ML111020338

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Initial Exam 2010-302 Final Sim-IN Plant JPMs
ML111020338
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/06/2011
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-324/10-302, 50-325/10-302
Download: ML111020338 (130)


Text

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

LESSON NUMBER: LOT-SIM-JP-010-A02 REVISION NO: 5

CAROLINA POWER & LIGHT COMPANY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT LESSON TITLE: Securing Local Deluge System Operation for SBGT (Unit 2)

LESSON NUMBER: AOT-OJT-JP-010-A02 REVISION NO: 01

Securing Local Deluge System Manual Operation for 2A SBGT Train SAFETY CONSIDERATIONS:

1. Observe radiological conditions to achieve ALARA.
2. Hard Hat, safety glasses, and ear protection are required in the Power Block.
3. Use caution in the vicinity of operating equipment.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section will be provided to the trainee. Mark up 2OP-10 section 8.3 completed through step 10.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.
3. This JPM must be performed on Unit 2.
4. This JPM may be performed on either SBGT Train, as selected by the evaluator.

Read the following to trainee.

TASK CONDITIONS:

1. A fire has occurred in the 2A SBGT train.
2. The SBGT temperature was greater than 210°F due to a fire in the train.
3. The local deluge system was initiated.
4. SBGT temperature has decreased to < 210°F.

INITIATING CUE:

You are directed by the Unit SCO to manually secure the deluge system per 2OP-10 section 8.3 step 11 on the 2A SBGT train. You are to inform the SCO when the deluge system has been secured.

LOT-OJT-JP-010-A02 Page 2 of 8 REV. 01

Securing Local Deluge System Manual Operation for 2A SBGT Train PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Provide a marked up copy of 2OP-10 Section 8.3 through step 10.

Marked up copy of 2OP-10 Section 8.3 through step 10 provided to examinee.

SAT/UNSAT*

TIME START: ___________

NOTE: The solenoid operated pilot valve bleeder valve is a small brass lever on the hexagonal connector on the valve neck just below the solenoid. On Train A, they are located on the right side of the hexagonal connectors.

All of the valves and controls are located on the Reactor Building 50 foot.

PROMPT: If steps to CLOSE the solenoid-operated pilot valve bleeder valve and manual isolation valves are performed correctly, inform the examinee that water has stopped flowing after each valve group is closed.

Step 2 - OBTAIN Unit SCO's approval to secure deluge system.

Marks step 11a as complete due to SCO's approval obtained (in the initiating cue).

SAT/UNSAT*

PROMPT: The Valves in steps 3 & 4 will be found in the OPEN position based on this procedure being in progress. Report valves OPEN if asked.

PROMPT: Some of the valve tag nomenclature in the following steps does not exactly match the procedure. (It is missing the 2-FP) If student states that the procedure cannot be completed or that SCO approval is needed to perform steps give cues to have the examinee continue in the procedure.

(A PRR will be issued after the exam)

LOT-OJT-JP-010-A02 Page 3 of 8 REV. 01

Securing Local Deluge System Manual Operation for 2A SBGT Train Step 3 - CLOSE deluge valve, DVA-2A1, MAIN ISOLATION VALVE DVA-2A1-B.

DVA-2A1 is turned in the clockwise direction until resistance is obtained and then marks step 11b as complete.

    • CRITICAL STEP ** SAT/UNSAT*

Step 4 - CLOSE deluge valve, DVA-2A2, MAIN ISOLATION VALVE DVA-2A2-B.

DVA-2A2 is turned in the clockwise direction until resistance is obtained and then marks step 11c as complete.

    • CRITICAL STEP ** SAT/UNSAT*

NOTE: The bleeder valves in steps 5 & 6 will be found in the vertical position based on this procedure being in progress. Report valves vertical on as found if asked.

Step 5 - CLOSE the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A1, by rotating the small lever on solenoid-operated pilot valve neck to the horizontal position.

Small lever rotated 90° to the horizontal position and then marks step 11d off as complete.

    • CRITICAL STEP ** SAT/UNSAT*

Step 6 - CLOSE the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A2, by rotating the small lever on solenoid-operated pilot valve neck to the horizontal position.

Small lever rotated 90° to the horizontal position and then marks step 11e off as complete

    • CRITICAL STEP ** SAT/UNSAT*

LOT-OJT-JP-010-A02 Page 4 of 8 REV. 01

Securing Local Deluge System Manual Operation for 2A SBGT Train NOTE: RESET-Overheat water spray 1 & 2 reset buttons are located on SBGT panel on 50 for the respective SBGT train on the XU-69 panel. On the right column of the top pushbutton is the reset for Water Spray No. 1 and the 4th one down on the right side is the reset for Water Spray No. 2.

Step 7 - DEPRESS local deluge system reset push button, RESET-OVERHEAT WATER SPRAY NO. 1:

RESET-OVERHEAT WATER SPRAY NO. 1 is accomplished by DEPRESSING the pushbutton above the "No. 1 Water Spray On" indicating light on XU-69 panel and then marks off the first half of step 11f.

    • CRITICAL STEP ** SAT/UNSAT*

Step 8 - DEPRESS local deluge system reset push button to reset system, RESET-OVERHEAT WATER SPRAY NO. 2:

RESET-OVERHEAT WATER SPRAY NO. 2 is accomplished by DEPRESSING the pushbutton above the "No. 2 Water Spray On" indicating light on XU-69 panel and then marks off the second half of step 11f.

    • CRITICAL STEP ** SAT/UNSAT*

PROMPT: Inform the examinee that the FIN Team will be notified to reset the deluge system valves and that another operator will complete the procedure.

TERMINATING CUE: The flowpath has been isolated via a deluge valve and its associated manual isolation valves.

TIME STOP: __________

  • Comments required for any step evaluated as UNSAT.

LOT-OJT-JP-010-A02 Page 5 of 8 REV. 01

Securing Local Deluge System Manual Operation for 2A SBGT Train LIST OF REFERENCES RELATED TASKS:

261503B104 Operate Deluge System Locally for SBGT per OP-10.

K/A REFERENCE AND IMPORTANCE RATING:

261000 A2.03 2.9/3.2 Ability to Predict Impact of High Train Temperature on SBGT 286000 A2.08 3.2/3.3 Failure of Fire Protection System to Actuate When Required

REFERENCES:

2 OP-10, Section 8.3, Revision 70 TOOLS AND EQUIPMENT:

1. Plant page (or)
2. Radio SAFETY FUNCTION (from NUREG 1123, Rev 2):

Safety Function 8, Plant Service Systems REASON FOR REVISION:

Changed some Open valves to close valves.

LOT-OJT-JP-010-A02 Page 6 of 8 REV. 01

Securing Local Deluge System Manual Operation for 2A SBGT Train Time Required for Completion: 15 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate x Actual ___ Unit: 2 Setting: Control Room Simulator (Not applicable to In-Plant JPMs)

Time Critical: Yes No x Time Limit N/A Alternate Path: Yes ___ No x EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure? Yes No (Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

LOT-OJT-JP-010-A02 Page 7 of 8 REV. 01

TASK CONDITIONS:

1. A fire has occurred in the 2A SBGT train.
2. The SBGT temperature was greater than 210°F due to a fire in the train.
3. The local deluge system was initiated.
4. SBGT temperature has decreased to < 210°F.

INITIATING CUE:

You are directed by the Unit SCO to manually secure the deluge system per 2OP-10 section 8.3 step 11 on the 2A SBGT train. You are to inform the SCO when the deluge system has been secured.

8.3 Local Deluge System Manual Operation C Continuous Use 8.3.1 Initial Conditions

1. The SBGT train temperature is greater than or equal to 210°F AND a fire is indicated in the train.
2. Unit CRS's approval is obtained prior to manual operation of deluge system.

8.3.2 Procedural Steps

1. START unaffected SBGT train by placing SBGT A(B) control switch to ON.

NOTE: The solenoid operated pilot valve bleeder valve is a small brass lever on the hexagonal connector on the valve neck just below the solenoid.

On Train A, they are located on the rear of the hexagonal connectors.

On Train B, they are located on the right side of the hexagonal connectors.

2. OPEN the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A1 (DVA-2B1), by rotating the small lever on solenoid-operated pilot valve neck 90°.
3. OPEN deluge valve, DVA-2A1 (DVA-2B1), MAIN ISOLATION VALVE DVA-2A1-B (DVA-2B1-B).
4. OPEN deluge valve, DVA-2A1 (DVA-2B1), OUTLET ISOLATION VALVE WW-V237 (WW-V230).
5. OPEN the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A2 (DVA-2B2), by rotating the small lever on solenoid-operated pilot valve neck 90°.
6. OPEN deluge valve, DVA-2A2 (DVA-2B2), MAIN ISOLATION VALVE DVA-2A2-B (DVA-2B2-B).

2OP-10 Rev. 72 Page 24 of 45

8.3.2 Procedural Steps

7. OPEN deluge valve, DVA-2A2 (DVA-2B2), OUTLET ISOLATION VALVE WW-V235 (WW-V231).
8. STOP affected SBGT train by placing SBGT A(B) control switch to STBY.
9. DEPRESS SBGT A(B) PUSH OFF push button for the affected SBGT train.
10. CLOSE the following valves to locally isolate the affected SBGT train and prevent possible water and smoke damage to the unaffected SBGT train:
a. SBGT TRAIN A(B) DISCHARGE VALVE, VA-2B-BFV-RB (VA-2E-BFV-RB).
b. SBGT TRAIN A(B) SUCTION VALVE, VA-2C-BFV-RB (VA-2G-BFV-RB).
11. WHEN SBGT train temperature is less than or equal to 210°F, THEN PERFORM the following:
a. OBTAIN Unit CRS's approval to secure deluge system.
b. CLOSE deluge valve, DVA-2A1 (DVA-2B1), MAIN ISOLATION VALVE DVA-2A1-B (DVA-2B1-B).
c. CLOSE deluge valve, DVA-2A2 (DVA-2B2), MAIN ISOLATION VALVE DVA-2A2-B (DVA-2B2-B).
d. CLOSE the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A1 (DVA-2B1), by rotating the small lever on solenoid-operated pilot valve neck to the horizontal position.
e. CLOSE the deluge valve solenoid-operated pilot valve bleeder valve for DELUGE VALVE, DVA-2A2 (DVA-2B2), by rotating the small lever on solenoid-operated pilot valve neck to the horizontal position.

2OP-10 Rev. 72 Page 25 of 45

8.3.2 Procedural Steps

f. DEPRESS both of the following local deluge system reset push buttons to reset system:

RESET-OVERHEAT WATER SPRAY NO. 1.

RESET-OVERHEAT WATER SPRAY NO. 2.

12. REALIGN the SBGT deluge system valves in accordance with 0OP-41.
13. NOTIFY Maintenance to change the SBGT filters in accordance with 0CM-FLT506.
14. ENSURE a Technical Specification LCO is written on the affected SBGT train.
15. NOTIFY E&RC to survey the area due to possible contamination from smoke and water runoff.
16. COMPLETE Attachment 5.

2OP-10 Rev. 72 Page 26 of 45

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT LESSON TITLE: Alternate Control Rod Insertion - LEP Venting The Scram Air Header (Faulted).

LESSON NUMBER: AOT-OJT-JP-300-J06 REVISION NO: 00

LEP Venting The Scram Air Header (Faulted)

SAFETY CONSIDERATIONS:

1. Observe radiological conditions to achieve ALARA.
2. Hard Hat, safety glasses, and ear protection are required in the Power Block.
3. Use caution in the vicinity of operating equipment.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.
2. This JPM can be performed on either unit.
3. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. An ATWS exists on unit . (designated by evaluator)
2. Scram valves are NOT open.
3. You are the Reactor Building Auxiliary Operator
4. Alternate Control Rod Insertion, 0EOP-01-LEP-02, Section 2 is being performed.
5. Attempts to open scram valves from the control room are unsuccessful.

INITIATING CUE:

You are directed by the Reactor Operator to perform the auxiliary operator actions associated with venting the scram air header for Alternate Control Rod Insertion per LEP-02, Section 2 and inform the control room when you have completed the actions.

Page 2 of 8

LEP Venting The Scram Air Header (Faulted)

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtains a current marked up revision of LEP-02, section 2.

Current marked up revision of LEP-02, Section 2 up to step 9 is provided to the examinee.

SAT/UNSAT*

START TIME:

Step 2 - Observe scram air header pressure on C11(C12)-PI-R013.

Scram air header pressure on C11(C12)-PI-R013 observed as is or if the air header is not pressurized then indicate 74 psig and then marks off step 9a.

SAT/UNSAT*

PROMPT: If requested, indicate scram air header pressure is as-seen (unless header is actually depressurized, then indicate pressure is 74 psig).

PROMPT: If informed as the RO as to the value of the pressure reading acknowledge the information and tell the examinee to continue in the procedure.

NOTE: Step 9b should be marked as NA.

Step 3 - Close backup scram valves instrument air isolation valve, C11(C12)-F095.

C11(C12)-F095 is closed by rotating the hand wheel in the clockwise direction until full resistance is obtained and then marks step 9c as complete.

    • CRITICAL STEP ** SAT/UNSAT*

NOTE: A pipe wrench is located in the 20-foot LEP toolbox.

