ML102520174
| ML102520174 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/16/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/10-301, 50-260/10-301, 50-296/10-301 50-259/10-301, 50-260/10-301, 50-296/10-301 | |
| Download: ML102520174 (170) | |
Text
JPM NO. 127 REV. NO. 13 PAGE 1 OF 15 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 127tcap TASK NUMBER: U-047-AL-11 TASK TITLE: Respond to a Reactor Building Fire at elevation 519 through 565 west of column line R11 K/A NUMBER: 600000 AA2.16 K/A RATING: RO 3.0 SRO: 3.5 TASK STANDARD: Simulate performing designated steps of an SSI as directed by the Unit 2 Unit Supervisor and 0-SSI-2-1.
LOCATION OF PERFORMANCE: PLANT REFERENCES/PROCEDURES NEEDED: 0-SSI-2-1, Attachment 2 OPERATOR 2 Manual Actions VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: 40 minutes (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: Time allowed is 20 minutes for section 1.0 and 20 minutes for section 2.0 Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are an Operator. Unit 2 was at 60% power and Unit 1 and 3 at 100% power. Due to a fire in the Unit 2 reactor building the SSIs have been entered. You have a hand-held radio.
INITIATING CUES: The Unit Supervisor directs you to perform the actions of 0-SSI-2-1, , Operator 2 Manual Actions.
Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 127 REV. NO. 13 PAGE 3 OF 15 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. SELF CHECKING 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. Observe ALL plant radiological and safety precautions. 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 "That's correct" (or That's 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 was at 60% power and Unit 1 and 3 at 100% power. Due to a fire in the Unit 2 reactor building the SSIs have been entered. You have a hand-held radio.
INITIATING CUES: The Unit Supervisor directs you to perform the actions of 0-SSI-2-1, , Operator 2 Manual Actions.
Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 127 REV. NO. 13 PAGE 4 OF 15 START TIME Performance Step 1: Critical X Not Critical _
ATTACHMENT 2 OPERATOR 2 MANUAL ACTIONS 1.0 4KV SHUTDOWN BOARD D ALIGNMENT (20 Min) 1 PROCEED to Electric Board Room 2B and Perform the following to align 4KV Shutdown Board D:
1.1 PROCEED to Compartment 5, 0-BKR-211-000D/005 BKR 1618 ALT SUPPLY TO 4KV S/D BD D FROM S/D BUS 1 AND PERFORM the following:
1.1.1 PLACE the BREAKER CONTROL TRANSFER SWITCH 43, 0-43-211-000D/05, in EMERG.
1.1.2 PLACE the BREAKER CONTROL SWITCH, 0-HS-211-000D/05B in TRIP.
Standard:
At Compartment 5, simulated placing transfer switch 43 to EMERG position and simulated placing the breaker control switch in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: The 43 Switch is in Emergency. If breaker was originally closed, the breaker is open the indicating lights are Red light OFF and Green light ON.
[Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 5 OF 15 Performance Step 2: Critical X Not Critical _
1.2 PROCEED to Compartment 13, 0-BKR-211-000D/013 NORM SUPPLY TO TRANSFORMER TDB TO 480V D/G AUX BD B, AND PERFORM the following:
1.2.1 PLACE BREAKER CONTROL SWITCH 0-HS-211-000D/013 in TRIP.
Standard:
At Compartment 13, simulated placing 0-HS-211-000D/013 in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: If breaker was originally closed, the breaker is open the indicating lights are Red light OFF and Green light ON. [Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 6 OF 15 Performance Step 3: Critical X Not Critical _
1.3 PROCEED to Compartment 16, 1-BKR-074-0039 RESIDUAL HEAT REMOVAL PUMP 1D AND PERFORM the following:
1.3.1 PLACE RHR PUMP 1D TRANSFER 1-43-074-0039 in EMERG.
1.3.2 PLACE RHR PUMP 1D, 2-HS-074-0039C in TRIP.
Standard:
At Compartment 16, simulated placing switch, 1-43-074 0039 in EMERG and simulated placing breaker control switch, 0-HS-074-0039C in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: The Transfer Switch is in Emergency. If breaker was originally closed, the breaker is open the indicating lights are Red light OFF and Green light ON.
[Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 7 OF 15 Performance Step 4: Critical X Not Critical _
NOTE RESIDUAL HEAT REMOVAL PUMP 2D will be started from Main Control Room for LPCI injection to reactor at 120 minutes. For "confirmation" purposes the switches in Steps 1.0[1.4.1] and 1.0[1.4.2] are realigned by Section 2.0 of this Attachment.
1.4 PROCEED to Compartment 17, 2-BKR-074-0039 RESIDUAL HEAT REMOVAL PUMP 2D AND PERFORM the following:
1.4.1 PLACE RHR PUMP D BREAKER CONTROL TRANSFER SWITCH 43, 2-43-074-0039 in EMERG.
1.4.2 PLACE RHR PUMP 2D, 1-HS-74-39C in TRIP.
Standard:
At Compartment 17, simulated placing switch 2-43-074-0039 in EMERG and simulated placing 2-HS-74-39C in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: The Transfer Switch is in Emergency. If breaker was originally closed, the breaker is open the indicating lights are Red light OFF and Green light ON.
[Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 8 OF 15 Performance Step 5: Critical X Not Critical _
1.5 PROCEED to Compartment 20, 0-BKR-211-000D/020 BKR 1816 TO 4KV S/D BD D FROM DG 1D AND PERFORM the following:
1.5.1 PLACE BKR 1816 EMER APP R ISOL SEL SWITCH (43AR),
0-43BU-211-000D/20, in EMER.
1.5.2 PLACE BREAKER CONTROL TRANSFER SWITCH 43, 0-43-211-000D/20 in EMERG.
1.5.3 PLACE BREAKER CONTROL SWITCH, 0-HS-211-000D/20B in TRIP.
Standard:
At Compartment 20, simulated placing switch 43AR in EMER, simulated placing switch 43 in EMERG and simulated placing breaker control switch in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: The 43AR Switch is in Emergency. The 43 Switch is in Emergency.
If breaker was originally closed, the breaker is open the indicating lights are Red light OFF and Green light ON.
[Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 9 OF 15 Performance Step 6: Critical X Not Critical _
1.6 PROCEED to Compartment 22, 0-BKR-211-000D/022 BKR 1724 NORM SUPPLY TO 4KV S/D BD D FROM S/D BUS 2 AND PERFORM the following:
1.6.1 PLACE BKR 1724 EMER APP R ISOL SEL SWITCH (43AR) 0-43BU-211-000D/22, in EMER.
1.6.2 PLACE BREAKER CONTROL TRANSFER SWITCH 43, 0-43-211-000D2/22, in EMERG.
1.6.3 PLACE BREAKER CONTROL SWITCH, 0-HS-211-000D/22B, in TRIP.
Standard:
At Compartment 22, simulated placing Switch 43AR in EMER, simulated placing Switch 43 in EMERG and simulated placing breaker control switch in TRIP.
SAT UNSAT N/A COMMENTS:
CUE: The 43AR Switch is in Emergency. The 43 Switch is in Emergency.
If breaker was originally closed, the breaker is open the indicating lights are Red light OFF, Green light ON. [Otherwise], the breaker is tripped.
JPM NO. 127 REV. NO. 13 PAGE 10 OF 15 Performance Step 7: Critical X Not Critical NOTE Synchronizing switch handle is located in box by door.
1.7 PROCEED to Compartment 6, 0-BKR -211-000D/006 BKR 1826 TO 4KV S/D BD D FROM 4KV S/D BOARD 3ED AND PERFORM the following:
1.7.1 PLACE BKR 1826 EMER APP R ISOL SEL SWITCH (43AR),
0-43BU-211-000D/006, in EMER.
1.7.2 PLACE BREAKER CONTROL TRANSFER SWITCH 43, 0-43-211-000D/06, in EMERG.
Standard:
At Compartment 6, simulated placing Switch 43AR in EMER and Switch 43 in EMERG.
SAT UNSAT N/A COMMENTS:
CUE: The 43AR Switch is in Emergency. The 43 Switch is in Emergency.
JPM NO. 127 REV. NO. 13 PAGE 11 OF 15 Performance Step 8: Critical X Not Critical 1.7.3 PLACE SYNCHRONIZING SWITCH 25-826, 0-25-211-000D/06B, in ON.
1.7.4 WHEN Synchronizing Panel INCOMING VOLTMETER indicates greater than 3950 volts, THEN PLACE BREAKER CONTROL SWITCH, 0-HS-211-000D/06B, in CLOSE.
1.7.5 PLACE SYNCHRONIZING SWITCH 25-826, 0-25-211-000D/06B, in OFF.
Standard:
Simulated placing Switch 25-826 in ON, verified incoming volts greater than 3950 volts.
Simulated placing the Breaker Control Switch in CLOSE. Simulated placing Switch 25-826 in OFF.
SAT UNSAT N/A COMMENTS:
CUE: Switch 25-826 in ON Shutdown Board Voltage is 4210 volts The breaker CLOSED and the indicating lamp changed from green to red.
Switch 25-826 in OFF
JPM NO. 127 REV. NO. 13 PAGE 12 OF 15 Performance Step 9: Critical Not Critical X 2 NOTIFY Unit 2 Unit Supervisor upon completion of this section.
3 REMAIN AT 4KV Shutdown Board D to perform Section 2.0 of this instruction.
Standard:
Simulated notifying Unit 2 Unit Supervisor of completion of 0-SSI-2-1, ATTACHMENT 2, SECTION 1.
SAT UNSAT N/A COMMENTS:
CUE: The Unit 2 Unit Supervisor directs you to complete attachment 2, section 2 RHR Pump 2D start.
INSTRUCTOR'S NOTE:
ENTER THE TIME SECTION 1.0 WAS COMPLETED HERE .
JPM NO. 127 REV. NO. 13 PAGE 13 OF 15 Performance Step 10: Critical Not Critical X 2.0 RHR PUMP 2D START (20 Min) 1 Notification has been received from the Unit 2 Unit Supervisor to perform this section.
NOTE If RHR pump fails to start, pushbutton on breaker must be used.
2 PROCEED TO 4KV Shutdown Board D Compt 17, 2-BKR-074-0039 RESIDUAL HEAT REMOVAL PUMP 2D, AND PERFORM the following:
2.1 PLACE RHR PUMP 2D BREAKER CONTROL TRANSFER SWITCH, 2-43-074-0039, in EMERG.
Standard:
Verifies that RHR Pump 2D Transfer Switch is in EMERG.
SAT UNSAT N/A COMMENTS:
CUE: Switch is still in Emergency from previous step 1.4. 2-43-074-0039 is in EMERGENCY.
JPM NO. 127 REV. NO. 13 PAGE 14 OF 15 Performance Step 11: Critical X Not Critical 2.2 PLACE RHR PUMP 2D, 2-HS-74-39C, in CLOSE.
Standard:
Simulated placing 2-HS-74-39C in CLOSE.
SAT UNSAT N/A COMMENTS:
CUE: There was NO noise of breaker closing and the green light is ON.
Performance Step 12: Critical X Not Critical DEPRESS MANUAL BREAKER CLOSE pushbutton.
Standard:
Simulated depressing MANUAL BREAKER CLOSE pushbutton.
SAT UNSAT N/A COMMENTS:
CUE: The THUD of the breaker closing was heard and the red light is ON and when amps are checked amps pegged high and now are indicating.
JPM NO. 127 REV. NO. 13 PAGE 15 OF 15 Performance Step 13: Critical Not Critical X 2.3 VERIFY RHR Pump 2D has started by Observing Breaker ammeter indication.
3 NOTIFY Unit 2 Unit Supervisor of the completion of this section.
4 PROCEED TO Intake Pumping Station in preparation of performing Section 3.0.
Standard:
Verifies ammeter reading and informs Unit supervisor that RHR Pump 2D is running.
SAT UNSAT N/A COMMENTS:
CUE: When operator reads the ammeter the reading is 80 amps.
Acknowledge operation of RHR Pump 2D when US contacted.
Another operator is completing section 3.0.
INSTRUCTOR'S NOTE:
ENTER THE TIME STEP 3.3 WAS COMPLETED HERE .
END OF TASK STOP TIME
JPM NO. 202 REV. NO. 0 PAGE 1 OF 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 202 TASK NUMBER: U-003-NO-04 TASK TITLE: Place a Second/Third RFPT in Service K/A NUMBER: 259001 A4.02 K/A RATING: RO 3.9 SRO: 3.7 TASK STANDARD: Places the Third RFPT in Service.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-OI-3 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are the Unit Operator at the controls. RFPT 2A is warmed and ready to be placed in service. Precautions and limitations have been reviewed. Radiation Protection has been notified that an RPHP is in effect for the impending action to place RFPT 2A in service.
Time of notification has been recorded in the NOMS Narrative Log. Appropriate data and signatures have been recorded on Appendix A.
INITIATING CUES: The Unit Supervisor directs you to place RFPT 2A in service and in automatic level control per 2-OI-3 Reactor Feedwater System section 5.7.
JPM NO. 202 REV. NO. 0 PAGE 3 OF 12 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the Unit Operator at the controls. RFPT 2A is warmed and ready to be placed in service. Precautions and limitations have been reviewed. Radiation Protection has been notified that an RPHP is in effect for the impending action to place RFPT 2A in service.
Time of notification has been recorded in the NOMS Narrative Log. Appropriate data and signatures have been recorded on Appendix A.
INITIATING CUES: The Unit Supervisor directs you to place RFPT 2A in service and in automatic level control per 2-OI-3 Reactor Feedwater System section 5.7.
JPM NO. 202 REV. NO. 0 PAGE 4 OF 12 START TIME Performance Step 1: Critical Not Critical _X 5.7 Placing the Second and Third RFP/RFPT In Service CAUTIONS
- 1) FAILURE to monitor SJAE/OG CNDR CNDS FLOW, 2-FI-2-42, on Panel 2-9-6 for proper flow (between 2 x 106 and 3 x 106 lbm/hr) may result in SJAE isolation.
- 2) Changes in Condensate System flow may require adjustment to SPE CNDS BYPASS, 2-FCV-002-0190.
NOTE Placing RFP 2A(2B)(2C) MIN FLOW VALVE, 2-HS-3-20(13)(6), in OPEN position will lock it open, preventing minimum flow valve oscillations at low flow.
[1] BEFORE placing a RFPT in service:
[1.1] NOTIFY Radiation Protection that an RPHP is in effect for the impending action to place RFPT 2A in service. RECORD time Radiation Protection notified in NOMS Narrative Log
[1.2] VERIFY appropriate data and signatures recorded on Appendix A per Appendix A instructions
[2] IF RFP/RFPT is NOT warmed, reset and rolling, THEN PERFORM the following: (Otherwise N/A)
Standard:
Given in initial conditions that step 1 and 2 are complete.
SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 5 OF 12 Performance Step 2: Critical X Not Critical _
[3] VERIFY RFP 2A MIN FLOW VALVE, 2-HS-3-20, in OPEN position.
- CHECK OPEN MIN FLOW VALVE, 2-FCV-3-20.
Standard:
Places RFP 2A MIN FLOW VALVE, 2-HS-3-20, in OPEN SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical Not Critical _X
[4] SLOWLY RAISE speed of RFPT using RFPT 2A SPEED CONT RAISE/LOWER, 2-HS-46-8A, to establish flow and maintain level in vessel.
[5] WHEN RFPT discharge pressure is within 250 psig of reactor pressure, THEN VERIFY OPEN RFP 2A DISCHARGE VALVE, 2-FCV-3-19.
Standard:
Raises RFPT speed and verifies discharge valve open SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 6 OF 12 Performance Step 4: Critical X Not Critical _
[6] SLOWLY RAISE RFPT speed using RFPT 2A SPEED CONT RAISE/LOWER switch, 2-HS-46-8A, to slowly raise RFP discharge pressure and flow on the following indications (Panel 2-9-6):
Raises RFPT speed and commences injection to the Reactor SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[7] WHEN sufficient flow is established to maintain RFP 2A MIN FLOW VALVE, 2-FCV-3-20, in CLOSED position (approximately 2 x 106 lbm/hr),
THEN PLACE RFP 2A MIN FLOW VALVE, 2-HS-3-20, in AUTO.
