Text

Initial Exam 2014-301 Draft SIM-In-Plant JPMs
	ML14154A369
Person / Time
Site:	Browns Ferry
Issue date:	06/02/2014
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
Shared Package
ML14155A059	List: ML14154A324; ML14154A337; ML14154A346; ML14154A365; ML14154A369; ML14154A373; ML14154A377; ML14154A383; ML14154A390; ML14154A393; ML14154A396; ML14154A399;
References
	50-259/OL-14, 50-260/OL-14, 50-296/OL-14
	Download: ML14154A369 (226)
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JPM a OPERATOR:

RO SRO DATE:

JPM NUMBER: a TASK NUMBER: U-068-NO-06 TASK TITLE: Dual Recirc Pump Quick Restart KIA NUMBER: 202001 A4.01 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: Perform control room operations necessary to restart Recirc Pump 2A LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 2-01-68 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:_______

EXAMiNER 1

JPM a INITIAL CONDITIONS:

You are an Operator on Unit 2. 2-SR-3.4.9.3&4 is being performed by another operator.

INITIATING CUE:

Start Recirc Pump 2A in accordance with 2-01-68, Reactor Recirculation System section 8.1.

2

JPM a IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 2. 2-SR-3.4.9.3&4 is being performed by another operator.

INITIATING CUE:

Start Recirc Pump 2A in accordance with 2-01-68, Reactor Recirculation System section 8.1.

3

JPM a START TIME Performance Step 1: Critical Not Critical X CAUTION DO NOT USE THIS SECTION UNLESS BOTH RECIRC PUMPS ARE TRIPPED!

NOTE This section provides the steps to be performed to restart a recirc pump immediately following a shutdown/trip of both recirc pumps in order to prevent thermal stratification.

[1] VERIFY Reactor in MODE 3.

[2] CHECK RESET the following annunciators:

RECIRC DRIVE VFD A(B) LOCKOUT 2-XA-96-42(43), 2-XA-55-4A(B), Window 6.

RECIRC PUMP A(B) COOLiNG WATER FLOW LOW 2-FA-68-53(66),

2-XA-55-4A(B), Window 34.

Standard:

Identifies Reactor is in MODE 3 and annunciators 2-XA-55-4A(B), window 6 and window 34 are reset.

SAT UNSAT N/A COMMENTS:___________________________

4

JPM a Performance Step 2: Critical Not Critical X

[3] VERIFY RPTs are reset IF it is desired to RESET RPT breakers from the control room, THEN PERFORM the following: (Otherwise REFER TO Section 8.5)

Standard:

Verifies RPTs are reset SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 3: Critical Not Critical X

[4] VERIFY OPEN, RECIRC PUMP 2A SUCTION VALVE, 2-FCV-68-l.

Standard:

Verifies Recirc Pump 2A Suction Valve OPEN SAT_ UNSAT_ N/A COMMENTS:______

5

JPM a Performance Step 4: Critical Not Critical X CAUTION The recirc pump is required to be started within 15 minutes after the performance of 2-SR-3.4.9.3&4 to prevent pump temperature changes due to cooldowri.

NOTES

1) Control Room copy of 2-SR-3.4.9.3 &4 should be used.

2) The RWCU System must be in service to perform 2-SR-3.4.9.3&4.

[5] PERFORM 2-SR-3.4.9.3&4, Reactor Recirculation Pump Start Limitations, to CHECK that coolant temperatures are within proper limits.

NOTIFY Management Services (Document Control) to replace Control Room copy of 2-SR-3.4.9.3&4.

Standard:

Checks with Operator that is performing surveillance that coolant temperatures are within limits.

SAT UNSAT N/A COMMENTS:

6

JPM a Performance Step 5: Critical Not Critical

[6] CHECK RECIRC LOOP A DIFF PRESS LOW annunciation, 2-XA-55-4A, Window 31, in ALARM.

Standard:

Checks 2-XA-55-4A, window 31 in ALARM SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 6: 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.

[7] VERIFY CLOSED RECIRC PUMP 2A DISCHARGE VALVE, 2-FCV-68-3.

Standard:

Operator closes RR Pump 2A Discharge Valve 2-HS-68-3. If the operator holds the handswitch in the close position for greater than 3 seconds after the valve indicates full closed (Red light off and green light on) this would constitute a failure due to the caution above.

SAT_ U1JSAT N/A _COMMENTS:________________________________

7

JPM a Performance Step 7: Critical Not Critical X

[8] VERIFY Recirc Drive Cooling System is in service (REFER TO Section 5.1).

Standard:

Verifies Recirc Drive Cooling System in service.

SAT_ UNSAT N/A COMMENTS:________________________________

Performance Step 8: Critical X Not Critical NOTE The following step will apply input voltage to the recirc drive but will not start the recirc pump.

[9] VERIFY CLOSED, RECIRC DRIVE 2A NORMAL FEEDER, 2-HS-57-17, or RECIRC DRIVE 2A ALTERNATE FEEDER, 2-HS-57-15.

Standard:

Closes Recirc Drive 2A Normal Feeder Breaker 2-HS 17.

SAT_ UNSAT_ N/A COMMENTS:________________________________

CUE: IF Asked tell operator to use Normal Feeder Breaker 8

JPM a Performance Step 9: *Critical Not Critical 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) When depressing the switches which control the recirc drives these switches must be firmly depressed to ensure all the contacts are made-up.

[101 IF starting 2A Recirc Pump, THEN:

[10.1] DEPRESS FAULT RESET, 2-HS-96-13

[10.2] CHECK DRIVE READY, 2-IL-96-37 is LIT.

[10.3] FIRMLY DEPRESS DRIVE START, 2-HS-96-11.

Standard:

For 2A Recire Pump Start, Depresses Fault Reset 2-HS-96-13. Checks drive ready light lit. Depresses Drive Start 2-HS-96-1 1.

SAT_ UNSAT_ N/A COMMENTS:______________________________

9

JPM a Performance Step 10: Critical Not Critical X

[12] CHECK the following for the recirc pump being started:

DRIVE RUNNING, 2-IL-96-41 is LIT

Pump DP rises to above 5 psid as indicated on PUMP DP, 2-PDI-68-65.

Recirc Pump 2A speed rises to 345 RPM, as indicated on RECIRC PUMP 2A SPEED, 2-SI-68-59.

RECIRC LOOP A DIFF PRESS LOW 2-PDS-68-65, 2-XA-55-4A, Window 31, is reset.

RECIRC PUMP 2A DISCHARGE VALVE, 2-FCV-68-3, begins to open by the automatic jogging circuit.

RECIRC DRIVE 2A STARTUP SEQ INCOMPLETE, 2-XA-96-40, 2-XA-55-4A, Window 4, is reset.

Standard:

Checks the above indications for the Recirc Pump that was just started.

SAT_ UNSAT N/A COMMENTS:____________________

10

JPM a Performance Step 13: Critical Not Critical X NOTE Recirc Pump A(B) will trip 85 seconds after initiation of the automatic jogging sequence if RECIRC PUMP 2A(2B) DISCHARGE VALVE, 2-FCV-68-3(79), is less than 90 percent open.

[13] VERIFY FULLY OPEN, RECIRC PUMP 2A DISCHARGE VALVE, 2-FCV-68-3.

Standard:

Checks Recirc Pump 2A Discharge Valve Fully Open SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 14: Critical Not Critical

[14] IF necessary to reset runback signal, THEN REFER TO Section 8.4, Resetting Recirc Pump Runback.

Standard:

Not necessary to reset runback signal.

SAT_ UNSAT N/A COMMENTS:________________________________

Performance Step 15: Critical X Not Critical

[15] PLACE in AUTO, RECIRC DRIVE 2A AUTO/MAN SELECT, 2-XS-57-16A. (N/A if recirc drive is supplied by alternate feeder.)

Standard:

Places Recirc Drive 2A 2-XS-16A in AUTO.

SAT_ UNSAT N/A COMMENTS:_____

11

JPM a Performance Step 16: Critical Not Critical

[161 RAISE Recirc Pump Speed 2A using RAISE SLOW (MEDIUM),

2-HS 1 5A( 1 5B)/LOWER SLOW(MEDIUM) 2-HS 1 7A( 1 7B), pushbuttons, to 480rpm.

Standard:

Raises Speed of 2A Recirc Pump to 480 RPM SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 17: Critical Not Critical X NOTE After returning the idle recirc loop to service, Technical Specifications Surveillance Requirements SR 3.4.1.1 and SR 3.4.2.1 have performance requirements which shall be referred to while performing Step 8.1 [16].

[17] Refer to Tech Specs 3.4.1 and 3.4.2.

[18] CHECK locally, RECIRC PUMP 2A breaker closing spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.

[19] PERFORM applicable Section 5.3 as follows:

N/A steps prior to starting the first recirc pump

N/A any steps already performed in this section, as directed by the Unit Supervisor.

Standard:

Dispatches operator to check charging springs SAT_ UNSAT N/A COMMENTS:_____________________________

j CUE: JPM Complete END OF TASK STOP TIME:_____

12

C JPM a OPERATOR:

RO SRO DATE:

JPM NUMBER: a TASK NUMBER: U-068-NO-06 TASK TITLE: Dual Recirc Pump Quick Restart K/A NUMBER: 202001 A4.01 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: Perform control room operations necessary to restart Recirc Pumps 3A LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 3-01-68 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1 1

\JL?L

JPM a INITIAL CONDITIONS:

You are an Operator on Unit 3. 3-SR-3.4.9.3&4 is being performed by another operator.

iNITIATING CUE:

Start Recirc Pump 3A in accordance with 3-01-68, Reactor Recirculation System section 8.1.

2

JPM a 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. V/hen your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 3. 3-SR-3.4.9.3&4 is being performed by another operator.

INITIATING CUE:

Start Recirc Pump 3A in accordance with 3-01-68, Reactor Recirculation System section 8.1.

3

JPM a START TIME____

Performance Step 1: Critical Not Critical X CAUTION DO NOT USE THIS SECTION UNLESS BOTH RECIRC PUMPS ARE TRIPPED!

NOTE to This section provides the steps be performed to restart a recirc pump immediately following a shutdownltrip of both recirc pumps in order to prevent thermal stratification.

[1] VERIFY Reactor in MODE 3.

[2] CHECK RESET the following annunciators:

RECIRC DRIVE VFD A(B) LOCKOUT 3-XA-96-42(43), 3-XA-55-4A(B), Window 6.

RECIRC PUMP A(B) COOLiNG WATER FLOW LOW 3-FA-68-53(66),

3-XA-55-4A(B), Window 34.

Standard:

Identifies Reactor is in MODE 3 and annunciators 3-XA-55-4A(B), window 6 and window 34 are reset.

SAT UNSAT N/A COMMENTS:_____________________________

4

JPM a Performance Step 2: Critical Not Critical X

[3] VERIFY RPTs are reset IF it is desired to RESET RPT breakers from the control room, THEN PERFORM the following: (Otherwise REFER TO Section 8.5)

Standard:

Verifies RPTs are reset SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 3: Critical Not Critical X

[4] VERIFY OPEN, RECIRC PUMP 3A SUCTION VALVE, 3-FCV-68-l.

Standard:

Verifies Recirc Pump 3A Suction Valve OPEN SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 4: Critical Not Critical X

[5] VERIFY in MANUAL, RECIRC DRIVE 3A AUTO/MAN SELECT, 3-XS-57-16A.

Standard:

Verifies Recirc Drive 3A, 3-XS-57-16A in MANUAL.

SAT_ UNSAT N/A COMMENTS:__________

5

JPM a Performance Step 5: Critical Not Critical X CAUTION The recirc pump is required to be started within 15 minutes after the performance of 3-SR-3.4.9.3&4 to prevent pump temperature changes due to cooldown.

NOTES

1) Control Room copy of 3-SR-3.4.9.3&4 should be used.

2) The RWCU System must be in service to perform 3-SR-3.4.9.3&4.

[6] PERFORM 3-SR-3.4.9.3&4, Reactor Recirculation Pump Start Limitations, to CHECK that coolant temperatures are within proper limits.

NOTIFY TIC to replace Control Room copy of 3-SR-3.4.9.3&4.

Standard:

Checks with Operator that is performing surveillance that coolant temperatures are within limits.

SAT_ UNSAT N/A _COMMENTS:_____________________________

CUE: Coolant Temperatures are within Limits and Management Services has been notified.

6

JPM a Performance Step 6: Critical Not Critical

[7] CHECK RECIRC LOOP A DIFF PRESS LOW annunciation, 3-XA-55-4A, Window 31, in ALARM.

Standard:

Checks 3-XA-55-4A, window 31 in ALARM SAT_ UNSAT_ N/A COMMENTS:_____________________________

Performance Step 7: 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 ( 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.

[8] VERIFY CLOSED RECIRC PUMP 3A DISCHARGE VALVE, 3-FCV-68-3.

Standard:

Operator closes RR Pump 3A Discharge Valve 3-HS-68-3. If the operator holds the handswitch in the close position for greater than 3 seconds after the valve indicates full closed (Red light off and green light on) this would constitute a failure due to the caution above.

SAT_ UNSAT N/A COMMENTS:_______________________________

7

JPM a Performance Step 8: Critical Not Critical

[9] VERIFY Recirc Drive Cooling System is in service (REFER TO Section 5.1).

Standard:

Verifies Recirc Drive Cooling System in service.

SAT_ UNSAT N/A COMMENTS:________________________________

Performance Step 9: Critical X Not Critical NOTE The following step will apply input voltage to the recirc drive but will not start the recirc pump.

[101 VERIFY CLOSED, RECIRC DRIVE 3A NORMAL FEEDER, 3-HS-57-17, or RECIRC DRIVE 3A ALTERNATE FEEDER, 3-HS-57-15.

Standard:

Closes Recirc Drive 3A Normal Feeder Breaker 3-HS-57-17.

SAT_ UNSAT N/A COMMENTS:______________

CUE: IF Asked tell operator to use Normal Feeder Breaker I 8

JPM a Performance Step 10: X Not Critical 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) When depressing the switches which control the recirc drives these switches must be firmly depressed to ensure all the contacts are made-up.

[11] IF starting 2A Recirc Pump, THEN:

[1 1.11 DEPRESS FAULT RESET, 3-HS-96-13

[11.2] CHECK DRIVE READY, 3-IL-96-37 is LIT.

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

Standard:

For 3A Recirc Pump Start, Depresses Fault Reset 3-HS-96-13. Checks drive ready light lit. Depresses Drive Start 3-HS-96-1 1.

SAT_ UNSAT_ N/A COMMENTS:____________________________

9

JPM a Performance Step 11: Critical Not Critical X

[13] CHECK the following for the recirc pump being started:

DRIVE RUNNING, 3-IL-96-41 is LIT

Pump DP rises to above 5 psid as indicated on PUMP DP, 3-PDI-68-65.

Recirc Pump 3A speed rises to 345 RPM, as indicated on RECIRC PUMP 3A SPEED, 3-SI-68-59.

RECIRC LOOP A DIFF PRESS LOW 3-PDS-68-65, 3-XA-55-4A(B), Window 31, is reset.

RECIRC PUMP 3A DISCHARGE VALVE, 3-FCV-68-3, begins to open by the automatic jogging circuit.

RECIRC DRIVE 3A STARTUP SEQ iNCOMPLETE, 3-XA-96-40, 3-XA-55-4A, Window 4, is reset.

Standard:

Checks the above indications for the Recirc Pump that was just started.

SAT_ UNSAT N/A COMMENTS:____________________

10

JPM a Performance Step 14: Critical Not Critical X NOTE Recirc Pump A(B) will trip 85 seconds after initiation of the automatic jogging sequence if RECIRC PUMP 3A(3B) DISCHARGE VALVE, 3-FCV-68-3(79), is less than 90 percent open.

[14] VERIFY FULLY OPEN, RECIRC PUMP 3A DISCHARGE VALVE, 3-FCV-68-3.

Standard:

Checks Recirc Pump 3A Discharge Valve Fully Open SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 15: Critical Not Critical X

[15] IF necessary to reset runback signal, THEN REFER TO Section 8.4, Resetting Recirc Pump Runback.

Standard:

Not necessary to reset runback signal.

SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 16: Critical X Not Critical

[16] PLACE in AUTO, RECIRC DRIVE 3A AUTO/MAN SELECT, 3-XS-57-16A. (N/A if recirc drive is supplied by alternate feeder.)

Standard:

Places Recirc Drive 3A, 3-XS-16A in AUTO.

SAT_ UNSAT N/A COMMENTS:_____

11

JPM a Performance Step 17: Critical Not Critical

[16] RAISE Recirc Pump Speed 3A using RAISE SLOW (MEDIUM),

3 -HS 1 5A( 1 5B)/LOWER SLOW(MEDIUM) 3 -HS-96.. 1 7A( 1 7B), pushbuttons, to 480rpm.

Standard:

Raises Speed of 3A Recirc Pump to 480 RPM SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 18: Critical Not Critical NOTE After returning the idle recirc loop to service, Technical Specifications Surveillance Requirements SR 3.4.1.1 and SR 3.4.2.1 have performance requirements which shall be referred to while performing Step 8.1 [16].

[17] Refer to Tech Specs 3.4.1 and 3.4.2.

[18] CHECK locally, RECIRC PUMP 3A breaker closing spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.

Standard:

Dispatches operator to check charging springs SAT_ UNSAT N/A COMMENTS:_______________________________

I CUE: JPM Complete END OF TASK STOP TIME:

12

JPM b OPERATOR:

RU SRO DATE:

JPM NUMBER: b TASK NUMBER: U-003-NO-08 TASK TITLE: RFPT Trip Recovery lAW 3-01-3 Section 8.1 KIA NUMBER: 259001 A2.01 KJA RATING: RU 3.7 SRO 3.7 TASK STANDARD: Perform control room operations necessary to place an Alternate RFPT in service lAW 3-01-3 Section 8.1.

LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 3-01-3 VALIDATION TIME: minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

JPM b INITIAL CONDITIONS:

You are an Operator on Unit 3. Unit 3 is in MODE 2 with a start up in progress.

RFPT 3C has tripped, the actions of RFPT Tripped 3-XA-55-6C window 29 are complete.

RFPT 3B has been warmed, is reset and rolling. RPHP is in effect for placing RFPT 3B in service and appropriate data and signatures are recorded on Appendix A.

INITIATING CUE:

In accordance with 3-01-3, Reactor Feedwater System section 8.1, place the Alternate 3B RFPT in service and recover Reactor Level.

2

JPM b IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 3. Unit 3 is in MODE 2 with a start up in progress.

RFPT 3C has tripped, the actions of RFPT Tripped 3-XA-55-6C window 29 are complete.

RFPT 3B has been warmed, is reset and rolling. RPHP is in effect for placing RFPT 3B in service and appropriate data and signatures are recorded on Appendix A.

INITIATING CUE:

In accordance with 3-01-3, Reactor Feedwater System section 8.1, place the Alternate 3B RFPT in service and recover Reactor Level.

3

JPM b START TIME Performance Step 1: Critical Not Critical X NOTE Unless otherwise noted, all actions are performed at Panel 3-9-6.

8.1 RFPT Trip Recovery

[1] VERIFY complete actions of Alarm Response RFPT TRIPPED, 3-XA-55-6C Window 29.

Standard:

Given in initial conditions that this step is complete.

SAT_ U1JSAT N/A COMMENTS:_____________________________

Performance Step 2: Critical X Not Critical

[2] CHECK CLOSED RFP 3C DISCH TESTABLE CHECK VLV, 3-FCV-3-92, by one of the following:

Observe RFP discharge flow indicator.

Locally listening to check valve slam.

A. IF testable check valve did NOT close, THEN CLOSE tripped RFP discharge and suction valves.

Standard:

RFPT 3C Discharge Testable Check Valve failed to close, Operator closes RFPT 3C Discharge and Suction Valves 3-HS-3-5A and 3-HS-2-108A.

SAT_ UNSAT N/A COMMENTS:_____________________________

4

JPM b Performance Step 3: Critical X Not Critical

[3] IF desired to place alternate RFP/RFPT in service AND another RFPT is available, THEN PERFORM applicable action: (Otherwise N/A)

IF no RFP/RFPT in service, THEN REFER TO Section 5.5.

Standard:

Operator refers to section 5.5 to place RFPT 3B in service SAT_ UNSAT N/A COMMENTS:_____________

5

JPM b Performance Step 4: Critical Not Critical X 5.5 Placing the First RFPIRFPT in Service CAUTIONS

1) Operators should verify Reactor Pressure greater than Condensate Pressure before opening first RFP Discharge Valve. This will prevent unwanted level addition to Reactor Vessel.