The key for the LEP toolbox is assigned to the on-duty Reactor Building Auxiliary Operator.

Page 3 of 8

LEP Venting The Scram Air Header (Faulted)

Step 4 - Remove screw pipe cap on test connection for one of the pressure switches listed in Table 1 Screw pipe cap on test connection for one of the pressure switches listed in Table 1 is removed using the pipe wrench obtained from the LEP toolbox. The pipe cap required to be removed is upside down. The pipe wrench must be rotated clockwise from the top view to unloosen the pipe cap and rotated until the cap is completely removed. Then circles the pressure switch that is being used and signs off step 9d as complete.

    • CRITICAL STEP ** SAT/UNSAT*

TABLE 1 SCRAM AIR HEADER VENT POINTS Pressure Switch Instrument Drain Valve C11(C12)-PSL-3363 C11(C12)-IV-1039 C11(C12)-PSL-3364 C11(C12)-IV-1041 C11(C12)-PSL-N012 C11(C12)-IV-632 Step 5 - Open the instrument drain valve listed in Table 1 for the pressure switch selected.

The hand wheel is rotated in the counter clockwise direction and it rotates freely without hearing any air venting from the pipe. Recognizes the valve is broken.

SAT/UNSAT*

NOTE: This starts the alternate path in that the selected valve will not vent the scram air header and another valve must be selected.

PROMPT: Indicate that the instrument valve selected from Table 1 is spinning freely and does NOT meet resistance. Also indicate that the examinee does NOT hear any air flow from drain line as hand wheel is turned.

PROMPT: If asked as the CRS that the examinee can not complete the procedure to vent the scram air header inform the examinee that the Scram Air Header needs to be vented as soon as possible.

Page 4 of 8

LEP Venting The Scram Air Header (Faulted)

Step 6 - Remove a different pipe cap than previously removed on test connection for one of the pressure switches listed in Table 1 Screw pipe cap on test connection for a different pressure switch listed in Table 1 is removed using the pipe wrench obtained from the LEP toolbox. The pipe cap required to be removed is upside down. The pipe wrench must be rotated clockwise from the top view to unloosen the pipe cap and rotated until the cap is completely removed.

    • CRITICAL STEP ** SAT/UNSAT*

Step 7 - Open the instrument drain valve listed in Table 1 for the second pressure switch selected The hand wheel is rotated in the counter clockwise direction until full resistance is obtained. As the valve is being opened air will be heard discharging from where the pipe cap was removed. Marks step 9e as complete.

    • CRITICAL STEP ** SAT/UNSAT*

PROMPT: If requested, indicate scram air header pressure is dropping toward, and then reaches zero psig.

Step 8 - When scram air header pressure decreases to 0 psig, then notify Control Operator.

Control Operator notified scram air header pressure is zero psig as read on C11(C12)-PI-R013.

SAT/UNSAT*

TERMINATING CUE: When AO actions of LEP-02, Section 2 have been performed, this JPM is complete.

COMPLETION TIME:

  • Comments required for any step evaluated as UNSAT.

Page 5 of 8

LEP Venting The Scram Air Header (Faulted)

RELATED TASKS:

200 651 B5 04, Vent The Scram Air Header To Open The Scram Valves Per EOP-01-LEP-02 K/A REFERENCE AND IMPORTANCE RATING:

295037 EA1.05 3.9/4.0 Ability to operate and/or monitor CRD Hydraulics as they apply to Scram Condition present and reactor power above APRM downscale or unknown

REFERENCES:

0EOP-01-LEP-02 TOOLS AND EQUIPMENT:

LEP toolbox key Pipe wrench SAFETY FUNCTION (from NUREG 1123):

1 - Reactivity Control REASON FOR REVISION:

New JPM.

Page 6 of 8

LEP Venting The Scram Air Header (Faulted)

Validation Time: 10 Minutes APPLICABLE METHOD OF TESTING Performance: Simulate X Actual Unit: 1/2 Setting: Control Room Simulator (N/A for Admin or In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure Revision?: Yes No Comments:

Comments reviewed with Student Evaluator Signature: Date:

Page 7 of 8

TASK CONDITIONS:

1. An ATWS exists on unit . (designated by evaluator)
2. Scram valves are NOT open.
3. You are the Reactor Building Auxiliary Operator
4. Alternate Control Rod Insertion, 0EOP-01-LEP-02, Section 2 is being performed.
5. Attempts to open scram valves from the control room are unsuccessful.

INITIATING CUE:

You are directed by the Reactor Operator to perform the auxiliary operator actions associated with venting the scram air header for Alternate Control Rod Insertion per LEP-02, Section 2 and inform the control room when you have completed the actions.

Page 8 of 8

Section 2 The purpose of this section is to deenergize the scram pilot valve solenoids, initiate ARI, and vent the scram air header in order to open all scram valves.

NOTE: Manpower: 1 Reactor Operator 1 Auxiliary Operator 1 Independent Verifier Special equipment 4 PA2235 keys for RPS trip logic switches 1 LEP toolbox key 1 pipe wrench (LEP toolbox on 20' elevation) 1 fuse puller RO: 1. IF NOT previously initiated, THEN INITIATE ARI.

RO: 2. IF all scram valves are open, THEN RETURN to Step 2.6 Today / Now on page 3.

3. PLACE the following keylock RPS test channel trip logic switches to TRIP:
a. On Panel H12-P609:

RO: - RPS TEST CH A1 TRIP LOGIC, C71A(C72)-S2A RO: - RPS TEST CH A2 TRIP LOGIC, C71A(C72)-S2C

b. On Panel H12-P611:

RO: - RPS TEST CH B1 TRIP LOGIC, C71A(C72)-S2B RO: - RPS TEST CH B2 TRIP LOGIC, C71A(C72)-S2D 0EOP-01-LEP-02 Rev. 27 Page 9 of 30

Section 2 (Continued) Initials

4. PLACE the following keylock RPS test channel trip logic switches to NORMAL:
a. On Panel H12-P609:

RO: - RPS TEST CH A1 TRIP LOGIC, RO /

C71A(C72)-S2A Ind.Ver.

RO: - RPS TEST CH A2 TRIP LOGIC, RO /

C71A(C72)-S2C Ind.Ver.

b. On Panel H12-P611:

RO: - RPS TEST CH B1 TRIP LOGIC, RO /

C71A(C72)-S2B Ind.Ver.

RO: - RPS TEST CH B2 TRIP LOGIC, RO /

C71A(C72)-S2D Ind.Ver.

RO: 5. IF all scram valves are open, THEN RETURN to Step 2.6 Today / Now on page 3.

6. PULL the following fuses to deenergize all scram pilot valve solenoids:
a. In Panel H12-P609, Terminal Board CC:

RO: - Fuse C71A(C72A)-F18A RO: - Fuse C71A(C72A)-F18E RO: - Fuse C71A(C72A)-F18C RO: - Fuse C71A(C72A)-F18G

b. In Panel H12-P611, Terminal Board CC:

RO: - Fuse C71A(C72A)-F18B RO: - Fuse C71A(C72A)-F18F RO: - Fuse C71A(C72A)-F18D RO: - Fuse C71A(C72A)-F18H 0EOP-01-LEP-02 Rev. 27 Page 10 of 30

Section 2 (Continued) Initials

7. WHEN all fuses have been removed, THEN INSTALL the following fuses to reenergize all scram pilot valve solenoids:
a. In Panel H12-P609, Terminal Board CC:

RO: - Fuse C71A(C72A)-F18A RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18E RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18C RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18G RO /

Ind.Ver.

b. In Panel H12-P611, Terminal Board CC:

RO: - Fuse C71A(C72A)-F18B RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18F RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18D RO /

Ind.Ver.

RO: - Fuse C71A(C72A)-F18H RO /

Ind.Ver.

RO: 8. IF all scram valves are open, THEN RETURN to Step 2.6 on page 3. Today / Now

9. VENT the scram air header by performing the following:

NOTE: C11(C12)-PI-R013, is located by CRD instrument rack 20 foot elevation in the reactor building.

AO: a. OBSERVE scram air header pressure on C11(C12)-PI-R013.

RO: b. IF scram air header pressure has decreased to 0 psig, THEN RETURN to Step 2.6 on page 3.

0EOP-01-LEP-02 Rev. 27 Page 11 of 30

Section 2 (Continued)

NOTE: BACKUP SCRAM VALVES INSTRUMENT AIR ISOLATION VALVE, C11(C12)-F095, is located behind 20 foot elevation CRD instrument rack.

AO: c. CLOSE BACKUP SCRAM VALVES INSTRUMENT AIR ISOLATION VALVE, C11(C12)-F095.

NOTE: Scram Air Header Vent Points are located by CRD instrument rack, 20 foot elevation in reactor building.

AO: d. REMOVE screw pipe cap on test connection for one of the pressure switches listed in Table 1, Scram Air Header Vent Points. (Circle pressure switch used).

TABLE 1 SCRAM AIR HEADER VENT POINTS Pressure Switch Instrument Drain Valve C11(C12)-PSL-3363 C11(C12)-IV-1039 C11(C12)-PSL-3364 C11(C12)-IV-1041 C11(C12)-PSL-N012 C11(C12)-IV-632 AO: e. OPEN the instrument drain valve listed in Table 1 for the pressure switch selected in Step 9.d as necessary to vent the scram air header.

AO: f. WHEN scram air header pressure decreases to 0 psig, THEN NOTIFY Reactor Operator.

0EOP-01-LEP-02 Rev. 27 Page 12 of 30

Section 2 (Continued) Initials

g. WHEN directed by Reactor Operator, THEN PERFORM the following:

AO: (1) CLOSE the instrument drain valve for the /

pressure switch selected in Step 9.d on Ind.Ver.

page 12.

AO: (2) REPLACE screw pipe cap on test /

connection for the pressure switch selected Ind.Ver.

in Step 9.d on page 12.

AO: (3) OPEN BACKUP SCRAM VALVES /

INSTRUMENT AIR ISOLATION VALVE, Ind.Ver.

C11(C12)-F095.

RO: 10. RETURN to Step 2.6 on page 3.

Date/Time Completed Performed By (Print) Initials Reviewed By:

Unit CRS/SRO 0EOP-01-LEP-02 Rev. 27 Page 13 of 30

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE IN-PLANT LESSON TITLE: Alternate Coolant Injection LEP Heater Drain Pumps LESSON NUMBER: AOT-OJT-JP-300-J13 REVISION NO: 3

Alternate Coolant Injection LEP Heater Drain Pumps SAFETY CONSIDERATIONS:

1. Observe radiological conditions to achieve ALARA.
2. Hard Hat, safety glasses, and ear protection are required in the Power Block.
3. Use caution in the vicinity of operating equipment.

EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.
2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. A low Reactor Water level condition exists on Unit One.
2. The SCO is executing RVCP
3. RVCP directs use of Alternate Coolant Injection per EOP-01-LEP-01.
4. Steps 1 through 4 of LEP-01, Section 2, Heater Drain Pump Injection have been completed.
5. RPV Pressure is 450 psig.
6. The main condenser is under vacuum.

INITIATING CUE:

You are directed to perform the Auxiliary Operator actions for Heater Drain Pump Injection per LEP-01 Section 2, and inform the Control Room when all required Auxiliary Operator actions are complete.

AOT-OJT-JP-300-J13 Page 2 of 8 REV. 3

Alternate Coolant Injection LEP Heater Drain Pumps PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a marked up current revision of EOP-01-LEP-01, Section 2.

Examinee provided with a Current marked up copy of LEP-01, Section 2.

SAT/UNSAT*

TIME STARTED:

NOTE: Each of the level controllers must be placed in manual and the air signal decreased to 0%.

Placing each of the controllers in manual is accomplished by moving the black slide bar from the left (AUTO position) to the far right (MAN position).

When in MAN then the air signal is lowered to zero by rotating the manual output dial (to the left) until the orange needle is on 0 output. (This is an air to close valve)

Step 2 - Place Feedwater Heater 4A Level Control HD-LC-75 to MAN and decrease the air signal to 0%.

HD-LC-75 black slide bar is in the far right position (MAN) and the manual output dial is rotated to where the orange output signal indicator is on 0%.

    • CRITICAL STEP ** SAT/UNSAT*

Step 3 - Place Feedwater Heater 5A Level Control HD-LC-83 to MAN and decrease the air signal to 0%.

HD-LC-83 black slide bar is in the far right position (MAN) and the manual output dial is rotated to where the orange output signal indicator is on 0%.

    • CRITICAL STEP ** SAT/UNSAT*

AOT-OJT-JP-300-J13 Page 3 of 8 REV. 3

Alternate Coolant Injection LEP Heater Drain Pumps Step 4 - Place Feedwater Heater 4B Level Control HD-LC-79 to MAN and decrease the air signal to 0%.

HD-LC-79 black slide bar is in the far right position (MAN) and the manual output dial is rotated to where the orange output signal indicator is on 0%.

    • CRITICAL STEP ** SAT/UNSAT*

Step 5 - Place Feedwater Heater 5B Level Control HD-LC-87 to MAN and decrease the air signal to 0%.

HD-LC-87 black slide bar is in the far right position (MAN) and the manual output dial is rotated to where the orange output signal indicator is on 0%.

