ML112800679
| ML112800679 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/2011 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/11-302, 50-260/11-302, 50-296/11-302 | |
| Download: ML112800679 (188) | |
Text
JPM a PAGE 1 OF 10 OPERATOR:
JPMMJMBER: a TASK NUMBER: U-068-AB-01 TASK TITLE: Recirc Pump Recovery with Manual Scram K/A NUMBER: 202001 A2.04 K/A RATING: RO 3.7 SRO 3.8 TASK STANDARD: Recover tripped Recirc Pump at power and insert a manual Reactor Scram when the operating Recirc Pump trips LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-01-68, 2-AOI-68-1A, 2-AOI-100-l VALIDATION TIME: 6 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:______________________________
Additional comment sheets attached? [ES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMThER
INITIAL CONDITIONS: You are a Unit Operator. 2A Recirc Pump has tripped. All actions of 2-AOI-68-1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, have been completed. The problem with 2A Recirc Pump has been corrected. The SRO has directed 2A Recirc Pump be restarted. The Reactor Engineer is in the control room. All prerequisites have been met and 2-SR-3.4.9.3 & 4 has been successfully completed. The startup procedure has been completed through step 5.3 [9.11 of 2-01-68, Reactor Recirculation System.
INITIATING CUES: The US directs you to continue the return of 2A Recirc Pump to service as directed by 2-01-68, Reactor Recirculation System, starting at Step 5.3 [10].
JPM a PAGE 3 OF 10 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. 2A Recirc Pump has tripped. All actions of 2-AOI-68-1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, have been completed. The problem with 2A Recirc Pump has been corrected. The SRO has directed 2A Recirc Pump be restarted. The Reactor Engineer is in the control room. All prerequisites have been met and 2-SR-3.4.9.3 & 4 has been successfully completed. The startup procedure has been completed through step 5.3[9.l] of 2-01-68, Reactor Recirculation System.
INITIATING CUES: The US directs you to continue the return of 2A Recirc Pump to service as directed by 2-01-6 8, Reactor Recirculation System, starting at Step 5.3 [10].
JPM a PAGE 4 OF 10 START TIME____
Performance Step 1: Critical Not Critical X
[10] CHECK RECIRC LOOP A DIFF PRESS LOW annunciation, 2-XA-55-4A, Window 31 in ALARM.
NOTE All faults and alarms should be reset prior to closing a Recirc Pump Discharge Valve to ensure the DRIVE READY light is obtained thus preventing the loop from cooling down causing the start limitations of the recirc pump to possibly be exceeded thus delaying the startup.
Standard:
Operator verifies 2-XA-55-4A, window 31 is in Alarm SAT_ UNSAT N/A Performance Step 2: Critical Not Critical X
[11] DEPRESS FAULT RESET, 2-HS-96-13, ThEN VERIFY all Faults or Alarms are reset on ICS Screen VFDAAL.
[11.1] IF all faults and alarms are clear, THEN CONTINUE recirc pump startup at Step 5.3[12]
Standard:
Operator depresses FAULT RESET and verifies all Faults and Alarms are reset on ICS Screen VFDAAL. Operator proceeds to step 5.3 [12]
SAT UNSAT N/A COMMENTS:_____________________________
JPM a PAGE 5 OF 10 Performance Step 3: Critical X Not Critical CAUTION The closure circuit for RECIRC PUMP 2A(2B) DISCHARGE VALVE, 2-HS-68-3A(79A) is a seal-in and is NOT to be held in the CLOSE position unless specifically directed. If the handswitch is held to the close position ( 2.5 seconds) after the valve has reached its full close valve position this will allow the reclosure circuit to engage. This reclosure causes the motor to re-engage at a rapid rate 10 times a second), which can cause the motor to heat and also to exceed the recommended valve seat loading.
[12] VERIFY CLOSED, RECIRC PUMP 2A DISCHARGE VALVE, 2-FCV-68-3 CAUTION Recirc System operation is restricted by criteria in Unit 2 Power to Flow Map (ICS or Station Reactor Engineering, 0-TI-248) and Illustration 1.
NOTES
- 1) The DRIVE READY light will only light after the FAULT RESET pushbutton is depressed, if all the active faults are reset. ICS screen VFDAAL(VFDBAL) can be referred to verify the Number of Active Faults is zero after depressing the fault reset pushbuttons. Any faults listed after the FAULT RESET pushbutton has been depressed, are keeping the drive from being ready to run.
- 2) Capacitor bank fuses are subject to clearing when the unit boards are being supplied from the 161 source and large pumps are started. Unit Supervisors are to evaluate the need to place the Capacitor Banks in Manual prior to starting a recirc pump from the Alternate feeder. The evaluation should consider placing a Caution order on the recirc pumps start switches stating, evaluate the need to place CAP Banks in Manual prior to starting Pumps from the ALTERNATE FEED.
- 3) The actions which occur after the START pushbutton is depressed are listed on the next page.
- 4) When depressing the switches which control the recirc drives, these switches must be firmly depressed to ensure all the contacts are made-up.
Standard:
Operator closes 2-FCV-68-3 SAT UNSAT N/A COMMENTS:________________________________
JPM a PAGE 6 OF 10 Performance Step 4: Critical_ Not Critical X
[131 IF the recirc drive startup seq incomplete alarm is received and the recirc discharge valve is jogging OPEN THEN: (N/A if alarm is not received)
Standard:
Operator N/As this step and proceeds to step [14]
SAT_ UNSAT N/A COMMENTS:_____________________________
Performance Step 5: Critical_ Not Critical X NOTES
- 1) Tech Spec LCO 3.4.1 should be reviewed prior to starting a Recirc pump in Step 5.3[14]. The applicability for the Tech Spec is Modes 1 & 2.
- 2) Step 5.3[14] is used to start Recirc Pump 2A under normal conditions.
- 3) Step 5.3[15] can be used to start Recirc Pump 2A during cold shutdown (Mode 4) when it is desired to start the pump and open the discharge valve without the jogging circuit.
[14] IF starting Recirc Pump 2A, THEN PERFORM the following (Otherwise N/A):
[14.1] VERIFY Tech Spec LCO 3.4.1 requirements are satisfied.
Standard:
Given in initial conditions SAT_ UNSAT N/A COMMENTS:_____________________________
CUE: IF Asked: State that LCO 3.4.1 requirements have been implemented.
JPM a PAGE 7 OF 10 Performance Step 6: Critical_ Not Critical X
[14.2] DEPRESS FAULT RESET, 2-HS-96-13 Standard:
Operator depresses fault reset pushbutton, 2-HS-96-1 3 SAT_ UNSAT N/A COMMENTS:______________________________
Performance Step 7: Critical_ Not Critical
[14.3] CHECK DRIVE READY, 2-IL-96-37 is LIT.
Standard:
Operator checks drive ready light, 2-IL-96-37, is lit SAT_ UNSAT N/A COMMENTS:_____________________________
Performance Step 8: Critical X Not Critical
[14.4] FIRMLY DEPRESS DRIVE START, 2-HS-96-11.
Standard:
Operator depresses drive start pushbutton, 2-HS-96-1 1 SAT_ UNSAT N/A _COMMENTS:_______________________________
NOTE: Simulator driver: When Recirc Pump 2A trips due to incomplete start sequence then insert 2B Reciro Pump Trip imf thO3b
JPM a PAGE 8 OF 10 Performance Step 9: Critical X Not Critical 2-AOI-68-1A Recirc Pump Trip/Core Flow Decrease OPRMs Operable 4.2 Subsequent Actions
[1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN (Otherwise N/A),
[1.1] SCRAM the Reactor.
Standard:
Operator recognizes trip of 2B Recirc Pump and inserts a manual reactor scram based on 2-AOI-68-1A section 4.2 step [1.1]. The action to Scram the Reactor is a SUBSEQUENT action in 2-AOI 1 A; therefore, the applicants performance is Satisfactory if he/she refers to 2-AOI 1 A before Scramming the Reactor SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 10: Critical X Not Critical 2-AOI-100-1 Reactor Scram 4.1 Immediate Actions
[1] DEPRESS REACTOR SCRAM A and B, 2-HS-99-5A/S3A and 2-HS-99-5A/S3B, on Panel 2-9-5.
Standard:
Operator depresses Reactor Scram A and B pushbuttons on Panel 2-9-5.
SAT_ UNSAT N/A COMMENTS:____________________________
JPM a PAGE 9 OF 10 Performance Step 11: Critical_ Not Critical X
[2] IF scram is due to a loss of RPS, THEN PAUSE in START & HOT STBY mode for approximately 5 seconds before going to REFUEL. (Otherwise N/A)
Standard:
Operator does not perform this step, Scram is not due to loss of RPS.
SAT_ UNSAT N/A _COMMENTS:_____________________________
Performance Step 12: Critical_ Not Critical X
[3] REFUEL MODE ONE ROD PERMISSIVE light check:
[3.1] PLACE REACTOR MODE SWITCH, 2-HS-99-5A-S1, in REFUEL.
[3.2] CHECK REFUEL MODE ONE ROD PERMISSIVE light, 2-XI-85-46, illuminates.
[3.3] IF REFUEL MODE ONE ROD PERMISSIVE light, 2-XI-85-46, is not illuminated, THEN CHECK all control rod positions at Full-In Overtravel, or Full-In.
Standard:
Operator places Reactor Mode Switch in Refuel and observes Refuel Mode One Rod Permissive Light Illuminated SAT_ UNSAT N/A COMMENTS:_____________________________
JPM a PAGE 10 OF 10 Performance Step 13: Critical X Not Critical
[4] PLACE REACTOR MODE SWITCH, 2-HS-99-5A-S1, in SHUTDOWN position.
Standard:
Operator places Reactor Mode Switch in Shutdown position SAT UNSAT N/A _COMMENTS:____________
CUE: After SCRAM report another operator will continue in 2-AOI-100-1 I
ENT OF TASK STOP TIME
JPM a PAGE 1 OF 10 OPERATOR:
RO___ SRO___ DATE:________
JPM NUMBER: a TASK NUMBER: U-068-AB-01 TASK TITLE: Recirc Pump Recovery with Manual Scram KJA NUMBER: 202001 A2.04 K/A RATING: RO 3.7 SRO 3.8 TASK STANDARD: Recover tripped Recirc Pump at power and insert a manual Reactor Scram when the operating Recirc Pump trips LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-01-68, 3-AOI-68-1A, 3-AOI-100-1 VALIDATION TIME: 6 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ U1JSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. 3A Recirc Pump has tripped. All actions of 3-AOI-68-1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, have been completed. The problem with 3A Recirc Pump has been corrected. The SRO has directed 3A Recirc Pump be restarted. The Reactor Engineer is in the control room. All prerequisites have been met and 3-SR-3.4.9.3 & 4 has been successfully completed. The startup procedure has been completed through step 5.3 [9.11 of 3-01-68, Reactor Recirculation System.
INITIATING CUES: The US directs you to continue the return of 3A Recirc Pump to service as directed by 3-01-68, Reactor Recirculation System, starting at Step 5.3 [101.
JPM a PAGE 3 OF 10 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. 3A Recirc Pump has tripped. All actions of 3-AOI-68-1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, have been completed. The problem with 3A Recirc Pump has been corrected. The SRO has directed 3A Recirc Pump be restarted. The Reactor Engineer is in the control room. All prerequisites have been met and 3-SR-3.4.9.3 & 4 has been successfully completed. The startup procedure has been completed through step 5.3 [9.1] of 3-01-6 8, Reactor Recirculation System.
INITIATING CUES: The US directs you to continue the return of 3A Recirc Pump to service as directed by 3-01-68, Reactor Recirculation System, starting at Step 5.3 [10].
JPM a PAGE 4 OF 10 START TIME Performance Step 1: Critical Not Critical X
[10] VERIFY RECIRC LOOP A DIFF PRESS LOW annunciation, 3-XA-55-4A, window 31 in ALARM.
NOTE All faults and alarms should be reset prior to closing a Recirc Pump Discharge Valve to ensure the DRIVE READY light is obtained thus preventing the ioop from cooling down causing the start limitations of the recirc pump to possibly be exceeded thus delaying the startup.
Standard:
Operator verifies 3-XA-55-4A, window 31 is in Alarm SAT_ UNSAT N/A COMMENTS:_____________________________
Performance Step 2: Critical Not Critical X
[11] DEPRESS FAULT RESET, 3-HS-96-13, THEN VERIFY all Faults or Alarms are reset on ICS Screen VFDAAL.
[11.1] IF all faults and alarms are clear, THEN CONTINUE recirc pump startup at Step 5.3[12]
Standard:
Operator depresses FAULT RESET and verifies all Faults and Alarms are reset on ICS Screen VFDAAL. Operator proceeds to step 5.3 [12]
SAT_ UNSAT N/A COMMENTS:____________________________
JPM a PAGE 5 OF 10 Performance Step 3: Critical X Not Critical CAUTION The closure circuit for RECIRC PUMP 3A(3B) DISCHARGE VALVE, 3-HS-68-3A(79A) is a seal-in and is NOT to be held in the CLOSE position unless specifically directed. If the handswitch is held to the close position (approx. 2.5 seconds) after the valve has reached its full close valve position this will allow the reclosure circuit to engage. This reclosure causes the motor to re-engage at a rapid rate (approx. 10 times a second), which can cause the motor to heat and also to exceed the recommended valve seat loading.
[121 VERIFY CLOSED, RECIRC PUMP 3A DISCHARGE VALVE, 3-FCV-68-3 CAUTION Recirc System operation is restricted by criteria in Unit 3 Power to Flow Map (ICS or Station Reactor Engineering, 0-TI-248) and Illustration 1.
NOTES
- 1) The DRIVE READY light will only light after the FAULT RESET push button is depressed, if all the active faults are reset. ICS screen VFDAAL(VFDBAL) can be referred to verify the Number of Active Faults is zero after depressing the fault reset push buttons. Any faults listed after the FAULT RESET push button has been depressed, are keeping the drive from being ready to run.
- 2) Capacitor bank fuses are subject to clearing when the unit boards are being supplied from the 161 source and large pumps are started. Unit Supervisors are to evaluate the need to place the Capacitor Banks in Manual prior to starting a Recirc pump from the Alternate feeder. The evaluation should consider placing a Caution order on the Recirc pumps start switches stating, evaluate the need to place CAP Banks in Manual prior to starting Pumps from the ALTERNATE FEED.
- 3) The actions which occur after the START push-button is depressed are listed on the next page.
- 4) When depressing the switches which control the Recirc Drives these switches are to be firmly depressed to ensure all the contacts are made-up.
Standard:
Operator closes 3-FCV-68-3 SAT UNSAT N/A COMMENTS:_______________________________
JPM a PAGE 6 OF 10 Performance Step 4: Critical_ Not Critical X
[13] IF the recirc drive startup seq incomplete alarm is received and the recirc discharge valve is jogging OPEN THEN: (N/A if alarm is not received)
Standard:
Operator N/As this step and proceeds to step [14]
SAT UNSAT N/A COMMENTS:__________________________
Performance Step 5: Critical_ Not Critical X NOTES
- 1) Tech Spec LCO 3.4.1 should be reviewed prior to starting Recirc Pump 3A in Step 5.3[14]
The applicability for the Tech Spec is Modes 1 & 2.
- 2) Step 5.3[14] is used to start Recirc Pump 3A under normal conditions.
- 3) Step 5.3[15] can be used to start Recirc Pump 3A during cold shutdown (Mode 4) when it is desired to start the pump and open the discharge valve without the jogging circuit.
[14] IF starting Recirc Pump 3A, THEN PERFORM the following (Otherwise N/A):
[14.1] VERIFY Tech Spec LCO 3.4.1 requirements are satisfied.
Standard:
Given in initial conditions SAT UNSAT N/A _COMMENTS:
JPM a PAGE 7 OF 10 Performance Step 6: Critical_ Not Critical X
[14.2] DEPRESS FAULT RESET, 3-HS-96-13 Standard:
Operator depresses fault reset pushbutton, 3-HS-96-13 SAT_ UNSAT N/A _COMMENTS:______________________________
Performance Step 7: Critical_ Not Critical X
[14.3] CHECK DRIVE READY, 3-IL-96-37 is LIT.
Standard:
Operator checks drive ready light, 3-IL-96-37, is lit SAT UNSAT N/A COMMENTS:______________________________
Performance Step 8: Critical X Not Critical
[14.4] FIRMLY DEPRESS DRIVE START, 3-HS-96-1 1.
