Text

Initial Exam 2008-302 Final SIM/In-Plant JPMs
	ML091810132
Person / Time
Site:	Browns Ferry
Issue date:	06/30/2009
From:	; NRC/RGN-II
To:	;
References
	JPM No. 606F, Rev 5, U-000-EM-73
	Download: ML091810132 (216)
	v • d • e

JPM NO. 606F REV. NO.5 PAGE 1 of 11 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCEMEASURf?

JPM NUMBER: 606F TITLE: EOI APPENDIX-3A - SLC INJECTION TASK NUMBER: U-OOO-EM-73

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151M "A" UNIT-21 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 606F REV. NO.5 PAGE 2 of 11 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 05/12/01 All Initial issue 1 10/22/98 All Re-formatted 2 10103/00 All General revision 3 09/13/02 All Modified failure mode for NRC 4 07/08/06 All General revision 5 06/12/08 All General revision & re-format

JPM NO. 606F REV. NO.5 PAGE 3 of 11

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BROWNS FERRY NUCLEARPLANT JQePERFORMANCE MEASIIRE; OPERATOR: _______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 606F TASK NUMBER: U-000-EM-73 TASK TITLE: EOI APPENDIX-3A - SLC INJECTION K/A NUMBER: 211000A4.02 KIA RATING: RO 4.2 SRO 4.2 TASK STANDARD: PERFORM OPERATION NECESSARY TO START AN SLC PUMP AND INJECT SLC SOLUTION INTO THE RPV AS DIRECTED BY 2-EOI APPENDIX-3A PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM _

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-3A, Rev 5 VALIDATION TIME: S IMULATOR: __--05::. . ;. 0::;....;:0'---_

LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 606F REV. NO.5 PAGE 4 of 11

(

BROWNS FER,RY NUCLEARP'LANJ

.. J.0BPERF0RMANCEIVIEASORE 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 an operator on Unit 2.

The reactor has scrammed and control rods failed to insert.

2-EOI-1 has been entered and followed to RC/Q-12.

Reactor power is >5%.

RWL has been lowered per EOI C5 and Appendix-4.

MSIV's are closed.

INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 2-EOI Appendix-3A, SLC Injection.

JPM NO. 606F REV. NO.5 PAGE 5 of 11 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-EOI Appendix-3A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

1. UNLOCK and PLACE 2-HS-63-6A, SLC PUMP 2A12B, control switch in START-A or START -B position.

STANDARD:

Unlocked and Placed SLC pump control switch in either START-A or START-B position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 606F REV. NO.5 PAGE 6 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. CHECK SLC System for injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 9-5 (2-XA-55-5B, Window 20).

2-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 2-IL-63-11, SLC FLOW, red light illuminated on Panel 9-5,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 9-5 (2-XA-55-5B, Window 14).

STANDARD:

Verified selected SLC pump is injecting to RPV by Observing the above parameters.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 606F REV. NO.5 PAGE 7 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF ..... Proper system operation CANNOT be verified, THEN ... RETURN to Step 1 and START other SLC pump.

STANDARD:

N/A - verified proper operation of running pump and continues to step 4.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

4. VERIFY RWCU isolation by observing the following:

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RWCU Pumps 2A and 2B tripped

"

2-FCV-69-1, RWCU INBD SUCT ISOLATION VALVE closed

2-FCV-69-2, RWCU OUTBD SUCT ISOLATION VALVE closed

2-FCV-69-12, RWCU RETURN ISOLATION VALVE closed STANDARD:

Examinee Recognized the failure of RWCU to isolate and manually Closes 2-FCV-69-1 by taking 2-HS-69-1 to the close direction on panel 9-4 OR trips both RWCU pumps.

(closing 69-1 will trip both pumps) (Attempts but Notices that 69-2 and 69-12 will NOT close and notifies US) Verified illuminated Green valve position indicating lights above the 69-1 valve handswitch and Verified RWCU pumps tripped by Observing illuminated Green breaker position indicating lights above pump handswitches. (Only closing 69-1 OR tripping the pumps is Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

(

JPM NO. 606F REV. NO.5 PAGE 8 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. VERIFY ADS inhibited.

STANDARD:

Verified 2-XS-1-159A and 2-XS-1-161A, Panel 2-9-3, in the INHIBIT position and Verified Alarm Panel 2-XA-55-3C, Window 18, "ADS LOGIC BUS A INHIBITED and 2-XA-55-3C, Window 31, "ADS LOGIC BUS B INHIBITED", in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

6. MONITOR reactor power for downward trend.

STANDARD:

Monitored all available APRMs/l RMs for downward reactor power trend.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 606F REV. NO.5 PAGE 9 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

7. MONITOR 2-Ll-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping approximately 1% per minute.

STANDARD:

Observed 2-Ll-63-1A and Verified SLC storage tank level decreasing.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 606F REV. NO.5 PAGE 10 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 11 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 an operator on Unit 2.

The reactor has scrammed and control rods failed to insert.

2-EOI-1 has been entered and followed to RC/Q-12.

Reactor power is >5%.

RWL has been lowered per EOI C5 and Appendix-4.

MSIV's are closed.

INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 2-EOI Appendix-3A, SLC Injection.

JPM NO. 328F REV. NO. 0 PAGE 1 of 11 JPM NUMBER: 328F TITLE: EOI APPENDIX-3A - SLC INJECTION TASK NUMBER: U-OOO-EM-73 151M "A" UNIT-31 SUBMITTED BY: DATE: - - - - -

VALIDATED BY: DATE: _ _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: __________________ DATE: _____

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 328F REV. NO. 0 PAGE 2 of 11

(

REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/17/08 All Initial issue

JPM NO. 328F REV. NO. 0 PAGE 3 of 11 OPERATOR: _______________________________________________

RO SRO DATE: _ _ _ _ _ __

JPM NUMBER: 328F TASK NUMBER: U-OOO-EM-73 TASK TITLE: EOI APPENDIX-3A - SLC INJECTION K/A NUMBER: 211000A4.02 KIA RATING: RO 4.2 SRO 4.2 TASK STANDARD: PERFORM OPERATION NECESSARY TO START AN SLC PUMP AND INJECT SLC SOLUTION INTO THE RPV AS DIRECTED BY 3-EOI APPENDIX-3A PERFORMANCE LOCATION: S IMULATOR ---,-X-,--_

REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-3A, Rev 1 VALIDATION TIME: SIMULATOR: __--.::5:::..!.::O~O~_ LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _________________ DATE: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 4 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 an operator on Unit 3.

The reactor has scrammed and control rods failed to insert.

3-EOI-1 has been entered and followed to RC/Q-12.

Reactor power is > 5%.

Suppression pool temperature is 105°F and rising.

INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 3-EOI Appendix-3A, SLC Injection.

JPM NO. 328F REV. NO. 0 PAGE 5 of 11

( START TIME _ _ _ _ __

Simulator Driv$r: ThisJ~Mr,e'quirQs,ahATWS > 5% and Torus temp -105°F,and 3..FCV+Q9-1, failed$uch'that it vviUnot A u t o C l o $ e . , . .". . . . ,. .. .

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 3-EOI Appendix-3A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

(

1. UNLOCK and PLACE 3-HS-63-6A, SLC PUMP 3A/3B, control switch in START PUMP 3A or START PUMP 3B position.

STANDARD:

Unlocked and Placed SLC pump control switch in either START-A or START-B position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 6 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. CHECK SLC System for injection by observing the following:

Selected pump starts, as indicated by red light illuminated above pump control switch.

Squib valves fire, as indicated by SQUIB VALVE A and B CONTINUITY blue lights extinguished,

SLC SQUIB VALVE CONTINUITY LOST Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 20).

3-PI-63-7A, SLC PUMP DISCH PRESS, indicates above RPV pressure.

System flow, as indicated by 3-IL-63-11, SLC FLOW, red light illuminated on Panel 3-9-5,

SLC INJECTION FLOW TO REACTOR Annunciator in alarm on Panel 3-9-5 (3-XA-55-5B, Window 14).

STANDARD:

Verified selected SLC pump is injecting to RPV by Observing the above parameters.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 7 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF ..... Proper system operation CANNOT be verified, THEN '" RETURN to Step 1 and START other SLC pump.

STANDARD:

N/A ~ verified proper operation of running pump and continues to step 4.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

4. VERIFY RWCU isolation by observing the following:

RWCU Pumps 3A and 3B tripped

3~FCV~69~1, RWCU INBD SUCT ISOLATION VALVE closed

3~FCV~69~2, RWCU OUTBD SUCT ISOLATION VALVE closed

3~FCV~69~12, RWCU RETURN ISOLATION VALVE closed STANDARD:

Examinee Recognized the failure of 3~FCV~69~1 to isolate and manually Closes 3~FCV~

69-1 by taking 3-HS~69-1 to the close direction on panel 9-4. Verified illuminated Green valve position indicating lights above the (other) respective valve handswitches and Verified RWCU pumps tripped by Observing illuminated Green breaker position indicating lights above pump handswitches. (Only closing 69-1 is Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 8 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. VERIFY ADS inhibited.

STANDARD:

Verified 3-XS-1-159A and 3-XS-1-161A, Panel 3-9-3, in the INHIBIT position and Verified Alarm Panel 3-XA-55-3C, Window 18, "ADS LOGIC BUS A INHIBITED and 3-XA-55-3C, Window 31, "ADS LOGIC BUS B INHIBITED", in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

6. MONITOR reactor power for downward trend.

STANDARD:

Monitored all available APRMsIIRMs for downward reactor power trend.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 9 of 11 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

7. MONITOR 3-Ll-63-1A, SLC STORAGE TANK LEVEL, and CHECK that level is dropping approximately 1% per minute.

STANDARD:

Observed 3-Ll-63-1A and Verified SLC storage tank level decreasing.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

8. WHEN ... EITHER of the following exists:

SLC tank level drops to 0%,

OR

As directed by SRO, THEN ... STOP SLC Pump 3A or 38.

STANDARD:

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 328F REV. NO. 0 PAGE 10 of 11

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 11 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 an operator on Unit 3.

The reactor has scrammed and control rods failed to insert.

3-EOI-1 has been entered and followed to RC/Q-12.

Reactor power is > 5%.

Suppression pool temperature is 105°F and rising.

INITIATING CUES: The Unit Supervisor has directed you to inject SLC per 3-EOI Appendix-3A, SLC Injection.

JPM NO. 14F REV. NO.5 PAGE 1 of 17 BRPWN&"F:ERRYf\JUCLEARPLANT JS:BPI;RF,():RMANCE MEASURE .

JPM NUMBER: 14F TITLE: 2-EOI APPENDIX-5A - INJECTION SYSTEMS LlNEUP-CONDENSATE/FEEDWATER, HP HTRs ISOLATED.

TASK NUMBER: U-OOO-EM-29

( 151M "8" UNIT -21 SUBMITTED BY: DATE:. _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: ________________ DATE: _____

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 14F REV. NO.5 PAGE 2 of 17 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 10/23/98 All Initial issue 1 10/23/01 3,4 Procedure revision, format, setpoint change 2 08/14/03 All Procedure revision, editorial, add setup cue 3 08/24/06 3 Procedure revision 4 06/01/07 All General revision 5 06/12/08 All General revision & re-format

JPM NO. 14F REV. NO.5 PAGE 3 of 17 OPERATOR: _______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 14F TASK NUMBER: U-000-EM-29 TASK TITLE: 2-EOI APPENDIX-5A - INJECTION SYSTEMS LlNEUP-CONDENSATE/FEEDWATER, HP HTRs ISOLATED.

K/A NUMBER: 295031 EA 1.08 KIA RATING: RO 3.8 SRO 3.9 TASK STANDARD: PERFORM CONTROL ROOM ACTIONS REQUIRED TO ESTABLISH THE CONDENSATE/FEEDWATER SYSTEM AS AN RPV INJECTION SYSTEM lAW 2-EOI APPENDIX-5A PERFORMANCE LOCATION: SIMULATOR.x PLANT __ CONTROL ROOM _

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-5A, Rev 8 VALIDATION TIME: SIMULATOR: __1,-,1~:0:...::c0_ LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 4 of 17 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. The reactor has scrammed due to a trip of all Reactor Feedwater pumps and EOI-1 has been followed through RC/L-3.

INITIATING CUES: The problem that caused the trip of the RFP's has been corrected and the Unit Supervisor has directed you to restore and maintain RPV water level +2" to +51" as directed by 2-EOI Appendix-5A, INJECTION SYSTEMS LINEUP -

CONDENSATE/FEEDWATER.

JPM NO. 14F REV. NO.5 PAGE 5 of 17 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-EOI Appendix-5A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. VERIFY Condensate System in service, supplying suction to RFPs.

STANDARD:

Verified condensate system in service by observation of valve alignment, condensate and condensate booster pump operation and RFP alignment.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 6 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. VERIFY OPEN MSIVs, supplying steam to RFPTs.

STANDARD:

Verified MSIVs open by illuminated RED valve position indicating lamps on Panel 2-9-3 (vertical panel or benchboard).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. VERIFY Hotwell Pressure below -7 in. Hg.

STANDARD:

Verified Hotwell Pressure below -7 inches Hg. as indicated on 2-XR-2-2, Panel 2-9-6 or ICS computer.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

4. VERIFY CLOSED 2-FCV-1-121(129)(137), RFPT 2A(2B)(2C) LP STEAM SUPPLY VALVE.

STANDARD:

Verified illuminated RED valve position indicating lamps above 2-HS-1-121, (129), or (137) on Panel 2-9-6 is lit for RFPT 2A, B, and C and take actions to close valve(s).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. VERIFY OPEN 2-FCV-1-125(133)(141), RFPT 2A(2B)(2C) HP STEAM SUPPLY VALVE.

STANDARD:

Verified illuminated RED valve position indicating lamp above 2-HS-1-125, (133), or (141 ).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 8 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

6. DEPRESS 2-HS-46-8A(9A)(1 OA), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER, and VERIFY amber light is illuminated.

STANDARD:

Depressed 2-HS-46-8A, (9A), or (1 OA) for selected RFPT Speed Cont Raise/Lower and Verified amber light illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

7. VERIFY a Main Oil Pump is running for RFPT to be started.

STANDARD:

Verified a Main Oil Pump is running for the selected RFPT by observing a RED indicating light above handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 9 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

8. VERIFY for EACH of the following pushbuttons, the green light is illuminated and the red light is extinguished:

2-HS-3-208A, RX WTR LVL CH A HI RFPT/MT TRIP RESET

2-HS-3-2088, RX WTR LVL CH 8 HI RFPT/MT TRIP RESET STANDARD:

Verified GREEN light illuminated and RED light extinguished on 2-HS-3-208A & 2088.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

9. VERIFY OPEN the following valves:

2-FCV-3-75, HP HTR 2A1 FW OUTLET ISOL VLV

2-FCV-3-76, HP HTR 281 FW OUTLET ISOL VLV

2-FCV-3-77, HP HTR 2C1 FW OUTLET ISOL VLV STANDARD:

Recognizes HP heater inlet and outlet valves closed and Opens a minimum of one set of the HP Heater FW Isolation Valves (inlet and outlet, 3-38 & 3-75, or 3-31 & 3-76, or 3-24 & 3-77).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 10 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

10. DEPRESS 2-HS-3-124A(150A)(175A), RFPT 2A(2B)(2C) TRIP RESET, and CHECK the following:

Blue light extinguished.

