct AO to investigate/re-charge CRD accumulator.
BOP - Monitors the plant Success Path: TS 3.1.5 declared and then accumulator re-charged to clear annunciator.
Event Termination: At the direction of the Chief Examiner, go to Event 3.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 21 of 89 EVENT 2: Accumulator Alarm Time Pos EXPECTED Operator Response NOTES Acknowledges receipt of alarm SRO A-07 (6-1) CRD Accum Lo Press/Hi Level Reviews Tech Spec 3.1.5 with the accumulator pressure <940 psig.
Declares the Control Rod scram time slow (Condition A.1)
OR Declares Accumulator INOP (Condition A.2)
When accumulator is re-charged to >940 psig, exits Tech Spec 3.1.5.
May conduct a brief (see Enclosure 1 page 71)
BOP Monitors the plant Acknowledge, report, reviews alarm ATC A-07 (6-1) CRD Accum Lo Press/Hi Level Dispatches RB AO to determine Accumulator condition.
Direct the Accumulator to be re-charged IAW 2OP-08.
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 25 of 89 EVENT 3: Raise Reactor Power Simulator Operator Actions Simulator Operator Role Play If contacted as RE, concur with any recommendations provided by the crew.
If asked report that the Alternate Power verification at 90% power was SAT.
Evaluator Notes Plant Response: From an initial power of 90% RTP, the operating crew will increase reactor power to 97% using Recirc flow.
Objectives: SRO - Direct actions for power increase using Recirc flow RO - Raise power BOP - Monitor balance of plant Success Path: Power is raised to 97% using Recirc flow.
Event Termination: Once reactor power reaches 97%, and at the direction of the Chief Examiner, go to Event 4.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 26 of 89 EVENT 3: Raise Reactor Power Time Pos EXPECTED Operator Response NOTES Directs power to be raised using recirculation SRO flow SRO May conduct a brief (see Enclosure 1 page 71)
May verify operation on the Power to Flow Map BOP BOP Monitors and adjusts balance of plant conditions ATC May reference 2OP-02 section 6.1.3 ATC Request peer checker / reactivity team Speed changes are accomplished by Raises power using recirculation flow to ~97% depressing Raise Slow or Raise power. Medium pushbuttons. The Raise Slow pushbutton changes Recirc pump
- Raise recirc pump speed by depressing the speed at 0.06%/increment at 1 Master Raise Slow or Medium pushbutton. rpm/second. The Raise Medium pushbutton changes Recirc pump speed at 0.28%/increment at 5
- Confirm the following:
rpm/second
- A rise in Recirc Pump A(B) Speed Demand, Calculated Speed, and a rise in Actual Speed.
- A rise in reactor power
- A rise in B32-R617(R613) [Recirc Pump A(B) Discharge Flow]
- A rise in B32-VFD-IDS-003A(B) [Recirc VFD 2A(B) Output Wattmeter]
- A rise in B32-VFD-IDS-001A(B) [Recirc VFD 2A(B) Output Frequency Meter]
- May null the DVM as power is raised.
- Continues raising recirc pump speed until 97% power is obtained
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 32 of 89 EVENT 4: CRD Pump Trip due to High Filter d/P Simulator Operator Actions When directed by the Lead Examiner, Insert Trigger 4, CRD suction filter high differential pressure, (It takes about 1 min 15 sec for the first alarm and then another 30 seconds for the pump trip)
When directed to swap CRD suction filters, Insert Trigger 5, to open the standby filter isolation valves and close the in service isolation valves.
Simulator Operator Role Play When RBAO requested to swap suction filters (2OP-08 Section 6.3.5), report the swap is complete after SIM OP completes the action. (Ensure that when reporting back as the RBAO, use the phrase Time Compression is being used)
If contacted acknowledge request for maintenance to change filter.
If asked as RBAO, report pre-start checks completed for appropriate CRD Pump.
When directed as RBAO to perform 2OP-02, Section 6.3.6, Restoring Seal Purge Flow with Pump Running - Seal Leakage Normal, report steps 4 & 5 are complete and verified. After directed, Report steps 8, 9 & 10 actions are complete.
Evaluator Notes Plant Response: CRD Pump will trip due to high differential pressure on the suction filter. The standby suction filter will need to be placed in service and then the CRD Pump can be restarted.
Objectives: SRO - Direct CRD suction filters swapped and CRD pump restarted.
RO - Direct AO to swap CRD suction filters.
BOP - Monitor the plant.
Success Path: CRD suction filters are swapped and CRD pump restarted IAW 2OP-08.
Event Termination: At the direction of the Chief Examiner, go to Event 5.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 33 of 89 EVENT 4: CRD Pump Trip due to Filter d/P Time Pos EXPECTED Operator Response NOTES Direct RO to announce and enter 0AOP-02.0, SRO Control Rod Malfunction/Misposition.
Direct Maintenance to replace CRD Suction Filter A.
Direct CRD suction filters swapped and CRD pump restarted.
May conduct a brief (see Enclosure 1 on page 71 for format)
BOP Monitors the plant Acknowledge and report A-05 alarms:
6-1 CRD Pump Inlet Filter P High ATC 3-1 CRD Pump 2A Lo Suct Press 5-1 CRD Pump 2B Lo Suct Press Announce and enter 0AOP-02.0, Control Rod Malfunction/Misposition.
Direct AO to swap CRD suction filters IAW 2OP-08, Section 6.3.5.
Start CRD pump IAW 0AOP-2.0, Step 4.2.8 OR 2OP-08 Section 6.3.20 Restore seal purge flow IAW OP-02, Section 6.3.6.
AO to perform steps 4 & 5, and then 8, 9 & 10.
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 40 of 89 EVENT 5: Off Gas Filter High D/P Simulator Operator Actions At the direction of the lead evaluator, Initiate Trigger 6 to bring in Off-Gas Filter Diff-Hi annunciator Simulator Operator Role Play IF contacted as Outside AO to verify Off-gas filter Diff pressure, report local DP indication is reading 11 inches water.
IF contacted as Unit One report steps 6.3.3.2 and 3 are complete. (1-OG-FV-244-4, 1-OG-FV-244-5, and 1-AOG-HCV-101 are closed)
IF contacted as Outside AO report 1-OG-CD-V7 is CLOSED (Step 4)
IF contacted as Outside AO report 2-OG-CD-V7 is OPEN (Step 5)
IF contacted as Outside AO to verify Off-gas filter Diff pressure after filter swap, report local DP indication is reading 3 inches water.
When contacted as AO report 2-AOG-HCV-101 is in OPEN position.
Evaluator Notes Plant Response: Off-Gas Filter Diff-Hi alarm annunciates.
Objectives: SRO -Direct actions in response to a Off-gas Filter Diff-Hi alarm.
BOP - Respond to clogged off-gas filter IAW APP and 2OP-30.
Success Path: Swap Off-gas filters per OP-30.
Event Termination: At the direction of the Chief Examiner, go to Event 6.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 41 of 89 EVENT 5: Off Gas Filter High D/P Time Pos EXPECTED Operator Response NOTES Direct crew to perform the actions of UA-3, 4-3, SRO OFF GAS FILTER DIFF-HIGH alarm Direct crew to swap Off-gas filters per 2OP-30 Section 6.3.3.
May conduct a brief (see Enclosure 1 on page 71 for format)
ATC Monitors the plant.
Respond to UA-3, 4-3, OFF GAS FILTER DIFF-HIGH alarm BOP Dispatch Outside AO to verify Off-gas filter Diff Hi locally Place Off-gas Standby filter in service per OP-30 Section 6.3.3
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 45 of 89 EVENT 6: HPCI Logic Bus A Failure Simulator Operator Actions When directed by lead evaluator, Initiate Trigger 7 to activate HPCI fuse failure.
If requested to open breakers for E41-F041 and F042 (MCC 2XDA) when valves are shut, After AO is dispatched to the breakers set up auto triggers based on red light off on the appropriate valves from the panel mimic (P601 Section A2).
When E41-F041 indicates closed, open breaker (TRG 8 HP_ZVHP041M).
When E41-F042 indicates closed, open breaker (TRG 9 HP_ZVHP042M).
Simulator Operator Role Play If asked as AO to investigate, report all circuit breakers in DC SWBD 2A & Panel 4A are closed If asked as I&C to investigate, wait 2 minutes and report fuse E41-F1 in panel P620 is blown (blows again if replaced).
If asked as WCC SRO for clearance or Equipment Control tags, acknowledge request.
If requested to open breakers for E41-F041 and F042 (MCC 2XDA) after Sim Op sets up auto Triggers 8 and 9, inform RO that you are standing by.
Evaluator Notes Plant Response: The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable IAW TS 3.5.1.
Objectives: SRO - Directs OATC to address applicable APPs.
Evaluate TS 3.5.1 Condition D and TRM 3.6 RO - Diagnose logic failure, and respond IAW A-01 (5-5)
BOP - Monitor balance of plant Success Path: HPCI declared inoperable IAW TS 3.5.1 and isolated IAW A-01 (5-5)
Event Termination: Once HPCI is isolated with TSs addressed or upon Chief Examiner direction if the applicant elects not to pursue TSs at this time, the Chief Examiner can move to Event 7.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 46 of 89 EVENT 6: HPCI Logic Bus A Failure Time Pos EXPECTED Operator Response NOTES SRO Direct annunciator response for A-1 (5-5) and (6-4)
Contacts I&C to investigate HPCI LOGIC BUS A SRO PWR FAILURE 3.5.1 ECCS Operating:
CONDITION D: HPCI system inoperable REQUIRED ACTION:
D.1 Verify by administrative means RCIC System is OPERABLE.
Immediately SRO AND D.2. Restore HPCI System to OPERABLE status.
TRM 3.6 Bus Power Monitors:
Condition A - Verify bus power availability to the system's logic in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
May conduct a brief SRO (see Enclosure 1 on page 71 for format)
BOP Monitors Plant ATC/
Verifies RCIC in standby lineup (Administratively operable)
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 47 of 89 Acknowledge and report annunciators A-1 (5-5)
ATC and (6-4)
May report HPCI Suction is aligned to both the ATC CST and Suppression Pool.
Performs A-1 (5-5) actions:
- 1. Close the Condensate Storage Tank Suction Valve, E41-F004.
- 1) CLOSE STEAM SUPPLY INBOARD ISOL VLV, E41-F002.
- 2) CLOSE STEAM SUPPLY OUTBOARD ISOL VLV, E41-F003.
- 3. Close the Turbine Exhaust Vacuum Breaker Valve, E41-F075.
Contacts RBAO to standby for opening breakers on MCC 2XDA when the following valves indicate Full Closed.
- 4. Close the Torus Suction Valve, E41-F041.
- 5. Close the Torus Suction Valve, E41-F042.
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 55 of 89 EVENT 7: Intake Blockage Simulator Operator Actions When directed by lead evaluator, Initiate Trigger 10 to start Intake blockage When CW Pump C is started and report of large amount of gracilaria is approaching intake structure, Modify CW015F, CW SCREEN HI DELTA P to 100 Simulator Operator Role Play As Outside AO report that there appears to be a small influx of gracilaria.
If asked report that screen A d/P is 20 inches and rising.
If asked report travelling screens are in high speed.
When CWIP A trips report screen A d/P is 48 inches and rising.
When CW Pump C is started report a large amount of gracilaria is approaching the intake structure.
If requested report pre-start checks for CWIP C are SAT.
Evaluator Notes Plant Response: An influx of gracilaria will cause intake structure alarms and then trip of CW Pumps.
The crew will start the CW Pump C. After the standby pump is started a total blockage of the traveling screens will occur requiring the crew to insert a manual scram.
Objectives: SRO - Direct entry into 0AOP-37.1, Direct starting of the standby CW Pump.
RO - Reduce power to maintain vacuum.
BOP - Start a standby CW Pump.
Success Path: Starts the standby CW Pump.
Event Termination: When CW Pump C has been started and a reactor manual scram has been inserted go to Event 8.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 56 of 89 EVENT 7: Intake Blockage Time Pos EXPECTED Operator Response NOTES Acknowledge report of CW alarms.
Direct entry into 0AOP-37.1, Intake Structure Blockages.
SRO May direct placing Circ Isol Valves Mode Selector switch to the D position Direct starting of the standby CW Pump.
May direct reactor power reduced.
May conduct a brief (see Enclosure 1 on page 71 for format)
Reduces reactor power as directed by the CRS ATC in accordance with 0ENP-24.5.
Inserts a reactor manual scram when directed by the CRS.
Monitor the plant
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 57 of 89 EVENT 7: Intake Blockage Time Pos EXPECTED Operator Response NOTES Reports UA-01 CW alarms as they occur:
1(2)(3)(4)-5, CW Screen A(B)(C)(D) Diff-High BOP Or Stopped 1-4, CW Screen Diff Hi-Hi 1(2)(3)(4)-7, CW Pump A(B)(C)(D) Trip Announces and enters 0AOP-37.1, Intake BOP Structure Blockages Directs Outside AO to report / investigate CW BOP intake alarms.
Places Circ Isol Valves Mode Selector switch to the D position and starts CW Pump C.
BOP Continues to start available CW Pumps until a manual reactor scram is inserted.
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 66 of 89 EVENT 8: Scram Actions / ATWS Simulator Operator Actions When power is lowered to 3.5%, Initiate Trigger 12 to trip SLC Pump If requested to defeat Group I LL3, wait 2 minutes, and Initiate Trigger 13.
If requested to install LEP-02, Section 2.3 jumpers, wait 5 minutes, and Initiate Trigger 14.
Delete ARI malfunction when a level band is established IAW ATWS step RC/L-17, and at the direction of the Lead Evaluator.
Delete ATWS when scram reset and air header is re-pressurized.
DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Simulator Operator Role Play Acknowledge request as Maintenance/I&C to investigate failures (SLC, and ARI reset logic) acknowledge the requests.
Acknowledge request to perform LEP-03 actions.
When scram jumpers requested, after 5 minutes and when Sim OP has performed trigger then inform crew that Scram Jumpers are installed IAW LEP-02 Section 2.3 When a level band is established IAW ATWS step RC/L-17, and at the direction of the lead evaluator, Inform crew that ARI can be reset (found a loose wire).
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 67 of 89 Evaluator Notes Plant Response: Following the SCRAM, the crew will transition to 2EOP-01-ATWS with the BOP operator maintaining directed level/pressure bands. The MSIV will close due to vacuum loss, the crew is expected to enter 0EOP-02-PCCP on torus temperature, and control pressure with SRVs. ADS will be inhibited (Critical task). The crew will perform 0EOP-01-LEP-02 for control rod insertion. The ATC will inform the CRS of the failure of ARI to reset. The CRS will direct terminate and prevent RPV injection.
(Critical Task to be performed to prevent exceeding HCTL). One SLC Pump will trip when started and the other SLC pump will trip shortly after being started and LEP-03 will need to be performed. Rod insertion will continue IAW 0EOP-01-LEP-02 to lower power so as to not perform Emergency Depressurization on HCTL exceedance (0EOP-02-PCCP). When a level band is established IAW ATWS step RC/L-17, and at the direction of the lead evaluator, ARI will be fixed. The crew can reset the scram and insert all rods via manual scram.
Objectives: SRO - Enter and Direct actions to control reactor power, terminate and prevent injection, Inject SLC, and control Torus temperature IAW ATWS and PCCP.
ROs - Perform ATWS and PCCP actions as directed by the CRS:
SCRAM Immediate Actions, Control pressure with SRVs, Terminate and Prevent injection, Initiate SLC / LEP-03, Insert rods, and Align Torus Cooling Success Path: Inhibit ADS, reduce reactor power by tripping recirc pumps, lowering reactor water level IAW ATWS and inserting rods IAW LEP-02.
Scenario Termination: When all rods are inserted and level is being restored towards the normal band, the Chief Examiner can terminate this scenario.
Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluator/instructor.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 68 of 89 EVENT 8: ATWS Time Pos EXPECTED Operator Response NOTES Enters RSP, transitions to ATWS and SRO announces to crew.
Directs or Verifies:
- Mode switch to shutdown when steam flow is <3 Mlbms/hr
- ARI initiation RC/Q-2
- RR pumps verified tripped RC/Q-5
- Inhibit ADS
- insertion of rods per LEP-02
- pressure band 800-1000 psig
- Terminate and Prevent Injection (based on APRM >2% and level >90 inches).RC/L-2 When second SLC pump is reported as tripped; Directs injection of boron IAW LEP-03 Contacts maintenance to investigate When Torus temp is > 95°F:
- enters and announces PCCP
- directs maximize torus cooling If table Q-2 conditions are met, directs continuation of terminate and prevent until table Q-2 is no longer met. (APRM downscale, TAF)
If DW temp reaches 150°F directs:
Secures SLC injection.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 69 of 89 Performs SCRAM Immediate Actions ATC (Enclosure 2 Page 72)
When directed performs initial ATWS actions:
- places MODE switch in shutdown when steam flow is <3 Mlbms/hr
- verifies tripped RR pumps
- reports reactor power When directed insert control rods using one Critical Task #1 or more methods contained in 0EOP-01-LEP-02 to achieve reactor shutdown under all conditions prior to exceeding HCTL (Enclosure 3 see page 73)
- Inserts control rods with RMCS.
- Reports failure of ARI to reset
- Requests scram jumpers installed
- When LEP 02 Section 2.3 jumpers are installed performs section 2.3 manual scram actions.
Monitors reactor power and reports if APRM downscales are reached.
2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 70 of 89 EVENT 8: ATWS Time Pos EXPECTED Operator Response NOTES Controls RPV pressure and level as directed by BOP the CRS When directed,
- To prevent an uncontrolled RPV Critical Task #2 depressurization and subsequent power excursion, inhibit ADS prior to automatic initiation of ADS
- defeats Group 10 isolation
- Initiates or verifies any isolations and actuations for level which should have occurred When directed, Terminate and Prevent (T/P) Critical Task #3 injection into the RPV (except for CRD/SLC/RCIC) from ECCS and Feedwater until conditions are met to re-establish injection to prevent exceeding HCTL.
(Enclosure 4 Pages 81)
When directed, injects SLC.
When pumps trip reports failure of SLC pumps.
Aligns CRD for Boron injection IAW LEP-03 (Enclosure 5, Page 83)
When directed performs terminate and prevent based on Table Q-2. (Enclosure 4, Page 81)
Note- this may be a continuation of the initial terminate and prevent based on power.
When APRM downscales or TAF is reached, maintains RPV level as directed by CRS.
When Torus temperature is greater than 95° F, places Torus Cooling in service.
(Enclosure 6, Pages 84)
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2020 NRC SCENARIO 2, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 88 of 89 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment Category Standard Scenario Content Total Malfunctions 5-8 8 Malfunctions after EOP 1-2 2 Entry Abnormal Events 2-4 2 Major Transients 1-2 1 EOPs Used 1-2 2 EOP Contingency 1-2 3 Crew Critical Tasks >2 3 Tech Specs 2 2 Instrument / Component 2 - ATC 2 Failures before Major 2 - BOP 2 Instrument / Component 2 2 Failures after Major Normal Operations 1 1 Reactivity manipulation 1 1
LOI SIMULATOR EVALUATION GUIDE ATTACHMENT 2 - Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek J. Pierce B. Craig Manager: Manager:
Mode: 1 Rx Power: 90%
Plant Risk:
Green Current EOOS Risk Assessment is:
SFP Time to 90.1 hrs. Days Online: 300 days 200 Deg F:
Place 2A SJAE in Full Load and shutdown 2B SJAE IAW 2OP-30, Section 6.3.1 for planned maintenance on 2B SJAE.
Rod Adjustments have been completed. The next step of the reactivity Turnover: plan directs raising reactor power to 97% using recirculation flow in accordance with 0GP-12 (no restrictions).
APRM 2 Failed Downscale and bypassed.
1A NSW Under Clearance.
Protected Equipment: 2A/2B NSW.
The BOP is to place 2A SJAE in Full Load, 2OP-30, Section 6.3.1 is Comments: complete up to step 3.
After 2A SJAE is in Full Load, raise reactor power to 97%.
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: NRC 3 Op-Test No.: Draft Examiners: ___________________________ Operators: ____________________________
Initial Conditions: Reactor power is 100%, APRM 2 is bypassed. 1A NSW Pump is under clearance.
Turnover: The BOP Operator is to perform 0PT-40.2.11, Main Generator Voltage Regulator Manual and Automatic Operational Check.
Critical Task #1 Insert a reactor scram when HPCI reaches its Max Safe Operating Value (HPCI Area Temperature Max normal is equal to Max Safe.)
Critical Task #2 (time critical) Isolate fire protection to the Reactor Building within 15 minutes of HELB.
Critical Task #3 Perform Emergency Depressurization when more than one area exceeds the same Max Safe Operating Value or EQ Envelope for the same parameter Event Malf. No. Event Type* Event No. Description
- Perform PT-40.2.11, Main Generator Voltage N-BOP 1 Regulator Manual And Automatic Operational N-CRS Check C-ATC *Failure of DWED pump to run 2
C-CRS A-04 I-ATC *Recirc Loop B Flow transmitter failure 3 NI063F I-CRS TS 3.3.1.1, TRM 3.3 CW025F C-BOP NSW Pump Trip, Standby Fails to Auto Start 4
- Condenser Tube leak \ Isolate condenser C-BOP 5 CN012F waterbox CSRO AOP-26 R-ATC 5a Lower power due to tube leak N-CRS M
C *HPCI Unisolable Steam Leak 6 ES047F C *RHR Room Cooler Trip AOP-5.0, RVCP, SCCP M Emergency Depressurization 7
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 SCENARIO DESCRIPTION
SUMMARY
Event Description Perform 0PT-40.2.11, Main Generator Voltage Regulator Manual And Automatic 1
Operational Check.
Following receipt of annunciator A-4 (1-1), the crew is expected to diagnose a failure 2
of the DWED pump to run. The ATC is then expected to start a DWED pump.
The Recirc Loop B flow transmitter to APRM Channel 4 will fail downscale resulting in a rod block and a trip input to each voter. The crew will respond per APPs and 3 bypass APRM 4. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. APRM TS Actions to be taken requires the APRM mode selector switch to be place in INOP IAW 0OI-18 The running NSW pump will trip on motor overload. The STBY NSW pump will fail to 4 auto start. The BOP operator should recognize the failure and manually start the STBY NSW pump. The CRS will evaluate Tech Specs A tube leak will occur in the main condenser resulting in high conductivity alarms.
5 The crew will respond per 0AOP-26.0. Water box will be isolated IAW OP-29 or 0AOP-26.0 5a Power will be reduced to 53% for water box removal A HPCI steam line break will occur. The crew will enter AOP-05 and EOP-03-SCCP.
HPCI will fail to isolate. The reactor will be manually scrammed when HPCI area 6 exceeds its Maximum Safe Operating Temperature. Secondary Containment area temperatures will continue to rise.
RHR Room Cooler Fans Trip 2 Areas will exceed Max Safe Operating Temperature requiring ED.
2 ADS valves will fail to open requiring the crew to open two additional SRVs.
7 When actions are taken to depressurize the reactor to < 100psig, or at the discretion of the chief examiner, the scenario may be terminated.
BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2020 NRC SCENARIO 3, ES-D-2 0PT-40.2.11, APRM FLOW UNIT FAILURE,DWED PMP, NSW PMP, CONDENSER TUBE LEAK, HPCI STM LEAK, ROOM COOLER TRIP, 2 ADS VALVES FAIL REVISION 0 Developer: S. Cotton Date: 5/18/20 Technical Review: Bob Bolin Date: 6/18/20 Validators: Mike Long Date: 8/19/20 Mike Maricle Steve Hildebrandt Facility Representative: Rob Mehs Date: 9/15/20 Training Approval: Ed Rau Date: 09/16/20
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 65 REVISION
SUMMARY
0 Scenario developed for 2020 NRC Exam.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 3 of 65 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE .................................................................................................................. 4 2.0 SCENARIO DESCRIPTION
SUMMARY
.................................................................................. 5 1.0 CREW CRITICAL TASKS ........................................................................................................... 6 2.0 TERMINATION CRITERIA .......................................................................................................... 7 4.0 IMPLEMENTING REFERENCES .............................................................................................. 7 5.0 SETUP INSTRUCTIONS ............................................................................................................. 8 6.0 INTERVENTIONS....................................................................................................................... 10 7.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES .................................... 14 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment .................................................... 64 ATTACHMENT 2 - Shift Turnover ........................................................................................................ 65
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 4 of 65 1.0 SCENARIO OUTLINE Event Malf. No. Type* Event Description N-BOP *Perform 0PT-40.2.11, Main Generator Voltage Regulator 1
N-CRS Manual And Automatic Operational Check C-ATC *Failure of DWED pump to run 2
C-CRS A-04 I-ATC *Recirc Loop B Flow transmitter failure 3 NI063F I-CRS TS 3.3.1.1, TRM 3.3 CW025F C-BOP NSW Pump Trip, Standby Fails to Auto Start 4
- Condenser Tube leak C-BOP 5 CN012F Isolate condenser waterbox C- CRS AOP-26 R-ATC Lower power due to tube leak 5a R-CRS M
C *HPCI Unisolable Steam Leak 6 ES047F C *RHR Room Cooler Trip AOP-5.0, RVCP, SCCP M Emergency Depressurization 7
(*) Not Used Previous 2 NRC Exams, (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 5 of 65 2.0 SCENARIO DESCRIPTION
SUMMARY
Event Description Perform 0PT-40.2.11, Main Generator Voltage Regulator Manual And Automatic 1
Operational Check.
Following receipt of annunciator A-4 (1-1), the crew is expected to diagnose a failure 2
of the DWED pump to run. The ATC is then expected to start a DWED pump.