2) Quick charging a high pressure heater could result in piping and/or hanger/support damage.

3) Failure to verify high pressure heater outlet pressure is approximately equal to Condensate Booster pump discharge pressure, prior to opening a reactor feed pump discharge valve could result in quick charging the high pressure heater.

NOTE Illustration 1 has general information on Startup Level Control Panel Display Station (PDS),

3-LIC-3-53.

[1] REFER TO Section 5.4 and VERIFY RFP/RFPT has been warmed, reset and rolling.

[2] BEFORE placing the RFPT in service:

[2.1] NOTIFY Radiation Protection that an RPHP is in effect for the impending action to place RFPT 3A(3B)(3C) in service. RECORD time Radiation Protection notified in NOMS Narrative Log [BFN PER 1262111.

[2.2] VERIFY appropriate data and signatures recorded on Appendix A per Appendix A instructions [Tech Spec 5.7] [BFN PER 126211].

Standard:

Given in initial conditions that this is complete.

SAT_ UNSAT N/A _COMMENTS:_________________________

6

JPM b Performance Step 5: Critical Not Critical X

[3] CHECK the following:

RPV pressure? 450 psig.

RFP Discharge Pressure for pump to be placed in service is less than Reactor pressure.

Standard:

Checks RPV Pressure is greater than 450 psig and the RFP Discharge Pressure is less than RPV Pressure.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 6: Critical Not Critical

[4] VERIFY the following on RFW START-UP LEVEL CONTROL, 3-LIC-3-53 (Panel 3-9-5):

Column 3 selected and in MANUAL.

Valve position demand set at 0 or slightly negative value.

Standard:

Verifies Start Up Level Control has column 3 selected and the valve position demand is at zero.

SAT_ UNSAT N/A _COMMENTS:____

7

JPM b Performance Step 7: Critical Not Critical X CAUTION TACF 3-13-002-0003 cut and caps long cycle cleanup piping to the miscellaneous drains header and power removed on 3-FCV-003-0071, 3-FCV-003-0072 and 3-FCV-003-0073 (Long Cycle to Condenser). Long cycle clean-up will NOT be available while TACF 3-13-002-0003 is in effect.

[5] VERIFY CLOSED the following valves:

(N/A if TACF 3-13-002-0003 is in effect.)

[6] VERIFY OPEN the following on available heater strings:

HP HTR 3A2 FW INLET ISOL VALVE, 3-HS-3-38A

HP HTR 3A1 FW OUTLET ISOL VLV, 3-HS-3-75A

HP HTR 3B2 FW INLET ISOL VALVE, 3-HS-3-31A

HP HTR 3B1 FW OUTLET ISOL VLV, 3-HS-3-76A

HP HTR 3C2 FW INLET ISOL VALVE, 3-HS-3-24A

HP HTR 3C1 FW OUTLET ISOL VLV, 3-HS-3-77A Standard:

Step 5 is NA TACF 3-13-002-0003 is in effect, verifies OPEN the 6 listed heater string valves.

SAT_ UNSAT N/A COMMENTS:____

8

JPM b Performance Step 8: Critical Not Critical X

[7] CHECK indicated pressure on HP HTR OUTLET, 3-PI-3-45 approximately equal to indicated pressure on CNDS BSTR PMP DISCH HDR PRESS, 3-PI-2-70 (Panel 3-9-6).

IF high pressure heater outlet pressure is NOT within approximately 50 psig of Condensate Booster pump discharge pressure, THEN REFER TO Section 5.2 (Placing the Startup Level Control Valve in Service) to charge high pressure heaters to within 50 psig of Condensate Booster pump discharge pressure.

Standard:

Verifies 3-PI-3-45 is within 50 psig of 3-PI-2-70.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 9: Critical Not Critical X

[8] IF RFW START-UP LEVEL CONTROL, 3-LIC-3-53 was used to charge high pressure heater in Step 5.5[7], THEN VERIFY the following on RFW START-UP LEVEL CONTROL, 3-LIC-3-53 (On Panel 3-9-5):

(Otherwise N/A)

Standard:

Step is NA SAT_ UNSAT N/A _COMMENTS:____

9

JPM b Performance Step 10: Critical Not Critical

[9] OPEN RFP discharge valve for pump being placed in service:

RFP 3B DISCHARGE VALVE, 3-FCV-3-12 Standard:

OPENS 3-FCV-3-12 SAT_ UNSAT_ N/A COMMENTS:_____________________________

Performance Step 11: Critical Not Critical NOTE Placing REP 3A(3B)(3C) M11SI FLOW VALVE, 3-HS-3-20(13)(6), in OPEN position will keep valve open, thus preventing minimum flow valve oscillations at low flow.

[10] VERIFY RFP MIN FLOW VALVE in OPEN position.

RFP 3B MIN FLOW VALVE, 3-HS-3-13, in OPEN position and 3-FCV-3-13, MIN FLOW VALVE is OPEN.

Standard:

Places 3B Minimum Flow Valve 3-HS-3-13 in the OPEN position SAT_ UNSAT N/A COMMENTS:________________________________

Performance Step 12: Critical Not Critical X

[11] REFER TO 3-01-2 and VERIFY at least one Condensate and one Condensate Booster pumps running.

Standard:

Verifies one Condensate and Condensate Booster Pump in service SAT_ UNSAT_ N/A _COMMENTS:_______________________________

10

JPM b Performance Step 13: Critical X Not Critical CAUTIONS

1) FAILURE to monitor SJAE/OG CNDR CNDS FLOW, 3-FI-2-42, on Panel 3-9-6 for proper flow (between 2 x 106 and 3 x 106 lbmlhr) may result in SJAE isolation.

2) Changes in Condensate System flow may require adjustment to SPE CNDS BYPASS, 3-FCV-002-01 90.

NOTE Illustration 2 has information concerning RFPT Speed Control Panel Display Stations (PDS).

[12] SLOWLY RAISE speed of RFPT using RFPT SPEED CONT RAISE/LOWER switch, to establish flow to vessel and maintain level.

RFPT 3B SPEED CONT RAISE/LOWER switch, 3-HS-46-9A Standard:

Raises speed of RFPT 3B to establish flow to the vessel and maintain level.

SAT_ UNSAT N/A COMMENTS:________________________________

END OF TASK STOP TIME:

11

JPM c OPERATOR:

RO SRO DATE:

JPM NUMBER: c Alternate Path TASK NUMBER: U-00l-AB-01 TASK TITLE: RESPOND TO STUCK OPEN SRV KJA NUMBER: 239002 A2.03 KJA RATING: RO 4.1 SRO 4.2 TASK STANDARD: Perform control room operations necessary to respond to a stuck open SRV as directed by 2-AOl-i-i LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 2-AOl- 1-1 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

JPM C INITIAL CONDITIONS:

You are an Operator. Unit 2 is at 100% power.

INITIATING CUE:

Respond to the next event.

2

JPM c 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. Unit 2 is at 100% power.

INITIATING CUE:

Respond to the next event.

3

JPM c START TIME Simulator Driver: This JPM requires SRV 1-5 stuck open (imf adOla 50). I Performance Step 1: Critical Not Critical NOTE Once a MSRV is operated, a time delay of 15 to 30 seconds can be expected before a response can be detected on 2-TR- 1-1, MSRV DISCHARGE TAILPIPE TEMPERATURE.

ICS can be used to monitor the discharge tailpipe temperature, but the appropriate indications on 2-TR- 1-1 must be confirmed.

4.1 Immediate Action

[1] IDENTIFY stuck open relief valve by OBSERVING the following:

SRV TAILPIPE FLOW MONITOR, 2-FMT-l-4, on Panel 2-9-3, OR

MSRV DISCHARGE TAILPIPE TEMPERATURE recorder, 2-TR-1-1 on Panel 2-9-47.

Standard:

Identified MSRV 1-5 OPEN as indicated on 2-FMT-1-4 SRV Tailpipe Flow Monitor on Panel 2-9-3 or elevated tailpipe temperature as indicated on 2-TR-1-1, Panel 2-9-47.

SAT_ UNSAT_ N/A COMMENTS:________________________________

4

JPM c Performance Step 2: Critical X Not Critical

[2] IF relief valve transient occurred while operating above 90%

power, THEN REDUCE reactor power to 90% RTP with recirc flow.

Standard:

Operator Reduces reactor power to 90% RTP with recirc flow.

SAT_ UNSAT N/A COMMENTS:__________________________

Performance Step 3: Critical Not Critical

[3] WHILE OBSERVING the indications for the affected Relief valve on the Acoustic Monitor; CYCLE the affected relief valve control switch as required up to three times:

CLOSE to OPEN to CLOSE positions Standard:

Placed 2-HS-l-5 in the CLOSE-OPEN-CLOSE position up to three times. Determines valve DID NOT close as indicated by MSRV TAILPIPE FLOW MONITOR or NO indicated increase in generator Mwe.

SAT_ UNSAT N/A COMMENTS:___________________________

5

JPM c Performance Step 4: Critical Not Critical X

[4] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Verified that the SRV did not close and continues in the procedure at step 4.2.1 SAT_ UNSAT N/A _COMMENTS:________________________________

Performance Step 5: Critical Not Critical X NOTES

1) Once initial transient of SRV opening has stabilized (pressure regulator compensation) the Heat balance will indicate bad data.

2) The SRV TAILPIPE FLOW MONITOR may seal-in an OPEN position indication.

4.2 Subsequent Action 4.2.1 Action if a fire exists with SRV stuck open

[1] IF an SRV is open and a fire exists in ANY Appendix R fire area, THEN (Otherwise N/A):

Standard:

No fire is indicated. This step is not applicable.

SAT_ UNSAT N/A 6

JPM c Performance Step 6: Critical Not Critical X 4.2 Subsequent Action 4.2.2 Attempt to close valve from Panel 9-3:

[1] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the OFF position.

[2] PLACE the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON position.

[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.4. (Otherwise N/A)

Standard:

Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the off position and verifies the power is off. Placed the SRV TAILPIPE FLOW MONITOR POWER SWITCH in the ON Position and verifies SRV 1-5 did not close and continues at step [4].

SAT_ UNSAT_ N/A COMMENTS:_____________________________

7

JPM c Performance Step 7:

Critical X Not Critical

[4] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT, 2-XS-l-202 in iNHIBIT:

[5] IF relief valve closes, THEN OPEN breaker or PULL fuses as necessary using Attachment 1 (Unit 2 SRV Solenoid Power Breaker/Fuse Table).

Standard:

Placed MSRV AUTO ACTUATION LOGIC INHIBIT, 2-XS-1-202 in INHIBIT.

Verifies SRV 1-5 did NOT close.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 8: Critical Not Critical

[6] PLACE MSRV AUTO ACTUATION LOGIC INHIBIT 2-XS-l-202, in AUTO.

Standard:

Places MSRV AUTO ACTUATION LOGIC INHIBIT 2-XS-1-202, in AUTO.

SAT_ UNSAT N/A _COMMENTS:__________________________

8

JPM c Performance Step 9: Critical X Not Critical NOTES I) Only the appropriate sections for the stuck open relief valve are required to be performed.

2) The ADS valves that have more than one power supply will AUTO TRANSFER on a loss of power, and are NORMAL SEEKING.

3) ADS Relief valves with hand-switches on Panel 25-32 are listed below and should be operated from that location first.

4) When opening breakers and pulling fuses, opening the breakers is the preferred method when time permits. However, the breakers with multiple locations will require opening each breaker to de-energize the control circuit. In this case, pulling the fuses from Panel 25-32 may be quicker than opening the breakers.

[7] IF the SRV valve did not close, THEN PERFORM the appropriate section from table below.

RELIEF STEP Switch Breaker Fuse VALVE NUMBER Location Location Location SRV 1-5 Step 4.23[1J Panel 25-32 Multiple Panel 25-32 Standard:

Determines step 4.2.3[l] is required SAT UNSAT N/A COMMENTS:

I CUE: Proceed to Panel 25-32 Driver: When operator exits the control room disable the annunciators and delete the malfunction for the open SRV 9

JPM c Performance Step 10: Critical Not Critical NOTES

1) 2-PCV-1-5 is an ADS Valve

2) 2-PCV-1-5 has two power supplies, it will auto transfer on loss of power and is Normal Seeking.

3) Attachment 1 may be address for fuse and breaker information.

4.2.3 Attempt to close valve from outside the control room:

[1] IF 2-PCV-1-5 is NOT closed, THEN PERFORM the following:

[1.1] On Panel 2-25-32 PLACE the transfer switch associated MAIN STM LINE A RELIEF VALVE XFR, 2-XS-1-5 in EMERG position.

Standard:

Places 2-XS-1-5 in EMERG SAT_ UNSAT N/A COMMENTS:_______________________________

I CUE: When operator calls Control Room report SRV did NOT close I 10

JPM c Performance Step 11: Critical X Not Critical

[1.2] IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 2-PCV-1-5 on the Acoustic Monitor:

CYCLE the MAIN STM LINE A RELIEF VALVE, 2-HS-1-5C to the following positions several times. CLOSE/AUTO to OPEN to CLOSE/AUTO Standard:

Cycles 2-HS-1-5C several times SAT_ UNSAT N/A COMMENTS:

I CUE: When operator calls Control Room report SRV CLOSED I Performance Step 12: Critical Not Critical

[1.3] IF the SRV does NOT close, THEN PERFORM the following: (Otherwise N/A)

[1.4] IF the SRV does NOT close, THEN REMOVE the power from 2-PCV-l-5 by performing one of the following: (Opening breakers are the preferred method) (Otherwise N/A)

[1.5] IF the valve does NOT close, THEN CLOSE the breakers or REINSTALL fuses removed in Step 4.2.3[1.4J.

Standard:

SRV Closed in step 1.2 all remaining steps are NA, if OPERATOR requests fuses pulled or breakers open or places 2-XS-1-5 back to NORM then this would constitute a FAILURE.

SAT_ UNSAT_ N/A COMMENTS:________

END OF TASK STOP TIME:_____

11

JPM d OPERATOR:

RU___ SRO___ DATE:

JPM NTJMBER: d Alternate Path TASK NUMBER: U-085-AL-12 TASK TITLE: RPS Channel Functional KIA NUMBER: 201002 A2.02 KJA RATING: RU 3.2 SRO: 3.3 TASK STANDARD: Perform RPS Channel Functional, successful test on RPS A, when RPS B tested two control rods will scram, requiring the operator to insert a manual scram JAW AOI-85-5, Rod Drift In LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-SR-3 .3.1.1.8(11), 2-AOI-85-5 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

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

DATE:

EXAMINER 1

INITIAL CONDITIONS:

You are an Operator on Unit 2.

iNITIATiNG CUE:

The Unit Supervisor has directed you to continue with the quarterly scheduled surveillance 2-SR-3.3.l.l.8(11) Reactor Protection System Manual Scram Functional Test at step 7.2[l].

1PM d IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfUlly, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 2.

INITIATING CUE:

The Unit Supervisor has directed you to continue with the quarterly scheduled surveillance 2-SR-3 .3.1.1.8(11) Reactor Protection System Manual Scram Functional Test at step 7.2[1 j.

3

JPM d START TIME____

Performance Step 1: Critical Not Critical 7.2 RPS Manual Scram Channel A Functional Test

[1] MOMENTARILY DEPRESS Reactor Scram A push-button, Panel 2-9-5.

Standard:

Depresses Reactor Scram A push-button SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 2: Critical Not Critical

[2] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A indicating lights (4) extinguished.

One System A Back-Up Scram Valve light 2-IL-99-5A/AB and System B Back-Up Scram Valve light 2-IL-99-5AJCD extinguished.

Reactor Scram A push-button illuminated.

Annunciator REACTOR CHAN14EL A MAN SCRAM (2-XA-55-5B, window 8) in alarm.

[3] VERIFY ICS point 50E033 indicates TRIP.

Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A COMMENTS:____

4

JPM d Performance Step 3: Critical Not Critical

[4] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 1/4 position.

Standard:

Places Scram Reset switch to GP 1/4 position SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 4: Critical Not Critical X

[5] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights 1 and 4 illuminated, and lights 2 and 3 extinguished.

Both System A Backup Scram Valve lights 2-IL-99-5AJAB illuminated.

One System B Backup Scram Valve light 2-IL-99-5AJCD illuminated, and one System B Backup Scram Valve light 2-IL-99-5A/CD extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A _COMMENTS:___

5

1PM d Performance Step 5: Critical Not Critical

[6] MOMENTARILY DEPRESS Reactor Scram A push-button.

Standard:

Depresses Reactor Scram A push-button SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 6: Critical Not Critical

[7] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights 1 and 4 extinguished.

One System A Backup Scram Valve light 2-IL-99-5AJAB extinguished.

Standard:

Verifies the conditions listed above are met.

SAT_ UNSAT_ N/A COMMENTS:___________________________

Performance Step 7: Critical Not Critical

[8] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5 to Reset Gp 2/3 position.

Standard:

Places Scram Reset switch to GP 2/3 position.

SAT_ UNSAT N/A COMMENTS:_____

6

1PM d Performance Step 8: Critical Not Critical X

[9] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights 2 and 3 illuminated, and lights 1 and 4 extinguished.

Both System B Backup Scram Valve lights 2-IL-99-5AJCD illuminated.

One System A Backup Scram Valve light 2-IL-99-5A/AB on System A Backup Scram Valve light illuminated, and one System A Backup Scram Valve light 2-IL-99-5A/AB extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

[10] VERIFY ICS point S0E033 indicates NOTTRIP.

Standard:

Verifies the conditions listed above are met.

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 9: Critical X Not Critical

[11] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 1/4 position.

Standard:

Places Scram Reset switch to GP 1/4 position.

SAT_ UNSAT N/A COMMENTS:_____

7

JPM d Performance Step 10: Critical Not Critical X

[12] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 2-IL-99-5AIAB illuminated.

System B Back-Up Scram Valve lights 2-IL-99-5AJCD illuminated.

Reactor Scram A push-button extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) reset.

[13] VERIFY the following computer points indicates NOTTRIP.

ICS point S0E033

ICS point S0E034 Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A COMMENTS:____

8

JPM d Performance Step 11: Critical X Not Critical 7.3 RPS Manual Scram Channel B Functional Test

[1] MOMENTARILY DEPRESS Reactor Manual Scram B push-button, Panel 2-9-5.

Standard:

Depresses Reactor Scram B push-button SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 12: Critical X Not Critical Determines that multiple rods are drifting into the core.

Standard:

Determines that more than one control rod has scrammed or drifted into the core.

SAT_ UNSAT N/A _COMMENTS:_____________________________

9

JPM d Performance Step 13: Critical Not Critical Rod Drift In 2-AOI-85-5 4.1 Immediate Actions

[1] IF multiple rods are drifting into core, THEN MANUALLY SCRAM Reactor. Refer to 2-AOl- 100-1.

DEPRESS REACTOR SCRAM A and B, 2-HS-99-5A/S3A and 2-HS-99-5AJS3B, on Panel 2-9-5.

Standard:

Inserts a Manual SCRAM.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 14: Critical Not Critical Reactor Scram 2-AOI-100-1

[4] PLACE REACTOR MODE SWITCH, 2-HS-99-5A-S1, in SHUTDOWN.

Standard:

Places Reactor Mode Switch in Shutdown.

SAT_ UNSAT N/A COMMENTS:________________

CUE: After Scram report another operator will continue in 2-AOI-100-1.

STOP TIME____

END OF TASK 10

C Browns Ferry Nuclear Plant Unit 2 Surveillance Procedure 2-SR-3.3.1 .1.8(11)

Reactor Protection System Manual Scram Functional Test Revision 0004 Quality Related Level of Use: Continuous Use Effective Date: 09-18-2008 Responsible Organization: OPS, Operations Prepared By: Michael S. Rice Approved By: John T. Kulisek

BFN Reactor Protection System Manual 2-SR-3.3.1.1.8(11)

UnIt 2 Scram Functional Test Rev. 0004 Page 2 of 18 Current Revision Description Pages Affected: All Type of Change: XP Conversion Tracking Number: 006 This procedure was converted from Word 95 to Word 2003 using Rev 3.

