ML112790096

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Initial Exam 2011-302 Draft Sim_IN-Plant JPMs
ML112790096
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/04/2011
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
U-068-AB-01, 50-259/11-302, 50-260/11-302, 50-296/11-302
Download: ML112790096 (190)


Text

JPM a PAGE 1 OF 10 OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: a TASK NUMBER: U-068-AB-O1 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-A0I-68-1A, 2-A0I-100-l 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 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 aid1I-rquirenents-ofFech-Spee-EeO-+/-4tare 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[1O] and-baiancjpuip.

flQs

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 CONIMTIONS: 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 and all requirements of Tech Spec LCO 3.4.1 are satisfied for Single Loop Operations. 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. 1] 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[lO] and balance jet pump flows

JPM a PAGE 4 OF 10 START TIME Performance Step 1: Critical Not Critical

[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 COMMENTS:______________________________

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 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.

[121 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

[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 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.

[141 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:

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 13 SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 7: Critical_ Not Critical X

[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-96-11 SAT UNSAT N/A COMMENTS:_____________________________

NOT& Simulator driver: When Recite Pump 2A trips due to incomplete start sequence then insert 2B Recite Pump Trip 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]. Operator performs immediate actions of 2-AOI-100-1 Reactor Scram 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

[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:______________________________

j CUE: After SCRAM report another operator will continue in 2-AOI-100-1 END 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 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: 3-01-68, 3-AOI-68-1A, 3-AOI-100-1 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 a Unit Operator. 3A Recirc Pump has tripped. All actions of 3-AOI 1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable, have been completed. The problem with 3A Recirc Pump has been corrected and all requirements of Tech Spec LCO 3.4.1 are satisfied for Single Loop Operations. 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.l] 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 and balance jet pump flows

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 That s Incorrect, if T

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 and all requirements of Tech Spec LCO 3.4.1 are satisfied for Single Loop Operations. 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 3-01-68, 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[1O] and balance jet pump flows

JPM a PAGE 4 OF 10 START TIME____

Performance Step 1: Critical Not Critical X

[101 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 loop 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 Performance Step 2: Critical Not Critical

[11] DEPRESS FAULT RESET, 3-HS-96-13, THEN VERIFY all Faults or Alarms are reset on ICS Screen VFDAAL.

[11.11 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 [121 SAT UNSAT N/A COMMENTS:_____________________________

JPM a PAGE 5 OF 10 Performance Step 3: Critical 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.

[12] 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 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

[14.21 DEPRESS FAULT RESET, 3-HS-96-13 Standard:

Operator depresses fault reset pushbutton, 3-HS 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 Not Critical

[14.4] FIRMLY DEPRESS DRIVE START, 3-HS-96-11.

Standard:

Operator depresses drive start pushbutton, 3-HS-96-1 1 SAT_ UNSAT N/A _COMMENTS:_____________________________

NOTE: Simulator driver: When Recirc Pump 3Atrips due to incomplete start sequence.

then insert 3BRecirc PumpTrip 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),

[1.1] 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 [1.1]. Operator performs immediate actions of 3-AOI-100-1 Reactor Scram SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 10: Critical X Not Critical 3-AOI-100-1 Reactor Scram 4.1 Immediate Actions

[1] DEPRESSREACTOR SCRAM A and B, 3-HS-99-5A/S3A and 3-HS-99-5A/S3B, 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

[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

[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:______________________________

IPM a PAGE 10 OF 10 Performance Step 13: Critical Not Critical

[4] PLACE REACTOR MODE SWITCH, 3-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 3-AOl- 100-1 END OF TASK STOP TIME

JPM b PAGE 1 OF 11 OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: b TASK NUMBER: U-000-EM-28 TASK TITLE: 2-EOI Appendix-4 Injection Prevention K/A NUMBER: 295031 EA1.12 K/A RATING: RO 3.9 SRO 4.1 TASK STANDARD: Prevent Injection per 2-EOI Appendix-4, and then maintain level minus 50 to minus 100 inches using 2-EOI-Appendix-5A LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-4, 2-EOI-Appendix-5A 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 a Unit Operator. An ATWS is in progress. Plant conditions are as found.

INITIATING CUE: The Unit Supervisor directs you to stop and prevent all injection into the RPV except RCIC, CRD and SLC in accordance with 2-EOI Appendix-4, Prevention of Injection, once level has lowered to minus 50 inches, maintain level minus 50 to minus 100 inches using 2-EOI-Appendix-5A.

JPM b 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 a Unit Operator. An ATWS is in progress. Plant conditions are as found.

INITIATING CUE: The Unit Supervisor directs you to stop and prevent all injection into the RPV except RCIC, CRD and SLC in accordance with 2-EOI Appendix-4, Prevention of Injection, once level has lowered to minus 50 inches, maintain level minus 50 to minus 100 inches using 2-EOI-Appendix-5A.

JPM b PAGE 4 OF 11 START TIME______

Performance Step 1: *CrjtjcalX Not Critical NOTE Steps 1 through 6 may be performed in any order.

1. PREVENT injection from HPCI by performing the following:
a. IF HPCI Turbine is NOT at zero speed, THEN PRESS and HOLD 2-HS-73-18A, HPCI TURBINE TRIP push-button.
  • b. WHEN HPCI Turbine is at zero speed, THEN PLACE 2-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 2-HS-73-18A, HPCI TURBINE TRIP push-button Standard:

Verifies HPCI Turbine at zero speed and places FIPCI Aux Oil Pump in Pull to Lock SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical_ Not Critical

2. PREVENT injection from RCIC by performing the following:
a. IF DIRECTED by SRO to allow RCIC injection, THEN EXIT step 2.
b. PRESS 2-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC Turbine.

Standard:

RCIC is not prevented SAT UNSAT N/A COMMENTS:

JPM b PAGE 5 OF 11 Performance Step 3: Critical Not CriticaiX NOTE Following receipt of a CORE SPRAY automatic initiation signal, it is NOT necessary to wait until a pump starts before performing step 3.

3. PREVENT injection from CORE SPRAY following an initiation signal by PLACING ALL Core Spray pump control switches in STOP.

Standard:

No initiation signal exists and DOES NOT place Core Spray pump control switches in STOP.

SAT UNSAT N/A COMMENTS:

JPM b PAGE 6 OF 11 Performance Step 4: Critical Not CriticalX

4. PREVENT injection from LPCI SYSTEM I by performing the following:

NOTE Injection may be prevented by performing EITHER step 4.a or step 4.b.

a. Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,
1) PLACE 2-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

AND

2) VERIFY CLOSED 2-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

Standard:

Closes 2-FCV-74-52 before RPV pressure drops below 450 psig SAT UNSAT N/A COMMENTS:

JPM b PAGE 7 OF 11 Performance Step 5: Critical Not Critical

5. PREVENT injection from LPCI SYSTEM II by performing the following:

NOTE jection may be prevented by performing EITHER step 5.a or step 5.b.

a. Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,
1) PLACE 2-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL in BYPASS.

AND

2) VERIFY CLOSED 2.-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE.

Standard:

Closes 2-FCV-74-66 before RPV pressure drops below 450 psig SAT UNSAT N/A COMMENTS:

JPM b PAGE 8 OF 11 Performance Step 6: Critical Not Critical X

6. PREVENT injection from CONDENSATE and FEED WATER by performing the following:
a. IF Immediate injection termination from a reactor feedwater pump is required, THEN PERFORM step 6.d for the desired pump.
b. LOWER RFPT 2C speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 2-9-5:
  • Using 2-LIC-46-5, REACTOR WATER LEVEL CONTROL, in MANUAL AND individual 2-SIC-46-10, RFPT 2C SPEED CONTROL in AUTO, OR
  • Using individual 2-SIC-46-10, RFPT 2C SPEED CONTROL in MANUAL, OR
  • Using individual 2-HS-46-1OA, RFPT 2C SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR.