The Recirc Loop B flow transmitter to APRM Channel 4 will fail downscale resulting in a rod block and a trip input to each voter. The crew will respond per APPs and 3 bypass APRM 4. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. APRM TS Actions to be taken requires the APRM mode selector switch to be place in INOP IAW 0OI-18 The running NSW pump will trip on motor overload. The STBY NSW pump will fail to 4 auto start. The BOP operator should recognize the failure and manually start the STBY NSW pump. The CRS will evaluate Tech Specs A tube leak will occur in the main condenser resulting in high conductivity alarms.
5 The crew will respond per 0AOP-26.0. Water box will be isolated IAW OP-29 or 0AOP-26.0 5a Power will be reduced to 53% for water box removal A HPCI steam line break will occur. The crew will enter AOP-05 and EOP-03-SCCP.
HPCI will fail to isolate. The reactor will be manually scrammed when HPCI area 6 exceeds its Maximum Safe Operating Temperature. Secondary Containment area temperatures will continue to rise.
RHR Room Cooler Fans Trip 2 Areas will exceed Max Safe Operating Temperature requiring ED.
2 ADS valves will fail to open requiring the crew to open two additional SRVs.
7 When reactor is depressurized, the scenario may be terminated at the direction of the chief examiner.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 65 1.0 CREW CRITICAL TASKS Critical Task #1 Insert a manual reactor scram prior to HPCI reaching its Max Safe Operating Value. (HPCI Area Temperature Max normal is equal to Max Safe. ~165 Deg. F)
Critical Task #2 (0AP-064, Time Critical Actions/Time Sensitive Actions Supplement - HELB 1)
Isolate fire protection to the Reactor Building within 15 minutes of HELB report to the control room.
Critical Task #3 Perform Emergency Depressurization when more than one area exceeds the same Max Safe Operating Value or EQ Envelope for the same parameter.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 7 of 65 2.0 TERMINATION CRITERIA 3.0 When actions are taken to depressurize the reactor to < 100psig, or at the discretion of the chief examiner, the scenario may be terminated.
4.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.
Number Title A-06, 2-8 APRM Upscale A-06, 3-8 APRM Upscale Trip / Inop A-06, 5-7 Flow Ref Off Normal A-05, 2-2 Rod Out Block A-05, 4-8 OPRM Trip Enabled A-05, 5-8 OPRM PBA/CDA Alarm UA-4, 3-5 Condenser A Hotwell Cndy High UA-01, 1-10 Nuclear Header Serv Wtr Press-Low UA-01, 2-10 Nuclear Hdr SW Pump A Trip UA-17, 6-1 BUS E3 4KV Motor Ovld 0AOP-18.0 Nuclear Service Water System Failures 0AOP-37.0 Low Condenser Vacuum A-04, 1-1 Drywell Equip Drain Sump Lvl Hi A-02, 5-7 Stm Leak Det Ambient Temp High A-01, 4-1 HPCI Turb Trip Sol Ener A-01, 3-5 HPCI Isol Trip Sig A Initiated A-01, 4-5 HPCI Isol Trip Sig B Initiated A-01, 5-4 HPCI Valves Mtr Overload UA-03, 2-7 Area Rad Rx Bldg High UA-05, 1-9 Fan Clg Unit CS Pump Rm A Inl Press Lo
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 65 5.0 SETUP INSTRUCTIONS
- 1. PERFORM TAP-438, Establishing Simulator Exam Security.
- 2. RESET the Simulator to IC-13.
- 4. ENSURE appropriate keys have blanks in switches.
- 6. ENSURE no rods are bypassed in the RWM.
- 7. VERIFY ERFIS and the Process Computer are updating in RUN (check clock time and selected points updating).
- 8. PLACE all SPDS displays to the Critical Plant Variable display (#100).
- 9. VERIFY Fireworks alarms are clear.
- 10. ENSURE hard cards, flow charts, panel gauges, indicators and recorders are cleaned up
- 11. ENSURE OP Aid Placards are updated as necessary.
- 12. VERIFY RHR Think Switches are GREEN FLAGGED
- 14. TAKE the SIMULATOR OUT OF FREEZE
- 15. ALIGN the plant as follows:
Manipulation
- 1. Bypass APRM 2.
- 2. Ensure 2A NSW pump is running, 2B in standby, and both are in Auto
- 16. LOAD Scenario File.
- 17. IF desired, take a SNAPSHOT and save into an available IC for later use.
- 18. PLACE a clearance on the following equipment.
Component Position APRM 2 Blue Tag
- 19. INSTALL Protected Equipment signage and UPDATE RTGB placard as follows:
Protected Equipment 2A and 2B NSW pumps
- 20. VERIFY 0ENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-13 is in place.
- 21. ENSURE each Implementing References listed in Section 5 is intact and free of marks.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 9 of 65
- 22. ENSURE all materials in the table below are in place and marked-up to the step identified.
Required Materials 0PT-40.2.11.
- 23. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.
- 24. PROVIDE Shift Briefing sheet for the CRS.
- 25. CONDUCT exam pre-job brief with evaluation team IAW AD-TQ-ALL-0420, Conduct of Simulator Training and Evaluation.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 10 of 65 6.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Annunciator ZA411 - [DRYWELL EQUIP DRAIN SUMP LVL HI]
2 Malfunction NI063F - [RECIRC LOOP B XMITTER FAILURE]
3 Malfunction CW025F - [NUC SERVICE WATER PUMP MOTOR OVERLOAD]
4 Malfunction CN012F - [MAIN COND 2A-S TUBE LEAK]
5 Remote Function CF_IAHWRJM - [HW MAN CNTRL S.P. FOR REJECT (0.0:1.0)]
6 Remote Function CF_CDDFAUTO - [CDD E VALVE AUTO/MANUAL]
6 Remote Function CF_FCDDDMAN - [CDD E VALVE MANUAL DEMAND]
7 Remote Function CW_ZVCW016M - [CW-V16 CW V-16 A-S CW OUTLET VLV BRK]
8 Remote Function CW_ZVCW177D - [CW-V177 CW V-177 A-S DEBR FIL VLV]
9 DI Override K5624A - [RHR PMP ROOM VENT FAN B]
9 DI Override K5623A - [RHR PMP RM VENT FAN A]
9 DI Override K5623A - [RHR PMP RM VENT FAN A]
9 DI Override K5624A - [RHR PMP ROOM VENT FAN B]
9 DI Override K5624A - [RHR PMP ROOM VENT FAN B]
9 DI Override K5623A - [RHR PMP RM VENT FAN A]
9 DO Override Q5624UGG - [RHR PUMP ROOM VENT FAN B OFF G]
9 DO Override Q5623UGG - [RHR PUMP RM VENT FAN A OFF G]
9 Malfunction ES047F - [HPCI STM BRK HPCI ROOM]
10 Remote Function HP_ZVMS402T - [E41-F002 INBD STM VLV]
11 Malfunction HP001F - [E41-F003]
13 Malfunction CW019F - [NUC SERVICE WATER PUMP MOTOR WINDING FAULT]
14 Remote Function CW_ZVCW177M - [CW-V177 CW V-177 A-S DEBR FIL VLV BRK]
15 Remote Function RD_CORV6 - [PC-4105 ISOL VALVES, CRD SUCTION FROM CDD]
16 Remote Function EP_IAEOPJ18 - [DEFEAT RCIC DIV 1 & 2 HIGH TEMP. ISOLATION LOGIC (SEP-10)]
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 65 Trig # Trigger Text 8 !Q4B033G5 - Not [COND BACKWASH CW (G)]
10 Q1116LG1 - [STM LINE VLV E41-F002 GREEN]
11 Q1117LG1 - [STM LINE VLV E41-F003 GREEN]
13 ZUA1761 - [BUS E3 4KV MOTOR OVLD]
14 !q4b033g5 && q4b033r5 - Not [COND BACKWASH CW (G)] And [COND BACKWASH V177 (R)]
MALFUNCTIONS Malf Mult Current Target Rmp Actim Dacti Description Trig ID ID Value Value time e me RECIRC LOOP B XMITTER NI063F APRM 4 0.00 0.00 2 FAILURE NI032F APRM 2 APRM FAILS LO True True NUC SERVICE WATER PUMP CW025F A False True 3 MOTOR OVERLOAD CN012F MAIN COND 2A-S TUBE LEAK 0.000 100.00 01:00:00 4 ES047F HPCI STM BRK HPCI ROOM 0.000 0.50 00:01:00 9 E41-F002 FAILURE TO AUTO ES053F True True CLOSE E41-F003 FAILURE TO AUTO ES054F True True CLOSE STEAM SUPPLY LINE
- VLV E41-HP001F E41-F003 False True 11 F003 NUC SERVICE WATER PUMP CW019F A False True 00:10 13 MOTOR WINDING FAULT
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 12 of 65 REMOTES Mult Current Target Rmp Remf Id Description Actime Trig Id Value Value time HW MAN CNTRL S.P. FOR REJECT CF_IAHWRJM .1400 0 00:03:00 5 (0.0:1.0)
CDD CF_CDDFAUTO CDD E VALVE AUTO/MANUAL AUTO MAN 6 A
CDD CF_FCDDDMAN CDD E VALVE MANUAL DEMAND 61.9679 0 00:01:00 00:00:10 6 A
CW-V16 CW V-16 A-S CW CW_ZVCW016M ON OFF 7 OUTLET VLV BRK CW-V177 CW V-177 A-S DEBR FIL CW_ZVCW177D NORMAL OPEN 8 VLV HP_ZVMS402T E41-F002 INBD STM VLV ON OFF 10 CW-V177 CW V-177 A-S DEBR FIL CW_ZVCW177M ON OFF 14 VLV BRK PC-4105 ISOL VALVES, CRD RD_CORV6 OPEN CLOSE 15 SUCTION FROM CDD DEFEAT RCIC DIV 1 & 2 HIGH EP_IAEOPJ18 TEMP. ISOLATION LOGIC (SEP- OFF ON 16 10)
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 65 PANEL OVERRIDES Position / Actual Override Rmp Tag ID Description Actime Dactime Trig Target Value Value time NUC HDR SW PMP B K4B21A AUTO ON OFF DISCH VLV NUC HDR SW PMP B K4B21A MAN OFF ON DISCH VLV K5623A RHR PMP RM VENT FAN A AUTO ON ALLOFF 00:08:00 9 K5623A RHR PMP RM VENT FAN A OFF OFF ALLOFF 00:08:00 9 K5623A RHR PMP RM VENT FAN A ON OFF ALLOFF 00:08:00 9 RHR PMP ROOM VENT K5624A AUTO ON ALLOFF 00:04:00 9 FAN B RHR PMP ROOM VENT K5624A OFF OFF ALLOFF 00:04:00 9 FAN B RHR PMP ROOM VENT K5624A ON OFF ALLOFF 00:04:00 9 FAN B RHR PUMP RM VENT FAN Q5623UGG ON/OFF ON OFF 00:08:00 9 A OFF G RHR PUMP ROOM VENT Q5624UGG ON/OFF ON OFF 00:04:00 9 FAN B OFF G AUTO DEPRESS VLV B21-K1503A AUTO ON OFF F013H AUTO DEPRESS VLV B21-K1503A OPEN OFF OFF F013H AUTO DEPRESS VLV B21-K1507A AUTO ON OFF F013C AUTO DEPRESS VLV B21-K1507A OPEN OFF OFF F013C Override Window Description Tagname OVal AVal Actime Dactime Trig Type DRYWELL EQUIP DRAIN 1-1 ZA411 ON ON OFF 1 SUMP LVL HI
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 65 7.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1: 0PT-40.2.11 Simulator Operator Actions Ensure Monitored Parameters is open and Variables are loaded.
Simulator Operator Role Play Acknowledge any requests for the Load Dispatcher.
When asked the voltage regulator operation was smooth and in the same direction of the rheostat.
Inform crew that another operator will make necessary log entries.
Evaluator Notes Plant Response: BOP performs 0PT-40.2.11 Objectives: SRO - Directs BOP to perform 0PT-40.2.11 BOP - Performs 0PT-40.2.11 RO - Monitor Balance of Plant Success Path: 0PT-40.2.11 is completed.
Event Termination: When directed by the Chief Examiner, go to next event.
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Direct performance of 0PT-40.2.11 May conduct a brief (see Enclosure 1 page 54 for format)
RO Monitors the plant Performs 0PT-40.2.11 BOP
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 22 of 65 EVENT 2: DWEDT PUMP FAILURE Simulator Operator Actions At the direction of the Chief Examiner or at simulator time 35 minutes, Initiate Trigger 1 to activate the DWED Sump Lvl Hi Annunciator.
(NOTE: This event can be performed in conjunction with Event 1)
If the simulator is left in run the DWED Sump Lvl Hi Alarm will annunciate on its own after NOTE approximately 66 minutes. (The sumps will automatically start pumping if allowed to annunciate)
When either sump pump has been running for ~30 seconds delete malfunction for the DWED Sump Lvl Hi Annunciator.
Simulator Operator Role Play Acknowledge requests as I&C for troubleshooting DWED Sump Pump auto start failure.
If asked, the last time the sumps were pump was ~4 hours ago.
Evaluator Notes Plant Response: Annunciator A-04 (1-1), Drywell Equip Drain Sump Lvl Hi.
Objectives: RO - Pump the DWEDT Success Path: Pumps the DWEDT.
Event Termination: Go to next event at the direction of the Chief Examiner.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 23 of 65 EVENT 2: DWEDT PUMP FAILURE Time Pos EXPECTED Operator Response Comments Direct actions of APPs Direct RO to start DWEDS Pump, if asked.
SRO Contact I/C for troubleshooting the failure of the DWEDS to auto start.
May conduct a brief (see Enclosure 1 page 54 SRO for format)
Refer to APP:
RO A-04 (1-1), Drywell Equip Drain Sump Lvl Hi Diagnose failure of DWEDS Pump Start a DWEDS Pump (may use 0OP-47 Section 5.3.5)
Verifies pump shuts off after a period of time.
BOP Monitors the plant
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 25 of 65 EVENT 3: RECIRC LOOP B FLOW TRANSMITTER FAILURE Simulator Operator Actions At the direction of the Chief Examiner, Initiate Trigger 2 to activate Recirc Loop B Flow failure.
Simulator Operator Role Play If contacted as I&C to investigate, acknowledge the request.
After LCO entries have been determined and SRO is waiting for I&C, call as WCCSRO and request the OATC to place APRM 4 in a tripped condition to support I&C trouble shooting. The WCC will hang the status control tag paperwork.
If asked to pull fuses (for TRM 3.3 actions, 2-C12A-F1 Labeled ROD OUT BLOCK RELAYS C12A in P616 panel) acknowledge the request Evaluator Notes Plant Response: Flow reference off normal alarm, rod block and scram signal to all 4 voters Flow transmitter signals are displayed on PC display 845, and on individual NUMACs by selecting Input Status.
Objectives: SRO - Determine LCO for APRM 4 inoperability and direct placing channel in trip.
RO - Respond To A Flow Unit/Transmitter Failure Per APP A-06 5-7.
Success Path: APRM 4 TS 3.3.1.1 declaration and placed in trip condition IAW 0OI-18.
Event Termination: Go to next event at the direction of the Chief Examiner.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 26 of 65 EVENT 3: RECIRC LOOP B FLOW TRANSMITTER FAILURE Time Pos EXPECTED Operator Response Comments Direct actions of APPs SRO Direct I&C to investigate Evaluate Tech Spec 3.3.1.1 Reactor Protection System Instrumentation TS 3.3.1.1, Function 2b, Required Action A1.
With one or more required channels inoperable, place in trip condition in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Evaluate TRM 3.3 Control Rod Block Instrumentation TRM 3.3, Function 1a, Required Condition A1.
With one of the required channels not operable -
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore to operable.
Refers to 0OI-18 for actions to place APRM 4 in a tripped condition.
Direct APRM 4 mode selector switch placed in INOP to allow I&C troubleshooting.
Direct WCC to pull fuses IAW 0OI-18 for placing APRM in tripped condition.
May conduct a brief (see Enclosure 1 page 54 for format)
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 27 of 65 EVENT 3: RECIRC LOOP B FLOW TRANSMITTER FAILURE Time Pos EXPECTED Operator Response Comments BOP Monitors the plant.
May check back panel APRM indications.
Acknowledges, refers to & reports annunciators A-6 2-8 APRM UPSCALE 3-8 APRM UPSCALE TRIP/INOP ATC 5-7 FLOW REF OFF NORMAL A-5 2-2 ROD OUT BLOCK 4-8 OPRM TRIP ENABLED 5-8 OPRM PBA/CDA ALARM Diagnose and report failure of APRM 4 Flow Transmitter Obtains key number 114 from the SRO key locker to place APRM 4 in trip.
Places APRM mode selector switch in INOP IAW 0OI-18.
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 30 of 65 EVENT 4: NSW PUMP TRIP, STANDBY FAILS TO AUTO START Simulator Operator Actions At the discretion of the Chief Examiner, Initiate Trigger 3 to trip the NSW pump 2A.
NOTE Alarm will come in after ~2 minutes, trip will occur ~45 seconds later.
Simulator Operator Role Play If contacted as Outside AO to investigate NSW pump and breaker; For the breaker report 51 devices are tripped at the breaker on E3, For the pump report and no indication of smoke or fire at the pump.
If contacted as maintenance or I&C to investigate trip/Auto start failure, acknowledge request Evaluator Notes Plant Response: The running NSW pump will TRIP on motor overload. The STBY NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the STBY NSW pump. With a U1 NSW pump under clearance will require entry into TS.
Objectives: SRO - Direct actions for loss of NSW Determine actions required for LCO per Technical Specifications BOP - Respond to the failure of an automatic start of the B NSW pump Success Path: Determine TS required actions and Start 2B NSW Pump.
Event Termination: At the direction of the Chief Examiner, go to the next event.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 31 of 65 EVENT 4: NSW PUMP TRIP, STANDBY FAILS TO AUTO START Time Pos EXPECTED Operator Response NOTES Direct entry into 0AOP-18.0, Nuclear Service SRO Water System Failure.
Contact maintenance to investigate trip of 2A NSW Pump.
SRO May also report to I/C that 2B NSW Pump did not auto start.
Evaluate Tech Spec 3.7.2 Service Water System and Ultimate Heat Sink.
- Determine 2A NSW pump inoperable
- Determine 1B NSW Pump inoperable due to clearance.
- Per the Bases, 3 NSW pumps required site wide.
- 3.7.2 Condition B. One required NSW pump inoperable for reasons other than condition A. Required Action B.1 Restore required NSW pump to Operable status in 7 days May direct the standby CSW pump to be placed SRO in standby on the NSW header. (2OP-43, section 6.3.40)
SRO May conduct a brief (see Enclosure 1 page 54 for format)
ATC Monitors the plant
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 32 of 65 EVENT 4: NSW PUMP TRIP, STANDBY FAILS TO AUTO START Time Pos EXPECTED Operator Response NOTES Acknowledge / reference UA-17 (6-1) BUS E3 4KV Motor Ovld BOP UA-01 (1-10) Nuclear Header Serv Wtr Press-Low UA-01 (2-10) Nuclear Hdr SW Pump A Trip Recognize trip of 2A NSW pump and lowering NSW system pressure.
Announce and execute 0AOP-18.0, Nuclear Service Water System Failure.
Recognize the failure of the STBY NSW pump to start and starts standby pump.
- Places 2B NSW pump in Manual.
- Starts 2B NSW Pump.
May align the Standby CSW pump to standby on the NSW header (2OP-43, section 6.3.40 provides guidance to place CSW Pump on Nuclear Header).
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 35 of 65 EVENT 5: CONDENSER TUBE LEAK/LOWER POWER/ISOLATE WATERBOX Simulator Operator Actions At the discretion of the lead evaluator, Initiate Trigger 4 to start condenser tube leak.
If requested to secure reject to CST, Initiate Trigger 5.
If requested to secure a CDD, Initiate Trigger 6 to isolate CDD-A.
If requested to transfer CRD suction to the CST, wait 4 minutes and Initiate Trigger 15.
If requested to turn breaker off to CW-V16, Initiate Trigger 7.
If requested to open flush valve CW-V177 and turn off breaker to flush valve Initiate Trigger 8.
Simulator Operator Role Play If contacted as chemistry to sample reactor coolant and condensate, acknowledge the request.
Ensure 0AOP-26.0 conditions requiring manual scram are not met. (Condensate Pump conductivity 0.3 µmho, Rx water 5.0 µmho.)
If contacted as Reactor Engineer for instructions on power reduction, ask the CRS for their recommendation and then concur with the recommendation.
If requested as Radwaste to secure reject to CST or isolate a CDD, acknowledge request and inform Sim Operator.
If informed as plant management of chemistry conditions, acknowledge receipt of information.
If requested to secure cathodic protection, acknowledge the request.
If WCC is informed of waterbox A-S chloride/conductivity issues, report that 2OP-29 section 6.3.28 NPDES Permit Compliance Verification has been performed, and CW Mode position B is appropriate and that clearance development is in progress.
If asked to perform steps of 2OP-29 sect 6.3.9 or actions of 0AOP-26.0, coordinate actions with Sim Operator and proceed as follows:
If asked to shutdown condenser waterbox air removal system report 2OP-29, Section 6.3.16 has been completed.
Inform CR cathodic protection is shutdown for condenser 2A.
Turn breaker off to CW-V16 wait 1 minute inform Sim Operator to perform action and then report complete. (0AOP-26.0 step 5h)
Open flush valve CW-V177 and turn off breaker to flush valve wait 1 minute and inform Sim Operator to perform action and then report complete. (0AOP-26.0 step K& L)
If asked as Radwaste to isolate a CDD, wait 3 minutes and inform Sim Operator to perform action and then report complete.
If asked to close AR-V7 & V5, wait 10 min and report valves closed
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 36 of 65 Evaluator Notes Plant Response: A tube leak will occur in the main condenser resulting in high conductivity alarms.
The crew will respond per 0AOP-26.0 and remove the water box from service.
Power should be reduced to 53% for water box removal.
Objectives: SRO - Direct Actions For High Reactor Coolant Or Condensate Conductivity Per 0AOP-26.0.
BOP - Respond To A High Reactor Coolant Or Condensate Conductivity Per 0AOP-26.0.
Success Path: The crew will respond per 0AOP-26.0 and lower power to 53% and remove the waterbox from service.
Event Termination: Go to next event once reactor power is reduced, and the waterbox is isolated or at the direction of the Chief Examiner.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 37 of 65 EVENT 5/5a: CONDENSER TUBE LEAK/LOWER POWER/ISOLATE WATERBOX Time Pos EXPECTED Operator Response Comments Enter and direct activities of 0AOP-26.0 SRO Direct power reduction to 53%.
May direct entry into 2AOP-4.0, Low Core Flow SRO if a manual runback is performed.
May refer to TRM 3.13 for RCS chemistry limits SRO TRM 3.13 - Conductivity <2.0 mhos/cm Chlorides <0.5 mhos/cm SRO Direct 2A-S Water box isolated Direct power be reduced to 53% to support SRO water box removal If condensate pump discharge conductivity SRO exceeds 10 mho (2-CO-CR-3075), determine 0AI-81 action level 3 applies.
May conduct a brief (see Enclosure 1 page 54 SRO for format))
ATC Monitors the plant Reduce reactor power: IAW 0ENP-24.5:
Reduce reactor recirc to ~47 Mlbms/hr May reduce flow by using the Manual Runback feature.
Inserts control rods until power is <53%.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 38 of 65 EVENT 5/5a: CONDENSER TUBE LEAK/LOWER POWER/ISOLATE WATERBOX Time Pos EXPECTED Operator Response Comments When power is reduced to 53%:
Isolate the 2A-S water box per 0AOP-BOP 26.0 or 2OP-29 With one water box out of service, the circulating water mode switch should be in Position B with no more than three CWIPs operating Acknowledge conductivity alarms.
UA-4, 3 Condenser A Hotwell Cndy High.
As the scenario progresses more conductivity alarms will annunciate until the waterbox is isolated Enter and execute 0AOP-26.0.
If directed, enter and announce 2AOP-4.0, Low Core Flow Monitor reactor water, condensate, feedwater, and hotwell conductivity Determine high conductivity is from A-S waterbox
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 46 of 65 EVENT 6: HPCI STEAM LEAK AND REACTOR SCRAM Simulator Operator Actions At the discretion of the Lead Evaluator, Initiate Trigger 9 to a HPCI Steam Leak Verify RHR Room Cooler B trips 4 minutes after HPCI Steam leak is activated, and RHR Room Cooler A trips 8 minutes after steam leak.
If directed to defeat RCIC Area Hi Area Temperature Isolations IAW 0EOP-01-SEP-10, wait 3 minutes and Initiate Trigger 16.
Simulator Operator Role Play After ARM alarm, call as RBAO and report as leaving RB you saw steam at -17ft near HPCI.
NOTE If Reactor Building has been evacuated and being dispatched to the Reactor Building, report HPs are not allowing anyone into the Reactor Building until surveys are complete.
As Unit 1 RO/SRO report multiple Unit 2 fire alarms after ARM alarm If directed as OSAO to close PIV-33, wait 4 minutes and report PIV closed. (Time Critical Task)
If directed as Unit 1 to perform AD-EP-ALL-0202, acknowledge request.
Acknowledge request for EQ Envelopes.
If contacted as Maintenance or I&C, acknowledge request.
If contacted by I&C to investigate RHR Room Cooler trip, acknowledge request.
After Trigger 16 initiated, call CRS and report RCIC Area Hi Area Temperature Isolations have been defeated IAW 0EOP-01-SEP-10
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 47 of 65 Evaluator Notes Plant Response: Rx Bldg temperatures and rad levels rise. Rx Bldg negative pressure is lost. 2A RHR Room Cooler starts at 120°F in the HPCI room and 2B RHR Room Cooler starts at 145°F in the HPCI room. The 2B RHR Room Cooler will stop 4 minutes after the steam leak is activated and 2A RHR Room Cooler will stop 4 minutes later (8 minutes after the leak).