Standard:
Operator depresses drive start pushbutton, 3-HS-96-1 1 SAT_ UNSAT N/A COMMENTS:______________________________
NOTE: Simulator driver: When Recirc Pump 3A trips due to incomplete start sequence then insert 3B Recire Pump Trip thO3b
JPM a PAGE 8 OF 10 Performance Step 9: Critical Not Critical 3-AOI-68-1A Recirc Pump Trip/Core Flow Decrease OPRMs Operable 4.2 Subsequent Actions
[1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN (Otherwise N/A),
[1 .11 SCRAM the Reactor.
Standard:
Operator recognizes trip of 3B Recirc Pump and inserts a manual reactor scram based on 3-AOI-68-1A section 4.2 step [1.11. The action to Scram the Reactor is a SUBSEQUENT action in 3-AOI 1 A; therefore, the applicants performance is Satisfactory if he/she refers to 3 -AOI 1 A before Scramming the Reactor.
SAT IJNSAT N/A _COMMENTS:_____________________________
Performance Stei 10: Critical X Not Critical 3-AOI-100-1 Reactor Scram 4.1 Immediate Actions
[1] DEPRESS REACTOR SCRAM A and B, 3-HS-99-5A/S3A and 3-HS-99-5AJS3B, on Panel 3-9-5.
Standard:
Operator depresses Reactor Scram A and B pushbuttons on Panel 3-9-5.
SAT UNSAT N/A COMMENTS:____________________________
JPM a PAGE 9 OF 10 Performance Step 11: Critical_ Not Critical X
[2] IF scram is due to a loss of RPS, THEN PAUSE in START & HOT STBY mode for approximately 5 seconds before going to REFUEL. (Otherwise N/A)
Standard:
Operator does not perform this step, Scram is not due to loss of RPS.
SAT UNSAT N/A COMMENTS:___________________________
Performance Step 12: Critical_Not Critical X
[3] REFUEL MODE ONE ROD PERMISSIVE light check:
[3.1] PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S1, in REFUEL.
[3.2] CHECK REFUEL MODE ONE ROD PERMISSIVE light, 3-XI-85-46, illuminates.
[3.3] IF REFUEL MODE ONE ROD PERMISSIVE light, 3-XI-85-46, is not illuminated, THEN CHECK all control rod positions at Full-In Overtravel, or Full-In.
Standard:
Operator places Reactor Mode Switch in Refuel and observes Refuel Mode One Rod Permissive Light Illuminated SAT UNSAT N/A COMMENTS:___________________________
JPM a PAGE 10 OF 10 Performance Step 13: Critical X Not Critical
[4] PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S 1, in SHUTDOWN position.
Standard:
Operator places Reactor Mode Switch in Shutdown position SAT U1SAT N/A _COMMENTS:____________
f CUE: After SCRAM report another operator will continue in 3-AOI-lOO-1 I
END OF TASK STOP TIME
JPM b PAGE 1 OF 11 OPERATOR:
JPM NUMBER: b TASK NUMBER: U-000-EM-39 TASK TITLE: 2-EOI Appendix-7D Alternate RPV Injection System Lineup Standby Coolant KIA NUMBER: 295031 EA1.08 KIA RATING: RO 3.8 SRO 3.9 TASK STANDARD: Injects with Standby coolant in accordance with 2-EOI Appendix-7D LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-7D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Reactor Level and Pressure have lowered to their current value.
INITIATING CUE: The Unit Supervisor directs you to Align and Inject with Standby Coolant through RHR Loop 1 in accordance with 2-EOI Appendix-7D and restore level to +2 to +51 inches.
JPM b PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Reactor Level and Pressure have lowered to their current value.
INITIATING CUE: The Unit Supervisor directs you to Align and Inject with Standby Coolant through RHR Loop 1 in accordance with 2-EOI Appendix-7D and restore level to +2 to +51 inches.
JPM b PAGE 4 OF 8 START TIME Performance Step 1: Critical Not Critical
- 1. IF RHR Loop I is to be used for Standby Coolant, THEN PERFORM the following:
- a. VERIFY CLOSED the following valves:
- 2-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE
Standard:
Verifies the above listed valves are closed SAT UNSAT N/A COMMENTS:______________________
Performance Step 2: Critical_ Not CriticalX
- b. VERIFY RHR Pumps 2A and 2C are NOT running.
Standard:
Verifies RHR Pumps 2A and 2C are NOT running SAT UNSAT N/A COMMENTS:
JPM b PAGE 5 OF 8 Performance Step 3: Critical X Not Critical
- c. START RHRSW Pumps Dl and D2.
Standard:
Starts RHRSW Pumps Dl and D2 SAT UNSAT N/A COMMENTS:______________________
Performance Step 4: *Critical X Not Critical
- d. NOTIFY Unit 1 Operator to perform the following:
- 2) OPEN 1-FCV-23-57, STANDBY COOLANT VALVE FROM RHRSW, (Unit 1, Panel 1-9-3).
Standard:
Notifies Unit 1 Operator to verify closed 1-FCV-23-52 and open 1-FCV-23-57 SAT UNSAT N/A COMMENTS:_________________________
I CUE: Inform operator 1-FCV-23-52 is closed and 1-FCV-23-57 is open and insert remote function IRF SWO9 OPEN
JPM b PAGE 6 OF 8 Performance Step 5: Critical X Not Critical
- 3) DISPATCH personnel to CLOSE 2-BKR-074-0 100, RHR SYS lU-i DISCH XTIE, 480V RMOV Board 1B, Compartment 19A.)
Standard:
Dispatches personnel to close 2-BKR-074-0 100 SAT UNSAT N/A COMMENTS:__________________________
I CUE: Inform operator 2-BKR-074-0i00 is closed and delete override for 2-FCV-74-100 valve or change to NORM Performance Step 6: Critical Not Critical X
- e. NOTIFY Unit 3 Operator to VERIFY CLOSED 3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV (Unit 3, Panel 3-9-3).
Standard:
Notifies Unit 3 Operator to verify closed 3-FCV-23-52 SAT TJNSAT N/A COMMENTS:________________________
CUE: Inform operator 3-FCV-23-52 is closed
JPM b PAGE 7 OF 8 Performance Step 7: Critical Not Critical X
- f. INJECT Standby Coolant into RPV as follows:
Standard:
Closes 2-FCV-74-52 SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical X Not Critical
- 2) OPEN 2-FCV-74-100, RHR SYS I U-i DISCH XTIE.
Standard:
Opens 2-FCV 100 SAT UNSAT N/A COMMENTS:
JPM b PAGE 8 OF 8 Performance Step 9: Critical Not Critical X
Standard:
Verifies open 2-FCV-74-53 SAT UNSAT N/A COMMENTS:_________________________
Performance Step 10: Critical X Not Critical
Standard:
Opens 2-FCV-74-52 to inject water to Reactor. RHR flow will rise as indicated on Panel 2-9-3 indication 2-FI-74-50 as reactor pressure lowers or RPV Water Level will indicate rising on various Control Room Level indicators.
SAT UNSAT N/A COMMENTS:______
EI.ID OF TASK STOP TIME
JPM b PAGE 1 OF 11 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: b TASK NUMBER: U-000-EM-39 TASK TITLE: 3-EOI Appendix-7D Alternate RPV Injection System Lineup Standby Coolant K/A NUMBER: 295031 EA1.08 K/A RATING: RO 3.8 SRO 3.9 TASK STANDARD: Injects with Standby coolant in accordance with 3-EOI Appendix-7D LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-7D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:_____________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Reactor Level and Pressure have lowered to their current value.
INITIATING CUE: The Unit Supervisor directs you to Align and Inject with Standby Coolant in accordance with 3-EOI Appendix-7D and restore level to +2 to +51 inches.
JPM b PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Reactor Level and Pressure have lowered to their current value.
INITIATING CUE: The Unit Supervisor directs you to Align and Inject with Standby Coolant in accordance with 3-EOI Appendix-7D and restore level to +2 to +51 inches.
JPM b PAGE 4 OF 8 START TIME Performance Step 1: Critical Not Critical X
- 1. VERIFY RHR SYSTEM I available for Standby Coolant as follows (Unit 3, Panel 3-9-3):
- a. VERIFY CLOSED the following valves:
o 3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV o 3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV o 3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV o 3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE o 3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VLV o 3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV.
Standard:
Verifies the above listed valves are closed SAT UNSAT N/A COMMENTS:________________________
Performance Step 2: Critical_Not CriticaiX
- b. VERIFY RHR Pumps 3A and 3C are NOT running.
Standard:
Verifies RUR Pumps 3A and 3C are NOT running SAT UNSAT N/A COMMENTS:
JPM b PAGE 5 OF 8 Performance Step 3: Critical X Not Critical
- c. PLACE 3-BKR-074-0 100, RHR HTX A-C DISCH XTIE (TO U-2) VLV FCV-74-100 (M010-171) to ON (480V RMOV Board 3B, Compartment 19A).
Standard:
Dispatches personnel to close 3-BKR-074-0 100 SAT UNSAT N/A COMMENTS:___________________________
I CUE: Inform operator 3-BKR-074-0 100 is closed and delete override for 3-FCV-74-100 valve or change to NORM Performance Step 4: Critical X Not Critical
- 2. START RHRSW Pumps Bi and B2.
Standard:
Starts RHRSW Pumps Bi and B2 SAT USAT N/A COMMENTS:
JPM b PAGE 6 OF 8 Performance Step 5: Critical_ Not CriticaiX
- 3. NOTIFY Unit 1 Operator to VERIFY CLOSED 1-FCV-23-46, RHR HEAT EXCHANGER B COOL WATER OUTLET VLV (Unit 1, Panel 1-9-3).
Standard:
Notifies Unit 1 Operator to verify closed 1-FCV-23-46 SAT UNSAT N/A COMMENTS:
I CUE: Inform operator 1-FCV-23-46 is closed and 1-FCV-23-57 is open and modify remote function MRF SWO9 OPEN Performance Step 6:
- Critical X Not Critical
- 4. NOTIFY Unit 2 Operator to perform the following (Unit 2, Panel 2-9-3):
Standard:
Notifies Unit 2 Operator to verify closed 2-FCV-23-46 and open 2-FCV-23-57 SAT U1TSAT N/A COMMENTS:__________________________
I CUE: Inform operator 2-FCV-23-46 is closed and 2-FCV-23-57 is open and modify remote function MRF SWO9 OPEN
JPM b PAGE 7 OF 8 Performance Step 7: Critical Not Critical X
- 5. INJECT Standby Coolant into RPV as follows (Unit 3, Panel 3-9-3):
Standard:
Closes 3-FCV-74-52 SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical Not Critical
- b. OPEN 3-FCV-74-l00, RHR SYS I U-2 DISCH XTIE.
Standard:
Opens 3-FCV 100 SAT UNSAT N/A COMMENTS:
JPM b PAGE 8 OF 8 Performance Step 9: Critical Not Critical X
Standard:
Verifies open 3-FCV-74-53 SAT UNSAT N/A COMMENTS:
Performance Step 10: Critical X Not Critical
Standard:
Opens 3-FCV-74-52 to inject water to Reactor. RHR flow will rise as indicated on Panel 3-9-3 indication 3-FI-74-50 as reactor pressure lowers or RPV Water Level will indicate rising on various Control Room Level indicators.
SAT UNSAT N/A COMMENTS:_____
END OF TASK STOP TIME
JPM c PAGE 1 OF 11 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: c TASK NUMBER: U-000-EM-55 TASK TITLE: 2.-EOI-Appendix-1 1C Alternate RPV Pressure Control Systems HPCI Test Mode KIA NUMBER: 206000 A4.06 KIA RATING: RO 4.3 SRO 4.3 TASK STANDARD: 2-EOI-Appendix-1 1C complete with HPCI controlling RPV pressure in Test Mode LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI-Appendix-1 1C VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAIVIINER
INITIAL CONDITIONS: You are an operator. The Unit 2 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-1 1.
INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11C and maintain Reactor Pressure 800-1000 psig
JPM c PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator. The Unit 2 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI- 1 has been followed to RC/P- ii.
INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 2-EOI Appendix-i iC and maintain Reactor Pressure 800-1000 psig
JPM c PAGE 4 OF 11 Simulator Driver: This JPM requires tcO2 0 present on snap and malfunction hpO3 10 inserted when operator throttles the 73-35 valve, maintain Reactor water level with RCIC START TIME____
Performance Step 1: Critical Not Critical X CAUTION
- Operating HPCI turbine below 2400 rpm may result in unstable system operation and equipment damage.
- Operating HPCI Turbine with suction temperatures above 140°F may result in equipment damage.
- 1. IF Suppression Pool level drops below 12.75 ft, THEN TRIP HPCI and CONTROL RPV pressure using other options.
Standard:
Operator verifies Suppression Pool Level above 12.75 feet using either Narrow range or Wide range level indicators SAT_ UNSAT N/A _COMMENTS:________________________________
JPM c PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
- 2. IF Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN EXECUTE EOI Appendix 1 6C and 1 6D as necessary to bypass HPCI Low RPV pressure and Test Mode Isolation Interlocks.
Standard:
Operator determines Appendices 1 6C and 1 6D are not required SAT UNSAT N/A COMMENTS:______________
Cue: Emergency Depressurization or Steam Cooling is not required I
Performance Step 3: Critical Not Critical X
- 3. IF Suppression Pool level CANNOT be maintained below 5.25 in, THEN EXECUTE EOI Appendix 1 6E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.
Standard:
Operator verifies Suppression Pool level below 5.25 inches on Narrow Range level indicator and does not execute Appendix 1 6E SAT UNSAT N/A COMMENTS:____________________________
JPM c PAGE 6 OF 11 Performance Step 4: Critical Not Critical X
- 4. IFHPCIT urbine is operating, THEN ALIGN HPCI in test mode as follows:
- c. CLOSE 2-FCV-73-44, HPCI PUMP INJECTION VALVE.
- d. CONTINUE in this procedure at Step 6.
Standard:
Operator observes HPCI is not operating and NAs step 4 SAT UNSAT N/A _COMMENTS:__________
Performance Step 5: Critical Not Critical X
- a. VERIFY at least one SGTS Train in operation.
Standard:
Operator verifies SGT in operation by illuminated RED SGTS status indicating iamps on Panel 2-9-20 SAT UNSAT N/A COMMENTS:_____________________________
JPM c PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
- b. VERIFY 2-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller in AUTO and set for 5300 gpm.
Standard:
Operator verifies 2-FIC-73-33 in AUTO and set for 5300 gpm on controller digital readout SAT UNSAT N/A COMMENTS:________________________________
Performance Step 7: Critical X Not Critical NOTE HPCI Auxiliary Oil Pump will NOT start UNTIL 2-FCV-73-16, HPCI TURBINE STEAM SUPPLY VLV, starts to open.
- c. PLACE 2-HS-73-47A, HPCI AUXILIARY OIL PUMP handswitch, in START.
Standard:
Operator places 2-HS-73-47A in START.
SAT UNSAT N/A COMMENTS:_____________________________
JPM c PAGE 8 OF 11 Performance Step 8: Critical Not Critical X
- d. PLACE 2-HS-73-1OA, HPCI STEAM PACKJNG EXHAUSTER, in START.
Standard:
Operator places 2-HS-73-1OA in START.
SAT_ UNSAT N/A COMMENTS:______________________________
Performance Step 9: *Critjcal X Not Critical
- e. OPEN the following valves:
2-FCV-73-36, HPCI/RCIC CST TEST VLV 2-FCV-73-35, HPCI PUMP CST TEST VLV
- 2-FCV-73-30, HPCI PUMP MN FLOW VALVE.
Standard:
Operator places handswitches 2-HS-73-36A, 2-HS-73-35A, and 2-HS-73-30A in the OPEN position and verifies only RED valve position indicating iamps illuminated above associated control switches.
SAT UNSAT N/A COMMENTS:____________________________
JPM c PAGE 9 OF 11 Performance Step 10: Critical X Not Critical
Standard:
Operator places 2-HS-73-16A in OPEN and verifies illuminated RED valve position indicating lamp above handswitch SAT UNSAT N/A _COMMENTS:________________________________
Performance Step 11: Critical Not Critical X
- g. VERIFY HPCI Auxiliary Oil Pump starts and turbine accelerates above 2400 rpm.
Standard:
Operator verifies HPCI AUX Oil Pump starts by observing RED light illuminated above 2-HS-73-47A and verifies speed >2400 rpm on 2-51-73-5 1 SAT UNSAT N/A COMMENTS:_____________________________
JPM c PAGE 10 OF 11 Performance Step 12: Critical Not Critical X
- 6. VERIFY proper HPCI minimum flow valve operation as follows:
b IF HPCI flow is below 600 gpm, THEN VERIFY OPEN 2-FCV-73-30, HPCI PUMP M1N FLOW VALVE.