    • CRITICAL STEP ** SAT/UNSAT*

Step 6 - Ensure Heater Drain Deaerator Level Controller, HD-LC-91, is in AUTO.

Verifies that the HD-LC-91 level controller is in AUTO.

SAT/UNSAT*

PROMPT: Inform examinee that LEP-01, Section 2 Step 6 has been completed.

Inform Examinee that Heater Drain Pump 1A is to be started for alternate coolant injection.

NOTE: A CR104P key for Unit Trip Load Shed Selector Switch is located in the RO Desk locked drawer. A key can also be found in the Control room or WCC key lockers.

Heater Drain Pump 1A Unit Trip Load Selector Switch is on BOP Bus 1D.

Step 7 - Place Heater Drain Pump 1A Unit Trip Load Selector Switch in DISABLED.

Places the CR104P key in the Heater Drain Pump 1A Unit Trip Load Selector Switch and rotates the key to the DISABLED position. (The key can be removed once in the disabled position)

    • CRITICAL STEP ** SAT/UNSAT*

AOT-OJT-JP-300-J13 Page 4 of 8 REV. 3

Alternate Coolant Injection LEP Heater Drain Pumps Step 8 - Inform Control Room AO Actions for Alternate Coolant Injection using Heater Drain Pump Injection are complete.

Control Room informed AO actions per LEP-01, Section 2 are complete.

SAT/UNSAT*

TERMINATING CUE: When AO Actions for Alternate Coolant Injection using Heater Drain Pump Injection are complete, this JPM is complete.

  • Comments required for any step evaluated as UNSAT.

TIME COMPLETED:

AOT-OJT-JP-300-J13 Page 5 of 8 REV. 3

Alternate Coolant Injection LEP Heater Drain Pumps RELATED TASKS:

200072B504, Perform Alternate Coolant Injection With Heater Drain Pumps Per LEP-01 K/A REFERENCE AND IMPORTANCE RATING:

295031 EA1.08 3.8/3.9 Ability to operate alternate injection system systems as they apply to Reactor Water Level Low.

REFERENCES:

EOP-01-LEP-01 TOOLS AND EQUIPMENT:

CR104P key for Unit Trip Load Shed Selector switch.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

2 - Inventory Control REASON FOR REVISION:

Added details to the instructor cues. Removed the SSN blank.

AOT-OJT-JP-300-J13 Page 6 of 8 REV. 3

Alternate Coolant Injection LEP Heater Drain Pumps Time Required for Completion: 7 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit: 1 Setting: Control Room Simulator ( Not applicable to In-Plant JPMs )

Time Critical: Yes No Time Limit N/A Alternate Path: Yes No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure as Authorized Copy?: Yes No (Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

AOT-OJT-JP-300-J13 Page 7 of 8 REV. 3

TASK CONDITIONS:

1. A low Reactor Water level condition exists on Unit One.
2. The SCO is executing the Reactor Vessel Control Procedure (EOP-01-RVCP)
3. RVCP directs use of Alternate Coolant Injection per EOP-01-LEP-01.
4. RPV Pressure is 450 psig.
5. The main condenser is under vacuum.

INITIATING CUE:

You are directed to perform the Auxiliary Operator actions for Alternate Coolant Injection, Heater Drain Pump Injection per EOP-01-LEP-01, and inform the Control Room when all required Auxiliary Operator actions are complete.

Page 8 of 8

Section 2 Heater Drain Pump Injection NOTE: Manpower: 1 Reactor Operator 1 Auxiliary Operator 1 Independent Verifier Special equipment: 1 CR104P key for Unit Trip Load Shed Selector Switch RO: 1. INFORM the Unit CRS of the performance of this section.

RO: 2. ENSURE FEEDWATER RECIRC TO CONDENSER VLV, FW-FV-177, is closed.

RO: 3. OPEN RFP BYPASS VLV, FW-V13.

4. CLOSE the following valves:

RO: - RFP A SUCTION VLV, COD-V49 RO: - RFP B SUCTION VLV, COD-V50

5. MAINTAIN level in the heater drain tank as follows:
a. PLACE the following feedwater heater level controllers to MAN AND DECREASE the air signal to 0% to open the associated feedwater heater level control valves:

AO: (1) FEEDWATER HEATER 4A LEVEL CONTROLLER, HD-LC-75 AO: (2) FEEDWATER HEATER 5A LEVEL CONTROLLER, HD-LC-83 AO: (3) FEEDWATER HEATER 4B LEVEL CONTROLLER, HD-LC-79 AO: (4) FEEDWATER HEATER 5B LEVEL CONTROLLER, HD-LC-87 0EOP-01-LEP-01 Rev. 30 Page 9 of 38

Section 2 (Continued)

AO: b. Unit 1 Only: ENSURE HEATER DRAIN DEAERATOR LEVEL CONTROLLER, HD-LC-91, is in AUTO.

AO: c. Unit 2 Only: ENSURE HEATER DRAIN DEAERATOR LEVEL CONTROLLER, HD-LC-91, is in AUTO.

AO: d. Unit 2 Only: ENSURE HEATER DRAIN DEAERATOR LEVEL CONTROLLER, HD-LC-97, is in AUTO.

RO: e. IF the main condenser is under vacuum, THEN CONTINUE in this section at Step 6.

f. IF the Condensate Transfer System is available AND the condenser is NOT under vacuum, THEN PERFORM the following:

NOTE: RFP A (B) COND LEVEL, RFA-LI-56 (RFB-LI-57), indicator on XU-2 reading on-scale indicates level in the hotwell is sufficient to drain to the heater drain tank.

RO: (1) NOTIFY Radwaste to make up to the hotwell as necessary to maintain hotwell level above

+16 inches.

RO: (2) WHEN hotwell level is above +16 inches, THEN OPEN DEAERATOR FILL & DRAIN VLV, HD-V57, to drain the hotwell to the heater drain tank.

6. ENSURE the following valves are closed:

RO: - FW HTR 4A INLET VLV, FW-V118 RO: - FW HTR 4B INLET VLV, FW-V119 RO: - FW HTR 5A OUTLET VLV, FW-V6 RO: - FW HTR 5B OUTLET VLV, FW-V8 RO: - FW HTRS 4 & 5 BYP VLV, FW-V120 0EOP-01-LEP-01 Rev. 30 Page 10 of 38

Section 2 (Continued)

NOTE: Heater drain deaerator level must be greater than or equal to 48 inches to start a heater drain pump.

AO: 7. PLACE the Unit Trip Load Shed Selector Switch for the heater drain pump to be started, in DISABLED.

RO: 8. START the selected heater drain pump.

RO: 9. PLACE STARTUP LEVEL CONTROL VALVE, FW-LIC-3269, in M (Manual) AND OPEN, as necessary.

Initials

10. WHEN heater drain pump injection is no longer required, THEN PERFORM the following:

RO: a. STOP selected heater drain pump.

AO: b. PLACE Unit Trip Load Shed Selector Switch for /

the selected heater drain pump in ENABLED. Ind.Ver.

RO: c. CLOSE DEAERATOR FILL & DRAIN VLV, HD-V57.

d. PLACE the following feedwater heater level controllers to AUTO:

AO: (1) FEEDWATER HEATER 4A LEVEL CONTROLLER, HD-LC-75 AO: (2) FEEDWATER HEATER 5A LEVEL CONTROLLER, HD-LC-83 AO: (3) FEEDWATER HEATER 4B LEVEL CONTROLLER, HD-LC-79 AO: (4) FEEDWATER HEATER 5B LEVEL CONTROLLER, HD-LC-87 RO: e. RESTORE AND MAINTAIN hotwell level between

-7 and +7 inches.

0EOP-01-LEP-01 Rev. 30 Page 11 of 38

Section 2 (Continued) Initials RO: f. ALIGN the Feedwater System as required by plant conditions.

RO: g. EXIT this section AND CONTINUE in this procedure at Step 2.1, on page 3.

Date/Time Completed _______________________

Performed By (Print) Initials Reviewed By:

Unit CRS/SRO 0EOP-01-LEP-01 Rev. 30 Page 12 of 38

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

SIMULATOR SETUP:

A. Initial Conditions:

1. Recommended Initial Conditions IC 1 Rx. Pwr. 100%
2. Required Plant Conditions Drywell Pressure above 0.5 psig SLOWLY rising or stable, AND below 1.8 psig.

B. Malfunctions None required C. Overrides Meters Event Pane Tag Title Value Activate Deactivate l (ramp rate) Time (sec) Time (sec) 1.48 / 2 min E1 XU-3 G5B02G15 Main Stack Radiation 0 SEC N/A Trigger 1 Q6225LGT CAC-V23 Green Lamp = False D. Special Instructions Secure Drywell Coolers 2C and 2D Fans 1 and 2 and allow drywell pressure to rise to 0.6 psig as indicated on CAC-PI-2685-1 on XU-51, then restart Drywell Coolers 2D Fan 2 and allow Drywell pressure to stabilize. Override Drywell Cooler 2C Fans 1 and 2 and Drywell Cooler 2D Fan 1 control switches OFF.

LOT-SIM-JP-010-A02 Page 2 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

SAFETY CONSIDERATIONS:

NONE EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee, once it is demonstrated he/she knows the correct procedure.
2. Provide a marked up copy of 2OP-10, Section 8.2 to the performer.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. Drywell pressure is above normal due to a partial loss of Drywell Cooling.
2. Standby Gas Treatment System is in the Standby Alignment.
3. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent Isolation Override is in OFF.

INITIATING CUE:

The Unit CRS directs you to vent the Drywell via Standby Gas Treatment, and to inform him when drywell pressure has been reduced below 0.5 psig.

LOT-SIM-JP-010-A02 Page 3 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain current revision of 2OP-10, Section 8.2 and verify if applicable.

Current revision of 2OP-10, Section 8.2 is obtained and verified as required.

SAT/UNSAT TIME START Step 2 - Record D12-RR-R600B, STACK RAD MONITOR, digital point display, 1.06.

1.06 recorded in 2OP-10, step 8.2.2.1.

SAT/UNSAT Step 3 - Add 0.17 to the value to obtain the logarithmic equivalent of a 50% increase in stack radiation monitor reading and record result.

1.23 recorded in 2OP-10, step 8.2.2.2.

SAT/UNSAT NOTE: Step 8.2.2.3 is N/A.

Step 4 - Record the logarithmic equivalent determined in step 8.2.2.2.

1.23 recorded in 2OP-10, step 8.2.2.4.

SAT/UNSAT Step 5 - CLOSE Reactor Building SBGT Train 2A Inlet Valve, 2-VA-2D-BFV-RB.

Places the control switch for 2-VA-2D-BFV-RB in the close position and when the red light goes out releases the control switch to the neutral position.

    • CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-010-A02 Page 4 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

Step 6 - CLOSE Reactor Building SBGT Train 2B Inlet Valve, 2-VA-2H-BFV-RB.

Places the control switch for 2-VA-2H-BFV-RB in the close position and when the red light goes out releases the control switch to the neutral position.

    • CRITICAL STEP ** SAT/UNSAT Step 7 - OPEN SBGT DW Suct Damper, 2-VA-2F-BFV-RB.

Momentarily places the control switch for 2-VA-2F-BFV-RB in open. Observes the red light comes on and then the green light goes out.

    • CRITICAL STEP ** SAT/UNSAT PROMPT: If asked as the SCO, direct performer to vent the drywell.

2OP-10, step 8.2.2.8 is N/A.

Step 8 - OPEN DW Purge Exh Valve, 2-CAC-V9.

Momentarily places the control switch for 2-CAC-V9 in open. Observes the red light comes on and then the green light goes out.

    • CRITICAL STEP ** SAT/UNSAT CUE: When CAC-V23 is opened, verify Trigger 1 initiates to ramp Main Stack Rad Monitor value.

Step 9 - OPEN DW Purge Exh Valve, 2-CAC-V23.

Momentarily places the control switch for 2-CAC-V23 in open. Observes the red light comes on and then the green light goes out.

    • CRITICAL STEP ** SAT/UNSAT PROMPT: If requested as the SCO, inform performer that it is desired to vent from the drywell head.

Step 10 - OPEN DW Head Purge Exh Vlv, 2-CAC-V49.

Momentarily places the control switch for 2-CAC-V49 in open. Observes the red light comes on and then the green light goes out.

SAT/UNSAT LOT-SIM-JP-010-A02 Page 5 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

Step 11 - OPEN DW Head Purge Exh Vlv, 2-CAC-V50.

Momentarily places the control switch for 2-CAC-V50 in open. Observes the red light comes on and then the green light goes out.

SAT/UNSAT Step 12 - Monitor Stack Rad Monitor and determine reading has risen by >50%.

Determines Stack Rad Monitor reading has risen by >.17 (50%).

SAT/UNSAT NOTE: It is critical for at least one valve to be closed in each vent path that is open, i.e., CAC-V23 or CAC-V9, AND, CAC-V49 or CAC-V50, or that the primary containment suction valve VA-2F-BFV-RB is closed to isolate the release path.

CUE: When the vent path has been isolated, delete the meter override on the Main Stack Rad Monitor.

PROMPT: If the examinee informs the Unit SCO that the Main Stack has risen by >50%,

direct examinee as Unit SCO to perform required actions for the increase.

NOTE: Either Step 13 OR Step 14 is CRITICAL.