Objectives: SRO - Respond IAW 0AOP-5.0 and 0EOP-03-SCCP Direct Reactor Scram when HPCI reaches Max. Safe condition Direct action of RSP ATC -Diagnose and report HPCI steam leak - attempt to isolate.
Perform Scram immediate actions Restore and maintain RPV water level as directed by CRS Stabilize RPV pressure as directed by CRS BOP- Respond to Reactor Building radiation alarms Maintain stable condition on Balance of Plant Perform actions as directed by CRS Success Path: Scram immediate actions are completed, RPV pressure and level are stabilized and controlled within band.
Event Termination: Go to next event at the discretion of the Chief Examiner
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 48 of 65 EVENT 6: HPCI STEAM LEAK AND REACTOR SCRAM Time Pos EXPECTED Operator Response Comments Enter and direct activities of 0AOP-05.0, SRO Radioactive Spills, High Radiation, And Airborne Activity Direct HPCI isolation Direct Rx Bldg evacuation Enter and direct the activities of EOP-03-SCCP Following SCRAM, direct cooldown not to exceed 100°F/hr Contact TSC/Engineering for EQ envelope evaluations Contact MM and/or I/C for HPCI failure Direct service water alignment to vital header and RHR Room Cooler start Direct a manual reactor scram prior to HPCI Critical Task #1 reaching its Max Safe Operating Value. (HPCI Max Safe = Max Norm of 165°F)
Direct actions in RSP and RVCP.
Provide pressure band to ROs Direct RPV level be maintained 166-206 inches Monitor Containment parameters Direct verifications of Actuations and Isolations.
May conduct a brief (see Enclosure 1 page 54 for format)
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 49 of 65 EVENT 6: HPCI STEAM LEAK AND REACTOR SCRAM Time Pos EXPECTED Operator Response Comments ATC Diagnose and report HPCI steam line break Acknowledge and report alarms:
A-02 5-7 STM LEAK DET AMBIENT TEMP HIGH A-01 4-1 HPCI TURB TRIP SOL ENER A-01 3-5 HPCI ISOL TRIP SIG A INITIATED A-01 4-5 HPCI ISOL TRIP SIG B INITIATED Attempt HPCI isolation and recognize and report failure to isolate Acknowledge and report A-01 5-4 HPCI VALVES MTR OVERLOAD Insert a manual reactor scram prior to HPCI Critical Task #1 reaching its Max Safe Operating Value.
Perform Scram Immediate Actions (Enclosure 2 see page 55)
Stabilize pressure as directed by the SRO, Then may establish a cooldown.
Restore and maintain RPV water level 166-206 Inches
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 50 of 65 EVENT 6: HPCI STEAM LEAK AND REACTOR SCRAM/ SBGT FAILURE Time Pos EXPECTED Operator Response Comments Acknowledge and report BOP UA-03 2-7 AREA RAD RX BLDG HIGH (This is a SCCP entry)
Enter and announce AOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity Direct AO to Isolate fire protection to the Reactor Building within 15 minutes of HELB Critical Task #2 (Time Critical) report to the control room.
Announce Rx Bldg evacuation Acknowledge alarms UA-05 1-9 FAN CLG UNIT CS PUMP RM A INL PRESS LO UA-05 2-9 FAN CLG UNIT CS PUMP RM B INL PRESS LO Align service water to vital header Perform Balance of Plant actions and as directed by CRS May perform verification of actuations and Isolations
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 51 of 65 EVENTS 7: RHR Room Cooler Trip, Emergency Depressurization, ADS Valve Failure Simulator Operator Actions When directed by the Lead Evaluator, place the simulator in FREEZE Verify RHR Room Cooler B trips 4 minutes after HPCI Steam leak is activated, and RHR Room Cooler A trips 8 minutes after steam leak After scram actions complete, Modify HPCI Steam leak (ES047F) to a value of 8 with a 5 minute ramp.
DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Simulator Operator Role Play NOTE If Reactor Building has been evacuated and being dispatched to the Reactor Building, report HPs are not allowing anyone into the Reactor Building until surveys are complete.
If contacted by I&C to investigate RHR Room Cooler trip, acknowledge request.
After ED is anticipated or if RX pressure reaches 500 psig, call as RE and report EQ envelope has been exceeded for SRHR.
Evaluator Notes Plant Response: After room coolers trip, 2 areas will reach Max Safe Temperature and ED will be required. When the crew anticipates ED, EQ envelopes will be reported as exceeded.
2 ADS Valves will fail to open.
Objectives: SRO - Evaluate plant conditions and direct Emergency Depressurization.
ATC - Perform actions for Emergency Depressurization.
BOP - Assist with Reactor Water level control as directed by SRO Success Path: Reactor is depressurized and water level is in normal band.
Scenario Termination: When actions are taken to depressurize the reactor to < 100psig, or at the discretion of the chief examiner, the scenario may be terminated.
Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluator/instructor.
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 52 of 65 EVENTS 7: RHR Room Cooler Trip, Emergency Depressurization, ADS Valve Failure Time Pos EXPECTED Operator Response Comments SRO Continue reactor cooldown per RVCP direction.
May direct Anticipation of Emergency Depressurization IAW SEP-15.
Direct Emergency Depressurization when more than one area exceeds the same Max CRITICAL TASK #3 Safe Operating Value or EQ Envelope for the same parameter.
Direct RO/BOP to open 7 ADS valves.
Direct additional SRVs to be opened until 7 are open When Torus temperature is greater than 95° F, enters PCCP and directs Torus Cooling.
(See Enclosure 4 page 60)
Directs Drywell cooling restored per SEP-10.
May conduct a brief (see Enclosure 1 page 54 for format)
2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 53 of 65 EVENTS 7: RHR Room Cooler Trip, Emergency Depressurization, ADS Valve Failure Time Pos EXPECTED Operator Response Comments ATC/ Recognize and report failure of RHR Room BOP Coolers.
May perform SEP-15 to anticipate ED.
While maintaining main steam line flow less ATC/ than 3x106 lbm/hr, Rapidly depressurize RPV BOP with Main Turbine Bypass valves irrespective of cooldown rate ATC/ Open seven ADS valves as directed by SRO. CRITICAL TASK #3 BOP Opens additional SRVs to obtain 7 SRVs open.
ATC/ Maintain reactor water level as directed by SRO.
BOP (Should use condensate system via SULCV)
(Enclosure 3 see page 57)
Place available loops in Torus Cooling IAW hard ATC/
card.
BOP (Enclosure 4 page 60)
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2020 NRC SCENARIO 3, ES-D-2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 64 of 65 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment Category Standard Scenario Content Total Malfunctions 5-8 7 Malfunctions after EOP 1-2 2 Entry Abnormal Events 2-4 3 Major Transients 1-2 2 EOPs Used 1-2 2 EOP Contingency 1-2 1 Crew Critical Tasks >2 3 Tech Specs 2 2 Instrument / Component 2 - ATC Failures before Major 4 2 - BOP Instrument / Component 2 2 Failures after Major Normal Operations 1 1 Reactivity manipulation 1 1
LOI SIMULATOR EVALUATION GUIDE ATTACHMENT 2 - Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek J. Pierce B. Craig`
Manager: Manager:
Mode: 1 Rx Power: 100%
Plant Risk:
Green Current EOOS Risk Assessment is:
SFP Time to 134.6 Hrs. Days Online: 200 days 200 Deg F:
APRM 2 Failed Downscale and bypassed.
Turnover:
1A NSW Under Clearance.
Protected Equipment: 2A/2B NSW.
Perform 0PT-40.2.11, Main Generator Voltage Regulator Manual and Comments: Automatic Operational Check, after turnover. Required log entries will be made by another operator.
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM -A - 2020 NRC EXAM (RO / ISRO / USRO)
LESSON TITLE: Reset Recirc Pump Runback - Both Recirc Pumps Trip LESSON NUMBER: LOT-SIM-JP-002-A09 REVISION NO: 02 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Reset Recirc Pump Runback - Both Recirc Pumps Trip REVISION
SUMMARY
Rev. Revision Summary Minor Rev. Date No. Signature 02 Added designation as 2020 NRC exam JPM. Added NA NA performance standard.
01 Minor rev- no technical change. Added Alternate NA NA path begins here.
0 New JPM written for 2016 Initial NRC exam. NA NA LOT-SIM-JP-002-A09 Page 2 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip RELATED TASKS:
202201B401 Recover from a Reactor Recirculation Pump Runback Per OP-02 K/A REFERENCE AND IMPORTANCE RATING:
202002 A2.01 3.4/3.4 Ability to predict the impacts of recirculation pump trip and based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations.
REFERENCES:
2OP-02, Section 6.3.3, Recovery From Reactor Recirculation Pump Runback 2OP-02, Section 6.1.3, Raising Speed Using Individual Recirculation Pump Control 2AOP-04.0, Low Core Flow PERFORMANCE STANDARD:
Candidate will reset the recirculation pump runback and raise flow of Reactor Recirculation Pump 2B to match flow of Recirculation Pump 2A. When 4160V Bus 2B trips will take manual reactor scram actions due to a loss of both recirculation pumps with the mode switch in run.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
1 - Reactivity Control (Recirculation Flow Control System)
LOT-SIM-JP-002-A09 Page 3 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip SETUP INSTRUCTIONS SIMULATOR SETUP Initial Conditions
- 1. Recommended Initial Conditions IC-10
- 2. Required Plant Conditions Recirculation Pump A at approximately 70% flow, Recirculation Pump B at Limiter #1.
OPRM Trip Enabled annunciator in ALARM.
Malfunctions:
Insert the following malfunctions:
Current Target Malf ID Mult ID Description Rmptime Actime Deactime Trig Value Value VFD B RUNBACK RC024F VFD B False True
- 1ACTUATES EE026F Loss of 4160V Bus B False True 1 Set Trigger 1, Q2722RSM, VFD B Raise Medium pushbutton to TRUE.
Special Instructions Initiate VFD B runback and allow plant conditions to stabilize. Once runback is complete, delete malfunction RC024F. If necessary, insert control rods to get below the MELLL Line on the Power-Flow map. Verify VFD B RUNBACK #1 ACTUATES is clear. Reset Speed Hold, if amber light is illuminated.
LOT-SIM-JP-002-A09 Page 4 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip SAFETY CONSIDERATIONS:
- 1. None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM will be performed in the simulator on Unit Two.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. Reactor Recirculation Pump operation was previously in accordance with 2OP-02, Section 6.1.2.
- 2. Recirculation Pump 2B has run back to limiter number 1, and the cause has been corrected.
- 3. A reactivity management briefing is complete, and your reactivity management team is available in the Control Room.
- 4. Another operator is monitoring Nuclear Instrumentation.
INITIATING CUE:
You are directed by the Unit CRS to reset the Recirculation Pump runback signal and raise flow of Reactor Recirculation Pump 2B to match flow of Recirculation Pump 2A.
LOT-SIM-JP-002-A09 Page 5 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Obtain current revision of 2OP-02 Sections 6.3.3 may also get Section 6.1.3.
Provide current revision of 2OP-02 Section 6.3.3, and if asked Section 6.1.3.
SAT/UNSAT TIME START:
Step 2 - Verify the conditions that caused the runback have cleared, or Recirc Pump speed has been lowered below the runback setpoint.
Verifies Recirc Pump speed below the runback setpoint, and condition is clear as part of Task Conditions.
SAT/UNSAT Step 3 - ENSURE RECIRC PUMP B SPEED DEMAND signal is approximately the same as the following:
- RECIRC PUMP B CALCULATED SPEED
- RECIRC PUMP B ACTUAL SPEED Ensures Calculated Speed and Actual Speed approximately the same.
SAT/UNSAT Step 4 - RESET the Recirc Pump runback for Reactor Recirculation Pump B as follows:
- a. DEPRESS Recirc VFD B RUNBACK RESET push button.
Runback Reset push button is depressed.
- CRITICAL STEP** SAT/UNSAT
- b. CONFIRM yellow AUTOMATIC RUNBACK light extinguished.
Yellow Automatic Runback light is confirmed extinguished SAT/UNSAT
- c. CONFIRM annunciator RECIRC FLOW B LIMIT (A-07 2-4) is clear.
Annunciator confirmed clear.
SAT/UNSAT LOT-SIM-JP-002-A09 Page 6 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip PROMPT: If asked which VFD RAISE pushbutton to use, or if the VFD RAISE SLOW pushbutton is depressed, direct Examinee as the CRS to raise speed of the Recirculation Pump using the VFD RAISE MEDIUM pushbutton.
Step 5 - ADJUST flow as directed by the Unit CRS.
VFD RAISE MEDIUM push button is depressed in accordance with 2OP-02, Section 6.1.3, pages 39-42.
- CRITICAL STEP ** SAT/UNSAT NOTE: 4160 V Bus B will trip when the VFD RAISE MEDIUM push button is depressed.
- ALTERNATE PATH BEGINS HERE**********************************
Step 6 - Determines that no Recirc Pumps are running.
Diagnosis failure of Bus B which causes both Recirc Pumps to lose power.
SAT/UNSAT NOTE: The examinee may enter and announce entry into 2AOP-04.0, Low Core Flow.
Step 7 - Inserts a manual reactor scram IAW 2AOP-04.0, Immediate Operator Action, depresses both RPS Channel Manual Pushbuttons.
Performs the following scram immediate actions:
- 1. Ensure SCRAM valves OPEN by manual SCRAM or ARI initiation.
- 2. WHEN steam flow less than 3.0 Mlb/hr, THEN place reactor mode switch in SHUTDOWN.
- 3. IF reactor power below 2% (APRM downscale trip),
THEN trip main turbine.
- 4. Ensure master RPV level controller setpoint at +170 inches.
- 5. IF two reactor feed pumps running and RPV level is greater than 160 inches and rising, THEN trip one reactor feed pump.
- CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-002-A09 Page 7 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip Step 8 - Informs CRS that all rods are in, RPV water level value and RPV pressure value.
Acknowledge scram report as the CRS.
SAT/UNSAT TERMINATING CUE: Once a manual reactor scram is inserted and scram immediate actions are complete, the JPM can be terminated.
TIME COMPLETED:
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Not Critical Given as initial conditions 3 Not Critical Observation of indications 4a Critical Action required to reset the runback 4b Not Critical Observation of indications 4c Not Critical Observation of indications 5 Critical Action required to meet Initiating Cue 6 Not Critical Observation of indications 7 Not Critical Observation of indications 8 Critical Immediate Operator action from 2AOP-04.0 9 Not Critical Communication LOT-SIM-JP-002-A09 Page 8 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
NOTE: Comments required for any step evaluated as UNSAT LOT-SIM-JP-002-A09 Page 9 of 11 Rev. 02
Reset Recirc Pump Runback - Both Recirc Pumps Trip Validation Time: 12 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-002-A09 Page 10 of 11 Rev. 02
TASK CONDITIONS:
- 1. Reactor Recirculation Pump operation was previously in accordance with 2OP-02, Section 6.1.2.
- 2. Recirculation Pump 2B has run back to limiter number 1, and the cause has been corrected.
- 3. A reactivity management briefing is complete, and your reactivity management team is available in the Control Room.
- 4. Another operator is monitoring Nuclear Instrumentation.
INITIATING CUE:
You are directed by the Unit CRS to reset the Recirculation Pump runback signal and raise flow of Reactor Recirculation Pump 2B to match flow of Recirculation Pump 2A.
Page 11 of 11
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM -B - 2020 NRC EXAM (RO / ISRO)
LESSON TITLE: Feedwater Level Control Following a Reactor Scram with a SULCV failure LESSON NUMBER: LOT-SIM-JP-032-08 REVISION NO: 06 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 09/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Feedwater Level Control Following a Reactor Scram with a SULCV failure REVISION
SUMMARY
Rev. Revision Summary Minor Rev Date No. Signature 06 Added Performance Standard, updated steps NA NA to align with new hard card (0OI-37.17)
Changed title to match Hard Card title 5 New JPM format. NA NA Added Critical/Non Critical step explanation.
Procedure revision changes.
LOT-SIM-JP-032-08 Page 2 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure RELATED TASKS:
259202B101 Start the First Reactor Feed Pump per OP-32 K/A REFERENCE AND IMPORTANCE RATING:
259001 A4.01 3.6/3.5 Ability to manually operate and/or monitor in the control room: System flow.
REFERENCES:
0OI-37.17 rev. 04 section 5.10 PERFORMANCE STANDARD:
Candidate will take the actions to control reactor water level per EOP hard card ,
Feedwater Level Control Following a Reactor Scram (0OI-37.17). Candidate will detect failure of startup level control valve and use alternate method to provide feedwater flowpath.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123):
2 - Inventory Control LOT-SIM-JP-032-08 Page 3 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure SETUP INSTRUCTIONS:
Initial Conditions:
RPV water level 170, RFP high-level trips sealed in Triggers: None Malfunctions:
CF035F, S/U Lvl Cont Vlv Fails Closed Overrides: None Remote Functions: None Special Instructions:
- 1. Trip the Main Turbine to insert a reactor scram and perform immediate actions with exception of tripping one RFP; allow RFPs to trip on high level.
- 5. After each reset, Level Set will have to be restored to 187 inches LOT-SIM-JP-032-08 Page 4 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on Unit 2.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury
- 5. Hard card S/1205 will be provided to the examinee.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. A reactor scram has occurred.
- 2. RPV water level has dropped below 170 inches and Feedwater is required to restore RPV water level to the normal band.
INITIATING CUE:
You are directed by the Unit CRS to Perform Feedwater Level Control Following a Reactor Scram and restore RPV water level to 166-206 inches with a target of 170 inches.
Inform the Unit CRS when RPV water level has been restored above 170 inches.
LOT-SIM-JP-032-08 Page 5 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Perform take a minute at job site prior to beginning task.
Examinee should cover the following questions, as deemed necessary.
What are the hazards in the area? What PPE is required? Tools/PPE inspected prior to use? Energy sources secured/isolated? Is Clearance/Tag Out sufficient? What's the worst that can happen? Any ALARA concerns?
Will I affect plant status? HU Tools needed?
SAT / UNSAT TIME START: ___________
Step 2 - PLACE RFP A(B) RECIRC VLV, control switch to open RFP A(B) Recirc Valve, FW-FV-V46(47), control switch is placed to open and the valve is verified to indicate full open. (red light on, green light off)
RFPT A(B) SP CTL, indicates M with output at 0%.
SAT / UNSAT Step 4 - ENSURE RFP A(B) Discharge Valve, FW-V3(V4), open.
RFP A(B) Discharge Valve FW-V3(V4) verified to already indicate full open, (red light on, green light off).
SAT / UNSAT Step 5 - ENSURE A(B) MAN/DFCS Control Switch in MAN.
MAN/DFCS Control Switch is placed in MAN for A(B) RFP.
- CRITICAL STEP ** SAT/UNSAT*
LOT-SIM-JP-032-08 Page 6 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure NOTE: The next step is only critical if High Level Trip/Reset Pushbuttons have to be depressed.
Step 6 - ENSURE Reactor Water Level is less than +206 inches AND RFPT A&B High Level Trip/Reset Pushbuttons are reset.
Observes RPV water level is <206 inches using indications on the P603 Panel and depresses at least 2 of 3 reset push buttons and amber high level trip lamps on P603 are extinguished.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - DEPRESS RFPT A(B) RESET pushbutton.
RFPT A(B) reset pushbutton on XU-2 depressed and RFP Tripped annunciator cleared.
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - ENSURE RFP A(B) LP and HP Stop Valves are open.
Verifies RFPT A(B) LP and HP Stop Valves automatically opened on XU-2.
SAT / UNSAT Step 9 - ROLL RFPT A(B) to 1000 rpm by depressing RFP A(B) RFPT Start RFP A(B) START Pushbutton depressed and RFP speed verified to raise to
~1000 rpm.
Using the raise switch, RFP A(B) speed raised to ~2550 rpm.
- CRITICAL STEP ** SAT / UNSAT LOT-SIM-JP-032-08 Page 7 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure Step 12 - ENSURE MAN/DFCS control switch in DFCS.
MAN/DFCS verified in DFCS SAT / UNSAT Step 13 - RAISE RFPT A(B) SP CTL speed until discharge pressure is greater than or equal to 100 psig above reactor pressure Raises RFP A(B) discharge pressure to 100 psig above reactor pressure.
- CRITICAL STEP ** SAT / UNSAT
- ALTERNATE PATH BEGINS HERE*****
NOTE: ALTERNATE PATH BEGINS HERE The SULCV will not open and FW-V120 must be opened to raise water level.
Step 14 - ADJUST SULCV, FW-LIC-3269, to establish desired injection.
SULCV is adjusted in manual to open the valve. SULCV does not open.
SAT / UNSAT NOTE: 0AOP-23.0, Condensate/Feedwater System Failure contains the procedural guidance for establishing feedwater flow if the SULCV fails.
PROMPT: If examinee informs the CRS that the SULCV is failed, direct the examinee to inject feedwater by any available method.
Step 15 - Diagnosis of SULCV failure and opens the FW-V120, (or FW-V118 and FW-V6 OR FW-V119 and FW-V8), to provide a flowpath to the reactor in order to raise reactor water level.
RPV water level is restored above 170 inches by opening one of the following flowpaths:
Throttle the FW-V120 OR Open the FW-V6 and throttle the FW-V118 OR Open the FW-V8 and throttle the FW-V119.
- CRITICAL STEP ** SAT / UNSAT LOT-SIM-JP-032-08 Page 8 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure Step 16 - Inform Unit CRS that RPV water level is above +170.
Unit CRS informed.
SAT / UNSAT TERMINATING CUE: When Reactor water level is restored to above 170 inches and feedwater is being injected into the Reactor, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Critical Required to complete JPM 3 Not Critical Not required to complete task 4 Not Critical Not required to complete task 5 Critical Required to complete JPM 6 Critical Required to complete task 7 Critical Required to complete JPM.
8 Not Critical Not required to complete task 9 Critical Required to complete JPM.
10 Critical Required to complete JPM.
11 Critical Required to complete JPM.
12 Not Critical Not required to complete JPM 13 Critical Required to complete JPM 14 Not Critical Not required to complete JPM 15 Critical Required to complete JPM 16 Not Critical Inform step LOT-SIM-JP-032-08 Page 9 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer SAT/ UNSAT/ NE checking)
D. Proper Equipment Use (observe starting limitations, throttle SAT/ UNSAT/ NE valve closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety SAT/ UNSAT/ NE equipment, etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key SAT/ UNSAT/ NE control, etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-SIM-JP-032-08 Page 10 of 12 Rev 06
Feedwater Level Control Following a Reactor Scram with a SULCV failure Validation Time: 15 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-032-08 Page 11 of 12 Rev 06
TASK CONDITIONS:
- 1. A reactor scram has occurred.
- 2. RPV water level has dropped below 170 inches and Feedwater is required to restore RPV water level to the normal band.
INITIATING CUE:
You are directed by the Unit CRS to Perform Feedwater Level Control Following a Reactor Scram and restore RPV water level to 166-206 inches with a target of 170 inches.
Inform the Unit CRS when RPV water level has been restored above 170 inches.
Page 12 of 12
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM C - 2020 NRC EXAM (RO / ISRO)
LESSON TITLE: TURBINE OVERSPEED TRIP TEST LESSON NUMBER: LOT-SIM-JP-26.0-02 REVISION NO: 01 S. Cotton PREPARER / DATE Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR / DATE Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
TURBINE OVERSPEED TRIP TEST REVISION Rev. No. Revision Summary Minor Rev. Date Signature 1 Added performance standard. Updated JPM to NA NA reflect TCS modification and new 2PT-40.2.6.
Removed Alternate path LOT-SIM-JP-26.0-02 Page 2 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST RELATED TASKS:
245012B101 Shutdown The Main Turbine Per OP-26 K/A REFERENCE AND IMPORTANCE RATING:
241000 REACTOR/TURBINE PRESSURE REGULATING SYSTEM K1.22 Knowledge of the physical connection and/or cause-effect relationships between REACTOR/TURBINE PRESSURE REGULATING SYSTEM and the following:
Turbine Trip RO 3.4 / SRO
3.5 REFERENCES
2PT-40.2.6 PERFORMANCE STANDARD:
Candidate will perform steps of 2PT-40.2.6, Turbine Overspeed Trip Test . When the main turbine is tripped the candidate will determine that PCB 29B ( Generator 2 to Bus 2B 30KV PCB) failed to automatically open. Candidate will take action to open PCB 29B.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
3 - Reactor Pressure Control SETUP INSTRUCTIONS Main Turbine is on line. Loaded to 100-110Mwe.
EE037F, PCB 29 Trip Coil #1 Fails to Trip, for 29B to TRUE EE038F, PCB 29 Trip Coil #2 Fails to Trip, for 29B to TRUE Create Trigger 1 for PCB 29B in trip Enter the following expert command: trc:1,mfd:EE038F,29B LOT-SIM-JP-26.0-02 Page 3 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST SAFETY CONSIDERATIONS:
- 1. None.
EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM is to be performed on the Unit 2 Simulator. If the reverse power relay is picked up, then the Main Generator Severe Internal Damage instructor alarm will actuate.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. The Turbine is on line operating at ~ 100-110 MWe
- 2. 2PT-40.2.6, Turbine Overspeed Trip Test is currently in progress
- 3. All prerequisites have been verified by another operator
- 4. Section 7.1, Steps 1 through 8 have already been accomplished by another operator
- 5. The Load Dispatcher has been notified of impending grid separation INITIATING CUE:
You are directed by the Unit CRS to perform 2PT-40.2.6, Turbine Overspeed Trip Test, starting at Section 7.1, Step 9 LOT-SIM-JP-26.0-02 Page 4 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Obtain a current revision pre-marked version of 2PT-40.2.6, Turbine Overspeed Trip Test.
Current Revision of 2PT-40.2.6 obtained and verified if applicable.