Standard:

Attempts to lower 2C RFPT speed, cannot be lowered due to a controller failure SAT UNSAT N/A COMMENTS:

JPM b PAGE 9 OF 11 Performance Step 7: Critical Not CriticaiX

c. CLOSE the following valves BEFORE RPV pressure drops below 500 psig:
  • 2-FCV-3-19, RFP 2A DISCHARGE VALVE
  • 2-FCV-3-12, RFP 2B DISCHARGE VALVE
  • 2-FCV-3-5, RFP 2C DISCHARGE VALVE
  • 2-LCV-3-53, RFW START-UP LEVEL CONTROL Standard:

Determines that RPV pressure will remain above 500 psig and DOES NOT close RFP discharge valves SAT UNSAT N/A COMMENTS:

Performance Step 8: Critical X Not Critical

d. TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:
  • 2-HS-3-176A, RFPT 2C TRIP.

Standard:

Trips RFPT 2C SAT UNSAT N/A COMMENTS:

JPM b PAGE 10 OF 11 Perfonnance Step 9: Critical X Not Critical Lower level to less than -50 inches, then recommence injection with Feedwater using 2-EOI-Appendix-5A to maintain level band of -50 to -100 inches.

Standard:

Lowers level to minus 50 inches then performs 2-EOI-Appendix-5A to maintain level band SAT UNSAT N/A COMMENTS:

NOTE: Applicant must control level in designated level band Performance Step 10: Critical Not CriticaiX

1. IF it is desired to use a reactor feed pump that is in operation, THEN CONTINUE at step 12 to control the operating pump.

Standard:

Operator proceeds to step 12 SAT UNSAT N/A COMMENTS:

JPM b PAGE 11 OF 11 Performance Step 11: Critical Not Critical

12. SLOWLY ADJUST RFPT speed UNTIL feedwater flow to the RPV is indicated, using ANY of the following methods on Panel 2-9-5:
  • Individual 2-HS-46-8A(9A), RFPT 2A(2B) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
  • Individual 2-SIC-46-8(9), RFPT 2A(2B) SPEED CONTROL in MANUAL, OR
  • 2-LIC-46-5, REACTOR WATER LEVEL CONTROL, in MANUAL with individual 2-SIC-46--8(9), RFPT 2A(2B) SPEED CONTROL in AUTO.
13. ADJUST RFPT speed as necessary to control injection using the methods of step 12.

Standard:

Slowly adjusts RFP A or B speed until injection is indicated by one of the above methods, then adjusts RFP A or B speed to maintain level minus 50 to minus 100 inches SAT UNSAT N/A COMMENTS:

END OF TASK STOP TIME

JPM b PAGE 1 OF 11 OPERATOR:

RO___ SRO DATE:_________

JPM NUMBER: b TASK NUMBER: U-000-EM-28 TASK TITLE: 3-EOI Appendix-4 Injection Prevention K/A NUMBER: 295031 EA1.12 K/A RATING: RO 3.9 SRO 4.1 TASK STANDARD: Prevent Injection per 3-EOI Appendix-4, and then maintain level minus 50 to minus 100 inches using 3-EOI-Appendix--5A LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-4, 3-EOI-Appendix-5A 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 a Unit Operator. An ATWS is in progress. Plant conditions are as found.

INITIATING CUE: The Unit Supervisor directs you to stop and prevent all injection into the RPV except RCIC, CRD and SLC in accordance with 3-EOI Appendix-4, Prevention of Injection, once level has lowered to minus 50 inches, maintain level minus 50 to minus 100 inches using 3-EOI-Appendix-5A.

JPM b 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 a Unit Operator. An ATWS is in progress. Plant conditions are as found.

INITIATING CUE: The Unit Supervisor directs you to stop and prevent all injection into the RPV except RCIC, CRD and SLC in accordance with 3-EOI Appendix-4, Prevention of Injection, once level has lowered to minus 50 inches, maintain level minus 50 to minus 100 inches using 3-EOI-Appendix-5A.

JPM b PAGE 4 OF 11 START TIME______

Performance Step 1: *CrjticalX Not Critical NOTE Steps 1 through 6 may be performed in any order.

1. PREVENT injection from HPCI by performing the following:
a. IF HPCI Turbine is NOT at zero speed, THEN PRESS and HOLD 3-HS 1 8A, HPCI TURBINE TRIP push-button.
  • b. WHEN HPCI Turbine is at zero speed, THEN PLACE 3-HS-73-47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK and RELEASE 3-HS-73-18A, HPCI TURBINE TRIP push-button.

Standard:

Verifies HPCI Turbine at zero speed and places HPCI Aux Oil Pump in Pull to Lock SAT UNSAT N/A COMMENTS:

Performance Step 2: Critical_ Not CriticaiX

2. PREVENT injection from RCIC by performing the following:
a. IF DIRECTED by SRO to allow RCIC injection, THEN EXIT step 2.
b. PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC Turbine.

Standard:

RCIC is not prevented SAT UNSAT N/A COMMENTS:

JPM b PAGE 5 OF 11 Performance Step 3: Critical Not Critica1 NOTE Following receipt of a CORE SPRAY automatic initiation signal, it is NOT necessary to wait until a pump starts before performing step 3.

3. PREVENT injection from CORE SPRAY following an initiation signal by PLACING ALL Core Spray pump control switches in STOP.

Standard:

No initiation signal exists and DOES NOT place Core Spray pump control switches in STOP.

SAT UNSAT N/A COMMENTS:

JPM b PAGE 6 OF 11 Performance Step 4: Critical Not Critical

4. PREVENT injection from LPCI SYSTEM I by performing the following:

NOTE Injection may be prevented by performing EITHER step 4.a or step 4.b.

a. Following automatic pump start, PLACE RHR SYSTEM I pump control switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,
1) PLACE 3-HS-74-155A, LPCI SYS I OUTBD INJ VLV BYPASS SEL in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

Standard:

Closes 3-FCV-74-52 before RPV pressure drops below 450 psig SAT UNSAT N/A COMMENTS:

JPM b PAGE 7 OF 11 Performance Step 5: Critical Not Critical

5. PREVENT injection from LPCI SYSTEM II by performing the following:

NOTE Injection may be prevented by performing EITHER step 5.a or step 5.b.

a. Following automatic pump start, PLACE RHR SYSTEM II pump control switches in STOP.

OR

b. BEFORE RPV pressure drops below 450 psig,
1) PLACE 3-HS-74-155B, LPCI SYS II OUTBD INJ VLV BYPASS SEL in BYPASS.

AND

2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT VALVE.

Standard:

Closes 3-FCV-74-66 before RPV pressure drops below 450 psig SAT UNSAT N/A COMMENTS:

JPM b PAGE 8 OF 11 Performance Step 6: Critical Not Critical

6. PREVENT injection from CONDENSATE and FEEDWATER by performing the following:
a. IF Immediate injection termination from a reactor feedwater pump is required, THEN PERFORM step 6.d for the desired pump.
b. LOWER RFPT 3C speed to minimum setting (approximately 600 rpm) using ANY of the following methods on Panel 3-9-5:
  • Using 3-LIC-46-5, REACTOR WATER LEVEL CONTROL, in MANUAL AND individual 3-SIC-46-1O, RFPT 3C SPEED CONTROL in AUTO, OR
  • Using individual 3-SIC-46-10, RFPT 3C SPEED CONTROL in MANUAL, OR
  • Using individual 3-HS-46--1OA, RFPT 3C SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR.

Standard:

Attempts to lower 3C RFPT speed, cannot be lowered due to a controller failure SAT UNSAT N/A COMMENTS:

JPM b PAGE 9 OF 11 Performance Step 7: Critical Not Critical

c. CLOSE the following valves BEFORE RPV pressure drops below 500 psig:
  • 3-FCV-3-19, RFP 3A DISCHARGE VALVE
  • 3-FCV-3-12, RFP 3B DISCHARGE VALVE
  • 3-FCV-3-5, RFP 3C DISCHARGE VALVE
  • 3-LCV-3-53, RFW START-UP LEVEL CONTROL Standard:

Determines that RPV pressure will remain above 500 psig and DOES NOT close RFP discharge valves SAT UNSAT N/A COMMENTS:

Performance Step 8: Critical Not Critical

d. TRIP RFPTs as necessary to prevent injection by DEPRESSING the following push-buttons:
  • 3-HS-3-176A, RFPT 3C TRIP.