Step 13 - CLOSE DW Purge Exh Vlv, 2-CAC-V23.

Places the control switch for 2-CAC-V23 in the close position. Observes the green light comes on and then the red light goes out.

    • CRITICAL STEP ** SAT/UNSAT Step 14 - CLOSE Drywell Purge Exh Valve, 2-CAC-V9.

Places the control switch for 2-CAC-V9 in the close position. Observes the green light comes on and then the red light goes out.

    • CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-010-A02 Page 6 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

NOTE: Either Step 15 OR Step 16 is CRITICAL if the 2-CAC-49 and V50 were opened.

Step 15 - ENSURE DW Head Purge Exh Vlv, 2-CAC-V49, is closed.

Places the control switch for 2-CAC-V49 in the close position. Observes the green light comes on and then the red light goes out.

    • CRITICAL STEP ** SAT/UNSAT Step 16 - ENSURE DW Head Purge Exh Vlv, 2-CAC-V50, is closed.

Places the control switch for 2-CAC-V50 in the close position. Observes the green light comes on and then the red light goes out.

    • CRITICAL STEP ** SAT/UNSAT PROMPT: If asked, inform examinee as Unit SCO that E&RC has been notified to sample primary containment, and to reference E&RC 2020 Setpoint Determinations for Gaseous Radiation Monitors (Noble Gas Instantaneous Release Rate Determination).

NOTE: Step 17 is not critical if either step 13 or 14 AND either 15 or 16 was completed SAT. Release path may be isolated by closing 1 valve in each vent path OR by closing the common isolation in Step 17.

Step 17 - CLOSE SBGT DW Suct Damper, 2-VA-2F-BFV-RB.

Places the control switch for 2-VA-2F-BFV-RB in the close position. Observes the green light comes on and then the red light goes out.

    • CRITICAL STEP ** SAT/UNSAT TERMINATING CUE: When Primary containment Venting has been secured, by closing 1 valve in each vent path OR by closing the common isolation this JPM is complete.

TIME COMPLETED NOTE: Comments required for any step evaluated as UNSAT LOT-SIM-JP-010-A02 Page 7 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

LIST OF REFERENCES RELATED TASKS:

261 008 B1 01, Perform Normal Primary Containment Venting.

K/A REFERENCE AND IMPORTANCE RATING:

261000 A4.04 3.3/3.4, Ability to manually operate and monitor Primary Containment Pressure.

REFERENCES:

2OP-10, Sect. 8.2 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2):

Safety Function 9, Radioactivity Release REASON FOR REVISION:

Enhanced instructor cues.

LOT-SIM-JP-010-A02 Page 8 of 10 Rev.5

Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%

Time Required for Completion: 10 Minutes (approximate)

Time Taken:

APPLICABLE METHOD OF TESTING Performance: Simulate ___ Actual x Unit: 2 Setting: Control Room Simulator x Admin Time Critical: Yes No x Time Limit N/A Alternate Path: Yes x No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Comments:

Comments reviewed with Performer Evaluator Signature: Date:

LOT-SIM-JP-010-A02 Page 9 of 10 Rev.5

TASK CONDITIONS:

1. Drywell pressure is above normal due to a partial loss of Drywell Cooling.
2. Standby Gas Treatment System is in the Standby Alignment.
3. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent Isolation Override is in OFF.

INITIATING CUE:

The Unit CRS directs you to vent the Drywell via Standby Gas Treatment, and to inform him when drywell pressure has been reduced below 0.5 psig.

8.2 Venting Containment Via the SBGT C Continuous Use 8.2.1 Initial Conditions Date/Time Started Today / Now Initials

1. Drywell pressure has increased to greater than RO 0.15 psig.
2. SBGT System is in standby in accordance with RO Section 5.1.
3. Plant stack radiation monitor is in service AND RO CAC-CS-5519, CAC PURGE VENT ISOL OVRD, is in OFF OR E&RC has sampled the drywell atmosphere and has NA determined that it is suitable for release.
4. Unit CRS's approval is obtained prior to venting. RO 8.2.2 Procedural Steps NOTE: IF the plant stack radiation monitor is out of service, THEN Steps 1 through 4 are NOT applicable.

NOTE: Backwashing an RWCU filter or AOG effluent sampling may cause stack radiation to increase. Venting primary containment and RWCU backwashing or AOG effluent sampling should not be done concurrently.

1. RECORD 2-D12-RR-R600B, STACK RAD MONITOR, digital point display.

2-D12-RR-R600B:

2OP-10 Rev. 72 Page 18 of 45

8.2.2 Procedural Steps

2. IF the value obtained in Step 8.2.2.1 is greater than or equal to 1, ADD 0.17 to obtain the logarithmic equivalent of a 50% increase in stack radiation monitor reading.

0.17 + =

Step 8.2.2.1 Result NOTE: A 2-D12-RR-R600B, STACK RAD MONITOR indication of 1 and downscale denotes an effluent release value of < 10 µCi/sec as indicated on the Stack RM-23 panel.

3. IF the value obtained in Step 8.2.2.1 is less than 1 and downscale, SUBSTITUTE 1.17 to obtain the logarithmic equivalent as a conservative value to monitor for an increase in the stack radiation monitor reading.
4. RECORD the logarithmic equivalent OR substitute value for a stack radiation monitor increase as determined in Step 8.2.2.2 or 8.2.2.3.

Value:

5. CLOSE REACTOR BUILDING SBGT TRAIN 2A INLET VALVE, 2-VA-2D-BFV-RB.
6. CLOSE REACTOR BUILDING SBGT TRAIN 2B INLET VALVE, 2-VA-2H-BFV-RB.
7. OPEN SBGT DW SUCT DAMPER, 2-VA-2F-BFV-RB.

2OP-10 Rev. 72 Page 19 of 45

8.2.2 Procedural Steps R15 CAUTION Simultaneous venting of the Drywell and the Suppression Pool shall NOT be performed when the plant is in Mode 1, 2, or 3.

8. IF it is desired to vent the suppression chamber, THEN PERFORM the following:
a. OPEN SUPP POOL PURGE EXH VLV, 2-CAC-V172.
b. OPEN TORUS PURGE EXHAUST VLV, 2-CAC-V22.
c. MONITOR STACK RAD MONITOR, 2-D12-RR-R600B, on Panel XU-3 for an increase in activity during the performance of this procedure
d. IF stack radiation increases above the value determined in Step 8.2.2.4, THEN PERFORM the following to secure venting the suppression pool:

CLOSE SUPP POOL PURGE EXH VLV, /

2-CAC-V172. Ind.Ver.

CLOSE TORUS PURGE EXHAUST /

VLV, 2-CAC-V22. Ind.Ver.

NOTIFY E&RC to sample primary containment.

NOTIFY E&RC to reference 0E&RC-2020 Setpoint Determinations for Gaseous Radiation Monitors (Noble Gas Instantaneous Release Rate Determination).

2OP-10 Rev. 72 Page 20 of 45

8.2.2 Procedural Steps

e. WHEN the desired suppression chamber pressure is reached, as indicated on Computer Point L128, THEN CLOSE the following valves:

SUPP POOL PURGE EXH VLV, /

2-CAC-V172. Ind.Ver.

TORUS PURGE EXHAUST VLV, /

2-CAC-V22. Ind.Ver.

9. IF it is desired to vent the drywell, THEN PERFORM the following:
a. OPEN DW PURGE EXH VLV, 2-CAC-V9.
b. OPEN DW PURGE EXH VLV, 2-CAC-V23.
c. OPEN DW HEAD PURGE EXH VLV, 2-CAC-V49, if desired.
d. OPEN DW HEAD PURGE EXH VLV, 2-CAC-V50, if desired.
e. MONITOR STACK RAD MONITOR, 2-D12-RR-R600B, on Panel XU-3 for an increase in activity during the performance of this procedure.
f. IF stack radiation increases above the value determined in Step 8.2.2.4, THEN PERFORM the following to secure venting the drywell:

CLOSE DW PURGE EXH VLV, /

2-CAC-V23. Ind.Ver.

CLOSE DRYWELL PURGE EXH VLV, /

2-CAC-V9. Ind.Ver.

ENSURE DW HEAD PURGE EXH VLV, /

2-CAC-V49, is closed. Ind.Ver.

ENSURE DW HEAD PURGE EXH VLV, /

2-CAC-V50, is closed. Ind.Ver.

2OP-10 Rev. 72 Page 21 of 45

8.2.2 Procedural Steps NOTIFY E&RC to sample primary containment.

NOTIFY E&RC to reference 0E&RC-2020 Setpoint Determinations for Gaseous Radiation Monitors (Noble Gas Instantaneous Release Rate Determination).

g. WHEN the desired drywell pressure is reached as indicated on CAC-PI-2685-1 on Panel XU-51, THEN PERFORM the following:

CLOSE DW PURGE EXH VLV, /

2-CAC-V23. Ind.Ver.

CLOSE DRYWELL PURGE EXH VLV, /

2-CAC-V9. Ind.Ver.

ENSURE DW HEAD PURGE EXH VLV, /

2-CAC-V49, is closed. Ind.Ver.

ENSURE DW HEAD PURGE EXH VLV, /

2-CAC-V50, is closed. Ind.Ver.

10. CLOSE SBGT DW SUCT DAMPER, /

2-VA-2F-BFV-RB. Ind.Ver.

11. OPEN SBGT TRAIN 2B REACTOR BUILDING /

SUCTION VALVE, 2-VA-2H-BFV-RB. Ind.Ver.

12. OPEN SBGT TRAIN 2A REACTOR BUILDING /

SUCTION VALVE, 2-VA-2D-BFV-RB. Ind.Ver.

2OP-10 Rev. 72 Page 22 of 45

8.2.2 Procedural Steps NOTE: Technical Specification 3.6.1.6.1 (Modes 1, 2, or 3) requires completion of 0PT-02.3.1b, Suppression Pool To Drywell Vacuum Breaker Position Check, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open. Due to the inability to detect a vacuum breaker opening and subsequently reclosing, other than observation from a dedicated Operator, the conservative approach is to perform 0PT-02.3.1b following venting activities.

13. IF in Modes 1, 2, or 3, THEN PERFORM 0PT-02.3.1b, Suppression Pool To Drywell Vacuum Breaker Position Check, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open.

Date/Time Completed Performed By (Print) Initials Reviewed By:

Unit CRS/SRO 2OP-10 Rev. 72 Page 23 of 45

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Place SULCV In Service Following a Reactor Scram with a SULCV failure LESSON NUMBER: LOT-SIM-JP-032-08 REVISION NO: 04

Place SULCV In Service with a SULCV failure.

SIMULATOR SETUP A. Initial Conditions

1. Recommended Initial Conditions IC 11 Rx. Pwr. 100%

Core Age BOC

2. Required Plant Conditions RPV water level <170, RFP high-level trips sealed-in B. Malfunctions CF035F, S/U Lvl Cont Vlv Fails Closed C. Overrides None.

D. Special Instructions

1. Trip the Main Turbine to insert a reactor scram and perform immediate actions with exception of tripping one RFP; allow RFPs to trip on high level.
2. Lower RPV level to <170. Ensure RCIC is tripped and HPCI AOP is in PTL.
3. Perform actions of the SULCV Hard card up to step 9.
4. Place a red cap on the HPCI AOP.

LOT-SIM-JP-032-08 Page 2 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

SAFETY CONSIDERATIONS:

NONE EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.
2. If this is the first set of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the trainee.

Read the following to the trainee TASK CONDITIONS:

1. A reactor scram has occurred.
2. RPV water level has dropped below +170 and Feedwater is required to restore RPV water level to the normal band.
3. HPCI and RCIC are not available.
4. Feedwater Level Control Following A Reactor Scram Hard Card was started and completed up through step 8.
5. Feedwater Level Control Following a Reactor Scram - Reactor Feed Pump Startup is completed up to step 3.

INITIATING CUE:

You are directed by the Unit CRS to:

(1) restart Reactor Feed Pump A, (2) complete the actions to place the Startup Level Control Valve in service, and (3) restore RPV water level to +170 - +200.

Inform the Unit CRS when RPV water level has been restored above 170.

LOT-SIM-JP-032-08 Page 3 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain Hard Card S/1205.

Hard Card S/1205 obtained.

SAT/UNSAT*

TIME START ___________

NOTE: The Operator needs to flip the hard card over to the side for REACTOR FEED PUMP STARTUP instructions.

Step 2 - Open RFP A Recirc Valve FW-FV-V46.

RFP A Recirc Valve FW-FV-V46 control switch is placed to open and the valve is verified to indicate full open.(red light on, green light off)

    • CRITICAL STEP ** SAT/UNSAT*

Step 3 - Ensure open RFP A Discharge Valve FW-V3.

RFP A Discharge Valve FW-V3 verified to already indicate full open, (red light on, green light off).

SAT/UNSAT*

Step 4 - Place RFPT A SP CTL, C32-SIC-R601A in MANUAL at its lower limit.

RFPT A SP CTL, C32-SIC-R601A indicates M with output at 0%.

SAT/UNSAT*

Step 5 -Place A MAN/DFCS Control Switch to MANUAL.

MAN/DFCS Control Switch in MANUAL for A RFP.

    • CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-032-08 Page 4 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

Step 6 - Ensure Reactor Water Level is less than +206 inches AND RFPT A&B High Level Trip/Reset Pushbuttons are reset.

Observes RPV water level is <206 inches using indications on the P603 Panel and depresses at least 2 of 3 reset push buttons are depressed and amber high level trip amber lamps on P603 are extinguished.

    • CRITICAL STEP ** SAT/UNSAT*

Step 7 - Depress RFPT A RESET pushbutton.

RFPT A reset pushbutton on XU-2 depressed and RFP Tripped annunciator cleared.

    • CRITICAL STEP ** SAT/UNSAT*

Step 8 - Ensure RFP A LP and HP Stop Valves are open.

Verifies RFPT A LP and HP Stop Valves automatically opened on XU-2.

SAT/UNSAT*

Step 9 - Depress the RFP A START Pushbutton and verifies RFP at ~1000 rpms.

RFP A START Pushbutton depressed and RFP speed verified to raise to

~1000 rpm.

    • CRITICAL STEP ** SAT/UNSAT*

Step 10 - Raise RFP A speed to 2550 rpm using the LOWER/RAISE Control Switch on Panel XU-1.

Using the raise switch, raises RFP A speed to ~2550 rpm.

    • CRITICAL STEP ** SAT/UNSAT*

LOT-SIM-JP-032-08 Page 5 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

Step 11 - Depress the RFPT DFCS CTRL RESET Pushbutton and place MAN/DFCS Control Switch to DFCS.

Depresses RFPT DFCS CTRL RESET Pushbutton and verifies DFCS CTRL light is illuminated then places MAN/DFCS Control Switch in DFCS.

    • CRITICAL STEP ** SAT/UNSAT*

Step 12 - Selects RFP DEMAND on RFPT A SP CTL, C32-SIC-R601A and raises RFP A speed, until discharge pressure is greater than or equal to 100 psig above reactor pressure.

Raises RFP A discharge pressure to 100 psig above reactor pressure.

    • CRITICAL STEP ** SAT/UNSAT*

NOTE: The Operator needs to flip the hard card over to the other side for Feedwater Level Control Following a Reactor Scram and continue at step 10.

Step 9 was already completed during the startup of the Reactor Feed Pump.

Step 13 - Manually adjust the SULCV, FW-LIC-3269, for desired reactor water level.

SULCV is adjusted in manual to open the valve. Master controller verified to be at 187 inches.

SAT/UNSAT*

NOTE: This is the alternate path portion in that the SULCV will not open and the FW-V120 must be opened to raise water level.

PROMPT: if examinee informs the SCO that the SULCV is failed, direct the examinee to inject feedwater by any available method.

LOT-SIM-JP-032-08 Page 6 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

Step 14 - Diagnosis of SULCV failure and opens FW-V120, (or FW-V118 and FW-V6 OR FW-V119 and FW-V8), to provide a flowpath to the reactor in order to raise reactor water level to 187 inches.

RPV water level is restored above 170 inches by opening one of the following flowpaths:

Throttle the FW-V120 OR Open the FW-V6 and throttle the FW-V118 OR Open the FW-V8 and throttle the FW-V11.

    • CRITICAL STEP ** SAT/UNSAT*

Step 15 - Inform Unit CRS that RPV water level is above +170.

Unit CRS informed.

SAT/UNSAT*

TERMINATING CUE: RPV water level has been restored to >170 inches using the alternate flowpath.

Comments required for any step evaluated as UNSAT.

TIME COMPLETED _____________

LOT-SIM-JP-032-08 Page 7 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

RELATED TASKS:

259202B101 Start the First Reactor Feed Pump per OP-32 K/A REFERENCE AND IMPORTANCE RATING:

259001 A4.02 3.9, 3.7 Ability to manually start/control a RFP in the control room.

REFERENCES:

ATTACHMENT 6 of 2OP-32, Rev 171 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev. 2)

Safety Function 2, Inventory Control REASON FOR REVISION:

Modified to have SULCV failure which makes it an alternate path JPM.

LOT-SIM-JP-032-08 Page 8 of 10 Rev. 0

Place SULCV In Service with a SULCV failure.

Time required for Completion: 18 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator X (Not applicable to In-Plant JPMs)

Time Critical: Yes No X Time Limit N/A Alternate Path: Yes X No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure as Authorized Copy? Yes No (Each Student should verify one JPM per evaluation set.)

Comments:

Comments Reviewed With Trainee Evaluator Signature: Date:

LOT-SIM-JP-032-08 Page 9 of 10 Rev. 0

TASK CONDITIONS:

1. A reactor scram has occurred.
2. RPV water level has dropped below +170 and Feedwater is required to restore RPV water level to the normal band.
3. HPCI and RCIC are not available.
4. Feedwater Level Control Following A Reactor Scram Hard Card was started and completed up through step 8.
5. Feedwater Level Control Following a Reactor Scram - Reactor Feed Pump Startup is completed up to step 3.

INITIATING CUE:

You are directed by the Unit CRS to:

(1) restart Reactor Feed Pump A, (2) complete the actions to place the Startup Level Control Valve in service, and (3) restore RPV water level to +170 - +200.

Inform the Unit CRS when RPV water level has been restored above 170.

Page 10 of 10

ATTACHMENT 6 Page 1 of 2 Feedwater Level Control Following a Reactor Scram - Reactor Feed Pump Startup NOTE: This attachment is also applicable to the Simulator.

NOTE: This attachment is NOT to be used for routine system operation.

FEEDWATER LEVEL CONTROL FOLLOWING A REACTOR SCRAM

1. IF NECESSARY, THEN DISPATCH AN OPERATOR TO RFP A(B) TO RESPOND TO ANY LOCAL ANNUNCIATOR PANEL ALARMS.
2. CLOSE (FW-V6 AND FW-V8) OR (FW-V118 AND FW-V119).
3. ENSURE FW-FV-177 IS CLOSED.
4. OPEN FW-V10.

______ 5. PLACE FEEDWATER CONTROL MODE SELECT TO 1 ELEM.

6. IF BOTH RFPs HAVE TRIPPED, THEN ENSURE MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, IS IN M (MANUAL) AND SET TO MAINTAIN 187 INCHES.
7. ENSURE SULCV, FW-LIC-3269, IN M (MANUAL) AND SULCV CLOSED.
8. ENSURE B21-F032A AND B21-F032B ARE OPEN.
9. IF AN RFP IS RUNNING, THEN PLACE RFPT A (B) SP CTL, C32-SIC-R601A (B), IN M (MANUAL) AND ADJUST RFP A (B) SPEED UNTIL DISCHARGE PRESSURE IS APPROXIMATELY 100 PSI GREATER THAN REACTOR PRESSURE.
10. ADJUST SULCV, FW-LIC-3269, FOR DESIRED REACTOR WATER LEVEL.
11. IF DESIRED, THEN PLACE SULCV, FW-LIC-3269, IN A (AUTO).
12. ADJUST FW-FV-177 TO MAINTAIN SULCV, FW-LIC-3269, OUTPUT DEMAND SIGNAL BETWEEN 25% AND 55%.
13. IF SULCV, FW-LIC-3269, FAILS TO CONTROL LEVEL, THEN USE ONE OR MORE OF THE FOLLOWING VALVES TO AID IN LEVEL CONTROL:

FW-V120, (FW-V118 AND FW-V6), (FW-V119 AND FW-V8).

2/1204 S/1205 2OP-32 Rev. 171 Page 307 of 317

ATTACHMENT 6 Page 2 of 2 Feedwater Level Control Following a Reactor Scram - Reactor Feed Pump Startup NOTE: This attachment is also applicable to the Simulator.

NOTE: This attachment is NOT to be used for routine system operation.

REACTOR FEED PUMP STARTUP

1. IF NECESSARY, THEN DISPATCH AN OPERATOR TO RFP A(B) TO RESPOND TO ANY LOCAL ANNUNCIATOR PANEL ALARMS.

______ 2. ENSURE A FEEDWATER FLOW PATH IS ESTABLISHED TO THE REACTOR VESSEL.

3. OPEN RFP A (B) RECIRC VLV, FW-FV-46 (FW-FV-47).
4. ENSURE RFP A (B) DISCH VLV, FW-V3 (FW-V4) IS OPEN.
5. PLACE RFPT A (B) SP CTL, C32-SIC-R601A (B), IN M (MANUAL) AT ITS LOWER LIMIT.

______ 6. PLACE RFPT A(B) MAN/DFCS CONTROL SWITCH IN MAN.

7. ENSURE REACTOR WATER LEVEL IS LESS THAN +206 INCHES AND RFPT A&B HIGH LEVEL TRIP/RESET PUSHBUTTONS ARE RESET.
8. DEPRESS RFPT A (B) RESET PUSHBUTTON
9. ENSURE RFPT A (B) LP AND HP STOP VLVS ARE OPEN.
10. ROLL RFPT A (B) TO 1000 RPM BY DEPRESSING RFP A(B) START PUSHBUTTON.
11. RAISE RFPT A(B) SPEED TO APPROXIMATELY 2550 RPM USING THE LOWER/RAISE CONTROL SWITCH.

______ 12. DEPRESS RFPT A(B) DFCS CTRL RESET AND PLACE MAN/DFCS CONTROL SWITCH TO DFCS.

13. RAISE RFPT A (B) SPEED WITH RFPT A (B) SP CTL, C32-SIC-R601A (B),

UNTIL DISCHARGE PRESSURE IS GREATER THAN OR EQUAL TO 100 PSIG ABOVE REACTOR PRESSURE.

2/1204 S/1205 2OP-32 Rev. 171 Page 308 of 317

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Resetting CO-FIC-49, SJAE Cond Recirc FCV LESSON NUMBER: LOT-SIM-JP-032-10 REVISION NO: 0

Resetting CO-FIC-49 SIMULATOR SETUP:

Recommended Initial Conditions IC-8 Required Plant Conditions Initiate malfunctions to:

1. Adjust the controller to 5%
2. De-energize the CO-FIC-49
2. Re- energize the CO-FIC-49.

Malfunctions CF110F, CO-FIC-49 Loss of Power Overrides Remotes LOT-SIM-JP-032-10 Page 2 of 8 Rev. 0

Resetting CO-FIC-49 SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the performer.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

Read the following to the JPM performer.

TASK CONDITIONS:

1. Power has been lost to the CO-FIC-49, SJAE Cond Recirc FCV.
2. I&C has completed troubleshooting and repaired the problem.
3. Power has been restored to CO-FIC-49.

INITIATING CUE:

You are directed to reset the CO-FIC-49 IAW 2OP-32, Section 8.40, ensure condensate pump discharge header pressure of 190 - 230 psig, and inform the Unit SCO when the actions are complete.

LOT-SIM-JP-032-10 Page 3 of 8 Rev. 0

Resetting CO-FIC-49 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain current revision of 2OP-32, Section 8.40 and verify revision if applicable.

Current revision of 2OP-32, Section 8.40 obtained.

NA / SAT / UNSAT Time Started:___________

Step 2 - DISPATCH an operator to the Condensate Booster Pump Room to obtain SJAE CONDENSATE RECIRCULATION VALVE, CO-FV-49, % open actuator position.

AO reports the valve indicator is ~5% open.

SAT/UNSAT SIM OP: As the TB AO report that the CO-FV-49 valve indication is ~5% open.

Step 3 - SET SJAE COND RECIRC FCV, CO-FIC-49 OUT (output %) to the value reported by the Auxiliary Operator using the UP and DOWN pushbuttons as necessary Using the up arrow adjusts the setpoint to 5%.

    • CRITICAL STEP**SAT/UNSAT Step 4 - DEPRESS the illuminated RESET pushbutton AND CONFIRM the light goes out.

Depresses the illuminated Reset pushbutton and confirms that the light goes out.

    • CRITICAL STEP**SAT/UNSAT Step 5 -MONITOR condensate pump discharge header pressure.

Observes that condensate discharge header pressure is greater than 230 psig and depresses the up arrow to lower discharge pressure to a band of 190 - 230 psig.

    • CRITICAL STEP**SAT/UNSAT LOT-SIM-JP-032-10 Page 4 of 8 Rev. 0

Resetting CO-FIC-49 Step 6 - Informs Unit SCO that the CO-FIC-49 has been reset.

Unit SCO informed.

SAT/UNSAT TERMINATING CUE: When the CO-FIC-49 has been reset and condensate discharge pressure adjusted to 140 - 230 psig then this JPM is complete.

Time Completed: __________

Comments required for any step evaluated as UNSAT.

LOT-SIM-JP-032-10 Page 5 of 8 Rev. 0

Resetting CO-FIC-49 RELATED TASKS:

291003 K1.03 Operation of a valve controller, including seal-in features K/A REFERENCE AND IMPORTANCE RATING:

400000 A4.01 Ability to manually operate and/or monitor in the control room CCW indications and control

REFERENCES:

OP-32, Section 8.40 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2.):

8, Plant Service Systems REASON FOR REVISION:

New.

LOT-SIM-JP-032-10 Page 6 of 8 Rev. 0

Resetting CO-FIC-49 Validation Time: 5 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:

Time Critical: Yes No X Time Limit NA Alternate Path: Yes No X EVALUATION Performer:

JPM: Pass Fail Remedial Training Required: Yes No Did Performer Verify Procedure? Yes No (Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

LOT-SIM-JP-032-10 Page 7 of 8 Rev. 0

TASK CONDITIONS:

1. Power has been lost to the CO-FIC-49, SJAE Cond Recirc FCV.
2. I&C has completed troubleshooting and repaired the problem.
3. Power has been restored to CO-FIC-49.