SAT/UNSAT TIME START: ___________
NOTE:
MVD-DV3 (Mn Stm Lead After CV-3 Drn) operates with the limit switch position of the CV-1/CV-2 drain valves and the position can be confirmed with the indicating light on Panel XU-3.
CAUTION:
Operation at less than 33% turbine load and less than 25" Hg vacuum (greater than 5" Hga backpressure) can cause damage to the last stage buckets and should be avoided.
Step 2 - Open the following drain valves located on Panel XU-3:
VALVE SAT UNSAT MS-V46/47/48/49 (Mn Stm Ln Before SV Drns)
MVD-CV (Main SV & CV Above Seat Drn)
MVD-CV2 (Mn Stm Lead After CV-1 Drn)
MVD-CV4 (Mn Stm Lead After CV-2 Drn)
Places Valve switches in the open position. Green light extinguishes and red light illuminates. (MVD-CV, CV2, and CV4 are throttle valves) (When MVD-CV2 and CV4 are opened the MVD-DV3 will auto open, green light extinguishes and red light illuminates SAT/UNSAT Step 3 - Start the Motor Suction Pump.
Starts Motor Suction Pump by depressing Motor Suction Pump start pushbutton.
SAT/UNSAT LOT-SIM-JP-26.0-02 Page 5 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST Step 4 - Start the Turning Gear Oil Pump.
Starts Turning Gear Oil Pump by depressing Turning Gear Oil Pump start pushbutton.
SAT/UNSAT Step 5 - Test operation of OG-PS-110 and OG-PS-111 (Low Condenser Vacuum Switches) pressure set control and bypass valves, by performing the following:
a) Depress Bypass Valve Opening Jack Increase push button to throttle open a bypass valve to 12% to 18%.
Bypass Valve Opening Jack Increase push button depressed to throttle open a bypass valve to 12% to 18%.
SAT/UNSAT Step 6 - Test operation of OG-PS-110 and OG-PS-111 (Low Condenser Vacuum Switches) pressure set control and bypass valves, by performing the following:
b) Depress Bypass Valve Opening Jack Decrease push button to fully close the bypass valve.
Bypass Valve Opening Jack Decrease push button depressed to fully close the bypass valve.
SAT/UNSAT Step 7 - Notify Load Dispatcher of impending grid separation.
Provided as an initial condition.
SAT/UNSAT LOT-SIM-JP-26.0-02 Page 6 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST Step 8 - Pull 2-EHC-PB-RTGB-TRIP-1(Main Turbine RTGB Trip Switch- #1).
Main Turbine RTGB Trip Switch-#1 pulled.
- CRITICAL STEP** SAT/UNSAT Step 9- Pull 2-EHC-PB-RTGB-TRIP-2 (Main Turbine RTGB Trip Switch- #2).
Main Turbine RTGB Trip Switch-#2 pulled.
- CRITICAL STEP** SAT/UNSAT Step 10 - Confirm on the TCS HSI Valve Status Display 113 the following:
SAT UNSAT All four main stop valves go full CLOSED All four control valves go full CLOSED All four intercept valves go CLOSED All four intermediate stop valves go CLOSED Bypass valves throttle open to maintain reactor pressure constant at 1050 psig All components operate as described above SAT/UNSAT EVALUATOR NOTE: 230 KV PCB 29B fails to open in the following step.
EVALUATOR NOTE: If applicant reports unexpected PCB indications, examiner should ask their recommended action, and concur with that action.
LOT-SIM-JP-26.0-02 Page 7 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST Step 11 - WHEN generator MWe lowers to zero, THEN ensure both generator output breakers, Generator 2 to Bus 2A 230 KV PCB 29A and Generator 2 to Bus 2B 230 KV PCB 29B, are OPEN.
PCB 29A verified to open, red light off, green light on, UA-13 (1-7) in alarm PCB 29B is opened by taking control switch to the trip position and observing green light on, red light off, UA-13 (1-8) in alarm.
- CRITICAL STEP** SAT/UNSAT TERMINATING CUE: When 230 KV PCB 29A and 29B are open this JPM is complete.
Another operator will continue the task from here.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Not Critical Not necessary for PT completion 3 Not Critical Not necessary for PT completion 4 Not Critical Not necessary for PT completion 5 Not Critical Not necessary for PT completion 6 Not Critical Not necessary for PT completion 7 Not Critical Communication 8 Critical Necessary for PT completion 9 Critical Necessary for PT completion 10 Not Critical Not necessary for PT completion 11 Critical Necessary for failed auto action LOT-SIM-JP-26.0-02 Page 8 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-SIM-JP-26.0-02 Page 9 of 11 Rev.01
TURBINE OVERSPEED TRIP TEST Validation Time: 12 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-26.0-02 Page 10 of 11 Rev.01
TASK CONDITIONS:
- 1. The Turbine is on line operating at ~ 100 MWe
- 2. 2PT-40.2.6, Turbine Overspeed Trip Test is currently in progress
- 3. All prerequisites have been verified by another operator
- 4. Section 7.1, Steps 1 through 8 have already been accomplished by another operator
- 5. The Load Dispatcher has been notified of impending grid separation INITIATING CUE:
You are directed by the Unit CRS to perform 2PT-40.2.6, Turbine Overspeed Trip Test, starting at Section 7.1, Step 9 Page 11 of 11
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM D - 2020 NRC EXAM (RO / ISRO / USRO)
LESSON TITLE: OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD LESSON NUMBER: LOT-SIM-JP-024-A01 REVISION NO: 06 S. Cotton PREPARER / DATE Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD REVISION
SUMMARY
Rev. Revision Summary Minor Rev. Date No. Signature 06 Added performance standard. Updated to NA NA new reference, 0OI-37.17, EOP Hard Cards.
Corrected typographical errors.
5 New Format. Changed steps to reflect NA NA starting CAC-AT-4410 LOT-SIM-JP-024-A01 Page 2 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD RELATED TASKS:
223201B101, Startup the H2/O2 Analyzer (CAC-AT-4409/4410) IAW OP-24 K/A REFERENCE AND IMPORTANCE RATING:
223001 A4.04 3.5/3.6 223001 A4.05 3.6/3.6 Ability to manually operate and/or monitor containment hydrogen/oxygen concentrations.
REFERENCES:
0OI-37.17 EOP Hard Cards, Section 5.24 CAC-AT-4410 Startup PERFORMANCE STANDARD:
Candidate will locate and start up the CAC-AT-4410 using the EOP Hard Card.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
5 - Containment Integrity SETUP INSTRUCTIONS Recommended Initial Conditions IC-11 Rx Pwr 100%
BOC Required Plant Conditions:
DW >1.7 psig (PCIS Group 6 Isolation Initiated)
Special Instructions:
None.
LOT-SIM-JP-024-A01 Page 3 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD SAFETY CONSIDERATIONS:
- 1. None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM will be performed in the simulator on Unit Two.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. 0EOP-02-PCCP has been entered due to high drywell pressure.
- 2. Hydrogen/Oxygen monitor CAC-AT-4410 is isolated and was not previously in service.
INITIATING CUE:
You are directed by the Unit CRS to place the Primary Containment Hydrogen/Oxygen monitor CAC-AT-4410 in service using the hard card and inform him when step 6c of the hard card has been completed.
LOT-SIM-JP-024-A01 Page 4 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
TIME START: ___________
Step 1 - Obtain Hard Card, CAC-AT-4410 Startup - 0OI-37.17 EOP Hard Cards sect. 5.24 CAC-AT-4410 Startup Hard Card obtained.
SAT/UNSAT Step 2 - Ensure recorder function of CAC-AR-4410 (Cont Atm H2 & O2 Percent Rec) is ON.
CAC-AR-4410 (Cont Atm H2 & O2 Percent Rec) recorder function verified ON.
SAT/UNSAT Step 3 - IF an isolation signal is present, THEN place CAC-CS-3452 (CAM Div II Isol Ovrd) to ON.
CAC-CS-3452 (CAM Div II Isol Ovrd) placed in ON.
- CRITICAL STEP ** SAT/UNSAT Step 4 - Ensure the following valves are OPEN: CAC-SV-1218A at X206A-A, CAC-SV-1227A at X73-A, CAC-SV-1227B at X73-B, CAC-SV-1227E at X73-E, CAC-SV-1231B at X244-B, and CAC-SV-4541 RIP valves opened by depressing associated pushbutton twice and verifying the red light is ON; CAC-SV-4541 opened by taking its control switch to CLOSE and back to OPEN.
Valve SAT UNSAT CAC-SV-1218A at X206A-A CAC-SV-1227A at X73-A CAC-SV-1227B at X73-B CAC-SV-1227E at X73-E CAC-SV-1231B at X244-B CAC-SV-4541
- CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-024-A01 Page 5 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD Step 5 - IF available, THEN place Sample Select switch to Point 4.
Control switch CAC-CS-4410 is placed to position 4.
- CRITICAL STEP ** SAT/UNSAT Step 6 - At Sample Control Module CAC AT 4410, depress Start Sample push button and ensure the following: Sample inlet valve OPENS, Red Start Sample light comes ON, Red MS Drn Active light comes ON, and WHEN 20 to 40 seconds have elapsed, THEN red MS Drn Active light goes OFF and green MS Drain Standby light comes ON START SAMPLE push button depressed.
- CRITICAL STEP ** SAT/UNSAT Step 7 - After sample pushbutton depressed ensure the following: Sample inlet valve OPENS, Red Start Sample light comes ON, Red MS Drn Active light comes ON, and WHEN 20 to 40 seconds have elapsed, THEN red MS Drn Active light goes OFF and green MS Drain Standby light comes ON The following sequence is observed:
Sequence SAT UNSAT Sample inlet valve OPENS Red Start Sample light comes ON Red MS Drn Active light comes ON WHEN 20 to 40 seconds have elapsed, THEN red MS Drn Active light goes OFF and green MS Drain Standby light comes ON SAT/UNSAT Step 8 - IF the CAC-AT-4410 was NOT previously in service, THEN perform the following at Panel XU-79: Ensure system power Standby/Off switch in STANDBY and confirm the amber Standby light comes ON Standby/Off switch verified in Standby.
SAT/UNSAT LOT-SIM-JP-024-A01 Page 6 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD Step 9 - IF the CAC-AT-4410 was NOT previously in service, THEN perform the following at Panel XU-79: Ensure system power On/Off switch in ON Power On/Off switch placed in ON and green on light illuminates.
- CRITICAL STEP ** SAT/UNSAT PROMPT: Inform the examinee that another operator will complete the procedure after the power ON/Off switch is placed in ON.
The last two steps of the hard card (6d, and e) are after a 30 minute elapsed time.
Step 10 - Informs the CRS that Primary Containment Hydrogen/Oxygen monitor CAC-AT-4410 has been started using the hard card, and step 6c is complete CRS informed CAC-AT-4410 start up complete through step 6c of the Hard Card.
SAT/UNSAT TERMINATING CUE: CAC-AT-4410 system power On/Off switch has been placed in ON.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Not Critical Verification step 3 Critical Necessary to unisolate the CAC-AT-4410.
4 Critical Necessary for flowpath 5 Critical Necessary for flowpath 6 Critical Necessary for operation 7 Not Critical Verification step 8 Not Critical Verification step 9 Critical Necessary for operation 10 Not Critical Communication LOT-SIM-JP-024-A01 Page 7 of 9 Rev.06
OPERATE THE HYDROGEN AND OXYGEN MONITOR USING THE HARD CARD Validation Time: 10 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-024-A01 Page 8 of 9 Rev.06
TASK CONDITIONS:
- 1. 0EOP-02-PCCP has been entered due to high drywell pressure.
- 2. Hydrogen/Oxygen monitor CAC-AT-4410 is isolated and was not previously in service.
INITIATING CUE:
You are directed by the Unit CRS to place the Primary Containment Hydrogen/Oxygen monitor CAC-AT-4410 in service using the hard card and inform him when step 6c of the hard card has been completed.
Page 9 of 9
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM E - 2020 NRC EXAM (RO / ISRO / USRO)
LESSON TITLE: HPCI Pressure Control LESSON NUMBER: LOT-SIM-JP-019-15 REVISION NO: 02 Steve Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL/ DATE
HPCI Pressure Control Revision Summary:
No. Revision Summary Minor Revision Date Signature 02 Updated to current format. N/A N/A Updated to current revision of OI-37.17.
Added Performance Standard.
01 Updated to reflect updates to the HPCI hard N/A N/A card.
LOT-SIM-JP-019-15 Page 2 of 13 Rev. 02
HPCI Pressure Control RELATED TASKS:
206200B401 Place HPCI in Reactor Pressure Control From the Standby Lineup Per OP-19 K/A REFERENCE AND IMPORTANCE RATING:
206000 A4.06 4.3/4.3 Ability to manually operate and/or monitor in the control Room: Reactor Pressure
REFERENCES:
Hard Card S/1019, HPCI Pressure Control In EOPs PERFORMANCE STANDARD:
The examinee will place HPCI in service in pressure control mode of operation in accordance with the hard card to control reactor pressure 800-1000 psig.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev 2.):
4 - Heat Removal From Reactor Core LOT-SIM-JP-019-15 Page 3 of 13 Rev. 02
HPCI Pressure Control SIMULATOR SETUP:
Initial Conditions
- IC-13
- Rx Power - 100%
Malfunctions None Overrides None Special Instructions
- 1. Insert manual scram and perform immediate reactor operations
- 2. Close MSIVs
- 3. Control reactor pressure 800-1000 psig with SRVs until HPCI is in operation and controlling reactor pressure.
- 4. Start SBGT.
- 5. Control reactor water level <206 inches.
LOT-SIM-JP-019-15 Page 4 of 13 Rev. 02
HPCI Pressure Control SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL NOT be provided to the trainee.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 3. Copy of Task Conditions and Initiating Cue should be provided to the examinee.
Read the following to the JPM performer TASK CONDITIONS:
- 2. RPV water level is being maintained above LL2 by another operator.
- 4. SBGT is running.
INITIATING CUE:
You are directed by the Unit CRS to start HPCI for pressure control per the Hard Card to maintain RPV pressure between 800 - 1000 psig and inform the Unit CRS when the Hard Card actions are complete.
LOT-SIM-JP-019-15 Page 5 of 13 Rev. 02
HPCI Pressure Control PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
TIME START:
Step 1 - Obtain Hard Card - HPCI Pressure control.
Hard Card for HPCI Pressure Control obtained.
SAT/UNSAT*
Step 2 - If HPCI has on automatic initiation signal, Then depress E41-S17 (Initiation Signal/Reset) pushbutton.
Verifies HPCI auto initiation is reset as indicated by white initiation light off SAT/UNSAT*
Step 3 - If HPCI tripped, Then depress E41-S25 (High Water Level Signal Reset) pushbutton.
Verifies HPCI high water level light off.
SAT/UNSAT*
Step 4 - Ensure Auxiliary Oil Pump is not running.
Verifies Auxiliary Oil Pump not running (green light on / red light off).
SAT/UNSAT*
Step 5 - Place HPCI flow control, E41-FIC-R600, in M (manual), and adjust output demand to approximately midscale E41-FIC-R600 M (Manual) pushbutton is depressed and output is adjusted to ~ midscale SAT/UNSAT*
LOT-SIM-JP-019-15 Page 6 of 13 Rev. 02
HPCI Pressure Control Step 6 - Ensure E41-V8 (Turbine Stop Valve) and E41-V9 (Turbine control Valve) are closed.
E41-V8 and E41-V9 are verified closed by observing green light illuminated.
SAT/UNSAT*
Step 7 - Open E41-F011 (Redundant Isol To CST Vlv.)
Rotates control switch for E41-F011 in the clockwise direction (open position) observes red light illuminates / green light extinguishes.
- CRITICAL STEP** SAT/UNSAT*
Step 8 - Open E41-F059 (Cooling Water Supply Vlv).
Rotates control switch for E41-F059 in the clockwise direction (open position) observes red light illuminates / green light extinguishes.
- CRITICAL STEP** SAT/UNSAT*
Step 9 - Start Vacuum Pump and leave in START.
Rotates control switch for the Vacuum Pump in the clockwise direction (start position) observes red light illuminated.
SAT/UNSAT*
Step 10 - Open E41-F001 (Turbine Steam Supply Vlv).
Rotates control switch for E41-F001 in the clockwise direction (open position) observes red light illuminates / green light extinguishes.
- CRITICAL STEP** SAT/UNSAT*
Step 11 - Start Auxiliary Oil Pump and Leave in START.
Rotates control switch for the Auxiliary Oil Pump in the clockwise direction (start position) observes red light illuminated.
- CRITICAL STEP** SAT/UNSAT*
LOT-SIM-JP-019-15 Page 7 of 13 Rev. 02
HPCI Pressure Control Step 12 - Ensure E41-V8 (Turbine Stop Valve) and E41-V9 (Turbine control Valve) are OPEN.
E41-V8 and E41-V9 are verified open by observing red light illuminated.
SAT/UNSAT*
Step 13 - When speed stops increasing, Then adjust speed to approximately 2100 RPM.
Observes HPCI speed stabilizes Then adjusts turbine speed to approximately 2100 RPM SAT/UNSAT*
Step 14 - Throttle open E41-F008 (Bypass to CST Vlv) until flow is between 1400 gpm and 1800 gpm.
Rotates control switch for E41-F008 in the clockwise direction (open position) until flow is between is observed to be 1400 to 1800 gpm.
- CRITICAL STEP** SAT/UNSAT*
Step 15 - WHEN flow is greater than 1400 gpm, THEN ensure E41-F012 (Min Flow Bypass To Torus Vlv) closed.
Observes red light extinguishes and green light illuminates when flow is above 1400 gpm.
SAT/UNSAT*
Step 16 - Ensure E41-F025 (Cond Pump Disch Otbd Drain Vlv) and E41-F026 (Cond Pump Disch Inbd Drain Vlv) are closed.
E41-F025 and F026 are verified closed.
SAT/UNSAT*
Step 17 - Adjust E41-FIC-R600 (Flow Control) setpoint to match system flow, and then place E41-FIC-R600 (Flow Control) in A (automatic).
HPCI flow control setpoint is adjusted to match system flow, Then E41-FIC-R600 (Flow Control) is placed in A (automatic).
SAT/UNSAT*
LOT-SIM-JP-019-15 Page 8 of 13 Rev. 02
HPCI Pressure Control Step 18 - Start SBGT.
SBGT is running per initial conditions. May verify SBGT Trains are running.
SAT/UNSAT*
Step 19 - Ensure Barometric CNDSR Condensate pump is operating.
Verifies Barometric CNDSR Condensate pump is operating SAT/UNSAT*
Step 20 - Adjust HPCI as needed.
HPCI parameters adjusted by throttling E41-F008 or varying HPCI flow with the flow controller to control reactor pressure 800-1000 psig.
- CRITICAL STEP** SAT/UNSAT*
Step 21 - Informs the CRS that HPCI is in pressure control.
Acknowledge as the CRS.
SAT/UNSAT*
TERMINATING CUE: When HPCI is running in pressure control and adjustments are being made to maintain reactor pressure 800 to 1000 psi, and the Unit CRS is informed, this JPM is complete.
- Comments required for any step evaluated as UNSAT.
TIME COMPLETED:
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
LOT-SIM-JP-019-15 Page 9 of 13 Rev. 02
HPCI Pressure Control Step Critical / Not Critical Reason 1 Not Critical Administrative step 2 Not Critical Condition will not exist for JPM.
3 Not Critical Condition will not exist for JPM.
4 Not Critical Step not required to place system in pressure control.
5 Not Critical Step not required to place system in pressure control 6 Not Critical Step not required to place system in pressure control 7 Critical Establishes required waterside flowpath 8 Critical Establishes cooling water to HPCI turbine to prevent damage 9 Not Critical Step not required to place system in pressure control 10 Critical Establishes required steam flowpath to HPCI turbine.
11 Critical Establishes required steam flowpath to HPCI turbine and provides bearing lubrication.
12 Not Critical Verification step.
13 Not Critical Step not required to place system in pressure control 14 Critical Establishes required waterside flowpath 15 Not Critical Step not required to place system in pressure control 16 Not Critical Verification step.
17 Not Critical Step not required to place system in pressure control 18 Not Critical Step not required to place system in pressure control 19 Not Critical Step not required to place system in pressure control 20 Critical Required adjustments to HPCI turbine flow to control reactor pressure.
21 Not Critical Communication step LOT-SIM-JP-019-15 Page 10 of 13 Rev. 02
HPCI Pressure Control WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer SAT/ UNSAT/ NE checking)
D. Proper Equipment Use (observe starting limitations, throttle SAT/ UNSAT/ NE valve closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety SAT/ UNSAT/ NE equipment, etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer SAT/ UNSAT/ NE to AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key SAT/ UNSAT/ NE control, etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, SAT/ UNSAT/ NE etc.)
I. Radiation Protection (ALARA, understanding and use of SAT/ UNSAT/ NE RWP, frisking, etc.)
COMMENTS:
LOT-SIM-JP-019-15 Page 11 of 13 Rev. 02
HPCI Pressure Control Validation Time: 10 Minutes (approximate).
Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-019-15 Page 12 of 13 Rev. 02
TASK CONDITIONS:
- 2. RPV water level is being maintained above LL2 by another operator.
- 4. SBGT is running.
INITIATING CUE:
You are directed by the Unit CRS to start HPCI for pressure control per the Hard Card to maintain RPV pressure between 800 - 1000 psig and inform the Unit CRS when the Hard Card actions are complete.
Page 13 of 13
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM F - 2020 NRC EXAM (RO ONLY)
LESSON TITLE: Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation LESSON NUMBER: LOT-SIM-JP-09.6-02 REVISION NO: 04 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL /DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation Rev. No. Revision Summary Minor Rev. Date Signature 04 Added performance standard. Updated JPM to NA NA new procedure.
03 New JPM format. Added Critical/Non Critical NA NA step explanation.
LOT-SIM-JP-09.6-02 Page 2 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation RELATED TASKS:
215209B401, Operate the Power Range Neutron Monitoring System per OP-09 K/A REFERENCE AND IMPORTANCE RATING:
201005 A1.04 4.1/4.1 Ability to predict and/or monitor changes in Scram and Rod Block trip setpoints associated with operating APRM system controls.
REFERENCES:
2OP-09, NEUTRON MONITORING SYSTEM OPERATING PROCEDURE.
PERFORMANCE STANDARD:
Candidate will use 2OP-09 to restore APRM rod block and scram setpoints to two loop operation.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123):
7 - Instrumentation LOT-SIM-JP-09.6-02 Page 3 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation SETUP INSTRUCTIONS:
SETUP:
A. Initial Conditions:
- 1. Recommended Initial Conditions Any IC <75% Reactor Power B. Malfunctions None C. Overrides None D. Remote Function None E. Special Instructions Implement APRM rod block and scram setpoints for single loop operation IAW 2OP-09, Section 6.3.2 on APRM Channel 1.
LOT-SIM-JP-09.6-02 Page 4 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on Unit 2.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury Read the following to the JPM performer.
TASK CONDITIONS:
- 1. The A Recirculation Pump has been returned to service from single loop.
- 2. APRM Channel 1 rod block and scram setpoints for single loop operation are in effect per 2OP-09, NEUTRON MONITORING SYSTEM OPERATING PROCEDURE Section 6.3.2.
- 3. The password, 1-2-3-4, has been obtained from the Work Release Center cyber security password locker.
INITIATING CUE:
You are directed by the Unit CRS to restore APRM Channel 1 Rod Block and Scram setpoints for two loop operation per 2OP-09, section 6.3.3. Notify the Unit CRS when all required actions are complete.
LOT-SIM-JP-09.6-02 Page 5 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Perform take a minute at job site prior to beginning task.
Examinee should cover the following questions, as deemed necessary.
What are the hazards in the area? What PPE is required? Tools/PPE inspected prior to use? Energy sources secured/isolated? Is Clearance/Tag Out sufficient? What's the worst that can happen? Any ALARA concerns? Will I affect plant status? HU Tools needed?
SAT/UNSAT TIME START: ___________
Step 2 - Confirm Recirculation loops are operating in two loop operation Given in initial conditions SAT/UNSAT Step 3 - NOTIFY the Unit CRS that APRM 1 will be bypassed.
Unit CRS is notified.
SAT/UNSAT Step 4 - PLACE APRM 1 in BYPASS.
APRM 1 is placed in Bypass.
SAT/UNSAT Step 5 - CONFIRM, at all four APRM 2/4 Voters, BYPASSED LED is on for APRM 1.
Bypassed LED is verified at all four 2/4 voters.
SAT/UNSAT LOT-SIM-JP-09.6-02 Page 6 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation NOTE: A soft key has to be depressed for the titles of the soft keys to appear.
Step 6 - PRESS ETC soft key to obtain ENTER SET MODE soft key.
Enter Set Mode soft key is obtained.
SAT/UNSAT Step 7 - PRESS ENTER SET MODE soft key.
Enter Set Mode soft key is pressed.
- CRITICAL STEP** SAT/UNSAT Step 8 - ENTER password 1 2 3 4 AND PRESS ENT.
Password is entered and ENT is pressed.
- CRITICAL STEP ** SAT/UNSAT Step 9 - At the OPER-SET PARAMETERS INDEX display, SELECT SLO/BSP CONTROL using the cursor keys.
SLO/BSP Control is selected.
- CRITICAL STEP** SAT/UNSAT Step 10 - PRESS SET PARAMETERS soft key.
Set Parameters soft key is pressed.
- CRITICAL STEP** SAT/UNSAT Step 11 - CHANGE the SLO ENABLED DESIRED: field to NO using the UP/DOWN cursor keys.
SLO Enabled DESIRED: field is changed to NO.
- CRITICAL STEP** SAT/UNSAT LOT-SIM-JP-09.6-02 Page 7 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation Step 12 - PRESS ACCEPT soft key.
ACCEPT soft key is pressed.
- CRITICAL STEP** SAT/UNSAT Step 13 - CONFIRM SLO Enabled PRESENT: field changed to NO.