Added SR key number to Attachment I for Scheduling

BFN Reactor Protection System Manual 2-SR-3.3.1 .1 .8(11)

Unit 2 Scram Functional Test Rev. 0004 Page3ofl8 Table of Contents INTRODUCTION 4 1.0 Purpose 4 1.1 Scope 4 1.2 Frequency 4 1.3 1.4 Applicability 4

2.0 REFERENCES

5 2.1 Technical Specifications 5 2.2 Final Safety Analysis Report 5 2.3 GE Drawings 5 3.0 PRECAUTIONS AND LIMITATIONS 6 4.0 PREREQUISITES 7 5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED 7 6.0 ACCEPTANCE CRITERIA 7 7.0 PROCEDURE STEPS 8 7.1 Initial Requirements and Notifications 8 7.2 RPS Manual Scram Channel A Functional Test 10 7.3 RPS Manual Scram Channel B Functional Test 13 7.4 Completion and Notifications 15 8.0 ILLUSTRATIONSIATTACHMENTS 16 Attachment 1: Surveillance Procedure Review Form 17 Attachment 2: Control Room Components Affected by Surveillance Procedure Performance 18

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 4 of 18

1.0 INTRODUCTION

1.1 Purpose This surveillance procedure performs a functional test of the manual scram push-buttons in conformance with the requirements specified in Technical Specification Table 3.3.1.1-1 (Function 11). This procedure meets the requirements of SR 3.3.1.1.14. This procedure, also, partially satisfies the requirements of SR 3.10.3.1 and 3.10.4.1.

1.2 Scope This surveillance procedure completely satisfies the manual scram functional test requirements of Technical Specification 3.3.1.1.

This procedure provides overlap testing with 2-SR-3.3.1 .1.12 by verifying Scram Solenoid Group A and B Logic Reset lights extinguish with the associated RPS channel trip. This partially satisfies SR 3.3.1.1.14, Logic System Functional Test.

1.3 Frequency Once every 92 days.

1.4 Applicability The SR requirements of this procedure are applicable in Modes I and 2. Mode 5 is also applicable with any control rod withdrawn from a core cell containing one or more fuel assemblies.

BFN Reactor Protection System Manual 2$R-3.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 5oflB

2.0 REFERENCES

2.1 Technical Specifications Section 3.3.1.1, 3.10.3 and 3.10.4 2.2 Final Safety Analysis Report Section 7.2, Reactor Protection System 2.3 GE Drawings 2-730E915-6, Elementary Diagram Reactor Protection System 2-730E91 5 Sh. 7, Elementary Diagram Reactor Protection System 2-730E915RF Sh. 11, Elementary Diagram Reactor Protection System 2-730E915RF Sh. 12, Elementary Diagram Reactor Protection System 2-730E915-13, Elementary Diagram Reactor Protection System 2-730E915 Sh. 14, Elementary Diagram Reactor Protection System 2-730E915 Sh. 17, Elementary Diagram Reactor Protection System 2-730E915RF Sh. 18, Elementary Diagram Reactor Protection System

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 6 of 18 3.0 PRECAUTIONS AND LIMITATIONS A. If any control rod actually scrams during performance of this test, wait at least 10 seconds before resetting the scram to ensure that the scram has gone to completion.

B. Corrective Actions shall be handled in accordance with SPP-8.1, Conduct of Testing.

C. The following annunciators should alarm during the performance of this test:

REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8)

REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9)

0. The following Integrated Computer System (lCS) points should alarm during the performance of this test:

Point S0E033 Point S0E034 E. The Critical Step warning designates a step or series of steps for an activity which requires additional focus, attention, and increased awareness. The Operator performing these steps for the activity needs to ensure the Unit Supervisor and other Control Room staff are aware of the evolution. PEER checks are required for this activity and short briefs need to be made prior to performing the evolution. Included in the briefs are worst case scenario and contingencies.

BFN Reactor Protection System Manual 2-SR-.3.3..1 .1 .8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 7 of 18 Date 100A)/

4.0 PREREQUISITES This copy of 2-SR-3.3.1.1 .8(11) is verified the most current revision.

No other tests or maintenance are in progress which could initiate any of the logic in the Reactor Protection System.

5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED None 6.0 ACCEPTANCE CRITERIA A. Responses which fail to meet the acceptance criteria stated in this section shall constitute unsatisfactory SR results and require immediate notification of the Unit Supervisor at the time of failure.

1. Control Rod Logic Reset Solenoid Group A indicating lights (4) on Panel 2-9-5 are extinguished when Reactor Scram A push-button on Panel 2-9-5 is depressed.

2. Control Rod Logic Reset Solenoid Group B indicating lights (4) on Panel 2-9-5 are extinguished when Reactor Scram B push-button on Panel 2-9-5 is depressed.

B. Steps which verify acceptance criteria are designated by (AC) next to the initial blanks.

BFN Reactor Protection System Manual 2-SR4.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 8 of 18 Date 7.0 PROCEDURE STEPS 7.1 Initial Requirements and Notifications VERIFY Precautions and Limitations in Section 3.0 have been reviewed.

VERIFY Prerequisites listed in Section 4.0 are satisfied.

VERIFY the following on Panel 2-9-5:

/ Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

/ Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

/ System A Back-Up Scram Valve lights 2-lL-99-5A/AB illuminated.

/ System B Back-Up Scram Valve lights 2-lL-99-5AICD illuminated.

4 Reactor Scram A push-button extinguished.

A Reactor Scram B push-button extinguished.

I Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) reset.

/ Annunciator REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9) reset. fr (NRCICJ OBTAIN permission from the Unit Supervisor to perform this test. [LER 259189023J Us LNRCICI NOTIFY the Unit Operator (UO) before commencing this instruction. [LER 259/820321

BFN Reactor Protection System Manual 2-SR-33.i .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 9 of 18 Date 1DP)/

7.1 Initial Requirements and Notifications (continued)

PERFORM the following:

DISCUSS with the UO the effects this procedure has on plant equipment/status.

INFORM UO that the Integrated Computer System (ICS) will be affected during performance of this procedure and that ICS alarms may be received.

GIVE copy of Attachment 2, Control Room Components Affected by Surveillance Procedure Performance, to the UO as a reminder that this channel is in test.

RECORD the start date, start time, reason for the test, plant conditions, and any pre-test remarks on Attachment 1, Surveillance Procedure Review Form.

-7,

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

UnIt 2 Scram Functional Test Rev. 0004 Page 10 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test Start of Critical Step(s)

[1] MOMENTARILY DEPRESS Reactor Scram A push-button, Panel 2-9-5.

End of Critical Step(s)

[2] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A indicating lights (4) extinguished.

One System A Back-Up Scram Valve light 2-IL-99-5A!AB and System B Back-Up Scram Valve light 2-lL-99-5AICD extinguished.

Reactor Scram A push-button illuminated.

Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) in alarm.

[3] VERIFY ICS point S0E033 indicates TRIP.

[4] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 1/4 position.

[5] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights I and 4 illuminated, and lights 2 and 3 extinguished.

Both System A Backup Scram Valve lights 2-lL-99-5AIAB illuminated.

One System B Backup Scram Valve light 2-IL-99-5A/CD illuminated, and one System B Backup Scram Valve light 2-I L-99-5AICD extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 11 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

Start of Critical Step(s)

[6] MOMENTARILY DEPRESS Reactor Scram A push-button.

End of Critical Step(s)

[7] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights I and 4 extinguished.

One System A Backup Scram Valve light 2-IL-99-5A/AB extinguished.

[8] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5 to Reset Gp 213 position.

[9] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A lights 2 and 3 illuminated, and lights I and 4 extinguished.

Both System B Backup Scram Valve lights 2-IL-99-5AICD illuminated.

One System A Backup Scram Valve light 2-IL-99-5A!AB on System A Backup Scram Valve light illuminated, and one System A Backup Scram Valve light 2-lL-99-5NAB extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

[10] VERIFY ICS point S0E033 indicates NOTTRIP.

[11] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 1/4 position.

BFN Reactor Protection System Manual 2-SR4.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 12 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

[12] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 2-lL-99-5NAB illuminated.

System B Back-Up Scram Valve lights 2-lL-99-5AICD illuminated.

Reactor Scram A push-button extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (2-XA-55-5B, window 8) reset.

[13] VERIFY the following computer points indicates NOTTRIP.

ICS point S0E033 ICS point S0E034

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 13 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test Start of Critical Step(s)

[1] MOMENTARILY DEPRESS Reactor Manual Scram B push-button, Panel 2-9-5.

End of Critical Step(s)

[2] VERIFY the following on Panel 2-9-5:

. Control Rod Logic Reset Solenoid Group B indicating lights (4) extinguished.

. One System B Backup Scram Valve light 2-IL-99-5AICD and one System A Backup Scram Valve light 2-I L-99-5A/AB extinguished.

. Reactor Scram B push-button illuminated.

. Annunciator REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9) in alarm.

[3] VERIFY ICS point S0E034 indicates TRIP.

[41 MOMENTARILY PLACE the Scram Reset switch, Panel 2-9-5 to Reset Gp 1/4 position.

[5] VERIFY the following on Panel 2-9-5:

. Control Rod Logic Reset Solenoid Group B lights I and 4 illuminated and lights 2 and 3 extinguished.

. Both System B Backup Scram Valve lights 2-IL-99-5A!CD illuminated.

. One System A Backup Scram Valve light 2-IL-99-5AIAB illuminated and one System A Backup Scram Valve light 2-IL-99-5A/AB extinguished.

. Annunciator REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9) will NOT reset.

. Reactor Scram B push-button illuminated.

BFN Reactor Protection System Manual 2-SR-3.3.1.1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 14 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

Start of Critical Step(s)

[6] MOMENTARILY DEPRESS Reactor Scram B push-button.

End of Critical Step(s)

[7] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group B lights 1 and 4 extinguished.

One System B Backup Scram Valve light 2-IL-99-5A/CD extinguished.

[8] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 2/3 position.

[9] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group B lights 2 and 3 illuminated, and lights I and 4 extinguished.

Both System A Backup Scram Valve lights 2-IL-99-5A/AB illuminated.

One System B Backup Scram Valve light 2-IL-99-5AICD illuminated and one System B Backup Scram Valve light 2-IL-99-5A/CD extinguished.

Annunciator REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9) will NOT reset.

Reactor Scram B push-button illuminated.

[10] VERIFY ICS point S0E034 indicates NOTTRIP.

[11] MOMENTARILY PLACE Scram Reset switch, Panel 2-9-5, to Reset Gp 1/4 position.

BFN Reactor Protection System Manual 2-SR4.3.1.1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 15 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

[12] VERIFY the following on Panel 2-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 2-IL-99-5NAB illuminated.

System B Back-Up Scram Valve lights 2-IL-99-5NCD illuminated.

Reactor Scram B push-button extinguished.

Annunciator REACTOR CHANNEL B MAN SCRAM (2-XA-55-5B, window 9) reset.

[13] VERIFY the following computer points indicates NOTTRIP.

ICS point S0E033

ICS point S0E034 7.4 Completion and Notifications

[1] NOTIFY the Unit Operator that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

[2] COMPLETE Attachment 1, Surveillance Procedure Review Form up to Unit Supervisors review.

[3] NOTIFY the Unit Supervisor that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

BFN Reactor Protection System Manual 2-SR-3.3.1 .1 .8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 16 of 18 8.0 ILLUSTRATIONS/ATTACHMENTS Attachment 1: Surveillance Procedure Review Form Attachment 2: Control Room Components Affected By Surveillance Instruction Performance

BFN Reactor Protection System Manual 2-SR4.3.1 .1.8(11)

Unit 2 Scram Functional Test Rev. 0004 Page 17 of 18 Attachment I (Page 1 of I)

Surveillance Procedure Review Form REASON FOR TEST: DATEITIME STARTED I] Scheduled Surveillance DATE/TIME COMPLETED D System Inoperable (Explain in Remarks) PLANT CONDITIONS D Maintenance (WO No.

D Other (Explain in Remarks)

REMARKS:

PRE-TEST PERFORMED BY:

Initials Name (Print) Name (Signature)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? ID Yes ID No Acceptance Criteria Satisfied? ID Yes C No If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO C Yes C No UNIT SUPERVISOR Date______________

INDEPENDENT REVIEWER (OPS)______________________ Date______________

SCHEDULING COORDINATOR Date_____________

POST-TEST REMARKS:___________________________________________

The SR Key number is a Cross Reference only and is not part of the procedure. Key # 2081 I

BFN Reactor Protection System Manual 2-SR-3.3.1 .1.8(11)

UnIt 2 Scram Functional Test Rev. 0004 Page 18 of 18 Attachment 2 (Page 1 ofl)

Control Room Components Affected by Surveillance Procedure Performance UNID DESCRIPTION LOCATION 2-XA-55-5B Annunciator REACTOR CHANNEL A MAN SCRAM Panel 2-9-5 Window 8 2-XA-55-5B Annunciator REACTOR CHANNEL B MAN SCRAM Panel 2-9-5 Window 9 ICS point S0E033 ICS point S0E034 N/A INDICATING LIGHTS SCRAM SOLENOID Panel 2-9-5 GROUP A LOGIC RESET N/A BACK-UP SCRAM VALVE INDICATING LIGHTS Panel 2-9-5 The purpose of this sheet is to give the Unit Operator a log of the local alarms and indications in the main control room that will be affected by performance of this surveillance procedure.

This sheet is for operator information only and the copy of this sheet given to Unit Operator should be discarded upon notification that the instruction is complete.

C C

I C

JPM d OPERATOR:____________________

RO___ SRO___ DATE:

JPM NUMBER: d - Alternate Path TASK NUMBER: U-085-AL-12 TASK TITLE: RPS Channel Functional KJA NUMBER: 212000 A4.01 KJA RATING: RO 4.6 SRO: 4.6 TASK STANDARD: Perform RPS Channel Functional, successful test on RPS A, when RPS B tested two control rods will scram, requiring the operator to insert a manual scram lAW AOI-85-5 , Rod Drift In LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3 -SR-3 .3.1.1.8(11), 3-AOI-85-5 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

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

DATE:

EXAMINER 1

INITIAL CONDITIONS:

You are an Operator on Unit 3.

INITIATING CUE:

The Unit Supervisor has directed you to continue with the quarterly scheduled surveillance 3-SR-3 .3.1.1.8(11) Reactor Protection System Manual Scram Functional Test at step 7.2[1].

JPM d IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

You are an Operator on Unit 3.

INITIATING CUE:

The Unit Supervisor has directed you to continue with the quarterly scheduled surveillance 3 -SR-3 .3.1.1.8(11) Reactor Protection System Manual Scram Functional Test at step 7.2 [1].

3

JPM d START TIME____

Performance Step 1: Critical X Not Critical 7.2 RPS Manual Scram Channel A Functional Test

[1] MOMENTARILY DEPRESS Reactor Scram A push-button, Panel 3-9-5.

Standard:

Depresses Reactor Scram A push-button SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 2: Critical Not Critical X

[2] VERIFY the following on Panel 3-9-5:

Confrol Rod Logic Reset Solenoid Group A indicating lights (4) extinguished.

One System A Back-Up Scram Valve light 3-IL-99-5A/AB and System B Back-Up Scram Valve light 3-IL-99-5AJCD extinguished.

Reactor Scram A push-button illuminated.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) in alarm.

[3] VERIFY the following ICS points indicate TRIP:

S0E033

SOEl78 Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A _COMMENTS:____

4

JPM d Performance Step 3: Critical X Not Critical

[4] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

Standard:

Places Scram Reset switch to GP 1/4 position SAT_ UNSAT_ N/A COMMENTS:_____________________________

Performance Step 4: Critical Not Critical

[5] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights 1 and 4 illuminated, and lights 2 and 3 extinguished.

Both System A Backup Scram Valve lights 3-IL-99-5A/AB illuminated.

One System B Backup Scram Valve light 3-IL-99-5AICD illuminated, and one System B Backup Scram Valve light 3-IL-99-5A/CD extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

[6] VERIFY ICS point SOE178 indicates NOTTRIP.

Standard:

Verifies the conditions listed above are met SAT_ UNSAT_ N/A COMMENTS:____

5

JPM d Performance Step 5: Critical Not Critical

[7] MOMENTARILY DEPRESS Reactor Scram A push-button.

Standard:

Depresses Reactor Scram A push-button SAT_ UNSAT_ N/A COMMENTS:___________________________

Performance Step 6: Critical Not Critical X

[8] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights 1 and 4 extinguished.

One System A Backup Scram Valve light 3-IL-99-5AJAB extinguished.

[9] VERIFY the following ICS points indicate TRIP:

SOEO33

S0E178 Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A COMMENTS:___

6

JPM d Performance Step 7: Critical Not Critical

[10] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5 to Reset Gp 2/3 position.

Standard:

Places Scram Reset switch to GP 2/3 position SAT_ UNSAT_ N/A COMMENTS:____________________________

Performance Step 8: Critical Not Critical

[11] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights 2 and 3 illuminated, and lights 1 and 4 extinguished.

Both System B Backup Scram Valve lights 3-IL-99-5A/CD illuminated.

One System A Backup Scram Valve light 3-IL-99-5A/AB on System A Backup Scram Valve light illuminated, and one System A Backup Scram Valve light 3-IL-99-5AIAB extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-5 5-SB, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

[12] VERIFY ICS point S0E033 indicates NOTTRIP.

[13] VERIFY ICS point S0E178 indicates TRIP.

Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A _COMMENTS:_____________________________

7

JPM d Performance Step 9: Critical Not Critical

[14] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

Standard:

Places Scram Reset switch to GP 1/4 position SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 10: Critical Not Critical

[15] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 3-IL-99-5A/AB illuminated.

System B Back-Up Scram Valve lights 3-IL-99-5AJCD illuminated.

Reactor Scram A push-button extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) reset.

[16] VERIFY the following computer points indicates NOTTRIP.

ICS point 50E033

ICS point 5OE034

ICS point S0E178

ICS point S0E179 Standard:

Verifies the conditions listed above are met SAT_ UNSAT N/A COMMENTS:______________________________

8

JPM d Performance Step 11: Critical Not Critical 7.3 RPS Manual Scram Channel B Functional Test

[1] MOMENTARILY DEPRESS Reactor Manual Scram B push-button, Panel 3-9-5.

Standard:

Depresses Reactor Scram B push-button SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 12: Critical Not Critical Determines that multiple rods are drifting into the core Standard:

Determines that more than one control rod has scrammed or drifted into the core.

SAT_ UNSAT N/A COMMENTS:_______________________________

9

JPM d Performance Step 13: Critical Not Critical Rod Drift In 3-AOI-85-5 4.1 Immediate Actions

[1] IF multiple rods are drifting into core, THEN MANUALLY SCRAM Reactor. Refer to 3-AOl- 100-1.

DEPRESS REACTOR SCRAM A and B, 3-HS-99-5A/S3A and 3-HS--99-5A/S3B, on Panel 3-9-5.

Standard:

Inserts a Manual SCRAM SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 14: Critical Not Critical Reactor Scram 3-AOI-100-1

[4] PLACE REACTOR MODE SWITCH, 3-HS-99-5A-S1, in SHUTDOWN.

Standard:

Places Reactor Mode Switch in Shutdown SAT_ UNSAT N/A COMMENTS:________________

CUE: After Scram report another operator will continue in 3-AOI-100-1.

STOP TIME____

END OF TASK 10

(

Browns Ferry Nuclear Plant Unit 3 Surveillance Procedure 3-SR-3.3.1 .1.8(11)

Reactor Protection System Manual Scram Functional Test Revision 0005 Quality Related Level of Use: Continuous Use Effective Date: 09-22-2008 Responsible Organization: OPS, Operations Prepared By: Michael S. Rice © 6934 Approved By: John T. Kulisek

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 2 of 18 Current Revision Description Pages Affected: All Type of Change: XP Conversion & DCN Tracking Number 007 PCRs: 08000148 DCN: 51657 This procedure was converted from Word 95 to Word 2003 using Rev 4.

Minor editorial changes (no rev bars)

Deleted hand grenage icon from P&L section. This is no longer used in Operations Procedures.

Added computer points S0E178 and S0E179 to the procedure. These were added in DCN 51657. Placing the Reactor Scram Reset Switch to the Reset GP 114 position will reset the SOE1 78 and SOEI 79 computer points if tripped. Changes made ensure the computer poinsts operate as designed. See drawings 3-730E91 5-6 and 3-730E91 5RH-1 1, 12, & 18. (PCR 08000148)

Added SR key number to Attachment 1 for Scheduling.