INITIATING CUE:

You are directed to reset the CO-FIC-49 IAW 2OP-32, Section 8.40, ensure condensate pump discharge header pressure of 190 - 230 psig, and inform the Unit SCO when the actions are complete.

Page 8 of 8

8.40 Resetting CO-FIC-49 Following a Loss of Power R Reference Use 8.40.1 Initial Conditions

1. SJAE CONDENSATE RECIRCULATION VALVE, CO-FV-49, is failed as is following a loss of power.
2. Power has been restored and it is desired to reset SJAE COND RECIRC FCV, CO-FIC-49.

8.40.2 Procedural Steps NOTE: When power has been restored to SJAE COND RECIRC FCV, CO-FIC-49, the controller digital display will return, displaying OUT 0, MAN, and the RESET pushbutton will be illuminated.

1. DISPATCH an operator to the Condensate Booster Pump Room to obtain SJAE CONDENSATE RECIRCULATION VALVE, CO-FV-49, % open actuator position.
2. SET SJAE COND RECIRC FCV, CO-FIC-49 OUT (output %) to the value reported by the Auxiliary Operator using the UP and DOWN pushbuttons as necessary.
3. DEPRESS the illuminated RESET pushbutton AND CONFIRM the light goes out.
4. MONITOR condensate pump discharge header pressure AND ADJUST SJAE COND RECIRC FCV, CO-FIC-49, controller output to obtain the desired pressure.

2OP-32 Rev. 171 Page 231 of 317

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Manual Initiation of SLC System with RWCU Isolation Failure.

LESSON NUMBER: LOT-SIM-JP-005-01 REVISION NO: 01

Manual Initiation of SLC System with RWCU Isolation Failure.

SIMULATOR SETUP:

Recommended Initial Conditions IC-11, 100% Power, BOC Required Plant Conditions Initiate malfunctions to:

1. Defeat auto and manual scrams
2. Fail open an SRV.

Activate malfunctions/overrides to Fail ARI and then Initiate ARI.

Reduce Recirc to 10 percent and then trip both recirc pumps.

Activate malfunction for RWCU G31-F004 valve to fail to auto close.

Triggers Malfunctions ES002F, ADS Valve E Fails Open, TRUE RW016F, G31-F004 Failure to Auto Close, TRUE RP005F, Auto Scram Defeat, TRUE RP006F, Manual Scram Defeat, TRUE Overrides ARI failed.

Remotes LOT-SIM-JP-005-01 Page 2 of 8 Rev. 01

Manual Initiation of SLC System with RWCU Isolation Failure.

SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL NOT be provided to the performer.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

Read the following to the JPM performer.

TASK CONDITIONS:

1. SRV E failed open and cannot be closed.
2. 0AOP-30.0 directed a Manual Reactor Scram.
3. The Manual Reactor Scram pushbuttons have failed to initiate a scram.
4. The Unit SCO has entered Level Power Control.
5. ARI has been initiated.
6. The recirc pumps have been tripped.

INITIATING CUE:

You are directed to manually initiate Standby Liquid Control System, verify proper indications, and inform the Unit SCO when the actions are complete.

LOT-SIM-JP-005-01 Page 3 of 8 Rev. 01

Manual Initiation of SLC System with RWCU Isolation Failure.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

NOTE: The procedure may not be referenced for this task as it is considered skill of the craft, but the steps of the procedure are still required to be taken.

Step 1 - Obtain current revision of 2OP-05, Section 5.2 and verify revision if applicable.

Current revision of 2OP-05, Section 5.2 obtained.

NA / SAT / UNSAT Time Started:___________

Step 2 - Unlock and place SLC Pumps A & B, C41-CS-S1, in the Pump A & B RUN position.

SLC keylock switch rotated to the A & B RUN position.

    • CRITICAL STEP**SAT/UNSAT NOTE: The following steps may be performed in any order.

Step 3 - Observe the following indications:

Indication SAT UNSAT Squib Valve Continuity Loss Alarm SLC A Squib Valve Continuity Lights out SLC B Squib Valve Continuity Lights out SLC Pump A red indicating light on SLC Pump B red indicating light on SAT/UNSAT NOTE: Step 2 of the procedure would be marked as NA.

NOTE: The RWCU Isolation valve will close when the switch is taken to close.

Step 4 - Recognizes that the RWCU Outboard Isol Vlv, G31-F004, does not close.

Recognizes that the valve is still open.

SAT/UNSAT LOT-SIM-JP-005-01 Page 4 of 8 Rev. 01

Manual Initiation of SLC System with RWCU Isolation Failure.

Step 5 - Closes the RWCU Outboard Isol Vlv, G31-F004.

(Alternately the examinee may close the RWCU Inboard Isol Vlv., G31-F001)

Control switch for the isolation valve placed in close and observes the green light come on and the red light goes out. (F004 valve is a throttle valve)

    • CRITICAL STEP**SAT/UNSAT Step 6 - Ensure SLC Injection by:

Indication SAT UNSAT SLC Storage Tank Level is decreasing SLC Pump Discharge pressure greater than reactor pressure SAT/UNSAT Step 7 - Informs Unit SCO that SLC has been initiated and that the RWCU Isolation valve failed to close and had to manually close the valve.

Unit SCO informed.

SAT/UNSAT TERMINATING CUE: When the SLC pumps have been started and the RWCU Isolation valve has been closed then this JPM is complete.

Time Completed: __________

Comments required for any step evaluated as UNSAT.

LOT-SIM-JP-005-01 Page 5 of 8 Rev. 01

Manual Initiation of SLC System with RWCU Isolation Failure.

RELATED TASKS:

211005B501 K/A REFERENCE AND IMPORTANCE RATING:

211000 A4.08 4.2/

4.2 REFERENCES

Level Power Control OP-05, Section 5.2 TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2.):

1, Reactivity Control REASON FOR REVISION:

formatting.

LOT-SIM-JP-005-01 Page 6 of 8 Rev. 01

Manual Initiation of SLC System with RWCU Isolation Failure.

Validation Time: 5 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:

Time Critical: Yes No X Time Limit NA Alternate Path: Yes X No EVALUATION Performer:

JPM: Pass Fail Remedial Training Required: Yes No Did Performer Verify Procedure? Yes No (Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

LOT-SIM-JP-005-01 Page 7 of 8 Rev. 01

TASK CONDITIONS:

1. SRV E failed open and can not be closed.
2. 0AOP-30.0 directed a Manual Reactor Scram.
3. The Manual Reactor Scram pushbuttons have failed to initiate a scram.
4. The Unit SCO has entered Level Power Control.
5. ARI has been initiated.
6. The recirc pumps have been tripped.

INITIATING CUE:

You are directed to manually initiate Standby Liquid Control System, verify proper indications, and inform the Unit SCO when the actions are complete.

Page 8 of 8

5.2 Manual Initiation of SLC R Reference Use 5.2.1 Initial Conditions

1. Standby Liquid Control System in standby in accordance with Section 5.1.
2. Reactor can NOT be shut down by normal control rod drive or scram functions.
3. Manual initiation of SLC has been directed by Unit CRS.

5.2.2 Procedural Steps CAUTION WHEN the Standby Liquid Control System is manually initiated for a plant emergency, THEN the entire quantity of sodium pentaborate solution should be injected into the reactor before the SLC pumps are stopped to ensure the reactor is subcritical under all conditions.

1. UNLOCK AND PLACE SLC PUMPS A & B, C41-CS-S1, in the PUMP A & B RUN position AND OBSERVE the following:

- SQUIB VALVE CONTINUITY LOSS annunciator on Annunciator Panel A-04 on.

- SLC A/B SQUIB VALVE CONTINUITY indicating lights off at Panel P603.

- SLC PUMP A AND SLC PUMP B red indicating lights on.

2OP-05 Rev. 61 Page 9 of 52

5.2.2 Procedural Steps NOTE: The SLC pump discharge relief valve should NOT actuate with two pumps operating and only one squib valve open unless reactor pressure exceeds 1184 psig, which is possible during an ATWS even with 10 SRVs open.

2. IF SLC A SQUIB VALVE CONTINUITY OR SLC B SQUIB VALVE CONTINUITY indicating light on Panel P603 remains on AND reactor pressure is greater than or equal to 1184 psig, THEN PERFORM the following:
a. PLACE SLC PUMP A & B Control Switch, C41-CS-S1, to the SLC PUMP A OR SLC PUMP B position.
b. ENSURE the selected SLC pump red indicating light on.
3. ENSURE RWCU OUTBOARD ISOL VLV, G31-F004, closes.

NOTE: It will take approximately 29 to 40 minutes to completely empty the SLC Storage Tank with two-pump operation and 58 to 81 minutes with one-pump operation.

4. ENSURE SLC injection as follows:
a. SLC STORAGE TANK LEVEL indicating controller C41-LI-R601 indicates level decreasing.
b. SLC PUMP DISCHARGE PRESSURE, C41-PI-R600, is greater than reactor vessel pressure.

2OP-05 Rev. 61 Page 10 of 52

5.2.2 Procedural Steps CAUTION WHEN the Standby Liquid Control System is manually initiated for a plant emergency, failure to stop the SLC pumps when the liquid supply is exhausted may damage the pumps.

5. WHEN all the solution has been injected into the vessel as indicated by reading zero percent on level indicator C41-LI-R601 OR the Unit CRS has directed the SLC System be shutdown, THEN PLACE SLC PUMP A & B Control Switch, C41-CS-S1, in STOP AND LOCK.

2OP-05 Rev. 61 Page 11 of 52

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Cross-Tie 480 VAC Buses IAW 0AOP 36.1 LESSON NUMBER: LOT-SIM-JP-303-A01 REVISION NO: 01

Cross-Tie 480 VAC Buses IAW AOP 36.1 SIMULATOR SETUP:

A. Initial Conditions:

1. Recommended Initial Conditions IC Unit 2 IC 11 Rx. Pwr. 100% of Rated Thermal Power Core Age BOC
2. Required Plant Conditions
1. The plant has scrammed.
2. E4 and E8 are deenergized.
3. The normal 4160 VAC feeder breakers to E3 and E4 are tripped.
4. The JPM Development Instructor may provide an IC with required plant conditions.

B. Malfunctions DG027F, #4 DG Differential Fault C. Overrides ED, IARKAX5, E7 Breaker AX5, IN ED, IARKAI0, E8 Breaker AI0, IN D. Special Instructions

1. Activate Malfunction #1 to lockout DG #4.
2. Trip the normal 4160 VAC Feeder Breakers to Bus E3 and E4.
3. Verify DG #3 energizes bus E3.
4. Verify Bus E8 is deenergized.
5. Perform overrides to rack in 480V breakers.

Page 2 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the performer.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

Read the following to the JPM performer.

TASK CONDITIONS:

1. Unit 2 has scrammed.
2. Bus E4 and Bus E8 are deenergized.
3. DG #3 is in service supplying Bus E3 and Bus E7.
4. 0AOP-36.1, Loss of any 4160V Buses or 480V E-Buses, has been entered. The 480V crosstie breakers are racked in.
5. Plant conditions require Emergency Bus Cross-Tie operation.
6. DG #4 is unavailable due to a differential lockout.
7. The Unit 1 and Unit 2 SCOs have given permission to cross-tie 480V Emergency Buses.

INITIATING CUE:

You are directed by the Unit SCO to cross-tie 480V Emergency Buses by completing section 3.2.11 of 0AOP-36.1.

Inform the Unit SCO when 480V buses are cross-tied and section 3.2.11 of 0AOP-36.1 is complete.

Page 3 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain a copy of 0AOP-36.1, Section 3.2.11.

Copy of 0AOP-36.1, Section 3.2.11 obtained.

SAT/UNSAT*

TIME START ___________

Step 2 - GO TO section 3.2.11.2.c to cross-tie 480V buses Performer goes to section 3.2.11.2.c.

SAT/UNSAT*

Step 3 - TRIP breaker AZ5, SUB E8 480V MAIN BREAKER.

Breaker AZ5 is placed in the trip position and observes red light go out and green light come on.

    • CRITICAL STEP**SAT/UNSAT*

Step 4 - TRIP breaker AK7, BUS E4 to SUB E8.

Breaker AK7 is placed in the trip position and observes red light go out and green light come on.

    • CRITICAL STEP**SAT/UNSAT*

Prompt: Respond as AO if directed to locally monitor transformer amperage and temperature. Report that transformer amperage and temperature are within normal operating limits.

Page 4 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 Step 5 - PLACE AND HOLD the E7 to E8 cross-tie breaker control switch, BUS E7 TIE TO BUS E8, in CLOSE until cross-tie breakers AX5 and AI0 indicate closed.

Bus E7 Tie to Bus E8 control switch held in the close position until both breakers indicate closed, red lights on. (AX5 MSTR and AI0 SLAVE)

    • CRITICAL STEP**SAT/UNSAT*

Step 6 - ENSURE that the appropriate Battery Chargers have energized and are supplying DC loads.