Standard:
When flow >1200 gpm on 2-FIC-73-33, Operator verifies 2-FCV-73-30 closes by green light above handswitch SAT UNSAT N/A COMMENTS:_______________________________
Performance Step 13: Critical X Not Critical
- 7. THROTTLE 2-FCV-73-35, HPCI PUMP CST TEST VLV, to control HPCI pump discharge pressure at or below 1100 psig.
Standard:
Operator throttles 2-FCV-73-35 using handswitch to control HPCI pump discharge pressure less than or equal to 1100 psig on 2-PI-73-3 1A. If candidate exceeds Maximum Design Piping pressure of 1500 psig on 2-PI-73-3 1A while throttling 2-FCV-73-35 this would constitute unsatisfactory performance.
SAT_ UNSAT N/A COMMENTS:_______________________________
DRIVER: AFTER the applicant has demonstrated the ability to maintain Reactor Pressure between 800 and 1000 psig and the ability to control IIPCI discharge pressure at or below 1100 psig and at the Chief Examiner cue, insert malfunction: unf hpO3 at 10% to fail IIPCI flow controfler in automatic
JPM c PAGE 11 OF 11 Performance Step 14: Critical X Not Critical
Standard:
Operator attempts to adjust HPCI SYSTEM FLOW/CONTROL, however, controller has failed downscale in automatic. Operator shifts controller to manual and adjusts HPCI flow.
Operator adjusts controller and 2-FCV-73-35 to control Reactor pressure.
SAT UNSAT N/A _COMMENTS:_________________________________
Performance Step 15: Critical Not Critical X
- a. OPEN 2-FCV-73-44, HPCI PUMP INJECTION VALVE.
- c. GO TO EOI Appendix-5D.
Standard:
Operator monitors Reactor water level and determines HPCI injection to the RPV is not required SAT TJNSAT N/A _COMMENTS:_____________________________
Cue: Injection to the RPV is not necessary at this time END OF TASK I
STOP TIME____
JPM c PAGE 1 OF 11 OPERATOR:
RO___ SRO DATE:
JPM NUMBER: c TASK NUMBER: U-000-EM-55 TASK TITLE: 3-EOI-Appendix-1 1C Alternate RPV Pressure Control Systems HPCI Test Mode K/A NUMBER: 206000 A4.06 K/A RATING: RO 4.3 SRO 4.3 TASK STANDARD: 3-EOI-Appendix-1 1C complete with HPCI controlling RPV pressure in Test Mode LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI-Appendix-1 1C VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:
DATE:
EXAM1ISJER
INITIAL CONDITIONS: You are an operator. The Unit 3 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI- 1 has been followed to RC/P- 11.
INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 3-EOI Appendix-11C and maintain Reactor Pressure 800-1000 psig
JPM c PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator. The Unit 3 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI- 1 has been followed to RC/P- ii.
INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 3-EOI Appendix-i 1C and maintain Reactor Pressure 800-1000 psig
JPM c PAGE 4 OF 11 Simulator Driver: This 3PM requires tcO2 0 present on snap and malfunction hpO3 10 inserted when operator throttles the 73-35 valve, maintain Reactor water level with RCIC START TIME____
Performance Step 1: Critical Not Critical X CAUTION
- Operating HPCI turbine below 2400 rpm may result in unstable system operation and equipment damage.
- Operating HPCI Turbine with suction temperatures above 140°F may result in equipment damage.
- 1. IF Suppression Pool level drops below 12.75 ft, THEN TRIP HPCI and CONTROL RPV pressure using other options.
Standard:
Operator verifies Suppression Pool Level above 12.75 feet using either Narrow range or Wide range level indicators SAT_ UNSAT N/A COMMENTS:_____________________________
JPM c PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
- 2. IF Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN EXECUTE EOI Appendix 1 6C and 1 6D as necessary to bypass HPCI Low RPV pressure and Test Mode Isolation Interlocks.
Standard:
Operator determines Appendices 1 6C and 1 6D are not required SAT UNSAT N/A _COMMENTS:______________
f Cue: Emergency Depressurization or Steam Cooling is not required I
Performance Step 3: Critical Not Critical X
- 3. IF Suppression Pool level CANNOT be maintained below 5.25 in, THEN EXECUTE EOI Appendix 1 6E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.
Standard:
Operator verifies Suppression Pool level below 5.25 inches on Narrow Range level indicator and does not execute Appendix 1 6E SAT_ UNSAT N/A _COMMENTS:_____________________________
JPM c PAGE 6 OF 11 Performance Step 4: Critical Not Critical X
- c. CLOSE 3-FCV-73-44, HPCI PUMP INJECTION VALVE.
- d. CONTINUE in this procedure at Step 6.
Standard:
Operator observes HPCI is not operating and NAs step 4 SAT UNSAT N/A _COMMENTS:_______________________________
Performance Step 5: Critical Not Critical X
- a. VERIFY at least one SGTS Train in operation.
Standard:
Operator verifies SGT in operation by illuminated RED SGTS status indicating lamps on Panel 3-9-20 SAT UNSAT N/A _COMMENTS:_______________________________
JPM c PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
- b. VERIFY 3-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller in AUTO and set for 5300 gpm.
Standard:
Operator verifies 3-FIC-73-33 in AUTO and set for 5300 gpm on controller digital readout SAT_ UNSAT N/A _COMMENTS:________________________________
Performance Step 7: Critical X Not Critical NOTE HPCI Auxiliary Oil Pump will NOT start UNTIL 3-FCV-73-16, HPCI TURBINE STEAM SUPPLY VLV, starts to open.
- c. PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP handswitch, in START.
Standard:
Operator places 3-HS-73-47A in START.
SAT_ UNSAT N/A
JPM c PAGE 8 OF 11 Performance Step 8: Critical Not Critical X
- d. PLACE 3-HS-73-1OA, HPCI STEAM PACKiNG EXHAUSTER, in START.
Standard:
Operator places 3-HS-73-10A in START.
SAT UNSAT N/A COMMENTS:____________________________
Performance Step 9:
- Critical X Not Critical
- e. OPEN the following valves:
I.
3-FCV-73-36, HPCI/RCIC CST TEST VLV 3-FCV-73-35, RPCI PUMP CST TEST VLV 3-FCV-73-30, HPCI PUMP MIN FLOW VALVE.
Standard:
Operator places handswitches 3-HS-73-36A, 3-HS-73-35A, and 3-HS-73-30A in the OPEN position and verifies only RED valve position indicating lamps illuminated above associated control switches.
SAT UNSAT N/A COMMENTS:______________________________
JPM c PAGE 9 OF 11 Performance Step 10: Critical X Not Critical
Standard:
Operator places 3-HS-73-16A in OPEN and verifies illuminated RED valve position indicating lamp above handswitch SAT IJNSAT N/A _COMMENTS:________________________________
Performance Step 11: Critical Not Critical X
- g. VERIFY HPCI Auxiliary Oil Pump starts and turbine accelerates above 2400 rpm.
Standard:
Operator verifies HPCI AUX Oil Pump starts by observing RED light illuminated above 3-HS-73-47A and verifies speed >2400 rpm on 3-SI-73-51 SAT UNSAT N/A _COMMENTS:_____________________________
JPM c PAGE 10 OF 11 Performance Step 12: Critical Not Critical X
- 6. VERIFY proper HPCI minimum flow valve operation as follows:
b IF HPCI flow is below 600 gpm, THEN VERIFY OPEN 3-FCV-73-30, HPCI PUMP MIN FLOW VALVE.
Standard:
When flow >1200 gpm on 3-FIC-73-33, Operator verifies 3-FCV-73-30 closes by green light above handswitch SAT UNSAT N/A _COMMENTS:_______________________________
Performance Step 13: Critical Not Critical
- 7. THROTTLE 3-FCV-73-35, HPCI PUMP CST TEST VLV, to control HPCI pump discharge pressure at or below 1100 psig.
Standard:
Operator throttles 3-FCV-73-35 using handswitch to control HPCI pump discharge pressure less than or equal to 1100 psig on 3-PI-73-31A. If candidate exceeds Maximum Design Piping pressure of 1500 psig on 3-PI-73-31A while throttling 3-FCV-73-35 this would constitute unsatisfactory performance.
SAT_ UNSAT N/A COMMENTS:_____________________________
DRiVER: AFTER the applicant has demonstrated the ability to maintain Reactor Pressure between 800 and 1000 psig and the ability to control HPCI discharge pressure at or below 1100 psig and at the Chief Examiner cue, insert malfunction: imf hpO3 at 10% to fail HPCI flow controller in automatic
JPM c PAGE 11 OF 11 Performance Step 14: Critical X Not Critical
Standard:
Operator attempts to adjust HPCI SYSTEM FLOW/CONTROL, however, controller has failed downscale in automatic. Operator shifts controller to manual and adjusts HPCI flow.
Operator adjusts controller and 3-FCV-73-35 to control Reactor pressure.
SAT_ UNSAT N/A COMMENTS:________________________________
Performance Step 15: Critical Not Critical X
- a. OPEN 3-FCV-73-44, HPCI PUMP iNJECTION VALVE.
- c. GO TO EOI Appendix-5D.
Standard:
Operator monitors Reactor water level and determines HPCI injection to the RPV is not required SAT_ UNSAT N/A COMMENTS:__________________________
Cue: Injection to the RPV is not necessary at this time END OF TASK STOP TIME____
JPM d PAGE 1 OF 11 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: d TASK NUMBER: U-000-EM-63 TASK TITLE: 2-EOI-Appendix- 13 Emergency Venting Primary Containment KIA NUMBER: 295024 EA2.01 K/A RATING: RO 4.2 SRO 4.4 TASK STANDARD: 2-EOI-Appendix-13 complete with Drywell Pressure restored and maintained below 55 psig LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI-Appendix- 13 VALIDATION Tll\4E: 5 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are an operator. A large leak inside Primary Containment has developed on Unit 2. The Reactor has been scrammed and several control rods are not fully inserted. Primary containment pressure has exceeded the PSP curve (curve 6) and is approaching 55 psig and rising.
INITIATING CUE: The Unit Supervisor directs you to emergency vent Primary Containment as directed by 2-EOI Appendix 13 and maintain Primary Containment pressure below 55 psig
JPM d PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator. A large leak inside Primary Containment has developed on Unit 2. The Reactor has been scrammed and several control rods are not fully inserted. Primary containment pressure has exceeded the PSP curve (curve 6) and is approaching 55 psig and rising.
INITIATING CUE: The Unit Supervisor directs you to emergency vent Primary Containment as directed by 2-EOI Appendix 13 and maintain Primary Containment pressure below 55 psig
JPM d PAGE 4 OF 11 Simulator Driver: This JPM may require RIIR injection for level control START TIME____
Performance Step 1: Critical Not Critical X
- 1. NOTIFY Shift Manager / SED of the following:
- Emergency Venting of Primary Containment is in progress.
- Off-Gas Release Rate Limits will be exceeded.
Standard:
Operator notifies Shift Manager/SED SAT_ UNSAT N/A _COMMENTS:_____________________________
CUE: As Shift Manager/SED acknowledge report that Emergency Primary Containment Venting is in progress and Off-Gas release limits will be exceeded
JPM d PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
- 2. VENT the Suppression Chamber as follows (Panel 9-3):
- a. IF EITHER of the following exists:
- Suppression Pool water level CANNOT be determined to be below 20 ft, OR
- Suppression Chamber CANNOT be vented, THEN CONTINUE in this procedure at Step 3.
Standard:
Operator verifies Suppression Pool level below 20 ft using 2-LI 1 59A and does not continue to step 3 SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 3: Critical Not Critical
- b. PLACE keylock switch 2-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, in PERM.
Standard:
Operator places 2-HS-64-222B in the PERM position SAT UNSAT N/A _COMMENTS:_____________________________
JPM d PAGE 6 OF 11 Performance Step 4: Critical Not Critical
- c. CHECK blue indicating light above 2-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, illuminated.
Standard:
Operator verifies BLUE indicating lamp above 2-HS-64-222B Illuminated SAT UNSAT N/A COMMENTS:___________________________
Performance Step 5: Critical Not Critical X
Standard:
Operator places 2-HS-64-222A in the OPEN position and determines valve cannot be opened. Operator proceeds to set 3 by direction of step 2.a SAT UNSAT N/A COMMENTS:_______________________________
JPM d PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
- 3. IF Suppression Chamber vent path is NOT available, THEN VENT the Drywell as follows:
- a. NOTIFY Shift Manager / SED that Secondary Containment integrity failure is possible.
- b. NOTIFY Radiation Protection that Reactor Building is being evacuated due to imminent failure of Primary Containment vent ducts.
- c. EVACUATE ALL Reactor Buildings using P.A. System.
Standard:
Operator notifies the SM/SED that containment integrity failure is possible, notifies RP that the Reactor Building will be evacuated due to imminent failure of Primary Containment vent ducts, and makes P.A. announcement to evacuate Reactor Building.
SAT_ UNSAT N/A _COMMENTS:_____________________________
CUE: As SMISED acknowledge report of possible containment integrity failure, As RP acknowledge report of Reactor Building evacuation due to imminent failure of Primary Containment vent ducts.
Performance Stey 7: Critical Not Critical X
- d. START ALL available SGTS trains.
Standard:
Operator determines that all trains of SGTS are already in service SAT UNSAT N/A COMMENTS:_____________________________
JPM d PAGE 8 OF 11 Performance Step 8: Critical Not Critical
Standard:
Operator verifies 2-FCV-64-36 is closed on Panel 9-3 SAT_ U1JSAT N/A COMMENTS:_____________________________
Performance Step 9: Critical Not Critical
- f. VERIFY OPEN the following dampers (Panel 9-25):
Operator places control switches for dampers 2-FCO-64-40 and 2-FCO-64-41 to the open position on Panel 9-25 SAT UNSAT N/A COMMENTS:_______________________________
Performance Step 10: Critical Not Critical X
- g. VERIFY CLOSED 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 9-3 or Panel 9-54).
Standard:
Operator verifies 2-FCV-64-29 is closed on Panel 9-3 or Panel 9-54 SAT_ UNSAT N/A COMMENTS:_____________________________
JPM d PAGE 9 OF 11 Performance Step 11: Critical Not Critical X
- h. DISPATCH personnel to Unit 2 Auxiliary Instrument Room to perform the following:
- 1) REFER TO Attachment 1 and OBTAIN one 12-in, banana jack jumper from EOI Equipment Storage Box.
- 2) LOCATE terminal strip DD in Panel 9-43, Front.
- 3) JUMPER DD-76 to DD-77 (Panel 9-43).
Standard:
Operator contacts an AUO or an extra operator to perform step h.l) thru h.4)
SAT UNSAT N/A _COMMENTS:_____________________
CUE: When contacted to perform step h.1) thru h.4) provide repeat back and inform operator that the Jumper for 2-FCV-64-30 is in place Performance Step 12: Critical Not Critical
Standard:
Operator opens 2-FCV-64-30 on panel 9-3 SAT UNSAT N/A COMMENTS:___
JPM d PAGE 10 OF 11 Performance Step 13: Critical X Not Critical CAUTION
- The following step will fail ductwork inside Secondary Containment and may fail Secondary Containment Integrity.
- Off-Gas Release Rate Limits will be exceeded.
- j. PLACE keylock switch 2-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to DRYWELL (Panel 9-54).
Standard:
Operator places keylock switch 2-HS-84-36 to the DRYWELL position SAT_ UNSAT N/A COMMENTS:____________________________
Performance Step 14: Critical Not Critical X
Standard:
Operator verifies that 2-FCV-64-29 opens on Panel 9-54 SAT UNSAT N/A COMMENTS:_____________________________
JPM d PAGE 11 OF 11 Performance Step 15: Critical Not Critical
- 1. CHECK Drywell and Suppression Chamber pressure lowering.
- m. MAINTAIN Primary Containment pressure below 55 psig using 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, as directed by SRO.
Standard:
Operator checks that Drywell and Suppression Chamber pressure are lowering and informs SRO that Emergency Venting of the Drywell is in progress SAT UNSAT N/A COMMENTS:______________________________
CUE: As SRO acknowledge report of emergency venting of Drywell in progress.
JPM complete END OF TASK STOP TIME____
JPM d PAGE 1 OF 11 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: d TASK NUMBER: U-000-EM-63 TASK TITLE: 3-EOI-Appendix-13 Emergency Venting Primary Containment KJA NUMBER: 295024 EA2.01 K/A RATING: RO 4.2 SRO 4.4 TASK STANDARD: 3-EOI-Appendix-13 complete with Drywell Pressure restored and maintained below 55 psig LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3 -EOI-Appendix- 13 VALIDATION TIME: 5 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMiNER
INITIAL CONDITIONS: You are an operator. A large leak inside Primary Containment has developed on Unit 3. The Reactor has been scrammed and several control rods are not fully inserted. Primary containment pressure has exceeded the PSP curve (curve 6) and is approaching 55 psig and rising.