SLO Enabled PRESENT: field is verified to display NO.
SAT/UNSAT Step 14 - PRESS EXIT soft key.
Exit soft key is pressed.
SAT/UNSAT Step 15 - PRESS EXIT SET MODE soft key.
Exit Set Mode soft key is pressed.
SAT/UNSAT Step 16 - PRESS YES soft key.
Yes soft key is pressed.
SAT/UNSAT Step 17 - CONFIRM the APRM display header does NOT indicate SLO.
APRM display is verified to NOT indicate SLO.
SAT/UNSAT Step 18 - PRESS TRIP MEMORY RESET on all four 2/4 Voters AND CONFIRM TRIP and MEM LEDs are OFF for APRM 1.
Trip Memory Reset is pressed on all four 2/4 Voters and the Trip and Mem LEDs are verified OFF for APRM 1.
SAT/UNSAT LOT-SIM-JP-09.6-02 Page 8 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation Step 19 - CONFIRM the applicable APRM A-06 alarms are clear.
APRM alarms are verified clear.
SAT/UNSAT PROMPT: If notified, respond as the Unit CRS and direct APRM be removed from BYPASS.
Step 20 - REMOVE APRM 1 from BYPASS.
APRM 1 is removed from Bypass.
SAT/UNSAT PROMPT: Notify candidate that Exit Region 2 was not selected, if asked.
Step 21 - If Exit Region 2 was selected to support Single Loop Operations, Then ensure the Exit Region Alarm selection is returned to Exit Region 1 per Section 6.3.9, Exit Region Alarm Selection.
Exit Region 2 not selected. Step marked as NA.
Step 22 - NOTIFY Unit CRS.
Unit CRS is notified.
SAT/UNSAT TERMINATING CUE: When APRM 1 two loop rod block and scram setpoints have been restored and the Unit CRS is notified, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2-6 Not Critical Not required to complete JPM.
7-12 Critical Required to complete JPM.
13-22 Not Critical Verification and communication steps, not required to accomplish task.
LOT-SIM-JP-09.6-02 Page 9 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-SIM-JP-09.6-02 Page 10 of 12 Rev 04
Restoration of APRM Rod Block and Scram Setpoints from Single Loop Operation to Two Loop Operation Validation Time: 10 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-09.6-02 Page 11 of 12 Rev 04
TASK CONDITIONS:
- 1. The A Recirculation Pump has been returned to service from single loop.
- 2. APRM Channel 1 rod block and scram setpoints for single loop operation are in effect per 2OP-09, NEUTRON MONITORING SYSTEM OPERATING PROCEDURE Section 6.3.2.
- 3. The password, 1-2-3-4, has been obtained from the Work Release Center cyber security password locker.
INITIATING CUE:
You are directed by the Unit CRS to restore APRM Channel 1 Rod Block and Scram setpoints for two loop operation per 2OP-09, section 6.3.3. Notify the Unit CRS when all required actions are complete.
Page 12 of 12
DUKE ENERGY BRUNSWICK NUCLEAR PLANT JOB PERFORMANCE MEASURE SIM JPM G - 2020 NRC EXAM (RO / ISRO)
LESSON TITLE: Emergency Isolation of 230 KV Bus 2A LESSON NUMBER: LOT-SIM-JP-050-01 REVISION NO: 02 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL /DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Emergency Isolation of 230 KV Bus 2A Rev. No. Revision Summary Minor Rev. Date Signature 02 Added performance standard. Updated JPM to NA NA new procedure. Deleted procedure selection decision.
LOT-SIM-JP-050-01 Page 2 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A RELATED TASKS:
200100B401, Perform Emergency Isolation of 230 KV BUS 2A in accordance with 2OP-50 Section 6.3.31 K/A REFERENCE AND IMPORTANCE RATING:
262001 A4.01 3.4/3.7 Ability to manually operate and/or monitor in the control room: All breakers and disconnects (including available switchyard)
REFERENCES:
2OP-50 PERFORMANCE STANDARD:
Candidate will perform emergency isolation of the 2A 230 KV Bus IAW 2OP-50 Section 6.3.33.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123):
6 - Electrical LOT-SIM-JP-050-01 Page 3 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A SIMULATOR SETUP IC-13 (suggested) or any IC with the generator on line Triggers None Malfunctions EE006F, Main Generator PCB 29A SF6 Leak (activate with a severity of 2)
Overrides Override alarm ZUA1331 (Gen Loss Exc) on (prevents alarm continuously alarming and clearing during the actions of the JPM.
Remote Functions None Special Instructions Activate malfunction EE006F for PCB 29A (severity of 2) and alarm ZUA1331 Ensure UA-13 3-7 alarm seals in (PCB 29A indication should be lost)
Insert a manual scram Perform scram immediate actions Place simulator in freeze NOTE: A red alarm message will appear on the simulator instructor station stating Main Generator Severe Internal Damage.
Prior to candidate performing procedure-ensure simulator in RUN.
LOT-SIM-JP-050-01 Page 4 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on Unit 2.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury Read the following to trainee.
TASK CONDITIONS:
- 1. Unit Two was operating at power.
- 2. Alarm UA-13 3-7 Gen PCB A L/O Gas-Low was received and sealed in.
- 3. A reactor scram then occurred.
- 4. An operator has performed scram immediate actions.
- 5. PCB 29A has not opened requiring emergency isolation of the associated 230 KV Bus.
INITIATING CUE:
The CRS directs you to perform Emergency Isolation of 230 KV Bus 2A IAW 2OP-50 Section 6.3.33. Inform the CRS when actions to isolate 230 KV Bus 2A are complete.
LOT-SIM-JP-050-01 Page 5 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
START TIME:
Step 1 - Ensure Unit CRS permission is granted to implement this procedure Given in initial conditions SAT/UNSAT NOTE: PCB 29A has no light indication as expected with sudden loss of gas pressure, but alarm UA-13 1-7 (Gen PCB A Open) is clear indicating the PCB did not open.
Step 2 - Ensure Generator 2 to Bus 2A 230KV PCB 29A has failed to TRIP and 230KV Bus 2A is still Energized from off-site Determines that PCB 29A remains closed due to loss of indication and that UA-13 1-7 (Gen PCB A Open) is clear.
SAT/UNSAT Step 3 - Open Bus 2A To SAT & Caswell Beach 230 KV PCB 26A.
Bus 2A To SAT & Caswell Beach 230 KV PCB 26A switch is rotated to the trip position (red light extinguishes and green light illuminates) and then released.
- CRITICAL STEP ** SAT/UNSAT*
LOT-SIM-JP-050-01 Page 6 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A NOTE: Step 4 is performed for all four line PCBs listed in Table 1. Table 1 is duplicated on the following page to allow the examiner to keep track of the examinees actions.
It is not necessary to place the Auto Reclose switch to Manual to open the PCB.
Opening the PCB by control switch will actuate the breaker reclose lockout relay (86X).
The Supervisory switch must be placed to Local to open a line PCB from panel XU-5.
PCB 29B will already be open due to the generator lockout relays.
Step 4 - For each line PCB listed in Table 1.
- a. Place Auto Reclosure switch in Manual.
Auto Reclosure switch is placed in Manual.
SAT/UNSAT
- b. Place Supervisory switch in Local.
Supervisory switch is placed in Local.
- CRITICAL STEP ** SAT/UNSAT
- c. Open Breaker.
PCB Breaker switch is rotated to the trip position (red light extinguishes and green light illuminates) and then released.
- CRITICAL STEP ** SAT/UNSAT TABLE 1 Auto Reclose Supervisory Breaker Description in Manual in Local Open Bus 2A To Town Creek 230 KV PCB 27A Bus 2A To Wallace 230 KV PCB 28A Bus 2A To Delco West 230 KV PCB 30A Bus 2A To Whiteville 230 KV PCB 31A LOT-SIM-JP-050-01 Page 7 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A Step 5 - Ensure Generator 2 To Bus 2B 230 KV PCB 29B is open.
Verifies Generator 2 To Bus 2B 230 KV PCB 29B indicates open.
SAT/UNSAT PROMPT: When examinee informs Load Dispatcher of 230 KV Bus emergency isolation, role play as Dispatcher and acknowledges the report.
Step 6 - Notify the Load Dispatcher of 230 KV Bus 2A emergency isolation.
Load Dispatcher notified of 230 KV Bus 2A emergency isolation.
SAT/UNSAT Step 7 - Notify the CRS 230 KV Bus 2A emergency isolation actions are complete.
CRS notified 230 KV Bus 2A emergency isolation actions are complete.
SAT/UNSAT COMPLETION TIME:
TERMINATING CUE: When actions to emergency isolate 230 KV Bus 2A IAW 2OP-50 have been performed, this JPM is complete.
Comments required for any step evaluated as UNSAT.
Step Critical / Not Critical Reason 1 Not Critical Not required to complete JPM.
2 Not Critical Not required to complete JPM.
3 Critical Required to complete JPM.
4a Not Critical Not required to complete JPM.
4b Critical Required to complete JPM.
4c Critical Required to complete JPM.
5 Not Critical Not required to complete JPM.
6 Not Critical Not required to complete JPM.
7 Not Critical Not required to complete JPM.
LOT-SIM-JP-050-01 Page 8 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-SIM-JP-050-01 Page 9 of 11 REV. 02
Emergency Isolation of 230 KV Bus 2A Validation Time: 7 Minutes (approximate).
Time Taken: _________
APPLICABLE METHOD OF TESTING Performance: Simulate ___ Actual X Unit: 2 Setting: In-Plant Simulator X Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-050-01 Page 10 of 11 REV. 02
TASK CONDITIONS:
- 1. Unit Two was operating at power.
- 2. Alarm UA-13 3-7 Gen PCB A L/O Gas-Low was received and sealed in.
- 3. A reactor scram then occurred.
- 4. An operator has performed scram immediate actions.
- 5. PCB 29A has not opened requiring emergency isolation of the associated 230 KV Bus.
INITIATING CUE:
The CRS directs you to perform Emergency Isolation of 230 KV Bus 2A IAW 2OP-50 Section 6.3.33. Inform the CRS when actions to isolate 230 KV Bus 2A are complete.
Page 11 of 11
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIM JPM CR H - 2020 NRC EXAM (RO / ISRO)
LESSON TITLE: Manual Startup of Control Building Emergency Ventilation LESSON NUMBER: LOT-SIM-JP-037-A06 REVISION NO: 05 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Maricle VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL/DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL/ DATE
Manual Startup of Control Building Emergency Ventilation Rev. Revision Summary Minor Rev. Date No. Signature 05 Added performance standard. Updated to new NA NA format.
LOT-SIM-JP-037-A06 Page 2 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation RELATED TASKS:
288202B101, Start the Control Building ventilation System per OP-37 K/A REFERENCE AND IMPORTANCE RATING:
290003 A4.01 3.2/3.2 Ability to manually operate and/or monitor in the control room: Initiate/reset system.
REFERENCES:
0OI-37.17 EOP Hard Cards PERFORMANCE STANDARD:
Candidate will use hard card to place CREV in service.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2) 9- Radioactivity Release LOT-SIM-JP-037-A06 Page 3 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation SETUP:
Recommended Initial Conditions Any 100% Power IC Place the 2A CREV control switch in Pref Remotes Man. Trigger 1- MI_IACBLRM1, Unit 1 Cable Spread Room Vent Fans, OFF Man. Trigger 2- MI_ZVACS918_1, Unit 1 CB Mechanical Equip Room Vent Fans CS, STOP.
LOT-SIM-JP-037-A06 Page 4 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the performer.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.
- 3. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury Read the following to the JPM performer.
TASK CONDITIONS:
You are the Unit Two Control Operator.
INITIATING CUE:
You are directed to perform the actions for manual startup of the CREV System using the CREV fan with the control switch in PREF per the Hard Card and inform the Unit CRS when the actions are complete.
LOT-SIM-JP-037-A06 Page 5 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain Manual Startup of the Control Building Emergency Recirculation System hard card.
Hard card obtained.
SAT/UNSAT TIME START Step 2 - PLACE either 2A-ERF-CB or 2B-ERF-CB ON. (CB Emerg Recirc Fan)
Identifies 2A-ERF-CB is in PREF, and places 2A-ERF-CB control switch to ON.
2L-D-CB, Control Room Normal Makeup Damper verified closed.
SAT/UNSAT Step 4 - CONFIRM Control Building Emergency Recirculation Damper, VA-2J-D-CB, Opens.
VA-2J-D-CB, Control Building Emergency Recirculation Damper verified OPEN.
SAT/UNSAT Step 5 - STOP Control Building Washroom Exhaust Fan, 2D-EF-CB, and CONFIRM associated damper closes.
2D-EF-CB, Control Building Washroom Exhaust Fan, stopped and associated damper verified closed.
- CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-037-A06 Page 6 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation PROMPT: The CB Mech. Equip. Room Fans can only be stopped by simultaneously placing both Units control switches in OFF. When requested as Unit One to STOP the Control Building Mechanical Equipment Room Vent Fans initiate the appropriate trigger. (trigger 2)
Step 6 - STOP Control Building Mechanical Equipment Room Vent Fans, 2F-SF-CB and 2E-EF-CB, and CONFIRM associated Supply and Exhaust Dampers CLOSE.
2F-SF-CB and 2E-EF-CB, Control Building Mechanical Equipment Room Vent Fans stopped and associated Supply and Exhaust Dampers verified closed.
2A-SF-CB and 2A-EF-CB, Cable Spread Room 2 Vent Fans stopped and associated Supply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT PROMPT: When requested to STOP (Unit One) Cable Spread Room 1 Vent Fans initiate the appropriate trigger. (trigger 1)
Step 8 - Request Unit 1 STOP Cable Spread Room 1 Vent Fans, 1A-SF-CB and 1A-EF-CB, and CONFIRM associated Supply and Exhaust Dampers CLOSE.
1A-SF-CB and 1A-EF-CB, Cable Spread Room 1 Vent Fans stopped and associated Supply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT Step 9 - Inform Unit CRS that actions for manual startup of the Control Building Emergency Recirculation System are complete.
Unit CRS notified.
SAT/UNSAT LOT-SIM-JP-037-A06 Page 7 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation TERMINATING CUE: When the Control Building Emergency Recirculation System has been started per the hard card, this JPM is complete.
TIME COMPLETED NOTE: Comments required for any step evaluated as UNSAT.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Critical Required to complete JPM.
3 Not Critical Not required to complete JPM.
4 Not Critical Not required to complete JPM 5 Critical Required to complete JPM.
6 Critical Required to complete JPM.
7 Critical Required to complete JPM.
8 Critical Required to complete JPM 9 Not Critical Not required to complete JPM LOT-SIM-JP-037-A06 Page 8 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer SAT/ UNSAT/ NE checking)
D. Proper Equipment Use (observe starting limitations, throttle SAT/ UNSAT/ NE valve closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety SAT/ UNSAT/ NE equipment, etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key SAT/ UNSAT/ NE control, etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
NOTE: Comments required for any step evaluated as UNSAT LOT-SIM-JP-037-A06 Page 9 of 11 Rev. 05
Manual Startup of Control Building Emergency Ventilation Validation TIme 7 Minutes (approximate)
Time Taken:
APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:
Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-SIM-JP-037-A06 Page 10 of 11 Rev. 05
TASK CONDITIONS:
You are the Unit Two Control Operator.
INITIATING CUE:
You are directed to perform the actions for manual startup of the CREV System using the CREV fan with the control switch in PREF per the Hard Card and inform the Unit CRS when the actions are complete.
Page 11 of 11
DUKE ENERGY PROGRESS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT JPM I - 2020 NRC EXAM (RO / ISRO)
LESSON TITLE: Maintaining Generator Hydrogen Pressure LESSON NUMBER: AOT-OJT-JP-027.3-02 REVISION NO: 06 S. Cotton PREPARER / DATE Bob Bolin TECHNICAL REVIEWER / DATE S. Hildebrandt 08/20/20 VALIDATOR / DATE Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Maintaining Generator Hydrogen Pressure Revision Summary:
Rev. No. Revision Summary Minor Rev. Date Signature 06 Added performance standard NA NA 05 Revised JPM to the new JPM Template NA NA AOT-OJT-JP-027.3-02 Page 2 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure RELATED TASKS:
252*004*B1*04, Add Hydrogen to the Generator per OP-27.3.
K/A REFERENCE AND IMPORTANCE RATING:
Gen 2.1.30 Ability to locate and operate components, including local controls.
4.4/
4.0 REFERENCES
1(2)OP-27.3, Generator Gas System Operating Procedure PERFORMANCE STANDARD:
Candidate will use OP-27.3 to add hydrogen to the main generator. Candidate will recognize the requirement to secure the hydrogen addition line up on receipt of the Hydrogen supply pressure low alarm.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
4 (Heat Removal from the Core)
SETUP INSTRUCTIONS None AOT-OJT-JP-027.3-02 Page 3 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure SAFETY CONSIDERATIONS:
- 2. Determine actual radiological conditions and potentially contaminated areas to achieve ALARA.
- 3. Ensure all electrical safety requirements are observed.
- 4. Review Work Practices section prior to conduct of the JPM.
- 5. DO NOT OPERATE any plant equipment during performance of this JPM.
EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on Unit 1 or Unit 2 as selected by the evaluator.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury AOT-OJT-JP-027.3-02 Page 4 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure Read the following to the JPM performer.
TASK CONDITIONS:
This Task is to be performed on Unit _________
- 1. Generator casing is filled with hydrogen in accordance with Section 6.1.2
- 2. Hydrogen is available from the Hydrogen/Oxygen Storage Facility to the Generator Hydrogen Control Station
- 3. Annunciator H2 SUPPLY PRESS-LOW (UA-02 5-5) NOT in alarm
- 4. Generator gas pressure is 58 psig
- 5. The other Unit is NOT adding hydrogen to their generator
- 6. The HYDROGEN REGULATOR, HC-GRE-2, setpoint is 60 psig.
INITIATING CUE:
You are directed by the Unit Control Operator to add hydrogen to the Main Generator to raise generator pressure to 60 psig in accordance with 1(2)OP-27.3.
AOT-OJT-JP-027.3-02 Page 5 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Perform take a minute at job site prior to beginning task.
Examinee should cover the following, as deemed necessary.
Correct Unit / Train / Component. How will I prevent a PSC event? Action in case of an emergency. What are the hazards in the work area? What hazards will be created by the work? How will I eliminate or mitigate the hazards?
SAT / UNSAT TIME START: ___________
Step 2 - Ensures Hydrogen Regulator Inlet valve, HC-G-06, is open.
HC-G-06 is open by rotating in the valve in the counter-clockwise direction until full resistance is felt.
- CRITICAL STEP**SAT/UNSAT Step 3 -Slowly open Hydrogen Regulator Outlet Valve, HC-G-07.
HC-G-07 is opened by slowly rotating the valve in the counter-clockwise direction until full resistance is felt.
- CRITICAL STEP**SAT/UNSAT PROMPT: When HC-G-07 is opened, as the Unit RO inform examinee that control room alarm UA-02 5-5, H2 Supply Press-Low is alarming.
NOTE: Per caution, HC-G-07 valve should immediately be closed to prevent loss of hydrogen from the generator.
NOTE: Either closing HC-07 or HC-06 will isolate the generator gas pressure. Therefore either step 4 or step 5 will satisfy the critical step criteria.
AOT-OJT-JP-027.3-02 Page 6 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure Step 4 - Close Hydrogen Regulator Outlet Valve, HC-G-07.
HC-G-07 is closed by rotating the valve in the clockwise direction until full resistance is felt.
- CRITICAL STEP**SAT/UNSAT PROMPT: If isolation valve HC-G-07 is not closed as the Unit RO tell performer that generator pressure is slowly dropping is 55 psig and slowly lowering.
NOTE: Performer may close the HC-G-06 valve also to put the system in a stable condition.
Step 5 -Close Hydrogen Regulator Inlet valve, HC-G-06.
HC-G-06 is closed by rotating the valve in the clockwise direction until full resistance is felt.
TIME STOP: _________
NOTE: Comments required for any step evaluated as UNSAT.
AOT-OJT-JP-027.3-02 Page 7 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure 1 Not Critical Administrative 2 Critical Required to complete task.
3 Critical Required to complete task.
4 Critical Required to complete task.
5 Critical Required to complete task.
AOT-OJT-JP-027.3-02 Page 8 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
AOT-OJT-JP-027.3-02 Page 9 of 11 Rev. 06
Maintaining Generator Hydrogen Pressure Validation Time: 10 Minutes (approximate)
Time Taken: ___ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: 1/2 Setting: In-Plant X Simulator ____ Admin ____
Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
AOT-OJT-JP-027.3-02 Page 10 of 11 Rev. 06
TASK CONDITIONS:
This Task is to be performed on Unit _________
- 1. Generator casing is filled with hydrogen in accordance with Section 6.1.2
- 2. Hydrogen is available from the Hydrogen/Oxygen Storage Facility to the Generator Hydrogen Control Station
- 3. Annunciator H2 SUPPLY PRESS-LOW (UA-02 5-5) NOT in alarm
- 4. Generator gas pressure is 58 psig
- 5. The other Unit is NOT adding hydrogen to their generator
- 6. The HYDROGEN REGULATOR, HC-GRE-2, set-point is 60 psig.
INITIATING CUE:
You are directed by the Unit Control Operator to add hydrogen to the Main Generator to raise generator pressure to 60 psig in accordance with 1(2)OP-27.3.
Page 11 of 11
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE LESSON TITLE: Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
LESSON NUMBER: AOT-OJT-JP-303-14 REVISION NO: 04 Michael Nemec 07/22/2020 PREPARER DATE Bob Bolin 07/23/2020 TECHNICAL REVIEWER DATE P. McLoughlin 8/06/2020 LINE REVIEWER/VALIDATOR DATE Ed Rau 08/25/2020 TRAINING SUPERVISION APPROVAL/ DATE
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
REVISION
SUMMARY
REVISION REVISION
SUMMARY
MINOR REVISION MINOR REVISION NUMBER SIGNATURE DATE 04 Changed to Non-Time Critical due to being N/A N/A alternate path.
Replaced CCV with STAR for Core 4.
Added JPM performance standard Revised KA 03 Minor Change to step wording from new procedure revision to improve hard match criteria.
2 Minor changes and format updates.
Updated procedure sections for AOP 36.1, since AOP-36.2 is now SBO, with this section replaced by EOP-01-SBO-07.
Updated with the new Electrical Safety procedure, AD-HS-ALL-0110.
Enhanced explanations in Critical Step Bases Table.
Revalidated for 2016 Annual Exam.
Page numbers changed to hidden text on Task Cue sheet.
Reviewed for Time Critical or Time Sensitive Operator Actions 1 Formatting and numbering changes to match the JPM Template.
Step where performer demonstrates they can obtain procedure and verify current revision is no longer required to be observed and evaluated.
Procedure use is now evaluated in the Work Practices section, as applicable.
Deletes reference to old Touch STAR and reformats Work Practices section.
Revises Settings to In-Plant, Simulator and Admin per the JPM Template.
Added Validation Time and Time Taken to the top of the Evaluation form.
Ensured Time Start and Time Completed points are clearly identified.
0 New JPM AOT-OJT-JP-303-14 Page 2 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
RELATED TASKS:
262605 B104 Rack in a 480 V Electrically Operated Breaker per OP-50/AOP-36.2.
K/A REFERENCE AND IMPORTANCE RATING:
295003 AA1.01 3.7/3.8 Ability to Operate and/or Monitor AC Electrical Distribution System as it applies to a partial or complete loss of A.C. power
REFERENCES:
0EOP-01-SBO-07, 480V E-BUS CROSS-TIE PERFORMANCE STANDARD:
Examinee will rack in E7 and E8 480V cross-tie breakers and manually charge E8-A10 to support remote breaker closures IAW 0EOP-01-SBO-07.
TOOLS AND EQUIPMENT:
- 1. Racking tool for 480V Breakers
- 2. Manual charging handle for 480 V Breaker SAFETY FUNCTION (from NUREG 1123, Rev 2):
6 - Electrical Distribution)
TIME CRITICAL OPERATOR ACTIONS:
This is NOT a time critical JPM. However, this JPM is based upon the PRA Time Sensitive Operator Action for SBO per 1(2)EOP-01-SBO as follows:
TSOA Event# Operator Required When Validation Basis Procedure Validation Action Time Required Required NTM Model#
PRA 2 Cross Tie 60 Loss of Yes BNP-PSA- 1EOP 2057905-02 480v busses minutes power to 062 SBO E5 and E6 [Note 1] one of 480v 2EOP (E7 and E8) busses SBO [Note 3]
AOT-OJT-JP-303-14 Page 3 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
SAFETY CONSIDERATIONS:
- 2. Standard electrical precautions when working around energized electrical equipment.
- 3. Hard Hat, safety glasses, and ear protection are required in the Diesel Building.
EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.
- 3. Electrical safety requirements per AD-HS-ALL-0110, Electrical Safety, may be discussed ( Hazard Category 4, racking 480V Load Center Breakers when energized).
- 4. This JPM will be performed on Unit 2.
- 5. Critical Step Basis
- a. Prevents Task Completion
- b. May Result in Equipment Damage
- c. Affects Public Health and Safety
- d. Could Result in Personal Injury Read the following to Performer.
TASK CONDITIONS:
- 1. A complete Loss of Offsite Power and Station Blackout has occurred.
- 2. DG2 is available on Unit 1, supplying E2 4KV Bus.
- 3. E2 is cross-tied to E4, powering E8.
- 4. 0EOP-01-SBO-07 is being executed, completed through Section 2.3.3, Step 9.
- 5. ASSD Emergency Switchgear Bag is at the crosstie breaker on E7.
INITIATING CUE:
You are directed by the CRS to complete the field actions associated with energizing Substation E7 from E8 in accordance with 0EOP-01-SBO-07, Section 2.3.3 and inform the Reactor Operator when the E7 to E8 cross-tie breakers are ready to be closed.