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 3 of 18 Table of Contents

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4 1.3 Frequency 4 1.4 Applicability 4

2.0 REFERENCES

5 2.1 Technical Specifications 5 2.2 Final Safety Analysis Report 5 2.3 GE Drawings 5 3.0 PRECAUTIONS AND LIMITATIONS 6 4.0 PREREQUISITES 7 5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED 7

( ) 6.0 ACCEPTANCE CRITERIA 7 7.0 PROCEDURE STEPS 8 7.1 Initial Requirements and Notifications 8 7.2 RPS Manual Scram Channel A Functional Test 10 7.3 RPS Manual Scram Channel B Functional Test 13 7.4 Completion and Notifications 16 8.0 ILLUSTRATIONSIATTACHMENTS 16 Attachment 1: Surveillance Procedure Review Form 17 Attachment 2: Control Room Components Affected by Surveillance Procedure Performance 18

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(1 1)

Unit 3 Scram Functional Test Rev. 0005 Page 4 of 18

1.0 INTRODUCTION

1.1 Purpose This surveillance procedure performs a functional test of the manual scram push-buttons in conformance with the requirements specified in Technical Specification Table 3.3.1.1-1(Function 11). This procedure meets the requirements of SR 3.3.1.1.14. This procedure, also, partially satisfies the requirements of SR 3.10.3.1 and 3.10.4.1.

1.2 Scope This surveillance procedure completely satisfies the manual scram functional test requirements of Technical Specification 3.3.1.1.

This procedure provides overlap testing 3-SR-3.3.1 .1.12 by verifying Scram Solenoid Group A and B Logic Reset lights extinguish with the associated RPS channel trip. This partially satisfies SR 3.3.1.1.14, Logic System Functional Test.

1.3 Frequency Once every 92 days.

1.4 Applicability The SR requirements of this procedure are applicable in Modes I and 2. Mode 5 is also applicable with any control rod withdrawn from a core cell containing one or more fuel assemblies.

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 5 of 18

2.0 REFERENCES

2.1 Technical Specifications Section 3.3.1.1, 3.10.3 and 3.10.4 2.2 Final Safety Analysis Report Section 7.2, Reactor Protection System 2.3 GE Drawings 3-730E915-6, Elementary Diagram Reactor Protection System 3-730E915 Sh. 7, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 11, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 12, Elementary Diagram Reactor Protection System 3-730915-13, Elementary Diagram Reactor Protection System 3-730E915 Sh. 14, Elementary Diagram Reactor Protection System 3-730E91 5 Sh. 17, Elementary Diagram Reactor Protection System 3-730E915RF Sh. 18, Elementary Diagram Reactor Protection System

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 6 of 18 3.0 PRECAUTIONS AND LIMITATIONS A. If any control rod actually scrams during performance of this test, wait at least 10 seconds before resetting the scram to ensure that the scram has gone to completion.

B. Corrective Actions shall be handled in accordance with SPP-8.1, Conduct of Testing.

C. The following annunciators should alarm during the performance of this test:

REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8)

REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9)

D. The following Integrated Computer System (ICS) points should alarm during the performance of this test:

Point S0E033 Point S0E034 Point S0E178 Point S0E179 E. The Critical Step warning designates a step or series of steps for an activity which requires additional focus, attention, and increased awareness. The Operator performing these steps for the activity needs to ensure the Unit Supervisor and other Control Room staff are aware of the evolution. PEER checks are required for this activity and short briefs need to be made prior to performing the evolution. Included in the briefs are worst case scenario and contingencies.

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 7 of 18 Date 1bO 4.0 PREREQUISITES VERIFY this copy of 3-SR-3.3.1 .1.8(11) is the most current revision.

VERIFY no other tests or maintenance are in progress which could initiate any of the logic in the Reactor Protection System.

5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED None 6.0 ACCEPTANCE CRITERIA A. Responses which fail to meet the acceptance criteria stated in this section shall constitute unsatisfactory SR results and require immediate notification of the Unit Supervisor at the time of failure.

1. Control Rod Logic Reset Solenoid Group A indicating lights (4) on Panel 3-9-5 are extinguished when Reactor Scram A push-button on Panel 3-9-5 is depressed.

2. Control Rod Logic Reset Solenoid Group B indicating lights (4) on Panel 3-9-5 are extinguished when Reactor Scram B push-button on Panel 3-9-5 is depressed.

B. Steps which verify acceptance criteria are designated by (AC) next to the initial blanks.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 8 of 18 Date 7.0 PROCEDURE STEPS 7.1 Initial Requirements and Notifications VERIFY Precautions and Limitations in Section 3.0 have been reviewed.

VERIFY Prerequisites listed in Section 4.0 are satisfied.

VERIFY the following on Panel 3-9-5:

/ Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

/ Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated. 1W

/ System A Back-Up Scram Valve lights 3-IL-99-5NAB illuminated.

A System B Back-Up Scram Valve lights 3-IL-99-5A!CD illuminated.

/ Reactor Scram A push-button extinguished.

/ Reactor Scram B push-button extinguished.

/ Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) reset.

J Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) reset.

CHECK the following Unit 3 ICS points indicate NOTTRIP using the SOE status display on any available ICS workstation or ICS alarm printer:

S0E033

S0E034

S0E178

S0E179

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11)

Unit 3 Scram Functional Test Rev. 0005

Page9ofl8 Date I

7.1 InitIal Requirements and Notifications (continued)

OBTAiN permission from the Unit Supervisor to perform this test. [LER 259/89023]

US w [NRC/C] NOTIFY the Unit Operator (UO) before commencing this instruction. [LER 259/82032]

PERFORM the following:

DISCUSS with the UO the effects this procedure has on plant equipment/status.

INFORM UO that the Integrated Computer System (ICS) will be affected during performance of this procedure and that ICS alarms may be received. 1 GIVE copy of Attachment 2, Control Room Components Affected by Surveillance Procedure Performance, to the UO as a reminder that this channel is in test.

RECORD the start date, start time, reason for the test, plant conditions, and any pre-test remarks on Attachment 1, Surveillance Procedure Review Form.

BFN Reactor Protection System Manual 3-SR-3.3..1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 10 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test Start of Critical Step(s)

[1] MOMENTARILY DEPRESS Reactor Scram A push-button, Panel 3-9-5.

End of Critical Step(s)

[2] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A indicating lights (4) extinguished.

One System A Back-Up Scram Valve light 3-lL-99-5A/AB and System B Back-Up Scram Valve light 3-IL-99-5AICD extinguished.

Reactor Scram A push-button illuminated.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) in alarm.

[3] VERIFY the following ICS points indicate TRIP:

S0E033

S0E178

[4] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 114 position.

[5] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights I and 4 illuminated, and lights 2 and 3 extinguished.

Both System A Backup Scram Valve lights 3-IL-99-5NAB illuminated.

One System B Backup Scram Valve light 3-IL-99-5NCD illuminated, and one System B Backup Scram Valve light 3-IL-99-5AICD extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(1 1)

Unit 3 Scram Functional Test Rev. 0005 Page 11 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

[6] VERIFY ICS point S0E178 indicates NOTTRIP.

Start of Critical Step(s)

[7] MOMENTARILY DEPRESS Reactor Scram A push-button.

End of Critical Step(s)

[8] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights I and 4 extinguished.

One System A Backup Scram Valve light 3-IL-99-5AIAB extinguished.

[9) VERIFY the following ICS points indicate TRIP:

S0E033

S0E178

[10] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5 to Reset Gp 2/3 position.

[11] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A lights 2 and 3 illuminated, and lights I and 4 extinguished.

Both System B Backup Scram Valve lights 3-lL-99-5AICD illuminated.

One System A Backup Scram Valve light 3-IL-99-5AIAB on System A Backup Scram Valve light illuminated, and one System A Backup Scram Valve light 3-lL-99-5AIAB extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) will NOT reset.

Reactor Scram A push-button illuminated.

[12] VERIFY ICS point S0E033 indicates NOTTRIP.

[13] VERIFY ICS point S0E178 indicates TRIP.

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 12 of 18 Date 7.2 RPS Manual Scram Channel A Functional Test (continued)

[14] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

[15] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 3-IL-99-5AIAB illuminated.

System B Back-Up Scram Valve lights 3-IL-99-5A/CD illuminated.

Reactor Scram A push-button extinguished.

Annunciator REACTOR CHANNEL A MAN SCRAM (3-XA-55-5B, window 8) reset.

[16] VERIFY the following computer points indicates NOTTRIP.

ICS point S0E033

ICS point S0E034

ICS point S0E178

ICS point S0E179

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 13 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test Start of Critical Step(s)

[I] MOMENTARILY DEPRESS Reactor Manual Scram B push-button, Panel 3-9-5.

End of Critical Step(s)

[2] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group B indicating lights (4) extinguished.

One System B Backup Scram Valve light 3-lL-99-5A/CD and one System A Backup Scram Valve light 3-lL-99-5AIAB extinguished.

Reactor Scram B push-button illuminated.

Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) in alarm.

[3] VERIFY the following ICS points indicate TRIP:

S0E034

S0E179

[4] MOMENTARILY PLACE the Scram Reset switch, Panel 3-9-5 to Reset Gp 1/4 position.

[5] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group B lights 1 and 4 illuminated and lights 2 and 3 extinguished.

Both System B Backup Scram Valve lights 3-IL-99-5AICD illuminated.

One System A Backup Scram Valve light 3-IL-99-5NAB illuminated and one System A Backup Scram Valve light 3-lL-99-5NAB extinguished.

Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) will NOT reset.

Reactor Scram B push-button illuminated.

BFN Reactor Protection System Manual 3-SR-3.3.1.1.8(11)

UnIt 3 Scram Functional Test Rev. 0005 Page 14 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

[61 VERIFY (CS point S0E179 indicates NOTTRIP.

Start of Critical Step(s)

[7] MOMENTARILY DEPRESS Reactor Scram B push-button.

End of Critical Step(s)

[8] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group B lights I and 4 extinguished.

One System B Backup Scram Valve light 3-IL-99-5NCD extinguished.

[9] VERIFY the following ICS points indicate TRIP:

S0E034

S0E179

[101 MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 2/3 position.

[11] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group B lights 2 and 3 illuminated, and lights I and 4 extinguished.

Both System A Backup Scram Valve lights 3-IL-99-5AIAB illuminated.

One System B Backup Scram Valve light 3-lL-99-5AICD illuminated and one System B Backup Scram Valve light 3-lL-99-5AICD extinguished.

Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) will NOT reset.

Reactor Scram B push-button illuminated.

[12] VERIFY ICS point S0E034 indicates NOTTR1P.

[13] VERIFY ICS point S0E179 indicates TRIP.

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 15 of 18 Date 7.3 RPS Manual Scram Channel B Functional Test (continued)

[14] MOMENTARILY PLACE Scram Reset switch, Panel 3-9-5, to Reset Gp 1/4 position.

[15] VERIFY the following on Panel 3-9-5:

Control Rod Logic Reset Solenoid Group A red indicating lights (4) illuminated.

Control Rod Logic Reset Solenoid Group B red indicating lights (4) illuminated.

System A Back-Up Scram Valve lights 3-IL-99-5A/AB illuminated.

System B Back-Up Scram Valve lights 3-lL-99-5AICD illuminated.

Reactor Scram B push-button extinguished.

Annunciator REACTOR CHANNEL B MAN SCRAM (3-XA-55-5B, window 9) reset.

[16] VERIFY the following computer points indicates NOTTRIP.

ICS point S0E033

ICS point S0E034

ICS point S0E178

ICS point S0E179

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 16 of 18 Date 7.4 Completion and Notifications

[1] NOTIFY the Unit Operator that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

[2] COMPLETE Attachment 1, Surveillance Procedure Review Form up to Unit Supervisors review.

[3] NOTIFY the Unit Supervisor that this test is complete and PROVIDE status of any Corrective Actions or unsatisfactory test results.

8.0 ILLUSTRATIONSIATTACHMENTS Attachment 1: Surveillance Procedure Review Form Attachment 2: Control Room Components Affected By Surveillance Instruction Performance

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 17 of 18 Attachment I (Page 1 ofl)

Surveillance Procedure Review Form REASON FOR TEST: DATE/TIME STARTED C Scheduled Surveillance DATE/TIME COMPLETED C System Inoperable (Explain in Remarks) PLANT CONDITiONS C Maintenance (WO No.

C Other (Explain in Remarks)

PRE-TEST REMARKS:

PERFORMED BY:

Initials Name (Print) Name (Signature)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? C Yes C No Acceptance Criteria Satisfied? C Yes C No If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO C Yes C No UNIT SUPERVISOR Date_____________

INDEPENDENT REVIEWER (OPS)______________________ Date______________

SCHEDULING COORDINATOR Date_____________

POST-TEST REMARKS:_____________________________________________

The SR Key number is a Cross Reference only and is not part of the procedure. Key # 3081

BFN Reactor Protection System Manual 3-SR-3.3.1 .1.8(11)

Unit 3 Scram Functional Test Rev. 0005 Page 18 of 18 Attachment 2 (Page 1 of 1)

Control Room Components Affected by Surveillance Procedure Performance UNID DESCRIPTION LOCATION 3-XA-55-5B Annunciator REACTOR CHANNEL A MAN SCRAM Panel 3-9-5 Window 8 3-XA-55-5B Annunciator REACTOR CHANNEL B MAN SCRAM Panel 3-9-5 Window 9 ICS point S0E033 ICS point S0E034 N/A INDICATING LIGHTS SCRAM SOLENOID Panel 3-9-5 GROUP A LOGIC RESET N/A BACK-UP SCRAM VALVE INDICATING LIGHTS Panel 3-9-5 The purpose of this sheet is to give the Unit Operator a log of the local alarms and indications in the main control room that will be affected by performance of this surveillance procedure.

This sheet is for operator information only and the photocopy of this sheet given to Unit Operator should be discarded upon notification that the instruction is complete.

JPM e OPERATOR:

RO SRO DATE:

JPM NUMBER: e TASK NUMBER: U-000-NO-12 TASK TITLE: Placing Primary Containment ventilation in service KJA NUMBER: 223001 A4.03 KJA RATING: RO 3.4 SRO 3.4 SAFETY FUNCTION: 5 PRA: NA TASK STANDARD: Perform control room operations required to place primary containment ventilation in service LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-01-64 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

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

DATE:

EXAMINER Jk 1

JPM e INITIAL CONDITIONS:

You are an Operator.

Primary Containment has been opened for unrestricted access

Drywell Personnel and Equipment Hatches are NOT open

Drywell Temperature as indicated on 2-TR-80-1 is 100 °F INITIATING CUES:

The Unit Supervisor directs you to place primary containment ventilation in service to the Suppression Chamber and the Drywell as directed by 2-01 64.

2

JPM e 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.

Primary Containment has been opened for unrestricted access

Drywell Personnel and Equipment Hatches are NOT open

Drywell Temperature as indicated on 2-TR-80-1 is 100 °F INITIATING CUES:

The Unit Supervisor directs you to place primary containment ventilation in service to the Suppression Chamber and the Drywell as directed by 2-01 64.

3

JPM e START TIME:

Performance Step 1: Critical Not Critical 8.5 Placing Primary Containment Ventilation in Service

[1] REVIEW all Precautions and Limitations in Section 3.0.

[2] The following initial conditions are satisfied:

The Primary Containment has been opened for unrestricted access.

Reactor Zone Fans are in fast speed. REFER TO 2-OI-30B.

Standard:

Primary containment open for unrestricted access is given in initial conditions, verifies Reactor Zone Fans in fast SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 2: Critical Not Critical X

[3] IF Drywell Personnel and Equipment Access Hatches are open, THEN PERFORM the following:

Standard:

Hatches are NOT open, given in initial conditions SAT_ UNSAT N/A COMMENTS:________

4

JPM e Performance Step 3: Critical Not Critical

[4] IF the Drywell Personnel and/or Equipment Access Hatches are NOT open, OR it is desired to ventilate the Suppression Chamber, THEN PERFORM the following:

[4.1] IF ventilating the Drywell, THEN START a sufficient number of Drywell Coolers, to assist the Primary Containment Purge Filter Fan in maintaining Drywell temperature less than 110°F as indicated on DRYWELL TEMPERATURES, 2-TR-80-1 (Panel 2-9-47). REFER TO Section 5.2.

Standard:

Given in initial conditions, in addition Drywell temperature indication on ICS and Panel 9-3 indicate Drywell temperature less than 110 °F SAT UNSAT_ N/A COMMENTS:_______________________________

Performance Step 4: Critical Not Critical

[4.2] VERIFY CLOSED the following valves (Panel 2-9-3):

DRYWELL INBD ISOLATION VLV, 2-FCV-64-31

SUPPR CHBR INBD ISOLATION VLV, 2-FCV-64-34 Standard:

Verifies closed 2-FCV-64-3 1 and 2-FCV-64-34 SAT_ UNSAT N/A COMMENTS:_________________

5

JPM e Performance Step 5: Critical X Not Critical

[4.3J On Panel 2-9-3, VERIFY OPEN the appropriate valves. To ventilate the Drywell only, USE 8.5[4.3]A, 8.5[4.3]B, 8.5[4.3]E, and 8.5[4.31F; to ventilate the Suppression Chamber only, USE 8.5[4.3]C, 8.5[4.3]D, and 8.5[4.3]G; and to ventilate both simultaneously, use all of the following:

A. DRYWELL VENT 1ISIBD ISOL VALVE, 2-FCV-64-29 Standard:

OPENs 2-FCV-64-29 SAT_ UNSAT_ N/A _COMMENTS:______________________________

Performance Step 6: Critical X Not Critical B. DRYWELL VENT OUTBD ISOLATION VLV, 2-FCV-64-30 Standard:

OPENs 2-FCV-64-30 SAT_ UISTSAT N/A COMMENTS:___________________________

Performance Step 7: Critical X Not Critical C. SUPPR CHBR VENT INBD ISOL VALVE, 2-FCV-64-32 Standard:

OPENs 2-FCV-64-32 SAT_ UNSAT N/A COMMENTS:____

6

JPM e Performance Step 8: Critical X Not Critical D. SUPPR CHBR VENT OUTBD ISOLATION VLV, 2-FCV-64-33 Standard:

OPENs 2-FCV-64-33 SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 9: Critical X Not Critical E. DW/SUPPR CHBR AIR PURGE ISOL VLV, 2-FCV-64-17 Standard:

OPENs 2-FCV-64-17 SAT_ UNSAT_ N/A COMMENTS:________________________________

Performance Step 10: Critical X Not Critical F. DRYWELL ATM SUPPLY INBD ISOLATION VLV, 2-FCV-64-18 Standard:

OPENs 2-FCV 18 SAT_ UNSAT N/A COMMENTS:____

7

JPM e Performance Step 11: Critical Not Critical G. SUPPR CHBR ATM SPLY INBD ISOLATION VLV, 2-FCV-64-19 Standard:

OPENs 2-FCV-64-19 SAT_ UNSAT N/A _COMMENTS:_______________________________

Performance Step 12: Critical Not Critical

[4.41 START CTMT PURGE FILTER FAN, using 2-HS-64-131 (RB, Primary Containment Purge Unit, El 621).

Standard:

Contacts Operator to start Containment Purge Filter Fan SAT_ UNSAT_ N/A COMMENTS:________________________________

DRIVER: When called start Containment Purge Fan irf pcO6 start Performance Step 13: Critical Not Critical X CAUTION Maintain purge air flow LESS THAN 6600 SCFM. Purge air flow is indicated on 2-FI 132 (Reactor Building, El 621), 2-FI-64-37 (2-9-25), and 2-FI-76-25 (2-9-3) [PER 223760].

[4.5] CHECK purge flow less than 6,600 SCFM, as indicated on CTMT PURGE FLT OUTL FLOW, 2-FI-64-37 on Panel 2-9-25.

Standard:

Verifies containment purge filter fan outlet flow less than 6600 scfm SAT_ UNSAT N/A COMMENTS:____________________

8

JPM e Performance Step 14: Critical Not Critical NOTE Primary Containment Purge Filter DP can be obtained by adding DPs obtained from HEPA FILTER PRESS DIFF ND, 2-PDI-64-125, and Charcoal Filter DP from CHARCOAL FILTER PRESS DIFF ND, 2-PDI-64-126.

[4.6] CHECK Primary Containment Purge Filter DP less than 6 inches water (locally).

[4.7] MONITOR Primary Containment Purge Filter periodically for any rise in DP.

[4.8] WHEN Primary Containment Purge Filter Fan is no longer needed for ventilation, THEN Standard:

Contacts operator to check primary containment purge filter DP less than 6 inches of water and to monitor periodically SAT_ UNSAT N/A COMMENTS:________

END OF TASK STOP TIME:

9

C I

C

JPM e OPERATOR:

RO SRO DATE:

JPM NUMBER: e TASK NUMBER: U-000-NO-12 TASK TITLE: Placing Primary Containment ventilation in service KJA NUMBER: 223001 A4.03 KJA RATING: RO 3.4 SRO 3.4 SAFETY FUNCTION: 5 PRA: NA TASK STANDARD: Perform control room operations required to place primary containment ventilation in service LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-01-64 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY UNSATISFACTORY SIGNATUR E:

DATE:

EXAMINER 1

JPM e INITIAL CONDITIONS:

You are an Operator.