INITIATING CUE: The Unit Supervisor directs you to emergency vent Primary Containment as directed by 3-EOI Appendix 13 arid maintain Primary Containment pressure below 55 psig
JPM d PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an operator. A large leak inside Primary Containment has developed on Unit 3. The Reactor has been scrammed and several control rods are not fully inserted. Primary containment pressure has exceeded the PSP curve (curve 6) and is approaching 55 psig and rising.
INITIATING CUE: The Unit Supervisor directs you to emergency vent Primary Containment as directed by 3-EOI Appendix 13 and maintain Primary Containment pressure below 55 psig
JPM d PAGE 4 OF 11 Simulator Driver: This JPM may require RIIR injection for level control I
START TIME____
Performance Step 1: Critical Not Critical X
- 1. NOTIFY Shift Manager / SED of the following:
- Emergency Venting of Primary Containment is in progress.
- Off-Gas Release Rate Limits will be exceeded.
Standard:
Operator notifies Shift Manager/SED SAT UNSAT N/A COMMENTS:
CUE: As Shift Manager/SED acknowledge report that Emergency Primary Containment Venting is in progress and Off-Gas release limits wifi be exceeded
JPM d PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
- 2. VENT the Suppression Chamber as follows (Panel 9-3):
- a. IF EITHER of the following exists:
- Suppression Pool water level CANNOT be determined to be below 20 ft, OR
- Suppression Chamber CANNOT be vented, THEN CONTINUE in this procedure at Step 3.
Standard:
Operator verifies Suppression Pool level below 20 ft using 3-LI-64-159A and does not continue to step 3 SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 3: Critical Not Critical
- b. PLACE keylock switch 3-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, in PERM.
Standard:
Operator places 3-HS-64-222B in the PERM position SAT UNSAT N/A COMMENTS:_____________________________
JPM d PAGE 6 OF 11 Performance Step 4: Critical Not Critical X
- c. CHECK blue indicating light above 3-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, illuminated.
Standard:
Operator verifies BLUE indicating lamp above 3-HS-64-222B Illuminated SAT_ UNSAT N/A COMMENTS:________________________________
Performance Step 5: Critical Not Critical X
Standard:
Operator places 3-HS-64-222A in the OPEN position and determines valve cannot be opened. Operator proceeds to set 3 by direction of step 2.a SAT UNSAT N/A COMMENTS:_______________________________
JPM d PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
- 3. IF Suppression Chamber vent path is NOT available, THEN VENT the Drywell as follows:
- a. NOTIFY Shift Manager / SED that Secondary Containment integrity failure is possible.
- b. NOTIFY Radiation Protection that Reactor Building is being evacuated due to imminent failure of Primary Containment vent ducts.
- c. EVACUATE ALL Reactor Buildings using P.A. System.
Standard:
Operator notifies the SM/SED that containment integrity failure is possible, notifies RP that the Reactor Building will be evacuated due to imminent failure of Primary Containment vent ducts, and makes P.A. announcement to evacuate Reactor Building.
SAT_ UNSAT N/A COMMENTS:_____________________________
CUE: As SMJSED acknowledge report of possible containment integrity failure, As RP acknowledge report of Reactor Building evacuation due to imminent failure of Primary Containment vent ducts.
Performance Step 7: Critical Not Critical
- d. START ALL available SGTS trains.
Standard:
Operator determines that all trains of SGTS are already in service SAT_ UNSAT N/A COMMENTS:
JPM d PAGE 8 OF 11 Performance Step 8: Critical Not Critical X
- e. VERIFY CLOSED 3-FCV-64-36, DW/SUPPR CHBR VENT TO SOT (Panel 9-3)
Standard:
Operator verifies 3-FCV-64-36 is closed on Panel 9-3 SAT IJNSAT N/A _COMMENTS:____________________________
Performance Step 9: Critical Not Critical
- f. VERIFY OPEN the following dampers (Panel 9-25):
- 3-FCO-64-41, REACTOR ZONE EXH TO SOTS Standard:
Operator places control switches for dampers 3-FCO-64-40 and 3-FCO-64-41 to the open position on Panel 9-25 SAT UNSAT N/A _COMMENTS:_____________________________
Performance Step 10: Critical Not Critical X
- g. VERIFY CLOSED 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 9-3 or Panel 9-54).
Standard:
Operator verifies 3-FCV-64-29 is closed on Panel 9-3 or Panel 9-54 SAT UNSAT N/A _COMMENTS:_____________________________
JPM d PAGE 9 OF 11 Performance Step 11: Critical Not Critical
- h. DISPATCHpersonnel to Unit 3 Auxiliary Instrument Room to perform the following:
- 1) REFER TO Attachment 1 and OBTAIN one 12-in, banana jack jumper from EOI Equipment Storage Box.
- 2) LOCATE terminal strip DD in Panel 3-9-43, Front.
- 3) JUMPER DD-76 to DD-77 (Panel 3-9-43).
Standard:
Operator contacts an AUO or an extra operator to perform step h. 1) thru h.4)
SAT_ U1JSAT N/A COMMENTS:_____________________________
CUE: When contacted to perform step h.1) thru h.4) provide repeat back and inform operator that the Jumper for 3-FCV-64-30 is in place Performance Step 12: Critical Not Critical
Standard:
Operator opens 3-FCV-64-30 on panel 9-3 SAT UNSAT N/A COMMENTS:___
JPM d PAGE 10 OF 11 Performance Step 13: Critical X Not Critical CAUTION
- The following step will fail ductwork inside Secondary Containment and may fail Secondary Containment Integrity.
- Off-Gas Release Rate Limits will be exceeded.
- j. PLACE keylock switch 3-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to DRYWELL (Panel 9-54).
Standard:
Operator places keylock switch 3-HS-84-36 to the DRYWELL position SAT UNSAT N/A _COMMENTS:_____________________________
Performance Step 14: Critical Not Critical X
- k. VERIFY OPEN 3-FCV-64-29, DRYWELL VENT LNBD ISOL VALVE (Panel 9-54).
Standard:
Operator verifies that 3-FCV-64-29 opens on Panel 9-54 SAT UNSAT N/A _COMMENTS:________________________________
JPM d PAGE 11 OF 11 Performance Step 15: Critical Not Critical X
- 1. CHECK Drywell and Suppression Chamber pressure lowering.
- m. MAINTAIN Primary Containment pressure below 55 psig using 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE, as directed by SRO.
Standard:
Operator checks that Drywell and Suppression Chamber pressure are lowering and informs SRO that Emergency Venting of the Drywell is in progress SAT_ UNSAT N/A _COMMENTS:_____________________________
CUE: As SRO acknowledge report of emergency venting of Drywell in progress.
JPM complete END OF TASK STOP TIME____
JPM e PAGE 1 OF 10 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: e TASK NUMBER: U-085-SU-02 TASK TITLE: 2-SR-3.3.2.1.2 RWM Functional Test for Startup KJA NUMBER: 201006 A2.05 KJA RATING: RO 3.1 SRO 3.5 TASK STANDARD: Complete 2-SR-3.3.2.1.2 RWM Functional Test for Startup LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-SR-3.3.2.1.2 completed to step 7.0[1]
Ensure 2-SR-3.1.3.5(A) is open to Group 1 rods VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:__________________ DATE:
EXAMINER
INITIAL CONDITIONS: You are an Operator on Unit 2. Unit 2 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 2-01-85. Reactor Engineering has performed 2-SR-3.3.2.1.7.
2-SR-3 .3.2.1.2 RWM Functional Test for Startup is complete through step 7.0 [4].
INITIATING CUES: The Unit Supervisor has directed you to complete 2-SR-3.3.2. 1.2, RWM Functional Test for Startup, a Reactor Engineer is present and monitoring as needed
JPM e PAGE 3 OF 10 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Operator on Unit 2. Unit 2 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 2-01-85. Reactor Engineering has performed 2-SR-3 .3.2.1.7.
2-SR-3.3.2.1 .2 RWM Functional Test for Startup is complete through step 7.0 [4].
INITIATING CUES: The Unit Supervisor has directed you to complete 2-SR-3 .3.2.1.2, RWM Functional Test for Startup, a Reactor Engineer is present and monitoring as needed
JPM e PAGE 4 OF 10 START TIME____
Performance Step 1: Critical Not Critical NOTE ALL operations are performed on Panel 2-9-5 in the main Control Room unless otherwise noted.
[5] PLACE the Control Rod Drive (CRD) POWER switch (2-HS-85-46) momentarily to OFF AND next SWITCH to ON.
Standard:
Places the CRD Power switch to OFF and then ON SAT DNSAT N/A COMMENTS:____________________________
Performance Step 2: Critical Not Critical X
[6] VERIFY ALL control rods are deselected on the rod select matrix.
Standard:
Verifies all control rods are deselected SAT UNSAT N/A COMMENTS:
JPM e PAGE 5 OF 10 Performance Step 3: Critical Not Critical X
[7] PERFORM the RWM Functional Test as follows:
[7.1] VERIFY OR PLACE the RWM in operation per 2-01-85.
[7.2] REQUEST Reactor Engineering to PERFORM 2-SR-3.3.2.1.7 OR VERIFY performance of 2-SR-3 .3.2.1.7.
Standard:
Given in initial conditions SAT_ UNSAT N/A COMMENTS:_______________________________
Performance Step 4: Critical X Not Critical
[7.3] REFER to the Control Rod Movement Data Sheet from 2-SR-3.1.3.5(A) to identify a rod from RWM Group 02.
[7.4] RECORD below the rod chosen:
Rod Number:
Standard:
Refers to 2-SR-3.1 .3.5(A) and chooses a rod from Group 2, records identified rod (can be ANY control rod from RWM Group 2 (A2 Startup Sequence) (02-31, 26-07, 58-23, 42-55, 10-39, 42-07, 58-39, 26-55, 10-23, 50-15, 50-47, 18-47, 18-15, 50-31, 34-47, 18-31, 34-15, 42-39, 26-39, 26-23, 42-23, or 34-31)
SAT UNSAT N/A COMMENTS:_____________________________
JPM e PAGE 6 OF 10 Performance Step 5:
- Critical Not Critical
- [7.5] SELECT the rod recorded in Step 7.O[7.4].
[7.6] VERIFY the SELECT ERROR status block on the RWM display is in alarm (red background).
Standard:
Selects the rod previously recorded and verifies select error in alarm SAT_ UNSAT N/A COMMENTS:____________________________
Performance Step 6: *Critical X Not Critical
- [77] NOTCH the selected rod to position 02.
[7.8] VERIFY that the rod moved to position 02 is identified as a withdraw error on the RWM display.
Standard:
Notches the rod to position 02 and verifies a withdraw error on the display SAT_ UNSAT N/A COMMENTS:_____________________________
JPM e PAGE 7 OF 10 Performance Step 7: *Critical Not Critical
- [79] PLACE the CRD Control switch (2-HS-85-48) to ROD OUT NOTCH AND VERIFY the following:
[7.9.1] The selected control rod does NOT withdraw.
[7.9.2] The WITHDRAW BLOCK status block on the RWM display is in alarm (red background).
[7.9.3] RWM ROD BLOCK (2-XA-55-5B, Window 35) is in ALARM.
Standard:
Places the CRD control switch to ROD OUT NOTCH and verifies rod does not withdraw.
Verifies withdraw block status block on RWM display is in alarm as well as RWM Rod Block alarm 2-XA-55-5B, window 35.
SAT UNSAT N/A COMMENTS:_______________________________
Performance Step 8: Critical X Not Critical
[7.10] INSERT the selected rod from position 02 to 00.
Standard:
Inserts the selected rod from position 02 to 00 SAT_ NSAT N/A _COMMENTS:_____
JPM e PAGE 8 OF 10 Performance Step 9: Critical Not Critical
[7.11] REFER to the Control Rod Movement Data Sheet from 2-SR-3.1.3.5(A) to identify a rod from RWM Group 01.
[7.12] RECORD below the rod chosen:
Rod Number:
Standard:
Refers to 2-SR-3.1.3.5(A) and chooses a rod from Group 1, records identified rod (can be ANY control rod from RWM Group 1 (A2 Startup Sequence) (58-31, 34-07, 02-23, 18-55, 50-39, 19-07, 02-39, 34-55, 50-23, 10-15, 10-47, 42-47, 42-15, 10-31, 26-47, 42-31, 26-15, 18-39, 34-39, 34-23, 18-23, or 26-31)
SAT UNSAT N/A COMMENTS:____________________________
Performance Step 10: Critical X Not Critical
[7.13] SELECT the rod recorded in Step 7.0[7.12].
Standard:
Selects the rod recorded previously SAT_ UNSAT N/A COMMENTS:_____________________________
JPM e PAGE 9 OF 10 Performance Step 11: Critical Not Critical X
[7.14] VERIFY the WITHDRAW BLOCK status block on the RWM display is NOT in alarm.
[7.15] VERIFY RWM ROD BLOCK (2-XA-55-5B, Window 35) will RESET.
[7.16] VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.
Standard:
Verifies the Withdraw Block status block on the RWM display is not in alarm and resets alarm window 35 on 2-XA-55-5B. Verifies that Group 1 is indicated as the latched Group on the RWM panel SAT_ UNSAT N/A _COMMENTS:________________________________
Performance Step 12: *Critical X Not Critical NOTE RWM Rod Withdraw Block may be received whenever deselecting rod.
- [717] PLACE the Control Rod Drive (CRD) Power switch (2- HS 46) momentarily to OFF AND next SWITCH to ON.
[7.18] VERIFY ALL control rods are deselected on the rod select matrix.
Standard:
Places the CRD Power switch to OFF and then ON and verifies all control rods are deselected on the rod select matrix SAT UNSAT N/A COMMENTS:________________________________
JPM e PAGE 10 OF 10 Performance Step 13: Critical Not Critical X
[8] NOTIFY the UO that this SR test procedure is complete.
[9] NOTIFY the US that this SR test procedure is complete and obtain Acceptance Criteria Review on STS.
Standard:
Notifies personnel of completion and requests US review Acceptance Criteria from STS SAT UNSAT N/A _COMMENTS:________________________________
END OF TASK STOP TIME
JPM e PAGE 1 OF 10 OPERATOR:_______________________
RO___ SRO___ DATE:________
JPM NUMBER: e TASK NUMBER: U-085-SU-02 TASK TITLE: 3-SR-3.3.2.1.2 RWM Functional Test for Startup K/A NUMBER: 201006 A2.05 K/A RATING: RO 3.1 SRO 3.5 TASK STANDARD: Complete 3-SR-3.3.2.1.2 RWM Functional Test for Startup LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-SR-3.3.2.1.2 completed to step 7.O[1]
Ensure 3-SR-3.1.3.5(A) is open to Group 1 rods VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are an Operator on Unit 3. Unit 3 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 3-01-85. Reactor Engineering has performed 3-SR-3 .3.2.1.7.
3-SR-3 .3.2.1.2 RWM Functional Test for Startup is complete through step 7.0 [4].
INITIATING CUES: The Unit Supervisor has directed you to complete 3-SR-3.3.2.1.2, RWM Functional Test for Startup, a Reactor Engineer is present and monitoring as needed
JPM e PAGE 3 OF 10 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Operator on Unit 3. Unit 3 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 3-01-85. Reactor Engineering has performed 3-SR-3.3.2.1.7.
3-SR-3.3.2.l.2 RWM Functional Test for Startup is complete through step 7.0 [4).
INITIATING CUES: The Unit Supervisor has directed you to complete 3-SR-3.3.2.1.2, RWM Functional Test for Startup, a Reactor Engineer is present and monitoring as needed
JPM e PAGE 4 OF 10 START TIME____
Performance Step 1: Critical Not Critical X NOTE ALL operations are performed on Panel 3-9-5 in the main Control Room unless otherwise noted.
[5] PLACE the Control Rod Drive (CRD) POWER switch (3-HS-85-46) momentarily to OFF AND next SWITCH to ON.
Standard:
Places the CRD Power switch to OFF and then ON SAT UNSAT N/A COMMENTS:____________________________
Performance Step 2: Critical Not Critical X
[6] VERIFY ALL control rods are deselected on the rod select matrix.
Standard:
Verifies all control rods are deselected SAT UNSAT N/A COMMENTS:
JPM e PAGE 5 OF 10 Performance Step 3: Critical Not Critical X
[7] PERFORM the RWM Functional Test as follows:
[7.1] VERIFY OR PLACE the RWM in operation per 3-01-85.
[7.2] REQUEST Reactor Engineering to PERFORM 3-SR-3.3.2.1.7 OR VERIFY performance of 3-SR-3 .3.2.1.7.