AOT-OJT-JP-303-14 Page 4 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Obtain current revision of 0EOP-01-SBO-07, 480V E-Bus Cross-Tie and verify copy if applicable.
Current revision of 0EOP-01 obtained and verified, as applicable.
SAT/UNSAT/NE TIME START ___________
NOTE: A 480 V racking tool is contained in the ASSD Equipment bag.
During performance of time-critical, emergency evolutions (e.g., Safe Shutdown, Station Blackout (SBO), Emergency Operating Procedure (EOP), Emergency Response Organization (ERO) actions), when overall plant nuclear safety or the safety of the general public take precedence, personnel may not be able to comply with all requirements of AD-HS-ALL-0110, Electrical Safety.
PROMPT: Inform Examinee that electrical equipment compartments are NOT to be breached.
Step 2 - At E7, Row A1, rack in 2-E7-AX5-52 (Cross-tie To Substation E8 Bkr Compt AX5),
confirm breaker is open.
Cross Tie breaker to E7, Compt AX5 on Bus E7 verified open as indicated by the green open flag.
SAT/UNSAT PROMPT: If asked, inform the examinee that the locking hasp position is as seen. Shutter moves freely.
Step 3 - If necessary, depress the locking hasp on E7 Compt. AX5 to allow opening of the racking shutter.
Locking hasp DEPRESSED or verified to already be depressed on E7 Compt.
AX5 SAT/UNSAT AOT-OJT-JP-303-14 Page 5 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
Step 4 - Rotate the racking crank CLOCKWISE at E7 Compt. AX5 until breaker stops in the CONNECT position.
Breaker E7 Compt. AX5 racking crank is turned in the clockwise direction until breaker stops. The breaker stops in the CONNECT position (racked in and shutter window closes when the racking tool is removed).
- CRITICAL STEP ** SAT/UNSAT PROMPT: When charging power switch is placed on, inform trainee that they hear a ratcheting sounds and then a clunk. Window indicates that the springs are charged.
Step 5 - Place the E7 Compt. AX5 charging power switch to the ON position, and determine springs charge.
Charging power switch for E7 Compt. AX5 placed to the ON position, springs determined charged.
- CRITICAL STEP ** SAT/UNSAT Step 6 - At E8, Row F1, rack in 2-E8-A10-52 (Cross-tie To Substation E7 Compt A10),
confirm breaker is open.
Cross Tie breaker to E8, Compt A10 on Bus E8 verified open as indicated by the green open flag.
SAT/UNSAT PROMPT: If asked, inform the examinee that the locking hasp position is as seen. Shutter moves freely.
Step 7 - If necessary, depress the locking hasp on E8 Compt. A10 to allow opening of the racking shutter.
Locking hasp DEPRESSED or verified to already be depressed on E8 Compt.
A10.
SAT/UNSAT Step 8 - Rotate the racking crank CLOCKWISE at E8 Compt. A10 until breaker stops in the CONNECT position.
Breaker E8 Compt. A10 racking crank is turned in the clockwise direction until breaker stops. The breaker stops in the CONNECT position (racked in and shutter window closes when the racking tool is removed).
- CRITICAL STEP ** SAT/UNSAT AOT-OJT-JP-303-14 Page 6 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
- Begin Alternate Path **
PROMPT: As requested, inform the examinee that the closing springs failed to charge as indicated by lack of charging noise when toggle switch turned on and/or lack of spring charged indicator at front of breaker.
Step 9 - Place the Compt A10 on Bus E8 charging power switch to the ON position, and determine springs failed to charge.
Charging power switch for E8 Compt A10 ON, springs determined not charged.
SAT/UNSAT NOTE: A manual charging handle for the 480 VAC cross-tie breaker springs is located in the Emergency Switchgear Operator ASSD bag and would be available to the examinee.
The manual charging lever is located at the bottom middle of the 480 VAC breaker. The breaker compartment door CAN be opened to demonstrate location of the manual charging lever even with the breaker racked out.
Step 10 - Manually charge closing springs as follows:
Manually charges closing springs per Attachment 1 as follows.
- a. Place charging power toggle switch to OFF.
Charging power toggle switch is placed in OFF.
SAT/UNSAT
- b. Open breaker compartment door and insert manual charging handle.
Manual charging handle is inserted in the breaker.
- CRITICAL STEP ** SAT/UNSAT PROMPT: After a few handle pumps, Provide you hear the springs click and the SPRINGS CHARGED flag is indicated AOT-OJT-JP-303-14 Page 7 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
- c. Pump manual charging handle until closing springs are charged (clicks into position) and confirm charge is satisfactory by Springs Charged indicator.
Charging handle is ratcheted (pumped) until the closing springs are fully charged.
- CRITICAL STEP ** SAT/UNSAT
- d. Remove manual charging handle and close compartment door.
Manual charging handle removed, compartment door closed.
SAT/UNSAT
- e. Place charging power toggle switch to ON.
Charging power toggle switch is placed in the ON position.
SAT/UNSAT PROMPT: When requested as control room to close E7-E8 tie breakers, inform examinee that the breakers are closed.
Step 11 - Inform Control Room that E7-E8 tie breakers are racked in and ready to be closed.
Control Room informed.
SAT/UNSAT TERMINATING CUE: Substation E7 and E8 Breakers are racked in and E7 is ready to be energized from Substation E8.
Time Completed: ___________
NOTE: Comments required for any step evaluated as UNSAT.
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
AOT-OJT-JP-303-14 Page 8 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
Critical Step Bases Step Critical / Not Critical Reason 1 Not Critical Administrative and work practices, if required for the applicable program.
2 Not Critical Verification step.
3 Not Critical Verification step. Action bounded by Step 4.
4 Critical Breaker required to be racked in for task completion.
5 Critical Breaker springs required to be charged for remote operation and task completion.
6 Not Critical Verification step.
7 Not Critical Verification step. Action bounded by Step 7.
8 Critical Breaker required to be racked in for task completion.
9 Critical Required to determine alternate path is required.
10a Not Critical Verification Step.
10b, c Critical Breaker springs required to be manually charged for remote operation and task completion.
10d, e Not Critical Follow-up actions not required for task completion.
11 Not Critical Communication step Confirmation and verification step.
AOT-OJT-JP-303-14 Page 9 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
AOT-OJT-JP-303-14 Page 10 of 15 Rev. 04
Energizing E7 from E8 Cross-Tie with Breaker Failure (AP)
Validation Time: 15 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate X Actual ___ Unit: 2 Setting: In-Plant X Simulator Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
AOT-OJT-JP-303-14 Page 11 of 15 Rev. 04
AX5 Page 12 of 15
Page 13 of 15 Page 14 of 15 Read the following to Performer.
TASK CONDITIONS:
- 1. A complete Loss of Offsite Power and Station Blackout has occurred.
- 2. DG2 is available on Unit 1, supplying E2 4KV Bus.
- 3. E2 is cross-tied to E4, powering E8.
- 4. 0EOP-01-SBO-07 is being executed, completed through Section 2.3.3, Step 9.
- 5. ASSD Emergency Switchgear Bag is at the crosstie breaker on E7.
INITIATING CUE:
You are directed by the CRS to complete the field actions associated with energizing Substation E7 from E8 in accordance with 0EOP-01-SBO-07, Section 2.3.3 and inform the Reactor Operator when the E7 to E8 cross-tie breakers are ready to be closed.
Page 15 of 15
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT JPM K - 2020 NRC EXAM (RO / ISRO / USRO)
LESSON TITLE: Restoring Service Air Header After Service Air Has Isolated (Alternate Path)
LESSON NUMBER: AOT-OJT-JP-046-A01 REVISION NO: 00 Steve Cotton PREPARER Bob Bolin TECHNICAL REVIEWER Brett Layton 06/18/20 VALIDATOR DATE S. Hildebrandt 08/20/20 VALIDATOR DATE Rob Mehs 9/15/20 LINE APPROVAL DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL DATE
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
REVISION Rev. No. Revision Summary Minor Rev. Date Signature 0 New JPM written to support NRC exam ILT 2020. NA NA AOT-OJT-JP-046-A01 Page 2 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
RELATED TASKS:
278001B401, Respond to a Loss of Pneumatics per AOP-20.0 K/A REFERENCE AND IMPORTANCE RATING:
295019 AA1.04 3.3 3.2 Ability to operate and/or monitor the following as they apply to Partial or Complete Loss of Instrument Air: Service Air Isolations Valves: Plant-Specific
REFERENCES:
0OP-46, Instrument and Service Air System Operating Procedure section 6.3.7, Restoring the Service Air Header After Service Air has Isolated PERFORMANCE STANDARD:
The examinee will take actions per 0OP-46 section 6.3.7 to restore the service air header.
The examinee will recognize the service air header pressure dropping below 110 psig and close the 1(2)SA-V8 IAW 0OP-46 section 6.3.7 step 6 prior to service air header pressure reaching 105 psig or the 1(2)SA-V8 reaching the full open position.
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
8 - Plant Service Systems TIME CRITICAL OPERATOR ACTIONS:
None for this JPM AOT-OJT-JP-046-A01 Page 3 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
SAFETY CONSIDERATIONS:
- 1. Use caution in the vicinity of operating equipment.
- 2. Use caution in vicinity of energized electrical equipment.
EVALUATOR NOTES: (Do not read to performer)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on either unit.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety
- 5. Could Result in Personal Injury.
Read the following to the performer.
TASK CONDITIONS:
- 1. Service Air is isolated.
- 2. All applicable prerequisites listed in Section 5.0 are met.
INITIATING CUE:
You are directed by the Unit CRS to restore the Service Air Header after Isolation IAW 0OP-46 Section 6.3.7 starting at step 2. Notify the Unit CRS when all required actions are complete.
AOT-OJT-JP-046-A01 Page 4 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
PERFORMANCE CHECKLIST NOTE: A marked up copy of 0OP-46.0, Section 6.3.7, is to be provided to the trainee.
Step 1 - Perform take a minute at job site prior to beginning task.
Examinee should cover the following, as deemed necessary.
Correct Unit / Train / Component. How will I prevent a PSC event? Action in case of an emergency. What are the hazards in the work area? What hazards will be created by the work? How will I eliminate or mitigate the hazards?
SAT / UNSAT TIME START: ___________
Step 2 - Ensure the 1(2)-SA-V8 is closed.
Simulates closing the 1(2)-SA-V8 by rotating the valve in the clockwise direction until full resistance is felt.
- CRITICAL STEP **SAT/UNSAT Step 3 - Ensure the 1(2)-SA-V10 is closed.
Simulates closing the 1(2)-SA-V10 by rotating the valve in the clockwise direction until full resistance is felt.
- CRITICAL STEP ** SAT/UNSAT PROMPT: IF asked, as the RO, inform the trainee that the 1(2)-SA-PV-706-1&2 (Service Air Isol Vlvs) switch is in OPEN.
Step 4 - Ensure 1(2)-SA-PV-706-1&2 (Service Air Isol Vlvs) switch is in OPEN.
Informed by the control room that the switch is open.
SAT/UNSAT Step 5 - Depress service air isolation Reset push button located in the Turbine Building to reset the service air isolation.
Simulates depressing the service air isolation Reset push button.
- CRITICAL STEP ** SAT/UNSAT AOT-OJT-JP-046-A01 Page 5 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
NOTE: The trainee should establish a method to monitor service air pressure. The 1(2)SA-PI-7363 or 1(2)IA-PI-724 both are located on large block column adjacent to the service air isolation valves and are both indicative of air pressure.
PROMPT: If contacted as the control room to monitor air pressure, acknowledge and report instrument air header pressure is 120 psig and service air header pressure is 0 psig.
PROMPT: When the 1(2)-SA-V8 is slowly opened inform the candidate that a large rush of air is heard through the piping.
Step 6 - Slowly throttle open 1(2)-SA-V8,(Inlet Isolation to SA-PV-706-1), to pressurize the downstream piping .
Simulates slowly throttling OPEN the 1(2)-SA-V8 by slowly rotating the valve in the counter-clockwise direction until the sound of rushing air is heard.
- CRITICAL STEP** SAT/UNSAT
- Begin Alternate Path **
PROMPT: After the trainee has established monitoring air pressure and begun to slowly OPEN the 1(2)-SA-V8, simulate lowering SA air pressure on either the 1(2)-SA-PI-7363 or 1(2)-IA-PI-724 (both are located on large block column adjacent to the Service Air isolation valves) or by control room report of lowering instrument air pressure.
Step 7 - When service air header pressure drop below 110 psig, Examinee CLOSES the 1(2)-
SA-V8.
Simulates closing the 1(2)-SA-V8,(Inlet Isolation to SA-PV-706-1), by rotating the valve in the clockwise direction until full resistance is felt.
- CRITICAL STEP ** SAT/UNSAT Step 8 - Examinee reports to the Control Room that Service air cannot be restored at this time due to indications of excessive leakage.
Examinee reports to control room of final system configuration and reason.
SAT/UNSAT AOT-OJT-JP-046-A01 Page 6 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
TERMINATING CUE: When the 1(2)-SA-V8 is re-closed or the service air pressure reaches 105 psig, this JPM is complete.
Time Completed: ___________
NOTE: Comments required for any step evaluated as UNSAT.
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Critical Step Bases Step Critical / Not Critical Basis / Reason 1 Not Critical Administrative 2 Critical Required for controlled restoration of air header.
3 Critical Required for controlled restoration of air header.
4 Not Critical This is a Control Room step and is provided to the candidate.
5 Critical Required to restore air header.
6 Critical Required to restore air header.
7 Critical Isolate excessive air leakage.
8 Not Critical Informing Control Room of results.
AOT-OJT-JP-046-A01 Page 7 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
AOT-OJT-JP-046-A01 Page 8 of 10 Rev 00
Restoring Service Air Header After Service Air has Isolated (Alternate Path)
Validation Time: Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: 1/2 Setting: In-Plant X Simulator Admin Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
AOT-OJT-JP-046-A01 Page 9 of 10 Rev 00
Read the following to the performer.
TASK CONDITIONS:
- 1. Service Air is isolated.
- 2. All applicable prerequisites listed in Section 5.0 are met.
INITIATING CUE:
You are directed by the Unit CRS to restore the Service Air Header after Isolation IAW 0OP-46 Section 6.3.7 starting at step 2. Notify the Unit CRS when all required actions are complete.
Page 10 of 10
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM COO1 - 2020 NRC EXAM - RO LESSON TITLE: EVALUATE STATUS OF OPERATOR LICENSES LESSON NUMBER: LOT-ADM-JP-201-D13 REVISION NO: 02 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER S. Hildebrandt VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE LOT-ADM-JP-201-D13 Page 1 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES REVISION
SUMMARY
Rev. Revision Summary Minor Rev. Date No. Signature 02 Added performance standard. Updated JPM NA NA to criteria of AD-OP-ALL-0107 which required modification of watch standing hours. Changed Operator #1 license status.
LOT-ADM-JP-201-D13 Page 2 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES RELATED TASKS:
None K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.4 3.3/3.8 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc
REFERENCES:
AD-OP-ALL-0107, Maintenance of RO and SRO Licenses rev. 2 PERFORMANCE STANDARD:
Candidate will analyze watch standing hour data and determine that Operators #1 and #3 will satisfy the criteria of AD-OP-ALL-0107, Maintenance of RO and SRO Licenses.
Candidate will determine that Operator #2 will NOT meet the criteria of AD-OP-ALL-0107.
TOOLS AND EQUIPMENT:
Calculator SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin - Conduct of Operation SETUP INSTRUCTIONS None LOT-ADM-JP-201-D13 Page 3 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES SAFETY CONSIDERATIONS:
- 2. Determine actual radiological conditions and potentially contaminated areas to achieve ALARA.
- 3. Ensure all electrical safety requirements are observed.
- 4. Review Work Practices section prior to conduct of the JPM.
- 5. DO NOT OPERATE any plant equipment during performance of this JPM.
EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury LOT-ADM-JP-201-D13 Page 4 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES Read the following to the JPM performer.
TASK CONDITIONS:
- 1. The following conditions apply for operators #1, #2, and #3:
- Operator #1: license was NOT active as of January 1st, 2020.
- Operator #2: license was active as of January 1st, 2020.
- Operator #3 is activating a new license.
- All required training is complete.
- Respirator qualifications are current.
- Emergency response organization qualifications are current.
- All required plant tours have been conducted by the Shift Manager within the required time frame.
- Shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts, including turnovers.
- When required, shifts were worked under the direction of an active license holder.
- The Unit CRS has verified each licensed watchstander meets qualification requirements.
- No-Solo restrictions do not apply.
Operator Shifts worked in 2020 Watch Position Operator #1 Day Shift: 3/24 through 3/26 Unit CRS Night Shift: 3/30 Operator #2 Night Shift: 3/30 through 4/3 Unit CRS Operator #3 Day Shift: 3/28 through 3/31 Reactor Operator LOT-ADM-JP-201-D13 Page 5 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES INITIATING CUE:
For Operator 1: Determine and circle whether the operators license is active or inactive as of April 4, 2020.
Active / Inactive For Operator 2: Determine and circle whether the operators license is active or inactive as of April 4, 2020.
Active / Inactive For Operator 3: Determine and circle whether the operators license has been properly activated as of April 4, 2020.
Active / Inactive LOT-ADM-JP-201-D13 Page 6 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
TIME START: ___________
NOTE: Sequence of the following actions is NOT critical.
Step 1 - Review data for Operator 1 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are met for Operator 1 (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> activation in the same calendar quarter.)
- CRITICAL STEP** SAT/UNSAT Step 2 - Review data for Operator 2 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are NOT met for Operator 2. (Five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts in the same calendar quarter; March 31 nightshift through April 3rd are NOT counted for maintaining license active since they span and exceed the calendar quarter.)
- CRITICAL STEP** SAT/UNSAT Step 3 - Review data for Operator 3 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are met for Operator 3. (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> watch standing time under instruction that is required for initial activation are met as of March 31.)
- CRITICAL STEP** SAT/UNSAT LOT-ADM-JP-201-D13 Page 7 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES TERMINATING CUE: When the examinee has completed a determination of Operator License status, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Critical Necessary to complete initiating cue.
2 Critical Necessary to complete initiating cue.
3 Critical Necessary to complete initiating cue.
LOT-ADM-JP-201-D13 Page 8 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. Correct Component Verification (CCV), Validate Assumptions
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. STAR (Use of Stop, Think, Act, Review) SAT/ UNSAT/ NE D. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE E. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
F. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
G. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
H. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
I. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE J. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-ADM-JP-201-D13 Page 9 of 12 Rev.02
EVALUATE STATUS OF OPERATOR LICENSES Validation Time: 20 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 0 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-ADM-JP-201-D13 Page 10 of 12 Rev.02
TASK CONDITIONS:
- 1. The following conditions apply for operators #1, #2, and #3:
- Operator #1: license was NOT active as of January 1st, 2020.
- Operator #2: license was active as of January 1st, 2020.
- Operator #3 is activating a new license.
- All required training is complete.
- Respirator qualifications are current.
- Emergency response organization qualifications are current.
- All required plant tours have been conducted by the Shift Manager within the required time frame.
- Shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts, including turnovers.
- When required, shifts were worked under the direction of an active license holder.
- The Unit CRS has verified each licensed watchstander meets qualification requirements.
- No-Solo restrictions do not apply.
Operator Shifts worked in 2020 Watch Position Operator #1 Day Shift: 3/24 through 3/26 Unit CRS Night Shift: 3/30 Operator #2 Night Shift: 3/30 through 4/3 Unit CRS Operator #3 Day Shift: 3/28 through 3/31 Reactor Operator Page 11 of 12
INITIATING CUE:
For Operator 1: Determine and circle whether the operators license is active or inactive as of April 4, 2020.
Active / Inactive For Operator 2: Determine and circle whether the operators license is active or inactive as of April 4, 2020.
Active / Inactive For Operator 3: Determine and circle whether the operators license has been properly activated as of April 4, 2020.
Active / Inactive Page 12 of 12
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM COO2 - 2020 NRC EXAM - RO LESSON TITLE: VERIFYING SLC OPERATING PARAMETERS LESSON NUMBER: AOT-ADM-JP-005-01 REVISION NO: 02 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER S. Hildebrandt VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE AOT-ADM-JP-005-01 Page 1 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS REVISION
SUMMARY
Rev. No. Summary Minor Rev. Date Signature 02 Added performance standard. NA NA Updated to new B-10 Atomic Enrichment numbers.
Updated related task 299601B204 to reflect deletion of 0OI-03.3 and inclusion of task guidance in eSOMS.
Made tank temperature UNSAT.
01 Formatting changes to match the JPM template, revision 3.
Changed numbers to make all parameters be within the acceptable range. Validated using 2OP-05 Standby Liquid Control Procedure revision 65.
Added Duke Energy Progress image to cover page.
Updated work practices to current plant expectations.
AOT-ADM-JP-005-01 Page 2 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS RELATED TASKS:
211602B104 - Determine SLC Tank Volume Manually Per OP-05 299601B204 - Perform Reactor Building Auxiliary Operator Daily Surveillance Report Per eSOMS, including all shifts and all mode checks.
K/A REFERENCE AND IMPORTANCE RATING:
211000 K5.06 - Knowledge of the operational implications of the tank level as it applies to SLC.
RO/SRO 3.0/3.2 Gen 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
RO/SRO 3.9/
4.2 REFERENCES
2OP-05 Standby Liquid Control System PERFORMANCE STANDARD Candidate will address SLC parameters given and determine SLC tank temperature is NOT in the required band per 2OP-05 Attachment 1, Normal Parameters. Candidate will address SLC tank concentration vs. level per 2OP-05 Attachment 2, and determine that the volume vs concentration is in the acceptable range. Candidate will address SLC tank temperature vs. SLC tank concentration per 2OP-05 attachment 3, and determine that the concentration vs. SLC tank temperature is acceptable.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Generic - Conduct of Operations SETUP INSTRUCTIONS None AOT-ADM-JP-005-01 Page 3 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS SAFETY CONSIDERATIONS:
- 1. None.
EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. The Unit Two SLC Tank normal level indication is out of service.
- 2. The distance from the surface of the liquid to the top of the tank is 70 inches.
- 3. The B-10 Atomic Enrichment is 92%.
- 4. Standby Liquid Control tank solution temperature (2-C41-TIC-R002) is 63°F.
- 5. The SLC Tank concentration is 8.7%
INITIATING CUE:
You are directed by the CRS to verify the following SLC parameters are within their normal standby limits. Inform the Control Room Supervisor of the results.
Parameter SAT UNSAT Sodium Pentaborate Solution Temperature-Concentration Requirement SLC Storage Tank temperature Sodium Pentaborate Solution Volume-Concentration Requirement AOT-ADM-JP-005-01 Page 4 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
Step 1 - Evaluate given data for SLC normal operating parameters using Attachments 1, 2, 3, and 4 from 2OP-05.
Evaluates the data.
SAT/UNSAT TIME START: ___________
Step 2 - Calculates using 2OP-05 Attachment 4 that the volume in the tank is ~2650 to 2700 gallons..
Calculates volume in the SLC tank as 2650-2700 gallons.
SAT/UNSAT Step 3 - Identifies that the temperature (tank 63° F) versus the concentration (8.7%) is within the acceptable range of Attachment 3 for the tank.
Identifies that for the temperature vs. concentration, is acceptable.
- CRITICAL STEP** SAT/UNSAT Step 4 - Identifies using Attachment 1 that the tank temperature is NOT within the operating range of 66-80°F.
Identifies that for the temperature is NOT acceptable.
- CRITICAL STEP** SAT/UNSAT Step 5 - Identifies that the volume (2650-2700 gallons) versus the concentration (8.7%) is within the acceptable range of Attachment 2 for the SLC system.
Identifies that for the volume vs. concentration, is acceptable.
- CRITICAL STEP** SAT/UNSAT Step 6 - Inform Control Room Supervisor of results of SLC parameters verification.
Control Room Supervisor informed of results.
SAT/UNSAT AOT-ADM-JP-005-01 Page 5 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS TERMINATING CUE: When SLC parameters verification has been competed, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Not Critical Not a critical parameter.
3 Critical Critical Parameter for task 4 Critical Critical Parameter for task 5 Critical Critical Parameter for task 6 Not Critical Communication AOT-ADM-JP-005-01 Page 6 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
AOT-ADM-JP-005-01 Page 7 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS Validation Time: 15 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
AOT-ADM-JP-005-01 Page 8 of 10 Rev.02
VERIFYING SLC OPERATING PARAMETERS
- EXAM KEY DO NOT GIVE TO STUDENT***
Parameter SAT UNSAT Sodium Pentaborate Solution Temperature-Concentration X Requirement SLC Storage Tank temperature X Sodium Pentaborate Solution Volume-Concentration X Requirement
- EXAM KEY DO NOT GIVE TO STUDENT***
AOT-ADM-JP-005-01 Page 9 of 10 Rev.02
TASK CONDITIONS:
- 1. The Unit Two SLC Tank normal level indication is out of service.
- 2. The distance from the surface of the liquid to the top of the tank is 70 inches.
- 3. The B-10 Atomic Enrichment is 92%.
- 4. Standby Liquid Control tank solution temperature (2-C41-TIC-R002) is 63°F.
- 5. The SLC Tank concentration is 8.7%
INITIATING CUE:
You are directed by the CRS to verify the following SLC parameters are within their normal standby limits. Inform the Control Room Supervisor of the results.