Primary Containment has been opened for unrestricted access

Drywell Personnel and Equipment Hatches are NOT open

Drywell Temperature as indicated on 3-TR-80-l is 97 °F INITIATING CUES:

The Unit Supervisor directs you to place primary containment ventilation in service to the Suppression Chamber and the Drywell as directed by 3-01 64.

2

JPM e 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.

Primary Containment has been opened for unrestricted access

Drywell Personnel and Equipment Hatches are NOT open

Drywell Temperature as indicated on 3-TR-80-1 is 97 °F INITIATING CUES:

The Unit Supervisor directs you to place primary containment ventilation in service to the Suppression Chamber and the Drywell as directed by 3-01 64.

3

JPM e START TIME:

Performance Step 1: Critical Not Critical 8.5 Placing Primary Containment Ventilation in Service

[1] REVIEW all Precautions and Limitations in Section 3.0.

[2] The following initial conditions are satisfied:

The Primary Containment has been opened for unrestricted access.

Reactor Zone Fans are in fast speed. REFER TO 3-OI-30B.

Standard:

Primary containment open for unrestricted access is given in initial conditions, verifies Reactor Zone Fans in fast SAT_ UNSAT_ N/A _COMMENTS:_______________________________

Performance Step 2: Critical Not Critical

[3] IF Drywell Personnel and Equipment Access Hatches are open, THEN PERFORM the following:

Standard:

Hatches are NOT open, given in initial conditions SAT_ UNSAT_ N/A _COMMENTS:________

4

JPM e Performance Step 3: Critical Not Critical

[4] IF the Drywell Personnel and/or Equipment Access Hatches are NOT open, OR it is desired to ventilate the Suppression Chamber, THEN PERFORM the following:

[4.11 IF ventilating the Drywell, THEN START a sufficient number of Drywell Coolers, to assist the Primary Containment Purge Filter Fan in maintaining Drywell temperature less than 110°F as indicated on DRYWELL TEMPERATURES, 3-TR-80-1 (Panel 3-9-47). REFER TO Section 5.2.

Standard:

Given in initial conditions, in addition Drywell temperature indication on ICS and Panel 9-3 indicate Drywell temperature less than 110 °F SAT_ UNSAT N/A _COMMENTS:________________________________

Performance Step 4: Critical Not Critical X

[4.2] VERIFY CLOSED the following valves (Panel 3-9-3):

DRYWELL INBD ISOLATION VLV, 3-FCV-64-31

SUPPR CHBR 1NBD ISOLATION VLV, 3-FCV-64-34 Standard:

Verifies closed 3-FCV-64-3 1 and 3-FCV-64-34 SAT_ UNSAT N/A COMMENTS:_______

5

JPM e Performance Step 5: Critical Not Critical

[4.3] On Panel 3-9-3, VERIFY OPEN the appropriate valves. To ventilate the Drywell only, USE 8.5[4.3]A, 8.5[4.3]B, 8.5[4.3]E, and 8.5[4.3]F; to ventilate the Suppression Chamber only, USE 8.5[4.3]C, 8.5[4.3]D, Section 5.2, and 8.5 [4.3 ]G; and to ventilate both simultaneously, use all of the following:

A. DRYWELL VENT INBD ISOL VALVE, 3-FCV-64-29 Standard:

OPENs 3-FCV-64-29 SAT UNSAT N/A COMMENTS:______________________________

Performance Step 6: Critical Not Critical B. DRYWELL VENT OUTBD ISOLATION VLV, 3-FCV-64-30 Standard:

OPENs 3-FCV-64-30 SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 7: Critical Not Critical C. SUPPR CHBR VENT 1NBD ISOL VALVE, 3-FCV-64-32 Standard:

OPENs 3-FCV-64-32 SAT_ UNSAT N/A COMMENTS:____

6

JPM e Performance Step 8: Critical Not Critical D. SUPPR CHBR VENT OUTBD ISOLATION VLV, 3-FCV-64-33 Standard:

OPENs 3-FCV-64-33 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 9: Critical Not Critical E. DW/SUPPR CHBR AIR PURGE ISOL VLV, 3-FCV-64-17 Standard:

OPENs 3-FCV-64-17 SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 10: Critical X Not Critical F. DRYWELL ATM SUPPLY INBD ISOLATION VLV, 3-FCV-64-18 Standard:

OPENs 3-FCV-64-18 SAT_ UNSAT N/A COMMENTS:____

7

JPM e Performance Step 11: Critical Not Critical G. SUPPR CHBR ATM SPLY 1NBD ISOLATION VLV, 3-FCV-64-19 Standard:

OPENs 3-FCV-64-19 SAT_ UNSAT N/A COMMENTS:________________________________

Performance Step 12: Critical X Not Critical

[4.4] START CTMT PURGE FILTER FAN, using 3-HS-64-131 (RB, Primary Containment Purge Unit, El 621).

Standard:

Contacts Operator to start Containment Purge Filter Fan SAT_ UNSAT N/A COMMENTS:_______________________________

DRIVER: When called start Containment Purge Fan irf pcO6 start Performance Step 13: Critical Not Critical X CAUTION Maintain purge air flow LESS THAN 6600 SCFM. Purge air flow is indicated on 3-FI 132 (Reactor Building, El 621), 3-FI-64-37 (3-9-25), and 3-FI-76-25 (3-9-3) [PER 223760].

[4.5] CHECK purge flow less than 6,600 SCFM, as indicated on CTMT PURGE FLT OUTL FLOW, 3-FI-64-37 on Panel 3-9-25.

Standard:

Verifies containment purge filter fan outlet flow less than 6600 scfm SAT_ UNSAT N/A COMMENTS:__________________

8

JPM e Performance Step 14: Critical Not Critical X NOTE Primary Containment Purge Filter DP can be obtained by adding DPs obtained from HEPA FILTER PRESS DIFF IND, 3-PDI-64-125, and Charcoal Filter DP from CHARCOAL FILTER PRESS DIFF IND, 3-PDI-64-126.

[4.6] CHECK Primary Containment Purge Filter DP less than 6 inches water (locally).

[4.7] MONITOR Primary Containment Purge Filter periodically for any rise in DP.

[4.8] WHEN Primary Containment Purge Filter Fan is no longer needed for ventilation, THEN Standard:

Contacts operator to check primary containment purge filter DP less than 6 inches of water and to monitor periodically SAT_ UNSAT N/A COMMENTS:________

END OF TASK STOP TIME:

9

JPM f OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: f Alternate Path TASK NUMBER: U-047-AL-18 TASK TITLE: Trip the Turbine, Generator PCB Failure to Open K/A NUMBER: 262001 A2.01 K/A RATING: RO 3.4 SRO 3.6 TASK STANDARD: Operator trips the Main Turbine and when the Generator PCB fails to open the operator takes actions to open the Generator PCB lAW 2-AOl- 100-1.

LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 2-AOl- 100-1 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATh:

EXAMINER 1

\\JLJ

INITIAL CONDITIONS:

You are an Operator. The Unit 2 reactor has scrammed.

INITIATING CUE:

The Unit Supervisor has directed you to trip the Main Turbine in accordance with step 4.2[9] of 2-AOl- 100-1, Reactor Scram.

1PM f 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 scranirned.

INITIATING CUE:

The Unit Supervisor has directed you to trip the Main Turbine in accordance with step 4.2[9] of 2-AOI-lOO-l, Reactor Scram.

3

JPM f START TIME____

Performance Step 1: Critical Not Critical NOTE To OPEN PCB 234 with the control room handswitch, ONE of the following is required:

2-XA-55-8A window 7, GEN REVERSE PWR FIRST RELAY OPERATION 2-EA-57-136, WITH GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A placed in TRIP.

OR GENERATOR PCB 224 CNTR WIREV BYPASS, 2-HS-242-224A placed in BYPASS.

[9] iivc] At 50 MWe, or as directed by the Unit Supervisor, VERIFY TRIPPED the Main Turbine as follows:

[9.1] DEPRESS the TRIP pushbutton, 2-HS-47-67D on Panel 2-9-7. [NER/CI [INPO SUER 81-015]

Standard:

Depresses the TRIP pushbutton and trips the Main Turbine SAT_ UNSAT N/A COMMENTS:____________

4

JPM f Performance Step 2: Critical Not Critical

[9.2] PERFORM the following as required to VERIFY OPEN GENERATOR PCB 224:

[9.2.1] CHECK green light illuminated and red light not illuminated above handswitch GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A.

Standard:

Checks for Green light on and Red light off, determines that indications are NOT correct and proceeds to step 9.2.2 SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 3: Critical Not Critical X

[9.2.2] IF Generator Breaker is CLOSED OR to RESET white disagreement light at GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A, THEN A. CONFIRM ANN 2-XA-55-8A window 7, GEN REVERSE PWR FIRST RELAY OPERATION 2-EA-57-136 is received, Standard:

Confirms 2-XA-55-8A window 7 is in alarm SAT_ UNSAT N/A COMMENTS:____

5

JPM f Performance Step 4: Critical Not Critical B. PLACE GENERATOR PCB 224 CNTR WIREV BYPASS, 2-HS-242-224A, in TRIP and release.

Standard:

Places 2-HS-242-224A in TRIP SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 5: Critical Not Critical C. VERIFY the following at GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A:

GREEN open target at 2-HS-242-224A

GREEN open light illuminated

RED closed light extinguished Standard:

Verifies Green open target, determines that indications are NOT correct the operator has a RED light ON and a GREEN light OFF. Operator proceeds to step 9.2.3 SAT_ UNSAT N/A COMMENTS:____________________________

6

JPM f Performance Step 6: Critical X Not Critical

[9.2.3] IF Generator Breaker remains CLOSED following step 4.2[9.2.2], THEN A. PLACE GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A, in BYPASS and release (will feel additional resistance at handswitch as it passes through TRIP to BYPASS position).

Standard:

Places 2-HS-242-224A in Bypass and releases SAT_ UNSAT N/A COMMENTS:__________________________

Performance Step 7: Critical Not Critical X B. VERIFY the following at GENERATOR PCB 224 CNTR W/REV BYPASS, 2-HS-242-224A:

GREEN open target at 2-HS-242-224A

GREEN open light illuminated

RED closed light extinguished Standard:

Verifies Green open target, Green light on and Red light off SAT_ UNSAT N/A COMMENTS:____________

7

JPM f Performance Step 8: Critical X Not Critical

[9.3] IMMEDIATELY PLACE VOLTAGE REGULATOR START/STOP SEL, 2-HS-57-24, to STOP and release.

Standard:

Places 2-HS-57-24 to STOP SAT_ UNSAT N/A _COMMENTS:_______________________________

Performance Step 9: Critical Not Critical

[9.4] CHECK the following at 2-HS-57-24:

GREEN light illuminated

RED light extinguished Standard:

Checks Green light on and Red light off SAT_ UNSAT N/A COMMENTS:______

STOP TIME____

END OF TASK 8

fl C JPM f OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: f- Alternate Path TASK NUMBER: U-047-AL-18 TASK TITLE: Trip the Turbine, Generator PCB Failure to Open K/A NUMBER: 262001 A2.01 K/A RATING: RO 3.4 SRO 3.6 TASK STANDARD: Operator trips the Main Turbine and when the Generator PCB fails to open the operator takes actions to open the Generator PCB JAW 3-AOI-100-1.

LOCATION OF PERFORMANCE: Simulator PRA: NA REFERENCES/PROCEDURES NEEDED: 3-AOl- 100-1 VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:__________________ DATh:

EXAMINER 1

INITIAL CONDITIONS:

You are an Operator. The Unit 3 reactor has scrammed.

iNITIATING CUE:

The Unit Supervisor has directed you to trip the Main Turbine in accordance with step 4.2[9] of 3-AOI-100-1, Reactor Scram.

JPM f 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.

INITL4L CONDITIONS:

You are an Operator. The Unit 3 reactor has scrammed.

ITNITIATING CUE:

The Unit Supervisor has directed you to trip the Main Turbine in accordance with step 4.2[9} of 3-AOI-lOO-l, Reactor Scram.

3

JPM f START TIME____

Performance Step 1: Critical X Not Critical NOTE To OPEN PCB 234 with the control room handswitch, ONE of the following is required:

3-XA-55-8A window 7, GEN REVERSE PWR FIRST RELAY OPERATION 3-EA-57-136, WITH GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A placed in TRIP.

OR GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A placed in BYPASS.

[9] [NER/CI At 50 MWe, or as directed by the Unit Supervisor, VERIFY TRIPPED the Main Turbine as follows:

[9.1] DEPRESS the TRIP pushbutton, 3-HS-47-67D on Panel 3-9-7. [NERJCI [INPO SOER 81-015]

Standard:

Depresses the TRIP pushbutton and trips the Main Turbine SAT_ UNSAT N/A COMMENTS:___________

4

JPM f Performance Step 2: Critical X Not Critical

[9.2] PERFORM the following as required to VERIFY OPEN GENERATOR PCB 234:

[9.2.11 CHECK green light illuminated and red light not illuminated above handswitch GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A.

Standard:

Checks for Green light on and Red light off, determines that indications are NOT correct and proceeds to step 9.2.2 SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 3: Critical Not Critical X

[9.2.2] IF Generator Breaker is CLOSED OR to RESET white disagreement light at GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A, THEN A. CONFIRM ANN 3-XA-55-8A window 7, GEN REVERSE PWR FIRST RELAY OPERATION 3-EA-57-136 is received, Standard:

Confirms 3-XA-55-8A window 7 is in alarm SAT_ UNSAT N/A COMMENTS:____

5

JPM f Performance Step 4: Critical X Not Critical B. PLACE GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A, in TRIP and release.

Standard:

Places 3-HS-242-234A in TRIP SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 5: Critical Not Critical C. VERIFY the following at GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A:

GREEN open target at 2-HS-242-224A

GREEN open light illuminated

RED closed light extinguished Standard:

Verifies Green open target, determines that indications are NOT correct the operator has a RED light ON and a GREEN light OFF. Operator proceeds to step 9.2.3 SAT_ UNSAT N/A COMMENTS:____________________________

6

JPM f Performance Step 6: Critical Not Critical

[9.2.3] IF Generator Breaker remains CLOSED following step 4.2[9.2.2], THEN A. PLACE GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A, in BYPASS and release (will feel additional resistance at handswitch as it passes through TRIP to BYPASS position).

Standard:

Places 3-HS-242-234A in Bypass and releases SAT_ UNSAT N/A COMMENTS:__________________________

Performance Step 7: Critical Not Critical B. VERIFY the following at GENERATOR PCB 234 CNTR W/REV BYPASS, 3-HS-242-234A:

GREEN open target at 3-HS-242-234A

GREEN open light illuminated

RED closed light extinguished Standard:

Verifies Green open target, Green light on and Red light off SAT_ UNSAT N/A COMMENTS:____________

7

JPM f Performance Step 8: Critical Not Critical

[9.3] IMMEDIATELY PLACE VOLTAGE REGULATOR START/STOP SEL, 3-HS-57-24, to STOP and release.

Standard:

Places 3-HS-57-24 to STOP SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 9: Critical Not Critical X

[9.4] CHECK the following at 3-HS-57-24:

GREEN light illuminated

RED light extinguished Standard:

Checks Green light on and Red light off SAT_ UNSAT N/A COMMENTS:______

STOP TIME____

ENI OF TASK 8

JPM g OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: g - Alternate Path TASK NUMBER: U-000-EM-74 TASK TITLE: Crosstie CAD to Drywell Control Air K/A NUMBER: 218000 A2.03 K/A RATING: RO 3.4 SRO 3.6 TASK STANDARD: Align Containment Air Dilution systems A and B to the Drywell Air System and then isolate CAD System A.

LOCATION OF PERFORMANCE: Simulator PRA: Transients %2LOPA 7.25E-1 1 0.00% Loss of Plant Air (U2)

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-8G VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMJ1SER 1

cD

\

INITIAL CONDITIONS:

You are an Operator. The Unit 2 reactor has scrammed. EOI-1 has been followed to RC/P-8.

INITIATING CUE:

The Unit Supervisor has directed you to perform 2-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g 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. EOI-l has been followed to RCIP-8.

INITIATING CUE:

The Unit Supervisor has directed you to perform 2-1301 Appendix-8G, Crosstie CAD to Drywell Control Air.

3

JPM g START TIME____

Performance Step 1: Critical X Not Critical

1. OPEN the following valves:

0-FCV-84-5, CAD SYSTEM AN2 SHUTOFF VALVE (Unit 1, Panel 9-54)

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 1, Panel 9-55)

Standard:

Opens 0-FCV-84-5 and 16 SAT_ UNSAT N/A COMMENTS:________________________

Performance Step 2: Critical Not Critical

2. VERIFY 0-PI-84-6, N2 VAPORIZER A OUTLET PRESSURE, and 0-PI-84-17, N2 VAPORIZER B OUTLET PRESSURE, indicate approximately 100 psig (Unit 1, Panel 9-54 and 9-55)

Standard:

Verified 0-PI-84-6 and 0-PI-84-l7 (Located on back of Unit 2 Panel 9-54 on simulator) indicating approximately 100 psig.

SAT_ IJNSAT N/A COMMENTS:___

4

JPM g Performance Step 3: *Ciiticaj Not Critical

3* PLACE keylock switch 2-HS-84-48, CAD A CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-54)

4. CHECK OPEN 2-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR, (Unit 2, Panel 9-54)

Standard:

Opens 2-FSV-84-48 SAT_ UNSAT_ N/A COMMENTS:_____________________________

Critical Not Critical Performance Step 4:

5 PLACE keylock switch 2-HS-84-49, CAD B CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-55)

6. CHECK OPEN 2-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-55)

Standard:

Opens 2-FSV-84-49 SAT_ UNSAT N/A COMMENTS:___

5

JPM g Performance Step 5: Critical X Not Critical

7. CHECK MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 2-PA-32-31, alarm cleared (2-XA-55-3D, Window 18)

Standard:

Recognizes MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW (2-XA-55-3D, Window 18) still in Alarm (would Not clear) and continues with procedure.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 6: Critical Not Critical X

8. IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 2-PA-32-31, annunciator is or remains in alarm (2-XA-5 5-3D, Window 18), THEN DETERMINE which Drywell Control Air header is depressurized as follows:

a. DISPATCH personnel to Unit 2, RB, El 565 ft, to MONITOR the following indications for low pressure:

2-PI-84-51, CAD N2 PRESSURE TO DWCA indicator, for CAD A (R-1O S-line, by Drywell Access Door)

2-PI-84-50, DW CONT AIR N2 SUPPLY PRESS indicator, for CAD B (R-12 U-line, behind 480V RB Vent Board 2B)

Standard:

Dispatches personnel to Reactor Building to monitor 2-PI-84-5 1 and 2-PI-84-50 for low pressure.

SAT_ UNSAT N/A COMMENTS:____________________________

CUE: ONLY report if directed by NRC 2-PI-84-51, CAD N 2 Pressure to DWCA indicator, for CAD A is reading 5 psig. 2-PI-84-50 reading normal.

6

JPM g Performance Step 7: Critical X Not Critical

b. MONITOR O-FI-84-7(18), CAD LiNE A(B) N2 FLOW, on Unit 1, Panel 1-9-54(55) for high flow.

Standard:

Recognizes O-FI-84-7 flow Higher than O-FI-84-18 flow SAT_ UNSAT N/A COMMENTS:_______________________________

NOTE CAD System A to Drywell Control Air supplies the following MSIVs:

2-FCV-1-14, MSIV LINE A INBOARD

2-FCV-l-26, MSIV LINE B INBOARD NOTE CAD System B to Drywell Control Air supplies the following MSIVs:

2-FCV-1-37, MSIV LINE C INBOARD

2-FCV-l-51, MSIV LINE D INBOARD Performance Step 8: Critical X Not Critical

c. MONITOR inboard MSIV indication status for valves drifting closed.