Standard:
Places RFP 2A MIN FLOW VALVE in AUTO SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 7 OF 12 Performance Step 6: Critical Not Critical X
[8] OBSERVE lowering in speed and discharge flows of other operating RFPs.
Standard:
Raises injection flow of RFPT 2A and monitors feedwater flow of other operating feed pumps.
SAT UNSAT N/A COMMENTS:
Performance Step 7: Critical X Not Critical
[9] PULL RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch, 2-HS-46-8A(9A)(10A), to FEEDWATER CONTROL position.
- CHECK amber light at switch extinguished.
Standard:
Pulls up on 2-HS-46-8A, verifies amber light extinguishes SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 8 OF 12 Performance Step 8: Critical X Not Critical
[10] PERFORM the following on RFPT 2A(2B)(2C) SPEED CONTROL (PDS),
2-SIC-46-8(9)(10) (Panel 2-9-5):
[10.1] SELECT Column 3.
[10.2] VERIFY PDS in MANUAL.
Standard:
Verifies column 3 selected.
SAT UNSAT N/A COMMENTS:
Performance Step 9: Critical Not Critical X
[11] VERIFY REACTOR WATER LEVEL CONTROL (PDS), 2-LIC-46-5 functioning properly and ready to control second or third RFP.
[12] SLOWLY RAISE RFP speed.
- CHECK discharge flow and discharge pressure rise.
Standard:
Raises speed of RFPT SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 9 OF 12 Performance Step 10: Critical X Not Critical
[13] WHEN RFP speed is approximately equal to operating RFP(s) speed, THEN on RFPT 2A(2B)(2C) SPEED CONTROL (PDS), 2-SIC-46-8(90(10):
[13.1] PLACE PDS in AUTO.
[13.2] VERIFY Column 3 selected.
Standard:
Places PDS in Auto SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 10 OF 12 Performance Step 11: Critical Not Critical X
[14] WHEN RFP is in automatic mode on REACTOR WATER LEVEL CONTROL, (PDS) 2-LIC-46-5, THEN CLOSE the following valves:
Standard:
Closes the above listed valves and contacts AUO to verify the last two valves.
SAT UNSAT N/A COMMENTS:
CUE: RFPT A HP STEAM SHUTOFF ABOVE SEAT DRAIN is closed RFPT A LP STEAM SHUTOFF ABOVE SEAT DRAIN is closed
JPM NO. 202 REV. NO. 0 PAGE 11 OF 12 Performance Step 12: Critical Not Critical X
[15] VERIFY CLOSED the following valves on first RFP started in Section 5.5:
Standard:
Verifies closed the above listed valves and contacts AUO to verify the last valves.
SAT UNSAT N/A COMMENTS:
CUE: RFPT B, C LP STEAM SHUTOFF ABOVE SEAT DRAIN are closed
JPM NO. 202 REV. NO. 0 PAGE 12 OF 12 Performance Step 13: Critical Not Critical X
[16] VERIFY both RFPT Main Oil Pumps running.
[17] IF desired to stop Turning Gear for in service RFPT, THEN PLACE appropriate handswitch in STOP and RETURN to AUTO:
- RFPT 2A TURNING GEAR MOTOR, 2-HS-3-101A
[18] REFER TO Section 6.0.
- CONTROL and MONITOR RFW system operation.
Standard:
Verifies both RFPT Main Lube Oil Pumps running, step 14 is NA and verifies proper operation of RFW system.
SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 202 REV. NO. 0 PAGE 1 OF 11 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 202 TASK NUMBER: U-003-NO-04 TASK TITLE: Place a Second/Third RFPT in Service K/A NUMBER: 259001 A4.02 K/A RATING: RO 3.9 SRO: 3.7 TASK STANDARD: Places the Third RFPT in Service.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-OI-3 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are the Unit Operator at the controls. RFPT 3A is warmed and ready to be placed in service. Precautions and limitations have been reviewed. Radiation Protection has been notified that an RPHP is in effect for the impending action to place RFPT 3A in service.
Time of notification has been recorded in the NOMS Narrative Log. Appropriate data and signatures have been recorded on Appendix A.
INITIATING CUES: The Unit Supervisor directs you to place RFPT 3A in service and in automatic level control per 3-OI-3 Reactor Feedwater System section 5.7.
JPM NO. 202 REV. NO. 0 PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the Unit Operator at the controls. RFPT 3A is warmed and ready to be placed in service. Precautions and limitations have been reviewed. Radiation Protection has been notified that an RPHP is in effect for the impending action to place RFPT 3A in service.
Time of notification has been recorded in the NOMS Narrative Log. Appropriate data and signatures have been recorded on Appendix A.
INITIATING CUES: The Unit Supervisor directs you to place RFPT 3A in service and in automatic level control per 3-OI-3 Reactor Feedwater System section 5.7.
JPM NO. 202 REV. NO. 0 PAGE 4 OF 11 START TIME Performance Step 1: Critical Not Critical _X 5.7 Placing the Second and Third RFP/RFPT In Service 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 lbm/hr) may result in SJAE isolation.
- 2) Changes in Condensate System flow may require adjustment to SPE CNDS BYPASS, 3-FCV-002-0190.
NOTE Placing RFP 3A(3B)(3C) MIN FLOW VALVE, 3-HS-3-20(13)(6), in OPEN position will lock it open, preventing minimum flow valve oscillations at low flow.
[1] BEFORE placing a RFPT in service:
[1.1] NOTIFY Radiation Protection that an RPHP is in effect for the impending action to place RFPT 3A in service. RECORD time Radiation Protection notified in NOMS Narrative Log
[1.2] VERIFY appropriate data and signatures recorded on Appendix A per Appendix A instructions
[2] IF RFP/RFPT is NOT warmed, reset and rolling, THEN PERFORM the following: (Otherwise N/A)
Standard:
Given in initial conditions that step 1 and 2 are complete.
SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 5 OF 11 Performance Step 2: Critical X Not Critical _
[3] VERIFY RFP 3A MIN FLOW VALVE, 3-HS-3-20, in OPEN position.
- CHECK OPEN MIN FLOW VALVE, 3-FCV-3-20.
Standard:
Places RFP 3A MIN FLOW VALVE, 3-HS-3-20, in OPEN SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical Not Critical _X
[4] SLOWLY RAISE speed of RFPT using RFPT 3A SPEED CONT RAISE/LOWER, 3-HS-46-8A, to establish flow and maintain level in vessel.
[5] WHEN RFPT discharge pressure is within 250 psig of reactor pressure, THEN VERIFY OPEN RFP 3A DISCHARGE VALVE, 3-FCV-3-19.
Standard:
Raises RFPT speed and verifies discharge valve open SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 6 OF 11 Performance Step 4: Critical X Not Critical _
[6] SLOWLY RAISE RFPT speed using RFPT 3A SPEED CONT RAISE/LOWER switch, 3-HS-46-8A, to slowly raise RFP discharge pressure and flow on the following indications (Panel 3-9-6):
Raises RFPT speed and commences injection to the Reactor SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[7] WHEN sufficient flow is established to maintain RFP 3A MIN FLOW VALVE, 3-FCV-3-20, in CLOSED position (approximately 2 x 106 lbm/hr),
THEN PLACE RFP 3A MIN FLOW VALVE, 3-HS-3-20, in AUTO.
Standard:
Places RFP 3A MIN FLOW VALVE in AUTO SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 7 OF 11 Performance Step 6: Critical Not Critical _X
[8] OBSERVE lowering in speed and discharge flows of other operating RFPs.
Standard:
Raises injection flow of RFPT 3A and monitors feedwater flow of other operating feed pumps.
SAT UNSAT N/A COMMENTS:
Performance Step 7: *Critical X Not Critical
[9] IF transferring RFPT from MANUAL GOVERNOR to individual RFPT Speed Control PDS, THEN PERFORM the following: (Otherwise N/A)
[9.2] VERIFY amber light at switch extinguished above RFPT 3A SPEED CONT RAISE/LOWER switch, 3-HS-46-8A.
3-SIC-46-8 (Panel 3-9-5):
[9.3.1] SELECT Column 3.
[9.3.2] VERIFY PDS in MANUAL.
Standard:
Pulls up on 3-HS-46-8A, verifies amber light extinguishes, selects column 3 and verifies in manual.
SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 8 OF 11 Performance Step 8: *Critical X Not Critical
[10] IF transferring control of RFPT from individual RFPT Speed Control PDS to AUTO control using REACTOR WATER LEVEL CONTROL PDS, 3-LIC-46-5, THEN PERFORM the following: (Otherwise N/A)
[10.1] VERIFY REACTOR WATER LEVEL CONTROL (PDS),
3-LIC- 46-5 is functioning properly and ready to control second or third RFP.
- [10.3] WHEN RFP speed is approximately equal to operating RFP(s) speed, THEN PERFORM the following on RFPT 3A SPEED CONTROL (PDS), 3-SIC-46-8:
[10.3.1] PLACE PDS in AUTO.
[10.3.2] VERIFY Column 3 selected.
Standard:
Raises RFP discharge flow and pressure, places PDS in auto and verifies column 3 selected.
SAT UNSAT N/A COMMENTS:
JPM NO. 202 REV. NO. 0 PAGE 9 OF 11 Performance Step 9: Critical Not Critical X
[11] WHEN RFP in automatic mode on REACTOR WATER LEVEL CONTROL, (PDS) 3-LIC-46-5, THEN CLOSE the following valves:
Standard:
Closes the above listed valves and contacts AUO to verify the last two valves.
SAT UNSAT N/A COMMENTS:
CUE: RFPT A HP STEAM SHUTOFF ABOVE SEAT DRAIN is closed RFPT A LP STEAM SHUTOFF ABOVE SEAT DRAIN is closed
JPM NO. 202 REV. NO. 0 PAGE 10 OF 11 Performance Step 10: Critical Not Critical X
[12] VERIFY CLOSED the following valves on first RFP started in Section 5.5:
Standard:
Verifies closed the above listed valves and contacts AUO to verify the last valves.
SAT UNSAT N/A COMMENTS:
CUE: RFPT B, C LP STEAM SHUTOFF ABOVE SEAT DRAIN are closed
JPM NO. 202 REV. NO. 0 PAGE 11 OF 11 Performance Step 11: Critical Not Critical X
[13] VERIFY both RFPT Main Oil Pumps running.
[14] IF desired to stop Turning Gear for in service RFPT, THEN PLACE appropriate handswitch in STOP and RETURN to AUTO:
- RFPT 3A TURNING GEAR MOTOR, 3-HS-3-101A
[15] REFER TO Section 6.0.
- CONTROL and MONITOR RFW system operation.
Standard:
Verifies both RFPT Main Lube Oil Pumps running, step 14 is NA and verifies proper operation of RFW system.
SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 203 REV. NO. 0 PAGE 1 OF 9 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 203 TASK NUMBER: U-001-NO-08 TASK TITLE: Close MSIVs During Power Operations K/A NUMBER: 239001 A4.01 K/A RATING: RO 4.2 SRO: 4.0 TASK STANDARD: Closes Inboard and Outboard MSIVs on Main Steam Line C LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-OI-1 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. No MSIVs LS-3 or LS-4 is failed. Precautions and limitations have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 2-OI-1 Main Steam System section 8.2.
JPM NO. 203 REV. NO. 0 PAGE 3 OF 9 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. No MSIVs LS-3 or LS-4 is failed. Precautions and limitations have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 2-OI-1 Main Steam System section 8.2.
JPM NO. 203 REV. NO. 0 PAGE 4 OF 9 START TIME Performance Step 1: Critical Not Critical _X 8.2.3 Closing Main Steam Line C Valve(s) During Power Operations NOTES
- 1) Test stroking an MSIV to the closed position takes about 45-60 seconds.
- 2) LS-5 limit switches cause the MSIV green position indicator light to illuminate at 85% open. The LS-3 and LS-4 limit switches for the Unit 3 MISVs actuate at 90% open to initiate a reactor scram via the RPS. During MSIV testing, a half-scram initiation signal will be received before the green position indicator light illuminates.
- 3) Closing a MSIV with another main steam line MSIV closed or a failed LS-3 or LS-4 switch, may cause a half or a full reactor scram. REFER TO Illustrations 1 and 2.
- 4) Main Steam Line Flow Indication goes to the Reactor Feed Control System.
Closing and Opening a MSIV will cause a fluctuation in the Reactor Feed Water System.
[1] REVIEW all Precautions and Limitations in Section 3.0.
[2] VERIFY that ALL MSIVs are open.
[3] CHECK by administration means that no MSIVs LS-3 or LS-4 has failed (i.e.,
Narrative Logs, Caution Orders, Work Orders).
[4] IF a failed LS-3 or LS-4 for a MSIV has been determined, THEN CHECK that a Half Scram will NOT occur when the valve to be operated is closed. (REFER TO Illustrations 1 and 2, and RPS Logic prints 730E915)
[5] IF a Half Scram is expected to occur, THEN STOP and OBTAIN Unit Supervisors permission to continue in the procedure.
[6] VERIFY or LOWER Reactor Power to 66% per 2-GOI-100-12 or 2-GOI-100-12A.
Standard:
Given in initial conditions for step 3, power is less than 66%
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 5 OF 9 Performance Step 2: Critical X Not Critical _
NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.0O, 3.0P and 3.0Q should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.0X.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[7] PERFORM the following to close MSIV LINE C INBOARD MSIV:
[7.1] DEPRESS and HOLD MSIV LINE C INBOARD TEST, 2-HS-1-37B push-button until Step 8.2.3[7.3].
[7.2] WHEN MSIV LINE C INBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3[7.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C INBOARD, 2-HS-1-37A in the CLOSE position.
[7.3] RELEASE MSIV LINE C INBOARD TEST, 2-HS-1-1-37B push-button.
Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 6 OF 9 Performance Step 3: Critical X Not Critical _
NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.0O, 3.0P and 3.0Q should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.0X.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[8] PERFORM the following to close MSIV LINE C OUTBOARD MSIV:
[8.1] DEPRESS and HOLD MSIV LINE C OUTBOARD TEST, 2-HS-1-38B push-button until Step 8.2.3[8.3].
[8.2] WHEN MSIV LINE C OUTBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3[8.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C OUTBOARD, 2-HS-1-38A in the CLOSE position.
[8.3] RELEASE MSIV LINE C OUTBOARD TEST, 2-HS-1-1-38B push-button.
Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 7 OF 9 Performance Step 4: Critical X Not Critical _
NOTES
- 1) When turbine generator RPM is above 1700 and one or more MSIVs fully close, Valves 2-FCV-1-168, -169, -170, and -171 will close and Valves 2-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF, and 2-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER opens, if closed, and their handswitches are in AUTO.
- 2) When opening the 2-FCV-1-55 and 2-FCV-56, Main Steam Line Drain Valves the HWC system may isolate on LOW OFFGAS Oxygen.
[9] OPEN 2-FCV-1-55 using MN STM LINE DRAIN INBD ISOLATION VLV, 2-HS-1-55A.
Standard:
Opens drain valve 2-FCV-1-55 SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 8 OF 9 Performance Step 5: Critical X Not Critical
[10] OPEN 2-FCV-1-56 using MN STM LINE DRAIN OUTBD ISOLATION VLV, 2-HS-1-56A.
Standard:
Opens drain valve 2-FCV-1-56 SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical Not Critical X
[11] VERIFY OPEN 2-FCV-1-57 using MSIV DOWNSTREAM DRAINS SHUTOFF, 2-HS-1-57A.
[12] VERIFY OPEN 2-FCV-1-58 using UPSTREAM MSL DRAIN TO CONDENSER, 2-HS-1-58A.
[13] CHECK CLOSED valves 2-FCV-1-168, -169, -170, and -171, ON 2-PNL-9-3 as follows:
VERIFY the green indicating light ILLUMINATED and the red indicating light EXTINGUISHED for MAIN STM LINE DRAIN VALVES POSITION, 2-ZI-1-174.