Parameter SAT UNSAT Sodium Pentaborate Solution Temperature-Concentration Requirement SLC Storage Tank temperature Sodium Pentaborate Solution Volume-Concentration Requirement Page 10 of 10
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM EC 2020 NRC EXAM - RO LESSON TITLE: DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B LESSON NUMBER: LOT-ADM-JP-201-E06 REVISION NO: 00 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER B. Layton 08/20/20 VALIDATOR / DATE S. Hildebrandt 08/20/20 VALIDATOR / DATE Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE LOT-ADM-JP-201-E06 Page 1 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B REVISION
SUMMARY
Rev. No. Revision Summary Minor Rev. Date Signature 0 New JPM written on the 2B RBCCW Pump. NA NA (modified from LOT-ADM-JP-201-E05)
LOT-ADM-JP-201-E06 Page 2 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B RELATED TASKS:
299020B301 Develop a Clearance Per AD-OP-ALL-0200, Clearance and Tagging K/A REFERENCE AND IMPORTANCE RATING:
Gen 2.2.13 Knowledge of tagging and clearance procedures (4.1/4.3)
REFERENCES:
AD-OP-ALL-0200 2OP-21 D-02538, Sheet 1,2 & 3 LL-09242, Sheet 24 PERFORMANCE STANDARD:
Candidate will use 2OP-21, AD-OP-ALL-0200, Clearance and Tagging and provided prints to determine adequate isolation boundary for the 2B RBCCW pump. Sequence must have the breaker first, the discharge and suction valves second and third, Drain valve(s) fourth and fifth, and vent valve last. If the control switch is included it must be before the breaker.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin - Equipment Control SETUP INSTRUCTIONS None LOT-ADM-JP-201-E06 Page 3 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B SAFETY CONSIDERATIONS:
- 2. Determine actual radiological conditions and potentially contaminated areas to achieve ALARA.
- 3. Ensure all electrical safety requirements are observed.
- 4. Review Work Practices section prior to conduct of the JPM.
- 5. DO NOT OPERATE any plant equipment during performance of this JPM.
EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM will be performed Unit 2.
- 4. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 5. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury Read the following to the JPM performer.
TASK CONDITIONS:
- 1. You are an operator in the Work Control Center. eSOMS is off-line. No historical clearances are available for review.
- 2. A Clearance has been requested by maintenance to place RBCCW Pump 2B under clearance for pump packing replacement.
- 3. RBCCW Pumps 2A and 2C will remain running.
- 4. Hanging the clearance will not result in any radiation dose.
- 5. The next available serial number is 20-0020.
INITIATING CUE:
You are directed to propose a Clearance Boundary for RBCCW Pump 2B by completing 2 page 2 of AD-OP-ALL-0200, Clearance and Tagging. Clearance removal will be developed by another operator.
LOT-ADM-JP-201-E06 Page 4 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B ANSWER KEY Do Not Provide to Trainee Note: Serial Numbers will change depending if No Tag is used.
Sequence must have the breaker first, the discharge and suction valve second and third, Drain valve(s) fourth and fifth, and vent valve last. If the control switch is included it must be before the breaker.
Minimum requirements for satisfactory boundary are breaker, discharge valve, suction valve, at least one drain valve, and vent valve.
Exact nomenclature, location, and serial number are not critical.
DO NOT PROVIDE KEY TO TRAINEE LOT-ADM-JP-201-E06 Page 5 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
NOTE: The examiner should provide a copy AD-OP-ALL-0200 and two blank copies of Attachment 22 page 2 of AD-OP-ALL-0200 to the examinee.
NOTE: The examiner should provide a copy of the required prints to the examinee (D-02538, Sheets 1,2& 3, LL-9242 Sheet 24).
TIME START: ___________
NOTE: CITs can have position OFF or In-Place / HUNG Step 1 - Identify control switch 2-RCC-CS-448 should be placed to OFF Determine 2-RCC-CS-448 should be placed to OFF.
SAT/UNSAT Step 2 - Identify breaker 2XF Compt ED7 should be DANGER tagged to OPEN/OFF/OFF-LOCKED.
Determine 2XF Compt ED7 should be DANGER tagged to OPEN, OFF or OFF/LOCKED.
- CRITICAL STEP** SAT/UNSAT NOTE: Sequence of suction or discharge valve closing is not critical so long as the pump motor is de-energized.
Step 3 - Identify discharge valve 2-RCC-V36 should be RED tagged closed.
Determine 2-RCC-V36 should be RED tagged closed.
- CRITICAL STEP** SAT/UNSAT Step 4 - Identify suction valve 2-RCC-V31 should be RED tagged closed.
Determine 2-RCC-V31 should be RED tagged closed.
- CRITICAL STEP** SAT/UNSAT LOT-ADM-JP-201-E06 Page 6 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B NOTE: Either 2-RCC-V133 or 2-RCC-V134 is critical. Both are not required to meet critical task standards.
NOTE: The vent valve is sequenced last.
Step 5 - Identify drain valve 2-RCC-V134 should be open.
Determine 2-RCC-V134 should be open.
- CRITICAL STEP** SAT/UNSAT Step 6 - Identify drain valve 2-RCC-V133 should be open.
Determine 2-RCC-V133 should be open.
- CRITICAL STEP** SAT/UNSAT Step 7 - Identify vent valve 2-RCC-V302 should be open.
Determine 2-RCC-V302 should be open.
- CRITICAL STEP** SAT/UNSAT NOTE: IV is not critical for CIT.
Step 8 - Identifies that Independent Verification is required.
Determine verification required for clearance steps.
SAT/UNSAT Step 9 - Submit proposed boundary to WCC SRO.
Proposed boundary submitted to WCC SRO.
SAT/UNSAT TERMINATING CUE: When the clearance boundary has been submitted, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
LOT-ADM-JP-201-E06 Page 7 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B Step Critical / Not Critical Reason 1 Not Critical Not an energy isolation point.
2 Critical Required energy isolation point.
3 Critical Required energy isolation point.
4 Critical Required energy isolation point.
5 Critical Required energy isolation point.
6 Critical Required energy isolation point.
7 Critical Required energy isolation point.
8 Not Critical Not an energy isolation point.
9 Not Critical Administrative LOT-ADM-JP-201-E06 Page 8 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-ADM-JP-201-E06 Page 9 of 12 Rev.0
DEVELOP A CLEARANCE BOUNDARY - RBCCW PUMP 2B Validation Time: 35 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-ADM-JP-201-E06 Page 10 of 12 Rev.0
TASK CONDITIONS:
- 1. You are an operator in the Work Control Center. eSOMS is off-line. No historical clearances are available for review.
- 2. A Clearance has been requested by maintenance to place RBCCW Pump 2B under clearance for pump packing replacement.
- 3. RBCCW Pumps 2A and 2C will remain running.
- 4. Hanging the clearance will not result in any radiation dose.
- 5. The next available serial number is 20-0020.
INITIATING CUE:
You are directed to propose a Clearance Boundary for RBCCW Pump 2B by completing 2 page 2 of AD-OP-ALL-0200, Clearance and Tagging. Clearance removal will be developed by another operator.
Page 11 of 12
Page 12 of 12 DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM RC 2020 NRC EXAM - RO LESSON TITLE: Determine Stay Time Limitations in High Radiation Areas LESSON NUMBER: LOT-ADM-JP-102-A03 REVISION NO: 04 Steve Cotton PREPARER Bob Bolin TECHNICAL REVIEWER S. Hildebrandt 08/20/20 VALIDATOR / DATE Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Determine Stay Time Limitations in High Radiation Areas REVISION
SUMMARY
Rev. No. Revision Summary Minor Rev. Signature Date 04 Updated to new format. NA NA 3a Minor revision. Added performance S. COTTON 08/15/19 standard.
LOT-ADM-JP-102-A03 Page 2 of 9 Rev 04
Determine Stay Time Limitations in High Radiation Areas RELATED TASKS:
None K/A REFERENCE AND IMPORTANCE RATING:
Generic 2.3.4 3.2/3.7 Knowledge of Radiation Exposure Limits under normal or emergency conditions Generic 2.3.7 3.5/3/6 Ability to comply with radiation work permit requirements during normal and abnormal conditions
REFERENCES:
PD-RP-ALL-0001, Radiation Worker Responsibilities PERFORMANCE STANDARD:
Examinee will determine the total dose accumulated for each worker is ~602.2 mrem and determines that the Duke Fleet administrative dose limits will not be exceeded.
TOOLS AND EQUIPMENT:
Calculator Radiation Survey Map of 50 Reactor Building SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
A.3 Radiation Control SETUP INSTRUCTIONS None LOT-ADM-JP-102-A03 Page 3 of 9 Rev 04
Determine Stay Time Limitations in High Radiation Areas SAFETY CONSIDERATIONS:
- 1. None EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM may be performed on Unit 1 or Unit 2 as selected by the evaluator. Survey map must reflect correct unit.
- 4. Critical Step Basis a) Prevents Task Completion b) May Result in Equipment Damage c) Affects Public Health and Safety d) Could Result in Personal Injury Read the following to the JPM performer.
TASK CONDITIONS:
Two trained radiation workers will be performing a lube check and coupling alignment on the Unit 2 RWCU Pump 2A.
Worker #1 has accumulated 300 mrem this year.
Worker #2 has accumulated 970 mrem this year.
Neither worker is a declared pregnant worker.
The elevator is out of service The following times for each worker have been estimated for performance of the job.
- 1. Traversing Southeast stairwell 20 - 50 Rx Bldg: 6 minutes
- 2. Staging time in access area directly outside the RWCU room: 45 minutes
- 3. Staging time in area directly inside room access door: 20 minutes
- 4. Work time at the A RWCU pump: 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- 5. Following completion of the job, an additional 60 mrem per worker will be received during de-staging activities and transit back to the maintenance shop.
INITIATING CUE:
Using the information above and the provided radiological survey using best ALARA practices:
- 1. Determine the total dose accumulated for each worker. (Assume the same task times for both workers).
- 2. Determine if the Duke Fleet administrative dose limits will be exceeded without an extension.
LOT-ADM-JP-102-A03 Page 4 of 9 Rev 04
Determine Stay Time Limitations in High Radiation Areas PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
TIME START ___________
Step 1 - Determines dose for each worker as follows:
(6 min) 0.1 Hr X 5 mr/hr = 0.5 mrem Estimate 0.5 mrem dose accumulation
- CRITICAL STEP** SAT/UNSAT
- b. Staging time in access area directly outside the RWCU room (45 min) 0.75 Hr X 20 mr/hr = 15 mrem Estimate 15 mrem dose accumulation
- CRITICAL STEP** SAT/UNSAT
- c. Staging time in area directly inside room access door (20 min) 0.33 Hr X 80 mr/hr = 26.7 mrem Estimates dose accumulation within the acceptable range of 26 to 27 mrem.
- CRITICAL STEP** SAT/UNSAT
- d. Work time at the A RWCU pump 2.5 Hrs X 200 mr/hr = 500 mrem Estimate 500 millirem dose accumulation
- CRITICAL STEP** SAT/UNSAT NOTE: An additional 60 mr will be accumulated once the job is done for de-staging activities.
- e. Total = 0.5 + 15 + 26.7 + 500 + 60 = 602.2 mrem.
Determines Total to be within the acceptable range of 601 to 603 mrem
- CRITICAL STEP** SAT/UNSAT LOT-ADM-JP-102-A03 Page 5 of 9 Rev 04
Determine Stay Time Limitations in High Radiation Areas Step 2 - Determines that neither worker would exceed the Brunswick administrative limit of 2 REM per calendar year if the estimated dose were accumulated.
Worker #1: 300 mr + 602.2 mr = 902.2 mr (< 2R limit).
Acceptable range 901 to 903 mr Worker #2: 970 mr + 602.2 mr = 1572.2 mr (< 2R limit).
Acceptable range 1571 to 1573 mr
- CRITICAL STEP** SAT/UNSAT TERMINATING CUE: When the total dose for each worker has been determined and the administrative limits addressed, the JPM is complete.
TIME COMPLETED:
NOTE: Comments required for any step evaluated as UNSAT.
Step Critical / Not Critical Reason 1a Critical Each calculation is critical to determine total dose for personnel safety.
1b Critical Each calculation is critical to determine total dose.
1c Critical Each calculation is critical to determine total dose.
1d Critical Each calculation is critical to determine total dose.
1e Critical Each calculation is critical to determine total dose.
2 Critical Total calculation and knowledge of Admin Dose Limit is required to complete JPM.
LOT-ADM-JP-102-A03 Page 6 of 9 Rev 04
Determine Stay Time Limitations in High Radiation Areas Validation Time: 15 Minutes (approximate)
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-ADM-JP-102-A03 Page 7 of 9 Rev 04
TASK CONDITIONS:
Two trained radiation workers will be performing a lube check and coupling alignment on the Unit 2 RWCU Pump 2A.
Worker #1 has accumulated 300 mrem this year.
Worker #2 has accumulated 970 mrem this year.
Neither worker is a declared pregnant worker.
The elevator is out of service The following times for each worker have been estimated for performance of the job.
- 1. Traversing Southeast stairwell 20 - 50 Rx Bldg: 6 minutes
- 2. Staging time in access area directly outside the RWCU room: 45 minutes
- 3. Staging time in area directly inside room access door: 20 minutes
- 4. Work time at the A RWCU pump: 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- 5. Following completion of the job, an additional 60 mrem per worker will be received during de-staging activities and transit back to the maintenance shop.
INITIATING CUE:
Using the information above and the provided radiological survey using best ALARA practices:
- 1. Determine the total dose accumulated for each worker. (Assume the same task times for each worker).
- 2. Determine if the Duke Fleet administrative dose limits will be exceeded without an extension.
Results:
Page 8 of 9
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM COO1 - 2020 NRC INITIAL EXAM - SRO LESSON TITLE: Evaluate Level Instrument Operability LESSON NUMBER: SOT-ADM-JP-307-C01 REVISION NO: 03 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER M. Long 08/20/20 VALIDATOR DATE Rob Mehs 9/15/20 LINE APPROVAL DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL DATE
Evaluate Level Instrument Operability.
REVISION
SUMMARY
Rev. No. Revision Summary Minor Rev. Date Signature 02 Added performance standard. NA NA Updated JPM to match changes to 0GP-14.
Changed a comparison value to be out of spec SOT-ADM-JP-307-C01 Page 2 of 16 Rev. 03
Evaluate Level Instrument Operability.
RELATED TASKS:
341010B302, Review Daily Surveillance Reports And Daily Check Sheets For Trends And Out Of Spec Conditions per 0OI-1.02.
341224B102, Determine Actions Required For Limiting Conditions For Operation per OI-01.08 and Technical Specifications K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.7 4.4/4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior , and instrument interpretation.
REFERENCES:
GP-14 Technical Specifications OI-18 PERFORMANCE STANDARD:
Candidate will review 0GP-14 attachment 2, Reactor Vessel Water Level channel checks and determines that the B21-LTM-N031B-1 is reading out of specification Low and that the comparison check is out of limits. Candidate will then determine that TSs 3.3.5.1 and 3.3.5.2 must be entered and that the B21-LTM-N031B-1 must be placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per TS 3.3.5.1 (most limiting)
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123):
A.1, Conduct Of Operations SETUP INSTRUCTIONS None SOT-ADM-JP-307-C01 Page 3 of 16 Rev. 03
Evaluate Level Instrument Operability.
Special Instructions Obtain current revision of GP-14, Attachment 2, Reactor Vessel Water Level Channel Checks. Fill in the following data:
Page 1 of 4 Item 1 190 Item 2 195 Item 3 175 Item 4 180 Item 5 5 inches Item 6 5 inches Page 2 of 4 Item 7 190 Item 8 185 Item 9 165 Item 10 175 Item 11 5 inches Item 12 5 inches Page 3 of 4 Item 13 195 Item 14 185 Item 15 170 Item 16 180 Item 17 10 inches Item 18 10 inches Page 4 of 4 Item 19 +125 Item 20 +150 SOT-ADM-JP-307-C01 Page 4 of 16 Rev. 03
Evaluate Level Instrument Operability.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Provide examinee with completed copy of GP-14, along with the completed data from Attachment 2. Ensure examinee has access to Technical Specifications.
- 3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
- 1. Unit Two is operating (Mode 1) in Extended Single Recirculation Loop Operation per GP-14. Recirculation Loop 2A is out of service.
- 2. A Reactor Operator has completed GP-14, Attachment 2, Reactor Vessel Water Level Channel Checks.
INITIATING CUE:
You are directed to perform the SRO Review of the completed GP-14, Attachment 2 and determine required Tech Spec action(s) for inoperable instrumentation (if any).
SOT-ADM-JP-307-C01 Page 5 of 16 Rev. 03
Evaluate Level Instrument Operability.
PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of GP-14.
Current Revision of GP-14 obtained.
SAT/UNSAT*
NOTE: Sequence of the following actions is NOT critical.
START TIME:
Step 2 - Review data for Level Instruments N024A-1-1, N024B-1-1 and determine acceptance criteria are met.
Determined that acceptance criteria are met for N024A-1-1 and N024B-1-1.
SAT/UNSAT*
Step 3 - Review data for Level Instruments N025A-1-1, N025B-1-1 and determine acceptance criteria are met.
Determined that acceptance criteria are met for N025A-1-1 and N025B-1-1.
SAT/UNSAT*
Step 4 - Review data for Level Instruments N031A-1, N031C-1 and determine acceptance criteria are met.
Determined that acceptance criteria are met for N031A-1 and N031C-1.
SAT/UNSAT*
Step 5a - Review data for Level Instruments N031B-1, N031D-1 and determine comparison value entered for item 12 is incorrect.
Determined that Item 12 should be 10 inches (not 5 inches)
SAT/UNSAT*
SOT-ADM-JP-307-C01 Page 6 of 16 Rev. 03
Evaluate Level Instrument Operability.
Step 5b - Review data for Level Instruments N031B-1, N031D-1 and determine acceptance criteria are NOT met.
Determined that N031B-1 is reading below TS/Oper Limit and channel check criteria is not met.
- CRITICAL STEP ** SAT/UNSAT*
Step 6 - Review data for Level Instruments N024A-2, N024B-2 and determine acceptance criteria are met.
Determined that acceptance criteria are met for N024A-2 and N024B-2.
SAT/UNSAT*
Step 7 - Review data for Level Instruments N025A-2, N025B-2 and determine acceptance criteria are met.
Determined that acceptance criteria are met for N025A-2 and N025B-2.
SAT/UNSAT*
Step 8 - Review data for Level Instruments N036-1, N037-1 and determine acceptance criteria is met.
Determined that acceptance criteria is met for N036-1 and N037-1.
SAT/UNSAT*
Step 9 - Declare Level Instrument N031B-1 Inoperable.
Level Instrument N031B-1 is declared Inoperable.
- CRITICAL STEP ** SAT/UNSAT*
Step 10 - Determine N031B-1 is required to comply with LCO 3.3.5.1 for Functions 1.a, 2.a, 3.a, 4.a and 5.a and LCO 3.3.5.2, Function 1.
Determined that N031B-1 is required to comply with LCO 3.3.5.1 for Functions 1.a, 2.a, 3.a, 4.a and 5.a and LCO 3.3.5.2, Function 1 SAT/UNSAT*
SOT-ADM-JP-307-C01 Page 7 of 16 Rev. 03
Evaluate Level Instrument Operability.
Step 11 - Determine LCO 3.3.5.1 and LCO 3.3.5.2, Action A requires entering Condition referenced by Table immediately (3.3.5.1 Condition B for Function 1.a, 2.a, and 3.a, and Condition E for Functions 4.a, and 5.a, 3.3.5.2 Condition B for Function 1)
Determine LCO 3.3.5.1 and LCO 3.3.5.2, Action A requires entering Condition referenced by Table immediately (3.3.5.1 Condition B for Function 1.a, 2.a, and 3.a, and Condition E for Functions 4.a, and 5.a, 3.3.5.2 Condition B for Function 1)
SAT/UNSAT*
NOTE: LCO 3.3.5.1, Action B1 and B2 are not required. LCO 3.3.5.1 Action E1 is not required; LCO 3.3.5.2, Action B1 is not required.
LCO 3.3.5.1, Actions B3 and E2 are required (the 8 days completion time applies to Action E2); and LCO 3.3.5.2, Action B2 is required.
It is critical the examinee determines the channel must be placed in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Step 12 - Determine LCO 3.3.5.1, Condition B and LCO 3.3.5.2, Condition B requires placing the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and LCO 3.3.5.1 Condition E requires placing the channel in trip in 8 days.
Determines the channel must be placed in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- CRITICAL STEP ** SAT/UNSAT*
TERMINATING CUE: When the examinee has completed review of GP-14, attachment 2 and Technical Specifications, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
SOT-ADM-JP-307-C01 Page 8 of 16 Rev. 03
Evaluate Level Instrument Operability.
Step Critical / Not Critical Reason 1 Not Critical Not necessary to complete initiating cue.
2 Critical Not necessary to complete initiating cue 3 Critical Not necessary to complete initiating cue.
4 Not Critical Not necessary to complete initiating cue 5a Not Critical Sub step of determining tech spec action, which is critical.
5b Critical Necessary to complete initiating cue.
6 Not Critical Not necessary to complete initiating cue 7 Not Critical Not necessary to complete initiating cue 8 Not Critical Not necessary to complete initiating cue 9 Critical Necessary to complete initiating cue.
10 Not Critical Not necessary to complete initiating cue 11 Not Critical Not necessary to complete initiating cue 12 Critical Necessary to complete initiating cue SOT-ADM-JP-307-C01 Page 9 of 16 Rev. 03
Evaluate Level Instrument Operability.
WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
SOT-ADM-JP-307-C01 Page 10 of 16 Rev. 03
Evaluate Level Instrument Operability.
Validation Time: 20 Minutes Time Taken: Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator N/A Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Trainee:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
SOT-ADM-JP-307-C01 Page 11 of 16 Rev. 03
TASK CONDITIONS:
- 1. Unit Two is operating (Mode 1) in Extended Single Recirculation Loop Operation per GP-14. Recirculation Loop 2A is out of service.
- 2. A Reactor Operator has completed GP-14, Attachment 2, Reactor Vessel Water Level Channel Checks.
INITIATING CUE:
You are directed to perform the SRO Review of the completed GP-14, Attachment 2 and determine required Tech Spec action(s) for inoperable instrumentation (if any).
Page 12 of 16
Page 13 of 16 Page 14 of 16 Page 15 of 16 Page 16 of 16 DUKE ENERGY PROGRESS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM COO 2020 NRC EXAM - SRO LESSON TITLE: Evaluate Partial View Of Core For Correct Core Loading LESSON NUMBER: SOT-ADM-JP-305-C01 REVISION NO: 01a Developer: Steve Cotton Technical Review: Robert Bolin Validator: J. Morrow Line Supervisor: J. Morrow Date: 07/31/19 Training Supervisor: Ed Rau Date: 08/05/19 SOT-ADM-JP-305-C01 Page 1 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading REVISION
SUMMARY
REV. REVISION
SUMMARY
MINOR REV SIG DATE 01a Updated to correct typographical errors, modify revision table format.
01 Changed Fuel Bundle Designators. Corrected NA NA Typographical errors. Added performance standard. Revised to new template.
RELATED TASKS:
234001B102, Verify proper fuel assembly orientation and seating in the Reactor per ENP-24.13 K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.42 2.5/3.4 Knowledge of new and spent fuel movement procedures
REFERENCES:
0ENP 24.12 0ENP-24.13 FH-11 PERFORMANCE STANDARD:
Examinee will identify that bundle LYJ568 (Step 3 of the Core Component Sequence Sheets) is not loaded in the correct location, identify that bundle LYJ468 (Step 5 of the Core Component Sequence Sheets) is not loaded in the correct location, and identify that bundle LYJ549 (Step 8 of the Core Component Sequence Sheets) is loaded in the incorrect orientation .
TOOLS AND EQUIPMENT:
None ADMINISTRATIVE CATEGORY (from NUREG 1123, Rev. 2, Supp. 1):
Conduct of Operations SOT-ADM-JP-305-C01 Page 2 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading SAFETY CONSIDERATIONS:
- 1. Perform Take-A-Minute actions to review any Safety concerns.
EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. This JPM will be performed on Unit 2.
- 4. Provide examinee with copy of prepared partial core view, prepared Core Component Sequence Sheet, and Reactor Vessel Core Map (ENP-24.12, Figure 1).
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. Unit 2 is in Mode 5. Core reload has just been completed.
- 2. You have a partial view of the reloaded core, along with the Core Component Sequence Sheets for those bundles, and Reactor Vessel Core Map (ENP-24.12, Figure 1).
INITIATING CUE:
You are directed by the Shift Manager to evaluate the partial core loading for core verification and inform the Shift Manager of the results.
SOT-ADM-JP-305-C01 Page 3 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.
TIME START:
Step 1 - Evaluate partial Core View, Core Component Sequence Sheets for those bundles, and Figure 1 from ENP-24.12, Reactor Vessel Core Map.
Partial Core View, Core Component Sequence Sheets for those bundles, and Figure 1 from ENP-24.12, Reactor Vessel Core Map evaluated.
SAT/UNSAT NOTE: It is critical that the examinee identifies the two bundles incorrectly loaded. It is NOT critical the examinee identifies the locations are swapped.
Step 2 - Identify that bundle LYJ568 (Step 3 of the Core Component Sequence Sheets) is specified for location 9-10 but bundle LYJ468 is loaded in that location.
Identify that bundle LYJ568 (Step 3 of the Core Component Sequence Sheets) is not loaded in the correct location.
- CRITICAL STEP ** SAT/UNSAT Step 3 - Identify that bundle LYJ468 (Step 5 of the Core Component Sequence Sheets) is specified for location 13-10 but bundle LYJ568 is loaded in that location.
Identify that bundle LYJ468 (Step 5 of the Core Component Sequence Sheets) is not loaded in the correct location.
- CRITICAL STEP ** SAT/UNSAT SOT-ADM-JP-305-C01 Page 4 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading Step 4 - Identify that bundle LYJ549 (Step 8 of the Core Component Sequence Sheets) is loaded in the incorrect orientation and that the Fastener location should be Southeast (as specified on the Core Component Sequence Sheets and not Northwest as shown in the partial core view (or that the bundle is rotated 180°).