Standard:

Recognizes 2-FCV-1-14 and 26 closed SAT_ UNSAT N/A COMMENTS:___

7

JPM g Performance Step 9: Critical Not Critical

9. IF Drywell Control Air header supplied from CAD System A shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 1, Panel 9-54)

2-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-54)

Standard:

Closes 0-FCV-84-5 and 0-FSV-84-48 SAT_ TJNSAT N/A COMMENTS:______________________________

Performance Step 10: Critical Not Critical X

10. IF Drywell Control Air header supplied from CAD B shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 1, Panel 9-55)

2-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 2, Panel 9-55)

Standard:

N/A No indications of being depressurized SAT_ UNSAT N/A COMMENTS:______

STOP TIME____

END OF TASK 8

C JPM g OPERATOR:

RO___ SRO___ DATE:________

JPM NUMBER: g - Alternate Path TASK NUMBER: U-000-EM-74 TASK TITLE: Crosstie CAD to Drywell Control Air K/A NUMBER: 218000 A2.03 K/A RATING: RO 3.4 SRO 3.6 TASK STANDARD: Align Containment Air Dilution systems A and B to the Drywell Air System and then isolate CAD System A.

LOCATION OF PERFORMANCE: Simulator PRA: Transient %3LOPA 5.62E-l 1 0.00% Loss of Plant Air (U3)

REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-8G VALIDATION TIME: 10 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:_______

EXAMINER 1

IMTIAL CONDITIONS:

You are an Operator. The Unit 3 reactor has scrammed. EOI-1 has been followed to RC/P-8.

INITIATING CUE:

The Unit Supervisor has directed you to perform 3-EOI Appendix-8G, Crosstie CAD to Drywell Control Air.

JPM g 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. EOI-l has been followed to RC/P-8.

1NITIATING CUE:

The Unit Supervisor has directed you to perform 3-WI Appendix-8G, Crosstie CAD to Drywell Control Air.

3

JPM g START TIME____

Performance Step 1: Critical Not Critical

1. OPEN the following valves:

O-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 3, Panel 3-9-54)

O-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 3, Panel 3-9-55)

Standard:

Opens O-FCV-84-5 and 16 SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 2: Critical Not Critical

2. VERIFY O-PI-84-6/3, VAPOR A OUTLET PRESSURE, and O-PI-84-17/3, VAPOR B OUTLET PRESSURE, indicate approximately 100 psig (Unit 3, Panel 3-9-54 and 3-9-55)

Standard:

Verified 0-PI-84-6 and 0-PI-84-17 indicating approximately 100 psig.

SAT_ UNSAT_ N/A COMMENTS:__________________

4

JPM g Performance Step 3: *Crffical Not Critical

3* PLACE keylock switch 3-HS-84-48, CAD A CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 3, Panel 3-9-54)

4. CHECK OPEN 3-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR, (Unit 3, Panel 3-9-54)

Standard:

Opens 3-FSV-84-48 SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 4: *Critical Not Critical

5* PLACE keylock switch 3-HS-84-49, CAD B CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 3, Panel 3-9-55)

6. CHECK OPEN 3-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3-9-55)

Standard:

Opens 3-FSV-84-49 SAT_ UNSAT N/A COMMENTS:____

5

JPM g Performance Step 5: Critical Not Critical

7. CHECK MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 3-PA-32-31, alarm cleared (3-XA-55-3D, Window 18)

Standard:

Recognizes MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW (3-XA-55-3D, Window 18) still in Alarm (would Not clear) and continues with procedure.

SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 6: Critical Not Critical

8. IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 3-PA-32-31, annunciator is or remains in alarm (3-XA-5 5-3D, Window 18), THEN DETERMINE which Drywell Control Air header is depressurized as follows:

a. DISPATCH personnel to Unit 3, RB, El 565 ft, to MONITOR the following indications for low pressure:

3 -P1-84-Si, CAD N2 PRESSURE TO DWCA indicator, for CAD A (R- 17 S-line, by Drywell Access Door)

3-PI-84-50, DW CONT AIR N2 SUPPLY PRESS indicator, for CAD B (R-19 U-line, behind 480V RB Vent Board 3B)

Standard:

Dispatches personnel to Reactor Building to monitor 3-PI-84-51 and 3-PI-84-50 for low pressure.

SAT_ UNSAT N/A COMMENTS:________________________________

CUE: ONLY report if directed by NRC 3-Pl-84-51, CAD N 2 Pressure to DWCA indicator, for CAD A is reading 5 psig. 3-Pl-84-50 reading normal.

6

JPM g Performance Step 7: Critical Not Critical

b. MONITOR O-FI-84-7/3(1 8/3), CAD LiNE A(B) N2 FLOW, on Panel 3-9-54(55) for high flow.

Standard:

Recognizes O-FI-84-7 flow Higher than O-FI-84-18 flow SAT_ UNSAT N/A COMMENTS:_____________________________

NOTE CAD System A to Drywell Control Air supplies the following MSIVs:

3-FCV-1-14, MSIV LINE A INBOARD

3-FCV-1-26, MSIV LINE B INBOARD NOTE CAD System B to Drywell Control Air supplies the following MSIVs:

3-FCV-1-37, MSIV LINE C INBOARD

3-FCV-l-51, MSIV LINE D INBOARD Performance Step 8: Critical X Not Critical

c. MONITOR inboard MSIV indication status for valves drifting closed.

Standard:

Recognizes 3-FCV-l-14 and 26 closed SAT_ UNSAT N/A COMMENTS:___

7

JPM g Performance Step 9: Critical X Not Critical

9. IF Drywell Control Air header supplied from CAD System A shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-5, CAD SYSTEM A N2 SHUTOFF VALVE (Unit 3, Panel 3-9-54)

3-FSV-84-48, CAD A CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3-9-54)

Standard:

Closes 0-FCV-84-5 and 3-FSV-84-48 SAT_ UNSAT_ N/A COMMENTS:_______________________________

Performance Step 10: Critical Not Critical

10. IF Drywell Control Air header supplied from CAD B shows indications of being depressurized, THEN CLOSE the following valves:

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 3, Panel 3-9-55)

3-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3-9-55)

Standard:

N/A No indications of being depressurized SAT UNSAT N/A COMMENTS:______

STOP TIME____

END OF TASK 8

1PM h OPERATOR:

RO___ SRO___ DATE:

3PM NUMBER: h TASK NUMBER: U-066-AB-02 TASK TITLE: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI K/A NUMBER: 271000A2.04 KIA RATING: RO 3.4 SRO 4.1 PRA: NA TASK STANDARD: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI Per 2-ARP-9-4C/35 and 2-AOI-66-2 LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-ARP-9-4C/35 and 2-AOI-66-2 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

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

EXAMINER 1

INITIAL CONDITIONS:

You are a Unit 2 Operator. Unit 2 is at 100% power.

INITIATING CUE:

The Unit Supervisor directs you to respond to an OFF-GAS POST-TREATMENT RADIATION HI-HI-HI annunciator, panel 9-4C Window 35

JPM h 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 is at 100% power.

INITIATING CUE:

The Unit Supervisor directs you to respond to an OFF-GAS POST-TREATMENT RADIATION HI-HI-HI annunciator, panel 9-4C Window 35 3

JPM h START TIME______

Examiner Note: If candidate goes directly to 2-AOI-66-2, Skip the following performance steps 1 through 3 and continue at performance step 4.

Performance Step 1: Critical Not Critical X 2-ARP-9-4C window 35 A. VERIFY alarm condition on the following:

OFFGAS RADIATION recorder, 2-RR-90-266 on Panel 2-9-2.

OG POST-TREATMENT CHAN A RAD MON RTMR radiation monitor, 2-RM-90-266A on Panel 2-9-10.

OG POST-TREATMENT CHAN B RAD MON RTMR radiation monitor, 2-RM-90-265A on Panel 2-9-10.

Standard:

Candidate verifies alarm condition on 2-RR-90-266 and 2-RM-90-265A & 266A.

SAT UNSAT N/A COMMENTS:

4

JPM h Performance Step 2: Critical Not Critical 2-ARP-9-4C window 35(continued)

B. VERIFY OFF-GAS SYSTEM ISOLATION VALVE, 2-FCV-66-28 has the mechanical restraint DISENGAGED and 2-FCV-66-28 is CLOSED.

Standard:

Candidate identifies that 2-FCV-66-28 failed to automatically close on OFF-GAS POST-TREATMENT HI-HI-HI radiation, and places 2-HS-66-28 in close.

Candidate may dispatch AUO locally to verify valve not restrained.

SAT UNSAT N/A COMMENTS:_______________________

F CUE: If asked, 2-FCV-66-28 is not mechanically restrained Performance Step 3: Critical Not Critical X 2-ARP-9-4C window 35 (continued)

C. REFER TO 2-AOI-66-2.

Standard:

Candidate refers to 2-AOI-66-2.

SAT UNSAT N/A COMMENTS:

5

1PM h Performance Step 4: *Crjtical Not Critical 2-AOI-66-2 4.1 Immediate Actions

[1] IF scram has NOT occurred, THEN PERFORM the following:

[1.11 IF core flow is above 60%, THEN REDUCE core flow to between 50-60%.

[12] MANUALLY SCRAM the Reactor. REFER TO 2-AOI-100-1.

Standard:

Candidate reduces core flow to between 50-60% with recirc system, manually scrams the Reactor, and refers to 2-AOl- 100-1.

SAT UNSAT N/A COMMENTS:

6

1PM h CUE: After the candidate has scrammed the reactor and given the scram report, Another operator will perform the actions of scram procedure; continue the actions of 2-AOI-66-2.

Performance Step 5: *Criticai Not Critical 4.2 Subsequent Actions

[1] IF OFFGAS SYSTEM ISOLATION VALVE, 2-FCV-066-0028 has been mechanically restrained open due to plant conditions, THEN DISENGAGE 2-FCV-066-0028 mechanical restraint by rotating the restraining handwheel fully in the counterclockwise direction, locally at the stack

[2] VERIFY CLOSED OFFGAS SYSTEM ISOLATION VALVE, 2-FCV-66-28 on Panel 2-9-53 or locally.

Standard:

Candidate identifies that 2-FCV-66-28 failed to automatically close on OFF-GAS POST-TREATMENT HI-HI-HI radiation, and places 2-HS-66-28 in close. Candidate may dispatch AUO locally to verify valve not restrained.

SAT UNSAT N/A COMMENTS:

CUE: If asked, 2-FCV-66-28 is not mechanically restrained :

7

1PM h Performance Step 6: Critical Not Critical

[3] MONITOR area radiation levels at Panel 2-9-Il.

Standard:

Candidate monitors radiation levels at Panel 2-9-11.

SAT UNSAT N/A COMMENTS:_________________________

Performance Step 7: Critical Not Critical

[4] REFER TO EPIP-1 for emergency classification level and response.

STANDARD:

Candidate continues to the next step.

SAT UNSAT N/A COMMENTS:

f CUE: The Shift Manager is implementing EPIP-l Classification.

I 8

JPM h Performance Step 8: Critical Not Critical X

[5] MONITOR the following parameters:

A. MAIN STEAM LINE RADIATION, 2-RR-90-135, Panel 2-9-2.

B. OFFGAS RADIATION, 2-RR-90-266, Panel 2-9-2.

C. STACK GAS RADIATION, O-RR-90-147, Unit 1 Panel 1-9-2.

Standard:

Monitors 2-RR-90-135, 266 on Unit 2 Panel 2-9-2 and calls Unit 1 Operator for a reading on O-RR-90-147, Unit 1 Panel 1-9-2.

SAT UNSAT N/A COMMENTS:

CUE: When Candidate calls Unit 1 Operator for a reading on O-RR-90-147, Report STACK GAS RADIATION, O-RR-90-147 is reading 6 x 106 cps.

9

JPM h Performance Step 9: Critical Not Critical

[6] IF after five minutes from scram the Offgas Post Treatment activity is NOT less than 6 x 1 O cps as indicated on OFFGAS RADIATION recorder 2-RR-90-266 on Panel 2-9-2, THEN CLOSE all Main Steam Isolation Valves and Main Steam Line Drain Valves, 2-FCV-1-55 and 2-FCV-1-56.

Standard:

Candidate recognizes that the OFF-GAS POST TREATMENT activity is > 6 x 1 O cps and CLOSES ALL Main Steam Isolation Valves. Candidate closes Main Steam Line Drain Valves, 2-FCV-1-55 and 56.

SAT UNSAT N/A COMMENTS:

CUE: The Unit has been scrammed for 5 minutes. I NOTE Placing additional Stack Dilution Air Fans in service should keep O-RM-90-147 and O-RM 148 on scale.

Performance Step 10: Critical X Not Critical

[7] PLACE STACK DILUTION FAN SEL control switch, 2-XS-66-29, Panel 2-9-8, in OFF.

Standard:

Places Stack Dilution Fan Sel switch in OFF SAT UNSAT N/A COMMENTS:

10

1PM h Performance Step 11: Critical Not Critical

[8] START standby STACK DILUTION FAN 2B(2A) using control switch, 2-HS-66-31A(29A), Panel 2-9-8.

Standard:

Starts the standby Stack Dilution Fan.

SAT UNSAT N/A COMMENTS:_________________________

Performance Step 12: Critical Not Critical X

[9] REQUEST Unit 1 and Unit 3 operators to START standby Stack Dilution Air Fans.

[10] REQUEST Chemistry perform 0-SI-4.8.B.2-8, Airborne Effluent Analysis -

Stack Noble Gas, to determine activity.

[11] REQUEST Chemistry sample reactor water for radioactivity.

Standard:

Requests Unit 1 and 3 start fans, request chemistry support SAT UNSAT N/A COMMENTS:

I CUE: Acknowledge requests END OF TASK STOP TIME 11

n JPM h OPERATOR:_______________________

RO___ SRO DATE:________

JPM NUMBER: h TASK NUMBER: U-066-AB-02 TASK TITLE: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI KJA NUMBER: 271000A2.04 KJA RATiNG: RO 3.4 SRO 4.1 PRA: NA TASK STANDARD: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI JAW 3-ARP-9-4C/35 and 3-AOI-66-2 LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-ARP-9-4C/35 and 3-AOI-66-2 VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:_______

EXAMINER 1

1NITIAL CONDITIONS:

You are a Unit 3 Operator. Unit 3 is at 100% power.

INITIATING CITE:

The Unit Supervisor directs you to respond to an OFF-GAS POST-TREATMENT RADIATION HI-HI-HI annunciator, panel 9-4C Window 35

JPM h 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.

1NITIAL CONIMTIONS:

You are a Unit 3 Operator. Unit 3 is at 100% power.

INITIATING CUE:

The Unit Supervisor directs you to respond to an OFF-GAS POST-TREATMENT RADIATION HI-HI-HI annunciator, panel 9-4C Window 35 3

JPM h START TIME______

Examiner Note: If candidate goes directly to 3-AOI-66-2, Skip the following performance steps I through 4 and continue at performance step 5.

Performance Step 1: Critical Not Critical 3-ARP-9-4C window 35 A. VERIFY alarm condition on the following:

OFFGAS POST-TREATMENT RADIATION recorder, 3-RR-90-265 on Panel 3-9-2.

OG POST-TREATMENT CHAN A RAD MON RTMR radiation monitor, 3-RM-90-266A on Panel 3-9-10.

OG POST-TREATMENT CHAN B RAD MON RTMR radiation monitor, 3-RM-90-265A on Panel 3-9-10.

Standard:

Candidate verifies alarm condition on 3-RR-90-265 and 3-RM-90-265 & 266.

SAT UNSAT N/A COMMENTS:

4

1PM h Performance Step 2: Critical Not Critical 3-ARP-9-4C window 35(continued)

B. CHECK the following is in alarm:

. 0FF-GAS ISOLATION VALVE CLOSED, 3-XA-55-7A Window 4.

Standard:

Candidate verifies alarm condition on OFF-GAS ISOLATION VALVE CLOSED, 3-XA-55-7A, Window 4.

SAT UNSAT N/A COMMENTS:_______________________

Performance Step 3: Critical Not Critical 3-ARP-9-4C window 35 (continued)

C. VERIFY OFF-GAS SYSTEM ISOLATION VALVE, 3-FCV-66-28 has the mechanical restraint DISENGAGED and 3-FCV-66-28 is CLOSED.

Standard:

Candidate identifies that 3-FCV-66-28 failed to automatically close on OFF-GAS POST TREATMENT HI-HI-HI radiation, and places 3-HS-66-28 in close.

Candidate may dispatch AUO locally to verify valve not restrained.

SAT UNSAT N/A COMMENTS:________

CUE: If asked, 3-FCV-66-28 is not mechanically restrained 5

1PM h Performance Step 4: Critical Not Critical X 3-ARP-9-4C window 35 (continued)

D. REFER TO 3-AOI-66-2.

Standard:

Candidate refers to 3-AOI-66-2.

SAT UNSAT N/A COMMENTS:__________________________

Performance Step 5: *Critjcaj X Not Critical 3 -AOI-66-2 4.1 Immediate Actions

[1) IF scram has NOT occurred, THEN PERFORM the following:

[1.1] IF core flow is above 60%, THEN REDUCE core flow to between 50-60%.

[12j MANUALLY SCRAM the Reactor. REFER TO 3-AOI-l00-1.

Standard:

Candidate reduces core flow to between 50-60% with recirc system, manually scrams the Reactor. Candidate refers to 3-AOI-100-1.

SAT UNSAT N/A COMMENTS:

6

JPM h CUE: After the candidate has scrammed the reactor and given the scram report, Another operator will perform the actions of scram procedure; continue the actions of 3-AOI-66-2.

Performance Step 6: *Criticaj Not Critical 4.2 Subsequent Actions

[1] IF OFFGAS SYSTEM ISOLATION VALVE, 3-FCV-066-0028 has been mechanically restrained open due to plant conditions, THEN DISENGAGE 3-FCV-066-0028 mechanical restraint by rotating the restraining handwheel fully in the counterclockwise direction, locally at the stack (otherwise N/A).

[2] VERIFY CLOSED OFFGAS SYSTEM ISOLATION VALVE, 3-FCV-66-28 on Panel 3-9-53 or locally.

Standard:

Candidate identifies that 3-FCV-66-28 failed to automatically close on OFF-GAS POST TREATMENT HI-HI-HI radiation, and places 3-HS-66-28 in close. Candidate may dispatch AUO locally to verify valve not restrained.

SAT UNSAT N/A COMMENTS:________

CUE: If asked, 3-FCV-66-28 is not mechanically restrained 7

1PM h Performance Step 7: Critical Not Critical X

[3] MONITOR area radiation levels at Panel 3-9-11.

Standard:

Candidate monitors radiation levels at Panel 3-9-11.

SAT UNSAT N/A COMMENTS:_________________________

Performance Step 8: Critical Not Critical

[4] REFER TO EPIP-1 for emergency classification level and response.

STANDARD:

Candidate continues to the next step.

SAT UNSAT N/A COMMENTS:

CUE: The Shift Manager is implementing EPIP-1 Classification.

I 8

1PM h Performance Step 9: Critical Not Critical

[5] MONITOR the following parameters:

A. MAIN STEAM LiNE RADIATION, 3-RR-90-135, Panel 3-9-2.

B. OFFGAS PRETREATMENT RADIATION, 3-RR-90-157, Panel 3-9-2.

C. OFFGAS POST-TREATMENT RADIATION, 3-RR-90-265, Panel 3-9-2.

D. STACK GAS RADIATION/CONT RM RADIATION, O-RR-90-147, on Panel 1-9-2.

Standard:

Monitors 3-RR-90-135, 157, 265, on Unit 3 Panel 3-9-2 and called Unit I Operator for a reading on O-RR-90-147, Unit 1 Panel 1-9-2.

SAT UNSAT N/A COMMENTS:_________________________

CUE: When Candidate calls Unit 1 Operator for a reading on O-RR-90-147, Report STACK GAS RADIATION, 0-RR-90-147 is reading 6 x 106 eps.

9

1PM h Performance Step 10: Critical Not Critical

[6] IF after five minutes from scram the Offgas Post Treatment activity is NOT less than 6 x i0 cps as indicated on 3-RR-90-265 on Panel 3-9-2, THEN CLOSE all Main Steam Isolation Valves and Main Steam Line Drain Valves, 3-FCV-001-0055 and 3-FCV-001-0056.

Standard:

Candidate recognizes that the OFF-GAS POST TREATMENT activity is > 6 x i0 cps and CLOSES ALL Main Steam Isolation Valves. Candidate closes Main Steam Line Drain Valves, 3-FCV-1-55 and 3-FCV-1-56.

SAT UNSAT N/A COMMENTS:

CUE: The Unit has been scrammed for 5 minutes. I NOTE Placing additional Stack Dilution Air Fans in service should keep 0-RM-90-147 and -148 on scale.

Performance Step 11: Critical X Not Critical

[7] PLACE STACK DILUTION FAN SEL control switch, 3-XS-66-29, Panel 3-9-8, in OFF.