Standard:

Trips RFPT 3C SAT UNSAT N/A COMMENTS:

JPM b PAGE 10 OF 11 Performance Step 9: Critical Not Critical Lower level to less than 50 inches, then recommence injection with Feedwater using 3-EOI-Appendix-5A to maintain level band of 50 to -100 inches.

Standard:

Lowers level to minus 50 inches then performs 3-EOI-Appendix-5A to maintain level band SAT UNSAT N/A COMMENTS:

NOTE: Applicant must control level in designated level band Performance Step 10: Critical Not Critical

1. IF It is desired to use a reactor feed pump that is in operation, THEN CONTINUE at step 12 to control the operating pump.

Standard:

Operator proceeds to step 12 SAT UNSAT N/A COMMENTS:

JPM b PAGE 11 OF 11 Performance Step 11: Critical Not Critical

12. SLOWLY ADJUST RFPT speed UNTiL feedwater flow to the RPV is indicated, using ANY of the following methods on Panel 3-9-5:
  • Individual 3-HS-46-8A(9A), RFPT 3A(3B) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR
  • Individual 3-SIC-46-8(9), RFPT 3A(3B) SPEED CONTROL in MANUAL, OR
  • 3-LIC-46-5, REACTOR WATER LEVEL CONTROL, in MANUAL with individual 3-SIC-46-8(9), RFPT 3A(3B) SPEED CONTROL in AUTO.
13. ADJUST RFPT speed as necessary to control injection using the methods of step 12.

Standard:

Slowly adjusts RFP A or B speed until injection is indicated by one of the above methods, then adjusts RFP A or B speed to maintain level minus 50 to minus 100 inches 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 K/A NUMBER: 206000 A4.06 K/A 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:

EXAMINER

\ \\

t\9

IMTIAL 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- 11.

INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 2-EOI Appendix-i 1C 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-1 1.

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 16C and 16D as necessary to bypass HPCJ Low RPV pressure and Test Mode Isolation Interlocks.

Standard:

Operator determines Appendices 16C and 16D 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

3. IF Suppression Pool level CANNOT be maintained below 5.25 in, THEN EXECUTE EOI Appendix 16E 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 16E SAT_ UNSAT N/A _COMMENTS:_____________________________

JPM C PAGE 6 OF 11 Performance Step 4: Critical Not Critical X

4. IF HPCI Turbine is operating, THEN ALIGN HPCI in test mode as follows:
a. OPEN 2-FCV-73-35, HPCI PUMP CST TEST VLV.
b. OPEN 2-FCV-73-36, HPCI/RCIC CST TEST VLV.
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

5. IF HPCI is in standby readiness, THEN START HPCI as follows:
a. VERIFY at least one SGTS Train in operation.

Standard:

Operator verifies SGT in operation by illuminated RED SGTS status indicating lamps 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 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 PACKING EXHAUSTER, in START.

Standard:

Operator places 2-HS-73-1OA in START.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 9: *Crjtical 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 MIN 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 oniy 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 Not Critical

f. OPEN 2-FCV-73-16, FIPCI TURBiNE STEAM SUPPLY VLV, to start HPCI Turbine.

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

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-SI-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:
a. IF HPCI flow is above 1200 gpm, THEN VERIFY CLOSED 2-FCV 30, HPCI PUMP MIN FLOW VALVE.

b IF HPCI flow is below 600 gpm, THEN VERIFY OPEN 2-FCV-73-30, HPCI PUMP MIN 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 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 pressure less than or equal to 1100 psig on 2-PI-73-3 1A SAT UNSAT_ N/A COMMENTS:______________________________

DRIVER: When operator throttles 2-FCV43-35 insert malfunction hpO3 at 10% to fail

. HPCI flow controller in automatic control

JPM c PAGE 11 OF 11 Perfonnance Step 14: Critical Not Critical

8. ADJUST 2-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller to control RPV pressure.

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

9. IF HPCI injection to the RPV becomes necessary, THEN ALIGN HPCI to the RPV as follows:
a. OPEN 2-FCV-73-44, HPCI PUMP INJECTION VALVE.
b. THROTTLE 2-FCV-73-35, HPCI PUMP CST TEST VLV, to control injection.
c. GO TO EOI Appendix-SD.

Standard:

Operator monitors Reactor water level and determines HPCI injection to the RPV is not required SAT_ UNSAT N/A _COMMENTS:_____________________________

f Cue Injection to the RPV is not necessary at this time 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: 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:_______

EXAMINER

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-i 1C 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-i has been followed to RC/P-i 1.

INITIATING CUE: The Unit Supervisor directs you to place HPCI in Alternate RPV Pressure Control as directed by 3-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

2. IF Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN EXECUTE EOI Appendix 16C and 16D as necessary to bypass HPCI Low RPV pressure and Test Mode Isolation Interlocks.

Standard:

Operator determines Appendices 16C and 16D are not required SAT UNSAT N/A COMMENTS:_______________

f Cue: Emergency Depressurization or Steam Cooling is not required 1

Performance Step 3: Critical Not Critical X

3. IF Suppression Pool level CANNOT be maintained below 5.25 in, THEN EXECUTE EOI Appendix 16E 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 16E SAT_ UNSAT N/A COMMENTS:

JPM C PAGE 6 OF 11 Performance Step 4: Critical Not Critical X

4. IF HPCI Turbine is operating, THEN ALIGN HPCI in test mode as follows:
a. OPEN 3-FCV-73-35, HPCI PUMP CST TEST VLV.
b. OPEN 3-FCV-73-36, HPCIJRCIC CST TEST VLV.
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

5. iF HPCI is in standby readiness, THEN START HPCI as follows:
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 COMMENTS:______________________________

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-73-1OA in START.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 9: *Critical X Not Critical

e. OPEN the following valves:

3-FCV-73-36, HPCIIRCIC CST TEST VLV 3-FCV-73-35, HPCI 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 Not Critical

f. OPEN 3-FCV-73-16, HPCI TURBINE STEAM SUPPLY VLV, to start HPCI Turbine.

Standard:

Operator places 3-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 3-HS-73-47A and verifies speed >2400 rpm on 3-S 1-73-5 1 SAT_ UNSAT N/A COMMENTS:______________________________

JPM C PAGE 10 OF 11 Performance Step 12: Critical Not Critical

6. VERIFY proper HPCI minimum flow valve operation as follows:
a. IF HPCI flow is above 1200 gpm, THEN VERIFY CLOSED 3-FCV 30, HPCI PUMP MIN FLOW VALVE.

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 pressure less than or equal to 1100 psig on 3-PI-73-31A SAT UNSAT N/A _COMMENTS:_____________________________

DRIVER: When operator throttles 3-VCV-73-35 insert malfunction hpO3 at 10% to fail IIPCI flow controflerhi automatic control

JPM C PAGE 11 OF 11 Performance Step 14: Critical Not Critical

8. ADJUST 3-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, controller to control RPV pressure.

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

9. IF HPCI injection to the RPV becomes necessary, THEN ALIGN HPCI to the RPV as follows:
a. OPEN 3-FCV-73-44, HPCI PUMP INJECTION VALVE.
1. THROTTLE 3-FCV-73-35, HPCI PUMP CST TEST VLV, to control injection.
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 I

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 K/A 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 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 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 f Simulator Driver: This JPM may require RHR injection for level control I

START TIME____

Performance Step 1: Critical Not Critical X

1. NOTIFY Shift Manager / SED of the following:
  • Off-Gas Release Rate Limits will be exceeded.

Standard:

Operator notifies Shift Manager/SED SAT_ UNSAT N/A COMMENTS:_____________________________

CUE: As Shift Manager/SET) 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-64-159A 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

d. OPEN 2-FCV-64-222, HARDENED SUPPR CHBR VENT OUTBD ISOL VLV.