Standard:
Verifies 2-FCV-1-57 and 58 are open and that 2-FCV-1-168, 169, 170, and 171 are closed.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 9 OF 9 Performance Step 7: Critical Not Critical X
[14] IF desired AND directed by the Unit Supervisor, THEN RAISE Reactor Power per 2-GOI-100-12, while maintaining the remaining steam lines below an average of 3.54 x 106 lbm/hr steam flow (approximately 80% Reactor Power), on the remaining three main steam lines.
Standard:
None, another Operator will raise power.
SAT UNSAT N/A COMMENTS:
CUE: Another Operator will raise Reactor Power END OF TASK STOP TIME
JPM NO. 203 REV. NO. 0 PAGE 1 OF 9 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 203 TASK NUMBER: U-001-NO-08 TASK TITLE: Close MSIVs During Power Operations K/A NUMBER: 239001 A4.01 K/A RATING: RO 4.2 SRO: 4.0 TASK STANDARD: Closes Inboard and Outboard MSIVs on Main Steam Line C LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-OI-1 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. No MSIVs LS-3 or LS-4 is failed. Precautions and limitations have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 3-OI-1 Main Steam System section 8.2.
JPM NO. 203 REV. NO. 0 PAGE 3 OF 9 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. No MSIVs LS-3 or LS-4 is failed. Precautions and limitations have been reviewed.
INITIATING CUES: The Unit Supervisor directs you to close both MSIVs on Main Steam Line C per 3-OI-1 Main Steam System section 8.2.
JPM NO. 203 REV. NO. 0 PAGE 4 OF 9 START TIME Performance Step 1: Critical Not Critical _X 8.2.3 Closing Main Steam Line C Valve(s) During Power Operations NOTES
- 1) Test stroking an MSIV to the closed position takes about 45-60 seconds.
- 2) LS-5 limit switches cause the MSIV green position indicator light to illuminate at 85% open. The LS-3 and LS-4 limit switches for the Unit 3 MSIVs actuate at 90% open to initiate a reactor scram via the RPS. During MSIV testing, a half-scram initiation signal will be received before the green position indicator light illuminates.
- 3) Closing a MSIV with another main steam line MSIV closed or a failed LS-3 or LS-4 switch, may cause a half or a full reactor scram. REFER TO Illustrations 1 and 2.
- 4) Main Steam Line Flow Indication goes to the Reactor Feed Control System.
Closing and Opening a MSIV will cause a fluctuation in the Reactor Feed Water System.
[1] REVIEW all Precautions and Limitations in Section 3.0.
[2] VERIFY that ALL MSIVs are open.
[3] CHECK by administration means that no MSIVs LS-3 or LS-4 has failed (i.e.,
Narrative Logs, Caution Orders, Work Orders).
[4] IF a failed LS-3 or LS-4 for a MSIV has been determined, THEN CHECK that a Half Scram will NOT occur when the valve to be operated is closed. (REFER TO Illustrations 1 and 2, and RPS Logic prints 730E915)
[5] IF a Half Scram is expected to occur, THEN STOP and OBTAIN Unit Supervisors permission to continue in the procedure.
[6] VERIFY or LOWER Reactor Power to 66% per 3-GOI-100-12 or 3-GOI-100-12A.
Standard:
Given in initial conditions for step 3, power is less than 66%
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 5 OF 9 Performance Step 2: Critical X Not Critical _
NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.0O, 3.0P and 3.0Q should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.0X.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[7] PERFORM the following to close MSIV LINE C INBOARD MSIV:
[7.1] DEPRESS and HOLD MSIV LINE C INBOARD TEST, 3-HS-1-37B push-button until Step 8.2.3[7.3].
[7.2] WHEN MSIV LINE C INBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3[7.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C INBOARD, 3-HS-1-37A in the CLOSE position.
[7.3] RELEASE MSIV LINE C INBOARD TEST, 3-HS-1-1-37B push-button.
Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 6 OF 9 Performance Step 3: Critical X Not Critical _
NOTES
- 1) To prevent a RPS Half Scram, only one set of Main Steam Line Isolation Valves (Inboard and Outboard) should be closed at a time.
- 2) Closing a MSIV may cause MSL drain valves to operate. P&L 3.0O, 3.0P and 3.0Q should be reviewed for applicability.
- 3) When a MSIV is closed at power, the potential exists for an isolation of the Hydrogen Water Chemistry System to occur. REFER TO Precaution 3.0X.
- 4) During power operations when using the test pushbutton to slow stroke the MISV closed, the MSIV is to be considered closed when either one of the following conditions are met:
- The red position indicating light on Panel 9-3 extinguishes, or
- The test pushbutton has been held for approximately 3 minutes and the steam flow in the isolated MSL is essentially zero (less than 0.4 Mlb/hr).
[8] PERFORM the following to close MSIV LINE C OUTBOARD MSIV:
[8.1] DEPRESS and HOLD MSIV LINE C OUTBOARD TEST, 3-HS-1-38B push-button until Step 8.2.3[8.3].
[8.2] WHEN MSIV LINE C OUTBOARD indicates closed OR AFTER approximately three minutes have past since Step 8.2.3[8.1] and steam flow in the isolated MSL has been verified as essentially zero, THEN
- PLACE MSIV LINE C OUTBOARD, 3-HS-1-38A in the CLOSE position.
[8.3] RELEASE MSIV LINE C OUTBOARD TEST, 3-HS-1-1-38B push-button.
Standard:
Operator depresses and holds the MSIV Line C Inboard test push button until the MSIV is closed, then places the switch to close, and then releases the test push button.
Note: if the valve goes back open after it is closed it would be a failure.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 7 OF 9 Performance Step 4: Critical X Not Critical _
NOTES
- 1) When turbine generator RPM is above 1700 and one or more MSIVs fully close, Valves 3-FCV-1-168, -169, -170, and -171 will close and Valves 3-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF, and 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER opens, if closed, and their handswitches are in AUTO.
- 2) When opening the 3-FCV-1-55 and 3-FCV-56, Main Steam Line Drain Valves the HWC system may isolate on LOW OFFGAS Oxygen.
[9] OPEN 3-FCV-1-55 using MN STM LINE DRAIN INBD ISOLATION VLV, 3-HS-1-55A.
Standard:
Opens drain valve 3-FCV-1-55 SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 8 OF 9 Performance Step 5: Critical X Not Critical
[10] OPEN 3-FCV-1-56 using MN STM LINE DRAIN OUTBD ISOLATION VLV, 3-HS-1-56A.
Standard:
Opens drain valve 3-FCV-1-56 SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical Not Critical X
[11] VERIFY OPEN 3-FCV-1-57 using MSIV DOWNSTREAM DRAINS SHUTOFF, 3-HS-1-57A.
[12] VERIFY OPEN 3-FCV-1-58 using UPSTREAM MSL DRAIN TO CONDENSER, 3-HS-1-58A.
[13] CHECK CLOSED valves 3-FCV-1-168, -169, -170, and -171, ON 3-PNL-9-3 as follows:
CHECK the green indicating light ILLUMINATED and the red indicating light EXTINGUISHED for MAIN STM LINE DRAIN VALVES POSITION, 3-ZI-1-174.
Standard:
Verifies 3-FCV-1-57 and 58 are open and that 3-FCV-1-168, 169, 170, and 171 are closed.
SAT UNSAT N/A COMMENTS:
JPM NO. 203 REV. NO. 0 PAGE 9 OF 9 Performance Step 7: Critical Not Critical X
[14] IF desired AND directed by the Unit Supervisor, THEN RAISE Reactor Power per 3-GOI-100-12, while maintaining the remaining steam lines below an average of 3.54 x 106 lbm/hr steam flow (approximately 80% Reactor Power), on the remaining three main steam lines.
Standard:
None, another Operator will raise power.
SAT UNSAT N/A COMMENTS:
CUE: Another Operator will raise Reactor Power END OF TASK STOP TIME
JPM NO. 207 REV. NO. 0 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 207 TASK NUMBER: U-92A-NO-03 TASK TITLE: Returning an IRM to Service from the Bypassed Condition K/A NUMBER: 215003 A2.02 K/A RATING: RO 3.5 SRO: 3.7 TASK STANDARD: Return IRM F to Service.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-OI-92A VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. Plant startup is in progress with IRM F bypassed and withdrawn. IRM F is ready to be returned to service.
INITIATING CUES: The Unit Supervisor directs you to return IRM F to service per 2-OI-92A Intermediate Range Monitors section 6.2.
JPM NO. 207 REV. NO. 0 PAGE 3 OF 6 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. Plant startup is in progress with IRM F bypassed and withdrawn. IRM F is ready to be returned to service.
INITIATING CUES: The Unit Supervisor directs you to return IRM F to service per 2-OI-92A Intermediate Range Monitors section 6.2.
JPM NO. 207 REV. NO. 0 PAGE 4 OF 6 START TIME Performance Step 1: Critical Not Critical _X 6.2 Returning an IRM to Service from the Bypassed Condition NOTE All operations are performed on Panel 2-9-5 unless specifically stated otherwise.
[1] REVIEW all precautions and limitations in Section 3.0.
CAUTION A bypassed IRM that is not fully inserted will receive a rod block signal when it is unbypassed, unless the reactor is in the RUN mode (Mode 1).
Standard:
Reviews precautions and Limitations SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical _
[2] IF necessary and required, THEN:
INSERT the bypassed IRM detector.
Standard:
Inserts IRM F by depressing IRM F Select pushbutton and then depressing Drive In pushbutton.
SAT UNSAT N/A COMMENTS:
JPM NO. 207 REV. NO. 0 PAGE 5 OF 6 Performance Step 3: Critical X Not Critical _
[3] IF required to avoid a scram signal, THEN:
PLACE the Range Switch for the IRM to be unbypassed to a position where its indication is between 25 and 75 on the 0-125 scale.
Standard:
Ranges IRM F to the correct position so a half scram is not received.
SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical _
[4] PLACE the applicable IRM Bypass selector switch to neutral (off):
- IRM BYPASS, 2-HS-92-7A/S4B Standard:
Places IRM Bypass switch to neutral for IRM F.
SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[5] CHECK Bypassed light is extinguished.
Standard:
Verifies bypass light out SAT UNSAT N/A COMMENTS:
JPM NO. 207 REV. NO. 0 PAGE 6 OF 6 Performance Step 6: Critical Not Critical _X
[6] For the IRM channel returned to service, PERFORM one of the following:
- DEPRESS the IRM Select pushbutton to extinguish the light.
Standard:
Verifies light off or turns light off by depressing IRM select pushbutton.
SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 207 REV. NO. 0 PAGE 1 OF 6 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 207 TASK NUMBER: U-92A-NO-03 TASK TITLE: Returning an IRM to Service from the Bypassed Condition K/A NUMBER: 215003 A2.02 K/A RATING: RO 3.5 SRO: 3.7 TASK STANDARD: Return IRM F to Service.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-OI-92A VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. Plant startup is in progress with IRM F bypassed and withdrawn. IRM F is ready to be returned to service.
INITIATING CUES: The Unit Supervisor directs you to return IRM F to service per 3-OI-92A Intermediate Range Monitors section 6.2.
JPM NO. 207 REV. NO. 0 PAGE 3 OF 6 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. Plant startup is in progress with IRM F bypassed and withdrawn. IRM F is ready to be returned to service.
INITIATING CUES: The Unit Supervisor directs you to return IRM F to service per 3-OI-92A Intermediate Range Monitors section 6.2.
JPM NO. 207 REV. NO. 0 PAGE 4 OF 6 START TIME Performance Step 1: Critical Not Critical _X 6.2 Returning an IRM to Service from the Bypassed Condition NOTE All operations are performed on Panel 3-9-5 unless specifically stated otherwise.
[1] REVIEW all precautions and limitations in Section 3.0.
CAUTION A bypassed IRM that is not fully inserted will receive a rod block signal when it is unbypassed, unless the reactor is in the RUN mode (Mode 1).
Standard:
Reviews precautions and Limitations SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical _
[2] IF necessary and required, THEN:
INSERT the bypassed IRM detector.
Standard:
Inserts IRM F by depressing IRM F Select pushbutton and then depressing Drive In pushbutton.
SAT UNSAT N/A COMMENTS:
JPM NO. 207 REV. NO. 0 PAGE 5 OF 6 Performance Step 3: Critical X Not Critical _
[3] IF required to avoid a scram signal, THEN:
PLACE the Range Switch for the IRM to be unbypassed to a position where its indication is between 25 and 75 on the 0-125 scale.
Standard:
Ranges IRM F to the correct position so a half scram is not received.
SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical _
[4] PLACE the applicable IRM Bypass selector switch to neutral (off):
- IRM BYPASS, 3-HS-92-7A/S4B Standard:
Places IRM Bypass switch to neutral for IRM F.
SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[5] CHECK Bypassed light is extinguished.
Standard:
Verifies bypass light out SAT UNSAT N/A COMMENTS:
JPM NO. 207 REV. NO. 0 PAGE 6 OF 6 Performance Step 6: Critical Not Critical _X
[6] For the IRM channel returned to service, PERFORM one of the following:
- DEPRESS the IRM Select pushbutton to extinguish the light.
Standard:
Verifies light off or turns light off by depressing IRM select pushbutton.
SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 208 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 208 TASK NUMBER: U-090-NO-01 TASK TITLE: Returning DW Radiation Monitor CAM, 2-RM-90-256 to service K/A NUMBER: 272000 A2.10 K/A RATING: RO 3.9 SRO: 4.1 TASK STANDARD: DW Radiation Monitor CAM, 2-RM-90-256 is in service LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-AOI-100-1 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 2-AOI-100-1 Reactor Scram. The lowest Reactor Level was minus 20 inches following the scram.
INITIATING CUES: The Unit Supervisor directs you to perform step 36 of 2-AOI-100-1 Reactor Scram.
JPM NO. 208 REV. NO. 0 PAGE 3 OF 7 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 2-AOI-100-1 Reactor Scram. The lowest Reactor Level was minus 20 inches following the scram.
INITIATING CUES: The Unit Supervisor directs you to perform step 36 of 2-AOI-100-1 Reactor Scram.
JPM NO. 208 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical X Not Critical _
[36] CHECK the following systems/equipment in service or RETURN them to service at standby readiness, as necessary, in accordance with the following or the appropriate OI:
[36.1] PLACE Drywell DP Air Compressor in service at Panel 2-9-3 as follows:
Standard:
Places 2-HS-64-31 and 34 in Auto after Open SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical _
- DEPRESS DRYWELL DP COMP SUCTION VLV RESET switch, 2-HS-64-139A.
- DEPRESS DRYWELL DP COMP DISCH VLV RESET switch, 2-HS-64-140A.
Standard:
Depresses 2-HS-64-139A and 140A to reset.
SAT UNSAT N/A COMMENTS:
JPM NO. 208 REV. NO. 0 PAGE 5 OF 7 Performance Step 3: Critical X Not Critical _
[36.2] PLACE Drywell Floor and Equipment Drains in service at Panel 2-9-4 as follows:
Standard:
Places 2-HS-77-15A and 15B in Auto after Open SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical
Standard:
Places 2-HS-77-2A and 2B in Auto after Open SAT UNSAT N/A COMMENTS:
JPM NO. 208 REV. NO. 0 PAGE 6 OF 7 Performance Step 5: Critical X Not Critical _
[36.3] PLACE DRYWELL RAD MONITOR in service at Panel 2-9-2 by DEPRESSING the following RESET pushbuttons:
- UPPER INBD SUPPLY ISOL VALVE RESET, 2-HS-90-254A-A
- LOWER INBD SUPPLY ISOL VALVE RESET, 2-HS-90-254B-A
- INBD RETURN ISOL VALVE RESET, 2-HS-90-257B-A
- OUTBD SUPPLY ISOL VALVE RESET, 2-HS-90-255A
- OUTBD RETURN ISOL VALVE RESET, 2-HS-90-257A-A Standard:
Depresses the five listed reset pushbuttons to return the Drywell Rad Monitor to service SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical Not Critical _X
[36.4] PERFORM the following to PLACE Drywell Atmosphere Monitors (H202) in service:
[36.4.1] DEPRESS ANALYZER 2A ISOLATION RESET pushbutton, 2-HS-76-91 on Panel 2-9-54.