Standard:

Places Stack Dilution fan Sel switch in OFF SAT UNSAT N/A COMMENTS:

10

JPM h Performance Step 12: Critical Not Critical

[8] START standby STACK DILUTION FAN 3B(3A) using control switch, 3-HS-66-31A(29A), Panel 3-9-8.

Standard:

Starts the standby Stack Dilution Fan.

SAT UNSAT N/A COMMENTS:________________________

Performance Step 13: Critical Not Critical

[9] REQUEST Unit 1 and Unit 2 operators to START standby Stack Dilution Air Fans.

[10] REQUEST Chemistry perform 0-SI-4.8.B.2-8, Airborne Effluent Analysis -

Stack Noble Gas, to determine activity.

[11] REQUEST Chemistry sample reactor water for radioactivity.

Standard:

Requests Unit 1 and 2 start fans, request chemistry support SAT UNSAT N/A COMMENTS:

CUE: Acknowledge requests I END OF TASK STOP TIME 11

JPM +/-

OPERATOR:

RO___ SRO DATE:_______

JPM NUMBER: i TASK NUMBER: U-000-EM-41 TASK TITLE: Drain PSC Tank Level Switch KJA NUMBER: 295031 EA1.08 KJA RATING: RU 3.8 SRO 3.9 TASK STANDARD: PSC Tank Level Switch drained LOCATION OF PERFORMANCE: Plant PRA: HFA_0002RPV_LVL, 1.15E-03, OPERATOR FAILS TO MAINTAIN RPV LEVEL REFERENCES/PROCEDURES NEEDED: 1-EOI Appendix-7G VALIDATION TIME: 15 minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

1TITIAL CONDITIONS:

You are an Auxiliary Unit Operator, the plant is operating in EOI-1 RPV Control.

INITIATING CUE:

The Unit Supervisor directs you to commence 1-EOI Appendix-7G, Alternate RPV Injection System Lineup Pressure Suppression Chamber Head Tank Pumps.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM +/-

IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. Touch STAAR may be carried out to the point of touching a label. If it becomes necessary to physically touch a control switch, use a non-conductive pointing device. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats correct (or Thats incorrect, if applicable). When you have completed your assigned task, you will say, My task is complete and I will acknowledge that your task is complete.

IMTIAL CONDITIONS:

You are an Auxiliary Unit Operator, the plant is operating in EOI-l RPV Control.

INITIATING CUE:

The Unit Supervisor directs you to commence l-EOI Appendix-7G, Alternate RPV Injection System Lineup Pressure Suppression Chamber Head Tank Pumps.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

3

JPM i START TIME____

Performance Step 1: Critical X Not Critical

1. ALIGN suction to PSC Head Tank Pumps as follows:

a. DISPATCH personnel to CLOSE 1-SHV-075-0616, PSC HEAD TANK FILL & DR SHV (RB SW, El 639 ft).

Standard:

Operator simulates closing 1 -SHV-075-06 16 SAT UNSAT N/A COMMENTS:____

CUE: When Operator simulates closing 1-SHV-075-0616, valve is closed.

Another Operator is installing jumpers.

PSC Head Tank Pumps failed to start proceed with step 4.

Performance Step 2: Critical Not Critical

4. IF PSC Head Tank Pumps fail to start, THEN DISPATCH personnel to perform the following:

a. REFER TO Attachment 1 and OBTAIN tools and equipment from EOI Equipment Storage Box (RB, El 621 ft).

Standard:

Identify where tools and equipment are located SAT_ UNSAT N/A COMMENTS:______

CUE: When Operator identifies the location of £01 Equipment storage box inform operator that they have the required tools and equipment 4

JPM i Performance Step 3: Critical Not Critical

b. REFER TO Attachment 2 and DRAIN 1-LS-075-0078B, PSC WTR HD TK HIGH LVL SW, into bucket as follows (RB SW, El 639 ft):

1) CONNECT tygon tubing and fitting to level switch drain 1-DRV-075-0078B, PSC WTR HD TK HIGH LS DR, using 10 in.

crescent wrench and ROUTE into bucket.

Standard:

Simulates connecting tygon tubing to level switch drain valve 1-DRV-075-0078B SAT_ UNSAT_ N/A COMMENTS:________________________________

j CUE: When simulated tygon tubing attached Performance Step 4: Critical X Not Critical

2) CLOSE the following valves:

1-RTV-075-0078BA, PSC HD TK HIGH LEVEL SW RTV

1-RTV-075-0078BB, PSC HD TK HIGH LEVEL SW RTV.

Standard:

Simulates closing 1 -RTV-075-0078BA and 1 -RTV-075-0078BB SAT_ UNSAT N/A COMMENTS:

CUE: 1-RTV-075-0078BA and 1-RTV-075-0078BB are closed 5

JPM +/-

Performance Step 5: Critical X Not Critical

3) OPEN the following valves:

1-DRV-075-0078B, PSC WTR HD TK HIGH LS DR

1-VTV-075-0078B, PSC WTR HD TK HIGH LS VENT.

Standard:

Simulates opening 1 -DRV-075-0078B and 1 -VTV-075-0078B SAT_ UNSAT N/A COMMENTS:______________________________

CUE: 1-DRV-075-0078B and 1-VTV-075-0078B are open, water is draining. Water has completed draining Performance Step 6: Critical X Not Critical

4) WHEN Contents from 1-LS-075-0078B, PSC WTR HD TK HIGH LVL SW, stop draining, THEN CLOSE the following valves:

1-DRV-075-0078B, PSC WTR HD TK HIGH LS DR

l-VTV-075-0078B, PSC WTR HD TK HIGH LS VENT.

Standard:

Simulates closing 1 -DRV-075-0078B and I -VTV-075-0078B SAT_ UNSAT N/A COMMENTS:_______________________________

CUE: 1-DRV-075-0078B and 1-VTV-075-0078B are closed 6

JPM +/-

Performance Step 7: Critical Not Critical

5) NOTIFY Unit 1 Operator to restart PSC Head Tank Pumps.

Standard:

Notifies Unit I Operator SAT UNSAT N/A COMMENTS:

CUE: Acknowledge notification and inform operator PSC Head Tank Pumps are running END OF TASK STOP TIME 7

JPM j OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: j TASK NUMBER: U-000-AB-05 TASK TITLE: Shutdown Cooling in service lAW CR Abandonment K/A NUMBER: 295016 AA1.07 K/A RATING: RO 4.2 SRO 4.3 TASK STANDARD: Perform field actions to place Shutdown Cooling in service from outside the Control Room in accordance with 1-AOI-100-2.

PRA: NA LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1 -AOl- 100-2 VALIDATION TIME: minutes PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATUR E:

DATE:

EXAMINER 1

INITIAL CONDITIONS:

You are a Unit Operator. Unit 1 has entered 1-AOl- 100-2, Control Room Abandonment.

The following conditions currently exist:

Reactor Pressure 45 psig and lowering

RHR Pump 1D is in Suppression Pool Cooling

RHRSW Pump D2 is operating

An Operator is standing by at 1 -HS-074-030B in the Reactor BLDG

An Operator is standing by at Panel 1-25-32

All 1 -AOl- 100-2 Panel Checklists are complete INITIATING CUE:

The Unit Supervisor directs you to initiate Shutdown Cooling with RHR Pump 1D in accordance with l-AOI-100-2.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j 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 a Unit Operator. Unit 1 has entered l-AOI-l00-2, Control Room Abandonment.

The following conditions currently exist:

Reactor Pressure 45 psig and lowering

RHR Pump 1D is in Suppression Pool Cooling

RHRSW Pump D2 is operating

An Operator is standing by at 1-HS-074-030B in the Reactor BLDG

An Operator is standing by at Panel 1-25-32

All 1 -AOl- 100-2 Panel Checklists are complete INITIATING CUE:

The Unit Supervisor directs you to initiate Shutdown Cooling with RHR Pump 1D in accordance with 1-AOI-100-2.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

3

JPM j START TIME____

Performance Step 1: *Ciitjcal X Not Critical

[201 INITIATE RHR Shutdown Cooling as follows:

[20.1] VERIFY REACTOR PRESSURE B, 1-PI-3-79, less than 50 psig at Panel 1-25-32.

[20.2] IF RHR pumps are operating in Suppression Pool Cooling or RHR LPCI, THEN PERFORM the following: (Otherwise N/A)

[2o.2.1] VERIFY CLOSED l-FCV-074-0073, using RHR SYS II SUPPR POOL CLG/TEST VLV, 1-HS-074-0073C at 480V RMOV Bd 1B, Compt.

R11C.

Standard:

Reactor Pressure less than 50 psig is given in CUE. *Simulates closing 1-FCV-074-0073 by holding 1-HS-74-73 in Close.

SAT_ UNSAT N/A _COMMENTS:________________________

Cue: IF Asked, 1-XS-74-073C is in Emergency.

l-FCV-74-73 Red Light On and Green Light On. When l-HS-74-73C is held in CLOSE switch is in close, Red light Off and Green light On.

4

JPM j Performance Step 2: Critical X Not Critical

[20.2.2] VERIFY CLOSED l-FCV-074-0071, using RHR SYS II SUPPR CHBR/POOL ISOL VLV, l-HS-074-OO7lC at 480V RMOV Bd IB, Compt. 11C.

Standard:

Simulates closing 1-FCV-074-0071 by placing l-FIS-74-71C in Close.

SAT_ UNSAT N/A COMMENTS:___________________

Cue: IF Asked, l-XS-74-071C is in Emergency.

l-FCV-74-71 Red Light On and Green Light Off. When l-HS-74-71C is placed in CLOSE switch is in close, Red light Off and Green light On.

Performance Step 3: Critical Not Critical X

[20.2.3] VERIFY CLOSED l-FCV-74-0066, using RHR SYS II LPCI OUTBD INJECT VLV, 1-HS-074-0066C at 480V RMOV Bd 1B, Compt. 3A.

Standard:

Verifies 1-FCV-74-066 closed.

SAT_ UNSAT N/A COMMENTS:

Cue: IF Asked, 1 -XS-74-066 is in Emergency.

1-FCV-74-66 Red Light Off and Green Light On.

5

JPM j Performance Step 4: X Not Critical

[20.2.4] PLACE RUR PUMP 1B, 1-HS-074-0028C, in TRIP at 4160V Shutdown Bd C, Compt. 17, to stop RHR PUMP lB

[20.2.5] PLACE RHR PUMP 1D, 1-HS-074-0039C, in TRIP at 4160V Shutdown Bd D, Compt. 16, to stop RHR PUMP 1D.

Standard:

Simulates tripping RHR Pump ID SAT_ UNSAT N/A COMMENTS:_____________________________

Cue: IF Asked, 1-43-74-039 is in Emergency. Amps are reading 150 amps 1-HS-74-39 is in Trip, Red Light Off and Green Light On, ZERO amps 6

JPM j Performance Step 5: Critical Not Critical NOTES

1) Appendix R modifications on Ui require MODE SELECTOR SWITCH LOOP II, l-HS-074-0158 to be in SHDN before l-FCV-074-0024 and 1-FCV-074-0035 can be operated

2) EDC 70723 requires 1-FCV-074-0024 and 0035 are NOT to be opened during normal and test conditions with differential pressure across the valve seats. Therefore, Mm Flow valve l-FCV-074-0030 shall be opened prior to opening the Torus suction valves.

(Reference Note 16 on print l-47E81 1-1)

CAUTION

[1NPO] Failure to verify closed RHR Pumps lB and 1D Suppression Pool Suction Valves (1-FCV-74-24 and l-FCV-74-35) and RHR System II Test Valve (l-FCV-74-73) may result in inadvertent draining of the Reactor Vessel when RHR Shutdown Cooling Suction Isolation Valves (1-FCV-74-47 and 1-FCV-74-48) are opened. [INPO SOER 87-002]

[20.3] VERIFY MODE SELECTOR SWITCH LOOP II, l-HS-074-0 158 in SHDN at 480V RMOV Bd lB Compt. bA.

Standard:

Simulates verifying 1-HS74-158 in Shutdown SAT_ UNSAT N/A COMMENTS:______

Cue: Switch is in Shutdown, Panel Checklist aligned this switch 7

JPM j Performance Step 6: Critical X Not Critical

[20.4] VERIFY CLOSED RHR Pump lB and 1D Suppression Pool Suction Valves at 480V RMOV Bd 1B, as follows:

VERIFY CLOSED RHR PUMP lB SUPPR POOL SUCT VLV, using l-HS-074-0024C at Compt. 4C.

VERIFY CLOSED RUR PUMP 1D SUPPR POOL SUCT VLV, using l-HS-074-0035C at Compt. 5C2.

Standard:

Simulates Closing l-HS-74-24 and l-HS-74-35.

SAT_ UNSAT N/A _COMMENTS:__________________________

Cue: If asked, 1 -XS-74-24 is in Emergency.

Red light On and Green light Off, when 1-HS-74-24C is placed in Close switch is in close, Red Light Off and Green light On If asked, l-XS-74-35 is in Emergency.

Red light On and Green light Off, when 1-HS-74-35C is placed in Close switch is in close, Red Light Off and Green light On 8

JPM j Performance Step 7: *Ci.itjcaj X Not Critical NOTE EQV 70932 requires that due to limitations on the valve actuator on 1-FCV-074-0025 and 1-FCV-074-0036 the valves shall not be stroked OPEN if the differential pressure across the disc exceeds 82 psid.

[20.5] OPEN RFIR Pump lB and 1D Shutdown Cooling Suction Valves at 480V RMOV Bd 1B, as follows:

PLACE RHR PUMP lB SD COOLiNG SUCT VLV, l-HS-074-0025C, in OPEN. (Compt. 6C2)

. PLACE R}IR PUMP 1D SD COOLING SUCT VLV, 1-HS-074-0036C, in OPEN. (Compt. 7C)

Standard:

Simulates opening Shutdown Cooling Suction Valves for RHR Pump 1 B and D SAT_ UNSAT N/A COMMENTS:____________________________

Cue: If asked, 1 -XS-74-25 is in Emergency.

Red light Off and Green light On, when 1-HS-74-25C is placed in Open switch is in open, Red Light On and Green light Off If asked, 1-XS-74-36 is in Emergency.

Red light Off and Green light On, when 1-HS-74-36C is placed in Open switch is in open, Red Light On and Green light Off 9

JPM j Performance Step 8:

Critical Not Critical NOTE RHR pump minimum flow and shutdown cooling suction valve interlock logic remains operable with RHR SYSTEM II MN FLOW VLV XFER, 1-XS-074-0030, in EMERG.

[20.6] VERIFY CLOSED 1-FCV-074-0030 using RHR SYSTEM II MN FLOW VALVE, l-HS-074-0030B at Reactor Building El 541, Southeast.

[20.7] PLACE RHR SYSTEM II MN FLOW VLV, l-BKR-074-0030 in OFF at 480V RMOV Bd 1B, Compt. Ri iE, to inhibit l-FCV-074-0030 operation.

Standard:

Operator verifies position with operator in Reactor Building then simulates turning

I -BKR-74-0030 Off SAT_ UNSAT N/A _COMMENTS:__________________________

Cue: When operator is called in Reactor Building l-FCV-74-30 indicates closed.

When simulated 1-BKR-74-30 is OFF 10

JPM j Performance Step 9: Critical Not Critical

[20.8] PLACE RHR SHUTDOWN COOUNG SUCT INBD ISOL VLV, 1-HS-074-0048C, at 480V RMOV Bd 1A, Compt. 8C, in OPEN.

[20.9] PERFORM the following at 250V DC RMOV Bd 1A, Compt. R1A:

[20.9.1] PLACE RHR SHUTDOWN COOUNG SUCT OUTBD ISOL VLV, 1-BKR-074-0047 in ON.

[20.9.2] PLACE RHR SHUTDOWN COOLiNG SUCT OUTBD ISOL VLV, 1-HS-074-0047C, in OPEN.

Standard:

Simulates opening 1-HS-74-48C, turning on 1-BKR-74-47 and opening 1-HS-74-47.

SAT UNSAT N/A COMMENTS:___________________________

Cue: If asked, 1-XS-74-48 is in Emergency.

Red light Off and Green light On, when 1 -HS-74-48C is placed in Open switch is in open, Red Light On and Green light Off If asked, 1-XS-74-47 is in Emergency. When 1-BKR-74-47 is placed in On, Breaker is On and Red light Off and Green light On.

When 1-HS-74-47C is placed in Open switch is in open, Red Light On and Green light Off 11

JPM j Performance Step 10: X Not Critical

[20.10] PLACE RHR SYS II LPCI OUTBD INJECT VLV, 1-HS-074-0066C, in CLOSE at 480V RMOV Bd 1B, Compt. 3A.

¶20.11] PLACE RHR SYS II LPCI INBD iNJECT VLV, 1-HS-074-0067C, in OPEN at 480V RMOV Bd IB, Compt. R1OA.

[20.12] IF RHR Pump lB is to be started, THEN PERFORM the following: (Otherwise N/A)

Standard:

Operator verifies 1-HS-74-66 closed and simulates opening *1.Hs..74.67. RHR Pump 1D is to be started. Step 21.12 isNA SAT_ UNSAT_ N/A COMMENTS:_______________________________

Cue: If asked, 1-XS-74-66 is in Emergency.

Red light Off and Green light On, 1 -HS-74-66C is in Close If asked, 1-XS-74-67 is in Emergency. When 1-HS-74-67C is placed in Open, switch is in open and Red light On and Green light Off.

12

JPM j Performance Step 11: Critical Not Critical

[20.131 IF RHR Pump 1D is to be started, THEN PERFORM the following:

[20.13.1] VERIFY RI{RSW Pump D2 operating using RHRSW HDR D PRESSURE, 0-PI-23-61/l, at Panel 1-25-32.

CAUTION RHR SYS II MIN FLOW VALVE, 1-FCV-074-0030, was defeated in Step 4.2[20.7]. Failure to establish flow using RHR SYS II LPCI OUTBD INJECT VALVE, 1 -FCV-074-0066, immediately after starting RHR Pump 1D could result in pump damage.

[20.13.2] DIRECT Ui Unit Supervisor to proceed to 480V RMOV Bd 1B, Compt.

3A and ESTABLISH communications.

Standard:

RHRSW Pump D2 operating is given in initial conditions. Operator directs Unit Supervisor to proceed to 480V RMOV Bd 1B, compartment 3A and the operator proceed to RHR Pump 1D Breaker.

SAT_ UNSAT N/A COMMENTS:______________________________

Cue: Unit Supervisor is standing by at 480V RMOV Bd 1B, compartment 3A I

13

JPM j Performance Step 12: *Critical Not Critical

[20.13.3] PLACE RHR PUMP 1D, 1-HS-074-0039C, in CLOSE at 4160V Shutdown Bd D, Compt. 16, to start RHR PUMP 1D.

[20.13.4] MONITOR RHR SYS II TOTAL FLOW, 1-FI-74-79 at Panel 1-25-32.

[20.13.5] THROTTLE OPEN R}IR SYS II LPCI OUTBD 1NJEC VLV, using 1-HS-074-0066C at 480V RMOV Bd 1B, Compt. 3A.

[20.13.6] WHEN RHR SYS I TOTAL FLOW, 1-FI-74-79 at Panel 1-25-32, indicates between 7,000 and 10,000 gpm flow, THEN DIRECT the operator to stop throttling 1-HS-074-0066C.

Standard:

Simulates starting RHR Pump 1D by placing 1-HS-74-39C in Close. Informs Operator at Panel 1-25-32 and the Unit Supervisor.

SAT_ UNSAT_ N/A COMMENTS:___________________________

Cue: When simulated 1-HS-74-39C is in Close, Red Light On and Green Light Off, Large bang heard when breaker activated and Amps pegged high and are now reading 100 amps.

STOP TIME END OF TASK 14

JPM k OPERATOR:

RO___ SRO___ DATE:

JPM NUMBER: k Alternate Path TASK NUMBER: U-000-SS-8 TASK TITLE: Operator 6 Manual Actions 0-SSI-16 KJA NUMBER: 600000 AA2.16 KJA RATING: RO 3.0 SRO 3.5 PRA: Control Building 617

- 4.62E-05 0.049 2.26E-06 %xLOOPFRCB TASK STANDARD: Aligns 480V RMOV BD 3B and starts RHR Pump 3A LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 0-SSI-16 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: 20 minutes for section 2.0 and 120 minutes for section 3.0.