HP Stop Valve OPEN as indicated by red light above the following, as applicable:

o 2-HS-3-108, RFPT 2A HP STOP VLV TEST o 2-HS-3-134, RFPT 2B HP STOP VLV TEST o 2-HS-3-159, RFPT 2C HP STOP VLV TEST

LP Stop Valve OPEN as indicated by red light above the following, as applicable:

o 2-HS-3-107, RFPT 2A LP STOP VLV TEST o 2-HS-3-133, RFPT 2B LP STOP VLV TEST o 2-HS-3-158, RFPT 2C LP STOP VLV TEST STANDARD:

Depressed TRI PRESET PB 3-124A, (150A), or (175A) for the selected pump, and Checked the BLUE light extinguished, HP Stop Valve Open as indicated by RED light above HS for the selected pump, and the LP Stop Valve Open as indicated by the RED light above HS for the selected pump.

SAT UNSAT N/A _ _ COMMENTS:, _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 11 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

11. VERIFY OPEN 2-FCV-3-20(13)(6), RFP 2A(2B)(2C) MIN FLOW VALVE.

STANDARD:

Verified illuminated RED valve position indicating light for minimum flow valve 3-20, (13), or (6)above HS for selected pump.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

12. PLACE 2-HS-46-112A(138A)(163A), RFPT 2A(2B)(2C) START/LOCAL ENABLE, in START.

STANDARD:

Placed Start/Local Enable switch for the selected pump 46-112A, (138A), or (163A) in START.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 12 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

13. CHECK RFPT 2A(2B)(2C) speed increases to approximately 600 rpm.

STANDARD:

Checked RFPT Speed accelerated to approximately 600 rpm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

14. VERIFY OPEN 2-FCV-3-19(12)(5), RFP 2A(2B)(2C) DISCHARGE VALVE.

STANDARD:

Verified illuminated RED valve position indicating light above discharge valve for the selected pump, 3-19, (12), or (5).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 13 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

15. RAISE RFPT 2A(2B)(2C) speed UNTIL RFP discharge pressure is approximately equal to RPV pressure using ANY of the following methods on Panel 2-9-5:

Using individual 2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 2-SIC-46-8(9)(10), RFPT 2A(2B)(2C) SPEED CONTROL PDS in MANUAL, OR

Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(10), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:

(

Raised selected RFPT speed Until RFP discharge pressure was approximately equal to RPV pressure utilizing one of the methods above on Panel 2-9-5.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 14 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

16. SLOWLY RAISE speed of RFPT UNTIL RFW flow to the RPV is indicated using ANY of the following methods on Panel 2-9-5:

Using individual 2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 2-SIC-46-8(9)(10), RFPT 2A(2B)(2C) SPEED CONTROL PDS in MANUAL, OR

Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(10), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:

Slowly raised speed of selected RFPT Until RFW flow to the RPV is indicated utilizing one of the above methods.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

17. ADJUST RFPT speed as necessary to control injection using ANY of the following methods on Panel 2-9-5:

Using individual 2-HS-46-8A(9A)(10A), RFPT 2A(2B)(2C) SPEED CONT RAISE/LOWER switch in MANUAL GOVERNOR, OR

Using individual 2-SIC-46-8(9)(1 0), RFPT 2A(2B)(2C) SPEED CONTROL PDS in MANUAL, OR

Using 2-LlC-46-5, REACTOR WATER LEVEL CONTROL PDS, in MANUAL with individual 2-SIC-46-8(9)(1 0), RFPT 2A(2B)(2C) SPEED CONTROL PDS in AUTO STANDARD:

( Adjusted speed of selected RFPT as required utilizing one of the above methods.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 14F REV. NO.5 PAGE 16 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ __

PAGE 17 of 17 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. The reactor has scrammed due to a trip of all Reactor Feedwater pumps and EOI-1 has been followed through RC/L-3.

INITIATING CUES: The problem that caused the trip of the RFP's has been corrected and the Unit Supervisor has directed you to restore and maintain RPV water level +2" to +51" as directed by 2-EOI Appendix-SA, INJECTION SYSTEMS LINEUP -

CONDENSATE/FEEDWATER.

JPM NO. 55F REV. NO. 0 PAGE 1 of 17 JPM NUMBER: 55F TITLE: 2-EOI APPENDIX EMERGENCY VENTING PRIMARY CONTAINMENT TASK NUMBER: U-OOO-EM-63

(

151M "e" UNIT -21 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE:. _ _ __

APPROVED BY: DATE:. _ _ __

TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ _ _ __ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 55F REV. NO. 0 PAGE 2 of 17 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 11/19/08 All Initial Issue

JPM NO. 55F REV. NO. 0 PAGE 3 of 17 OPERATOR: _________________________________________________

RO SRO DATE: _____________

JPM NUMBER: 55F TASK NUMBER: U-OOO-EM-63 TASK TITLE: 2-EOI APPENDIX EMERGENCY VENTING PRIMARY CONTAINMENT KIA NUMBER: 295024EA 1.14 KIA RATING: RO 3.4 SRO 3.5 TASK STANDARD: PERFORM CONTROL ROOM OPERATIONS REQUIRED TO EMERGENCY VENTILATE PRIMARY CONTAINMENT PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM __

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-13, Rev 6 VALIDATION TIME: SIMULATOR: _ _ __ LOCAL: _________

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAM INER S IGNATU RE: _____________________ DATE :_____________

(

JPM NO. 55F REV. NO. 0 PAGE 4 of 17 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 an Operator. A large leak inside primary containment has developed on Unit 2. The reactor scrammed and several control rods are still not fully inserted to 00 and primary containment pressure is approaching 55 psig and rising. The US is performing EOI-2 at PC/P-15.

INITIATING CUES: The Unit Supervisor directs you to emergency vent primary containment as directed by 2-EOI Appendix-13.

JPM NO. 55F REV. NO. 0 PAGE 5 of 17 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-EOI Appendix-13.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. NOTIFY Shift Manager / SED of the following:

Emergency Venting of Primary Containment is in progress.

Off-Gas Release Rate Limits will be exceeded.

STANDARD:

Notified Shift Manager/SED by voice contact with examiner.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 6 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. VENT the Suppression Chamber as follows (Panel 9-3):

a. IF ................ EITHER of the following exists:

Suppression Pool water level CANNOT be determined to be below 20 ft, OR

Suppression Chamber CANNOT be vented, THEN .......... CONTINUE in this procedure at Step 3.

STANDARD:

Verified Suppression Pool Level below 20 ft using 2-Ll-64-159A, SUPPR POOL WATER LEVEL and/or ICS.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

b. PLACE keylock switch 2-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, in PERM.

STANDARD:

Placed 2-HS-64-222B in the PERM position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

c. CHECK blue indicating light above 2-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, illuminated.

STANDARD:

Verified BLUE indicating lamp above 2-HS-64-222B Illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

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

STANDARD:

Placed 2-HS-64-222A in the OPEN position and Verified illuminated RED valve position indicating lamp above associated hand switch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 8 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

e. PLACE keylock switch 2-HS-64-221 B, HARDENED SUPPR CHBR VENT INBD PERMISSIVE, in PERM.

STANDARD:

Placed 2-HS-64-221 B in the PERM position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

f. CHECK blue indicating light above 2-HS-64-221 B, HARDENED SUPPR CHBR VENT INBD PERMISSIVE, illuminated.

STANDARD:

Verified BLUE indicating lamp above 2-HS-64-221 B Illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 9 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

g. OPEN 2-FCV-64-221, HARDENED SUPPR CHBR VENT INBD ISOL VLV.

STANDARD:

Placed 2-HS-64-221A in the OPEN position and recognized 2-FCV-64-221 failed to open and goes to step 3.0.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF .............. Suppression Chamber vent path is NOT available, THEN ....... VENT the Drywell as follows:

a. NOTIFY Shift Manager I SED that Secondary Containment integrity failure is possible.

STANDARD:

Notifies Shift Manager that Secondary Containment integrity failure is possible.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 10 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

b. NOTIFY Radiation Protection that Reactor Building is being evacuated due to imminent failure of Primary Containment vent ducts.

STANDARD:

Notifies Radiation Protection that Reactor Building is being evacuated due to imminent failure of Primary Containment vent ducts.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

c. EVACUATE ALL Reactor Buildings using P.A. System.

STANDARD:

Evacuates all Reactor Buildings.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 11 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

d. START ALL available SGTS trains.

STANDARD:

Verifies all 3 trains of SBGT are in service.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

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

STANDARD:

Verifies 2-FCV-64-36 is closed by illuminated green light above handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 12 of 17

(

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

f. VERIFY OPEN the following dampers (Panel 9-25):

2-FCO-64-40, REACTOR ZONE EXH TO SGTS

2-FCO-64-41, REACTOR ZONE EXH TO SGTS STANDARD:

Goes to panel 9-25 and Opens 2-FCO-64-40 and 41.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

g. VERIFY CLOSED 2-FCV-64-29, DRYWELL VENT INBD ISOL VALVE

( (Panel 9-3 or Panel 9-54).

STANDARD:

Verifies 2-FCV-64-29 is closed by illuminated green light above handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO.

PAGE 13 of 17

° PERFORMANCE STEP: CRITICAL NOT CRITICAL x

h. DISPATCH personnel to Unit 2 Auxiliary Instrument Room to perform the following:

1) REFER TO Attachment 1 and OBTAIN one 12-in. banana jack jumper from EOI Equipment Storage Box

2) LOCATE terminal strip DO in Panel 9-43, Front

3) JUMPER 00-76 to 00-77 (Panel 9-43)

4) NOTIFY Unit Operator that jumper for 2-FCV-64-30, DRYWELL VENT OUTBD ISOLATION VLV, is in place.

STANDARD:

Directs AUO or Outside US to perform step 3. h.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

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

STANDARD:

Verifies 2-FCV-64-30 is Open by illuminated red light above handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 14 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

j. PLACE keylock switch 2-HS-84-36, SUPPR CHBR/DW VENT ISOL BYP SELECT, to DRYWELL (Panel 9-54).

STANDARD:

Places keylock 2-HS-64-36 to Open (Critical) and Verifies illuminated red light above handswitch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

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

(

STANDARD:

Verifies 2-FCV-64-29 is Open by illuminated red light above handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x I. CHECK Drywell and Suppression Chamber pressure lowering.

STANDARD:

Verifies Drywell and Suppression Chamber pressure lowering. (have simulator driver lower leak, if necessary)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

m. MAINTAIN Primary Containment pressure below 55 psig using 2-FCV 29, DRYWELL VENT INBD ISOL VALVE, as directed by SRO.

STANDARD:

N/A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55F REV. NO. 0 PAGE 16 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 17 of 17 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 an Operator. A large leak inside primary containment has developed on Unit 2. The reactor scrammed and several control rods are still not fully inserted to 00 and primary containment pressure is approaching 55 psig and rising. The US is performing EOI-2 at PC/P-15.

INITIATING CUES: The Unit Supervisor directs you to emergency vent primary containment as directed by 2-EOI Appendix-13.

JPM NO. 201F REV. NO. 2 PAGE 1 of 24

(

JPM NUMBER: 201 F TITLE: LOSS OF SHUTDOWN COOLING TASK NUMBER: 0-74-AB-01 151M "0" UNIT -21 SUBMITTED BY: DATE:. _ _ __

VALIDATED BY: DATE:. _ _ _ __

APPROVED BY: DATE: _ _ _ __

TRAINING PLANTCONCURRENCE: ______________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 201F REV. NO. 2 PAGE 2 of 24 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/13/03 All Initial issue 1 03/28/06 All Procedure revision 2 06/29/08 All General revision & re-format

JPM NO. 201F REV. NO. 2 PAGE 30f24 OPERATOR: _________________________________________________

RO SRO DATE: _____________

JPM NUMBER: 201 F TASK NUMBER: 0-74-AB-01 TASK TITLE: LOSS OF SHUTDOWN COOLING K/A NUMBER: 295021 AA 1.02 K/A RATING: RO 3.5 SRO 3.5 TASK STANDARD: SUCCESSFULLY RESTORE SHUTDOWN COOLING FOLLOWING LOSS DUE TO INADVERTENT RPS ACTUATION.

PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED: 2-AOI-74-1, Rev 32 VALIDATION TIME: SIMULATOR: 25:00 LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 4 of 24 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 (Rx temp> 212°F) heading towards cold conditions for a refueling outage.

RHR Loop II using 2B RHR Pump was in shutdown cooling and Unit 3 is carrying 1350 gpm RHRSW flow for "B" RHRSW Header.

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.

The Unit Supervisor has notified the Shift Manager of the problem.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2B RHR pump in accordance with 2-AOI-74-1.

JPM NO. 201F REV. NO. 2 PAGE 50f24 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-AOI-74-1.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months post reactor shutdown, priorities are required to be placed on the recovery of shutdown cooling in an expeditious manner [BFN PER 02-003140-000].

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- (0-01-72)

Fuel Pool Cooling System- (2-01-78)

RWCU System- (2-01-69)

Ambient losses with natural or forced circulation

JPM NO. 201F REV. NO. 2 PAGE 6 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x 4.2 Subsequent Actions

[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s). (Otherwise N/A)

STANDARD:

Determines no EOI entry conditions have been met and N/As step.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[2] NOTIFY the Shift Manager.

STANDARD:

N/A - given in the initial conditions.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 7 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[3] IF Refueling is in progress, THEN NOTIFY the Refueling Floor SRO. (Otherwise N/A)

STANDARD:

N/A - Mode 3 given in initial conditions. Not required to notify Refueling Floor SRO.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[4] REVIEW EPIP-1, Emergency Plan Classification Logic, for entry conditions.

STANDARD:

N/A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 8of24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[5] IF Shutdown Cooling isolates on low RPV water level or high Drywell press (GROUP 2 ISOL) AND RPV water level needs restoring using LPCI, THEN (Otherwise N/A)

PERFORM the following before reaching -122 inches RPV water level:

[5.1] PERFORM .... .

[5.2] DEPRESS ..... .

[5.3] IF ................ .