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

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 SM/SEt) 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 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

e. VERIFY CLOSED 2-FCV-64-36, DW/SUPPR CHBR VENT TO SGT (Panel 9-3)

Standard:

Operator verifies 2-FCV-64-36 is closed on Panel 9-3 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 9: Critical X Not Critical

f. VERIFY OPEN the following dampers (Panel 9-25):
  • 2-FCO-64-40, REACTOR ZONE EXH TO SGTS
  • 2-FCO-64-41, REACTOR ZONE EXH TO SOTS Standard:

Operator verifies dampers 2-FCO-64-40 and 2-FCO-64-41 are open 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).
4) NOTIFY Unit Operator that jumper for 2-FCV-64-30, DRYWELL VENT OUTBD ISOLATION VLV, is in place.

Standard:

Operator contacts an AUO or an extra operator to perform step h. 1) thru h.4)

SAT_ UNSAT N/A COMMENTS:______________________

CUE When contacted to perform step li,1) thru Ji.4) prode repeat back and inform operator that the Jumper for 2-FCV-64-3 is in place Performance Step 12: Critical Not Critical

i. VERIFY OPEN 2-FCV-64-30, DRYWELL VENT OUTBD ISOLATION VLV (Panel 9-3).

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

  • Off-Gas Release Rate Limits will be exceeded.
j. PLACE keylock switch 2-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to DRY WELL (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

k. VERIFY OPEN 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 9-54).

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 X

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:_____________________________

I CUE As SRO acknowledge report of emergency venting of Drywell in progress.

[ 3PM 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 K/A 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 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 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 3EOI Appendix 13 and maintain Primary Containment pressure below 55 psig

JPM d PAGE 4 OF 11 j Simulator Driver: This JPM may require RBR injection for level control I

START TIME____

Performance Step 1: Critical Not Critical X

1. NOTIFY Shift Manager / SED of the following:
  • Off-Gas Release Rate Limits will be exceeded.

Standard:

Operator notifies Shift Manager/SED SAT UNSAT N/A COMMENTS:

CUE: As Shift Manager/SEI) 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

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 X 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:______________________________

IJPM d PAGE 6 OF 11 Performance Step 4: Critical Not Critical

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

d. OPEN 3-FCV-64-222, HARDENED SUPPR CHBR VENT OUTBD ISOL VLV.

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

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 SM/SED acknowledge report of possible containment integrity failure, As RI acknowledge report of Reactor fluilding evacuation due to imminent failure ofPrimary Contaimnent 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 SGT (Panel 9-3)

Standard:

Operator verifies 3-FCV-64-36 is closed on Panel 9-3 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 9: Critical Not Critical

f. VERIFY OPEN the following dampers (Panel 9-25):
  • 3-FCO-64-40, REACTOR ZONE EXH TO SGTS
  • 3-FCO-64-41, REACTOR ZONE EXH TO SGTS Standard:

Operator verifies dampers 3-FCO-64-40 and 3-FCO-64-41 are open 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. DISPATCH personnel 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).
4) NOTIFY Unit Operator that jumper for 3-FCV-64-30, DRYWELL VENT OUTBD ISOLATION VLV, is in place.

Standard:

Operator contacts an AUO or an extra operator to perform step h.1) 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 3-FCV-64-30 is in place Performance Step 12: Critical Not Critical

i. VERIFY OPEN 3-FCV-64-30, DRYWELL VENT OUTBD ISOLATION VLV (Panel 9-3).

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 Not Critical CAUTION

  • 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 INBD 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 K/A NUMBER: 201006 A2.05 K/A 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.

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 HThatis 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.

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 X 7.0 PROCEDURE STEPS

[11 VERIFY that the following initial conditions are satisfied:

[1.11 ALL precautions AND limitations in Section 3.0 have been reviewed.

[1.2] ALL prerequisites in Section 4.0 are satisfied Standard:

Reviews precautions and limitations and verifies initial conditions are satisfied SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 2: Critical Not Critical X

[2] OBTAIN permission from Unit Supervisor (US) to perform this 2-SR-3.3.2.1.2 test procedure

[3] NOTIFY Unit Operator (UO) before commencing this 2-SR-3.3.2.1.2 test procedure.

[4] RECORD the start date AND time, reason for test, plant conditions AND ANY pre-test remarks on Attachment 1, Surveillance Procedure Review Form in Section 8.0.

Standard:

Already completed SAT_ UNSAT N/A COMMENTS:

JPM e PAGE 5 OF 10 Performance Step 3: Critical X Not Critical NOTE ALL operations are performed on Panel 2-9-5 in the main Control Room unless otherwise noted.

[51 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_ UNSAT N/A Performance Step 4: Critical Not Critical X

[61 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 6 OF 10 Performance Step 5: Critical Not Critical

[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 6: Critical 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) (02-3 1, 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 34-3 1)

SAT_ UNSAT N/A COMMENTS:_____________________________

JPM e PAGE 7 OF 10 Performance Step 7: *Crjtjcal X Not Critical

  • [7.5] SELECT the rod recorded in Step 7.O[7.4}.

[7.61 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 8: *Critical Not Critical 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 8 OF 10 Performance Step 9: *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 10: 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 9 OF 10 Performance Step 11: Critical Not Critical X

[7.11] VERIFY the WITHDRAW BLOCK status block on the RWM display is NOT in alarm.

[7.12] VERIFY RWM ROD BLOCK (2-XA-55-5B, Window 35) will RESET.

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 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 12: Critical X Not Critical

[7.13] REFER to the Control Rod Movement Data Sheet from 2-SR-3.1.3.5(A) to identify a rod from RWM Group 01.

[7.14] 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, 10-3 1, 26-47, 42-3 1, 26-15, 18-39, 34-39, 34-23, 18-23, or 26-31)

SAT UNSAT_ N/A COMMENTS:_____________________________

JPM e PAGE 10 OF 10 Performance Step 13: *Critical Not Critical

  • [7.151 SELECT the rod recorded in Step 7.0[7.14].

[7.16] VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.

Standard:

Selects the rod recorded previously and verifies Group 1 is indicated as the latched group SAT_ UNSAT N/A _COMMENTS:______________________________

Performance Step 14: Critical Not Critical X

[8] RECORD the appropriate test information on Attachment 1, Surveillance Procedure Review Form (located in Section 8.0) AND COMPLETE up to the Unit Supervisor review.

[9] NOTIFY the UO that this SR test procedure is complete.

[10] NOTIFY the US that this SR test procedure is complete.

Standard:

Records test info on Attachment 1 up to US review and notifies personnel of completion 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 RWIvI 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 7.0[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.

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 t

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-OI-85. Reactor Engineering has performed 3-SR-3 .3.2.1.7.

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 7.0 PROCEDURE STEPS

[1] VERIFY that the following initial conditions are satisfied:

[1.lj ALL precautions AND limitations in Section 3.0 have been reviewed.

[1.2] ALL prerequisites in Section 4.0 are satisfied Standard:

Reviews precautions and limitations and verifies initial conditions are satisfied SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 2: Critical Not Critical

[2] OBTAIN permission from Unit Supervisor (US) to perform this 3-SR-3.3.2.1.2 test procedure

[3] NOTIFY Unit Operator (UO) before commencing this 3-SR-3.3.2.1.2 test procedure.

[4] RECORD the start date AND time, reason for test, plant conditions AND ANY pre-test remarks on Attachment 1, Surveillance Procedure Review Form in Section 8.0.

Standard:

Already completed SAT_ UNSAT N/A COMMENTS:_____________________________

JPM e PAGE 5 OF 10 Performance Step 3: Critical Not Critical 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 4: 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 6 OF 10 Performance Step 5: 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.

[7.21 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_ UNSAT_ N/A _COMMENTS:_____________________________

Performance Step 6: Critical X Not Critical

[7.3] REFER to the Control Rod Movement Data Sheet from 3-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 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) (02-3 1, 26-07, 58-23, 42-55, 10-39, 42-07, 58-39, 26-55, 10-23, 50-15, 50-47, 18-47, 18-15, 50-3 1, 34-47, 18-3 1, 34-15, 42-39, 26-39, 26-23, 42-23, or 34-3 1)

SAT UNSAT_ N/A COMMENTS:______________________________

JPM e PAGE 7 OF 10 Performance Step 7: *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 8: *Critical Not Critical

  • [7.7] 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 8 OF 10 Performance Step 9: *Crjtjcal X Not Critical

  • [79] PLACE the CRD 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 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 3-XA-55-5B, window 35.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 10: 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_ UNSAT N/A COMMENTS:_____

JPM e PAGE 9 OF 10 Performance Step 11: Critical Not Critical X

[7.11] VERIFY the WITHDRAW BLOCK status block on the RWM display is NOT in alarm.