Identify that bundle LYJ549 (Step 8 of the Core Component Sequence Sheets) is loaded in the incorrect orientation.
- CRITICAL STEP ** SAT/UNSAT NOTE: All other bundles are correctly loaded.
Step 5 - Identifies all other bundles are correctly loaded.
Identifies all other bundles are correctly loaded.
SAT/UNSAT Step 6 - Inform Shift Manager of results of partial core verification.
Shift Manager informed of results of partial core verification.
SAT/UNSAT TERMINATING CUE: When evaluation of the partial core load has been completed and the Shift Manager has been informed of the results, this JPM is complete.
TIME COMPLETED:
NOTE: Comments required for any step evaluated as UNSAT.
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
SOT-ADM-JP-305-C01 Page 5 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute / Two Minute Rule
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE SAF-NGGC-2175, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
SOT-ADM-JP-305-C01 Page 6 of 11 Rev. 01a
Evaluate Partial View Of Core For Correct Core Loading Validation Time: 10 Minutes (approximate)
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
SOT-ADM-JP-305-C01 Page 7 of 11 Rev. 01a
Page 8 of 11 Page 9 of 11 Page 10 of 11 TASK CONDITIONS:
- 1. Unit 2 is in Mode 5. Core reload has just been completed.
- 2. You have a partial view of the reloaded core, along with the Core Component Sequence Sheets for those bundles, and Reactor Vessel Core Map (ENP-24.12, Figure 1).
INITIATING CUE:
You are directed by the Shift Manager to evaluate the partial core loading for core verification and inform the Shift Manager of the results.
Page 11 of 11
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM EC - 2020 NRC EXAM - SRO LESSON TITLE: Determine Post Maintenance Testing Requirements LESSON NUMBER: LOT-OJT-JP-201-E-06 REVISION NO: 00 S. Cotton PREPARER Bob Bolin TECHNICAL REVIEWER Brian West 06/18/20 VALIDATOR / DATE M. Long 08/20/20 VALIDATOR/DATE Rob Mehs 9/15/20 LINE APPROVAL / DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL / DATE
Determine Post Maintenance Testing Requirements REVISION
SUMMARY
Rev. Revision Summary Minor Rev. Date No. Signature 00 JPM developed for NRC Exam 2020. NA NA LOT-OJT-JP-201-E-06 Page 2 of 12 Rev.0
Determine Post Maintenance Testing Requirements RELATED TASKS:
342013B302 Determine PMT Requirements Following Maintenance Activities per 0PLP-20 and AD-WC-ALL-0250 K/A REFERENCE AND IMPORTANCE RATING:
Generic 2.2.21 Knowledge of pre- and post-maintenance operability requirements.
4.1 REFERENCES
0PLP-20, Post-Maintenance Testing Program 0PT-34.2.2.1, Fire Door, Pressure Boundary Door, and ASSD Access/Egress Door Inspections PERFORMANCE STANDARD:
Candidate will refer to 0PT-34.2.2.1and 0PLP-20 to determine post maintenance testing requirements of Unit One reactor building door 205. Candidate will determine visual inspection of the door is required.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
3 - Equipment Control SETUP INSTRUCTIONS None LOT-OJT-JP-201-E-06 Page 3 of 12 Rev.0
Determine Post Maintenance Testing Requirements SAFETY CONSIDERATIONS:
- 1. None.
EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 3. This JPM may be administered in the simulator, control room, or classroom setting.
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. Maintenance is being planned for the Unit One Reactor Building ECCS pipe tunnel north door (1-RB1-DR-EL020-205).
INITIATING CUE:
You are directed to determine the Post Maintenance Test Procedure section(s) (if any) which must be performed for the Unit One Reactor Building ECCS pipe tunnel north door (1-RB1-DR-EL020-205).
LOT-OJT-JP-201-E-06 Page 4 of 12 Rev.0
Determine Post Maintenance Testing Requirements PERFORMANCE CHECKLIST NOTE: Sequence is not essential to completing the task, comments required for any step evaluated as UNSAT.
TIME START: ___________
Step 1 - Obtain a copy of 0PLP-20 and 0PT-34.2.2.1.
Obtains a copy of 0PLP-20 and 0PT-34.2.2.1.
Note: Either or both procedures may be obtained at this time. However, both procedures will need to be referenced to determine PMT requirements.
SAT/UNSAT Step 2 - References 0PT-34.2.2.1 section 7.3 and determines 1-RB1-DR-EL020-205 is a fire door.
References determines that the 1-RB1-DR-EL020-205 is a fire door .
- CRITICAL STEP**SAT/UNSAT Step 3 - References 0PLP-20 Attachment 2.
Identifies that tests 12 and 14 are applicable.
SAT/UNSAT Step 4- Identifies from Attachment 2 that test 12 is NOT required.
Identifies that the following Test 12 determined NOT to be required due to 1-RB1-DR-EL020-205 not being a pressure boundary door.
SAT/UNSAT Step 5 - Identifies from Attachment 2 that test 14 only is required.
Identifies that the following:
Test 14 Performance of visual inspection determined to be required per 0PT-34.2.2.1
- CRITICAL STEP** SAT/UNSAT LOT-OJT-JP-201-E-06 Page 5 of 12 Rev.0
Determine Post Maintenance Testing Requirements TERMINATING CUE: Termination criteria in cue: Determine adequacy of PMT, and list PMT requirements.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Critical Necessary to complete performance.
3 Not Critical Not Necessary to complete performance.
4 Not Critical Not necessary to complete performance 5 Critical Determination that the visual inspection of 0OPT-34.2.2.1 is required to complete performance.
LOT-OJT-JP-201-E-06 Page 6 of 12 Rev.0
Determine Post Maintenance Testing Requirements
- EXAM KEY DO NOT DISTRIBUTE***********************
- EXAM KEY DO NOT DISTRIBUTE***********************
LOT-OJT-JP-201-E-06 Page 7 of 12 Rev.0
Determine Post Maintenance Testing Requirements
- EXAM KEY DO NOT DISTRIBUTE***********************
- EXAM KEY DO NOT DISTRIBUTE***********************
LOT-OJT-JP-201-E-06 Page 8 of 12 Rev.0
Determine Post Maintenance Testing Requirements
- EXAM KEY DO NOT DISTRIBUTE***************************
- EXAM KEY DO NOT DISTRIBUTE***************************
LOT-OJT-JP-201-E-06 Page 9 of 12 Rev.0
Determine Post Maintenance Testing Requirements WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
LOT-OJT-JP-201-E-06 Page 10 of 12 Rev.0
Determine Post Maintenance Testing Requirements Validation Time: 10 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: N/A Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-OJT-JP-201-E-06 Page 11 of 12 Rev.0
TASK CONDITIONS:
- 1. Maintenance is being planned for the Unit One Reactor Building ECCS pipe tunnel north door (1-RB1-DR-EL020-205).
INITIATING CUE:
You are directed to determine the Post Maintenance Test Procedure section(s) (if any) which must be performed for the Unit One Reactor Building ECCS pipe tunnel north door (1-RB1-DR-EL020-205).
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DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM RC - 2020 NRC EXAM - SRO LESSON TITLE: Determine Authorization Requirements For Protection Of Property LESSON NUMBER: LOT-ADM-JP-102-A05 REVISION NO: 01 S. Cotton PREPARER / DATE Bob Bolin TECHNICAL REVIEWER / DATE M. Long 08/20/20 VALIDATOR DATE Rob Mehs 9/15/20 LINE APPROVAL DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL DATE
Determine Authorization Requirements For Protection Of Property REVISION
SUMMARY
Rev. No. Revision Summary Minor Rev. Date Signature 01 Added performance standard. Updated JPM to new NA NA format. Corrected position title to Shift Manager Emergency Coordinator to align with revision to AD-EP-ALL-0205 Emergency Exposure Controls. Changed K/A to 2.3.04 0 New JPM. NA NA LOT-ADM-JP-102-A05 Page 2 of 8 Rev. 01
Determine Authorization Requirements For Protection Of Property RELATED TASKS:
None K/A REFERENCE AND IMPORTANCE RATING:
Gen 2.3.4 3.2/3.7 Knowledge of radiation exposure limits under normal or emergency conditions
REFERENCES:
None PERFORMANCE STANDARD:
Examinee calculates total dose is 7 rem, which is less than the limit for protecting valuable property, determines that the Shift Manager must authorize, and it is NOT allowed to be verbally authorized.
TOOLS AND EQUIPMENT:
Examinee may use calculator SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Administrative Topic - Radiation Control SETUP INSTRUCTIONS None LOT-ADM-JP-102-A05 Page 3 of 8 Rev. 01
Determine Authorization Requirements For Protection Of Property SAFETY CONSIDERATIONS:
- 1. None EVALUATOR NOTES: (Do not read to performer)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
Read the following to the JPM performer.
TASK CONDITIONS:
- 1. A Site Area Emergency has been declared.
- 2. The TSC has NOT been activated.
- 3. An accident has occurred on Unit Two and a drywell entry is required to protect valuable equipment.
- 4. The job and radiation conditions in the drywell are detailed below:
Time Dose Rate Travel path in 12 min 10 R/hr Perform task 30 min 6 R/hr Travel path out 12 min 10 R/hr INITIATING CUE:
Determine the following:
- 1. Who is required to authorize exposure for protection of valuable property.
- 2. Calculate the Total Dose.
- 3. Determine whether the projected total dose is less than or greater than the dose limit for protection of valuable property.
- 4. Determine whether the authorization is or is NOT allowed to be approved verbally.
LOT-ADM-JP-102-A05 Page 4 of 8 Rev. 01
Determine Authorization Requirements For Protection Of Property PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
TIME START: ___________
NOTE: Sequence is not necessary.
Step 1 - Travel path dose to job calculated by converting minutes to fraction of an hour and multiplying by dose rate.
Calculates dose for travel path to job, by calculating 12 min / 60 min x 10R/hr.
- Determines dose to be 2 Rem for travel to job**.
SAT/UNSAT Step 2 -Dose to isolate valve calculated by converting minutes to fraction of an hour and multiplying by dose rate.
Calculates dose to isolate valve, by calculating 30 min / 60 min x 6R/hr.
- Determines dose to be 3 Rem to isolate valve **.
SAT/UNSAT Step 3 - Travel out of drywell dose calculated by converting minutes to fraction of an hour and multiplying by dose rate.
Calculates travel out of drywell dose, by calculating 12 min / 60 min x 10R/hr.
- Determines dose to be 2 Rem for travel to job**.
SAT/UNSAT Step 4 - Total dose calculated by adding dose for travel to job, isolation of valve, and travel out of drywell.
Calculates total dose, by adding 2R from step 1 + 3R from step 2 + 2R from step
- 3. **Determines total dose to be 7 Rem**.
Step 5 - Total dose determined to exceed 5 Rem but less than 10 Rem to protect valuable property.
Determines total dose is less than 10 Rem to protect valuable property.
- CRITICAL STEP** SAT/UNSAT LOT-ADM-JP-102-A05 Page 5 of 8 Rev. 01
Determine Authorization Requirements For Protection Of Property NOTE: IAW AD-EP-ALL-0205, Emergency Exposure Controls, The Shift manager authorizes emergency exposures, if needed, prior to activation of the TSC. In addition, If emergency exposure is estimated to be less than 5 Rem, then obtain verbal authorization from Shift Manager (while in command and control) or Emergency Coordinator to exceed Duke Energy Annual Dose Guidelines up to a maximum of 5 Rem.
Step 6 - Shift manager is determined to be who is responsible for authorization for the exposure.
Determines based on total dose and that the TSC is not yet activated, that the Shift manager (Shift Manager Emergency Coordinator) must authorize this exposure.
- CRITICAL STEP** SAT/UNSAT NOTE: The Shift Manager is executing the role as Shift Manager Emergency Coordinator (EC) prior to TSC activation.
Step 7 - Verbal authorization is determined to be NOT authorized for this exposure since it exceeds 5 Rem.
Determines based on total dose, that the dose is greater than 5 Rem, and therefore, the Shift manager (Shift Manager Emergency Coordinator) can NOT verbally authorize this exposure.
- CRITICAL STEP** SAT/UNSAT TERMINATING CUE: When total dose and authorization requirements are determined, this JPM is complete.
TIME COMPLETED: _____________
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical This is a calculation that is needed for the critical step of total dose 2 Not Critical This is a calculation that is needed for the critical step of total dose 3 Not Critical This is a calculation that is needed for the critical step of total dose 4 Critical Necessary to determine authorization requirement.
5 Critical Total dose less than limit is part of JPM task.
6 Critical Authorization requirement is part of JPM task 7 Critical Authorization requirement is part of JPM task LOT-ADM-JP-102-A05 Page 6 of 8 Rev. 01
Determine Authorization Requirements For Protection Of Property Validation Time: 15 Minutes (approximate)
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes No X Time Limit N/A Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
LOT-ADM-JP-102-A05 Page 7 of 8 Rev. 01
TASK CONDITIONS:
- 1. A Site Area Emergency has been declared.
- 2. The TSC has NOT been activated.
- 3. An accident has occurred on Unit Two and a drywell entry is required to protect valuable equipment.
- 4. The job and radiation conditions in the drywell are detailed below:
Time Dose Rate Travel path in 12 min 10 R/hr Perform task 30 min 6 R/hr Travel path out 12 min 10 R/hr INITIATING CUE:
Determine the following:
- 1. Who is required to authorize exposure for protection of valuable property.
- 2. Calculate the Total Dose.
- 3. Determine whether the projected total dose is less than or greater than the dose limit for protection of valuable property.
- 4. Determine whether the authorization is or is NOT allowed to be approved verbally.
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DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADM JPM EP - 2020 NRC EXAM - SRO TITLE: Determine Protective Action Recommendations (PARs) IAW AD-EP-ALL-0109, Offsite Protective Action Recommendations NUMBER: SOT-ADM-JP-301-A20 REVISION NO: 05 S. Cotton DEVELOPER / PREPARER R. Bolin TECHNICAL REVIEWER M. Long VALIDATOR Rob Mehs 9/15/20 LINE APPROVAL DATE Ed Rau 9/16/20 TRAINING SUPERVISION APPROVAL DATE
Determine Protective Action Recommendations (PARs)
REVISION
SUMMARY
Rev. No Summary Minor Revision Date 05 Added designation as administrative JPM for NA NA performance during NRC 2020 initial exam. Updated references .Changed order of decisions to more closely match flow of BNP Offsite Par Determination Worksheet.
SOT-ADM-JP-301-A20 Page 2 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
RELATED TASKS: (SRO Only) 344236B502 Direct Emergency Response As Emergency Coordinator following Declaration Of A General Emergency per AD-EP-ALL-0111, Control Room Activation of the ERO.
344005B102 Recommend Protective Actions To States And Counties per AD-EP-ALL-0109.
K/A REFERENCE AND IMPORTANCE RATING: (SRO Only)
GEN 2.4.44 2.4/4.4 Knowledge of Emergency Plan Protective Action Recommendations
REFERENCES:
CSD-EP-BNP-0101-02, EAL Wallchart (Both Hot and Cold)
AD-EP-ALL-0304, State and County Notifications AD-EP-ALL-0109, Offsite Protective Action Recommendations AD-EP-ALL-0202, Emergency Response Offsite Dose Assessment PERFORMANCE STANDARD:
Examinee will determine that Zones 3, 4, and 5 should be Evacuated 2-10 miles downwind, Zones 1 and 2 should be Sheltered 0-2 miles radius AND, determine that Potassium Iodide (KI) use should not be recommended to the General Public within 15 minutes.
TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Generic - Emergency Procedures/ Plan SETUP INSTRUCTIONS None TIME CRITICAL OPERATOR ACTIONS:
PARs must be made in 15 minutes from the Start Time. (Basis: 0ERP Radiological Emergency Response Plan, Appendix I,Section IV. C.2)
SOT-ADM-JP-301-A20 Page 3 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
SAFETY CONSIDERATIONS:
- 1. None EVALUATOR NOTES: (Do not read to performer.)
- 1. The POM procedures WILL be made available to the trainee.
- 2. Prior to the first JPM of the JPM set, provide the JPM briefing contained in NUREG-1021, Appendix E, or similar briefing (for non-regulated exams) to the trainee(s).
- 3. Emphasize to candidates that this is a Time Critical JPM and that following cue sheet review the evaluator will designate the START TIME on the board and stop the JPM at the applicable critical time.
- 4. A clock must be available and visible to examiner and examinees.
- 5. Explain to the examinees they should record their Protective Action Recommendation in the blocks provided beneath the Initiating Conditions.
SOT-ADM-JP-301-A20 Page 4 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
Read the following to the JPM performer:
- This is a Time Critical JPM**
TASK CONDITIONS:
A General Emergency, FG1.1 has just been declared due to an Unisolable RCIC steam line break, with fuel failure.
Both Standby Gas Treatment Trains have tripped OFF.
Reactor Building Static Pressure is POSITIVE.
Weather data is as follows:
- Date: October 20
- Time: 19:00
- Temperature: 57ºF
- Upper Wind Speed: 16.7 mph
- Lower Wind Speed: 15.8 mph
- Upper Wind Direction: 39.4º
- Lower Wind Direction: 40.8º
- Stability Class: D Projected offsite dose per AD-EP-ALL-0202, Emergency Response Offsite Dose Assessment, is 450 mRem TEDE and 3500 mRem CDE. Offsite field survey readings are 280 mRem/hour. The highest reading on the Drywell High Range Radiation Monitors is 22,000 R/hr.
The release is expected to drop rapidly due to an Emergency Depressurization in-progress per 0EOP-01-EDP, Emergency Depressurization Procedure. The Emergency Depressurization of the RPV was based on exceeding Maximum Safe Operating Temperatures (MSOT) in the Reactor Building per 0EOP-03-SCCP, Secondary Containment Control Procedure.
County and State governments have been notified, and have prepared local evacuation routes. There are no impediments to evacuation.
INITIATING CUE:
A hard copy Emergency Notification Form (ENF) is being completed. Determine what Initial Protective Action Recommendation (PAR) should be made to Off-Site Agencies AND, determine if the consideration of Potassium Iodide (KI) use should be recommended to the General Public.
- This is a time critical JPM** Time now is: .
TIME PAR Potassium Iodide KI (circle one) SHOULD / SHOULD NOT be recommended to the General Public.
SOT-ADM-JP-301-A20 Page 5 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless otherwise indicated, comments required for any step evaluated as UNSAT.
NOTE: Ensure a clock is visible for candidates. Announce and write the Start Time on the board. Start time is when the examinees have been given the initial conditions, initiating cue and state they understand the task (or state they have no questions)
NOTE: PARs must be made in 15 minutes from the Start Time. The candidates will have 15 minutes to perform the JPM.
NOTE: Per AD-EP-ALL-0304, State and County Notifications, All releases other than BNP Vent Stack are Ground Releases.
START TIME ___________
Step 1 - Reviews AD-EP-ALL-0109 and obtains the appropriate site specific offsite PAR determination worksheet.
Obtains [BNP] Attachment 1, BNP Offsite PAR Determination Worksheet.
SAT/UNSAT Step 2 - Reviews AD-EP-ALL-0109 Attachment 1 and determines INITIAL PAR conditions.
Determines this is the first PAR issued for General Emergency.
SAT/UNSAT Step 3 - Refers to AD-EP-ALL-0109 Attachment 1 Page 2 and evaluates Rapidly Progressing Severe Accident (RPSA) criteria.
Using AD-EP-ALL-0109, Attachment 1 Page 2, determines RPSA criteria applies.
SAT/UNSAT SOT-ADM-JP-301-A20 Page 6 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
NOTE: AD-EP-ALL-0109 Page 4 defines Non-Summer as September 1 to May 31. AD-EP-ALL-0109 Page 6 provides correct attachment determination.
Step 4 - Reviews AD-EP-ALL-0109 Attachment 1 and determines INITIAL PAR conditions.
Using AD-EP-ALL-0109, Reviews Attachment 1 and determines that Non-summer actions are appropriate .
SAT/UNSAT Step 5 - Refers to AD-EP-ALL-0109 Attachment 1 and evaluates PAR.
Determines SHELTER 2 mile radius, EVACUATE 2-10 miles Downwind.
SAT/UNSAT NOTE: AD-EP-ALL-0109 Attachment 1 Page 4, BNP 10 Mile EPZ Map, may be used to determine wind direction and evaluate affected Zones.
Step 6 - Refers to AD-EP-ALL-0109 Attachment 1 and evaluates Evacuation Zones based on wind direction.
Using AD-EP-ALL-0109 Attachment 1 Page 3, determines that Zones 3, 4, and 5 should be Evacuated 2-10 miles downwind.
- CRITICAL STEP** SAT/UNSAT Step 7 - Refers to AD-EP-ALL-0109 Attachment 1 and evaluates Shelter Zones based on wind direction.
Using AD-EP-ALL-0109 Attachment 1 Page 3, determines that Zones 1 and 2 should be Sheltered 0-2 miles radius.
- CRITICAL STEP** SAT/UNSAT Step 8 - Determinations made within 15 minutes from start time.
PAR Determinations made within 15 minutes.
- CRITICAL STEP ** SAT/UNSAT SOT-ADM-JP-301-A20 Page 7 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
NOTE: For actual or projected doses greater than 5 Rem CDE Thyroid, then recommend the consideration of KI use by the public.
Step 9 - Refers to AD-EP-ALL-0109 Attachment 1 Page 2 and evaluates whether Potassium Iodide should be recommended for use by the General Public.
Determines that KI should NOT be recommended for use by the Public.
SAT/UNSAT TERMINATING CUE: When final determination of PARs and KI recommendation, this JPM is complete.
TIME COMPLETED _____________
NOTE: Comments required for any step evaluated as UNSAT.
COLLECT AND CONTROL ALL JPM EXAM MATERIALS FOR EXAM SECURITY.
Step Critical / Not Critical Reason 1 Not Critical Administrative 2 Not Critical Evaluation step 3 Not Critical Evaluation step 4 Not Critical Evaluation step 5 Not Critical Evaluation step 6 Critical Evacuation Zones are critical for protection of the Public.
7 Critical Shelter Zones are critical for protection of the Public.
8 Critical 15- minute time limit is critical for protection of the Public.
9 Not Critical Recommending KI will not harm the Public.
SOT-ADM-JP-301-A20 Page 8 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
WORK PRACTICES:
Comments are required for any step evaluated as UNSAT A. CORE 4 SAT/ UNSAT/ NE
- 1. Task Preview / Pre-Job Briefs
- 2. Take-A-Minute
- 3. STAR (Use of Stop, Think, Act, Review)
- 4. Procedure and Work Instruction Use and Adherence (PU&A)
B. Communications (proper content, repeat backs, 3 step SAT/ UNSAT/ NE communications, etc.)
C. Peer Checking (if performer requests or discusses peer checking) SAT/ UNSAT/ NE D. Proper Equipment Use (observe starting limitations, throttle valve SAT/ UNSAT/ NE closures, etc.)
E. Safety Compliance (use of PPE, knowledge of safety equipment, SAT/ UNSAT/ NE etc.)
F. Electrical Safety And Arc Flash Protection Compliance (refer to SAT/ UNSAT/ NE AD-HS-ALL-0110, as applicable)
G. Security Compliance (controlled area entry and exit, key control, SAT/ UNSAT/ NE etc.)
H. Proper Tool Use (proper tool for the job, calibration dates, etc.) SAT/ UNSAT/ NE I. Radiation Protection (ALARA, understanding and use of RWP, SAT/ UNSAT/ NE frisking, etc.)
Comments:
SOT-ADM-JP-301-A20 Page 9 of 11 Rev. 05
Determine Protective Action Recommendations (PARs)
Validation Time: 15 Minutes (approximate).
Time Taken: ____ Minutes APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: In-Plant Simulator Admin X Time Critical: Yes X No Time Limit 15 minutes Alternate Path: Yes No X EVALUATION Performer:
JPM: Pass Fail Remedial Training Required: Yes No Comments:
Comments reviewed with Performer Evaluator Signature: Date:
SOT-ADM-JP-301-A20 Page 10 of 11 Rev. 05
Read the following to the JPM performer:
- This is a Time Critical JPM**
TASK CONDITIONS:
A General Emergency, FG1.1 has just been declared due to an Unisolable RCIC steam line break, with fuel failure.
Both Standby Gas Treatment Trains have tripped OFF.
Reactor Building Static Pressure is POSITIVE.
Weather data is as follows:
- Date: October 20
- Time: 19:00
- Temperature: 57ºF
- Upper Wind Speed: 16.7 mph
- Lower Wind Speed: 15.8 mph
- Upper Wind Direction: 39.4º
- Lower Wind Direction: 40.8º
- Stability Class: D Projected offsite dose per AD-EP-ALL-0202, Emergency Response Offsite Dose Assessment, is 450 mRem TEDE and 3500 mRem CDE. Offsite field survey readings are 280 mRem/hour. The highest reading on the Drywell High Range Radiation Monitors is 22,000 R/hr.
The release is expected to drop rapidly due to an Emergency Depressurization in-progress per 0EOP-01-EDP, Emergency Depressurization Procedure. The Emergency Depressurization of the RPV was based on exceeding Maximum Safe Operating Temperatures (MSOT) in the Reactor Building per 0EOP-03-SCCP, Secondary Containment Control Procedure.
County and State governments have been notified, and have prepared local evacuation routes.
There are no impediments to evacuation.
INITIATING CUE:
A hard copy Emergency Notification Form (ENF) is being completed. Determine what Initial Protective Action Recommendation (PAR) should be made to Off-Site Agencies AND, determine if the consideration of Potassium Iodide (KI) use should be recommended to the General Public.
- This is a time critical JPM** Time now is: .
TIME PAR Potassium Iodide KI (circle one) SHOULD / SHOULD NOT be recommended to the General Public.
Page 11 of 11