STANDARD:

Determines water level does NOT need restoring, N/A's all section 4.2[5] and continues to step 4.2[6]

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 9 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[6] IF Primary Containment Integrity is required, THEN VERIFY RHR system discharge piping pressure is being maintained

>TRM 3.5.4 Limits. REFER TO 2-01-74. (Otherwise N/A)

STANDARD:

Determines Primary Containment IS required in Mode 3 and Verifies pressure is ~ 35 psig on 2-PI-74-65 for Loop" RHR. (2-01-74r137 P&L 3.1.1 or verifies pressure above mark on 2-PI-74-65).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTES

1) With the Reactor in Cold Shutdown Condition (Mode 4 or Mode 5), reactor coolant stratification may be indicated by one of the following:

Reactor pressure above 0 psig with any reactor coolant temperature indication reading at or below 212°F.

Differential temperatures of 50°F or greater between either RX VESSEL BOTTOM HEAD (FLANGE DR LINE) 2-TE-56-29 (8) temperatures and RX VESSEL FW NOZZLE N4B END (N4B INBD)(N4B END)(N4D INBD) 2-TE 13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.

With recirculation pumps and shutdown cooling out of service, a Feedwater sparger temperature of 200°F or greater on any RX VESSEL FW NOZZLE (N4B END (N4B INBD)(N4D END)(N4D INBD) 2-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 2-TR-56-4.

2) [NER/C] For purposes of thermal stratification monitoring, the bottom head drain line is more representative as long as there is flow in the line. [GE SIL 251 and 430]

JPM NO. 201F REV. NO. 2 PAGE 10 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7] PLOT heatup/cooldown rate as necessary.

REFER TO 2-SR-3.4.9.1 (1).

STANDARD:

Checks step off and continues to step 4.2[8]

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

(

JPM NO. 201F REV. NO. 2 PAGE 11 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[8] DIRECT the STA to ESTIMATE the following times at least once per shift until a method of decay heat removal is restored:

[8.1] DETERMINE the time since shutdown.

[8.2] DETERMINE the current RPV heat-up rate from 2-SR-3.4.9.1 (1),

or, if reactor coolant stratification is suspected, USE Illustration 1.

IF additional information is required to determine the heat-up rates, THEN CONTACT Reactor Engineer.

[8.3] DETERMINE the reactor coolant temperature or use the last valid reactor coolant temperature available.

[8.4] ESTIMATE the time for reactor coolant temperature to reach 212°F, using data obtained in Steps 4.2[8.1] through 4.2[8.3].

[8.5] IF the Reactor Vessel head is removed and the cavity is flooded with the fuel pool gates installed, THEN (Otherwise N/A)

ESTIMATE the time for reactor coolant temperature to reach 125°F and 150°F using a plot of the actual heatup rate or Illustration 1.

STANDARD:

Directs STA to estimate the heat up rate and check for stratification at least once per shift.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 12 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[9] IF the loss of Shutdown Cooling is due to inadequate RHRSW flow, THEN START the standby RHRSW pump for the appropriate header.

REFER TO 0-01-23. (Otherwise N/A)

STANDARD:

N/As Step 4.2[9] since there is no loss of RHRSW.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[10] IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, WHEN conditions which permit resetting Group 2 PCIS isolation are met, THEN (Otherwise N/A)

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. 201F REV. NO. 2 PAGE 13 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[10.2] MOMENTARILY DEPRESS RHR SYS 1(11) 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 II SD CLG INBD INJECT ISOL RESET, 2-XS-74-132 (Critical). Verify 2-IL-74-132 extinguished (Not critical). Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 2-XS-74-126 (Not critical) and Verify 2-IL-74-126 extinguished (Not critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 14 of 24 PERFORMANCE STEP: 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)

PERFORM the following:

[11.1] VERIFy ... .

[11.2] OBTAIN .. .

[11 .3] DEFEAT .. .

[11.4] IF ........... .

STANDARD:

N/As all Step 4.2[11], the PCIS signal should have reset above.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 15 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12] IF the Group 2 PCIS Isolation has been reset, THEN RETURN the affected loop of RHR to Shutdown Cooling as follows.

[12.1] CLOSE RHR SYS 1(11) LPCI OUTBD INJECT VALVE, 2-FCV-74-52(66).

STANDARD:

Places 2-HS-74-66 in close until only GREEN valve position indicating lamp is illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTE 2-POI-74-2 aligns the RHR system to prevent SDC isolations during modes 4 and 5 operations. For Step 4.2[12.2], it accomplishes this by opening RHR SYS 1(11) LPCI INBD INJECT VALVE, 2-FCV-74-53(67) and opening its associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve.

JPM NO. 201F REV. NO. 2 PAGE 16 of 24 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.2] OPEN RHR SYS 1(11) LPCIINBD INJECT VALVE, 2-FCV-74-53(67)

(IF the valve is aligned per 2-POI-74-2 (valve open with its breaker open), THEN N/A this step).

STANDARD:

Opens 2-FCV-74-67 (Critical) and verifies only RED valve position indicating lamp illuminated (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.3] VERIFY RHR SYSTEM 1(11) MIN FLOW INHIBIT switch, 2-HS-74-148(149) in INHIBIT STANDARD:

Verifies 2-HS-74-149 is in INHIBIT.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 17of24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.4] VERIFY CLOSED RHR SYSTEM 1(11) MIN FLOW VALVE, 2-FCV-74-7(30).

STANDARD:

Verifies 2-FCV-74-30 is CLOSED.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.5] VERIFY CLOSED RHR PUMP 2A(2B) and 2C(2D) SUPPR POOL SUCT VLVs, 2-FCV-74-1(24) and 2-FCV-74-12(35).

STANDARD:

Verifies 2-FCV-74-24 and 2-FCV-74-35 are CLOSED.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 18 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.6] VERIFY OPEN RHR PUMP 2A(2B) and 2C(2D) SO COOLING SUCT VLVs, 2-FCV-74-2(25) and 2-FCV-74-13(36).

STANDARD:

Verifies 2-FCV-74-25 and 2-FCV-74-36 are OPEN.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTE 2-POI-74-2 aligns the RHR system to prevent SOC isolations during modes 4 and 5 operations. For Step 4.2[12.7], it accomplishes this by opening either RHR SHUTDOWN COOLING SUCT OUTBD VLV, 2-FCV-74-47 or INBD ISOL VLV, 2-FCV-74-48 and opening the associated breaker. If an isolation is received the valve will NOT close because the breaker is open. Therefore, to restore Shutdown Cooling, it is NOT necessary to manipulate this already open valve. The other valve will still have power and if closed, is required to be reopened.

JPM NO. 201F REV. NO. 2 PAGE 19 of 24 PERFORMANCE STEP: 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 (If either valve is aligned per 2-POI-74-2 (valve open with its breaker open), this step will be N/A for that valve. The other valve will still need to be opened to restore a suction path).

STANDARD:

Places 2-HS-74-47 in Open (Critical) and Verified 2-FCV-74-47 only RED valve position indicating lamp is illuminated (Not Critical) and Verified 2-FCV-74-48 only RED valve position indicating lamp is illuminated (Not Critical) (2-POI-74-2 is not in effect since not currently in Mode 4 or 5).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.8] RESTART tripped RHR pump(s) RHR PUMP 2A(2C)(2B)(2D) using 2-HS-74-5A(16A)(28A)(39A)

STANDARD:

Places 2-HS-74-28A (2B RHR Pump) in Start and Recognizes Failure to start.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 20 of 24 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Notify US of pump failure to start.

STANDARD:

Notifies US. (He/she should recommend starting 20 RHR pump)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL Start 20 RHR pump.

STANDARD:

Places 2-HS-74-39A (20 RHR Pump) in Start (Critical) and Verifies only RED light illuminated above handswitch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 21 of 24

(

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.9] THROTTLE RHR SYS 1(11) LPCI OUTBD INJECTION VALVE, 2-FCV-74-52(66), to establish and maintain RHR flow as indicated by 2-FI-74-50(64), RHR SYS 1(11) FLOW, as follows:

RHR Pumps 1 2 in Operation Loop Flow 7,000 to 10,000 14,000 to 20,000 Loop Flow (1 or more fuel bundles removed from core) 6,000 to 6,500 N/A STANDARD:

Manipulates 2-HS-74-66 to obtain RHR System II Loop flow between 7,000 and 10,000 gpm on 2-FI-74-64.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 22 of 24 PERFORMANCE STEP: 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.

CUE: [As Al../Q;;;

~'t~al{~r~p' STANDARD:

Dispatched personnel to Verify RHR Pump 20 breaker closing spring recharged and investigate 2B RHR pump failure.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.11 ] SLOWLY THROTTLE RHR HX 2A(2C)(2B)(2D) RHRSW OUTLET VALVE, 2-FCV-23-34(40)(46)(52), to obtain desired cooldown rate.

STANDARD:

Using 2-HS-23-52A and co-ordinating with Unit 3, reduces 02 RHRSW pump cooling flow to -900 gpm as indicated on 2-FI-23-54 (while Unit 3 picks up minimum flow) and using 2-HS-23-46A raises B2 RHRSW pump dilution flow to -4000 gpm (while Unit 3 lowers their flow to 0 gpm) as indicated on 2-FI-23-48.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 201F REV. NO. 2 PAGE 23 of 24

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ __

PAGE 24 of 24 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 (Rx temp> 212°F) heading towards cold conditions for a refueling outage.

RHR Loop" using 28 RHR Pump was in shutdown cooling and Unit 3 is carrying 1350 gpm RHRSW flow for "8" RHRSW Header.

An inadvertent loss of 28 RPS bus resulted in a partial isolation of RHR shutdown cooling.

RPS 28 has been restored on the alternate supply.

Another operator is assisting with recovery from the loss of 28 RPS.

The Unit Supervisor has notified the Shift Manager of the problem.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 28 RHR pump in accordance with 2-AOI-74-1.

JPM NO. 401F REV. NO. 1 PAGE 1 of 22 JPM NUMBER: 401 F TITLE: LOSS OF SHUTDOWN COOLING TASK NUMBER: 0-74-AB-01 151M "0" UNIT -31 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 401F REV. NO. 1 PAGE 2 of 22 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 12/29/07 All Initial issue 1 08/16/08 All General revision & re-format

JPM NO. 401F REV. NO. 1 PAGE 30f22 OPERATOR: _______________________________________________

RO SRO DATE: _ _ _ _ _ __

JPM NUMBER: 401 F TASK NUMBER: 0-74-AB-01 TASK TITLE: LOSS OF SHUTDOWN COOLING KIA NUMBER: 295021 AA1.02 KIA RATING: RO 3.5 SRO 3.5 TASK STANDARD: SUCCESSFULLY RESTORE SHUTDOWN COOLING FOLLOWING LOSS DUE TO INADVERTENT RPS ACTUATION.

PERFORMANCE LOCATION: S IMULATO R --=..X-'---_

REFERENCES/PROCEDURES NEEDED: 3-AOI-74-1, Rev 16 VALIDATION TIME: SIMULATOR: 25:00 LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 4 of22 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 (Rx temp >212 of) heading towards cold conditions for a refueling outage.

RHR Loop II using 38 RHR Pump was in shutdown cooling and Unit 2 is carrying 1350 gpm RHRSW flow for "8" RHRSW Header.

An inadvertent loss of 38 RPS bus resulted in a partial isolation of RHR shutdown cooling.

RPS 38 has been restored on the alternate supply.

Another operator is assisting with recovery from the loss of 38 RPS.

The US has notified the Shift Manager of the problem.

INITIATING CUES: The US directs you to restore shutdown cooling using 38 RHR pump in accordance with 3-AOI-74-1.

(

JPM NO. 401F REV. NO. 1 PAGE 50f22 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained a copy of 3-AOI-74-1.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

3.0 AUTOMATIC ACTIONS None 4.0 OPERATOR ACTIONS 4.1 Immediate Actions None 4.2 Subsequent Actions 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months post reactor shutdown, priorities shall be placed on the recovery of shutdown cooling in an expeditious manner [BFN PER 02-003140-000].

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- (0-01-72)

Fuel Pool Cooling System- (3-01-78)

RWCU System- (3-01-69)

Ambient losses with natural or forced circulation

JPM NO. 401F REV. NO. 1 PAGE 6 of 22

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[1] IF any EOI entry condition is met, THEN ENTER the appropriate EOI(s). (Otherwise N/A)

STANDARD:

Determines no EOI entry conditions have been met and N/As step.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[2] NOTIFY the Shift Manager.

STANDARD:

N/A - Given in the initial conditions.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 7 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[3] IF Refueling is in progress, THEN NOTIFY the Refueling Floor SRO. (Otherwise N/A)

STANDARD:

Mode 3 given in initial conditions. Not required to notify Refueling Floor SRO.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[4] REVIEW EPIP-1, Emergency Plan Classification Logic, for entry conditions. (Otherwise N/A)

STANDARD:

N/A SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 8 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[5] IF Shutdown Cooling isolates on low RPV water level or high Drywell press (GROUP 2 ISOL) AND RPV water level needs restoring using LPCI, THEN (Otherwise N/A)

PERFORM the following before reaching -122 inches RPV water level:

[5.1] Verify Closed ....

[5.2] Depress ....

[5.3] If the RHR. ...

STANDARD:

Determines water level does NOT need restoring, N/A's all section 4.2[5] and continues to step 4.2[6]

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 90f22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[6] IF Primary Containment Integrity is required, THEN (Otherwise N/A)

VERIFY RHR system discharge piping pressure is being maintained

> TRM 3.5.4 Limits. REFER TO 3-01-74.

STANDARD:

Determines Primary Containment IS required in Mode 3 and Verifies pressure is

~ 35 psig on 3-PI-74-65 for Loop II RHR. (3-01-74rS3 P&L 3.1.M).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTES

1) With the Reactor in Cold Shutdown Condition (Mode 4 or Mode 5), reactor coolant stratification may be indicated by one of the following:

Reactor pressure above 0 psig with any reactor coolant temperature indication reading at or below 212°F.

Differential temperatures of 50°F or greater between either RX VESSEL BOTTOM HEAD (FLANGE DR LINE) 3-TE-56-29 (S) temperatures and RX VESSEL FW NOZZLE N4B END (N4B INBD)(N4B END)(N4D INBD) 3-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 3-TR-56-4.

With recirculation pumps and shutdown cooling out of service, a Feedwater sparger temperature of 200°F or greater on any RX VESSEL FW NOZZLE (N4B END (N4B INBD)(N4D END)(N4D INBD) 3-TE-56-13(14)(15)(16) temperatures from the REACTOR VESSEL METAL TEMPERATURE recorder, 3-TR-56-4.

2) [NER/C] For purposes of thermal stratification monitoring, the bottom head drain line is more representative as long as there is flow in the line. [GE SIL 251 and 430]

JPM NO. 401F REV. NO. 1 PAGE 10 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7] PLOT heatup/cooldown rate as necessary. REFER TO 3-SR-3.4.9.1 (1).

STANDARD:

Checks step off and continues to step 4.2[8] (since another Operator is performing the SR), Candidate may select HUR on SPDS.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 11 of 22

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[8] REQUEST the SRO to ESTIMATE the following times at least once per shift until a method of decay heat removal is restored:

[8.1] DETERMINE the time since shutdown.