[7.121 VERIFY RWM ROD BLOCK (3-XA-55-5B, Window 35) will RESET.

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 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 12: Critical Not Critical

[7.13] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.5(A) to identify a rod from RWM Group 01.

[7.14] 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) (58-3 1, 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:______________________________

JPM e PAGE 10 OF 10 Performance Step 13: *Crjtjcal X Not Critical

  • [7.15] SELECT the rod recorded in Step 7.0[7.14].

[7.161 VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.

Standard:

Selects the rod recorded previously and verifies Group 1 is indicated as the latched group SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 14: Critical Not Critical X

[8] RECORD the appropriate test information on Attachment 1, Surveillance Procedure Review Form (located in Section 8.0) AND COMPLETE up to the Unit Supervisor review.

[9] NOTIFY the UO that this SR test procedure is complete.

[10] NOTIFY the US that this SR test procedure is complete.

Standard:

Records test info on Attachment 1 up to US review and notifies personnel of completion SAT_ UNSAT N/A COMMENTS:______________________________

END OF TASK STOP TIME

JPM f PAGE 1 OF 12 OPERATOR:

RO___ SRO DATE:

JPM NUMBER: f TASK NUMBER: U-000-SS-26 TASK TITLE:. Energize 4 KV SD BDs A and B from DGs K/A NUMBER: 600000 AA2.17 K/A RATING: RO 3.1 SRO: 3.6 TASK STANDARD: Operator will energize 4KV SD BDs A and B from the Unit 1/2 DGs and energize 4KV SD BD 3EA from 4KV SD BD A. Operator will be required to perform an Emergency Shutdown of the B Diesel Generator due to Low Lube Oil Pressure LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 0SSI-21 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: 20 minutes step 20, 20 minutes steps 22 thru 23, and 20 minutes steps 24thru28 PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:_______

EXAMINER

INITIAL CONDITIONS: You are the Unit 2 Operator, there is a fire in Unit 3 DG Building, the plant is operating in 0-SSI-21, Unit 3 Diesel Generator Building. All three units have been scrammed. Operator 4 has completed Section 1.0 of Attachment 4, and alignment of 4KV Shutdown Board 3EA is complete and ready to be re-energized. An AUO is stationed at the Diesel Generators.

INITIATING CUE: The Unit Supervisor directs you as the Unit 2 Operator to complete steps 20 through 26 in section 2.0 of 0-SSI-2 1 Unit 3 Diesel Generator Building Time Critical

JPM f PAGE 3 OF 12 IN-SIMIJLATOR: 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 the Unit 2 Operator, there is a fire in Unit 3 DG Building, the plant is operating in 0-SSI-21, Unit 3 Diesel Generator Building. All three units have been scrammed. Operator 4 has completed Section 1.0 of Attachment 4, and alignment of 4KV Shutdown Board 3EA is complete and ready to be re-energized. An AUO is stationed at the Diesel Generators.

INITIATING CUE: The Unit Supervisor directs you as the Unit 2 Operator to complete steps 20 through 26 in section 2.0 of 0-SSI-21 Unit 3 Diesel Generator Building Time Critical

JPM f PAGE 4 OF 12 START TIME____

Performance Step 1:

  • Critical Not Critical (20 Mm)

[201 IF Diesel Generator A is NOT running and supplying its respective Board, THEN DIRECT Unit 2 Operator to start Diesel Generator A, AND re-energize 4KV Shutdown Board A as follows:

  • [20.1j TRIP the 4KV SD BD A AUTO/LOCKOUT RESET switch by momentarily depressing the 4KV SD BD A AUTO TO MANUAL TRIP pushbutton, 0-HS-21 1-A on Panel 0-9-23-7.

[20.1.1] CHECK that 4KV SD BD A AUTO TO MANUAL TRW, 0-HS-21 1-A, amber light extinguished.

[20.1.21 CHECK that 4KV SD BD A AUTO/LOCKOUT RESET, 0-43 -21 1-A, trips.

Standard:

Depresses the 4KV SD BD A AUTO TO MANUAL TRIP pushbutton and verifies lockout trips.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 2: Critical_ Not Critical X

[20.2] PLACE 4KV SD BD A ALT FDR BKR 1716 control switch 0-HS-21 1-A/24A, in TRIP on Panel 0-9-23 -7.

Standard:

Trips Alternate Feeder Breaker 1716 SAT UNSAT N/A COMMENTS:______________________________

JPM f PAGE 5 OF 12 Performance Step 3: Critical_ Not Critical

[20.31 PLACE 4KV SD BD A EMER FDR BKR 1824 control switch 0-HS-211-A/4A in TRIP on Panel 0-9-23-7.

Standard:

Trips Emergency Feeder Breaker 1824 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 4: Critical X Not Critical

[20.4] PLACE 4KV SD BD A NORM FDR BKR 1614 control switch 0-HS-211-A/3A, in TRIP on Panel 0-9-23-7.

Standard:

Trips Normal Feeder Breaker 1614 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 5: Critical_ Not Critical X

[20.5] VERIFY DIESEL GENERATOR A started and DG A BKR 1818, 0.-HS-21 1-A/22A, closed to re-energize 4KV Shutdown Board A.

Standard:

Verifies DG A starts and DG A Breaker 1818 closes SAT_ UNSAT N/A COMMENTS:_____________________________

STOP TIME

JPM f PAGE 6 OF 12 START TIME____

Performance Step 6: Critical_ Not Critical X (20 Mm)

[21] VERIFY with Unit 3 Unit Supervisor that Operator 4 has completed Section 1.0 of Attachment 4, and alignment of 4KV Shutdown Board 3EA is complete and ready to be re-energized.

Standard:

Given in initial conditions SAT UNSAT N/A COMMENTS:

STOP TIME

JPM f PAGE 7 OF 12 START TIME____

Performance Step 7: *Critical Not Critical (20 Mm)

[22] DIRECT Unit 2 Operator to align 4KV Shutdown Board A to Shutdown Board 3EA, AND PERFORM the following at Panel 0-9-23:

  • [22.l] PLACE 4KV SDBD A BKR 1824 SYNC switch, 0-25-211-A/4A, to ON.
  • [22.2] PLACE 4KV SD BD A EMER FDR BKR 1824, in CLOSE, 0-HS-211-A/4A, AND VERIFY breaker closes.

[22.3] PLACE 4kV SD BD A BKR 1824 SYNC switch, 0-25-2 1 1-A/4A, to OFF.

Standard:

Places 4KV SDBD A BKR 1824 SYNC switch to on, Places 4KV SDBD A EMER FDR BKR 1824 in close and verifies breaker closes, and Places 4KV SDBD A BKR 1824 SYNC switch to off SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 8: Critical Not Critical

[23] DIRECT Unit 2 Operator to verify the following stopped at Panel 2-9-3:

A. CORE SPRAY PUMP 2A, 2-HS-75-5A B. RHR PUMP 2A, 2-HS-74-5A C. RFIRSW PUMP A2, 0-HS-23-5A/2 Standard:

Verifies the components listed above are stopped SAT_ UNSAT N/A COMMENTS:______________________________

STOP TIME

JPM f PAGE 8 OF 12 START TIME Performance Step 9: *Critical Not Critical (20 Mm)

[241 IF Diesel Generator B is NOT running and supplying its respective Board, TITEN DIRECT Unit 2 Operator to start Diesel Generator B, AND RE-ENERGIZE 4KV Shutdown Board B as follows:

  • [24.1] TRIP the 4KV SD BD B AUTO/LOCKOUT RESET switch by momentarily depressing the 4KV SD BD B AUTO TO MANUAL TRIP pushbutton, 0-HS-21 1-B, on Panel 0-9-23-7.