Standard:
Given in initial conditions SAT_ U1SAT N/A COMMENTS:_____________________________
Performance Step 4: Critical X Not Critical
[7.3] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.5(A) to identif a rod from RWM Group 02.
[7.4] RECORD below the rod chosen:
Rod Number:
Standard:
Refers to 3-SR-3.1.3.5(A) and chooses a rod from Group 2, records identified rod (can be ANY control rod from RWM Group 2 (A2 Startup Sequence) (02-31, 26-07, 5 8-23, 42-55, 10-39, 42-07, 58-39, 26-55, 10-23, 50-15, 50-47, 18-47, 18-15, 50-3 1, 34-47, 18-31, 34-15, 42-39, 26-39, 26-23, 42-23, or 34-31)
SAT IJNSAT N/A COMMENTS:_____________________________
JPM e PAGE 6 OF 10 Performance Step 5:
- Critical X Not Critical SELECT the rod recorded in Step 7.O[7.4].
[7.6] VERIFY the SELECT ERROR status block on the RWM display is in alarm (red background).
Standard:
Selects the rod previously recorded and verifies select error in alarm SAT UNSAT N/A _COMMENTS:_______________________________
Performance Step 6: *Critical X Not Critical
- [77] NOTCH the selected rod to position 02.
[7.8] VERIFY that the rod moved to position 02 is identified as a withdraw error on the RWM display.
Standard:
Notches the rod to position 02 and verifies a withdraw error on the display SAT_ UNSAT N/A COMMENTS:______________________________
JPM e PAGE 7 OF 10 Performance Step 7: *Critical X Not Critical
[7.9] PLACE the CR0 Control switch (3-HS-85-48) to ROD OUT NOTCH AND VERIFY the following:
[7.9.1] The selected control rod does NOT withdraw.
[7.9.2] The WITHDRAW BLOCK status block on the RWM display is in alarm (red background).
[7.9.3] RWM ROD BLOCK (3-XA-55-5B, Window 35) is in ALARM.
Standard:
Places the CR0 control switch to ROD OUT NOTCH and verifies rod does not withdraw.
Verifies withdraw block status block on RWM display is in alarm as well as RWM Rod Block alarm 3-XA-55-5B, window 35.
SAT UNSAT N/A _COMMENTS:_________________________
Performance Step 8: Critical Not Critical
[7.10] INSERT the selected rod from position 02 to 00.
Standard:
Inserts the selected rod from position 02 to 00 SAT UNSAT N/A COMMENTS:_____
JPM e PAGE 8 OF 10 Performance Step 9: Critical Not Critical
[7.11] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.5(A) to identify arod from RWM Group 01.
[7.12] RECORD below the rod chosen:
Rod Number:
Standard:
Refers to 3-SR-3.1 .3.5(A) and chooses a rod from Group 1, records identified rod (can be ANY control rod from RWM Group 1 (A2 Startup Sequence) (58-31, 34-07, 02-23, 18-55, 50-39, 19-07, 02-39, 34-55, 50-23, 10-15, 10-47, 42-47, 42-15, 10-3 1, 26-47, 42-3 1, 26-15, 18-39, 34-39, 34-23, 18-23, or 26-3 1)
SAT UNSAT N/A COMMENTS:_________________________
Performance Step 10: Critical X Not Critical
[7.13] SELECT the rod recorded in Step 7.0[7.12].
Standard:
Selects the rod recorded previously SAT UNSAT N/A COMMENTS:
JPM e PAGE 9 OF 10 Performance Step 11: Critical Not Critical X
[7.14] VERIFY the WITHDRAW BLOCK status block on the RWM display is NOT in alarm.
[7.15] VERIFY RWM ROD BLOCK (3-XA-55-5B, Window 35) will RESET.
[7.16] VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.
Standard:
Verifies the Withdraw Block status block on the RWM display is not in alarm and resets alarm window 35 on 3-XA-55-5B. Verifies that Group 1 is indicated as the latched Group on the RWM panel SAT_ UNSAT N/A _COMMENTS:_________________________
Performance Step 12: *Critical X Not Critical NOTE RWM Rod Withdraw Block may be received whenever deselecting rod.
- [717] PLACE the Control Rod Drive (CRD) Power switch (3-HS 46) momentarily to OFF AND next SWITCH to ON.
[7.18] VERIFY ALL control rods are deselected on the rod select matrix.
Standard:
Places the CRD Power switch to OFF and then ON and verifies all control rods are deselected on the rod select matrix SAT_ UNSAT N/A
JPM e PAGE 10 OF 10 Performance Step 13: Critical Not Critical X
[81 NOTIFY the UO that this SR test procedure is complete.
[9] NOTIFY the US that this SR test procedure is complete and obtain Acceptance Criteria Review on STS.
Standard:
Notifies personnel of completion and requests US review Acceptance Criteria from STS SAT UNSAT N/A _COMMENTS:_______________________________
END OF TASK STOP TIME
JPM f PAGE 1 OF 8 OPERATOR:
RO SRO___ DATE:
JPM NUMBER: f TASK NUMBER: S-000-NO-054 TASK TITLE: USST 1 B Transformer Tap Changer Auto Checks KIA NUMBER: 262001 A4.05 KIA RATING RO 3.3 SRO 3.3 TASK STANDARD: Completes Auto Checks Of USST lB Tap Changer LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 0-GOI-300-4 VALIDATION TIME: 10 minutes PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator.
INITIATING CUE: The Unit Supervisor directs you to perform USST lB Transformer Tap Changer (LTC) Auto checks, in accordance with O-GOI-300-4, Switchyard Manual section 6.7.2.
JPM f PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator.
INITIATING CUE: The Unit Supervisor directs you to perform USST lB Transformer Tap Changer (LTC) Auto checks, in accordance with O-GOI-300-4, Switchyard Manual section 6.7.2.
JPM f PAGE 4 OF 8 START TIME____
Performance Step 1: Critical X Not Critical NOTES
- 1) Red light 1-IL-243-lBAabove the raise/lower control switch l-HS-243-1BA is illuminated only when tap changer position is being changed.
- 2) Section 6.7.2 is performed on Panel 0-9-23-3.
- 3) Sections 6.7.2, 6.7.3, and 6.7.4 may be performed in any order.
- 5) Tap Changer position is read from 1-ZI-243-1B USST lB TAP CHANGER POSITION 6.7.2 USST lB Transformer Tap Changer (LTC) Auto Checks
[1] PLACE load tap changer control selector switch l-HS-243-1BC, USST lB LTC CONTROL SEL in MANUAL.
Standard:
Places l-HS-243-1BC in Manual SAT_ UNSAT N/A COMMENTS:_______________________
Simulator Driver: GO TO Plant Systems Index PSI ED and Simulation Diagram when the applicant has placed 1-HS-243-1BC in MANUAL select FAIL AS IS
JPM f PAGE 5 OF 8 Performance Step 2: Critical X Not Critical
[2] PLACE -HS-243-IBA USST lB LTC CONTROL to the RAISE position and raise the tap changer one tap and OBSERVE the resultant voltage.
Standard:
Places l-HS-243-IBA to raise (turns to the left) raises the tap changer one tap.
SAT_ UNSAT N/A COMMENTS:
Performance Step 3: Critical X Not Critical X
[3] IF the voltage is less than 4275, THEN RAISE the tap changer one more tap as per step 6.7.2[2].
Standard:
Checks voltage and determines voltage is less than 4275 and places l-HS-243-1BA to raise (turns to the left) raises the tap changer one more tap.
SAT UNSAT N/A COMMENTS: 3 4a4 -
M.
JPM f PAGE 6 OF 8 Performance Step 4: Critical Not Critical X NOTES
- 1) The tap changer will probably return a full two taps to its original position, but a one-tap return is acceptable.
- 2) The tap changer may return to its original position and overshoot one tap or overshoot one tap and return to its original position. This is acceptable if the resulting voltage is acceptable.
[4] PLACE l-HS-243-IBC USST lB LTC CONTROL SEL in AUTO and CHECK the tap changer returns at least one tap in the direction of its original position.
Standard:
Places l-HS-243-IBC to Auto, and checks the TAP changer, determines that the TAP changer failed to change. Determines step 5 is required.
SAT UNSAT N/A COMMENTS:__________________________
Simulator Driver:
when the applicant places l-HS-243-1BC to back to MANUAL in the next step. Delete the override FAIL AS IS on the handswitch.
JPM f PAGE 7 OF 8 Performance Step 5: Critical Not Critical
[5] IF the tap changer does not automatically at least one tap in the direction of its original position, THEN PERFORM the following: (Otherwise N/A)
[5.1] PLACE 1-HS-243-1BC USST lB LTC CONTROL SEL in MANUAL.
Standard:
Places l-HS-243-IBC to Manual SAT_ UNSAT N/A COMMENTS:______________________________
Performance Step 6: Critical X Not Critical
[5.2] PLACE l-HS-243-1BA USST lB LTC CONTROL to the RAISE position and RAISE the tap changer a maximum of one more tap unless the voltage is already over 4,300V.
Standard:
Determines voltage is less than 4300 volts, and places l-HS-243-1BA to raise (turns to the left) raises the tap changer one tap.
SAT_ UNSAT N/A COMMENTS:_____________________________
JPM f PAGE 8 OF 8 Performance Step 7: Critical Not Critical
[5.3] PLACE l-HS-243-1BC USST lB LTC CONTROL SEL in AUTO and CHECK the tap changer returns at least one tap in the direction of its original position.
Standard:
Places 1-HS-243-1BC to Auto and checks the TAP changer returns at least one TAP in the direction of its original position.
SAT UNSAT N/A COMMENTS:_____________________________
END OF TASK STOP TIME
JPM g PAGE 1 OF 14 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: g TASK NUMBER: U-000-EM-61 TASK TITLE: 2-EOI Appendix-12 Primary Containment Venting KJA NUMBER: 295017 AA1.03 K!A RATING: RO 3.4 SRO: 3.4 TASK STANDARD: Vent Primary Containment JAW 2-EOI Appendix-12, after Suppression Chamber Vent path fails will vent through Drywell and flow adjusted to limit high release rates.
LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-12 VALIDATION TIME: 7 minutes MAX. TIME ALLOWED:
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Unit2 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P-i. 2-FIC-84-19 Path B Vent Flow Controller has been danger tagged for maintenance INITIATING CUE: The Unit Supervisor directs you to vent the pressure suppression chamber in accordance with 2-EOI Appendix-12.
JPM g PAGE 3 OF 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Unit2 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P-i. 2-FIC-84-19 Path B Vent Flow Controller has been danger tagged for maintenance INITIATING CUE: The Unit Supervisor directs you to vent the pressure suppression chamber in accordance with 2-EOI Appendix-i2.
JPM g PAGE 4 OF 14 START TIME____
Performance Step 1: Critical Not Critical CAUTION Stack release rates exceeding 1.4 x 1 Oi jtCi/s, or 0-SI-4.8.B. l.a. 1 release fraction above 1.0 will result in ODCM release limits being exceeded.
- 1. VERIFY at least one SGTS train in service.
Standard:
Verifies SOTS in service SAT_ UNSAT N/A COMMENTS:____________________________
Performance Step 2: Critical Not Critical X
- 2. VERIFY CLOSED the following valves (Panel 2-9-3 or Panel 2-9-54):
- 2-FCV-64-31, DRYWELL INBOARD ISOLATION VLV,
- 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,
- 2-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,
- 2-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.
Standard:
Verifies closed the above listed valves SAT UNSAT N/A COMMENTS:
JPM g PAGE 5 OF 14 Performance Step 3: Critical Not Critical X
- 3. IF While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.
Standard:
Verifies Suppression Pool Level below 20 feet SAT_ USAT N/A COMMENTS:_____________________________
Performance Step 4: Critical Not Critical X
- 4. IF While executing this procedure, the desired vent path is lost or can not be established, THEN PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.
Standard:
NA SAT IJNSAT N/A _COMMENTS:____________________________
Performance Step 5: Critical Not Critical X
- 5. IF While executing this procedure, CAD addition per SAMG-2, Step 0-4 OR G-9, is to begin, THEN BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.
Standard:
NA SAT UNSAT N/A _COMMENTS:_______________________________
CUE: CAD addition is not required
JPM g PAGE 6 OF 14 Performance Stei 6: Critical Not Critical X NOTE: Venting may be accomplished using EITHER:
- 2-FIC-84-19, PATH B VENT FLOW CONT, OR
- 2-FIC-84-20, PATH A VENT FLOW CONT.
NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented.
- 6. IF ANY of the following exists:
- Suppression Pool water level can not be determined to be below 20 ft, OR
- Suppression Chamber can NOT be vented, OR
- SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:
- Step 10 to vent the Drywell through 2-FCV-84-19, OR
- Step 11 to vent the Drywell through 2-FCV-84-20.
Standard:
Verifies Suppression Pool Level below 20 feet and proceeds to step 7 SAT_ U1JSAT N/A _COMMENTS:____________________________
JPM g PAGE 7 OF 14 Performance Step 7: Critical Not Critical X
- 7. CONTINUE in this procedure at:
- Step 8 to vent the Suppression Chamber through 2-FCV-84-19, OR
- Step 9 to vent the Suppression Chamber through 2-FCV-84-20.
Standard:
Continues at Step 9 SAT_ UNSAT N/A _COMMENTS:
NRC: Candidate must start at step 9, due to 2-FIC-84-19 tagged out I
Performance Step 8: Critical X Not Critical
- 9. VENT the Suppression Chamber using 2-FIC-84-20, PATH A VENT FLOW CONT, as follows:
- a. VERIFY OPEN 2-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 2-9-3).
Standard:
Opens 2-FCV 141 SAT UNSAT N/A COMMENTS:
JPM g PAGE 8 OF 14 Performance Step 9: Critical X Not Critical
- b. PLACE keylock switch 2-HS-84-36, SUPPR CHBRDW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 2-9-54).
Standard:
Places 2-HS-84-36 in the SUPPR-CHBR position, When 2-HS-84-36 is placed in SUPPR-CHBR position 2-FCV-64-34 will not re-position and candidate will inform Unit Supervisor unable to vent the Suppression Chamber SAT_ UNSAT N/A _COMMENTS:____________________________
I CUE: SRO directs Drywdll Venting I NRC: Candidate will proceed to step 13 and secure Venting Lineup Performance Step 10: Critical Not Critical
- 13. WHEN ANY of the following exists:
- Venting is no longer required,
- Pressure in the space being vented approaches zero,
- Directed by Step 3, 4, or 5, THEN SECURE venting as follows:
- a. VERIFY the following keylock switches in OFF (Panel 2-9-54):
Standard:
Operator places 2-HS-84-36 in Off SAT_ UNSAT N/A COMMENTS:_______________________________
JPM g PAGE 9 OF 14 Performance Step 11: Critical Not Critical X
- b. VERIFY keylock switch 2-HS-84-20, 2-FCV-84-20 ISOLATION BYPASS, in NORMAL (Panel 2-9-55).
Standard:
Operator verifies keylock switch 2-HS-84-20 is in NORMAL SAT_ UNSAT N/A COMMENTS:_______________________________
Performance Step 12: Critical Not Critical
- c. VERIFY keylock switch 2-HS-84-19, 2-FCV-84-19 CONTROL, in CLOSE (Panel 2-9-55).
Standard:
Verifies 2-HS-84-19 is in Close SAT UNSAT N/A _COMMENTS:____________________________
Performance Step 13: Critical Not Critical X
- d. VERIFY CLOSED the following valves (Panel 2-9-3 or Panel 2-9-54):
- 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,
- 2-FCV-64-32, SUPPR CHBR VENT NBD ISOL VALVE.
Standard:
Verifies above listed valves are closed SAT UNSAT N/A COMMENTS:
JPM g PAGE 10 OF 14 Performance Step 14: Critical Not Critical
- e. VERIFY CLOSED 2-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 2-9-3).
Standard:
Closes 2-FCV 141 SAT UNSAT N/A _COMMENTS:_____________________________
NRC: Candidate will proceed to step 11 and Vent the Drywell through the 2-FIC-84-20 Path A Vent Flow Controller flowpath Performance Step 15: Critical Not Critical X
- 11. VENT the Drywell using 2-FIC-84-20, PATH A VENT FLOW CONT, as follows:
- a. VERIFY CLOSED 2-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 2-9-3).
Standard:
Verifies Closed 2-FCV-64-141 SAT UNSAT N/A COMMENTS:
JPM g PAGE 11 OF 14 Performance Step 16: Critical X Not Critical
- b. PLACE keylock switch 2-HS-84-35, SUPPR CHBR / DW VENT ISOL BYP SELECT, to DRYWELL position (Panel 2-9-54).