[36.4.2] IF H2/O2 Analyzer 2A was in service, THEN PULL and RELEASE the ANALYZER 2A SUPPR CHBR/DW SELECT hand-switch, 2-HS-76-49 on Panel 2-9-54.
Standard:
Depresses Analyzer 2A reset pushbutton, does not place analyzer in service SAT UNSAT N/A COMMENTS:
CUE: If Asked, Drywell Atmosphere Monitors (H202) were not in service
JPM NO. 208 REV. NO. 0 PAGE 7 OF 7 Performance Step 7: Critical Not Critical X
[36.4.3] DEPRESS ANALYZER 2B ISOLATION RESET pushbutton, 2-HS-76-92 on Panel 2-9-54.
[36.4.4] IF H2/O2 Analyzer 2B was in service, THEN PULL and RELEASE the ANALYZER 2B SUPPR CHBR/DW SELECT hand-switch, 2-HS-76-59 on Panel 2-9-54.
Standard:
Depresses Analyzer 2B reset pushbutton, does not place analyzer in service SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 208 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 208 TASK NUMBER: U-090-NO-01 TASK TITLE: Returning DW Radiation Monitor CAM, 3-RM-90-256 to service K/A NUMBER: 272000 A2.10 K/A RATING: RO 3.9 SRO: 4.1 TASK STANDARD: DW Radiation Monitor CAM, 3-RM-90-256 is in service LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-AOI-100-1 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 3-AOI-100-1 Reactor Scram. The lowest Reactor Level was minus 20 inches following the scram.
INITIATING CUES: The Unit Supervisor directs you to perform step 37 of 3-AOI-100-1 Reactor Scram.
JPM NO. 208 REV. NO. 0 PAGE 3 OF 7 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit Operator. Plant conditions are as found. The Unit Supervisor is operating in 3-AOI-100-1 Reactor Scram. The lowest Reactor Level was minus 20 inches following the scram. The Drywell Atmosphere Monitors (H202) were not in service.
INITIATING CUES: The Unit Supervisor directs you to perform step 37 of 3-AOI-100-1 Reactor Scram.
JPM NO. 208 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical X Not Critical _
[37] CHECK the following systems/equipment in service or RETURN them to service at standby readiness, as necessary, in accordance with the following or the appropriate OI:
[37.1] PLACE Drywell DP Air Compressor in service at Panel 3-9-3 as follows:
[37.1.1] PLACE DRYWELL INBD ISOLATION VLV switch, 3-HS-64-31, in AUTO after OPEN.
[37.1.2] PLACE SUPPR CHBR INBD ISOLATION VLV switch, 3-HS-64-34, in AUTO after OPEN.
Standard:
Places 3-HS-64-31 and 34 in Auto after Open SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical _
[37.1.3] DEPRESS DRYWELL DP COMP SUCTION VLV RESET switch, 3-HS-64-139A.
[37.1.4] DEPRESS DRYWELL DP COMP DISCH VLV RESET switch, 3-HS-64-140A.
Standard:
Depresses 3-HS-64-139A and 140A to reset.
SAT UNSAT N/A COMMENTS:
JPM NO. 208 REV. NO. 0 PAGE 5 OF 7 Performance Step 3: Critical X Not Critical _
[37.2] PLACE Drywell Floor and Equipment Drains in service at Panel 3-9-4 as follows:
[37.2.1] PLACE DW EQPT DRAIN INBD ISOL VALVE switch, 3-HS-77-15A, in AUTO after OPEN.
[37.2.2] PLACE DW EQPT DRAIN OUTBD ISOL VALVE switch, 3-HS-77-15B, in AUTO after OPEN.
Standard:
Places 3-HS-77-15A and 15B in Auto after Open SAT UNSAT N/A COMMENTS:
Performance Step 4: Critical X Not Critical
[37.2.3] PLACE DW FLOOR DRAIN INBD ISOL VALVE switch, 3-HS-77-2A, in AUTO after OPEN.
[37.2.4] PLACE DW FLOOR DRAIN OUTBD ISOL VALVE switch 3-HS-77-2B, in AUTO after OPEN.
Standard:
Places 3-HS-77-2A and 2B in Auto after Open SAT UNSAT N/A COMMENTS:
JPM NO. 208 REV. NO. 0 PAGE 6 OF 7 Performance Step 5: Critical X Not Critical _
[37.3] PLACE DRYWELL RAD MONITOR in service at Panel 3-9-2 by DEPRESSING the following RESET pushbuttons:
A. UPPER INBD SUPPLY ISOL VALVE RESET, 3-HS-90-254A-A B. LOWER INBD SUPPLY ISOL VALVE RESET, 3-HS-90-254B-A C. INBD RETURN ISOL VALVE RESET, 3-HS-90-257B-A D. OUTBD SUPPLY ISOL VALVE RESET, 3-HS-90-255A E. OUTBD RETURN ISOL VALVE RESET, 3-HS-90-257A-A Standard:
Depresses the five listed reset pushbuttons to return the Drywell Rad Monitor to service SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical Not Critical _X
[37.4] PERFORM the following to PLACE Drywell Atmosphere Monitors (H202) in service:
[37.4.1] DEPRESS ANALYZER 3A ISOLATION RESET pushbutton, 3-HS-76-91 on Panel 3-9-54.
[37.4.2] IF H2/O2 Analyzer 3A was in service, THEN PULL and RELEASE the ANALYZER 3A SUPPR CHBR/DW SELECT hand-switch, 3-HS-76-49 on Panel 3-9-54.
Standard:
Depresses Analyzer 3A reset pushbutton, does not place analyzer in service SAT UNSAT N/A COMMENTS:
CUE: If Asked, Drywell Atmosphere Monitors (H202) were not in service
JPM NO. 208 REV. NO. 0 PAGE 7 OF 7 Performance Step 7: Critical Not Critical X
[37.4.3] DEPRESS ANALYZER 3B ISOLATION RESET pushbutton, 3-HS-76-92 on Panel 3-9-54.
[37.4.4] IF H2/O2 Analyzer 3B was in service, THEN PULL and RELEASE the ANALYZER 3B SUPPR CHBR/DW SELECT hand-switch, 3-HS-76-59 on Panel 3-9-54.
Standard:
Depresses Analyzer 3B reset pushbutton, does not place analyzer in service SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical Not Critical _X NOTE RPV Water Level at or below -122 in. will pick up 3-1-58A2 and 58B2. This will start the drywell high pressure bypass timers, seal them in, and illuminate amber lights IL-1-202/203/204/205 located on Panel 9-30 in the Auxiliary Instrument Room.
[37.5] IF RPV Water Level lowered to -122 in. or below, THEN PERFORM the following in Unit 3 Aux. Inst Room : (Otherwise N/A)
Standard:
Step is NA SAT UNSAT N/A COMMENTS:
END OF TASK STOP TIME
JPM NO. 209 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 209 TASK NUMBER: U-000-EM-80 TASK TITLE: Drywell Sprays using Fire Protection K/A NUMBER: 295024 EA1.11 K/A RATING: RO 4.2 SRO: 4.2 TASK STANDARD: Perform Unit 1 and 2 Operator actions to spray the Drywell using Fire Protection System.
LOCATION OF PERFORMANCE: Control Room REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix 17B VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are the Operator in Unit 1 and 2 assigned to assist in spraying the Drywell using Fire Protection. AC Power remains available. The Unit 3 Unit Supervisor is operating in 3-EOI-2 Primary Containment Control, he has directed Drywell Sprays using Fire Protection.
INITIATING CUES: The Unit Supervisor directs you perform the actions in Unit 1 and 2 Control Room to spray the Drywell using Fire Protection per 3-EOI Appendix-17B RHR System Operation Drywell Sprays, commence at step 9 of 3-EOI Appendix-17B.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 209 REV. NO. 0 PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. SELF CHECKING 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. Observe ALL plant radiological and safety precautions. 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 "That's correct" (or That's incorrect", if applicable). When you have completed your assigned task, you will say, "My task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the Operator in Unit 1 and 2 assigned to assist in spraying the Drywell using Fire Protection. AC Power remains available. The Unit 3 Unit Supervisor is operating in 3-EOI-2 Primary Containment Control, he has directed Drywell Sprays using Fire Protection.
INITIATING CUES: The Unit Supervisor directs you perform the actions in Unit 1 and 2 Control Room to spray the Drywell using Fire Protection per 3-EOI Appendix-17B RHR System Operation Drywell Sprays, commence at step 9 of 3-EOI Appendix-17B.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 209 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical Not Critical X
- 5. IF Directed by SRO to spray the Drywell using Fire Protection, THEN CONTINUE in this procedure at Step 9.
NOTE: Steps 9 thru 12 are performed ONLY if directed by Step 5 to Spray the Drywell using Fire Protection.
- 9. IF ALL AC Power is NOT available, THEN REFER to Attachment 1 and DISPATCH personnel to manually operate the listed valves while performing the following steps.
Standard:
Given in Initial conditions AC Power available SAT UNSAT N/A COMMENTS:
Performance Step 2: Critical X Not Critical _
- 10. NOTIFY Unit 1 Operator to perform the following:
- a. VERIFY at least one electric or the diesel driven fire pump RUNNING (Unit 1, Panel 9-20).
Standard:
Simulates Starting an Electric or a Diesel Fire Pump at Panel 9-20 SAT UNSAT N/A COMMENTS:
CUE: No Fire Pump Operating, when simulated Fire Pump is operating, red light on
JPM NO. 209 REV. NO. 0 PAGE 5 OF 7 Performance Step 3: Critical Not Critical _X
- b. IF Diesel driven fire pump is RUNNING, THEN DISPATCH personnel to diesel fire pump as soon as possible to check proper operation.
Standard:
If Diesel Fire Pump started dispatches personnel SAT UNSAT N/A COMMENTS:
CUE: Acknowledge dispatch if required Performance Step 4: *Critical X Not Critical _
- c. VERIFY CLOSED the following valves (Unit 1, Panel 9-20):
- 0-FCV-25-32, RSW STRG TNK ISOLATION VALVE
- 0-FCV-25-70, RSW STRG TNK ISOLATION VALVE
- 1-FCV-23-57, STANDBY COOLANT VALVE FROM RHRSW (Unit 1, Panel 1-9-3).
Standard:
Simulates closing *0-FCV-25-32 and *0-FCV-25-70 and verifies 1-FCV-23-57 SAT UNSAT N/A COMMENTS:
CUE: 0-FCV-25-32 and 0-FCV-25-70 as found or red light on green light off, after operator simulates closing green light on red light off. 1-FCV-23-57 as found (closed), green light on, red light off
JPM NO. 209 REV. NO. 0 PAGE 6 OF 7 Performance Step 5: Critical Not Critical _X
- 11. NOTIFY Unit 2 Operator to VERIFY CLOSED the following valves (Unit 2, Panel 2-9-3):
- 2-FCV-74-101, RHR SYS II U-3 DISCH XTIE.
Standard:
Simulates verifying 2-FCV-23-46 and 2-FCV-74-101 closed SAT UNSAT N/A COMMENTS:
CUE: 2-FCV-23-46 as found (closed), green light on, red light off and 2-FCV-74-101 as found no indication (valve is normally down powered closed)
Performance Step 6: Critical Not Critical _X
- 12. INITIATE Drywell Spray on RHR Loop I using Fire Protection as follows:
- a. IF EITHER of the following exists:
- Directed by SRO, Standard:
Unit 3 Operator Actions SAT UNSAT N/A COMMENTS:
CUE: Step 12 a through f are complete, Unit 3 Operator notifies you to proceed with step 12 g.
JPM NO. 209 REV. NO. 0 PAGE 7 OF 7 Performance Step 7: Critical Not Critical X
- g. NOTIFY Unit 1 Operator to VERIFY CLOSED 1-FCV-23-46, RHR HEAT EXCHANGER B COOL WATER OUTLET VLV (Unit 1, Panel 1-9-3).
Standard:
Simulates verifying 1-FCV-23-46 closed SAT UNSAT N/A COMMENTS:
CUE: 1-FCV-23-46 as found (closed) green light on, red light off Performance Step 8: Critical X Not Critical
- h. NOTIFY Unit 2 Operator to OPEN 2-FCV-23-57, STANDBY COOLANT VALVE FROM RHRSW (Unit 2, Panel 2-9-3).
Standard:
Simulates opening 2-FCV-23-57 SAT UNSAT N/A COMMENTS:
CUE: 2-FCV-23-57 as found (closed), green light on, red light off. After simulates opening red light on green light off.
END OF TASK STOP TIME
JPM NO. 210 REV. NO. 0 PAGE 1 OF 16 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 210ap TASK NUMBER: U-047-AL-11 TASK TITLE: Generator Synchronization and Loading K/A NUMBER: 262001 A4.04 K/A RATING: RO 3.6 SRO: 3.7 TASK STANDARD: Synchronize the Generator, followed by manually tripping on high vibration.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 2-OI-47 and 2-ARP-9-7B VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. The turbine is at rated speed. Generator Bus Duct Cooling System is in service. Generator Hydrogen Cooling System is in service. Generator Stator Water Cooling System is in service. Hydrogen Seal Oil System is in service. Generator Circuit Breaker System is in service. Electrical System is in service. Precautions and limitations have been reviewed. Generator Condition Monitor in service. The Generator Breaker PCB 234 is ready to be closed 2-OI-35C, Section 5.1 is complete. Operations Manager has not authorized any local operation of the GENERATOR EXCITER FIELD BREAKER local manual control lever. Permission from the Operations Superintendent has been obtained.
INITIATING CUES: The Unit Supervisor directs you to synchronize and load the Main Turbine Generator per 2-OI-47 Turbine-Generator System section 5.5. You are directed to synchronize the generator using the Synchronous Check Relays and raise load to 60 to 80 MWe.
JPM NO. 210 REV. NO. 0 PAGE 3 OF 16 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's 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. The turbine is at rated speed. Generator Bus Duct Cooling System is in service. Generator Hydrogen Cooling System is in service. Generator Stator Water Cooling System is in service. Hydrogen Seal Oil System is in service. Generator Circuit Breaker System is in service. Electrical System is in service. Precautions and limitations have been reviewed. Generator Condition Monitor in service. The Generator Breaker PCB 234 is ready to be closed 2-OI-35C, Section 5.1 is complete. Operations Manager has not authorized any local operation of the GENERATOR EXCITER FIELD BREAKER local manual control lever. Permission from the Operations Superintendent has been obtained.
INITIATING CUES: The Unit Supervisor directs you to synchronize and load the Main Turbine Generator per 2-OI-47 Turbine-Generator System section 5.5. You are directed to synchronize the generator using the Synchronous Check Relays and raise load to 60 to 80 MWe.
JPM NO. 210 REV. NO. 0 PAGE 4 OF 16 START TIME Performance Step 1: Critical Not Critical _X 5.5 Generator Synchronization and Loading
[1] REVIEW all Precautions and Limitations, Section 3.0.
[2] VERIFY the following initial conditions are satisfied:
- The turbine is at rated speed. REFER TO Section 5.4.
- Generator Bus Duct Cooling System is in service. REFER TO Section 5.7.
- Generator Hydrogen Cooling System is in service. Refer to 2-OI-35.
- Generator Stator Water Cooling System is in service. Refer to 2-OI-35A.
- Hydrogen Seal Oil System is in service. Refer to 2-OI-35B.
- Electrical System is in service. Refer to 0-OI-57B, 0-OI-57C, 0-OI-57D.
NOTE This instruction is performed from Panel 2-9-8 unless otherwise specified.
[3] VERIFY Generator Condition Monitor in service, or in the process of being placed in service. Refer to 2-OI-35.
[4] VERIFY Generator Breaker PCB 224 is ready to be closed by completion of 2-OI-35C Section 5.1. (Turb. Bldg El 604').