[24.1.1] CHECK that 4KV SD BD B AUTO TO MANUAL TRIP, 0-HS-211-B, amber light extinguished.

[24.1.2] CHECK that 4KV SD BD B AUTO/LOCKOUT RESET, 0 211-B, trips.

Standard:

Depresses the 4KV SD BD B AUTO TO MANUAL TRIP pushbutton and verifies lockout trips.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 10: Critical_ Not Critical

[24.2] PLACE 4KV SD BD B ALT FDR BKR 1714 control switch, 0-HS-211-B/20A, in TRIP on Panel 0-9-23-7.

Standard:

Trips Alternate Feeder Breaker 1714 SAT UNSAT N/A COMMENTS:

JPM f PAGE 9 OF 12 Performance Step 11: Critical X Not Critical

[24.3] PLACE 4KV SD BD B NORM FDR BKR 1616 control switch, 0-HS-211-B/2A, in TRIP on Panel 0-9-23-7.

Standard:

Trips Normal Feeder Breaker 1616 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 12: Critical_ Not Critical X

[24.4] PLACE 4KV SD BD B EMER FDR BKR 1828 control switch, O-HS-21 1-B/19A in TRIP on Panel 0-9-23-7.

Standard:

Trips Emergency Feeder Breaker 1828 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 13: Critical_ Not Critical X

[24.5] VERIFY DIESEL GENERATOR B started, and DG B BKR 1822, 0-HS-211-B/4A, closed to re-energize 4KV Shutdown Board B.

Standard:

Verifies DG B starts and DG B Breaker 1822 closes SAT_ UNSAT N/A COMMENTS:_____________________________

JPM f PAGE 10 OF 12 DRIVER: after DG is started enter BAT NRC/DGBIowlube for Low Lube Oil Pressure Examiner note: ALARM on 9-23B win 4 DG B LUBE OIL ABNORMAL will alarm and LOW LOW OIL PRESSURE LIGHT for D DG will illuminate, the operator should respond per the ARP.

Performance Step 14: Critical Not Critical X RESPONDS to the Alarm 9-23B WIN 4 (DIESEL GEN B LUBE OIL ABNORMAL) and notices the AMBER LIGHT (LOW LOW OIL PRESSURE)

Standard:

Responds per the ARP and Verifies the AMBER LIGHT is lit.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 15: Critical Not Critical DIESEL GEN 3D LUBE OIL ABNORMAL Window 4 A. CHECK Panel 0-9-23-7 to see if Low Low Lube Oil pressure light is illuminated.

Standard:

Verifies the AMBER LIGHT is lit.

SAT UNSAT N/A COMMENTS:

JPM f PAGE 11 OF 12 CUE: If asked, continued operation of PG D is not absolutely necessary.

Performance Step 16: Critical Not Critical X DIESEL GEN 3D LUBE OIL ABNORMAL Window 4 B. DISPATCH personnel to diesel generator room to check:

Standard:

Contacts personnel in DG Room SAT_ UNSAT N/A COMMENTS:______________________________

CUE: if asked, continued operation of DG D is not absolutely necessary.

CUE: If Assistant Unit Operator is called, After Lube oil pressure alarm is received on 9-23, report lube oil pressure low at 5 psag and lowering Lube Oil is spraying out of a damaged coupling Performance Step 17: Critical X Not Critical DIESEL GEN 3D LUBE OIL ABNORMAL Window 4 C. SHUT DOWN the diesel generator with Emergency Stop Pushbutton, if necessary.

Standard:

Operator depresses Emergency Stop Pushbutton SAT_ UNSAT N/A COMMENTS:______________________________

Another operator will complete the remainder of the procedure, 3PM complete j If the operator fails to shutdown DG B he will continue to step 25 and 26 in procedure.

JPM f PAGE 12 OF 12 Performance Step 18: Critical Not Critical X

[251 DIRECT Unit 2 Operator to verify the following stopped at Panel 2-9-3:

A. CORE SPRAY PUMP 2C, 2-HS-75-14A B. RHR PUMP 2C, 2-HS-74-16A C. RHRSW PUMP C2, O-HS-23-12A/2 Standard:

Verifies the components listed above are stopped SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 19: Critical_ Not Critical

[26] DIRECT Unit 2 Operator to verify CONTROL BAY CHILLER A, O-HS-31-2100A, stopped at Panel 2-9-20.

Standard:

Verifies the component listed above is stopped SAT_ UNSAT N/A COMMENTS:______________________________

END OF TASK STOP TIME

JPM g PAGE 1 OF 16 OPERATOR:

RO SRO___ DATE:

JPM NUMBER: g TASK NUMBER: U-000-EM-61 TASK TITLE: 2-EOI Appendix-12 Primary Containment Venting K/A 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 2 Operator. Unit 2 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P- 1.

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 16 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 2 Operator. Unit 2 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P- 1.

INITIATING CUE: The Unit Supervisor directs you to vent the pressure suppression chamber in accordance with 2-EOI Appendix-12.

JPM g PAGE 4 OF 16 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.1.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

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 16 Performance Step 3: Critical Not Critical

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

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 16 Performance Step 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-FCV84-19, 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_ UNSAT N/A COMMENTS:______________________________

JPM g PAGE 7 OF 16 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 8 or 9 SAT UNSAT N/A COMMENTS:

NRC: Step 8 starts below, Step 9 starts at performance step 13 I

Performance Step 8: Critical Not Critical

8. VENT the Suppression Chamber using 2-FIC-84-19, PATH B VENT FLOW CONT, as follows:
a. PLACE keylock switch 2-HS-84-35, SUPPR CHBR/DW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 2-9-54).

Standard:

Placed 2-HS-84-35 in the SUPPR-CHBR position SAT_ UNSAT_ N/A COMMENTS:________

JPM g PAGE 8 OF 16 Performance Step 9: Critical Not Critical

b. VERIFY OPEN 2-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 2-9-54).

Standard:

2-FCV-64-32 fails to open Operator proceeds to Vent the Suppression Chamber using 2-FIC-84-20 Step 9.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 10: Critical 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 9 OF 16 Performance Step 11: Critical Not Critical

b. PLACE keylock switch 2-HS-84-36, SUPPR CHBRJDW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 2-9-54).

Standard:

Placed 2-HS-84-36 in the SUPPR-CHBR position SAT_ UNSAT_ N/A COMMENTS:______________________________

Performance Step 12: Critical Not Critical X

c. VERIFY OPEN 2-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV (Panel 2-9-54).

Standard:

Verifies 2-FCV-64-34 Open SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 13: 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:

Places 2-FIC-84-20 in Auto at 100 SCFM SAT_ UNSAT_ N/A _COMMENTS:______________________________

JPM g PAGE 10 OF 16 Performance Step 14: Critical Not Critical

e. PLACE keylock switch 2-HS-84-20, 2-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 2-9-55).
4. IF While executing this procedure, the desired vent path is lost or cannot be established, THEN PERFORM step 13 to secure the vent path and re-enter this procedure if further venting is required.

Standard:

2-FCV-84-20 will fail to Open, Operator proceeds to Step 4 which directs Step 13 SAT_ UNSAT N/A COMMENTS:_____________________________

CUE: SRO Directs Drywell venting

JPM g PAGE 11 OF 16 Performance Step 15: 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):
  • 2-HS-84-35, SUPPR CHBR / DW VENT ISOL BYP SELECT,
  • 2-HS-84-36, SUPPR CHBR / DW VENT ISOL BYP SELECT.

Standard:

Operator places 2-HS-84-35 and 36 in Off SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 16: Critical Not Critical

b. VERIFY keylock switch 2-HS-84-20, 2-FCV-84-20 ISOLATION BYPASS, in NORMAL (Panel 2-9-55).