Standard:
Places 2-HS-84-35 in the DRYWELL position SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 17: Critical Not Critical X
- c. VERIFY OPEN 2-FCV-64-31, DRYWELL INBD ISOL VALVE (Panel 2-9-54).
Standard:
Verifies 2-FCV-64-3 1 Opens SAT_ UNSAT N/A COMMENTS:_______________________________
Performance Step 18: Critical Not Critical X
- d. VERIFY 2-FIC-84-20, PATH A VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 2-9-55).
Standard:
Verifies 2-FIC-84-20 in Auto at 100 SCFM SAT_ UNSAT N/A COMMENTS:_____________________________
JPM g PAGE 12 OF 14 Performance Step 19: Critical X Not Critical
- e. PLACE keylock switch 2-HS-84-20, 2-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 2-9-55).
Standard:
Places 2-HS-84-20 in the BYPASS position SAT UNSAT N/A _COMMENTS:_______________________________
Performance Step 20: Critical Not Critical X
- f. VERIFY 2-FIC-84-.20, PATH A VENT FLOW CONT, is indicating approximately 100 scfm.
Standard:
Verifies 2-FIC-84-20 is indicating approximately 100 scfm and continues at step 12 SAT UNSAT N/A _COMMENTS:_______________________________
JPM g PAGE 13 OF 14 Performance Step 21: Critical Not Critical
- 12. ADJUST 2-FIC-84-19, PATH B VENT FLOW CONT, or 2-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:
- Stable flow as indicated on controller, AND
- 2-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND
- Release rates as determined below:
- i. IF PRIMARY CONTAINMENT FLOODING per C-i, Alternate Level Control, is in progress, THEN MAINTAIN release rates below those specified in Attachment 2.
ii. IF Severe Accident Management Guidelines are being executed, THEN MAINTAIN release rates below those specified by the TSC SAM Team.
iii. IF Venting for ANY other reason than items i or ii above, THEN MAINTAIN release rates below
- Stack release rate of 1.4 x 107 iCi/s AND
- 0-SI-4.8.B.i.a.i release fraction of 1.
Standard:
Request release rates from Log AUO SAT UNSAT N/A _COMMENTS:
CUE: Primary Containment Flooding and SAMG are not being executed CUE: When Release rates are requested hand operator First Requested Log Sheets
JPM g PAGE 14 OF 14 Performance Step 22: Critical X Not Critical REDUCE vent flow to obtain acceptable release rate/fraction readings.
Standard:
Recognized exceeding Release Rate Limit of 1.4 x 1 ü tCi/s and the release fraction and lowers discharge flow rate using 2-FIC-84-20 SAT_ UNSAT N/A _COMMENTS:____________________________
CUE: After flow is reduced hand operator Second Requested Log Sheets STOP TIME END OF TASK
JPM g PAGE 1 OF 14 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: g TASK NUMBER: U-000-EM-61 TASK TITLE: 3-EOI Appendix-12 Primary Containment Venting KJA NUMBER: 295017 AA1.03 K/A RATING: RO 3.4 SRO: 3.4 TASK STANDARD: Vent Primary Containment JAW 3-EOI Appendix-12, after Suppression Chamber Vent path fails will vent through Drywell and flow adjusted to limit high release rates.
LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-12 VALIDATION TIME: 7 minutes MAX. TIME ALLOWED:
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Unit 3 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P-i. 3-FIC-84-19 Path B Vent Flow Controller has been danger tagged for maintenance INITIATING CUE: The Unit Supervisor directs you to vent the pressure suppression chamber in accordance with 3-EOI Appendix-12.
JPM g PAGE 3 OF 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Unit 3 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P-i. 3-FIC-84-i9 Path B Vent Flow Controller has been danger tagged for maintenance INITIATING CUE: The Unit Supervisor directs you to vent the pressure suppression chamber in accordance with 3-EOI Appendix-12.
JPM g PAGE 4 OF 14 START TIME____
Performance Step 1: Critical Not Critical X CAUTION Stack release rates exceeding 1.4 x 107 iCi/s, or 0-SI-4.8.B. l.a. 1 release fraction above 1.0 will result in ODCM release limits being exceeded.
- 1. VERIFY at least one SGTS train in service.
Standard:
Verifies SGTS in service SAT_ UNSAT N/A COMMENTS:__________________________
Performance Step 2: Critical Not Critical X
- 2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):
- 3-FCV-64-31, DRYWELL iNBOARD ISOLATION VLV,
- 3-FCV-64-29, DRYWELL VENT 1NBD ISOL VALVE,
- 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,
- 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.
Standard:
Verifies closed the above listed valves SAT UNSAT N/A COMMENTS:__________________
JPM g PAGE 5 OF 14 Performance Step 3: Critical Not Critical X
- 3. IF While executing this procedure to vent the Suppression Chamber, Suppression Pool water level can not be determined to be below 20 ft, THEN PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.
Standard:
Verifies Suppression Pool Level below 20 feet SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 4: Critical Not Critical
- 4. IF While executing this procedure, the desired vent path is lost or can not be established, THEN PERFORM step 13 to secure the vent path and reenter this procedure if further venting is required.
Standard:
NA SAT_ UNSAT N/A COMMENTS:_____________________________
Performance Step 5: Critical_ Not Critical X
- 5. IF While executing this procedure, CAD addition per SAMG-2, Step G-4 OR G-9, is to begin, THEN BEFORE CAD is initiated, PERFORM Step 13 to secure the vent path.
Standard:
NA SAT_ UNSAT N/A COMMENTS:_____________________________
CUE: CAD addition is not required
JPM g PAGE 6 OF 14 Performance Step 6: Critical Not Critical X NOTE: Venting may be accomplished using EITHER:
- 3-FIC-84-19, PATH B VENT FLOW CONT, OR
- 3-FIC-84-20, PATH A VENT FLOW CONT.
NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY should be performed ONLY if the Suppression Chamber can NOT be vented.
- 6. IF ANY of the following exists:
- Suppression Pool water level can not be determined to be below 20 ft, OR
- Suppression Chamber can NOT be vented, OR
- SRO orders DIRECT drywell venting, THEN CONTINUE in this procedure at:
- Step 10 to vent the Drywell through 3-FCV-84-19, OR
- Step 11 to vent the Drywell through 3-FCV-84-20.
Standard:
Verifies Suppression Pool Level below 20 feet and proceeds to step 7 SAT UNSAT N/A COMMENTS:______________________________
JPM g PAGE 7 OF 14 Performance Step 7: Critical Not Critical X
- 7. CONTINUE in this procedure at:
- Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR
- Step 9 to vent the Suppression Chamber through 3-FCV-84-20.
Standard:
Continues at Step 9 SAT UNSAT N/A _COMMENTS:
NRC: Candidate must start at step 9, due to 3-FIC-84-19 tagged out I
Performance Step 8: Critical X Not Critical
- 9. VENT the Suppression Chamber using 3-FIC-84-20, PATH A VENT FLOW CONT, as follows:
- a. VERIFY OPEN 3-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).
Standard:
Opens 3 -FCV 141 SAT_ UNSAT N/A COMMENTS:
JPM g PAGE 8 OF 14 Performance Step 9: Critical X Not Critical
- b. PLACE keylock switch 3-HS-84-36, SUPPR CHBRIDW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).
Standard:
Places 3-HS-84-36 in the SUPPR-CHBR position, When 3-HS-84-36 is placed in SUPPR-CHBR position 3-FCV-64-34 will not re-position and candidate will inform Unit Supervisor unable to vent the Suppression Chamber SAT_ USAT N/A COMMENTS:________________________________
I CUE: SRO directs Drywell Venting I NRC: Candidate will proceed to step 13 and secure Venting Lineup Performance Step 10: Critical Not Critical X
- 13. WHEN ANY of the following exists:
- Venting is no longer required,
- Pressure in the space being vented approaches zero,
- Directed by Step 3, 4, or 5, THEN SECURE venting as follows:
- a. VERIFY the following keylock switches in OFF (Panel 3-9-54):
Standard:
Operator places 3-HS-84-36 in Off SAT_ UNSAT N/A COMMENTS:______________________________
JPM g PAGE 9 OF 14 Performance Step 11: Critical Not Critical
- b. VERIFY keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in NORMAL (Panel 3-9-55).
Standard:
Operator verifies keylock switch 3-HS-84-20 is in NORMAL SAT UNSAT N/A _COMMENTS:____________________________
Performance Step 12: Critical Not Critical X
- c. VERIFY keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in CLOSE (Panel 3-9-5 5).
Standard:
Verifies 3-HS-84-19 is in Close SAT UNSAT N/A _COMMENTS:______________________________
Performance Step 13: Critical Not Critical X
- d. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):
- 3-FCV-64-3l, DRYWELL 1NBD ISOLATION VLV,
- 3-FCV-64-29, DRYWELL VENT TNBD ISOL VALVE,
- 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.
Standard:
Verifies above listed valves are closed SAT UNSAT N/A COMMENTS:
JPM g PAGE 10 OF 14 Performance Step 14: Critical Not Critical
- e. VERIFY CLOSED 3-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).
Standard:
Closes 3-FCV-64-141 SAT UNSAT N/A _COMMENTS:_____________________________
NRC: Candidate will proceed to step 11 and Vent the Drywell through the 3-FIC-84-20 Path A Vent Flow Controller flowpath Performance Step 15: Critical Not Critical X
- 11. VENT the Drywell using 3-FIC-84-20, PATH A VENT FLOW CONT, as follows:
- a. VERIFY CLOSED 3-FCV-64-l4l, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).
Standard:
Verifies Closed 3-FCV-64-141 SAT UNSAT N/A COMMENTS:
JPM g PAGE 11 OF 14 Performance Step 16: Critical X Not Critical
- b. PLACE keylock switch 3-HS-84-35, SUPPR CHBR / DW VENT ISOL BYP SELECT, to DRYWELL position (Panel 3-9-54).
Standard:
Places 3-HS-84-35 in the DRYWELL position SAT UNSAT N/A _COMMENTS:____________________________
Performance Step 17: Critical Not Critical X
- c. VERIFY OPEN 3-FCV-64-31, DRYWELL LNBD ISOL VALVE (Panel 3-9-54).
Standard:
Verifies 3-FCV-64-3 1 Opens SAT UNSAT N/A _COMMENTS:_____________________________
Performance Step 18: Critical Not Critical X
- d. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).
Standard:
Verifies 3-FIC-84-20 in Auto at 100 SCFM SAT UNSAT N/A _COMMENTS:_____________________________
JPM g PAGE 12 OF 14 Performance Step 19: Critical X Not Critical
- e. PLACE keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 3-9-55).
Standard:
Places 3-HS-84-20 in the BYPASS position SAT UNSAT N/A _COMMENTS:____________________________
Performance Step 20: Critical Not Critical X
- f. VERIFY 3-FIC-84-20, PATH A VENT FLOW CONT, is indicating approximately 100 scfm.
Standard:
Verifies 3-FIC-84-20 is indicating approximately 100 scfm and continues at step 12 SAT UNSAT N/A _COMMENTS:_____________________________
JPM g PAGE 13 OF 14 Performance Step 21: Critical X Not Critical
- 12. ADJUST 3-FIC-84-19, PATH B VENT FLOW CONT, or 3-FIC-84-20, PATH A VENT FLOW CONT, as applicable, to maintain ALL of the following:
- Stable flow as indicated on controller, AND
- 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND
- Release rates as determined below:
- i. IF PRIMARY CONTMNMENT FLOODfNG per C-i, Alternate Level Control, is in progress, THEN MAINTAIN release rates below those specified in Attachment 2.
ii. IF Severe Accident Management Guidelines are being executed, THEN MAINTAIN release rates below those specified by the TSC SAM Team.
iii. IF Venting for ANY other reason than items i or ii above, THEN MAINTAIN release rates below
- Stack release rate of 1.4 x 107 pCi/s AND
- 0-SI-4.8.B.1.a.i release fraction of 1.
Standard:
Request release rates from Log AUO SAT U1JSAT N/A COMMENTS:
CUE: Primary Containment Flooding and SAMG are not being executed CUE: When Release rates are requested hand operator First Requested Log Sheets
JPM g PAGE 14 OF 14 Performance Step 22: Critical X Not Critical REDUCE vent flow to obtain acceptable release rate/fraction readings.
Standard:
Recognized exceeding Release Rate Limit of 1.4 x 1 O jtCi/s and the release fraction and lowers discharge flow rate using 3-FIC-84-20 SAT UNSAT N/A COMMENTS:____________________________
CUE: After flow is reduced hand operator Second Requested Log Sheets STOP TIME END OF TASK
BFN Airborne Effluent Release Rate 0-Sl-4.8.B.1.a.1 Unit 0 Rev. 0055 Page 40 of 56 First requested LOG Attachment 6 (Page lof 2)
Elevated Effluent Release Rate Log rToday Today Week From To S 0-RM90-147 0-RM-80-146 STACK FLOW RATE A H 0-FI-90-271 ..TACK RELEA.E y I Red Pen Green Pen INOP<16 366 RATE F GROSS COUNT RATE GROSS COUNT RATE (NOTES 1 & 3) OR (NOTE 2)
T (CPS) (C PS) HIGHEST GROSS A1TACH 7 CONVERSION (jiCi!SEC) 7.0[11iJ 7.0[11 .1] COUNT RATE (CPS) 7.0[1 t2] FACTOR 7.011 1.3] & 7.0[1 1.4)
F D 5.75 x e5 5.70 x e5 5.75 x e5 22700 1.23Bo3 1.6 x e7 R N I 1.23E-03 S D 1.23E-03 A N 1.23E..03 S D 1.23E-03 U N t23E-03 M D 1.23E-03 0 N t23E-03 T D t23E-03 U N I .23E-03 W D 1.23E-03 N t23E-03 T D t23E-03 H N 1.23E-03 1 Minimum acceptable flowrate for O-fi-90-271 operability is 16,366 SCFM (See note 3) 2 Data from manual sampling results or O-90-147/148[(Stack flow) X (l-lghest gross count rate) X 1 .23E-03j.
3 The minimum stack flow rate was revised to 16,366 SCFM (BFPER980545).
BFN Airborne Effluent Release Rate 0-Sl-4.8.Bi.a.1 Unit 0 Rev. 0055 Page 30 of 56 First requested LOG Attachment 2 (Page 1 ofl)
Site Effluent Release Rate Summary Today Today Week From To D S SI STEP Reactor Power (MWT) Building Initials A H Ventilation Total Site Y I Release Rate Stack Release Release Rate F Unit 1 Unit 2 Unit 3 Fraction Rate Fraction Fraction Acceptance Unit T 7.0[6] 70[7] 7.()[8.1j 71)181] 7.0[8.1) 71)[10.6] 7.0[1i.9] 7.0 12 Criteria AUO Supervisor FRI JR ]_JR 3440 0 3448 -j 0.09 [_. fjj__ 1.2 JR F DZ j.
SAT D 1.00 id SUN 0 i.o0 id 1.00 MON D 1.00 id 1.00 TUE 0 1.00 ici 1.OO WED D 100 N 1.00 THU 0 1.00 Initials added as a result of BFPER 960634.
BFN Airborne Effluent Release Rate 0-Sl-4.8.B.1.a.1 UnitO Rev. 0055 Page 40 of 56 Attachment 6 Second requested LOG (Page 1 of 2)
Elevated Effluent Release Rate Log Today Today Week From To D S O-RM-90-147 O-RM-90-148 STACK FLOW RATE A H 0-9-90-271 STACK RELEASE y i Red Pen Green Pen INOP<tlS 366 RATE F GROSS COUNT RATE GROSS COUNT RATE (NOTES 1 & 3) OR (NOTE 2)
T (CPS) (CPS) H(GHEST GROSS ATTACH? CONVERSION (IICUSEC) 7.O[11.1] 70[11.1] COUNTRATE(CPS) 7.O[11.21 FACTOR 7.0[1 1.3]& 70[11.4]
F R
0 N
4.65 x e5 4.6 x e5
[ 4.65 x e5 22700 I i.23E-03 1.23E-03 1.3 x e7 JE S 0 1 .23E-03 A N 1.23E-03 S 0 1.23E-03 U N 1.23E-03 M 0 1.23E-03 0 N 1.23E-03 T 0 123E-03
-ii N 1.23E-03 W D 1.23E-03 E N t23E-03 T 0 1 .23E-03 H N 1 .23E-03 1 Minimum acceptable flowrate for 041-90-271 operability is i6366 SCFM (See note 3) 2 Data from manual samphng results or 0-90-1471148[(Stack flow) X (highest gross count rate) X 1 .23E-03].