[8.2] DETERMINE the current RPV heat-up rate from 3-SR-3.4.9.1 (1),

or, if reactor coolant stratification is suspected, use Illustration 1.

[8.2.1] IF additional information is required to determine the heat-up rates, THEN NOTIFY Reactor Engineer.

[8.3] DETERMINE the reactor coolant temperature or use the last valid reactor coolant temperature available.

[8.4] IF the Reactor Vessel head is removed and the cavity is flooded with the fuel pool gates installed, THEN (Otherwise N/A)

ESTIMATE the time for reactor coolant temperature to reach 125°F and 150°F using a plot of the actual heatup rate or Illustration 1.

[8.5] ESTIMATE the time for reactor coolant temperature to reach 212°F, using data obtained in Steps 4.2[8.1] through 4.2[8.3].

STANDARD:

Requests SRO to estimate the heat up rate and check for stratification at least once per shift.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 12 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[9] IF the loss of Shutdown Cooling is due to inadequate RHRSW flow, THEN (Otherwise N/A)

START the standby RHRSW pump for the appropriate header. REFER TO 0-01-23.

STANDARD:

N/As Step 4.2[9] since there is no loss of RHRSW.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: 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, 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. 401F REV. NO. 1 PAGE 13 of 22 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[10.2] MOMENTARILY DEPRESS RHR SYS 1(11) 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 II SD CLG INBD INJECT ISOL RESET, 3-XS-74-132 (Critical). VERIFY 3-IL-74-132 extinguished (Not critical). Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 3-XS-74-126 (Not critical) and verify 3-IL-74-126 extinguished (Not critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: 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)

PERFORM the following:

[11.1] Verify .. ..

[11.2] Obtain .. ..

[11.3] Defeat.. ..

[11.4] If conditions ....

STANDARD:

N/As all Step 4.2[11], the PCIS signal should have reset above.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 14 of 22 PERFORMANCE STEP: 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 1(11) LPCI OUTBD INJECT VALVE, 3-FCV-74-52(66).

STANDARD:

Closes 3-HS-74-66 (Critical) and verifies ONLY GREEN valve position indicating lamp is illuminated (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.2] OPEN RHR SYS 1(11) LPCI INBD INJECT VALVE, 3-FCV-74-53(67).

STANDARD:

Opens 3-FCV-74-67 (Critical) and verifies ONLY RED valve position indicating lamp illuminated (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 15 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.3] VERIFY RHR SYSTEM 1(11) MIN FLOW INHIBIT switch, 3-HS-74-148(149) in INHIBIT STANDARD:

Verifies 3-HS-74-149 in INHIBIT.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.4] VERIFY CLOSED RHR SYSTEM 1(11) MIN FLOW VALVE, 3-FCV-74-7(30).

STANDARD:

Verifies 3-FCV-74-30 is closed.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 16 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.5] VERIFY CLOSED RHR PUMP 3A(3B) and 3C(3D) SUPPR POOL SUCT VLVs, 3-FCV-74-1 (24) and 3-FCV-74-12(35).

STANDARD:

Verifies 3-FCV-74-24 & 35 are closed.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.6] VERIFY OPEN RHR PUMP 3A(3B) and 3C(3D) SD COOLING SUCT VLVs, 3-FCV-74-2(25) and 3-FCV-74-13(36).

( STANDARD:

Verifies 3-FCV-74-25 & 36 are open.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 17 of 22 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 3-FCV-74-47 and 3-FCV-74-48.

STANDARD:

Places 3-HS-74-47 in Open (Critical)and verified 3-FCV-74-48 ONLY RED valve position indicating lamp is illuminated (Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.8] RESTART RHR PUMP 3A(3C)(3B)(3D) using 3-HS-74-5A, (16A), (28A), (39A).

STANDARD:

Places 3-HS-74-28A (3B RHR Pump) in Start and Recognizes Failure To Start.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 18 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Notify US of pump failure to start.

STANDARD:

Notifies US.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL Start 3D RHR pump.

STANDARD:

PLACES 3-HS-74-39a for 3D RHR Pump in START (Critical) and verifies it starts by red light above handswitch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 19 of 22 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[12.9] THROTTLE RHR SYS 1(11) LPCI OUTBD INJECT VALVE, 3-FCV-74-52(66), to establish and maintain RHR flow as indicated by 3-FI-74-50(64), RHR SYS 1(11) 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-74-66 to obtain RHR System II Loop flow between 7,000 and 10,000 gpm on 3-FI-74-64.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 20 of 22 PERFORMANCE STEP: 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 3D breaker closing spring recharged and investigate 3B RHR pump failure.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[12.11] SLOWLY THROTTLE RHR HX 3A(3C)(3B)(3D) RHRSW OUTLET VALVE, 3-FCV-23-34(40)(46)(52), to obtain desired cooldown rate.

STANDARD:

Using 3-HS-23-52A and co-ordinating with Unit 2, reduces 02 RHRSW pump cooling flow to -900 gpm as indicated on 3-FI-23-54 (while Unit 2 picks up minimum flow) and using 3-HS-23-46A raises B2 RHRSW pump dilution flow to -4000 gpm (while Unit 2 lowers their flow to 0 gpm) as indicated on 3-FI-23-48.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 401F REV. NO. 1 PAGE 21 of 22 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 22 of 22 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 (Rx temp >212 of) heading towards cold conditions for a refueling outage.

RHR Loop" using 3B RHR Pump was in shutdown cooling and Unit 2 is carrying 1350 gpm RHRSW flow for "B" RHRSW Header.

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.

The US has notified the Shift Manager of the problem.

INITIATING CUES: The US directs you to restore shutdown cooling using 3B RHR pump in accordance with 3-AOI-74-1.

JPM NO. 376 REV. NO. 1 PAGE 2 of 14 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 11/09/07 All Initial issue 1 08/28/08 All General revision & re-format

JPM NO. 376 REV. NO. 1 PAGE 3 of 14 OPERATOR: _______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 376 TASK NUMBER: U-OOO-EM-64 TASK TITLE: 3-EOI APPENDIX-14B - CAD OPERATION TO THE DRYWELL KIA NUMBER: 223001A4.04 KIA RATING: RO 3.5 SRO 3.6 TASK STANDARD: PERFORM MANIPULATIONS AS DIRECTED BY 3-EOI APPENDIX-14B REQUIRED TO ADMIT NITROGEN TO THE DRYWELL WITH THE CAD SYSTEM PERFORMANCE LOCATION: S 1M U LATOR -----'-X-'--_

REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-14B, Rev 4 VALIDATION TIME: S IMULATOR:_-.;5;;....:...:O::.....;:O,--_ LOCAL: _ _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 4 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 an Operator.

A LOCA has led to fuel failure and a rising level of hydrogen concentration in the Unit 3 Drywell.

EOI-2 has been exited and SAMG-2 entered.

INITIATING CUES: The Unit Supervisor has directed you to align CAD System A to the drywell as directed by SAMG-2 step G-4 using 3-EOI Appendix-14B.

JPM NO. 376 REV. NO. 1 PAGE 5 of 14 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 3-EOI Appendix-14B.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTE CAD may be initiated using either CAD TRAIN A (Division I) or CAD TRAIN B (Division II). Equipment identifiers for CAD Train B are in parentheses in the steps below.

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. VERIFY containment hydrogen/oxygen analyzer sample pumps in service.

STANDARD:

Verified Sample Pumps in service by observing illuminated RED status lamps above 3-HS-76-59 and 49 on Panels 3-9-54 and 55.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 6 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. MONITOR Drywell and Suppression Chamber Hydrogen and Oxygen concentrations with H2/02 CONCENTRATION recorders 3-XR-76-11 OA or 3-XR-76-110B (Panel 9-54 or 9-55).

STANDARD:

Located 3-XR-76-110A and 3-XR-76-11 OB and read off approximate indications.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF.............. Drywell or Suppression Chamber hydrogen or oxygen analyzers are or become inoperable, THEN....... NOTIFY Chem Lab to sample Drywell and Suppression Chamber for hydrogen and oxygen using CI-644.

STANDARD:

Acknowledged the above step and continued.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 7 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

4. NOTIFY STA to record post-LOCA containment parameters on Attachment 1 of this procedure every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as required by FSAR.

STANDARD:

Simulated Notifying STA by phone or voice to perform Attachment 1 of this procedure every four (4) hours.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 8 of 14 CAUTION CAD operation with Primary Containment pressure above 30 psig may result in Containment failure.

The following are outside the CAD system FSAR design basis:

Venting Primary Containment during CAD addition.

Adding CAD to Drywell and Suppression Chamber at same time.

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. IF.............. While executing this procedure for CAD addition per SAMG-2, Step G-4 or G-9,

Primary Containment Pressure approaches 30 psig, OR

Primary Containment is to be vented, THEN....... BEFORE:

Primary Containment Pressure reaches 30 psig, OR

Primary Containment venting begins, PERFORM Step 7 to STOP CAD addition to the Primary Containment.

STANDARD:

Verified Primary Containment < 30 psig and acknowledges primary containment not to be vented at this time.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 9 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

6. PLACE CAD System in service as follows:

a. IF ............. CAD addition is required per SAMG-2, Step G-4 or G-9, THEN....... VERIFY all Primary Containment venting is stopped AND Primary Containment Pressure is below 30 psig.

STANDARD:

Verified Primary Containment < 30 psig and acknowledges primary containment not being vented.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b. OPEN 0-FCV-84-5(16), CAD SYSTEM A(8) N2 SHUTOFF VALVE, on Panel 3-9-54(55).

STANDARD:

Placed 0-HS-84-5A in the OPEN position (Critical) and verified illuminated RED valve position indicating lamp (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 10 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

c. IF ............. CAD addition to Suppression Chamber is required, THEN....... CONTINUE in this procedure at Step 6.e.

STANDARD:

Recognizes that Cad addition to the Suppression Chamber is not required (from Initial Conditions and Initiating Cues) and continues at step d.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

d. INITIATE CAD to Drywell as follows:

1) PLACE 3-HS-B4-BAlB(BC/D), SUPPR CHBRlDW CAD 3A(3B)

SPLY SEL, handswitch on Panel 3-9-54(55), in DRYWELL.

2) CONTINUE in this procedure at Step 6.f.

STANDARD:

Placed 3-HS-B4-BAIB in the DRYWELL position (Critical) and continues at step 6f (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 11 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

f. CHECK CAD operating properly as follows on Panel 3-9-54(55):

0-FI-84-7/3(18/3), CAD A(8) N2 SYSTEM FLOW, indicates between 90 and 100 scfm.

0-TI-84-27/3(28/3), VAPOR A(8) OUTLET TEMP, indicates approximately 20 degrees below outside air temperature.

0-PI-84-6/3(17/3), VAPOR A(8) OUTLET PRESS, indicates below 150 psig.

STANDARD:

Located 0-FI-84-7/3, 0-TI-84-27/3, and 0-PI-84-6/3 (on side of Unit 3 Panel) and Verified acceptable indications.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 12 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

7. WHEN...... Directed by SRO or by Step 5, THEN....... STOP CAD addition to the Drywell or Suppression Chamber as follows:

a. PLACE 3-HS-84-8NB(8C/D), SUPPR CHBRlDW CAD 3A(3B) SPLY SEL handswitch on Panel 3-9-54(55), in OFF.

b. VERIFY O-FI-84-7/3(18/3), CAD LINE A(B) N2 FLOW, indicates 0 scfm on Panel 3-9-54(55).

c ...... IF ..... . CAD is NOT being used to supply Drywell Control Air, THEN ... CLOSE O-FCV-84-5(16), CAD SYSTEM A(B) N2 SHUTOFF, on Panel 3-9-54(55).

STANDARD:

N/A SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 376 REV. NO. 1 PAGE 13 of 14

(

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 14 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 an Operator.

A LOCA has led to fuel failure and a rising level of hydrogen concentration in the Unit 3 Drywell.

EOI-2 has been exited and SAMG-2 entered.

INITIATING CUES: The Unit Supervisor has directed you to align CAD System A to the drywell as directed by SAMG-2 step G-4 using 3-EOI Appendix-14B.

JPM NO. 385F REV. NO. 1 PAGE 1 of 14 JPM NUMBER: 385F TITLE: DIESEL GENERATOR LOW LOW OIL PRESSURE TASK NUMBER: U-082-AL-04 151M "F" UNIT -31 SUBMITTED BY: DATE:. _ _ _ __

VALIDATED BY: DATE: _ _ _ __

APPROVED BY: DATE: _ _ _ __

TRAINING PLANTCONCURRENCE: ____________________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 385F REV. NO. 1 PAGE 2 of 14 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 12/22/07 All Initial issue 1 08/28/08 All General revision & re-format

JPM NO. 385F REV. NO. 1 PAGE 3 of 14 OPERATOR: _______________________________________________

RO SRO DATE: _____________

JPM NUMBER: 385F TASK NUMBER: U-082-AL-04 TASK TITLE: DIESEL GENERATOR LOW LOW OIL PRESSURE KIA NUMBER: 264000K4.01 KIA RATING: RO 3.5 SRO 3.7 TASK STANDARD: SHUTDOWN DG WHEN LOW LOW OIL PRESSURE LIGHT IS ILLUMINATED ON PANEL 9-23 IN THE MCR PERFORMANCE LOCATION: S IMULATOR ---=..X-,--_

REFERENCES/PROCEDURES NEEDED: 3-SR-3.8.1.1 (3A), Rev 34, 3-ARP-9-23A, Rev 10 VALIDATION TIME: SIMULATOR: _ _ __ LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS: A copy of 3-SR-3.8.1.1(3Al marked-up to step 7.8[1] is required to provide to the student.

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 4 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 an extra operator.

The (3A) Diesel Generator Monthly test 3-SR-3.8.1.1 (3A) is in progress for December.

The DG has been rolled and AUO is stationed at the DG with a stopwatch.

(

All other support personnel are also standing by at the DG.

INITIATING CUES: You are at step 7.8[1] of 3-SR-3.8.1.1 (3A) ready to start the DG, The AUO is standing by waiting on your mark to start his/her stopwatch locally.

JPM NO. 385F REV. NO. 1 PAGE 5 of 14 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 3-SR-3.8.1.1 (3A).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

(

JPM NO. 385F REV. NO. 1 PAGE 6 of 14 NOTES

1) The Fast Start Section 7.8, should be performed during the first scheduled runs for the months of June and December or directed by the Shift Manager. Upon the Shift Manager's direction, Fast Starts of the Diesel Generator may be performed as required. It is desired to perform the fast starts as scheduled, but as conditions warrant, fast starts may be performed to facilitate maintenance activities.

2) The Operator in Diesel Generator Room 3A should begin timing on mark from the Operator at Panel 3-9-23 when Diesel Generator 3A Control Switch is taken to the start position and stop timing when engine speed reaches 900 RPM as indicated on the engine RPM meter on the Diesel Engine Control Cabinet.