Standard:

Places 2-HS-84-20 to Normal SAT_ UNSAT N/A COMMENTS:______________________________

JPM g PAGE 12 OF 16 Performance Step 17: 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 18: Critical Not Critical X

d. VERIFY CLOSED the following valves (Panel 2-9-3 or Panel 2-9-54):
  • 2-FCV-64-31, DRYWELL INBD ISOLATION VLV,
  • 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,
  • 2-FCV-64-34, SUPPR CHBR INBD ISOLATION VLV,
  • 2-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

Standard:

Verifies above listed valves are closed SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 19: Critical Not Critical X

e. 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:____________________________

CUE: SRO Directs Drywell venting

JPM g PAGE 13 OF 16 Performance Step 20: Critical X Not Critical

10. VENT the Drywell using 2-FIC-84-19, PATH B VENT FLOW CONT, as follows:
a. VERIFY CLOSED 2-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 2-9-3).

Standard:

Verify Closed 2-FCV-64-141 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 21: Critical X Not Critical

b. PLACE keylock switch 2-HS-84-36, SUPPR CHBRIDW VENT ISOL BYP SELECT, to DRY WELL position (Panel 2-9-54).

Standard:

Placed 2-HS-84-36 in the DRYWELL position SAT UNSAT N/A COMMENTS:______________________________

Performance Step 22: Critical Not Critical

c. VERIFY OPEN 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 2-9-54).

Standard:

Verifies 2-FCV-64-29 Opens SAT_ UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 14 OF 16 Performance Step 23: Critical Not Critical

d. PLACE 2-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 2-9-55).

Standard:

Places 2-FIC-84-19 in Auto at 100 SCFM SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 24: Critical X Not Critical

e. PLACE keylock switch 2-HS-84-19, 2-FCV-84-19 CONTROL, in OPEN (Panel 2-9-55).

Standard:

Places 2-HS-84-19 in Open SAT_ UNSAT_ N/A _COMMENTS:_____________________________

Performance Step 25: Critical Not Critical X

f. VERIFY 2-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.
g. CONTINUE in this procedure at step 12.

Standard:

Verifies 2-FIC 19 is indicating approximately 100 scfm and continues at step 12 SAT UNSAT N/A COMMENTS:______________________________

JPM g PAGE 15 OF 16 Performance Step 26: Critical Not Critical X

12. ADJUST 2-FIC-84-19, PATH B 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 iiCils AND
  • 0-SI-4.8.B.1.a.i release fraction of 1.

Standard:

Request release rates from Log AUO SAT_ UNSAT N/A _COMMENTS:

j CUE: Pnmary Containment Flooding and SAMO are not being executed CUE: When Release rates are requested report a Stack Release Rate of 1.6.x 7 i0 [tCi/s and release fraction of .95

JPM g PAGE 16 OF 16 Performance Step 27: Critical X Not Critical REDUCE vent flow to obtain acceptable release rate/fraction readings.

Standard:

Recognized exceeding Release Rate Limit of 1.4 x iO iCi/s and adjusted 2-FIC-84-19 SAT_ UNSAT N/A _COMMENTS:______________________________

CUE: If Flow is reduced report a new Stack Release Rate of 13 x IO jiCi/s and a release fraction of .85 STOP TIME END OF TASK

JPM g PAGE 1 OF 16 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: g TASK NUMBER: U-000-EM-61 TASK TITLE: 3-EOI Appendix-12 Primary Containment Venting K/A NUMBER: 295017 AA1.03 K/A RATING: RO 3.4 SRO: 3.4 TASK STANDARD: Vent Primary Containment lAW 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 2 Operator. Unit 3 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P- 1.

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 16 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 3 Operator. Unit 2 reactor has scrammed. A small leak exists in primary containment. EOI-2 has been followed to PC/P-i.

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 16 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.1.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 INBD ISOL VALVE,
  • 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,
  • 3-FCV-64-32, SUPPR CHBR VENT 1NBD ISOL VALVE.

Standard:

Verifies closed the above listed valves SAT UNSAT N/A COMMENTS:

JPM g PAGE 5 OF 16 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 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_ UNSAT N/A COMMENTS:______________________________

Performance Step 5: Critical_ Not Critical

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 requfred

JPM g PAGE 6 OF 16 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 16 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 8 or 9 SAT_ UNSAT_ N/A COMMENTS:

NRC: Step 8 starts below, Step 9 starts at performance step 13 I

Performance Step 8: Critical X Not Critical

8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT FLOW CONT, as follows:
a. PLACE keylock switch 3-HS-84-35, SUPPR CHBRJDW VENT ISOL BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).

Standard:

Placed 3-HS-84-35 in the SUPPR-CHBR position SAT UNSAT N/A COMMENTS:________

JPM g PAGE 8 OF 16 Performance Step 9: Critical Not Critical

b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE (Panel 3-9-54).

Standard:

3-FCV-64-32 fails to open Operator proceeds to Vent the Suppression Chamber using 3-FIC-84-20 Step 9.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 10: Critical 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 9 OF 16 Performance Step 11: 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:

Placed 3-HS-84-36 in the SUPPR-CHBR position SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 12: Critical Not Critical X

c. VERIFY OPEN 3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV (Panel 3-9-54).

Standard:

Verifies 3-FCV-64-34 Open SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 13: 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:

Places 3-FIC-84-20 in Auto at 100 SCFM SAT UNSAT N/A COMMENTS:______________________________

JPM g PAGE 10 OF 16 Performance Step 14: Critical Not Critical X

e. PLACE keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in BYPASS (Panel 3-9-55).
4. IF While executing this procedure, the desired vent path is lost or cannot be established, THEN PERFORM step 13 to secure the vent path and re-enter this procedure if further venting is required.

Standard:

3-FCV-84-20 will fail to Open, Operator proceeds to Step 4 which directs Step 13 SAT_ UNSAT N/A _COMMENTS:_____________________________

CUE: SRO Directs Drywell venting

JPM g PAGE 11 OF 16 Performance Step 15: 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):
  • 3-HS-84-35, SUPPR CHBR / DW VENT ISOL BYP SELECT,
  • 3-HS-84-36, SUPPR CHBR / DW VENT ISOL BYP SELECT.

Standard:

Operator places 3-HS-84-35 and 36 in Off SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 16: Critical Not Critical X

b. VERIFY keylock switch 3-HS-84-20, 3-FCV-84-20 ISOLATION BYPASS, in NORMAL (Panel 3-9-55).

Standard:

Places 3-HS-84-20 to Normal SAT_ UNSAT N/A COMMENTS:______________________________

JPM g PAGE 12 OF 16 Performance Step 17: Critical Not Critical X

c. VERIFY keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in CLOSE (Panel 3-9-55).

Standard:

Verifies 3-HS-84-19 is in Close SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 18: Critical Not Critical X

d. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):
  • 3-FCV-64-31, DRYWELL INBD ISOLATION VLV,
  • 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,
  • 3-FCV-64-34, SUPPR CHBR INBD ISOLATION VLV,
  • 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.

Standard:

Verifies above listed valves are closed SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 19: Critical Not Critical X

e. VERIFY CLOSED 3-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 3-9-3).

Standard:

Verifies closed 3-FCV 141 SAT_ UNSAT N/A COMMENTS:_____________________________

CUE: SRO Directs Drywell venting

JPM g PAGE 13 OF 16 Performance Step 20: Critical Not Critical

10. VENT the Drywell using 2-FIC-84-19, PATH B VENT FLOW CONT, as follows:
a. VERIFY CLOSED 2-FCV-64-141, DRYWELL DP COMP BYPASS VALVE (Panel 2-9-3).

Standard:

Verify Closed 2-FCV-64-141 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 21: Critical Not Critical

b. PLACE keylock switch 3-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to DRYWELL position (Panel 3-9-54).

Standard:

Placed 3-HS-84-36 in the DRYWELL position SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 22: Critical Not Critical X

c. VERIFY OPEN 3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE (Panel 3-9-54).

Standard:

Verifies 3-FCV-64-29 Opens SAT_ UNSAT N/A COMMENTS:______________________________

JPM g PAGE 14 OF 16 Performance Step 23: Critical Not Critical

d. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with setpoint at 100 scfm (Panel 3-9-55).

Standard:

Places 3-FIC-84-19 in Auto at 100 SCFM SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 24: Critical X Not Critical

e. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN (Panel 3-9-55).

Standard:

Places 3-HS-84-19 in Open SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 25: Critical Not Critical X

f. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating approximately 100 scfm.
g. CONTINUE in this procedure at step 12.