Standard:
Given in initial conditions SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 5 OF 16 Performance Step 2: Critical Not Critical _X
[5] VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 2-HS-57-27, is in MAN.
NOTES
- 1) On closure of the generator exciter field breaker, Communications Room Common Alarm, 2-XA-55-8A Window 35, may be received for EOR0086, GEN 2 EXC/GEN FIELD GROUND. Alarm is verified on ICS Alarm Mimic or alarm printer for generator exciter ground. This occurs due to charging current on the field.
- 2) If GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P) is not set properly, a loss of field voltage could occur after approximately 10 seconds from closure of the GENERATOR EXCITER FIELD BREAKER.
- 3) When closing the generator exciter field breaker in Step 5.5[6.1], Step 5.5[7] offers contingency steps to be taken should a generator ground alarm occur and Step 5.5[7.1]offers contingency steps to be taken should a loss of field voltage occur.
Standard:
Verifies voltage regulator is in manual.
SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical X Not Critical _
[6] CLOSE GENERATOR EXCITER FIELD BREAKER by either.
[6.1] PLACE GENERATOR EXCITER FIELD BREAKER, 2-HS-57-24, in CLOSE.
OR NOTES
- 1) Performance of step 5.5[6.3] requires permission of the Operations Manager to perform.
- 2) If necessary the local manual control lever can be obtained from electrical maintenance.
Standard:
Closes Generator Exciter Field Breaker with handswitch.
SAT UNSAT N/A COMMENTS:
CUE: If Asked, Operations Manager Permission has not been obtained for step 6.3
JPM NO. 210 REV. NO. 0 PAGE 6 OF 16 Performance Step 4: Critical Not Critical X_
[7] IF GEN 2 EXC/GEN FIELD GROUND is received, THEN PERFORM EOR0086 - GEN 2 EXC/GEN FIELD GROUND Operator Actions provided in 2-ARP-9-8A Attachment 2. (Otherwise N/A)
Standard:
NA SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[8] IF a Loss of Field Voltage occurs, THEN PERFORM the following; (Otherwise N/A):
[9] CHECK GEN SYNC AVAILABLE light, 2-IL-242-4, is illuminated.
NOTES
- 1) SYNC AVAILABLE light will not illuminate if another unit is in SYNC CHECK INTLK.
- 2) In Step 5.5[9], the Synchroscope should rotate slow in the fast direction (clockwise) at one revolution every 10-15 seconds if in SYNC CHK INTLK and at one revolution every 15-20 seconds if in MANUAL.
Standard:
Step 8 is NA, Checks GEN SYNC AVAILABLE light is illuminated SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 7 OF 16 Performance Step 6: Critical X Not Critical _
[10] PLACE GENERATOR PCB 224 SYNC SELECT, 2-HS-242-6 in SYNC CHK INTLK OR MANUAL, as necessary.
[10.1] OPERATE TURBINE GENERATOR SYNC SPEED ADJUST, 2-XS-57-20, to obtain SYNCHROSCOPE, 2-XI-57-55 rotation slow in FAST direction (clockwise).
Standard:
Places PCB 234 in synch chk intlk or manual and operates Sync Speed Adjust to obtain rotation in Fast direction.
SAT UNSAT N/A COMMENTS:
Performance Step 7: *Critical X Not Critical
- [11] MATCH GEN SYNC REF VOLTAGE, 2-EI-57-54, to SYSTEM SYNC REF VOLTAGE, 2-EI-57-56, using GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P), 2-HS-57-25.
[12] CHECK GENERATOR VOLTS, 2-EI-57-39, indicates between 21 and 23 KV.
Standard:
Matches reference voltage to system voltage by adjusting *2-HS-57-25 and verifies generator volts between 21 and 23 KV.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 8 OF 16 Performance Step 8: *Critical X Not Critical CAUTION Frequent monitoring of GENERATOR MVARS, 2-EI-57-51, is required as long as the VOLTAGE REGULATOR MAN/AUTO SEL switch is in MAN.
NOTES
- 1) Operation of the Main Generator without automatic voltage control could impact grid voltage requirements as referenced in Sections 6.1[10], 8.10.1[8].
- 2) When the Main generator is online, the Voltage Regulator is required to be operated in Automatic, unless coordinated with the Transmission Operator (TOp).
[13] ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 2-HS-57-26, until GEN TRANSFER VOLTS, 2-EI-57-41, indicates zero.(N/A if Auto Regulator is not available)
- [14] PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 2-HS-57-27, in AUTO.(N/A if Auto Regulator is not available)
[15] VERIFY GEN VOLT REGULATOR TRIP TO MAN, 2-EA-57-132 (2-XA-55-8A, window 3) ANNUNCIATES.(N/A if Auto Regulator is not available)
Standard:
Adjust 2-HS-57-26 until generator transfer volts indicates zero, places voltage regulator in
- auto and verifies annunciator.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 9 OF 16 Performance Step 9: Critical Not Critical X
[16] CHECK RESET the following annunciators on Panel 2-9-8:
- GEN VOLT REGULATOR TRIP TO MAN (2-XA-55-8A, window 3) (N/A if Auto Regulator is not available)
- GENERATOR EXCITER OVERVOLTAGE (2-XA-55-8A, window 4)
- GENERATOR EXCTR FIELD OVERCURRENT (2-XA-55-8A, window 6)
- GEN VOLTS PER CYCLE HIGH (2-XA-55-8A, window 9)
- MAIN TURBINE SHUTDOWN (2-XA-55-8A, window 11)
- MAIN XFMR USST 2A/2B OIL LEVEL ABNORMAL, 2-LA-57-142, (2-XA-55-8A, window 13)
- MAIN XFMR USST 2A/2B COOL SYS FAILURE, 2-XA-57-144, (2-XA-55-8A, window 15)
- PCB 224 SF6 LO/SF6 LO-LO DENSITY 2-PA-242-6 (2-XA-55-8D, window 29).
- PCB 224 250 VDC/43L ABNORMAL 2-EA-242-2 (2-XA-55-8D, window 30).
- PCB 224 LO/LO-LO SPRING ENERGY 2-EA-242-4 (2-XA-55-8D, window 57).
- PCB 224 DS 89 GS, 57-1, GS 57-2 MTR OVERLOAD 2-EA-242-1 (2-XA-55-8D, window 59).
[17] NOTIFY Operations Duty Specialist (ODS) that Unit 2 Generator is ready to tie to the electrical grid.
[17.1] ENTER notification made, name, date and time in the Narrative Log.
Standard:
Verifies annunciators reset, notifies Operations Duty Specialist and requests log entry SAT UNSAT N/A COMMENTS:
CUE: ODS Notified, Narrative Log entry made.
JPM NO. 210 REV. NO. 0 PAGE 10 OF 16 Performance Step 10: Critical Not Critical X NOTE If tying online with the Voltage Regulator in Manual, the reason and expected duration is required to be entered in the Narrative Log.
[18] NOTIFY the Transmission Operator (TOp) that Unit 3 Generator is ready to tie to the electrical grid and report Voltage Regulator status.
[18.1] ENTER notification made, date, time, and voltage regulator status in the Narrative Log.
Standard:
Notifies Transmission Operator and requests log entry SAT UNSAT N/A COMMENTS:
CUE: Transmission Operator Notified, Narrative Log entry made.
JPM NO. 210 REV. NO. 0 PAGE 11 OF 16 Performance Step 11: *Critical X Not Critical CAUTIONS
- 1) DO NOT exceed 150°F/hr heat up rate on Turbine first stage shell. .
- 2) DO NOT exceed 75°F Turbine first stage shell inner to outer surface temperature differential..
- 3) The temperature rise of oil across a bearing should be less than 35°F. Temperature rise should be gradual as turbine load is raised, and any sudden rise of greater than 5°F should be investigated immediately.
[19] Manually SYNCHRONIZE the Generator as follows:
[19.1] OBTAIN permission from the Operations Superintendent.
- [19.2] VERIFY GENERATOR PCB 234 SYNC SELECT, 2-HS-242-6, in MANUAL.
Standard:
Verify in manual SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 12 OF 16 Performance Step 12: Critical X Not Critical NOTE In Step 5.5[19.3], the Synchroscope is adjusted for a rotation slow in the fast direction (clockwise) at one revolution every 15-20 seconds.
[19.3] PERFORM the following concurrently to obtain both conditions at the same time:
- OPERATE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P),
2-HS-57-26 to match SYSTEM SYNC REF VOLTAGE, 2-EI-57-56 to GEN SYNC REF VOLTAGE, 2-EI-57-54. (N/A if Voltage Regulator is in Manual)
- OPERATE GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P),
2-HS-57-25 to match GEN SYNC REF VOLTAGE, 2-EI-57-54, to SYSTEM SYNC REF VOLTAGE, 2-EI-57-56. (N/A if Voltage Regulator is in Auto)
- OPERATE TURBINE GENERATOR SYNC SPEED ADJUST, 2-XS-57-20, to obtain SYNCHROSCOPE, 2-XI-57-55, rotation slow in the FAST direction (clockwise) at one revolution every 15 seconds to 20 seconds.
NOTE When the generator breaker is closed in Step 5.5[19.4], generator output will automatically rise to between 60-80 MWe.
Standard:
Operates 2-HS-57-26 to match voltage and operates 2-XS-57-20 to obtain synch scope rotation in fast direction one revolution every 15 to 20 seconds.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 13 OF 16 Performance Step 13: Critical X Not Critical NOTE When the generator breaker is closed in Step 5.5[18.4], generator output will automatically rise to between 60-80 MWe.
[19.4] WHEN SYNCHROSCOPE, 2-XI-57-55, indicator is at the green (MANUAL) mark, THEN CLOSE GENERATOR PCB 224 by placing Handswitch, 2-HS-242-0224A, in CLOSE.
Standard:
Closes generator breaker 234 when synch scope is at green mark on scope.
SAT UNSAT N/A COMMENTS:
Performance Step 14: Critical Not Critical X
[19.5] PLACE GENERATOR PCB 224 SYNC SELECT switch, 2-HS-242-6, in OFF.
Standard:
Places 2-HS-242-6 to off.
SAT UNSAT N/A COMMENTS:
Simulator Driver: Once Generator is synched INSERT turbine vibration greater than 12 mils on two bearings. Batch file nrcjpm2010synch
JPM NO. 210 REV. NO. 0 PAGE 14 OF 16 Performance Step 15: Critical Not Critical X NOTES
- 1) Unless otherwise directed, the normal band for Generator MVARS should be 0 + or - 50 mvars while regulation is in manual.
- 2) When operated in Automatic, the Generator Voltage Regulator has an electronic limit which limits incoming reactive, at full load, to approximately 150 MVAR. When operated in Manual, there is an administrative limit of 150 MVAR. These limits are intended to prevent the possibility of the Generator slipping a pole.
- 3) See Section 8.13 for operation with the voltage regulator in Manual.
[19.6] OPERATE GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P),
2-HS-57-25 as required to maintain generator parameters.
NOTES
- 1) Steps 5.5[20] through 5.5[25.2] are performed from Panel 2-9-7 unless indicated otherwise.
- 2) When the exhaust hood temperature is above 125°F, turbine load should be raised slowly until the temperature falls below 125°F. Plant operating history indicates that maintaining load at about 80 MWe will aid in lowering the Exhaust temperatures due to more steam flow.
Standard:
Operates 2-HS-57-25 as required SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 15 OF 16 Performance Step 16: Critical Not Critical X
[20] IF necessary, THEN DEPRESS Load Set RAISE pushbutton, 2-HS-47-75C, or LOWER pushbutton, 2-HS-47-75B, to maintain desired generator output between 60 MWe to 80 MWe.
[21] HOLD generator output between 60 MWe to 80 MWe UNTIL turbine first stage and valve chest temperatures stabilize and exhaust hood temperature lowers to less than 125°F, as indicated on 2-XR-47-20.
Standard:
Maintains load 60 to 80 MWe by depressing load set pushbuttons.
SAT UNSAT N/A COMMENTS:
Performance Step 17: Critical Not Critical X MAIN TURBINE VIBRATION HIGH 2-VA-47-15 A. VERIFY alarm by checking the following:
- On EHC WORKSTATION, Turbine Vibration screen.
- On ICS, MAIN TURBINE BEARINGS (TURBBRG) screen.
- TURBINE GENERATOR VIBRATION recorder, 2-XR-47-15 (Panel 2-9-7).
Standard:
Acknowledges receipt of Main Turbine Vibration Alarm and checks turbine vibration levels.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 16 OF 16 Performance Step 18: Critical X Not Critical B. IF alarm is valid, THEN
- 1. DETERMINE cause by checking PROBABLE CAUSE section above.
- 2. REDUCE load and OBSERVE vibration.
- 3. IF any of the vibration limits requiring a trip are met in Table 1, THEN DEPRESS Turbine TRIP pushbutton, 2-HS-47-67D:
Standard:
Verifies vibration levels greater than 12 mils and trips the main turbine by depressing turbine trip pushbutton.
SAT UNSAT N/A COMMENTS:
CUE: Another operator will take care of the AOI actions, JPM complete.
END OF TASK STOP TIME
JPM NO. 210 REV. NO. 0 PAGE 1 OF 14 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 210ap TASK NUMBER: U-047-AL-11 TASK TITLE: Generator Synchronization and Loading K/A NUMBER: 262001 A4.04 K/A RATING: RO 3.6 SRO: 3.7 TASK STANDARD: Synchronization the Generator using Synch Check Interlock, followed by manually tripping on high vibration.
LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: 3-OI-47 and 3-ARP-9-7B VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit Operator. The turbine is at rated speed. Generator Bus Duct Cooling System is in service. Generator Hydrogen Cooling System is in service. Generator Stator Water Cooling System is in service. Hydrogen Seal Oil System is in service. Generator Circuit Breaker System is in service. Electrical System is in service. Precautions and limitations have been reviewed. Generator Condition Monitor in service. Knife Blade switches CS-1, CS-2, and CS-3 are closed. Operations Manager has not authorized any local operation of the GENERATOR EXCITER FIELD BREAKER local manual control lever. Permission from the Operations Superintendent has been obtained to synchronize the Main Generator. Synchronize the generator using the Synch Check Interlock.
INITIATING CUES: The Unit Supervisor directs you to synchronize and load the Main Turbine Generator per 3-OI-47 Turbine-Generator System section 5.5. You are directed to synchronize the generator using the Synchronous Check Relays and raise load to 60 to 80 MWe.
JPM NO. 210 REV. NO. 0 PAGE 3 OF 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's 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. The turbine is at rated speed. Generator Bus Duct Cooling System is in service. Generator Hydrogen Cooling System is in service. Generator Stator Water Cooling System is in service. Hydrogen Seal Oil System is in service. Generator Circuit Breaker System is in service. Electrical System is in service. Precautions and limitations have been reviewed. Generator Condition Monitor in service. Knife Blade switches CS-1, CS-2, and CS-3 are closed. Operations Manager has not authorized any local operation of the GENERATOR EXCITER FIELD BREAKER local manual control lever. Permission from the Operations Superintendent has been obtained to synchronize the Main Generator. Synchronize the generator using the Synch Check Interlock.
INITIATING CUES: The Unit Supervisor directs you to synchronize and load the Main Turbine Generator per 3-OI-47 Turbine-Generator System section 5.5. You are directed to synchronize the generator using the Synchronous Check Relays and raise load to 60 to 80 MWe.
JPM NO. 210 REV. NO. 0 PAGE 4 OF 14 START TIME Performance Step 1: Critical Not Critical _X 5.5 Generator Synchronization and Loading
[1] VERIFY the following initial conditions are satisfied:
- The turbine is at rated speed. REFER TO Section 5.4.
- Generator Bus Duct Cooling System is in service. REFER TO Section 6.11
- Generator Hydrogen Cooling System is in service. REFER TO 3-OI-35.
- Generator Stator Water Cooling System is in service. REFER TO 3-OI-35A.
- Hydrogen Seal Oil System is in service. REFER TO 3-OI-35B.
- Generator Circuit Breaker System is in service. REFER TO 3-OI-35C.