3) The first Operator at Panel 3-9-23 should begin timing on mark from the second Operator at Panel 3-9-23 when Diesel Generator 3A Control Switch is taken to the start position and should stop timing when frequency at Panel 3-9-23 reads greater than 58.8 Hz.

4) The second Operator at Panel 3-9-23 should begin timing when Diesel Generator 3A Control Switch is taken to the start position and stop timing when Generator Voltage reaches greater than 3940 Vas indicated on the Diesel Generator Voltmeter located on Panel 3-9-23.

( 5) Diesel Generator 3A Operating Data is obtained from Data Acquisition Unit connected in accordance with 0-TI-298.

Data Acquisition is normally performed during the months of June and December.

Data Acquisition may be required as a result of maintenance, testing, or surveillance not performed as scheduled during the required months.

6) Electrical Maintenance is required to record Generator Turbo Charger (NO LOAD) vibration readings in accordance with 0-TI-230 at 900 rpm.

JPM NO. 385F REV. NO. 1 PAGE 7 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x 7.8 Fast Start of Diesel Generator (continued)

[1] REVIEW the notes on the previous page.

STANDARD:

Reviews notes on previous page.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[2] VERIFY the following Diesel Generator Rm Exhaust Fans are not Running:

DIESEL GENERATOR RM 3A EXHAUST FAN A

DIESEL GENERATOR RM 3A EXHAUST FAN B STANDARD:

Verifies exhaust fans are not running.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 8 of 14 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[3] PLACE DG 3A BKR 1838 SYNC SWITCH, 3-25-211-3EA/9A to the ON position.

STANDARD:

Places DG 3A BKR 1838 SYNC, 3-25-211-3EA/9A to the ON position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTE Steps 7.8[4] and 7.8[5] are time critical and are to be completed without delay and may be signed off after the completion of Step 7.8[5].

(

JPM NO. 385F REV. NO. 1 PAGE 9 of 14 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[4] SIMULTANEOUSLY PERFORM the following:

START the Diesel Generator using DG 3A CONTROL, 3-HS-82-3A/1 A, AND

START the stopwatches.

STANDARD:

Places DG 3A CONTROL 3-HS-82-3A/1A to START and STARTS the stop watch Simultaneously while communicating with the second Operator and the AUO locally so they can start their stopwatch(s).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 10 of 14 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[5] STOP the stopwatches at the following conditions:

STOP the Control Room frequency stopwatch when DG frequency reaches greater than 58.8 Hz.

STOP the Control Room voltage stopwatch when voltage reaches greater than 3940 V.

STOP the DG Room stopwatch when engine speed reaches at least 900 RPM on DIESEL GENERATOR 3A TACHOMETER, 3-SI-082-0003A.

STANDARD:

Operator stops the stop watch when parameter is reached, < 10 sec.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 11 of 14

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[6] RECORD the elapsed time from all three stopwatches.

First Control Room stopwatch (frequency) (less than or equal to 10 sec) sec_ _

Second Control Room stopwatch (voltage) (less than or equal to 10 sec) sec__

DG Room stopwatch (speed) (less than or equal to 10 sec) sec_ _

STANDARD:

Operator records the times from all 3 stopwatches.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7] CHECK that the times recorded from the voltage stopwatch and the frequency stopwatch meets the criteria specified in Step 6.0A.1.

STANDARD:

Verifies voltage and frequency times meet the (AC).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 12 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x RESPONDS to the Alarm 9-23A WIN 4 (DIESEL GEN 3A LUBE OIL ABNORMAL) and notices the AMBER LIGHT (LOW LOW OIL PRESSURE)

STANDARD:

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

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL SHUTS DOWN the DG with the Emergency Stop Pushbutton per the ARP.

STANDARD:

Shuts Down the DG with the Emergency Stop Pushbutton.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 385F REV. NO. 1 PAGE 13 of 14 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 14 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 an extra operator.

The (3A) Diesel Generator Monthly test 3-SR-3.8.1.1 (3A) is in progress for December.

The DG has been rolled and AUO is stationed at the DG with a stopwatch.

All other support personnel are also standing by at the DG.

INITIATING CUES: You are at step 7.8[1] of 3-SR-3.8.1.1 (3A) ready to start the DG, The AUO is standing by waiting on your mark to start his/her stopwatch locally.

JPM NO. 329F REV. NO. 0 PAGE 1 of 13 JPM NUMBER: 329F TITLE: RESPOND TO A RBCCW PUMP DISCH. HDR PRESSURE LOW ALARM TASK NUMBER: U-070-AL03

(

151M "G" UNIT -31 SUBMITTED BY: DATE:, _ _ __

VALIDATED BY: DATE:, _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ _ _ __ DATE :________

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 329F REV. NO. 0 PAGE 2 of 13 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/12/08 All Initial issue

JPM NO. 329F REV. NO. 0 PAGE 3 of 13 OPERATOR: _______________________________________________

RO SRO DATE: _____________

JPM NUMBER: 329F TASK NUMBER: U-070-AL03 TASK TITLE: RESPOND TO A RBCCW PUMP DISCH. HDR PRESSURE LOW ALARM KIA NUMBER: 226001 A4.12 KIA RATING: RO 3.8 SRO 3.8 TASK STANDARD: RESPOND TO A RBCCW PUMP DISCH.HDR PRESS LOW ALARM PER THE ARP.

PERFORMANCE LOCATION: S IMULATOR ---=-X-=---_

REFERENCES/PROCEDURES NEEDED: 3-ARP-9C Window 12, Rev 30 3-AOI-70-1, Rev 14 3-0i-70, Rev 37 VALIDATION TIME: SIMULATOR: _ _ __ LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 4 of 13 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 an Operator.

Unit 3 is Operating at 100 % power.

Nothing is out of service.

(

INITIATING CUES: Respond to the next Event.

JPM NO. 329F REV. NO. 0 PAGE 5 of 13 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x RECEIVES ALARM (RBCCW PUMP DISCH HDR PRESS LOW).

STANDARD:

Refers to the ARP FOR 3-XA-55-4C WIN 12.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.

STANDARD:

Verifies 3-FCV-70-48 is NOT CLOSING/CLOSED and CLOSES 3-FCV-70-48.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 6 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x B. VERIFY RBCCW pumps A and B in service.

STANDARD:

Verifies RBCCW pumps A and B in service. (" A" pump is uncoupled, Candidate will not know until AUO is sent into the field).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x C. VERIFY RBCCW surge tank low level alarm is reset.

STANDARD:

Verifies RBCCW surge tank low level alarm is reset.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 7 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x D. DISPATCH personnel to check the following:

RBCCW surge tank level locally.

RBCCW pumps for proper operation.

STANDARD:

Dispatches personnel to check the RBCCW surge tank level locally and RBCCW pumps for proper operation.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

(

PERFORMANCE STEP: CRITICAL x NOT CRITICAL Operator Secures 3A RBCCW pump after AUO calls in from the field that the pump is uncoupled.

STANDARD:

Secures 3A RBCCW pump.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 8 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x E. REFER TO 3-AOI-70-1 for RBCCW System failure and 3-01-70, for starting spare pump.

STANDARD:

References 3-AOI-70-1 and 3-01-70.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x 3-AOI-70-1 4.1 Immediate Actions

(

[1] IF RBCCW Pump(s) has tripped, THEN ATTEMPT to restart tripped pump(s).

[2] IF RBCCW Pump(s) cannot be restarted, THEN: (Otherwise N/A)

SHUT DOWN RWCU System Pumps. (Reference TRM 3.4.1)

STANDARD:

Candidate should shutdown RWCU pumps (If system has not already isolated).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 9 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x 4.2 Subsequent Actions

[1] IF Reactor is at power AND Drywell Cooling cannot be immediately restored, THEN PERFORM the following (otherwise N/A):

[1.1] ... -[1.4]

STANDARD:

All of section 1, [1.1] - [1.4] should be N/A. Drywell Cooling is Not affected.

SAT UNSAT NIA _----.,.- COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[2] IF any EOI entry condition is met, THEN: (Otherwise N/A)

ENTER appropriate EOI(s)

STANDARD:

N/A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 10 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[3] IF unable to restart a tripped pump, *THEN PLACE Spare RBCCW Pump in service. REFER TO 3-01-70.

(Otherwise N/A)

STANDARD:

Refers to 3-01-70 and Contacts Unit 1 Operator to place the spare RBCCW pump in service to Unit 3.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[4] IF RBCCW flow was restored to two pump operation by placing the Spare RBCCW pump in service in the preceding step, THEN (Otherwise N/A)

PERFORM the following:

[4.1] REOPEN RBCCW SECTIONALIZING VLV, 3-HS-70-4BA.

STANDARD:

Reopens RBCCW Sectionalizing vlv, 3-HS-70-4BA. after the Spare RBCCW pump is placed I/S.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 329F REV. NO. 0 PAGE 11 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[4.2] RESTORE the RWCU system to operation. (REFER TO 3-01-69).

STANDARD:

N/A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

(

JPM NO. 329F REV. NO. 0 PAGE 12 of 13 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 13 of 13 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 an Operator.

Unit 3 is Operating at 100 % power.

Nothing is out of service.

INITIATING CUES: Respond to the next Event.

JPM NO. 333 REV. NO. 0 PAGE 1 of 12 JPM NUMBER: 333 TITLE: 3-EOI APPENDIX 8B - REOPENING MSIVs FOLLOWING GROUP I ISOLATION TASK NUMBER: U-OOO-EM-46 151M "H" UNIT -31 SUBMITTED BY: DATE: _ _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 333 REV. NO. 0 PAGE 2 of 12 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 07/20108 All Initial issue

(

JPM NO. 333 REV. NO. 0 PAGE 3 of 12 OPERATOR: _________________________________________________

RO SRO DATE: _____________

JPM NUMBER: 333 TASK NUMBER: U-000-EM-46 TASK TITLE: 3-EOI APPENDIX 8B - REOPENING MSIVs FOLLOWING GROUP I ISOLATION K/A NUMBER: 223002A4.03 KIA RATING: RO 3.6 SRO 3.5 TASK STANDARD: PERFORM THE CORRECT EQUIPMENT MANIPULATIONS REQUIRED TO EQUALIZE AROUND THE MSIVs AND REOPEN THE MSIVs PER 3-EOI APPENDIX-8B PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM --

REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-8B, Rev 2 VALIDATION TIME: SIMULATOR: 25:00 LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ _ _ __

JPM NO. 333 REV. NO. 0 PAGE 4 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 a Unit 3 Operator.

Unit 3 reactor has scrammed and isolated.

HPCI is in service for RPV pressure control.

( * "B" SJAE, and "A" OFF GAS PREHEATER are in service from AUX BOILER steam.

Venting Primary containment per APP-12.

EOI-1 and EOI-2 have been entered and conditions allow the MSIVs to be reopened to establish the main condenser as a heat sink.

INITIATING CUES: The Unit Supervisor directs you to reopen the MSIVs as directed by 3-EOI Appendix-88.

JPM NO. 333 REV. NO. 0 PAGE 5 of 12 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 3-EOI Appendix-8B.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. VERIFY ALL MSIV control switches in CLOSE position.

STANDARD:

Verified all eight MSIVs hand switches in the CLOSE position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 333 REV. NO. 0 PAGE 6 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

2. RESET PCIS logic (Panel 9-4).

STANDARD:

Placed both PCIS reset switches on Panel 9-4 to the left and right position (Critical) and Verified that four RED light above the reset switches were illuminated (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. DEPRESS the following push buttons to trip RFPTs (Panel 9-6):

3-HS-3-125, RFPT 3A TRIP

3-HS-3-151, RFPT 38 TRIP

3-HS-3-176, RFPT 3C TRIP STANDARD:

Depressed 3-HS-3-125, 151, 176, or verified all 3 RFP's tripped.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 333 REV. NO. 0 PAGE 7 of 12 NOTE: To prevent auto opening of 3-FCV-1-58, handswitch 3-HS-1-58A must be held in the CLOSE position until main turbine speed decreases to below 1700 RPM.

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

4. VERIFY CLOSED the following drain valves (Panel 9-3):

3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER

3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER STANDARD:

Verified illuminated GREEN valve position indicating lights above 3-HS-1-59 (Not Critical). Placed 3-HS-1-58 in the CLOSE position (Critical) and Verified illuminated GREEN valve position indicating lamp above associated control switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 333 REV. NO. 0 PAGE 8 of 12

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

5. OPEN the following outboard MSIVs (Panel 9-3):

3-FCV-1-15, MSIV LINE A OUTBOARD

3-FCV-1-27, MSIV LINE B OUTBOARD

3-FCV-1-38, MSIV LINE C OUTBOARD

3-FCV-1-52, MSIV LINE D OUTBOARD STANDARD:

Placed 3-HS-1-15, 27, 38 and 52 in the OPEN position (Critical) and Verified illuminated RED valve position indicating lamps above the associated control switches (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

6. VERIFY EHC is in HEADER PRESSURE CONTROL with SETPOINT set above reactor pressure.

STANDARD:

Depressed 3-HS-1-16 and/or Verified illuminated. Adjusts Setpoint as indicated on 3-PI-47-162 such that it indicates greater than reactor pressure.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 333 REV. NO. 0 PAGE 9 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

7. OPEN the following drain valves (Panel 9-3):

3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV

3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV

3-FCV-1-57, MSIV DOWNSTREAM DRAINS SHUTOFF STANDARD:

Placed 3-HS-1-55 and 3-HS-1-56 in the OPEN position (Critical) and Verified illuminated RED valve position indicating lamps above the associated control switches (Not Critical). Verified illuminated RED valve position indicating lamp above 3-HS-1-57 (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

CAUTION Opening MSIVs when differential pressure is above 50 psid may result in piping system dama e.

JPM NO. 333 REV. NO. 0 PAGE 10 of 12

(" ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

8. WHEN .. . Main steam pressure is within 50 psig of RPV pressure, THEN .. . OPEN the following inboard MSIVs (Panel 9-3):

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

3-FCV-1-26, MSIV LINE B INBOARD

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

3-FCV-1-51, MSIV LINE D INBOARD STANDARD:

When main steam pressure as indicated by 3-PI-47-99 on Panel 9-7 is within 50 psig of reactor pressure, Placed HS-1-14, 26, 37 and 51 in the AUTO/OPEN position (Critical) and Verified RED valve position indicating lamps above associated hand switches (Non Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

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.*:.:.*. l.~. ,I.~ .r

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...:::.*.. ..:...:*.*.':.*..'.";.i,.* ;,'~~!!n.u:I;.!iJ!!

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  !::Ii.**.'*.::.!'.":::.*

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JPM NO. 333 REV. NO. 0 PAGE 11 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS:, _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 12 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 a Unit 3 Operator.

Unit 3 reactor has scrammed and isolated.

HPCI is in service for RPV pressure control.

"B" SJAE, and "A" OFF GAS PREHEATER are in service from AUX BOILER steam.