3 The minimum stack flow rate was revised to 16,366 Sc.FM (8FPER980545).
BFN Airborne Effluent Release Rate 0-Sl-4.8.B.1.a.1 UnitO Rev. 0055 Page 30 of 56 Attachment 2 Second requested LOG (Page 1 of 1)
Site Effluent Release Rate Summary Today Today Week From To D S SI STEP Reactor Power (MVT) Building Initials A H Ventilation Total Site Y I Release Rate Stack Release Release Rate F Unit 1 Unit 2 Unit 3 Fraction Rate Fraction Fraction Acceptance Unit T 7.0161 7 0171 7018.11 7 018.11 7 018.11 7 0110.61 Criteria Sunerviso FRI D N
JR L ]_JR 3440 0 3448 [ j_0.09 jjj 1.00 1.00 DZ L SAT D 1.00 N 1.00 SUN D MON D 1.00 1.00 TUE D 1.00 1.00 WED D 1.00 ii 1.00 THU D 1.00 1.00 Initials added as a result of BFPER 960634.
JPM h PAGE 1 OF 8 OPERATOR:
RO___ SRO DATE:
JPM NUMBER: h TASK NUMBER: U-001-NO-08 TASK TITLE: Close MSIVs during Power Operations KJA NUMBER: 239001 A4.0l KIA RATING: RO 4.2 SRO 4.0 TASK STANDARD: Closes Inboard and Outboard MSIVs on Main Steam Line C LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-01-1 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY___
SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. B Inboard Main Steam Isolation Valve, 2-FCV-1-26, has a failed LS-3 and fuse 2-FU1-1-27B has been pulled.
No other MSIVs LS-3 or LS-4 is failed. Precautions and limitations of 2-01-1, Main Steam System, have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 2-01-1, Main Steam System, section 8.2
JPM h PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. B Inboard Main Steam Isolation Valve, 2-FCV- 1-26, has a failed LS-3 and fuse 2-FU 1-1 -27B has been pulled.
No other MSIVs LS-3 or LS-4 is failed. Precautions and limitations of 2-01-1, Main Steam System, have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 2-01-1, Main Steam System, section 8.2
JPM h PAGE 4 OF 8 START TIME____
Performance Step 1: Critical Not Critical X 8.2.3 Closing Main Steam Line C Valve(s) During Power Operations NOTES
- 1) Test stroking an MSIV to the closed position takes about 45-60 seconds.
- 2) LS-5 limit switches cause the MSIV green position indicator light to illuminate at 85% open. The LS-3 and LS-4 limit switches for the Unit 2 MISVs actuate at 90% open to initiate a reactor scram via the RPS. During MSIV testing, a half-scram initiation signal will be received before the green position indicator light illuminates.
- 3) Closing a MSIV with another main steam line MSIV closed or a failed LS-3 or LS-4 switch, may cause a half or a full reactor scram. REFER TO Illustrations 1 and 2.
- 4) Main Steam Line Flow Indication goes to the Reactor Feed Control System.
Closing and Opening a MSIV will cause a fluctuation in the Reactor Feed Water System.
[1] REVIEW all Precautions and Limitations in Section 3.0.
[2] VERIFY that ALL MSIVs are open.
[3] CHECK by administration means that no MSIVs LS-3 or LS-4 has failed (i.e.,
Narrative Logs, Caution Orders, Work Orders).
[4] IF a failed LS-3 or LS-4 for a MSIV has been determined, THEN CHECK that a Half Scram will NOT occur when the valve to be operated is closed. (REFER TO Illustrations 1 and 2, and RPS Logic prints 730E915)
[5] IF a Half Scram is expected to occur, THEN STOP and OBTAIN Unit Supervisors permission to continue in the procedure.
[6] VERIFY or LOWER Reactor Power to 66% per 2-GOI-100-12 or 2-GOI-100-12A.
Standard:
Given in initial conditions for step 3, verifies with Illustrations 1 and 2 that a Half Scram will not occur when the C Steam Line MSIVs are closed, power is less than 66%
SAT_ UNSAT N/A _COMMENTS:____________________________
JPM h PAGE 5 OF 8 Performance Step 2: Critical X Not Critical NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.3A, 3.3B and 3.3C should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.2.1B.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[7] PERFORM the following to close MSIV LINE C INBOARD MSIV:
[7.1] DEPRESS and HOLD MSIV LINE C INBOARD TEST, 2-HS-1-37B push button until Step 8.2.3 [7.3].
[7.2] WHEN MSIV LINE C INBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3 [7.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C INBOARD, 2-HS-1-37A in the CLOSE position.
[7.3] RELEASE MSIV LINE C INBOARD TEST, 2-HS-l-1-37B push-button Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT_ UNSAT N/A COMMENTS:
JPM h PAGE 6 OF 8 Performance Step 3: Critical X Not Critical NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.3A, 3.3B and 3.3C should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.2.1B.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[8] PERFORM the following to close MSIV LINE C OUTBOARD MSIV:
[8.1] DEPRESS and HOLD MSIV LINE C OUTBOARD TEST, 2-HS-1-38B push button until Step 8.2.3[8.3].
[8.2] WHEN MSIV LINE C OUTBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3 [8.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C OUTBOARD, 2-HS-1-38A in the CLOSE position.
[8.3] RELEASE MSIV LINE C OUTBOARD TEST, 2-HS-l-1-38B push-button.
Standard:
Operator depresses and holds the MSIV Line C Outboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A _COMMENTS:_____________________________
JPM h PAGE 7 OF 8 Performance Step 4: Critical Not Critical NOTES
- 1) When turbine generator RPM is above 1700 and one or more MSIVs fully close, Valves 2-FCV-1-168, -169, -170, and -171 will close and Valves 2-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF, and 2-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER opens, if closed, and their handswitches are in AUTO.
- 2) When opening the 2-FCV-1-55 and 2-FCV-56, Main Steam Line Drain Valves the HWC system may isolate on LOW OFFGAS Oxygen.
[9] OPEN 2-FCV-1-55 using MN STM LINE DRAIN INBD ISOLATION VLV, 2-HS-1-55A.
Standard:
Opens drain valve 2-FCV-1-55 SAT UNSAT N/A COMMENTS:__________________________
Performance Step 5: Critical X Not Critical
[10] OPEN 2-FCV-1-56 using MN STM LINE DRAIN OUTBD ISOLATION VLV, 2-HS- 1 -56A.
Standard:
Opens drain valve 2-FCV-1-56 SAT UNSAT N/A COMMENTS:
JPM h PAGE 8 OF 8 Performance Step 6: Critical Not Critical X
[11] VERIFY OPEN 2-FCV-1-57 using MSIV DOWNSTREAM DRAINS SHUTOFF, 2-HS-1 -57A.
[12] VERIFY OPEN 2-FCV-1-58 using UPSTREAM MSL DRAIN TO CONDENSER, 2-HS- 1 -58A.
[13] CHECK CLOSED valves 2-FCV-1-168, -169, -170, and -171, ON 2-PNL-9-3 as follows:
VERIFY the green indicating light ILLUMINATED and the red indicating light EXTINGUISHED for MAIN STM LINE DRAIN VALVES POSITION, 2-ZI-1-174.
Standard:
Verifies 2-FCV-1-57 and 58 are open and that 2-FCV-1-168, 169, 170, and 171 are closed.
SAT_ UNSAT N/A _COMMENTS:_____________________________
Performance Step 7: Critical Not Critical X
[14] IF desired AND directed by the Unit Supervisor, THEN RAISE Reactor Power per 2-GOI-100-12, while maintaining the remaining steam lines below an average of 3.54 x 106 ibm/hr steam flow (approximately 80% Reactor Power), on the remaining three main steam lines.
Standard:
None, another Operator will raise power.
SAT_ U1JSAT N/A _COMMENTS:_______________________________
CUE: Another Operator will raise Reactor Power END OF TASK STOP TIME
JPM h PAGE 1 OF 8 OPERATOR:
RO___ SRO___ DATE:
JPM NUMBER: h TASK NUMBER: U-00 1 -NO-08 TASK TITLE: Close MSIVs during Power Operations K/A NUMBER: 239001 A4.01 K/A RATING: RO 4.2 SRO 4.0 TASK STANDARD: Closes Inboard and Outboard MSIVs on Main Steam Line C LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-01-1 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ U1SSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. B Inboard Main Steam Isolation Valve, 3-FCV-1-26, has a failed LS-3 and fuse 3-FU1-l-27B has been pulled.
No other MSTVs LS-3 or LS-4 is failed. Precautions and limitations of 3-01-1, Main Steam System, have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 3-01-1, Main Steam System, section 8.2
JPM h PAGE 3 OF 8 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say my task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. B Inboard Main Steam Isolation Valve, 3-FCV-1-26, has a failed LS-3 and fuse 3-FU1-l-27B has been pulled.
No other MSIVs LS-3 or LS-4 is failed. Precautions and limitations of 3-01-1, Main Steam System, have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 3-01-1, Main Steam System, section 8.2
JPM h PAGE 4 OF 8 START TIME____
Performance Step 1: Critical Not Critical 8.2.3 Closing Main Steam Line C Valve(s) During Power Operations NOTES
- 1) Test stroking an MSIV to the closed position takes about 45-60 seconds.
- 2) LS-5 limit switches cause the MSIV green position indicator light to illuminate at 85% open. The LS-3 and LS-4 limit switches for the Unit 3 MISVs actuate at 90% open to initiate a reactor scram via the RPS. During MSIV testing, a half-scram initiation signal will be received before the green position indicator light illuminates.
- 3) Closing a MSIV with another main steam line MSIV closed or a failed LS-3 or LS-4 switch, may cause a half or a full reactor scram. REFER TO Illustrations 1 and 2.
- 4) Main Steam Line Flow Indication goes to the Reactor Feed Control System.
Closing and Opening a MSIV will cause a fluctuation in the Reactor Feed Water System.
[1] REVIEW all Precautions and Limitations in Section 3.0.
[2] VERIFY that ALL MSIVs are open.
[3] CHECK by administration means that no MSIVs LS-3 or LS-4 has failed (i.e.,
Narrative Logs, Caution Orders, Work Orders).
[4] IF a failed LS-3 or LS-4 for a MSIV has been determined, THEN CHECK that a Half Scram will NOT occur when the valve to be operated is closed. (REFER TO Illustrations 1 and 2, and RPS Logic prints 730E915)
[5] IF a Half Scram is expected to occur, THEN STOP and OBTAIN Unit Supervisors permission to continue in the procedure.
[6] VERIFY or LOWER Reactor Power to 66% per 3-GOI-100-12 or 3-GOI-100-12A.
Standard:
Given in initial conditions for step 3, verifies with Illustrations 1 and 2 that a Half Scram will not occur when the C Steam Line MSIVs are closed, power is less than 66%
SAT_ UNSAT N/A COMMENTS:_____________________________
JPM h PAGE 5 OF 8 Performance Step 2: Critical Not Critical NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.3A, 3.3B and 3.3C should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.2.1C.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[7] PERFORM the following to close MSIV LiNE C iNBOARD MSIV:
[7.1] DEPRESS and HOLD MSIV LiNE C INBOARD TEST, 3-HS-1-37B push button until Step 8.2.3 [7.3].
[7.2] WHEN MSIV LiNE C INBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3 [7.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C INBOARD, 3-HS-1-37A in the CLOSE position.
[7.3] RELEASE MSIV LINE C INBOARD TEST, 3-HS-1-1-37B push-button Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT_ U]NJSAT N/A _COMMENTS:_______________________________
JPM h PAGE 6 OF 8 Performance Step 3: Critical X Not Critical NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.3A, 3.3B and 3.3C should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.2.1C.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[8] PERFORM the following to close MSIV LINE C OUTBOARD MSIV: (Otherwise N/A this section)
[8.1] DEPRESS and HOLD MSIV LINE C OUTBOARD TEST, 3-HS-1-38B push button until Step 8.2.3[8.3].
[8.2] WHEN MSIV LINE C OUTBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3[8.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C OUTBOARD, 3-HS-1-38A in the CLOSE position.
[8.3] RELEASE MSIV LINE C OUTBOARD TEST, 3-HS-1-1-38B push-button.
Standard:
Operator depresses and holds the MSIV Line C Outboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A COMMENTS:____________________________
JPM h PAGE 7 OF 8 Performance Step 4: Critical Not Critical NOTES
- 1) When turbine generator RPM is above 1700 and one or more MSIVs fully close, Valves 3-FCV-1-168, -169, -170, and -171 will close and Valves 3-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF, and 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER opens, if closed, and their handswitches are in AUTO.
- 2) When TACF 3-10-004-001 is in effect, 3-FCV-1-170 is maintained in the OPEN position with its breaker maintained in the OFF position. The valve will not automatically open or close and can only be repositioned locally using the manual handwheel. The valve is located in the Unit 3 Turbine Bldg. steam tunnel.
- 3) When opening the 3-FCV-1-55 and 3-FCV-56, Main Steam Line Drain Valves the HWC system may isolate on LOW OFFGAS Oxygen.
[9] OPEN 3-FCV-1-55 using MN STM LINE DRAIN 1NBD ISOLATION VLV, 3-HS-1-55A.
Standard:
Opens drain valve 3-FCV-1-55 SAT UNSAT N/A COMMENTS:_________________________
Performance Step 5: Critical X Not Critical
[10] OPEN 3-FCV-1-56 using MN STM LiNE DRAIN OUTBD ISOLATION VLV, 3-HS- 1 -56A.
Standard:
Opens drain valve 3-FCV-1-56 SAT_ UNSAT N/A COMMENTS:
JPM h PAGE 8 OF 8 Performance Step 6: Critical Not Critical
[11] VERIFY OPEN 3-FCV-1-57 using MSIV DOWNSTREAM DRAINS SHUTOFF, 3-HS- 1 -57A.
[12] VERIFY OPEN 3-FCV-1-58 using UPSTREAM MSL DRAIN TO CONDENSER, 3-HS-1 -58A.
[13] CHECK CLOSED valves 3-FCV-1-168, -169, -170, and -171, ON 3-PNL-9-3 as follows:
VERIFY the green indicating light ILLUMINATED and the red indicating light EXTINGUISHED for MAIN STM LI1JE DRAIN VALVES POSITION, 3-ZI-1-174.
Standard:
Verifies 3-FCV-1-57 and 58 are open and that 3-FCV-1-168, 169, 170, and 171 are closed.
SAT_ U1JSAT N/A _COMMENTS:___________________________
Performance Step 7: Critical Not Critical X
[14] IF desired AND directed by the Unit Supervisor, THEN RAISE Reactor Power per 3-GOI-100-12, while maintaining the remaining steam lines below an average of 3.54 x 106 ibm/hr steam flow (approximately 80% Reactor Power), on the remaining three main steam lines.
Standard:
None, another Operator will raise power.
SAT UNSAT N/A COMMENTS:
CUE: Another Operator will raise Reactor Power END OF TASK STOP TIME
JPM +/-
PAGE 1 OF S OPERATOR:
RO__ SRO DATE:
JPM NUMBER: i TASK NUMBER: U-35A-AL-04 TASK TITLE: Stator Cooling Water System Return to Automatic Temp Control K!A NUMBER: 241000 A2.10 KJA RATING: RO 3.1 SRO 3.2 TASK STANDARD: Stator Cooling Water System simulated returned to Automatic Temperature Control LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 2-ARP-25-1 14A, Window 9, STATOR CLG WATER GEN INLET HI TEMP VALIDATION TIME: 5 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are an Auxiliary Unit Operator. Annunciator STATOR CLG WATER GEN iNLET HI TEMP alarmed on Panel-25-l 14A, Window 9. The Turbine Building AUO responded JAW 2-ARP-25-1 14A, Window 9. Control Air Supply to 2-TCV-35-54 was manually isolated. Subsequently, an automatic isolation signal was received. The failure was determined to be failed temperature controller, 2-TC-35-54, the controller has been replaced and the system is ready to be returned to automatic control.
INITIATING CUE: You are directed to return the Stator Water Cooling system to automatic temperature control in accordance with 2-ARP-25-1 14A, Window 9, step L CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM +/-
PAGE 3 OF 6 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.
IMTIAL CONDITIONS: You are an Auxiliary Unit Operator. Annunciator STATOR CLG WATER GEN INLET HI TEMP alarmed on Panel-25-1 14A, Window 9. The Turbine Building AUO responded JAW 2-ARP-25-1 14A, Window 9. Control Air Supply to 2-TCV-35-54 was manually isolated. Subsequently, an automatic isolation signal was received. The failure was determined to be failed temperature controller, 2-TC-35-54, the controller has been replaced and the system is ready to be returned to automatic control.
INITIATING CUE: You are directed to return the Stator Water Cooling system to automatic temperature control in accordance with 2-ARP-25-114A, Window 9, step L CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM +/-
PAGE 4 OF 6 START TIME____
Performance Step 1: Critical X Not Critical L. WHEN ready to return to automatic temperature control, THEN PERFORM the following:
VERIFY OPEN TCV-35-54 ISOL, 2-32-1007.