Battery Chargers are verified energized by Control Room alarms and indications and/or AO is dispatched.

SAT/UNSAT*

Prompt: If requested, respond as the AO that Battery Chargers 2B-1 and 2B-2 are energized and carrying load.

Step 7 - START Battery Room 2A and 2B Ventilation Fans.

Battery Room 2A and 2B Ventilation fans are started by placing the associated control switch in START until the associated dampers open and fans start.

SAT/UNSAT*

Note: The step requires restarting Battery Room Fans. Both Unit 2 Battery Room Fans (2A from E7 and 2B from E8) will require starting.

Step 8- ENSURE available Drywell Coolers are operating.

All Drywell Coolers are verified to be operating.

SAT/UNSAT*

Page 5 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 Step 9 - NOTIFY the Unit SCO that Bus E7 is cross-tied to E8 and section 3.2.11 of 0AOP-36.1 is complete.

Unit SCO is notified that Bus E7 is cross-tied to E8 and section 3.2.11 is complete.

SAT/UNSAT*

TERMINATING CUE: When section 3.2.11 of 0AOP-36.1 is complete and the Unit SCO is notified, this JPM is complete.

TIME COMPLETED _____________

Page 6 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 LIST OF REFERENCES RELATED TASKS:

262007B401 Crosstie Emergency 480 VAC Buses Per AOP-36.1 K/A REFERENCE AND IMPORTANCE RATING:

262001 A2.07 (3.0/3.2)

Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: energizing a dead bus

REFERENCES:

AOP-36.1, LOSS OF ANY 4160V BUSES OR 480V E-BUSES.

TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev 2.):

Group 6, Electrical REASON FOR REVISION:

Update to new revision of AOP-36.1.

Page 7 of 9

Cross-Tie 480 VAC Buses IAW AOP 36.1 Time Required for Completion: 10 Minutes (approximate).

Time Taken: ____

APPLICABLE METHOD OF TESTING Performance: Simulate ___ Actual Unit: 2 Setting: Control Room Simulator (Not applicable to In-Plant JPMs)

Time Critical: Yes No Time Limit N/A Alternate Path: Yes No EVALUATION Performer:

JPM: Pass Fail Remedial Training Required: Yes No Did Performer Verify Procedure? Yes No (Each Student should verify one JPM per evaluation set)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

Page 8 of 9

TASK CONDITIONS:

1. Unit 2 has scrammed.
2. Bus E4 and Bus E8 are deenergized.
3. DG #3 is in service supplying Bus E3 and Bus E7.
4. 0AOP-36.1, Loss of any 4160V Buses or 480V E-Buses, has been entered. The 480V crosstie breakers are racked in.
5. Plant conditions require Emergency Bus Cross-Tie operation.
6. DG #4 is unavailable due to a differential lockout.
7. The Unit 1 and Unit 2 SCOs have given permission to cross-tie 480V Emergency Buses.

INITIATING CUE:

You are directed by the Unit SCO to cross-tie 480V Emergency Buses by completing section 3.2.11 of 0AOP-36.1.

Inform the Unit SCO when 480V buses are cross-tied and section 3.2.11 of 0AOP-36.1 is complete.

Page 9 of 9

3.0 OPERATOR ACTIONS 3.2.11 Emergency Bus Cross-Tie

1. IF desired to cross-tie a 4160V E bus, THEN PERFORM the following:
a. CONFIRM indications of a lockout OR phase RO overcurrent trip do NOT exist as identified on Attachment 5.
b. CONFIRM the opposite unit has both diesel RO generators OR off-site power is available.
c. OBTAIN permission from both Units CRS to close RO the 4160V E bus cross-tie breakers.

NOTE Placing the local CROSS-TIE BREAKER CONTROL SELECTOR SWITCH, SS-B, in MAINT with a LOCA signal present initiates a 10 minute delay before breaker closure is permitted.

NOTE: E Bus Cross-Tie Breaker keys (TEM30), from the WCC keylocker (Key #93) or Main Control Room Key Locker (Key #91 or #92), will be needed to allow closing the breakers addressed in this section.

d. PLACE the following selected bus cross-tie keylock control switches in MAINT:

Cross-tie E1 and E3:

CONTROL SELECTOR SWITCH, SS-B, RO located on Bus E1, Compt. AG0 (Row-O1),

AND CONTROL SELECTOR SWITCH, SS-B, RO located on Bus E3, Compt. AJ5 (Row-N1)

Cross-tie E2 and E4:

CONTROL SELECTOR SWITCH, SS-B, RO located on Bus E2, Compt. AH9 (Row-P1),

AND CONTROL SELECTOR SWITCH, SS-B, RO located on Bus E4, Compt. AL5 (Row-Q1) 0AOP-36.1 Rev. 53 Page 49 of 94

3.0 OPERATOR ACTIONS CAUTION Due to breaker design limitations, 1200 amps should NOT be exceeded on the incoming feeder to the 4160V E bus supplying power through the cross-tie.

CAUTION In this configuration, one diesel generator may be carrying all the divisional loads for both units. Close coordination between units is required when starting any load to prevent tripping the diesel generator. Maximum diesel generator loading is 3850 KW.

e. PLACE AND HOLD the following selected RTGB RO bus cross-tie control switch in CLOSE until both cross-tie breakers indicate closed AND the undervoltage annunciator clears for the bus(s) energized:

Cross-tie E1 and E3:

BUS E1 TIE TO BUS E3, breaker AG0 AND RO AJ5 Cross-tie E2 and E4:

BUS E2 TIE TO BUS E4, breaker AH9 AND RO AL5

2. IF 4160V E buses are NOT cross-tied AND it is desired to cross-tie 480V E buses, THEN PERFORM the following:
a. OBTAIN permission from both Units CRS to close the 480V E bus cross-tie breakers.

0AOP-36.1 Rev. 53 Page 50 of 94

3.0 OPERATOR ACTIONS

b. RACK IN the following selected cross-tie breakers in accordance with 1(2)OP-50:

Cross-tie E5 and E6:

TIE BREAKER TO E6, located on Sub E5, RO Compt. AT4 (Row-A1),

AND TIE BREAKER TO E5, located on Sub E6, RO Compt AX1 (Row-F1)

Cross-tie E7 and E8:

Sub E7, Compt AX5, TIE BREAKER TO E8 (Row-A1),

AND Sub E8, Compt A10, TIE BREAKER TO E7 (Row-F1)

CAUTION Tripping the main breaker on the energized 480V E bus will result in loss of an additional 480V E bus.

c. PLACE the following selected RTGB 480V main breaker control switch, for the 480V de-energized bus, in TRIP, AND ENSURE the breaker opens:

Cross-tie E5 and E6:

SUB E5 480V MAIN BREAKER, breaker AU9, OR SUB E6 480V MAIN BREAKER, breaker AV4 0AOP-36.1 Rev. 53 Page 51 of 94

3.0 OPERATOR ACTIONS Cross-tie E7 and E8:

SUB E7 480V MAIN BREAKER, breaker AZ1, OR SUB E8 480V MAIN BREAKER, breaker AZ5 CAUTION Tripping the supply breaker to the energized 480V E bus will result in loss of an additional 480V E bus.

d. PLACE the following selected RTGB 4160V supply breaker control switch, for the 480V de-energized bus, in TRIP, AND ENSURE the breaker opens:

Cross-tie E5 and E6:

BUS E1 TO SUB E5, breaker AF8, OR BUS E2 TO SUB E6, breaker AH1 Cross-tie E7 and E8:

BUS E3 TO SUB E7, breaker AJ0, OR BUS E4 TO SUB E8, breaker AK7 0AOP-36.1 Rev. 53 Page 52 of 94

3.0 OPERATOR ACTIONS CAUTION Substation current should be periodically monitored locally to ensure loading remains below 2400 amps. High temperature alarms 1(2)APP-UA-15 (16, 17, 18) Window 3-4, may also result if substation loading is too high. In either case, substation load reduction may be required.

CAUTION In this configuration, one diesel generator will be carrying all 480V E bus loads for the unit. Particular attention to diesel generator loading is required when starting any E bus load. Maximum diesel generator loading is 3850 KW.

e. PLACE AND HOLD the following selected RTGB bus cross-tie control switch in CLOSE until both cross-tie breakers indicate closed:

Cross-tie E5 and E6:

BUS E5 TIE TO BUS E6, breaker AT4 AND AX1 Cross-tie E7 and E8:

BUS E7 TIE TO BUS E8, breaker AX5 AND A10

f. CONFIRM the undervoltage annunciator clears for the bus(s) just reenergized.
3. ENSURE the following appropriate battery chargers have energized and are supplying DC loads:

Cross-tie E5 and E6:

- BATTERY CHARGER 1A-1 (Sub E5/MCC 1CA)

- BATTERY CHARGER 1A-2 (Sub E5/MCC 1CA)

- BATTERY CHARGER 1B-1 (Sub E6/MCC 1CB)

- BATTERY CHARGER 1B-2 (Sub E6/MCC 1CB).

0AOP-36.1 Rev. 53 Page 53 of 94

3.0 OPERATOR ACTIONS Cross-tie E7 and E8:

- BATTERY CHARGER 2A-1 (Sub E7/MCC 2CA)

- BATTERY CHARGER 2A-2 (Sub E7/MCC 2CA)

- BATTERY CHARGER 2B-1 (Sub E8/MCC 2CB)

- BATTERY CHARGER 2B-2 (Sub E8/MCC 2CB).

NOTE: Operating each battery room supply and exhaust fan combination will require approximately 6 KW.

4. START the following associated battery room ventilation fans:

Cross-tie E5 and E6:

- BATTERY ROOM 1A VENT FANS, 1C-SF-CB AND 1C-EF-CB (Sub E5/MCC 1CA)

- BATTERY ROOM 1B VENT FANS, 1B-SF-CB AND 1B-EF-CB (Sub E6/MCC 1CB).

Cross-tie E7 and E8:

- BATTERY ROOM 2A VENT FANS, 2C-SF-CB AND 2C-EF-CB (Sub E7/MCC 2CA)

- BATTERY ROOM 2B VENT FANS, 2B-SF-CB AND 2B-EF-CB (Sub E8/MCC 2CB).

5. ENSURE available drywell coolers are operating.

END OF SECTION 0AOP-36.1 Rev. 53 Page 54 of 94

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Emergency Equalization Around MSIVs - using the Hard Card.

LESSON NUMBER: LOT-SIM-JP-025-A01 REVISION NO: 3

Emergency Equalization Around MSIVs - using the Hard Card.

SIMULATOR SETUP:

A. Initial Conditions:

1. Recommended Initial Conditions IC Any 100% IC Rx. Pwr. 100%

Core Age Any

2. Required Plant Conditions Mode 3 with MSIVs closed, SJAEs tripped, and RFPs tripped B. Malfunctions None C. Overrides None D. Remote Function MS_IAGP1BYP Lo Cond Vacuum GP1 Trip Byp E. Special Instructions Perform a MANUAL Scram carry out EOP-01-RSP initial operator actions. Close the MSIVs, Trip the SJAEs, RFPs and OPEN the condenser vacuum breakers to reduce vacuum to <10". After this is done place the MSIV control switches to OPEN.

LOT-SIM-JP-025-A01 Page 2 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to performer)

1. The applicable procedure section WILL be provided to the performer.
2. If this is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021, Appendix E, or similar to the performer.

Read the following to the JPM performer.

TASK CONDITIONS:

1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
4. The Unit SCO has anticipated that Emergency Depressurization may be required.
5. The condenser vacuum bypass switches are in the bypass position
6. Another operator will control reactor pressure 800 - 1000 psig using SRVs.

INITIATING CUE:

You are directed to perform the control operator actions associated with emergency equalization around the MSIVs, and open MSIVs when pressure is <200 psid, using the Hard Card.

You are to inform the Unit SCO when all of the MSIVs are open IAW the Hard Card.

LOT-SIM-JP-025-A01 Page 3 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain "Hard Card" for MSIV equalization (S1032).

"Hard Card" obtained for MSIV equalization.

SAT/UNSAT TIME START ___________

Step 2 - Ensure the condenser vacuum bypass switches in bypass position.

Vacuum bypass switches are verified to be in bypass from the Initial Conditions given or by recognizing that alarms A-7, 5-6, Low Cndsr Vacuum Bypass Sys A and A-7, 6-6, Low Cndsr Vacuum Bypass Sys B are in alarm.

SAT/UNSAT Step 3 - Place all MSIV control switches in the CLOSE position.

All MSIV control switches, B21-F022A, B, C & D, B21-F028A, B, C & D, placed in CLOSE position.

SAT/UNSAT Step 4 - Reset Group 1 Isolation.

Group 1 Isolation reset switches, A72-S32 and S33, on P601, are depressed and White lights are ON.

    • CRITICAL STEP ** SAT/UNSAT Step 5 - Open Outboard MSIVs.

Outboard MSIV control switches, B21-F028A, B21-F028B, B21-F028C, B21-F028D, placed in OPEN and MSIVs are OPEN as indicated by the red lights on, green lights off.

    • CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-025-A01 Page 4 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

Step 6 - Open MS-F020.

Ensures MSL Drain Isolation Valve, MS-F020, is open.

SAT/UNSAT Step 7 - Open B21-F019.