Venting Primary containment per APP-12.

EOI-1 and EOI-2 have been entered and conditions allow the MSIVs to be reopened to establish the main condenser as a heat sink.

INITIATING CUES: The Unit Supervisor directs you to reopen the MSIVs as directed by 3-EOI Appendix-8B.

JPM NO. 335 REV. NO.6 PAGE 1 of20 JPM NUMBER: 335 TITLE: START RCIC FROM OUTSIDE CONTROL ROOM TASK NUMBER: U-000-AB-05 Provide a copy of 3-AOI-1 00-2, Attachment 3.

liN-PLANT "A"I SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 335 REV. NO.6 PAGE 2 of 20 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 10108/96 All Initial issue 1 11/04/97 All Procedure revision, added 3-way comm ..

2 10/28/98 All General revision 3 11/12/99 2,6-16 Procedure revision 4 08/13/03 All re-format, mark critical steps consistently 5 08/18/07 All Procedure revision 6 06/07/08 All General revision & re-format

(

JPM NO. 335 REV. NO.6 PAGE 30f20 OPERATOR: _______________________________________________

RO SRO DATE: _____________

JPM NUMBER: 335 TASK NUMBER: U-000-AB-05 TASK TITLE: START RCIC FROM OUTSIDE CONTROL ROOM K/A NUMBER: 295016AA 1.07 KIA RATING: RO 4.2 SRO 4.3 TASK STANDARD: SIMULATE PERFORMING OPERATIONS NECESSARY TO ALIGN RCIC FROM OUTSIDE CONTROL ROOM AS DIRECTED BY 3-AOI-1 00-2.

PERFORMANCE LOCATION: SIMULATOR __ PLANT X CONTROL ROOM __

REFERENCES/PROCEDURES NEEDED: 3-AOI-100-2, Rev 17 VALIDATION TIME: CONTROLROOM: ________ LOCAL: __. . ;.1=..:2:=-00~_

MAX. TIME ALLOWED: ________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES ____ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAM INER SIGNATURE: _____________________ DATE: ___________

JPM NO. 335 REV. NO.6 PAGE 4 of 20 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: Unit 3 Control Room has been abandoned due to toxic gas in the Control Room.

Pressure control has been established at the backup control panel 3-25-32.

The RCIC system is being aligned for injection to the RPV.

You are an operator assigned to the reactor building and you are in radio contact with the operators at the backup control panel.

INITIATING CUES: The Unit Operator directs you to perform Attachment 3, Part A, of 3-AOI-100-2.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM NO. 335 REV. NO.6 PAGE 50f20 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner, identify/obtain copy of required procedure.

STANDARD:

Identified or obtained copy of 3-AOI-100-2, Attachment 3.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 6 of20 NOTE PAX phone Ext. 2336 is located at Column R-18, P-line.

Reactor Bldg. - RCIC Backup Control Panel 3-LPNL-925-0031 E1621' PERFORMANCE STEP: CRITICAL x NOT CRITICAL 3-XS-071-0036B RCIC SYSTEM FLOW TRANSFER EMERG _ _

3-XS-071-0045 RCIC TURB BRG OIL TEMP HIGH XFR EMERG _ _

3-XS-071-0023 RCIC OIL CLR OUTLET OIL TEMP HIGH EMERG _ _

CONTINUE Part A of this Attachment.

STANDARD:

At Panel 3-LPNL-925-0031 , Simulated placing 3-XS-071-0036B, 3-XS-071-0045 and 3-XS-071-0023 in EMERG.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 7 of 20 CAUTION Failure to place control switch for each component in desired position prior to transferring to emergency may result in inadvertent actuation of the component.

NOTE PAX phone Ext. 2326 is located at Column R-16, R-line between West-side HCUs.

PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - E1565' 1E 3-BKR-071-0029 RCIC TURB BAROMETRIC CNDR CNDS PUMP BREAKER 3-XS-071-0029 RCIC BAROMETRIC CNDR CNDS PUMP EMER TRANS SWITCH EM ERG- -

3-HS-071-0029C RCIC VAC TANK CNDS PUMP EMER HAND SWITCH START STANDARD:

At 250v DC RMOV bd 3C, compartment 1E, Simulated placing 3-XS-071-0029 in the EMERG position and 3-HS-071-0029C in the START position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 8 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - E1565' 3B 3-BKR-071-0037 RCIC PUMP DISCH VALVE BREAKER (GE-13-20) 3-XS-071-0037 RCIC PUMP DISCH VALVE EMER TRANS SWITCH EMERG- -

3-HS-071-0037C RCIC PUMP DISCH VALVE EMER HAND SWITCH OPEN STANDARD:

At 250v DC RMOV bd 3C, compartment 3B, Simulated placing 3-XS-071-0037 in the EMERG position and 3-HS-071-0037C in the OPEN position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 9 of20 PERFORMANCE STEP: CRITICAL x NOT CRITICAL Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI565' 3D 3-BKR-071-0039 RCIC PUMP INJECTION VALVE BREAKER (GE-13-21) 3-XS-071-0039 RCIC PUMP INJECTION VALVE EMER TRANS SWITCH EMERG- -

3-HS-071-0039C RCIC PUMP INJECTION VALVE EMER HAND SWITCH OPEN STANDARD:

At 250v DC RMOV bd 3C, compartment 3D, Simulated placing 3-XS-071-0039 in the EMERG position and 3-HS-071-0039C in the OPEN position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 10 of 20 PERFORMANCE STEP: CRITICAL x NOT CRITICAL Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI565' 4B 3-BKR-071-0008 RCIC TURBINE STM SUPPLY VALVE BREAKER (GE-13-131) 3-XS-071-0008 RCIC TURBINE STM SUPPLY VALVE EMER TRANS SWITCH EMERG 3-HS-071-0008C RCIC TURBINE STM SUPPLY VALVE EMER HAND SWITCH NOR_ __

STANDARD:

At 250v DC RMOV bd 3C, compartment 4B, Simulated placing 3-XS-071-0008 in the EMERG position and 3-HS-071-0008C in the NOR position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 11 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - E1565' 6D 3-BKR-071-0019 RCIC CST 3 SUCT VALVE BREAKER (GE-13-18) 3-XS-071-00 19 RCIC CST 3 SUCT VALVE EMER TRANS SWITCH EMERG- -

3-HS-071-0019C RCIC CST 3 SUCT VALVE EMER HAND SWITCH OPEN STANDARD:

At 250v DC RMOV bd 3C, compartment 60, Simulated placing 3-XS-071-0019 in the EMERG position and 3-HS-071-0019C in the OPEN position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 12 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 7B 3-BKR-071-0038 RCIC PUMP TEST VALVE BREAKER (GE-13-30) 3-XS-071-0038 RCIC PUMP TEST VALVE EMER TRANS SWITCH EMERGENCY_ _

3-HS-071-0038C RCIC PUMP TEST VALVE EMER HAND SWITCH CLOSE _ _ __

STANDARD:

(

At 250v DC RMOV bd 3C, compartment 7B, Simulated placing 3-XS-071-0038 in the EMERGENCY position and 3-HS-071-0038C in the CLOSE position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 13 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 70 3-BKR-071-0018 RCIC SUPPR POOL OUTBD SUCT VALVE BREAKER (GE-13-39) 3-XS-071-0018 RCIC SUPPR POOL OUTBD SUCT EMER TRANS SWITCH EMERGENCY_ _

3-HS-071-0018C RCIC SUPPR POOL OUTBD SUCT VALVE EMER HAND SWITCH CLOSE _ _ __

(

STANDARD:

At 250v DC RMOV bd 3C, compartment 70, Simulated placing 3-XS-071-0018 in the EMERGENCY position and 3-HS-071-0018C in the CLOSE position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 14 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 88 3-BKR-071-0017 RCIC SUPPR POOL INBD SUCTVALVE BREAKER (GE-13-41) 3-XS-071-0017 RCIC SUPPR POOL INBD SUCT EMER TRANS SWITCH EMERGENCY_ _

3-HS-071-0017C RCIC SUPPR POOL INBD SUCT VALVE EMER HAND SWITCH CLOSE, _ _ __

(

STANDARD:

At 250v DC RMOV bd 3C, compartment 8B, Simulated placing 3-XS-071-0017 in the EMERGENCY position and 3-HS-071-0017C in the CLOSE position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 15 of 20 PERFORMANCE STEP: CRITICAL x NOT CRITICAL Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 80 3-BKR-071-0025 RCIC LUBE OIL COOLING WATER VALVE BREAKER (GE-13-18) 3-XS-071-0025 RCIC LUBE OIL CLR COOLING WATER VALVE EMER TRANS SWITCH EMERGENCY 3-HS-071-0025C RCIC LUBE OIL CLR COOLING WATER VALVE EMER HAND SWITCH OPEN

(

STANDARD:

At 250v DC RMOV bd 3C, compartment 80, Simulated placing 3-XS-071-0025 in the EMERG position and 3-HS-071-0025C in the OPEN position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 16 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 10E 3-BKR-071-0031 RCIC TURB BAROMETRIC CNDR VAC PUMP BREAKER 3-XS-071-0031 RCIC BAROMETRIC CNDR VAC PUMP EMER TRANS SWITCH EMERGENCY_ _

3-HS-071-0031C RCIC BAROMETRIC CNDR VAC PUMP EMER HAND SWITCH START

(

STANDARD:

At 250v DC RMOV bd 3C, compartment 10E, Simulated placing 3-XS-071-0031 in the EMERG position and 3-HS-071-0031C in the START position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 17 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x NOTIFY UO at Panel 3-25-32 upon completion of Part A.

STANDARD:

Simulated notifying UO of completion of Attachment 3, Part A, using radio or PAX phone Ext. 2326 at R-16, R-Line (Between west side HCU's).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x STOP here until directed to perform Part B.

STANDARD:

N/A SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 18 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER complied with all safety rules and regulations STANDARD:

PERFORMER complied with all safety rules and regulations (hardhat, safety glasses, sideshields, and hearing protection was worn AS REQUIRED.)

ELECTRICAL SAFETY was also adhered to AS REQUIRED: Exposed conductive articles such as rings, metal wristwatches, bracelets, and metal necklaces shall not be worn by employees within reaching distance of exposed energized electrical conductors of 50 volts or greater.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated proper radiological practices AS REQUIRED STANDARD:

PERFORMER applied proper radiological practices, AS REQUIRED, during JPM performance.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 335 REV. NO.6 PAGE 19 of 20 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ __

PAGE 20 of 20 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: Unit 3 Control Room has been abandoned due to toxic gas in the Control Room.

Pressure control has been established at the backup control panel 3-25-32.

The RCIC system is being aligned for injection to the RPV.

You are an operator assigned to the reactor building and you are in radio contact with the operators at the backup control panel.

INITIATING CUES: The Unit Operator directs you to perform Attachment 3, Part A, of 3-AOI-1 00-2.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

(

BFN Control Room Abandonment 3-AOI-100-2 Unit3 Rev. 0017 Page 36 of 90 Attachment 3 (Page 1 of 9)

Unit 3 RB AUO Panel Checklist Date _ __

NOTE PAX phone Ext. 2336 is located at Column R-18, P-line.

1.0 PART A Switchl Required Breaker Number Component Description Position Initials Reactor Bldg. - RCIC Backup Control Panel 3-LPNL-925-0031 EI 621' 3-XS-071-0036B RCIC SYSTEM FLOW TRANSFER EMERG 3-XS-071-0045 RCIC TURB BRG OIL TEMP HIGH XFR EMERG 3-XS-071-0023 RCIC OIL CLR OUTLET OIL TEMP HIGH EMERG CONTINUE Part A of this Attachment.

BFN Control Room Abandonment 3-AOI-100-2 Unit 3 Rev. 0017 Page 37 of 90 Attachment 3 (Page 2 of 9)

Unit 3 RB AUO Panel Checklist Date _ __

1.0 PART A (continued)

CAUTION Failure to place control switch for each component in desired position prior to transferring to emergency may result in inadvertent actuation of the component.

NOTE PAX phone Ext. 2326 is located at Column R-16, R-line between West-side HCUs.

Switch!

Breaker Component Required Number Description Position Initials Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 1E 3-BKR-071-0029 RCIC TURB BAROMETRIC CNDR CNDS PUMP BREAKER 3-XS-071-0029 RCIC BAROMETRIC CNDR CNDS PUMP EMER TRANS SWITCH EMERG 3-HS-071-0029C RCIC VAC TANK CNDS PUMP EMER HAND SWITCH START 3B 3-BKR-071-0037 RCIC PUMP DISCH VALVE BREAKER (GE-13-20) 3-XS-071-0037 RCIC PUMP DISCH VALVE EMER TRANS SWITCH EMERG 3-HS-071-0037C RCIC PUMP DISCH VALVE EMER HAND SWITCH OPEN

BFN Control Room Abandonment 3-AOI-100-2 Unit3 Rev. 0017 Page 38 of 90 Attachment 3 (Page 3 of 9)

Unit 3 RB AUO Panel Checklist Date 1.0 PART A (continued)

Switch!

Breaker Component Required Number Description Position Initials Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 3D 3-BKR-071-0039 RCIC PUMP INJECTION VALVE BREAKER (GE-13-21 )

3-XS-071-0039 RCIC PUMP INJECTION VALVE EMER TRANS SWITCH EMERG 3-HS-071-0039C RCIC PUMP INJECTION VALVE EMER HAND SWITCH OPEN 4B 3-BKR-071-0008 RCIC TURBINE STM SUPPLY VALVE BREAKER (GE-13-131) 3-XS-071-0008 RCIC TURB STM SUPPLY EMER TRANS SWITCH EMERG 3-HS-071-0008C RCIC TURB STM SUPPLY VALVE EMER HAND SWITCH NOR 60 3-BKR-071-0019 RCIC CST 3 SUCT VALVE BREAKER (GE-13-18) 3-XS-071-0019 RCIC CST 3 SUCT VALVE EMER TRANS SWITCH EMERGENCY 3-HS-071-0019C RCIC CST 3 SUCT VALVE EMER HAND SWITCH OPEN

BFN Control Room Abandonment 3-AOI-100-2 Unit 3 Rev. 0017 Page 39 of 90 Attachment 3 (Page 4 of 9)

Unit 3 RB AUO Panel Checklist Date _ __

1.0 PART A (continued)

Switch!