Standard:

Verifies 3-FIC 19 is indicating approximately 100 scfm and continues at step 12 SAT_ UNSAT N/A COMMENTS:_____________________________

JPM g PAGE 15 OF 16 Performance Step 26: Critical Not Critical

12. ADJUST 3-FIC-84-19, PATH B 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 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 iiCils AND
  • 0-SI-4.8.B.1.a.l release fraction of 1.

Standard:

Request release rates from Log AUO SAT_ UNSAT N/A COMMENTS:__________

C1JE Primary Containment Flooding and SAMG are not being executed CUE: When Release rates are requested report a Stack Release Rate of 1.6 x iø jiCifs and release fraction of .95

JPM g PAGE 16 OF 16 Performance Step 27: Critical Not Critical REDUCE vent flow to obtain acceptable release rate/fraction readings.

Standard:

Recognized exceeding Release Rate Limit of 1.4 x iO jiCi/s and adjusted 3-FIC 19 SAT_ UNSAT N/A COMMENTS:______________________________

CUE: If Flow is reduced report a new Stack Release Rate of 1.3 x iü iiCils and a release fraction of .85 STOP TIME END OF TASK

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 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: 2-01-1 VALIDATION TIME: 20 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. No 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. No 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 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 MIS Vs 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, 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).

[71 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-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 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-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 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.

[91 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 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 lbmlhr 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 h PAGE 1 OF 8 OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: h TASK NUMBER: U-001-NO-08 TASK TITLE: Close MSTVs 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 V REFERENCES/PROCEDURES NEEDED: 3-01-1 VALIDATION TIME: 20 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. No 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 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. No MSIVs LS3 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 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 3 MIS Vs 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.

[21 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, 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 3.2.1C.
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-l-37B push-button Standard:

Operator depresses and holds the MSIV Line C Inboard test push button until the MSTV 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 3.2.1C.
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[8.1j 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 X 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 3-10-004-00 1 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 INBD ISOLATION VLV, 3-HS-1-55A.

Standard:

Opens drain valve 3-FCV-1-55 SAT_ UNSAT N/A COMMENTS:___________________________

Performance Step 5: Critical 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 LINE 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_ UNSAT N/A COMMENTS:___________________________

Performance Step 7: Critical Not Critical X

[141 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 8 OPERATOR:

RO SRO DATE:

JPM NUMBER:

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 VAIJDATION 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. The Unit 2 Main Generator was tied to the grid several days ago. Approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> later, Annunciator STATOR CLG WATER GEN INLET HI TEMP was received on Panel 1 14A, Window 9. The Turbine Building AUO responded in accordance with 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 WJLL 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 Auxiliary Unit Operator. The Unit 2 Main Generator was tied to the grid several days ago. Approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> later, Annunciator STATOR CLG WATER GEN INLET HI TEMP was received on Panel-25-l 14A, Window 9. The Turbine Building AUO responded in accordance with 2-ARP-25-l 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 i 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:_______________________________________

CUE: When location of 2-32-1007 is identified and operator has simulated opening the valve, .the valve is open

JPM i PAGE 5 OF 6 Performance Step 2: Critical 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 operatorhas 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 +/-

PAGE 6 OF 6 Performance Step 3: Critical Not Critical FULLY LOWER (Clockwise) the 2TCV-35-54 handwheel.

Standard:

Operator simulates turning the 2-TCV-35-54 handwheel fully clockwise SAT UNSAT___ Comments:___________________________________

CUE: When location of 2TCV-35-54 is detemiined and operator has simulated turning the handwheel fully clockwise, the valve is FULLY LOWERED EN]) OF TASK STOP TIME_____

JPM j PAGE 1 OF 11 OPERATOR:

RO___ SRO DATE:

JPM NUMBER: j TASK NUMBER: S-082-NO-0l TASK TITLE: Transfer DG A control to A 4KV SD BD & Secure DG A K/A NUMBER: 264000 A2.0l 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.

The control room operator has lost control of DG A from Panel 9-23 while lowering load for termination from parallel operation. Current load is 100 kW and 75 kVAR. 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.

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 11 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 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. Current load is 100 kW and 75 kVAR. 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.

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 4 OF 11 START TIME____

Performance Step 1: Critical Not Critical X 8.4 Transfer of Diesel Generator Control to 4-ky 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.

[11 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 COMMENTS:_____________________________

Performance Step 2: Critical Not Critical

[21 STATION an operator at the Central Diesel Information Center, Panel 25-4 1.

Standard:

Given in initial conditions SAT_ UNSAT N/A COMMENTS:

JPM j PAGE 5 OF 11 Performance Step 3: Critical Not Critical

[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 CUE: If requested when arriving at DG A Output Breaker 1818, Voltage is 4250, Amp meters A, B, and C indicate 50 amps, kVAR = 75, kW = 700. Breaker 1818 red light is ON and amber light is ON. DG Control Switch Red light ON

JPM j PAGE 6 OF 11 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-082-000A/5B 22 B DG B MODE SWITCH 0-HS-082-000B/5B 4 C DG C MODE SWITCH 0-HS-082-000CI5B 4 D DG D MODE SWITCH 0HS-082-000DI5B 20 Standard:

Simulates pulling and placing DG A Mode Switch, O-HS-082-000A/5B, in Parallel with System SAT UNSAT N/A COMMENTS:_______________________________

CUES As Unit Operator, DO 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 Systent

JPM j PAGE 7 OF 11 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 O-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 COMMENTS:_____________________________

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 8 OF 11 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 COMMENTS:___________________________

CUE: When candidate simulates operating DO 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:____________________________

CUE: Acknowledge notification as Unit Operator I

JPM j PAGE 9 OF 11 Performance Step 8: Critical Not Critical X

[71 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

[81 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 10 OF 11 Performance Step 10: *Critical X Not Critical 7.2 Shutdown at 4-ky Shutdown Board

[1J 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-kV 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 11 OF 11 Performance Step 12: Critical Not Critical

[31 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 pulling out and pushing back in the DG A CONTROL switch, White lIght ON, Red light ON. DG Volt reading goes from 4400 to 2200 Volts.

JPM Complete another Operator will continue 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 K/A 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.

IMTIATING 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.

IMTIAL CONIMTIONS:

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.

IMTIATING 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 2.d Performance Step 1: Critical Not Critical

2. NOTIFY Unit 1 Operator to perform the following:
c. VERIFY CLOSED the following valves (Panel 1-9-20B):
  • O-FCV-25-32, RSW STG TNK ISOL VLV
  • O-FCV-25-70, RSW STG TNK ISOL CNTRL VLV Standard:

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:______________________________

I CUE: O-FCV-25-32 and O-FCV-25-70 are as found or closed I

JPM k Page 5 of 7 Performance Step 2: Critical Not Critical

d. VERIFY CLOSED 1-FCV-23-52, RHR HX 1D RHRSW OUTLET VLV (Panel 1-9-3).

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 j CUE: UI Operator directs you to OPEN the valve listed in Step 2 e t

Performance Step 3: Critical Not Critical

e. OPEN 1-FCV-23-57, STANDBY COOLANT VALVE FROM RHRSW (Unit 1, Panel 9-3).

Standard:

Simulates engaging handwheel and rotating 1-FCV-23-57 handwheel in the COUNTERCLOCKWISE direction SAT_ UNSAT N/A _COMMENTS:_____________________________

CUE: When simulated, the bandwbeel is turning and the valve stem is moving outward (PAUSE), the handwbeel is now snug I

JPM k Page 6 of 7 t CUE: Ui Operator directs you to OPEN the valve listed in Step S I Performance Step 4: Critical Not Critical

5. OPEN 1-FCV-74-1O1, UNITS 1-2 DISCHARGE CROSST1E, (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, thç 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 1 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 handwbeel is turning and the valve stem is moving outward (PAUSE, the handwheel is nOw snug

JPM k Page 7 of 7 Performance Step 6: Critical Not Critical X l-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:____________________________

If bandwbeel manipulation simulated, handwheel. is snug.

I CUE: JPM complete I

END OF TASK STOP TIME____