Standard:
Operator simulates opening 2-32-1007 SAT UNSAT Comments:_____________________________________
Zon of 007 is identified and operator has simulated opening the
JPM +/-
PAGE 5 OF 6 Performance Step 2: Critical X Not Critical IF the air supply to 2-TCV-35-54 was automatically isolated, THEN PRESS 2-HS-35-54 to RESET (OPEN) the air supply to 2-TCV-35-54.
Standard:
Operator simulates depressing 2-HS-35-54 to RESET (OPEN) the air supply to 2-TCV-3 5-54 SAT UNSAT Comments:____________________________________
CUE: When location of 2-HS-35-54 is identified and operator has simulated depressing the button, the air supply to 2-TCV-35-54 is open.
NOTE: The reset button is on panel 25-1 14A (Stator Water Cooling Panel)
JPM i PAGE 6 OF 6 Performance Step 3: Critical Not Critical FULLY LOWER (Clockwise) the 2-TCV-35-54 handwheel.
Standard:
Operator simulates turning the 2-TCV-35-54 handwheel fully clockwise SAT UNSAT Comments:_________________________________
When location of2-TCV-35-54 is determined and handwheel fully clockwise, the valve is FULLY LOWERED END OF TASK STOP TIME
JPM j PAGE lOF 10 OPERATOR:
RU___ SRO___ DATE:
JPM NUMBER: j TASK NUMBER: 5-082-NO-Ol TASK TITLE: Transfer DG A control to A 4KV SD BD & Secure DG A K/A NUMBER: 264000 A2.01 K/A RATING: RO 3.5 SRO 3.6 TASK STANDARD: Simulate transfer of Diesel Generator A control to 4KV Shutdown Board A and simulate securing the Diesel Generator from the Shutdown Board LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 0-01-82, Standby Diesel Generator System VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS: You are the extra operator. DG A is running and aligned in Parallel with System for a monthly operability check. DG A is paralleled and loaded with the A 4KV SD BD. The control room operator has lost control of DG A from Panel 9-23 while lowering load for termination from parallel operation. The Unit Operator is standing by at Panel 9-23 and has given you permission to transfer control of the Diesel Generator to the 4KV Shutdown Board. An AUO is on station at the Central Diesel Information Center, Panel 25-41, with a radio. An AUO is also on station locally at the Diesel Generator, with a radio, to obtain any local readings or perform any local actions. All Precautions and Limitations of 0-01-82, Standby Diesel Generator System, section 3.0, have been reviewed.
DG A Output Breaker Indications:
- Volts 4250
- Amp Meters A, B and C indicate 50 Amps
- kVAR-75
- kW100
- Breaker 1818 Red light ON, Amber light ON
- DG Control switch Red light ON INITIATiNG CUE: The Unit 2 Unit Supervisor has directed you to transfer DG A control to the A 4KV SD BD, in accordance with 0-01-82, Standby Diesel Generator System, Section 8.4; THEN shutdown the diesel from the A 4KV Shutdown board in accordance with 0-01-82, Standby Diesel Generator System, Section 7.2.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM j PAGE 3 OF 10 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WELL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the extra operator. DO A is running and aligned in Parallel with System for a monthly operability check. DO A is paralleled and loaded with the A 4KV SD BD. The control room operator has lost control of DO A from Panel 9-23 while lowering load for termination from parallel operation. The Unit Operator is standing by at Panel 9-23 and has given you permission to transfer control of the Diesel Generator to the 4KV Shutdown Board. An AUO is on station at the Central Diesel Information Center, Panel 25-41, with a radio. An AUO is also on station locally at the Diesel Generator, with a radio, to obtain any local readings or perform any local actions. All Precautions and Limitations of 0-01-82, Standby Diesel Generator System, section 3.0, have been reviewed.
DO A Output Breaker Indications:
- Volts 4250
- Amp Meters A, B and C indicate 50 Amps
- kVAR-75
- kW100
- Breaker 1818 Red light ON, Amber light ON
- DO Control switch Red light ON INITIATING CUE: The Unit 2 Unit Supervisor has directed you to transfer DO A control to the A 4KV SD BD, in accordance with 0-01-82, Standby Diesel Generator System, Section 8.4; THEN shutdown the diesel from te A 4KV Shutdown board in accordance with 0-01-82, Standby Diesel Generator System, Section 7.2.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM j PAGE 4 OF 10 START TIME Performance Step 1: Critical Not Critical 8.4 Transfer of Diesel Generator Control to 4-kV Shutdown NOTE Transfer of Diesel Generator control to the associated 4-ky shutdown board is usually performed for test purposes or for loss of Diesel Generator control on Panel 9-23.
[1] REQUEST permission from the Unit Operator to transfer control of the Diesel Generator to the 4-ky shutdown board.
Standard:
Given in initial conditions SAT_ UNSAT N/A Performance Step 2: Critical Not Critical X
[2] STATION an operator at the Central Diesel Information Center, Panel 25-41.
Standard:
Given in initial conditions SAT UNSAT N/A COMMENTS:
JPM j PAGE 5 OF 10 Performance Step 3: Critical Not Critical X
[3] ESTABLISH communications between personnel at 4-ky Shutdown Board A and the Central Diesel Information Center.
Standard:
Given in initial conditions SAT UNSAT N/A _COMMENTS:,
CUE: If necessary, communicate with candidate as operator at the Central Diesel
. Information Center Performance Step 4: Critical X Not Critical
[4] IF the Diesel Generator output breaker is closed, THEN PULL and PLACE DIESEL GENERATOR A OPER MODE SELECTOR SWITCH on 4-ky Shutdown Board A in the same position as the DIESEL GENERATOR A OPERATION MODE SELECTOR switch on Panel 9-23.
Diesel Handswitch Name Handswitch No. Compartment A DG A MODE SWITCH 0-HS-082-000AJ5B 22 B DG B MODE SWITCH 0-HS-082-000B/5B 4 C DG C MODE SWITCH 0-HS-082-000C/5B 4 D DG D MODE SWITCH 0-HS-082-000D/5B 20 Standard:
Simulates pulling and placing DG A Mode Switch, 0-HS-082-000A/5B, in Parallel with System SAT_ UNSAT N/A CUE: As Unit Operator, DG A Mode Switch is in Parallel with System on Panel 9-23.
When candidate simulates operating OPER MODE SELECTOR SWITCH on 4KV Shutdown Board A, switch is in Parallel with System.
JPM j PAGE 6 OF 10 Performance Step 5: Critical X Not Critical CAUTION Failure to verify the breaker local control switch in normal after close before placing the control transfer switch in EMERG can prevent auto closing of the Diesel Generator breaker on degraded voltage or loss of voltage to the Shutdown Board.
[5] IF transfer of Diesel Generator control to 4-ky Shutdown Board A is required, THEN PERFORM the following:
[5.1] VERIFY DG A OUTPUT BKR 1818 local control switch in NORM AFTER CLOSE.
Diesel Handswitch Name Handswitch No. Compartment A BREAKER CONTROL SWITCH 0-HS-21 1-000A/22B 22 B BREAKER CONTROL SWITCH 0-HS-21 1-000B/04B 4 C BREAKER CONTROL SWITCH 0-HS-21 1-000C/04B 4 D BREAKER CONTROL SWITCH 0-HS-21 1-000D/20B 20 Standard:
Simulates placing DG A OUTPUT BKR 1818 local control switch in NORM AFTER CLOSE to obtain a RED flag.
SAT_ UNSAT N/A CUE: When candidate simulates operating DG A OUTPUT BKR 1818 local control switch on 4KV Shutdown Board A, breaker switch is in NORM AFTER CLOSE, Red Flag indicated
JPM j PAGE 7 OF 10 Performance Step 6: Critical X Not Critical
[5.2] PLACE DIESEL GENERATOR A CONTROL TRANSFER SWITCH in EMERG.
Diesel Handswitch Name Handswitch No. Compartment A BREAKER CONTROL TRANSFER SWITCH 43 0-43-2 1 1-000A/022 22 B BREAKER CONTROL TRANSFER SWITCH 43 0-43-2 1 1-000B/04 4 C BREAKER CONTROL TRANSFER SWITCH 43 0-43-2 1 1-000C/04 4 D BREAKER CONTROL TRANSFER SWITCH 43 0-43-2 1 1-000D/20 20 Standard:
Simulates placing DG A CONTROL TRANSFER SWITCH in EMERG SAT UNSAT N/A CUE: When candidate simulates operating DG A CONTROL TRANSFER SWITCH on 4KV Shutdown Board A, switch is in EMERG. Synch Available light is ON and Parallel with System light is ON.
Performance Step 7: Critical Not Critical X
[6] NOTIFY the Unit Operator that control of the Diesel Generator has been transferred to the 4-ky shutdown board.
Standard:
Notifies Unit Operator that control of DG A has been transferred to 4KV Shutdown Board SAT_ UNSAT N/A COMMENTS:_____________________________
f CUE: Acknowledge notification as Unit Operator I
JPM j PAGE 8 OF 10 Performance Step 8: Critical Not Critical X
[7] IF the Diesel Generator is operating, THEN VERIFY the following on 4-ky Shutdown Board A:
A. The appropriate Mode light (SINGLE UNIT or PARALLEL SYSTEM) illuminates.
B. The CONTROL AVAILABLE light illuminates (SYN AVAIL).
Standard:
Verifies proper light indications SAT UNSAT N/A COMMENTS:
CUE: PARALLEL SYSTEM light on SYN AVAIL light on Performance Step 9: Critical Not Critical X
[8] PULL and PLACE the associated Diesel Generator mode selector switch in SINGLE UNIT at Panel 9-23.
Standard:
Directs Unit Operator to place DG A mode selector switch to SINGLE UNIT on Panel 9-23 SAT UNSAT N/A COMMENTS:
JPM j PAGE 9 OF 10 Performance Step 10: X Not Critical 7.2 Shutdown at 4-ky Shutdown Board
[1] VERIFY the following initial conditions:
A. All Precautions and Limitations in Section 3.0 have been reviewed.
- B. DG A Output Bkr 1818 is OPEN.
Standard:
Simulates opening DG A Output Bkr 1818 by placing 0-HS-21 1-000A/22B to Trip.
SAT UNSAT N/A _COMMENTS:____________________________
CUE: When candidate simulates opening DG A Output Bkr on 4KV Shutdown Board Red light Off, Green light On Performance Step 11: Critical Not Critical X
[2] IF Diesel Generator control has NOT been transferred to the 4-ky shutdown board, THEN REFER TO Section 8.4 and TRANSFER Diesel Generator control.
Standard:
Operator has already completed this step SAT UNSAT N/A _COMMENTS:_____________________________
JPM j PAGE 10 OF 10 Performance Step 12: Critical Not Critical
[3] PULL OUT then PUSH BACK IN DIESEL GENERATOR A CONTROL switch in NORMAL to initiate the shutdown sequence.
Diesel Handswitch Name Handswitch No. Compartment A DG A CONTROL SWITCH 0-HS-082-000A/1B 22 B DG B CONTROL SWITCH 0-HS-082-000B/1B 4 C DG C CONTROL SWITCH 0-HS-082-000C/1B 4 D DG D CONTROL SWITCH 0-HS-082-000D/1B 20 NOTE The diesel engine will idle between 440 RPM and 460 RPM for approximately 11.5 minutes after receiving a stop signal. An additional 3 minutes should be allowed for the logic timer to reset.
Standard:
Simulates pulling out and pushing back in the DG A CONTROL switch SAT_ UNSAT N/A COMMENTS:_______________________________
CUE: When candidate simulates puffing out and pushing back in the DG A CONTROL switch, White light ON, Red light ON. DG Volt reading is 2200 Volts.
Another Operator will continue 3PM Complete END OF TASK STOP TIME____
JPM k Page 1 of 7 OPERATOR:
RO___ SRO DATE:
JPM NUMBER: k TASK NUMBER: U-000-EM-44 TASK TITLE: Line up Alternate RPV Injection System Fire System in accordance with 1 -EOI-Appendix-7K KIA NUMBER: 29503 1EA1.01 K/A RATING: RO 4.4 SRO 4.4 TASK STANDARD: Simulate performing valve manipulations required to align the Fire System to inject into the RPV via the RHR System as directed by 1 -EOI-Appendix-7K LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1 -EOI-Appendix-7K VALIDATION TIME: 25 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE: DATE:
EXAMINER
INITIAL CONDITIONS:
You are an extra operator. A tornado has caused Unit 1 reactor to scram and no AC power is available, all Diesel Generators failed. Due to an un-isolable leak and several equipment failures the RPV inventory cannot be maintained above TAF. The diesel fire pump is running. A Radiation Protection Technician is with you.
INITIATING CUES:
The Unit 1 Operator directs you to perform manual valve alignments per Attachment 1 of 1 -EOI Appendix 7K. You have a radio and the Unit 1 operator will direct you to perform valve manipulations in accordance with the procedure steps listed in 1 -EOI Appendix-7K.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM k Page 3 of 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.
INITIAL CONDITIONS:
You are an extra operator. A tornado has caused Unit 1 reactor to scram and no AC power is available, all Diesel Generators failed. Due to an un-isolable leak and several equipment failures the RPV inventory cannot be maintained above TAF. The diesel fire pump is running. A Radiation Protection Technician is with you.
INITIATING CUES:
The Unit 1 Operator directs you to perform manual valve alignments per Attachment 1 of 1 -EOI Appendix 7K. You have a radio and the Unit 1 operator will direct you to perform valve manipulations in accordance with the procedure steps listed in 1-EOI Appendix-7K.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!
JPM k Page 4 of 7 START TIME____
CUE: UI Operator directs you to verify CLOSED the valves listed in Step 2.c and 24 Performance Step 1: Critical Not Critical X
- 2. NOTIFY Unit 1 Operator to perform the following:
- c. VERIFY CLOSED the following valves (Panel 1-9-20B):
Checks closed O-FCV-25-32, RSW STG TNK ISOL VLV and O-FCV-25-70, RSW STG TNK ISOL CNTRL VLV by the position indication devices SAT_ UNSAT N/A _COMMENTS:______________________________
CUE: O-FCV-25-32 and O-FCV-25-70 are as found or closed I
JPM Ic Page 5 of 7 Performance Step 2: Critical Not Critical X
Standard:
Verifies 1-FCV-23-52 valve position indicator indicating CLOSED or simulates engaging handwheel and rotating handwheel in the CLOCKWISE direction SAT_ UNSAT N/A COMMENTS:_______________________________
CUE: If handwheel manipulation simulated, handwheel is snug I CUE: Ui Operator directs you to OPEN the valve listed in Step 2.e I Performance Step 3: Critical X Not Critical
Standard:
Simulates engaging handwheel and rotating 1-FCV-23-57 handwheel in the COUNTERCLOCKWISE direction SAT UNSAT N/A COMMENTS:_______________________________
CUE: When simulated, the handwheel is turning and the valve stem is moving outward PAUSE), the handwheel is now snug
JPM k Page 6 of 7 I CUE: Ui Operator directs you to OPEN the valve listed in Step 5 I Performance Step 4: Critical X Not Critical
- 5. OPEN l-FCV-74-1O1, UNITS 1-2 DISCHARGE CROSSTIE, (Panel 1-9-3).
Standard:
Simulates engaging handwheel and rotating 1-FCV-74-1O1 handwheel in the COUNTERCLOCKWISE direction SAT_ UNSAT N/A _COMMENTS:____________________________
CUE: When simulated, the handwheel is turning and the valve stem is moving outward (PAUSE), the handwheel is now snug I CUE: Ui Operator directs you to verify OPEN the valves listed in Step 6 I Performance Step 5: Critical Not Critical
- 6. VERIFY OPEN the following valves (Panel 1-9-3):
1-FCV-74.-67, RHR SYS II LPCI INBD INJECT VALVE Standard:
Simulates engaging handwheel and rotating 1 -FCV-74-67 handwheel in the COUNTERCLOCKWISE direction SAT_ UNSAT N/A COMMENTS:____________________________
CUE: When simulated, the handwheel is turning and the valve stem is moving outward (PAUSE), the handwheel is now snug
JPM Ic Page 7 of 7 Performance Step 6: Critical Not Critical X 1-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE Standard:
Verifies 1 -FCV-74-66 valve position indicator indicating OPEN or simulates engaging handwheel and rotating handwheel in the COUNTERCLOCKWISE direction SAT_ UNSAT_ N/A COMMENTS:____________________________
CUE: If handwheel manipulation simulated, handwheel is snug I
CUE: JPM complete I
END OF TASK STOP TIME