- Electrical System is in service. REFER TO 0-OI-57B, 0-OI-57C, 0-OI-57D.
[2] REVIEW all Precautions and Limitations. REFER TO Section 3.0.
NOTE This instruction is performed from Panel 3-9-8 unless otherwise specified.
[3] VERIFY Generator Condition Monitor in service, or in the process of being placed in service. REFER TO 3-OI-35.
[4] VERIFY CLOSED knife blade switches CS-1, CS-2, and CS-3, located in the ACB 234 control cabinet (Turb. Bldg El 604').
Standard:
Given in initial conditions SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 5 OF 14 Performance Step 2: Critical Not Critical _X
[5] VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, is in MAN.
NOTES
- 1) On closure of the generator exciter field breaker, Communications Room Common Alarm, 3-XA-55-8A Window 35, may be received for EOR0086, GEN 3 EXC/GEN FIELD GROUND. Alarm is verified on ICS Alarm Mimic or alarm printer for generator exciter ground. This occurs due to charging current on the field.
- 2) If GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P) is not set properly, a loss of field voltage could occur after approximately 10 seconds from closure of the GENERATOR EXCITER FIELD BREAKER.
- 3) When closing the generator exciter field breaker in Step 5.5[6.1], Step 5.5[7] offers contingency steps to be taken should a generator ground alarm occur and Step 5.5[7.1]offers contingency steps to be taken should a loss of field voltage occur.
Standard:
Verifies voltage regulator is in manual.
SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical X Not Critical _
[6] CLOSE GENERATOR EXCITER FIELD BREAKER by either.
[6.1] PLACE GENERATOR EXCITER FIELD BREAKER, 3-HS-57-24, in CLOSE.
OR NOTES
- 1) Performance of step 5.5[6.3] requires permission of the Operations Manager to perform.
- 2) If necessary the local manual control lever can be obtained from electrical maintenance.
Standard:
Closes Generator Exciter Field Breaker with handswitch.
SAT UNSAT N/A COMMENTS:
CUE: If Asked, Operations Manager Permission has not been obtained for step 6.3
JPM NO. 210 REV. NO. 0 PAGE 6 OF 14 Performance Step 4: Critical Not Critical X_
[7] IF GEN 3 EXC/GEN FIELD GROUND is received, THEN PERFORM EOR0086 - GEN 3 EXC/GEN FIELD GROUND Operator Actions provided in 3-ARP-9-8A Attachment 2. (Otherwise N/A)
Standard:
NA SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical Not Critical _X
[8] CHECK GEN SYNC AVAILABLE light, 3-IL-242-4, is illuminated.
NOTES
- 1) SYNC AVAILABLE light will not illuminate if another unit is in SYNC CHECK INTLK.
- 2) In Step 5.5[9], the Synchroscope should rotate slow in the fast direction (clockwise) at one revolution every 10-15 seconds if in SYNC CHK INTLK and at one revolution every 15-20 seconds if in MANUAL.
Standard:
Checks GEN SYNC AVAILABLE light is illuminated SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 7 OF 14 Performance Step 6: Critical X Not Critical _
[9] PLACE GENERATOR PCB 234 SYNC SELECT, 3-HS-242-6 in SYNC CHK INTLK OR MANUAL, as necessary.
[9.1] OPERATE TURBINE GENERATOR SYNC SPEED ADJUST, 3-XS-57-20, to obtain SYNCHROSCOPE, 3-XI-57-55 rotation slow in the FAST direction (clockwise).
Standard:
Places PCB 234 in synch chk intlk and operates Sync Speed Adjust to obtain rotation in Fast direction.
SAT UNSAT N/A COMMENTS:
Performance Step 7: *Critical X Not Critical
- [10] MATCH GEN SYNC REF VOLTAGE, 3-EI-57-54, to SYSTEM SYNC REF VOLTAGE, 3-EI-57-56, using GENERATOR FIELD VOLTAGE MANUAL ADJUST (70P), 3-HS-57-25.
[11] CHECK GENERATOR VOLTS, 3-EI-57-39, indicates between 21 and 23 KV.
Standard:
Matches reference voltage to system voltage by adjusting *3-HS-57-25 and verifies generator volts between 21 and 23 KV.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 8 OF 14 Performance Step 8: *Critical X Not Critical CAUTION Frequent monitoring of GENERATOR MVARS, 3-EI-57-51, is required as long as the VOLTAGE REGULATOR MAN/AUTO SEL switch is in MAN.
NOTES
- 1) Operation of the Main Generator without automatic voltage control could impact grid voltage requirements as referenced in Sections 6.1[10], 8.10.1[8].
- 2) When the Main generator is online, the Voltage Regulator is required to be operated in Automatic, unless coordinated with the Transmission Operator (TOp).
[12] ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-57-26, UNTIL GEN TRANSFER VOLTS, 3-EI-57-41, indicates zero.
- [13] PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, in AUTO.
[14] VERIFY GEN VOLT REGULATOR TRIP TO MAN, 3-EA-57-132 (3-XA-55-8A, window 3) ANNUNCIATES.
Standard:
Adjust 3-HS-57-26 until generator transfer volts indicates zero, places voltage regulator in
- auto and verifies annunciator.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 9 OF 14 Performance Step 9: Critical Not Critical X
[15] VERIFY RESET the following annunciators on Panel 3-9-8:
- GEN VOLT REGULATOR TRIP TO MAN (3-XA-55-8A, window 3)
- GENERATOR EXCITER OVERVOLTAGE (3-XA-55-8A, window 4)
- GENERATOR EXCTR FIELD OVERCURRENT (3-XA-55-8A, window 6)
- GEN VOLTS PER CYCLE HIGH (3-XA-55-8A, window 9)
- MAIN TURBINE SHUTDOWN (3-XA-55-8A, window 11)
- MAIN XFMR USST 3A/3B OIL LEVEL ABNORMAL, (3-XA-55-8A, window 13)
- MAIN XFMR USST 3A/3B COOL SYS FAILURE, (3-XA-55-8A, window 15)
- PCB 234 AIR ABN 3-PA-242-4 (3-XA-55-8D, window 57).
[16] NOTIFY Chattanooga Load Coordinator that Unit 3 Generator is ready to tie to the electrical grid.
[16.1] ENTER notification made, name, date and time in the Narrative Log.
Standard:
Verifies annunciators reset, notifies Operations Duty Specialist and requests log entry SAT UNSAT N/A COMMENTS:
CUE: ODS Notified, Narrative Log entry made.
JPM NO. 210 REV. NO. 0 PAGE 10 OF 14 Performance Step 10: Critical X Not Critical CAUTIONS
- 1) DO NOT exceed 150°F/hr heat up rate on Turbine first stage shell. .
- 2) DO NOT exceed 75°F Turbine first stage shell inner to outer surface temperature differential..
- 3) The temperature rise of oil across a bearing should be less than 35°F. Temperature rise should be gradual as turbine load is raised, and any sudden rise of greater than 5°F should be investigated immediately.
[17] IF Synchronizing using the Synchronous Check Relays, THEN PERFORM the following:
[17.1] VERIFY GENERATOR PCB 234 SYNC SELECT, 3-HS-242-6, in SYNC CHK INTLK.
[17.2] PERFORM the following concurrently to obtain both conditions at the same time:
- OPERATE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P),
3-HS-57-26 to match SYSTEM SYNC REF VOLTAGE, 3-EI-57-56 to GEN SYNC REF VOLTAGE, 3-EI-57-54. (N/A if Voltage Regulator is in Manual)
- OPERATE TURBINE GENERATOR SYNC SPEED ADJUST, 3-XS-57-20, to obtain SYNCHROSCOPE, 3-XI-57-55, rotation slow in the FAST direction (clockwise) at one revolution every 15 seconds to 20 seconds.
Standard:
Operates 3-HS-57-26 to match voltage and operates 3-XS-57-20 to obtain synch scope rotation in fast direction one revolution every 15 to 20 seconds.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 11 OF 14 Performance Step 11: Critical X Not Critical
[17.3] WHEN SYNCHROSCOPE, 3-XI-57-55, indicator is at the red SYNC CHECK INTERLOCK mark, THEN CLOSE GENERATOR PCB 234 by placing handswitch, 3-HS-242-0234A, in CLOSE.
Standard:
Closes generator breaker 234 when synch scope is at red mark on scope.
SAT UNSAT N/A COMMENTS:
Performance Step 12: Critical Not Critical X
[17.4] PLACE GENERATOR PCB 234 SYNC SELECT switch, 3-HS-242-6 in OFF.
Standard:
Synch select to Off SAT UNSAT N/A COMMENTS:
Simulator Driver: Once Generator is synched INSERT turbine vibration greater than 12 mils on two bearings. Batch file nrcjpm2010synch
JPM NO. 210 REV. NO. 0 PAGE 12 OF 14 Performance Step 13: Critical Not Critical X
[18] IF performing Synchronization manually, THEN (Otherwise N/A)
Standard:
Step 18 is NA SAT UNSAT N/A COMMENTS:
Performance Step 14: Critical Not Critical X NOTES
- 1) Steps 5.5[19] through5.5[24] are performed from Panel 3-9-7 unless indicated otherwise.
- 2) When the exhaust hood temperature is above 125°F, turbine load should be raised slowly until the temperature falls below 125°F. Plant operating history indicates that maintaining load at about 80 MWe will aid in lowering the Exhaust temperatures due to more steam flow.
[19] IF necessary, THEN DEPRESS Load Set RAISE pushbutton, 3-HS-47-75C, or LOWER pushbutton, 3-HS-47-75B, to maintain desired generator output between 60 MWe to 80 MWe.
Standard:
Maintains load 60 to 80 MWe by depressing load set pushbuttons.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 13 OF 14 Performance Step 15: Critical Not Critical X MAIN TURBINE VIBRATION HIGH 3-VA-47-15 A. VERIFY alarm by checking the following:
- On EHC WORKSTATION, Turbine Vibration screen.
- On ICS, MAIN TURBINE BEARINGS (TURBBRG) screen.
- TURBINE GENERATOR VIBRATION recorder, 3-XR-47-15 (Panel 3-9-7).
Standard:
Acknowledges receipt of Main Turbine Vibration Alarm and checks turbine vibration levels.
SAT UNSAT N/A COMMENTS:
JPM NO. 210 REV. NO. 0 PAGE 14 OF 14 Performance Step 16: Critical X Not Critical B. IF alarm is valid, THEN
- 1. DETERMINE cause by checking PROBABLE CAUSE section above.
- 2. REDUCE load and OBSERVE vibration.
- 3. IF any of the vibration limits requiring a trip are met in Table 1, THEN DEPRESS Turbine TRIP pushbutton, 3-HS-47-67D:
Standard:
Verifies vibration levels greater than 12 mils and trips the main turbine by depressing turbine trip pushbutton.
SAT UNSAT N/A COMMENTS:
CUE: Another operator will take care of the AOI actions, JPM complete.
END OF TASK STOP TIME
JPM NO. 211 REV. NO. 0 PAGE 1 OF 8 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 211ap TASK NUMBER: A-082-NO-09 TASK TITLE: Emergency Shutdown at Diesel Engine K/A NUMBER: 264000 K4.07 K/A RATING: RO 3.3 SRO: 3.4 TASK STANDARD: Shutdown at Diesel Engine Control Cabinet and emergency shutdown at Diesel Engine.
LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 3-OI-82 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are an Auxiliary Unit Operator. Diesel Generator 3A Output breaker 1838 is open. Precautions and Limitations have been reviewed. The Unit Operator has been notified that the Diesel Generator will be made inoperable as a result of shutting down the 3A Diesel Engine at the Diesel Engine Control Cabinet. Shutdown of Diesel Generator 3A at the Diesel Engine Control Cabinet is being performed for testing purposes.
INITIATING CUES: The Unit Supervisor directs you to shutdown the 3A Diesel Engine from the Diesel Engine Control Cabinet per 3-OI-82 Standby Diesel Generator System, section 7.3.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 211 REV. NO. 0 PAGE 3 OF 8 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. SELF CHECKING 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. Observe ALL plant radiological and safety precautions. 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 "That's correct" (or That's incorrect", if applicable). When you have completed your assigned task, you will say, "My task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Auxiliary Unit Operator. Diesel Generator 3A Output breaker 1838 is open. Precautions and Limitations have been reviewed. The Unit Operator has been notified that the Diesel Generator will be made inoperable as a result of shutting down the 3A Diesel Engine at the Diesel Engine Control Cabinet. Shutdown of Diesel Generator 3A at the Diesel Engine Control Cabinet is being performed for testing purposes.
INITIATING CUES: The Unit Supervisor directs you to shutdown the 3A Diesel Engine from the Diesel Engine Control Cabinet per 3-OI-82 Standby Diesel Generator System, section 7.3.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 211 REV. NO. 0 PAGE 4 OF 8 START TIME Performance Step 1: Critical Not Critical _X 7.3 Shutdown at Diesel Engine Control Cabinet NOTE Diesel Generator shutdown from the Diesel Engine Control Cabinet is usually performed for test purposes.
[1] VERIFY the following initial conditions:
A. All Precautions and Limitations in Section 3.0 have been reviewed.
B. DG 3A(3B,3C,3D) Output Bkr 1838 (1842, 1832, 1836) is OPEN.
NOTES
- 1) The Diesel Generator will be made inoperable as a result of taking 3-BKR-254-000A(B,C,D)/06, DSL GEN 3A(3B,3C,3D) LOGIC RELAY PANEL (LOGIC BREAKER), in OFF and will be made operable when 3-BKR-254-000A(B,C,D)/06, DSL GEN 3A(3B,3C,3D)
LOGIC RELAY PANEL (LOGIC BREAKER), is returned to ON. REFER TO Tech Spec 3.8.1 and 3.8.2, Operation with Inoperable Equipment.
- 2) All manipulations of the Diesel Generator Logic Breaker are required to be logged in the Narrative Log.
[2] NOTIFY the Unit Operator that the Diesel Generator will be made inoperable as a result of performing this section.
Standard:
Given in initial conditions SAT UNSAT N/A COMMENTS:
JPM NO. 211 REV. NO. 0 PAGE 5 OF 8 Performance Step 2: Critical X Not Critical _
[3] PLACE 3-BKR-254-000A/06, DSL GEN 3A LOGIC RELAY PANEL (LOGIC BREAKER), in OFF On 3-BDGG-254-0003A , 125 VDC DSL SYS BAT BOARD A.
Standard:
Simulates placing 3-BKR-254-000A/06 in off.
SAT UNSAT N/A COMMENTS:
CUE: 3-BKR-254-000A/06 is OFF.
Performance Step 3: Critical X Not Critical _
[4] DEPRESS both ENGINE STOP push-buttons simultaneously to initiate the shutdown sequence.
Standard:
Simulates depressing both engine stop push buttons.
SAT UNSAT N/A COMMENTS:
CUE: Both engine stop push buttons are depressed.
Engine speed remains unchanged.
DG 3A Oil Pressure light has illuminated and alarmed.
If Lube oil pressure is CHECKED, CUE pressure is 5 psig.
Control Room reports they have Lube oil alarm and low oil pressure light.
Directs Emergency Shutdown of 3A Diesel Generator at Diesel Engine per section 7.5
JPM NO. 211 REV. NO. 0 PAGE 6 OF 8 Performance Step 4: Critical X Not Critical _
7.5 Emergency Shutdown at Diesel Engine CAUTION If diesel engine speed rises to greater than 1035 RPM, the Diesel Generator room should be evacuated immediately due to the potential for personnel injury.
NOTES
- 1) This section should only be performed during an emergency condition which requires the Diesel Generator to be stopped immediately. The Diesel Generator will be made inoperable as a result of performing this section. REFER TO Technical Specification 3.8.1 and 3.8.2, Operation With Inoperable Equipment.
- 2) When time permits, all manipulations of the Diesel Generator Logic Breaker are required to be logged in the Narrative Log.
[1] PULL OUT and HOLD the Injector Control Lever in the No Fuel position until the diesel engine comes to a complete stop.
Standard:
Simulates pulling out and holding the Injector Control Lever in the No Fuel position.