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY___ UNSATISFACTORY SIGNATURE:_________________ DATE:

EXAMINER 1

INITIAL CONDITIONS:

You are Operator 6, the plant is operating in O-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

iNITIATING CUE:

The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k 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 Operator 6, the plant is operating in 0-SSI-l6 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

INITIATING CUE:

The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

3

JPM k START TIME____

Performance Step 1: Critical X Not Critical 2.0 Align 480V REACTOR MOV BOARD 3B (20 Mm)

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

[2] PERFORM the following to align 480V Reactor MOV Board 3B:

[2.1] PROCEED TO Compt 2A, AND PLACE NORMAL FEEDER CONTROL SWITCH, 3-HS-268B/2A-A, in TRIP CUE: 3-HS-268B/2A-A is in Trip, Green light On Red light Off.

[2.2] PROCEED TO Compt 16A, AND PLACE EMERGENCY FEEDER CONTROL SWITCH, 3-HS-268-B/16A-A, in CLOSE.

CUE: 3-HS-268-B/16A-A is in Close, Red light On Green Light Off I

Standard:

Simulates placing 3-HS-268B/2A-A in Trip and 3-HS-268-B/16A-A in Close SAT_ UNSAT N/A COMMENTS:_______________________________

4

JPN k Performance Step 2:

Critical X Not Critical

[2.3] PROCEED TO Compt 1C, AND PERFORM the following:

[231] PLACE RCIC STM LINE EMER TRANS SWITCH 3-XS-071-0002, in EMERG.

[2.3.2] VERIFY OPEN RCIC STM LINE 1NBD ISOL VALVE, 3-HS-071-0002B.

CUE: 3-XS-071-0002 is in Emergency and RCIC Steam Line Inboard Isolation Valve has Red Light On, Green Light Off Standard:

Simulates placing 3-XS-071-0002 in Emergency and verifies RCIC STM LINE 1NBD ISOL VALVE Open SAT_ UNSAT N/A Performance Step 3: Critical X Not Critical

[2.4] PROCEED TO Compt 4C, AND PLACE O-BKR-084-0016A CONTAINMENT ATMOSPHERE DILUTION SYSTEM B HEATER, breaker in OFF.

CUE: O-BKR-084-0016A is in Off I

Standard:

Simulates placing O-BKR-084-0016A in Off SAT_ UNSAT N/A COMMENTS:_______________________________

STOP TIME____

5

JPM k Performance Step 4: Critical Not Critical X

[3] NOTIFY Unit 3 Unit Supervisor of completion of this section.

[4] PROCEED TO 4160V Shutdown Board 3EA in preparation of performing Section 3.0.

Standard:

Notifies Unit 3 Unit Supervisor and proceeds to 4160 SD BD 3EA SAT_ UNSAT N/A COMMENTS:_______________________________

CUE: Acknowledge notification and Notify Operator to perform section 3.0 6

JPM k START TIME____

Performance Step 5:

Critical Not Critical 3.0 RBR PUMP 3A LOCAL START (120 Miii)

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

NOTE If RHR pump fails to start, pushbutton on breaker must be used.

[2] PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.1] PLACE RHR PUMP 3A TRANSFER, 3-43-074-0005, in EMERG.

CUE: 3-43-074-0005 is in Emergency I

[2.2] PLACE RHR PUMP 3A, 3-HS-074-0005C, in CLOSE.

[2.3] VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

CUE: 3-HS-074-0005C is in Close, No AMPS are indicated, Red light OFF, Green Light On, Yellow light remained On.

If asked No breaker trips are indicated.

Standard:

Simulates placing 3-43-074-0005 in Emergency and 3-HS-074-0005C in Close SAT_ UNSAT N/A COMMENTS:_______________________________

7

JPM k Performance Step 6:

Critical Not Critical 3.0 RHR PUMP 3A LOCAL START (120 Mm)

NOTE

IfPJ{R pump fails to start, pushbutton on breaker must be used.

CUE: Breaker 3-BKR-074-0005 pushbutton is depressed I

[2] PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.3] VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

f CUE: AMPS pegged high, Red light ON and Green Light OFF Breaker CLOSED, current AMP reading is 180 AMPS I Standard:

Simulates depressing pushbutton on 3-BKR-074-0005 and verifies Amps SAT UNSAT N/A STOP TIME____

8

JPM k Performance Step 7: Critical Not Critical

[3] NOTIFY Unit 3 Unit Supervisor of the completion of this section.

[4] PROCEED TO 4160 Shutdown Board A in preparation of performing Section 4.0.

Standard:

Notifies Unit 3 Unit Supervisor SAT_ UNSAT N/A _COMMENTS:

CUE: Another Operator will continue with section 4.0 END OF TASK 9

n n BFN Control Building Fire EL 593 Through 0-SSI-16

Unit 0 EL 617 Rev. 0032 Page 209 of 246 Attachment 6 (Page 1 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 3B, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA In the event of a loss of radio communications the Unit 3 Backup Control Panel, 3-25-32, phone number is 2335.

(10 Mm)

( PROCEED TO 480V Reactor MOV Board 3B, AND PLACE 7 the breaker at the following compartments in OFF:

Compt 14C1, 3-BKR-099-0003B PRI ISOL BREAKER FEEDING COMPT 14C2 RPS MG SET 3B. Dp (120 Mm)

Compt 7E, 3-BKR-023-0046 RHRSW HEAT EXCHANGER 3B SERVICE WATER DISCHARGE VALVE, 3-FCV-23-46. -

(10 Mm)

PROCEED TO 3-LPNL-925-0658 MSRV TRANSFER CONTROL PANEL (Mounted on south wall of board room).

PLACE the following Transfer Switches in DISCT/EMERG:

MAIN STEAM LINE C RELIEF VALVE DISCONNECT SW, 3-XS-001 -0031 7 op MAIN STEAM LINE A RELIEF VALVE DISCONNECT SW, 3-XS-001-0179 MAIN STEAM LINE B RELIEF VALVE TRANSFER SW, 0

3-XS-00 1-0018

MAIN STEAM LINE B RELIEF VALVE TRANSFER SW, f 3-XS-001 -0019 op

BFN Control Building Fire EL 593 Through 0-SSI-16 Unit 0 EL 617 Rev. 0032 Page 210 of 246 Attachment 6 (Page 2 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 3B, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA (continued) 5 c PROCEED TO 41 60V Shutdown Board 3EA. cD If Breaker Control Switch fails, pushbutton ker may be used.

(20 Mm)

PERFORM the following to align 4160V Shutdown Board 3EA:

OBTAIN Sync Switch located in box near entrance door. p p PROCEED TO Compt 8, Bottom, OPEN door, AND PLACE 250V DC CONTROL POWER TRANSFER, 3-XSW-21 1-OO3EA knife switch in 4160V SHUTDOWN BD 3EA ALTERNATE CONTROL POWER FROM 0 r BATTERY BD 2 BKR 703, down position.

PROCEED TO Compt 1, 3-BKR-21 1-O3ENOOI BKR 1844 TIE TO BKR 1824 4KV S/D BD A, AND PERFORM the following:

PLACE BKR 1844 EMER APP R ISOL SEL SWITCH (43AR), 3-43BU-21 1-O3EAJOI, in EMER. op

[5 .2 PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-211-O3EA/01, in EMERG.

/

(sA PLACE BREAKER CONTROL SWITCH, 3-HS-211-O3EAIOIB,inTRIP. op

BFN Control Building Fire EL 593 Through 0-SSI-16 UnitO EL617 Rev. 0032 Page 211 of 246 Attachment 6 (Page 3 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 3B, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA (continued)

PROCEED TO Compt 4, 3-BKR-21 1-03EA1004 BKR 1726 TIE FROM BKR 1732 4KV BUS TIE BD, AND PERFORM the following:

5. . PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-211-03EN04, in EMERG. C))

PLACE BREAKER CONTROL SWITCH, 3-HS-211-O3EA/04B, in TRIP. Cc)

PROCEED TO Compt 5, 0-BKR-023-0085 RHRSW PUMP A3, AND PERFORM the following:

PLACE RHRSW PUMP A3 EMER/NORM CONT TRANS SWITCH, 0-43-023-0085, in EMERG.

PLACE BACKUP CONTROL SWITCH FOR RHRSW PUMP A3, 0-HS-023-0085C, in TRIP.

PROCEED TO Compt 6, 3-BKR-075-0005 CS PUMP 3A

> MOTOR BREAKER, AND PERFORM the following:

[?1$ PLACE CS PUMP 3A CONTROL TRANS SWITCH, 0

)- 3-XSW-075-0005, in EMERG.

[ j) PLACE CS PUMP 3A EMER HAND SWITCH, 3-HS-075-0005C, in TRIP.

BFN Control Building Fire EL 593 Through 0-SSI-16 UnitO EL617 Rev 0032 Page 212 of 246 Attachment 6 (Page 4 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 3B, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA (continued)

PROCEED TO Compt 7, 3-BKR-21 1-03EN007 NORM FDR BKR 1334 TIE FROM BKR 1326 4KV UNIT BD 3A, AND PERFORM the following:

0 PLACE BKR 1334 EMER APP R ISOL SEL SWITCH (43AR), 3-43BU-21 1-03EA107, in EMER.

0 PLACE BREAKER CONTROL TRANSFER SWITCH 43, 3-43-21 1-03EA107, in EMERG. op PLACE BREAKER CONTROL SWITCH, 3-HS-21 1-O3ENO7B, in TRIP.

0 PROCEED TO Compt 11, 3-BKR-085-0002 CONTROL ROD DRIVE PUMP 3B, AND PERFORM the following:

PLACE CONTROL ROD DRIVE PUMP 3B

$1 CONTROL TRANS SWITCH, 3-XS-85-2, in EMERG.

0 PLACE CONTROL ROD DRIVE PUMP 3B EMER HAND SWITCH, 3-HS-085-0002C, in TRIP. op 0

RHR PUMP 3A will be started by Section 3.0 of this Attachment. For confirmation purposes the switch in Step I .0[5.9.21 is realigned by another step in the procedure PROCEED TO Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

PLACE RHR PUMP 3A TRANSFER, 343-074-0005, in EMERG. op PLACE RHR PUMP 3A, 3-HS-074-0005C, in TRIP. 0?

BFN Control Building Fire EL 593 Through 0-SSI-16 UnitO EL617 Rev 0032 Page 213 of 246 Attachment 6 (Page 5 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 3B, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA (continued)

PROCEED TO Compt 9, 3-BKR-21 1-03EA1009 EMER FDR BKR 1838 FROM DIESEL GEN 3A, AND PERFORM the following:

PLACE BKR 1838 EMER APP R ISOL SEL SWITCH (43AR), 3-43BU-21 I -O3EA/09, in EMER 51JL PLACE BREAKER CONTROL TRANSFER SWITCH 43, 343-21 1-O3EA/09, in EMERG. Of PLACE DG 3A CONTROL SWITCH, 3-HS-082-003A/1 B, in START.

L351 PLACE SYNCHRONIZING SWITCH 25, 3-25-21 1-O3EA/09B, in ON. 0 WHEN INCOMING VOLTMETER on the SYNCHRONIZING PANEL indicates greater than 3950 volts, THEN PLACE BREAKER CONTROL SWITCH, 3-HS-21 1-O3EAIO9B, in CLOSE. cm

[) PLACE SYNCHRONIZING SWITCH 25, 3-25-21 1-O3ENO9B, in OFF. 92 D

01 PROCEED TO 250V Reactor MOV Board 3B.

BFN Control Building Fire EL 593 Through 0-SSI-16 UnitO EL617 Rev. 0032 Page 214 of 246 Attachment 6 (Page 6 of 12)

Operator 6 Manual Actions INITIALS 1.0 ALIGN 480V RMOV BOARD 38, 250V RMOV BOARD 3B AND 4KV SHUTDOWN BOARD 3EA (continued)

PERFORM the following to align 250V Reactor MOV Board 3B:

PROCEED TO Compt 5B, AND PERFORM the following:

PLACE RCIC STM LINE EMER TRANS SWITCH,

) 3-XS-071 -0003, in EMERG.

V1 VERIFY OPEN RCIC TURB STM LINE OUTBD ISOL VALVE EMER HAND SWITCH, 3-HS-071-0003C.

Op PROCEED TO Compt 5D, AND PERFORM the following:

PLACE RCIC PUMP MIN FLOW VALVE EMER TRANS SWITCH, 3-XS-071-0034 in EMERG. Op (1j3 VERIFY CLOSED RCIC PUMP MIN FLOW VALVE EMER HAND SWITCH, 3-HS-071-0034C. op NOTIFY Unit 3 Unit Supervisor of completion of this section.

[9 PROCEED to 480V Reactor MOV Board 3B in preparation of performing Section 2.0.

BFN Control Building Fire EL 593 Through 0-SSI-16 UnitO EL617 Rev. 0032 Page 215 of 246 Attachment 6 (Page 7 of 12)

Operator 6 Manual Actions INITIALS 2.0 ALIGN 480V REACTOR MOV BOARD 3B

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

(20 Mm)

[21 PERFORM the following to align 480V Reactor MOV Board 3B:

[2.1] PROCEED TO Compt 2A, AND PLACE NORMAL FEEDER CONTROL SWITCH, 3-HS-268B/2A-A, in TRIP.

12.2] PROCEED TO Compt 16A, AND PLACE EMERGENCY FEEDER CONTROL SWITCH, 3-HS-268-BII6A-A, in CLOSE.

[2.3] PROCEED TO Compt IC, AND PERFORM the following:

[2.3.1] PLACE RCIC STM LINE EMER TRANS SWITCH 3-XS-071-0002, in EMERG.

[2.3.2] VERIFY OPEN RCIC STM LINE INBD ISOL VALVE, 3-HS-071 -0002B.

[2.4] PROCEED TO Compt 4C, AND PLACE 0-BKR-.084-0016A CONTAINMENT ATMOSPHERE DILUTION SYSTEM B HEATER, breaker in OFF.

[3] NOTIFY Unit 3 Unit Supervisor of completion of this section.

[4] PROCEED TO 4160V Shutdown Board 3EA in preparation of performing Section 3.0.

BFN Control Building Fire EL 593 Through O-SSI-16 Unit 0 EL 617 Rev. 0032 Page 216 of 246 Attachment 6 (Page 8 of 12)

Operator 6 Manual Actions INITIALS 3.0 RHR PUMP 3A LOCAL START

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

NOTE If RHR pump fails to start, pushbutton on breaker must be used.

(120 Mm)

[2] PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.1] PLACE RHR PUMP 3A TRANSFER, 3-43-074-0005, in EMERG.

[2.2] PLACE RHR PUMP 3A, 3-HS-074-0005C, in CLOSE.

[2.3] VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

[3] NOTIFY Unit 3 Unit Supervisor of completion of this section.

[4] PROCEED TO 4160V Shutdown Board A in preparation of performing Section 4.0.

BFN Control Building Fire EL 593 Through 0-SSI-16 Unit 0 EL 617 Rev. 0032 Page 217 of 246 Attachment 6 (Page 9 of 12)

Operator 6 Manual Actions INITIALS 4.0 START RHRSW PUMP Al AND ELECTRIC BOARD ROOM AHU IA

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

(120 Mm)

[2] PROCEED TO 4160V Shutdown Board A, Compt 10, 0-BKR-023-0001 RHRSW PUMP Al, AND PERFORM the following:

[2.11 PLACE RHRSW PUMP Al EMER/NORM CONT TRANS SWITCH, 0-43-023-0001, in EMERG.

[2.2] PLACE RHRSW PUMP Al MOTOR, 0-HS-023-000IC, in CLOSE.

[2.3] VERIFY RHRSW Pump IA has started by observing breaker AMMETER indication.

(240 Mm)

[3] PERFORM the following to start ELEC BD RM AHU IA:

[3.1] PROCEED TO I-LPNL-925-8613, AND PLACE APPX R AHU IA CONT XFER SW, 1-XSW-031-2300, in EMER.

[3.2] PROCEED TO I-LPNL-925-0539, AND PERFORM the following:

[3.2.1] PLACE ELEC BD RM AHU IA REMOTE? LOCAL XFER SWITCH, I-XS-031-2300, in LOCAL.

[3.2.2] PLACE ELEC BD RM AHU IA LOCAL CONTROL SWITCH, 1-HS-031-2300A, in START and RETURN to NORMAL.

[4] NOTIFY Unit 3 Unit Supervisor of completion of this section.

[5] PROCEED TO 480V Reactor MOV Board 3B in preparation of performing Section 5.0.

BFN Control Building Fire EL 593 Through 0-SSI-16 Unit 0 EL 617 Rev. 0032 Page 218 of 246 Attachment 6 (Page 10 of 12)

Operator 6 Manual Actions INITIALS 5.0 SHED LOADS FROM 480V REACTOR MOV BOARD 3B

[1] Notification has been received from the Unit 3 Unit Supervisor to perform this section.

(180 Mm)

[2] PROCEED TO 480V Reactor MOV Board 3B, AND PLACE the following breakers in OFF:

A. Compt IA, 3-BKR-077-000IB, DRYWELL FLOOR DRAIN SUMP PUMP 3B B. Compt 1B, REACTOR BLDG FLOOR DRAIN SUMP PUMP 3B C. Compt 4A, 3-BKR-070-0088 DRYWELL BLOWER 3B-3 D. Compt 5CI, RPS ALTERNATE POWER TRANSFORMER TRP-3 E. Compt 6C1, 0-BKR-251-0000B 48V ANNUNCIATOR BATTERY CHGR B F. Compt 8B, 3-BKR-064-0073 CORE SPRAY NE ROOM COOLER FAN G. Compt 9A, 3-BKR-063-0005B SLC PUMP 3B TRACE HEAT AND MOTOR HEATER H. Compt 11 C, 3-BKR-069-0060/A PRI ISOL BKR FD CMPT IIB RWCU DEMIN HLD PMP 3B I. Compt 13C1, 3-BKR-247-LS-300 REACTOR BLDG EMER LTG XFMR I PHASE 480 TO 520-236/1 18V J. Compt 13C2, 0-BKR-031-7213 CREVS FILTRATION UNIT B K. Compt 14C1, 3-BKR-099-0003B PRI ISOL BKR FEEDING COMPT 14C2 RPS MG SET 3B L. Compt I 5A, 3-BKR-070-0089 DRYWELL BLOWER 3B-4

BFN Control Building Fire EL 593 Through 0-SSI-16 Unit 0 EL 617 Rev. 0032 Page 219 of 246 Attachment 6 (Page 11 of 12)

Operator 6 Manual Actions INITIALS 5.0 SHED LOADS FROM 480V REACTOR MOV BOARD 3B (continued)

M. Compt 17A, 3-BKR-031 -01 39 UNIT 3 CONTROL BAY SUPPLY FAN 3B N. Compt 17D, 3-BKR-268-003B/17D UNIT PREFERRED TRANSFORMER TUP3

0. Compt 18A, DRYWELL EQUIPMENT DRAIN SUMP PUMP 3B P. Compt 18B, REACTOR BUILDING EQUIPMENT DRAIN SUMPPUMP3B Q. Compt 18E, 3-BKR-047-003B118E TURB BRG LIFT PUMPS 7&1O, 8&9 R. Compt R9A, 3-BKR-031-0651 SDBR CHILLER 3A-2 S. Compt R9B-1, 3-BKR-031 -0667 SDBR CHILLER 3B-2 T. Compt R9B-2, 3-BKR-031 -0608 DIVISION II DUCT HEATERS SHUTDOWN BOARD ROOMS UNIT 3 U. Compt R9C, 3-BKR-031 -0645 CHILLED WATER CIRC PUMP 3A-2 SHUTDOWN BOARD ROOMS UNIT 3 V. Compt R9D, 3-BKR-031 -0661 CHILLED WATER CIRC PUMP 3B-2 SHUTDOWN BOARD ROOMS UNIT 3 W. Compt R9E, 3-BKR-031-061 I AIR HANDLING UNIT 3A-2 SHUTDOWN BOARD ROOMS UNIT 3 X. Compt R9F, 3-BKR-031-0612 AIR HANDLING UNIT 3B-2 SHUTDOWN BOARD ROOMS UNIT 3

BFN Control Building Fire EL 593 Through O-SSI-16 Unit 0 EL 617 Rev. 0032 Page 220 of 246 Attachment 6 (Page 12 of 12)

Operator 6 Manual Actions INITIALS 5.0 SHED LOADS FROM 480V REACTOR MOV BOARD 3B (continued)

[3] NOTIFY Unit 3 Unit Supervisor of completion of this attachment.

NAME (Print) INITIALS Performed by:

Reviewed by:

US Date

ML14154A369

Text

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

1.0 INTRODUCTION

2.0 REFERENCES

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