Breaker Component Required Number Description Position Initials Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 7B 3-BKR-071-0038 RCIC PUMP TEST VALVE BREAKER (GE-13-30) 3-XS-071-0038 RCIC PUMP TEST VALVE EMER TRANS SWITCH EMERGENCY 3-HS-071-0038C RCIC PUMP TEST VALVE EMER HAND SWITCH CLOSE 70 3-BKR-071-0018 RCIC SUPPR POOL OUTBD SUCT VALVE BREAKER (GE-13-39) 3-XS-071-00 18 RCIC SUPP POOL OUTBD SUCT EMER TRANS SWITCH EMERGENCY 3-HS-071-0018C RCIC SUPPR POOL OUTBD SUCT VALVE EMER HAND SWITCH CLOSE 8B 3-BKR-071-0017 RCIC SUPPR POOL INBD SUCT VALVE BREAKER (GE-13-41) 3-XS-071-00 17 RCIC SUPP POOL INBD SUCT EMER TRANS SWITCH EMERGENCY 3-HS-071-0017C RCIC SUPPR POOL INBD SUCTVALVE EMER HAND SWITCH CLOSE

BFN Control Room Abandonment 3-AOI-100-2 Unit3 Rev. 0017 Page 40 of 90 Attachment 3 (Page 5 of 9)

Unit 3 RB AUO Panel Checklist Date _ __

1.0 PART A (continued)

Switchl Breaker Component Required Number Description Position Initials Reactor Bldg. - 250V DC Reactor MOV Board 3C - EI 565' 8D 3-BKR-071-0025 RCIC LUBE OIL COOLING WATER VALVE BREAKER (GE-13-132) 3-XS-071-0025 RCIC LUBE OIL CLR COOLING WATER VALVE EMER TRANS SWITCH EMERGENCY 3-HS-071-0025C RCIC LUBE OIL CLR COOLING WATER VALVE EMER HAND SWITCH OPEN 10E 3-BKR-071-0031 RCIC TURB BAROMETRIC CNDR VAC PUMP BREAKER 3-XS-071-0031 RCIC BAROMETRIC CNDR VAC PUMP EMER TRANS SWITCH EMERGENCY 3-HS-071-0031 C RCIC BAROMETRIC CNDR VAC PUMP EMER HAND SWITCH START NOTIFY UO at Panel 3-25-32 upon completion of Part A.

STOP here until directed to perform Part B.

JPM NO. 99 REV. NO.5 PAGE 1 of 10

(

JPM NUMBER: 99 TITLE: EOI APPENDIX 16H - BYPASSING RCIC HIGH RPV WATER LEVEL SHUTDOWN INTERLOCKS TASK NUMBER: U-000-EM-42 Provide a copy of 2-EOI Appendix-16H liN-PLANT "8"1 SUBMITTED BY: DATE: _ _ _ __

VALIDATED BY: DATE: _ _ _ __

APPROVED BY: DATE: _ _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 99 REV. NO.5 PAGE 2 of 10 REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 1 12/08/94 1,2,3,4 Revise to new format 2 11/09/95 All Procedure revision 3 11/23/99 2,3,4,8 Added plant work expectations Safety, Touch STAAR, and 3-Way Comm.

4 05/17/06 All Procedure revision 5 05/31/08 All General revision & re-format

JPM NO. 99 REV. NO.5 PAGE 3 of 10 OPERATOR: _________________________________________________

RO SRO DATE :_____________

JPM NUMBER: 99 TASK NUMBER: U-000-EM-42 TASK TITLE: EOI APPENDIX 16H - BYPASSING RCIC HIGH RPVWATER LEVEL SHUTDOWN INTERLOCKS KIA NUMBER: 217000A4.03 KIA RATING: RO 3.4 SRO 3.3 TASK STANDARD: SIMULATE PERFORMING ACTIONS REQUIRED TO DEFEAT RCIC HIGH RPV LEVEL SHUTDOWN INTERLOCKS AS DIRECTED BY EOI APPENDIX 16H.

PERFORMANCE LOCATION: SIMULATOR_ PLANT X CONTROL ROOM __

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-16H, Rev 5 VALIDATION TIME: CONTROLROOM: __~5~:0~0___ LOCAL: __-=2..:. . : :0. .=;. 0___

MAX. TIME ALLOWED: ________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES ____ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ______________ DATE: ________

JPM NO. 99 REV. NO.5 PAGE 4 of 10 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 reactor has scrammed due to a leak in the drywell.

Reactor water level cannot be determined.

EOI-1 has been followed to C4-6.

The RCIC system, using auxiliary steam, is to be used as an injection source as directed by Appendix 7H.

You have a hand-held radio with you.

INITIATING CUES: The UNIT SUPERVISOR directs you to bypass the RCIC high RPV water level shutdown interlocks as directed by 2-EOI Appendix 16H.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM NO. 99 REV. NO.5 PAGE 5 of 10 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner, identify/obtain copy of required procedure.

STANDARD:

Identified or obtained copy of 2-EOI Appendix-16H.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

( PERFORMANCE STEP: CRITICAL x NOT CRITICAL

1. PLACE 2-XS-071-0008, RCIC TURB STM SUPPLY EMER TRANS SWITCH, to EMERG position (250V RMOV Board 2C, Compartment 4B).

STANDARD:

Located and Simulated placing 2-XS-071-0008 in the EMERG position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 99 REV. NO.5 PAGE 6 of 10 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

2. WHEN ... Requested by Unit Operator, THEN ... OPEN 2-FCV-71-8, RCIC TURB STM SUPPLY VALVE (250V RMOV Board 2C, Compartment 4B).

STANDARD:

At Compartment 4, 250V DC RMOV Board 2C. Simulated placing 2-HS-71-8C in the OPEN position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

(

JPM NO. 99 REV. NO.5 PAGE 7 of 10

( ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. WHEN ... 2-FCV-71-8, RCIC TURB STM SUPPLY VALVE, is open, THEN ... NOTIFY Unit Operator.

STANDARD:

Simulated notifying Unit 2 Operator using hand-held radio.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 99 REV. NO.5 PAGE 8 of 10 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER complied with all safety rules and regulations STANDARD:

PERFORMER complied with all safety rules and regulations (hardhat, safety glasses, sideshields, and hearing protection was worn AS REQUIRED.)

ELECTRICAL SAFETY was also adhered to AS REQUIRED: Exposed conductive articles such as rings, metal wristwatches, bracelets, and metal necklaces shall not be worn by employees within reaching distance of exposed energized electrical conductors of 50 volts or greater.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated proper radiological practices AS REQUIRED STANDARD:

PERFORMER applied proper radiological practices, AS REQUIRED, during JPM performance.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 99 REV. NO.5 PAGE 9 of 10 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 10 of 10 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 reactor has scrammed due to a leak in the drywell.

Reactor water level cannot be determined.

EOI-1 has been followed to C4-6.

The RCIC system, using auxiliary steam, is to be used as an injection source as directed by Appendix 7H.

You have a hand-held radio with you.

INITIATING CUES: The UNIT SUPERVISOR directs you to bypass the RCIC high RPV water level shutdown interlocks as directed by 2-EOI Appendix 16H.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

(

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 2-EOI APPENDIX-16H BYPASSSING RCIC HIGH RPV WATER LEVEL SHUTDOWN INTERLOCKS REVISION 5 PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: A. S. Bhatnagar EFFECTIVE DATE: 10/26/00 LEVEL OF USE: REFERENCE USE VALIDATION DATE: 05/09/92 QUALITY-RELATED

HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-16H REV.

NO. DATE: REVISED PAGES REASON FOR CURRENT REVISION o 6/15/92 ALL New procedure. Necessary to support implementation of Revision 4 EPGs into BFNP EOIs.

1 7/10/92 ALL Incorporated Writer's Guide discrepancies, typos, and plant nomenclature discrepancies 2 4/21/93 ALL Converted from WordPerfect 5.1 to Pagemaker 4.0 to better support desktop publishing capabilities.

3 Changed Location for procedure performance from control room to reactor building.

Changed location information regarding valve operation for clarity.

3 12/28/93 1 Revised nomenclature and UNID to reflect new system labels.

(

4 8/3/95 1 Revised valve nomenclature and UNIO to reflect new system labels.

5 10/26/00 All Converted to MS-Word.

2-EOI APPENDIX-16H Rev. 5 Page 1 of 1 2-EOI APPENDIX-16H BYPASSSING RCIC HIGH RPV WATER LEVEL SHUTDOWN INTERLOCKS LOCATION: Unit 2 Reactor Building, 250V RMOV Board 2C ATTACHMENTS: None

1. PLACE 2-XS-071-0008, RCIC TURB STM SUPPLY EMER TRANS SWITCH, to EMERG position (250V RMOV Board 2C, Compartment 4B) .

2. WHEN ... Requested by Unit Operator, THEN .. . OPEN 2-FCV-71-8, RCIC TURB STM SUPPLY VALVE (250V RMOV Board 2C, Compartment 4B) .

3. WHEN ... 2-FCV-71-8, RCIC TURB STM SUPPLY VALVE, is open, THEN .. . NOTIFY Unit Operator.

,I LAST PAGE

JPM NO. 115F REV. NO.1 PAGE 1 of 12 JPM NUMBER: 115F TITLE: PLACE A 4KV SHUTDOWN BOARD 250V BATTERY CHARGER IN SERVICE TASK NUMBER: S-57D-NO-11 Provide a copy of 0-01-570, Section 5.16 (include 0-01-570, Section 3.0)

[IN-PLANT "C"[

SUBMITTED BY: DATE: _ _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPMNO.115F REV. NO.1 PAGE 2 of 12

(

REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/19/06 All Initial issue 1 07/20108 All General revision & re-format

(

JPM NO. 115F REV. NO.1 PAGE 3 of 12

(

OPERATOR: _______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 115F TASK NUMBER: S-57D-NO-11 TASK TITLE: PLACE A 4KV SHUTDOWN BOARD 250V BATTERY CHARGER IN SERVICE KIA NUMBER: 263000K1.02 KIA RATING: RO 3.2 SRO 3.3 TASK STANDARD: SIMULATE PERFORMING OPERATIONS REQUIRED TO PLACE A 4KV SHUTDOWN BOARD 250V DC BATTERY CHARGER IN SERVICE PERFORMANCE LOCATION: SIMULATOR __ PLANT X CONTROL ROOM __

REFERENCESIPROCEDURES NEEDED: 0-01-570, Rev 119 VALIDATION TIME: CONTROL ROOM LOCAL: _____

MAX. TIME ALLOWED: __--'-N.:..:,.:/A-'--_ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _______________ DATE: _ _ _ _ _ __

JPM NO. 115F REV. NO.1 PAGE 4 of 12 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.

4KV Shutdown Board A control power is being supplied by its alternate source in accordance with Section 8.6 of 0-01-570.

4KV Shutdown Board 250V Battery Charger SB-A has been temporarily out of service for maintenance which has been completed.

Diesel Generator A is NOT running.

INITIATING CUES: You are directed to return 4KV Shutdown Board 250V Battery Charger SB-A to service.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM NO. 115F REV. NO.1 PAGE 5 of 12 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner, identify/obtain copy of required procedure.

STANDARD:

Identified or obtained copy of 0-01-570.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x 5.16 Placing the 4kV Shutdown Board 250V Battery Charger SB-A(B)(C)(D) in Service

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

STANDARD:

Reviewed section 3.0 SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

(

JPM NO. 115F REV. NO.1 PAGE 6 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[2] VERIFY OFF SHUTDOWN BDS 250V DC SPARE BAT CHGR TRANS SW SB-A(B)(C)(D), O-XSW-248-0000A(B)(C)(D).

STANDARD:

Simulated placing O-XSW-248-0000A in the OFF position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[3] FOR CHARGER SB-C ONLY, VERIFY APPENDIX R TRANSFER SWITCH, O-XSW-248-000C1 IS IN THE NORMAL POSITION.

STANDARD:

N/A - SB-C charger not being used SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 115F REV. NO.1 PAGE 7 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[4] VERIFY ON MAIN DISCONNECT FOR O-PNLA-248-A(B)(C)(D),

O-FUDS-248-0001 A(B)(C)(D).

STANDARD:

Verified O-FUDS-248-0001A in the ON position SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[5] VERIFY ON DISTRIBUTION PANEL SUPPLY FROM BAT CHGR

(

O-CHGA-248-A(B)(C)(D),O-FUDS-248-000AF(BF)(CF)(DF).

STANDARD:

Simulated verifying O-FUDS-248-000AF in the ON position SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 115F REV. NO.1 PAGE 8 of 12 CAUTION If a charger malfunction occurs the AC and DC power breakers should be placed to the OFF position. The Shift Manager should be informed immediately of this condition.

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[6] CLOSE BATTERY CHARGER O-CHGA-248-A(B)(C)(D) AC SUPPLY BKR, O-BKR-248-000AlAC(BIAC )(CIAC )(DIAC).

STANDARD:

Simulated placing O-BKR-248-000AlAC in the ON position SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 115F REV. NO.1 PAGE 9 of 12 CAUTION If a charger malfunction occurs the AC and DC power breakers should be placed to the OFF position. The Shift Manager should be informed immediately of this condition.

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7] CHECK SHUTDOWN BDS 250V DC BATTERY CHGR SB-A(B)(C)(D),

0-EI-248-AlB(B/B)(C/B)(D/B) indicates greater than 250 volts and stable.

STANDARD:

Indicated location of 0-EI-248-AlB and approximate pointer position for 250 volts.

When CUE given, refers to CAUTION (top of this page) and SIMULATES OPENING the AC and DC power breakers and immediately notifies the Shift Manager (Only simulating opening the AC breaker is Critical, the DC breaker has not been closed yet).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPMNO.115F REV. NO.1 PAGE 10 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER complied with all safety rules and regulations STANDARD:

PERFORMER complied with all safety rules and regulations (hardhat, safety glasses, sideshields, and hearing protection was worn AS REQUIRED.)

ELECTRICAL SAFETY was also adhered to AS REQUIRED: Exposed conductive articles such as rings, metal wristwatches, bracelets, and metal necklaces shall not be worn by employees within reaching distance of exposed energized electrical conductors of 50 volts or greater.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

(

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated proper radiological practices AS REQUIRED STANDARD:

PERFORMER applied proper radiological practices, AS REQUIRED, during JPM performance.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 115F REV. NO.1 PAGE 11 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 12 of 12 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.

4KV Shutdown Board A control power is being supplied by its alternate source in accordance with Section 8.6 of 0-01-570.

4KV Shutdown Board 250V Battery Charger SB-A has been temporarily out of service for maintenance which has been completed.

Diesel Generator A is NOT running.

INITIATING CUES: You are directed to return 4KV Shutdown Board 250V Battery Charger SB-A to service.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

c~

BFN DC Electrical System 0-01-57D UnitO Rev. 0119 Page 14 of 249 3.0 PRECAUTIONS AND LIMITATIONS A. In the event a Unit Battery System is removed from service or a 250VDC RMOV Board is transferred to the alternate supply, one or more of the limitations below may apply. If time permits, a Caution Order should be placed on the affected MOV handswitches prior to transfer of board to alternate to prevent violation of these safe shutdown restrictions.