SAT UNSAT N/A COMMENTS:
CUE: The Diesel Engine is NOT slowing.
JPM NO. 211 REV. NO. 0 PAGE 7 OF 8 Performance Step 5: Critical Not Critical _X
[2] IF the diesel engine does NOT stop, THEN PERFORM the following:
[2.1] PLACE 3-BKR-254-000A/06, DSL GEN 3A LOGIC RELAY PANEL (LOGIC BREAKER), in OFF on 3-BDGG-254-0003A, 125 VDC DSL SYS BAT BOARD A.
[2.2] DEPRESS both ENGINE STOP push-buttons simultaneously on the Engine Control Cabinet to initiate the shutdown sequence (this will also stop the Priming Fuel Pump).
Standard:
Verifies 3-BKR-254-000A/06 is OFF and simulates depressing both engine stop push buttons.
SAT UNSAT N/A COMMENTS:
CUE: 3-BKR-254-000A/06 is still in OFF. Engine Stop push buttons depressed, Engine is still running.
JPM NO. 211 REV. NO. 0 PAGE 8 OF 8 Performance Step 6: Critical X Not Critical _
[2.3] CLOSE ENGINE DRIVEN FUEL PMP SUCT, 0-SHV-018-0664-3A.
Standard:
Simulates closing 0-SHV-018-0664-3A SAT UNSAT N/A COMMENTS:
CUE: 0-SHV-018-0664-3A is closed and Engine is slowing Performance Step 7: Critical X Not Critical _
[2.4] PLACE both DG 3A START CIRCUIT 1 CONT POWER BKR, 3-BKR-082-003A 35W1 and DG 3A START CIRCUIT 2 CONT POWER BKR, 3-BKR-082-003A 35W2 in the OFF position at the Electrical Control Cabinet.
Standard:
Simulates placing 3-BKR-082-003A 35W1 and 3-BKR-082-003A 35W2 in off.
SAT UNSAT N/A COMMENTS:
CUE: 3-BKR-082-003A 35W1 is in off and 3-BKR-082-003A 35W2 is in off.
Another Operator has been dispatched for step 3, JPM Complete.
END OF TASK STOP TIME
JPM NO. 212 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 212 TASK NUMBER: U-000-EM-83 TASK TITLE: Suppression Pool Water Inventory Removal K/A NUMBER: 295029 EK2.01 K/A RATING: RO 3.0 SRO: 3.3 TASK STANDARD: Pump started to remove water from suppression pool.
LOCATION OF PERFORMANCE: Plant REFERENCES/PROCEDURES NEEDED: 1-EOI Appendix-18 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are an Auxiliary Unit Operator. Suppression Pool water level is high and Unit 1 is currently operating in EOI-2 Primary Containment Control. Radiation Protection and Radwaste have been notified. Radwaste has been notified that approximately 15000 gallons will be pumped to Radwaste.
INITIATING CUES: The Unit Supervisor directs you to remove water from the suppression pool using RHR Drain Pump 1A, per 1-EOI Appendix-18 Suppression Pool Water Inventory Removal and Makeup.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 212 REV. NO. 0 PAGE 3 OF 7 IN-PLANT: I will explain the initial conditions and state the task to be performed. ALL STEPS WILL BE SIMULATED. Do NOT operate any plant equipment. SELF CHECKING 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. Observe ALL plant radiological and safety precautions. 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 "That's correct" (or That's incorrect", if applicable). When you have completed your assigned task, you will say, "My task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are an Auxiliary Unit Operator. Suppression Pool water level is high and Unit 1 is currently operating in EOI-2 Primary Containment Control. Radiation Protection and Radwaste have been notified. Radwaste has been notified that approximately 15000 gallons will be pumped to Radwaste.
INITIATING CUES: The Unit Supervisor directs you to remove water from the suppression pool using RHR Drain Pump 1A, per 1-EOI Appendix-18 Suppression Pool Water Inventory Removal and Makeup.
CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT
JPM NO. 212 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical Not Critical _X SUPPRESSION POOL WATER INVENTORY REMOVAL AND MAKEUP
- 1. IF................. Suppression Pool Water makeup is required, THEN...........CONTINUE in this procedure at Step 5.
- 2. IF ................. Gross fuel failure is suspected, THEN.............OBTAIN SED/SRO permission to pump down Suppression Pool BEFORE continuing in this procedure.
- 3. IF ................. Directed by SRO, THEN...........REMOVE water from Suppression Pool as follows:
- a. DISPATCH personnel to perform the following (Unit 1 RB, El 519 ft, Torus Area):
Standard:
Directed to remove water from pool SAT UNSAT N/A COMMENTS:
CUE: No Gross Fuel Failure is suspected
JPM NO. 212 REV. NO. 0 PAGE 5 OF 7 Performance Step 2: Critical Not Critical X_
Standard:
Simulates verifying 1-SHV-074-0786A open SAT UNSAT N/A COMMENTS:
CUE: 1-SHV-0786A is OPEN or AS Found Performance Step 3: Critical X Not Critical _
- 2) OPEN the following valves:
Standard:
Simulates opening 1-SHV-074-0564A and 1-SHV-074-0529A.
SAT UNSAT N/A COMMENTS:
CUE: 1-SHV-074-0564A and 1-SHV-074-0529A are OPEN.
JPM NO. 212 REV. NO. 0 PAGE 6 OF 7 Performance Step 4: Critical X Not Critical _
Standard:
Simulates unlocking and opening 1-SHV-074-0765A.
SAT UNSAT N/A COMMENTS:
CUE: 1-SHV-074-0765A is unlocked and open Performance Step 5: Critical Not Critical X_
- 4) NOTIFY Unit Operator that RHR Drain Pump 1A is lined up to remove water from Suppression Pool.
- 5) REMAIN at torus area UNTIL Unit 1 Operator directs starting of RHR Drain Pump 1A.
Standard:
Notifies Unit Operator and remains in area.
SAT UNSAT N/A COMMENTS:
CUE: Acknowledge notification and direct AUO to start RHR Drain Pump 1A.
JPM NO. 212 REV. NO. 0 PAGE 7 OF 7 NOTE: B and C are the Control Room Steps
- b. IF Main Condenser is desired drain path, THEN OPEN 1-FCV-74-62, RHR MAIN CNDR FLUSH VALVE.
- c. IF Radwaste is desired drain path, THEN PERFORM the following:
- 1) ESTABLISH communications with Radwaste.
- 2) OPEN 1-FCV-74-63, RHR RADWASTE SYS FLUSH VALVE.
Performance Step 6: Critical X Not Critical _
- d. NOTIFY personnel in Unit 1 RB, El 519 ft, Torus Area to START RHR Drain Pump A using 1-HS-074-0105, RHR DRAIN PUMP 1A (mounted on wall to left of pump).
Standard:
Simulates starting RHR Drain Pump 1A.
SAT UNSAT N/A COMMENTS:
CUE: RHR Drain Pump 1A is running.
This completes this JPM END OF TASK STOP TIME
JPM NO. 225 REV. NO. 0 PAGE 1 OF 11 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 225ap TASK NUMBER: 0-74-AB-01 TASK TITLE: Loss of Shutdown Cooling K/A NUMBER: 295021 AA1.02 K/A RATING: RO 3.5 SRO: 3.5 TASK STANDARD: Restore Shutdown Cooling and after RHR 2A Pump develops a seal leak, secures 2A RHR Pump and start 2C RHR Pump.
LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 2-AOI-74-1, 2-ARP-9-3D VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit 2 operator. Unit 2 is in Mode 3 (Recirc Loop B temp
> 212ºF) heading towards cold conditions for a refueling outage. RHR Loop I using 2A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.
An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. An Auxiliary Operator is standing by for 2A RHR Pump start.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2A RHR pump in accordance with 2-AOI-74-1 starting at step 10.
JPM NO. 225 REV. NO. 0 PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's 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 in Mode 3 (Recirc Loop B temp
> 212ºF) heading towards cold conditions for a refueling outage. RHR Loop I using 2A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.
An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. An Auxiliary Operator is standing by for 2A RHR Pump start.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2A RHR pump in accordance with 2-AOI-74-1 starting at step 10.
JPM NO. 225 REV. NO. 0 PAGE 4 OF 11 START TIME CAUTIONS
- 1) Reactor vessel stratification may occur until Shutdown Cooling is restored or a Reactor Recirculation Pump is placed in service.
- 2) Loss of Shutdown Cooling during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is most critical due to massive decay heat and limitations on the RHRSW Piping. If Shutdown Cooling is lost during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post reactor shutdown, priorities shall be placed on the recovery of shutdown cooling in an expeditious manner.
NOTE The following systems, if available, may be used as alternate methods of decay heat removal .Refer to the applicable Tec Spec Bases B 3.4.7, B 3.4.8, B 3.9.7, B 3.9.8 ADHR System- (0-OI-72)
Fuel Pool Cooling System- (2-OI-78)
RWCU System- (2-OI-69)
Ambient losses with natural or forced circulation Performance Step 1: Critical Not Critical X
[10] IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, THEN (Otherwise N/A)
WHEN conditions permit resetting Group 2 PCIS isolation are met, PERFORM the following:
[10.1] RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, and PCIS DIV II RESET, 2-HS-64-16A-S33, in reset.
STANDARD:
On Panel 2-9-4, RESETS Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, in reset and PCIS Div II RESET, 2-HS-64-16A-S33 to reset.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
[10.2] MOMENTARILY DEPRESS RHR SYS I(II) SD CLG INBD INJECT ISOL RESET, 2-XS-74-126 and 2-XS-74-132. VERIFY 2-IL-74-126 and 2-IL-74-132 extinguished.
STANDARD:
Momentarily Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 2-XS-74-132 and verifies 2-IL-74-132 extinguished.
SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical Not Critical X
[11] IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset, or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)
STANDARD:
N/As all Step 4.2[11], the PCIS signal is reset in step 10.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 6 OF 11 Performance Step 4: Critical X Not Critical
[12] IF the Group 2 PCIS Isolation has been reset, THEN (otherwise N/A)
RETURN the affected loop of RHR to Shutdown Cooling as follows:
[12.1] CLOSE RHR SYS I LPCI OUTBD INJECT VALVE, 2-FCV-74-52.
STANDARD:
Closes 2-FCV-74-52 SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical X Not Critical
[12.2] OPEN RHR SYS I LPCI INBD INJECT VALVE, 2-FCV-74-53.
STANDARD:
Opens 2-FCV-74-53 SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
[12.3] VERIFY RHR SYSTEM I MIN FLOW INHIBIT switch, 2-HS-74-148 in INHIBIT STANDARD:
Verifies 2-HS-74-148 in INHIBIT.
SAT UNSAT N/A COMMENTS:
Performance Step 7: Critical Not Critical X
[12.4] VERIFY CLOSED RHR SYSTEM I MIN FLOW VALVE, 2-FCV-74-7.
STANDARD:
Verifies 2-FCV-74-7 is closed.
SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical Not Critical X
[12.5] VERIFY CLOSED RHR PUMP 2A and 2C SUPPR POOL SUCT VLVs, 2-FCV-74-1 and 2-FCV-74-12.
STANDARD:
Verifies 2-FCV-74-1 & 12 are closed.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 8 OF 11 Performance Step 9: Critical Not Critical X
[12.6] VERIFY OPEN RHR PUMP 2A and 2C SD COOLING SUCT VLVs, 2-FCV-74-2 and 2-FCV-74-13.
STANDARD:
Verifies 2-FCV-74-2 & 13 are open.
SAT UNSAT N/A COMMENTS:
Performance Step 10: *Critical X Not Critical
[12.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 2-FCV-74-47 and 2-FCV-74-48.
STANDARD:
Opens *2-HS-74-47 and verifies 2-FCV-74-48 open.
SAT UNSAT N/A COMMENTS:
Performance Step 11: Critical X Not Critical
[12.8] RESTART RHR PUMP 2A using 2-HS-74-5A.
STANDARD:
Starts 2A RHR Pump SAT UNSAT N/A COMMENTS:
CUE: Once RHR Pump 2A is started insert alarm ON for RHR System I Pump A Seal Leakage High
JPM NO. 225 REV. NO. 0 PAGE 9 OF 11 Performance Step 12: Critical Not Critical X Notify Unit Supervisor 2A RHR Pump Seal Leakage High CUE: [As US] Acknowledge report. If necessary, ask; What do you recommend?
STANDARD:
Notifies Unit Supervisor.
SAT UNSAT N/A COMMENTS:
Performance Step 13: Critical Not Critical X RHR SYS I PUMP A SEAL LEAKAGE HIGH A. VERIFY RHR HX HEAT EXCHANGER A OUTLET valve, 2-SHV-74-10, OPEN by red position indicating light on Panel 2-9-3.
B. DISPATCH personnel to investigate pump seal leak off.
STANDARD:
Verifies 2-SHV-74-10 open and dispatches personnel to investigate SAT UNSAT N/A COMMENTS:
Driver: If called for Seal Leakage on RHR Pump 3A report significant seal leakage.
JPM NO. 225 REV. NO. 0 PAGE 10 OF 11 Performance Step 14: Critical X Not Critical C. IF possible to swap pumps, THEN STOP the operating Pump and START another RHR pump.
STANDARD:
Stops 2A RHR Pump and starts 2C RHR Pump.
SAT UNSAT N/A COMMENTS:
Performance Step 15: Critical X Not Critical
[12.9] THROTTLE RHR SYS I LPCI OUTBD INJECT VALVE, 2-FCV-74-52, to establish and maintain RHR flow as indicated by 2-FI-74-50, RHR SYS I FLOW, as follows:
RHR Pumps in 1 2 Operation Loop Flow 7,000 to 10,000 gpm 14,000 to 20,000 gpm Loop Flow (1 or more fuel 6,000 to 6,500 gpm N/A bundles removed from core)
STANDARD:
Manipulates 2-HS-74-52 to obtain RHR System I Loop flow between 7,000 and 10,000 gpm on 2-FI-74-50.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 11 OF 11 Performance Step 16: Critical Not Critical X
[12.10] WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.
STANDARD:
Dispatched personnel to verify RHR Pump 2C breaker closing spring recharged and investigate 2A RHR pump failure.
SAT UNSAT N/A COMMENTS:
CUE: If requested, Acknowledge and state Operator in route Performance Step 17: Critical X Not Critical
[12.11] SLOWLY THROTTLE RHR HX 2C RHRSW OUTLET VALVE, 2-FCV-23-40, to obtain desired cooldown rate.
STANDARD:
Throttles 2-FCV-23-40 open to commence cooldown SAT UNSAT N/A COMMENTS:
CUE: That completes this task.
END OF TASK STOP TIME:
JPM NO. 225 REV. NO. 0 PAGE 1 OF 11 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 225ap TASK NUMBER: 0-74-AB-01 TASK TITLE: Loss of Shutdown Cooling K/A NUMBER: 295021 AA1.02 K/A RATING: RO 3.5 SRO: 3.5 TASK STANDARD: Restore Shutdown Cooling and after RHR 3A Pump develops a seal leak, secures 3A RHR Pump and start 3C RHR Pump.
LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED: 3-AOI-74-1, 3-ARP-9-3D VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: ______________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ___ UNSATISFACTORY_____
SIGNATURE: ______________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are a Unit 3 operator. Unit 3 is in Mode 3 (Recirc Loop B temp
> 212ºF) heading towards cold conditions for a refueling outage. RHR Loop I using 3A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.
An inadvertent loss of 3B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 3B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 3B RPS. An Auxiliary Operator is standing by for 3A RHR Pump start.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 3A RHR pump in accordance with 3-AOI-74-1 starting at step 9.
JPM NO. 225 REV. NO. 0 PAGE 3 OF 11 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are a Unit 3 operator. Unit 3 is in Mode 3 (Recirc Loop B temp
> 212ºF) heading towards cold conditions for a refueling outage. RHR Loop I using 3A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.
An inadvertent loss of 3B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 3B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 3B RPS. An Auxiliary Operator is standing by for 3A RHR Pump start.
INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 3A RHR pump in accordance with 3-AOI-74-1 starting at step 9.
JPM NO. 225 REV. NO. 0 PAGE 4 OF 11 START TIME CAUTIONS
- 1) Reactor vessel stratification may occur until Shutdown Cooling is restored or a Reactor Recirculation Pump is placed in service.
- 2) Loss of Shutdown Cooling during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is most critical due to massive decay heat and limitations on the RHRSW Piping. If Shutdown Cooling is lost during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post reactor shutdown, priorities shall be placed on the recovery of shutdown cooling in an expeditious manner.
NOTE The following systems, if available, may be used as alternate methods of decay heat removal .Refer to the applicable Tec Spec Bases B 3.4.7, B 3.4.8, B 3.9.7, B 3.9.8 ADHR System- (0-OI-72)
Fuel Pool Cooling System- (3-OI-78)
RWCU System- (3-OI-69)
Ambient losses with natural or forced circulation Performance Step 1: Critical Not Critical X
[9] IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, THEN (Otherwise N/A)
WHEN conditions permit resetting Group 2 PCIS isolation are met, PERFORM the following:
[9.1] RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 3-HS-64-16A-S32, and PCIS DIV II RESET, 3-HS-64-16A-S33, in reset.
STANDARD:
On Panel 3-9-4, RESETS Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 3-HS-64-16A-S32, in reset and PCIS Div II RESET, 3-HS-64-16A-S33 to reset.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 5 OF 11 Performance Step 2: Critical Not Critical X
[9.2] MOMENTARILY DEPRESS RHR SYS I(II) SD CLG INBD INJECT ISOL RESET, 3-XS-74-126 and 3-XS-74-132. VERIFY 3-IL-74-126 and 3-IL-74-132 extinguished.
STANDARD:
Momentarily Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 3-XS-74-132 and verifies 3-IL-74-132 extinguished.
SAT UNSAT N/A COMMENTS:
Performance Step 3: Critical Not Critical X
[10] IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset, or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)
STANDARD:
N/As all Step 4.2[11], the PCIS signal is reset in step 10.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 6 OF 11 Performance Step 4: Critical X Not Critical
[11] IF the Group 2 PCIS Isolation has been reset, THEN (otherwise N/A)
RETURN the affected loop of RHR to Shutdown Cooling as follows:
[11.1] CLOSE RHR SYS I LPCI OUTBD INJECT VALVE, 3-FCV-74-52.
STANDARD:
Closes 3-FCV-74-52 SAT UNSAT N/A COMMENTS:
Performance Step 5: Critical X Not Critical
[11.2] OPEN RHR SYS I LPCI INBD INJECT VALVE, 3-FCV-74-53.
STANDARD:
Opens 3-FCV-74-53 SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 7 OF 11 Performance Step 6: Critical Not Critical X
[11.3] VERIFY RHR SYSTEM I MIN FLOW INHIBIT switch, 3-HS-74-148 in INHIBIT STANDARD:
Verifies 3-HS-74-148 in INHIBIT.
SAT UNSAT N/A COMMENTS:
Performance Step 7: Critical Not Critical X
[11.4] VERIFY CLOSED RHR SYSTEM I MIN FLOW VALVE, 3-FCV-74-7.
STANDARD:
Verifies 3-FCV-74-7 is closed.
SAT UNSAT N/A COMMENTS:
Performance Step 8: Critical Not Critical X
[11.5] VERIFY CLOSED RHR PUMP 3A and 3C SUPPR POOL SUCT VLVs, 3-FCV-74-1 and 3-FCV-74-12.
STANDARD:
Verifies 3-FCV-74-1 & 12 are closed.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 8 OF 11 Performance Step 9: Critical Not Critical X
[11.6] VERIFY OPEN RHR PUMP 3A and 3C SD COOLING SUCT VLVs, 3-FCV-74-2 and 3-FCV-74-13.
STANDARD:
Verifies 3-FCV-74-2 & 13 are open.
SAT UNSAT N/A COMMENTS:
Performance Step 10: *Critical X Not Critical
[11.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 3-FCV-74-47 and 3-FCV-74-48.
STANDARD:
Opens *3-HS-74-47 and verifies 3-FCV-74-48 open.
SAT UNSAT N/A COMMENTS:
Performance Step 11: Critical X Not Critical
[11.8] RESTART RHR PUMP 3A using 3-HS-74-5A.
STANDARD:
Starts 3A RHR Pump SAT UNSAT N/A COMMENTS:
CUE: Once RHR Pump 3A is started insert alarm ON for RHR System I Pump A Seal Leakage High
JPM NO. 225 REV. NO. 0 PAGE 9 OF 11 Performance Step 12: Critical Not Critical X Notify Unit Supervisor 3A RHR Pump Seal Leakage High.
CUE: [As US] Acknowledge report. If necessary, ask; What do you recommend?
STANDARD:
Notifies Unit Supervisor.
SAT UNSAT N/A COMMENTS:
Performance Step 13: Critical Not Critical X RHR SYS I PUMP A SEAL LEAKAGE HIGH A. VERIFY RHR Hx A disch valve, 3-HCV-74-10, OPEN by red position indicating light on Panel 3-9-3.
B. DISPATCH personnel to investigate pump seal leak off.
STANDARD:
Verifies 3-HCV-74-10 open and dispatches personnel to investigate SAT UNSAT N/A COMMENTS:
Driver: If called for Seal Leakage on RHR Pump 3A report significant seal leakage.
JPM NO. 225 REV. NO. 0 PAGE 10 OF 11 Performance Step 14: Critical X Not Critical C. IF possible, THEN STOP pump and START another RHR pump.
STANDARD:
Stops 3A RHR Pump and starts 3C RHR Pump.
SAT UNSAT N/A COMMENTS:
Performance Step 15: Critical X Not Critical
[11.9] THROTTLE RHR SYS I LPCI OUTBD INJECT VALVE, 3-FCV-74-52, to establish and maintain RHR flow as indicated by 3-FI-74-50, RHR SYS I FLOW, as follows:
RHR Pumps in 1 2 Operation Loop Flow 7,000 to 10,000 gpm 14,000 to 20,000 gpm Loop Flow (1 or more fuel 6,000 to 6,500 gpm N/A bundles removed from core)
STANDARD:
Manipulates 3-HS-74-52 to obtain RHR System I Loop flow between 7,000 and 10,000 gpm on 3-FI-74-50.
SAT UNSAT N/A COMMENTS:
JPM NO. 225 REV. NO. 0 PAGE 11 OF 11 Performance Step 16: Critical Not Critical X
[11.10] WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.
STANDARD:
Dispatched personnel to verify RHR Pump 3C breaker closing spring recharged and investigate 3A RHR pump failure.
SAT UNSAT N/A COMMENTS:
CUE: If requested, Acknowledge and state Operator in route Performance Step 17: Critical X Not Critical
[11.11] SLOWLY THROTTLE RHR HX 3C RHRSW OUTLET VALVE, 3-FCV-23-40, to obtain desired cooldown rate.
STANDARD:
Throttles 3-FCV-23-40 open to commence cooldown SAT UNSAT N/A COMMENTS:
CUE: That completes this task.
END OF TASK STOP TIME:
JPM NO. 80 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 80ap TASK NUMBER: U-085-AB-05 TASK TITLE: RESPOND TO CONTROL ROD DRIFT IN K/A NUMBER: 201002A2.02 K/A RATING: RO 3.2 SRO: 3.3 TASK STANDARD: Respond to a Control Rod Drift In as directed by AOI-85-5 LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: AOI-85-5, SR-3.1.3.3 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: __________________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ____ UNSATISFACTORY______
SIGNATURE: ___________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are the Unit Operator at the controls. SR 3.1.3.3 is complete for fully withdrawn control rods.
INITIATING CUES: The Unit Supervisor directs you to perform Surveillance 3.1.3.3 Control Rod Exercise Test for Withdrawn Control Rods, for partially withdrawn control rods only.
JPM NO. 80 REV. NO. 0 PAGE 3 OF 7 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the Unit Operator at the controls. SR 3.1.3.3 is complete for fully withdrawn control rods.
INITIATING CUES: The Unit Supervisor directs you to perform Surveillance 3.1.3.3 Control Rod Exercise Test for Withdrawn Control Rods, for partially withdrawn control rods only.
JPM NO. 80 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical X Not Critical _
[1] SELECT desired control rod by DEPRESSING appropriate CRD ROD SELECT pushbutton 2-XS-85-40.
[2] OBSERVE the following for selected control rod:
- CHECK CRD ROD SELECT pushbutton is brightly ILLUMINATED.
- CHECK white light on the Full Core Display ILLUMINATED.
- CHECK Rod Out Permit light is ILLUMINATED.
Standard:
Selects a withdrawn control rod SAT UNSAT N/A COMMENTS:
Examiner Note: May select any partially withdrawn control rod in any order.
Performance Step 2: Critical X Not Critical _
[3] INSERT control rod one notch by performing the following:
[3.1] PLACE CRD CONTROL SWITCH 2-HS-85-48 in ROD IN and RELEASE.
[3.2] OBSERVE control rod settles into the desired position and ROD SETTLE light extinguishes.
Standard:
Inserts withdrawn control rod one notch SAT UNSAT N/A COMMENTS:
JPM NO. 80 REV. NO. 0 PAGE 5 OF 7 Performance Step 3: Critical X Not Critical _
[5] WITHDRAW selected control rod one notch by performing the following:
[5.1] PLACE CRD CONTROL SWITCH 2-HS-85-48 in ROD OUT NOTCH and RELEASE.
[5.2] OBSERVE control rod settles into the desired position and ROD SETTLE light extinguishes.
Standard:
Withdraws withdrawn control rod one notch SAT UNSAT N/A COMMENTS:
JPM NO. 80 REV. NO. 0 PAGE 6 OF 7 Performance Step 4: Critical Not Critical _X
[7] DOCUMENT completion of control rod test as follows:
[7.1] PERFORMER INITIAL Attachment 2 (Control Rod Exercise Data Sheet) in the box corresponding to the control rod coordinates for the control rod just exercised to document proper movement and CRD latching.
[9] REPEAT Steps 7.3[1] through 7.3[8] for all remaining, operable, partially withdrawn control rods.
Standard:
Initials attachment 2 for exercised control rod and continues to exercise rods.
SAT UNSAT N/A COMMENTS:
Examiner Note: Performs above actions for two control rods.
Simulator Driver: INSERT the rod drift malfunction RD07 for a minimum of two control rods. Once two partially withdrawn control rods have been exercised.
JPM NO. 80 REV. NO. 0 PAGE 7 OF 7 Performance Step 5: Critical X Not Critical _
Performer recognizes CR Drift in and responds per 2-AOI-85-5.
Standard:
Responds per 2-AOI-85-5.
SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical X Not Critical 4.1.[1] IF multiple rods are drifting into the core, THEN Manually SCRAM Reactor. REFER TO 2-AOI-100-1.
Standard:
Recognizes multiple rod drifts and manually SCRAMS the Reactor.
- Depresses both scram pushbuttons. ________
- Places mode switch in shutdown. ________
- Verifies All Rods in. ________
CUE: REPEAT BACK SCRAM REPORT THEN STATE, THIS COMPLETES THE JPM. THAT WILL BE ALL FOR NOW, ANOTHER OPERATOR WILL CONTINUE IN 2-AOI-100-1 STOP TIME
JPM NO. 80 REV. NO. 0 PAGE 1 OF 7 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ________________________________
JPM NUMBER: 80ap TASK NUMBER: U-085-AB-05 TASK TITLE: RESPOND TO CONTROL ROD DRIFT IN K/A NUMBER: 201002A2.02 K/A RATING: RO 3.2 SRO: 3.3 TASK STANDARD: Respond to a Control Rod Drift In as directed by AOI-85-5 LOCATION OF PERFORMANCE: SIMULATOR REFERENCES/PROCEDURES NEEDED: AOI-85-5, SR-3.1.3.3 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS: __________________________________
Additional comment sheets attached? YES NO RESULTS: SATISFACTORY ____ UNSATISFACTORY______
SIGNATURE: ___________ DATE: __
EXAMINER
BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE INITIAL CONDITIONS: You are the Unit Operator at the controls. SR 3.1.3.3 is complete for fully withdrawn control rods.
INITIATING CUES: The Unit Supervisor directs you to perform Surveillance 3.1.3.3 Control Rod Exercise Test for Withdrawn Control Rods, for partially withdrawn control rods only.
JPM NO. 80 REV. NO. 0 PAGE 3 OF 7 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 "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.
INITIAL CONDITIONS: You are the Unit Operator at the controls. SR 3.1.3.3 is complete for fully withdrawn control rods.
INITIATING CUES: The Unit Supervisor directs you to perform Surveillance 3.1.3.3 Control Rod Exercise Test for Withdrawn Control Rods, for partially withdrawn control rods only.
JPM NO. 80 REV. NO. 0 PAGE 4 OF 7 START TIME Performance Step 1: Critical X Not Critical _
[1] SELECT desired control rod by DEPRESSING appropriate CRD ROD SELECT pushbutton 3-XS-85-40.
[2] OBSERVE the following for selected control rod:
- CHECK CRD ROD SELECT pushbutton is brightly ILLUMINATED.
- CHECK white light on the Full Core Display ILLUMINATED.
- CHECK Rod Out Permit light is ILLUMINATED.
Standard:
Selects a withdrawn control rod SAT UNSAT N/A COMMENTS:
Examiner Note: May select any partially withdrawn control rod in any order.
Performance Step 2: Critical X Not Critical _
[3] INSERT control rod one notch by performing the following:
[3.1] PLACE CRD CONTROL SWITCH 3-HS-85-48 in ROD IN and RELEASE.
[3.2] OBSERVE control rod settles into the desired position and ROD SETTLE light extinguishes.
Standard:
Inserts withdrawn control rod one notch SAT UNSAT N/A COMMENTS:
JPM NO. 80 REV. NO. 0 PAGE 5 OF 7 Performance Step 3: Critical X Not Critical _
[5] WITHDRAW selected control rod one notch by performing the following:
[5.1] PLACE CRD CONTROL SWITCH 3-HS-85-48 in ROD OUT NOTCH and RELEASE.
[5.2] OBSERVE control rod settles into the desired position and ROD SETTLE light extinguishes.
Standard:
Withdraws withdrawn control rod one notch SAT UNSAT N/A COMMENTS:
JPM NO. 80 REV. NO. 0 PAGE 6 OF 7 Performance Step 4: Critical Not Critical _X
[7] DOCUMENT completion of control rod test as follows:
[7.1] PERFORMER INITIAL Attachment 2 (Control Rod Exercise Data Sheet) in the box corresponding to the control rod coordinates for the control rod just exercised to document proper movement and CRD latching.
[9] REPEAT Steps 7.3[1] through 7.3[8] for all remaining, operable, partially withdrawn control rods.
Standard:
Initials attachment 2 for exercised control rod and continues to exercise rods.
SAT UNSAT N/A COMMENTS:
Examiner Note: Performs above actions for two control rods.
Simulator Driver: INSERT the rod drift malfunction RD07 for a minimum of two control rods. Once two partially withdrawn control rods have been exercised.
JPM NO. 80 REV. NO. 0 PAGE 7 OF 7 Performance Step 5: Critical X Not Critical _
Performer recognizes CR Drift in and responds per 3-AOI-85-5.
Standard:
Responds per 3-AOI-85-5.
SAT UNSAT N/A COMMENTS:
Performance Step 6: Critical X Not Critical 4.1.[1] IF multiple rods are drifting into the core, THEN Manually SCRAM Reactor. REFER TO 3-AOI-100-1.
Standard:
Recognizes multiple rod drifts and manually SCRAMS the Reactor.
- Depresses both scram pushbuttons. ________
- Places mode switch in shutdown. ________
- Verifies All Rods in. ________
CUE: REPEAT BACK SCRAM REPORT THEN STATE, THIS COMPLETES THE JPM. THAT WILL BE ALL FOR NOW, ANOTHER OPERATOR WILL CONTINUE IN 3-AOI-100-1 STOP TIME