1. In the event any 250VDC RMOV Board is on its alternate supply, the following restrictions apply to DC motor operated valves that are supplied from a battery that is feeding any RMOV board alternate supply:

a. No DC MOV may be operated except as required to mitigate accident conditions, to obtain safe shutdown or to comply with Technical Specifications(i.e. to comply with LCO ACTIONS statements only).

b. Testing(including SI/SRs) that requires DC motor operated valve operation is NOT allowed. [Ref. Dwgs. 1-45E701-3,2-45E702-4, 3-45E703-3]

DC MOVs that may NOT be operated except as required to mitigate accident conditions or to obtain safe shutdown or to comply with Technical Specifications(i.e. to comply with LCO ACTIONS statements only) with RMOV boards on alternate supply.

MAY NOT OPERATE MOVs RMOV NORMAL ALTERNATE SUPPLIED FROM RMOV BOARD ON SUPPLY SUPPLY BD (i.e. supplied from the ALTERNATE BATTERY BATTERY alternate battery) 1A 1 2 1C, 2A, 3C, 1A 1B 3 1 1A, 2C, 3B, 1B 1C 2 1 1A, 2C, 3B, 1C 2A 2 3 1B, 2B, 3A, 2A 2B 3 1 1A, 2C, 3B, 2B 2C 1 2 1C, 2A, 3C, 2C 3A 3 2 1C, 2A, 3C, 3A 3B 1 3 1B, 2B, 3A, 3B 3C 2 3 1B, 2B, 3A, 3C

BFN DC Electrical System 0-01-570 UnitO Rev. 0119 Page 15 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

2. If Battery System 1 is out of service or 250VDC RMOV Board 1A is on alternate supply, the following actions are required:

[Ref. Dwg.: 1-45E701-3, 1-45E712-1]

a. If Battery System 1 is out of service, 1-FCV-073-0044, 2-FCV-73-44 and 3-FCV-73-44 and their supply circuit breakers must be open.

b. If 250V DC MOV Board 1A is transferred to alternate supply, 1-FCV-0073-0044 and 2-FCV-73-44 and their supply circuit breakers must be open.

3. If Battery System 2 is out of service or 250VDC RMOV Board 2A is on the alternate supply, the following additional actions and limitations are required: [Ref. Dwgs.: 2-45E702-4,2-45E712-1]

a. If Battery System is out of service, valves 1-FCV-73-44, 2-FCV-73-44 and 3-FCV-73-44 and their associated supply circuit breakers must be opened.

b. If 250VDC RMOV Board 2A is transferred to the alternate supply, valves 2-FCV-73-44 and 3-FCV-73-44 and their associated supply circuit breakers must be opened.

4. If Battery System 3 is out of service or 250VDC RMOV Board 3A is on the alternate supply, the following additional actions and limitations are required: [Ref. Dwgs.: 3-45E703-3, 3-45E712-1]

a. If Battery System is out of service, valves 1-FCV-73-44, 2-FCV-73-44 and 3-FCV-73-44 and their associated supply circuit breakers must be opened.

b. If 250VDC RMOV Board 3A is transferred to the alternate supply, valves 3-FCV-73-44 and 2-FCV-73-44 and their associated supply circuit breakers must be opened.

B. If Battery System 4, 5 or 6 becomes inoperable the emergency bearing oil pump motor must be started upon transfer to the alternate source. This action ensures D.C. system availability during design basis conditions.

C. Prior to entry into Battery Room(s) ventilation fans to the Battery Room(s) should be in service.

D. Extreme care should be used when deenergizing equipment while locating grounds to prevent interruption of power to vital and safeguard equipment.

REFER TO O-GOI-300-2, Electrical.

BFN DC Electrical System 0-01-570 Unit 0 Rev. 0119 Page 16 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

E. All safety requirements concerning smoking, fires or sparks should be observed when in the Battery-Battery Board Rooms because of potential accumulation of hydrogen in flammable amounts.

F. 250V Unit Battery Charger 1 ,2A,2B and 3 Emergency ON select switch bypasses battery charger emergency load shed contacts. Placing the select switch in Emergency ON reestablishes charger operations with an accident signal present and Diesel Generator voltage available. Battery Charger 4 supply breaker, 480V Shutdown Board 3B, Compt 60, receives a trip signal from the load shed logic and the breaker must be manually re-closed after a 40 second time delay to restore the charger to service. The annunciation circuit for the 250V Unit Battery Charger 3 does NOT work when the EMER/OFF/ON Select Switch is in the EMER Position.

G. [IIIC] Neutron monitoring battery chargers are NOT stand alone power supplies and shall only be operated while connected to the neutron monitoring batteries.

[BFPER 940862]

H. Within 30 minutes after the loss of the normal charger to a 250V Unit Battery another charger shall be placed in service to that battery and load reduced so that the battery is NOT discharging.

I. [NRC/C] Upon return to service of 24V DC Neutron Monitoring Battery A or B, Instrument Maintenance must perform functional tests on SRMs and IRMs that are powered from the affected battery board (In that the IRMs and SRMs are normally inoperable after entering RUN mode due to lack of testing, these tests are N/A for the IRMs and the SRMs if the Unit is in RUN Mode and the IRMs and SRMs are inoperable). Prior to calling the IRMs and SRMs operable, the tests have to be performed. [NRC IE Inspect Follow-up Item 86-40]

J. To return equipment to service following a failure or trip, the shutdown section of this instruction should be performed on the equipment failed. The initial conditions may NOT be applicable in this case.

K. [NRC/C] The transfer of 250VOC control power to a 4kV Shutdown Board with a diesel generator operating may cause an inadvertent start of a RHRSW pump.

[LER 88021/25]

BFN DC Electrical System 0-01-570 UnitO Rev. 0119 Page 17 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

L. The 250 V DC RMOV boards have alternate power supplies from another 250 V Unit DC board. For a unit in MODES 1, 2, or 3, the boards are considered inoperable when powered from their alternate feeder breakers because a single failure of the power source could affect both divisions depending on the board alignment.

1. The alternate battery that has been loaded due to the transfer may be considered operable if the controlled drawing restrictions as referenced in P&L Ware met.

2. Transfer of individual loads required by the Technical Specifications on the Unit Batteries such as the RPT Logic should be considered inoperable if divisional separation cannot be proven. If transfer of such loads is performed solely due to an inoperable distribution board or source, then Technical Specification LCO 3.0.6 can apply to the loads, however, a distribution LCO must be entered.

3. For a unit in MODE 4 or 5, the DC boards can be placed on their alternate feeder breakers and considered OPERABLE as long as the restrictions on the associated drawings are met.

M. A 250V DC unit battery charger should NOT be considered operable if its safety related supply is NOT available. If normal power(safety related supply) is available but the charger is on its alternate supply it is still considered operable.

N. When a 250V RMOV board is transferred to the alternate supply (except for 2B 250V DC RMOV Bd), both divisions (I and II) will be supplied from the same source.

O. Battery Boards should be unloaded before removing Battery or Battery Charger from service, unless the evolution is of short duration (i.e. transferring battery chargers) or plant conditions warrant otherwise.

P. A critical voltage for any cell is 2.13 volts. Prolonged operation of a cell below 2.13 volts will reduce its life expectancy. However it is NOT unusual for a replacement cell to measure 2.07 volts (on float charge) and to slowly rise in voltage over a 3 month period to normal float voltage ranges.

Q. Any Battery suspected to have been discharged shall be recharged immediately to prevent battery damage.

BFN DC Electrical System 0-01-570 Unit 0 Rev. 0119 Page 18 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

R. The 125V DC Diesel Generator Batteries 0-BATB-254-A(B)(C)(D) and 3-BATB-254-3A(3B)(3C)(3D) are designed to normally operate with 60 cells.

The batteries have sufficient capacity to maintain minimum acceptable voltages with one(1) cell jumpered out of service (Strapped Out). The cell SHALL BE jumpered out (Strapped Out) in accordance with Drawing 0-761 E580-1 NOTE 9 or 3-C196C11017, NOTE 8, as applicable The plant SHALL NOTIFY the Site Engineering Manager prior to implementation. [see EDC 69382]

S. The 250V DC Shutdown Boards Batteries 0-BATA-248-A(B)(C)(D) and 3-BATA-248-3EB are designed to normally operate with 120 cells. The batteries have sufficient capacity to maintain minimum acceptable voltages with two(2) cells jumpered out of service (Strapped Out). The cells SHALL BE jumpered out (Strapped Out) in accordance with Drawing 0-45E709-1 NOTE 10 or 3-45E709-2, NOTE 13, as applicable The plant SHALL NOTIFY the Site Engineering Manager prior to implementation. [see EDC 69382]

T. The 250V spare battery charger shall be stored in the seismic restraint at all times unless the charger is being transported to another location.

U. Battery Board 1 is the only EO power supply to Unit 2 ADS valves 1-5 and 1-34.

Valves 1-5 and 1-34 are still considered operable when on there alternate power supply.

V. [lIfF] To prevent the interruption of test equipment and chemical analyses, the Radiochemical Lab (RCL) shall be notified prior to transferring the power supply to Battery Board 2. [1I-B-91-056]

W. Environmental calculations assume battery ambient temperatures at 60° to 110°F for all batteries except Shutdown Board 3EB and DG batteries which are 40°F - 110°F.

X. [CAQRlC] Unless the spare and normal 48V Annunciator battery chargers are operated in parallel, a discharged battery CANNOT be recharged within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while supplying normal loads. [CAQR BFP 880827]

BFN DC Electrical System 0-01-570 Unit 0 Rev. 0119 Page 19 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

Y. Plant controlled drawings document restrictions on Unit 1, 2, & 3 loads which could adversely affect Unit 1, 2, 3 Safe Shutdown capability based on Nuclear Engineering calculations for plant configurations. Due to these restrictions operators must check the restrictions on the associated prints prior to manipulating the following loads.

BOARD Drawing No.

250V Battery Bd 1 1-45E701-3 250V Battery Bd 2 2-45E702-4 250V Battery Bd 3 3-45E703-3 250V Battery Bd 4 0-45E704 250V Battery Bd 5 0-45E704-1 250V Battery Bd 6 0-45E704-2 250V RMOV Bd 1A 1-45E712-1 250V RMOV Bd 1B 1-45E712-2 250V RMOV Bd 1C 1-45E712-3 250V RMOV Bd 2A 2-45E712-1 250V RMOV Bd 2B 2-45E712-2 250V RMOV Bd 2C 2-45E712-3 250V RMOV Bd 3A 3-45E712-1 250V RMOV Bd 3B 3-45E712-2 250V RMOV Bd 3C 3-45E712-3

BFN DC Electrical System 0-01-570 Unit 0 Rev. 0119 Page 20 of 249 3.0 PRECAUTIONS AND LIMITATIONS (continued)

z. Plant controlled drawings document Technical Specification restrictions on Unit 1, 2, & 3 when a Shutdown Boards Control Power is transferred to its Alternate source. Due to these restrictions, operators must check the restrictions on the associated prints prior to transferring Control Power.

Shutdown Board Norm Control Power Transfer Switch Drawing 4160V SO BO A 250V Battery SB-A O-XSW-211-A 0-45E724-1 4160V SO SO B 250V Battery SS-S O-XSW-211-B 0-45E724-2 4160V SO BO C 250V Battery SB-C O-XSW-211-C 0-45E724-3 4160V SO SO 0 250V Battery SB-O O-XSW-211-0 0-45E724-4 4160V SO BO 3EA 250V Battery BO 1 3-XSW-211-3EA 3-45E724-6 4160V SO SO 3EB 250V Battery SS-3EB 3-XSW-211-3EB 3-45E724-7 4160V SO BO 3EC 250V Battery SO 3 3-XSW-211-3EC 3-45E724-8 4160V SO BO 3EO 250V Battery BO 2 3-XSW-211-3EO 3-45E724-9 480V SO BO 1A 250V Battery SS-A 1-XSW-231-1A 1-45E749-1 480V SO BO 1B 250V Battery SB-C 1-XSW-231-1B 1-45E749-2 480V SO BO 2A 250V Battery SB-S 2-XSW-231-2A 2-45E749-3 480V SO BO 2B 250V Battery SB-O 2-XSW-231-2B 2-45E749-4 480V SO BO 3A 250V Battery SO 1 3-XSW-231-3A/A 3-45E749-5 480V SO BO 3S 250V Battery BO 3 3-XSW-231-3B/A 3-45E749-6

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BFN OC Electrical System 0-01-570 UnitO Rev. 0119 Page 106 of 249 5.16 Placing the 4kV Shutdown Board 250V Battery Charger SB-A(B)(C)(O) in Service

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

[2] VERIFY OFF SHUTDOWN BDS 250V DC SPARE BAT CHGR TRANS SW SB-A(B)(C)(D), 0-XSW-24B-0000A(B)(C)(D). D

[3] FOR CHARGER SB-C ONLY, VERIFY APPENDIX R TRANSFER SWITCH, 0-XSW-24B-000C1 IS IN THE NORMAL POSITION. D

[4] VERIFY ON MAIN DISCONNECT FOR 0-PNLA-24B-A(B)(C)(D),O-FUDS-24B-0001A(B)(C)(D). D

[5] VERIFY ON DISTRIBUTION PANEL SUPPLY FROM BAT CHGR 0-CHGA-24B-A(B)(C)(D),

O-FU DS-24B-000AF (BF)(CF)(DF). D CAUTION If a charger malfunction occurs the AC and DC power breakers should be placed to the OFF position. The Shift Manager should be informed immediately of this condition.

[6] CLOSE BATTERY CHARGER 0-CHGA-24B-A(B)(C)(D) AC SUPPLY BKR, 0-BKR-24B-000AlAC(B/AC)(C/AC)(D/AC). D

[7] CHECK SHUTDOWN BDS 250V DC BATTERY CHGR SB-A(B)(C)(D), 0-EI-24B-AlB(B/B)(C/B)(D/B) indicates greater than 250 volts and stable. D

[B] CHECK SHUTDOWN BDS 250V DC BATTERY CHGR SB-A(B)(C)(D), 0-1I-24B-AlB(B/B)(C/B)(D/B) indicates from 0-50 amps and stable. D

[9] CLOSE BATTERY CHARGER 0-CHGA-24B-A(B)(C)(D) DC SUPPLY, 0-BKR-24B-000AlDC(BIDC)(C/DC)(D/DC). D

BFN OC Electrical System 0-01-570 Unit 0 Rev. 0119 Page 107 of 249 5.16 Placing the 4kV Shutdown Board 250V Battery Charger SB-A(B)(C)(O) in Service (continued)

[10] CHECK the following indications on SHUTDOWN BDS 250V DC DISTRIBUTION PNL SB-A(B)(C)(D),

0-PNLA-248-0000A(B)(C)(D):

SHUTDOWN BDS 250V DC DISTRIBUTION PNL SB-A(B)(C)(D), 0-EI-248-AlA(B/A)(C/A)(D/A) indicates greater than 250 volts. o

SHUTDOWN BDS 250V DC DISTRIBUTION PNL SB-A(B)(C)(D), 0-II-248-AlA(B/A)(C/A)(D/A) indicates zero amps or less. o

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ML091810132

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