Places the control switch for MSL Outboard Drain Isolation Valve, B21-F019, to open and verifies the red light comes on and the green light goes out.

    • CRITICAL STEP ** SAT/UNSAT Step 8 - Ensure the following valves are closed:

Main Steam to SJAE, MS-V3 Main Steam to SJAE, MS-V4 Stm to East MSR Drain Vlv, MS-V43 Stm to West MSR Drain Vlv, MS-V44 Drn Vlv, MS-V45 RFP B HP Stop & Ln Drn, MS-V37, MS-V39 RFP A HP Stop & Ln Drn, MS-V41, MS-V42 Stm to SJAE Drain Vlv, MS-V36 Mn Stm Ln Before SV Drains, MS-V46 Mn Stm Ln Before SV Drains, MS-V47 Mn Stm Ln Before SV Drains, MS-V48 Mn Stm Ln Before SV Drains, MS-V49 Mn Stm to BPV Chest Drn Vlv, MS-V35 Main Steam Line Drain Vlv, MVD-F021 2nd Stg RH Stm Vlv, RSSV-1 2nd Stg RH Stm Vlv, MS-RSSV-2 Ensures all listed valves are closed.

SAT/UNSAT Step 9 - Ensure both Reactor Feed Pumps tripped.

Verifies both Reactor Feed Pumps are tripped.

SAT/UNSAT LOT-SIM-JP-025-A01 Page 5 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

Step 10 - Open B21-F016.

MSL Inboard Drain Isolation Valve, B21-F016, open.

    • CRITICAL STEP ** SAT/UNSAT*

Step 11 - Open MS-F038 A, B, C, D.

MSL Orifice Bypass Valve, MS-F038A, B, C, and D, open

    • CRITICAL STEP ** SAT/UNSAT Step 12 - Ensure steam line pressure is increasing downstream of Outboard MSIVs.

Steam line pressure rising as indicated on Main Steam Pressure A/B indications on XU-1.

SAT/UNSAT Step 14 - When < 200 psid across the valves, open Inboard MSIVs.

Inboard MSIVs B21-F022A, B, C & D are open.

    • CRITICAL STEP ** SAT/UNSAT Step 20 - Notify Unit SCO that MSIVs are open for anticipating emergency depressurization.

Unit SCO notified MSIVs have been opened per the Hard Card.

SAT/UNSAT TERMINATING CUE: When the actions to equalize around and open MSIVs have been performed per the hard card, this JPM is complete.

TIME COMPLETED _____________

NOTE: Comments required for any step evaluated as UNSAT LOT-SIM-JP-025-A01 Page 6 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

RELATED TASKS:

239 201 B4 01 Equalize Around And Open Main Steam Isolation Valves Per Hot Startup OP-25.

K/A REFERENCE AND IMPORTANCE RATING:

239001 A4.01 4.2/4.0 Ability to manually operate and or monitor in the Control Room: MSIVs

REFERENCES:

EOP-01-RVCP, Reactor Vessel Control Procedure Hard Card for Emergency MSIV equalization and reopening (S/1032)

TOOLS AND EQUIPMENT:

None SAFETY FUNCTION (from NUREG 1123, Rev .2) 3 - Reactor Pressure Control (Main and Reheat Steam System)

REASON FOR REVISION:

Revised to match latest revision for hard card S/1032, OP-25.

LOT-SIM-JP-025-A01 Page 7 of 9 Rev. 3

Emergency Equalization Around MSIVs - using the Hard Card.

Validation Time: 15 Minutes (approximate).

Time Taken: _________

APPLICABLE METHOD OF TESTING Performance: Simulate Actual X Unit: 2 Setting: Control Room Simulator X In-Plant:

Time Critical: Yes No X Time Limit Alternate Path: Yes No X EVALUATION Performer:

JPM: Pass Fail Remedial Training Required: Yes No Comments:

Comments reviewed with Performer Evaluator Signature: Date:

LOT-SIM-JP-025-A01 Page 8 of 9 Rev. 3

TASK CONDITIONS:

1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
4. The Unit SCO has anticipated that Emergency Depressurization may be required.
5. The condenser vacuum bypass switches are in the bypass position
6. Another operator will control reactor pressure 800 - 1000 psig using SRVs.

INITIATING CUE:

You are directed to perform the control operator actions associated with emergency equalization around the MSIVs, and open MSIVs when pressure is <200 psid, using the Hard Card.

You are to inform the Unit SCO when the actions to equalize and open the MSIVs per the Hard Card are complete.

Page 9 of 9

ATTACHMENT 4 Page 1 of 1 2OP-25, Equalization Around and Opening of MSIVs For Anticipation of Emergency Depressurization or Reactor Pressure Control During an ATWS

______: IF IN MODE 3 AND CONDENSER VACUUM IS LOW, THEN ENSURE VACUUM BYPASS SWITCHES ARE IN BYPASS

______: PLACE MSIV CONTROL SWITCHES TO CLOSE

______: RESET GROUP 1 ISOLATION

______: OPEN OUTBOARD MISVs

______: OPEN MS-F020

______: OPEN B21-F019

______: ENSURE CLOSED MS-V3, MS-V4, MS-V43, MS-V44, MS-V45, MS-V37/V39, MS-V41/V42, MS-V36, MS-V46, MS-V47, MS-V48, MS-V49, MS-V35, MVD-F021, RSSV-1, RSSV-2

______: ENSURE BOTH REACTOR FEED PUMPS TRIPPED

______: OPEN B21-F016

______: OPEN MS-F038A, B, C, AND D

______: ENSURE STEAM LINE PRESSURE IS INCREASING DOWN STREAM OF OUTBOARD MSIVs

______: WHEN LESS THAN 50 PSID OR 200 PSID ACROSS THE VALVE FOR A RAPID RECOVERY, OPEN INBOARD MSIVs

______: OPEN MVD-V5005

______: ENSURE OPEN MS-V3, MS-V4, MS-V43, MS-V44, MS-V45, MS-V37/V39, MS-V41/V42, MS-V36, MS-V46, MS-V47, MS-V48, MS-V49, MS-V35, MVD-F021

______: CONTINUE WITH PRESSURE CONTROL STEPS AS DIRECTED BY THE EOPs 2/1031 S/1032 2

2OP-25 Rev. 61 Page 62 of 64

PROGRESS ENERGY - CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: RCIC Start in Pressure Control - Exhaust Diaphragm Failure LESSON NUMBER: LOT-SIM-JP-016-08 REVISION NO: 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure SIMULATOR SETUP Recommended Initial Conditions IC-11 Required Plant Conditions:

1. Scram the Reactor and close MSIVs
2. Perform scram immediate actions
3. Ensure RPV level is stable and >LL2
4. Reset the scram, Set CRD to 30 gpm, RWCU reject at 35 gpm
5. Place SBGT in service.

Triggers:

Create Trigger 1: E51-F045 Red Light Equal to TRUE.

Malfunctions:

ES041F, RCIC Failure to Auto Start Lamps E1, P601, Q1612SWM, Auto Isol Sig A White, ON E1, P601, Q1611SWM, Auto Isol Sig B White, ON Alarms E1, P601, ZA352, RCIC Isol Trip Sig A, ON E1, P601, ZA362, RCIC Isol Trip Sig B , ON E1, P601, ZA324, RCIC Turb Exh Diaph Press Hi, Remotes None Special Instructions:

HPCI in PTL and place a red cap on switch.

LOT-SIM-JP-016-08 Page 2 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL NOT be provided to the trainee.
2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. The reactor has scrammed due to MSIV closure.
2. RPV water level is stable.
3. HPCI Aux Oil Pump is under clearance.
4. Another operator will control RPV pressure using SRVs.

INITIATING CUE:

You are directed by the SCO to start RCIC for pressure control and lower pressure to 800 psig per the Hard Card and inform the SCO when the actions are complete.

LOT-SIM-JP-016-08 Page 3 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain Hard Card RCIC Instructional Aid for EOPs.

Hard Card RCIC Instructional Aid for EOPs obtained at P601.

SAT/UNSAT Time Start: ___________

Step 2 - Ensure the following valves are open: Turbine Trip & Throttle Valve, E51-V8, and Turbine Trip & Throttle Valve Actuator, E51-V8, and Turbine Governor Valve, E51-V9.

Verifies E51-V8 (valve position) E51-V8 (actuator position) and E51-V9 are open.

SAT/UNSAT Step 3 - Open Cooling Water Supply Valve, E51-F046.

E51-F046 control switch is placed in OPEN (spring return to Auto) and red light comes on and green light goes out.

    • CRITICAL STEP ** SAT/UNSAT Step 4 - Start Vacuum Pump and leave switch in START.

Vacuum Pump control switch is placed in Start and red light comes on and green light goes out.

SAT/UNSAT Step 5 - Ensure closed RCIC Injection Valve, E51-F013.

E51-F013 green light verified on.

SAT/UNSAT LOT-SIM-JP-016-08 Page 4 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure Step 6 - Open Redundant Isol to CST Vlv, E41-F011.

E41-F011 control switch is placed in open and red light comes on and green light goes out.

    • CRITICAL STEP ** SAT/UNSAT NOTE: The control switch for this valve is on the HPCI system.

Step 7 - Open Bypass to CST Vlv, E51-F022, until dual indication is obtained E51-F022 control switch is placed in open until the red light comes on and then is released.

    • CRITICAL STEP ** SAT/UNSAT Step 8 - Open Turbine Steam Supply Vlv, E51-F045.

E51-F045 control switch is placed in open and red light comes on and green light goes out.

    • CRITICAL STEP ** SAT/UNSAT Step 9 - Ensure that the RCIC turbine starts and comes up to speed as directed by RCIC FLOW CONTROL.

RCIC Turbine speed observed to come up to speed.

SAT/UNSAT/NE Step 9 - Adjust RCIC turbine to get 500 gpm and controller full open.

Adjusts the controller or F022 valve to obtain 500 gpm with the controller output at 100%.

SAT/UNSAT/NE LOT-SIM-JP-016-08 Page 5 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure NOTE: Alternate Path - The RCIC system annunciators will alarm for exhaust diaphragm failure and isolation but the RCIC system does not isolate.

SIM OP: Activate trigger 1 when instructed to by the examiner.

Step 11 - Recognize the RCIC Exhaust diaphragm failure.

RCIC isolation failure is recognized.

SAT/UNSAT/NE Step 12 - Recognize the failure of the RCIC Steam Supply Valves, E51-F007 and E51-F008, to close.

Failure of E51-F007 and E51-F008 to close is recognized.

SAT/UNSAT NOTE: The examinee may trip the turbine first to isolate the leak and then close the isolation valves.

Step 13 - Manually close RCIC Steam Supply Valve, E51-F007 OR RCIC Steam Supply Valve, E51-F008 OR both.

Places control switches for E51-F007 or E51-F008 or both to the closed position and verifies that the red lights go out and the green lights come on.

    • CRITICAL STEP ** SAT/UNSAT Step 14 - Notify the Unit SCO that the RCIC Exhaust Diaphram has ruptured and that E51-F007 and E51-F008 were manually closed to isolate the leak.

Unit SCO is notified SAT/UNSAT TERMINATING CUE: When the RCIC System is isolated and the Unit SCO is notified, this JPM is complete.

LOT-SIM-JP-016-08 Page 6 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure Time Completed: ___________

Comments required for any step evaluated as UNSAT.

LOT-SIM-JP-016-08 Page 7 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure RELATED TASKS:

217003B101, Manually Startup The RCIC System Per OP-16 K/A REFERENCE AND IMPORTANCE RATING:

217000 A4.08 3.7/3.6 Ability to manually operate and/or monitor RCIC system flow

REFERENCES:

S/969 (RCIC Hard Card)

TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

2 - Inventory Control REASON FOR REVISION:

New JPM.

LOT-SIM-JP-016-08 Page 8 of 10 Rev. 0

RCIC Start in Pressure Control - Exhaust Diaphragm Failure Validation Time: 10 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit: 2 Setting: Control Room Simulator ( Not applicable to In-Plant JPMs )

Time Critical: Yes No Time Limit N/A Alternate Path: Yes No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure?: Yes No (Each Student should verify one JPM per evaluation set.)

Comments:

Comments reviewed with Student Evaluator Signature: Date:

LOT-SIM-JP-016-08 Page 9 of 10 Rev. 0

TASK CONDITIONS:

1. The reactor has scrammed due to MSIV closure.
2. RPV water level is stable.
3. HPCI Aux Oil Pump is under clearance.
4. Another operator will control RPV pressure using SRVs.

INITIATING CUE:

You are directed by the SCO to start RCIC for pressure control and lower pressure to 800 psig per the Hard Card and inform the SCO when the actions are complete.

Page 10 of 10

ATTACHMENT 7 Page 1 of 1 RCIC Instructional Aid for EOPs MANUAL RCIC INJECTION (2OP-16 Section 5.3)

1. ENSURE THE FOLLOWING VALVES ARE OPEN: E51-V8 (VALVE POSITION),

E51-V8 (ACTUATOR POSITION), AND E51-V9.

2. OPEN E51-F046
3. START VACUUM PUMP AND LEAVE SWITCH IN START.
4. OPEN E51-F045
5. OPEN E51-F013
6. ENSURE RCIC TURBINE STARTS AND COMES UP TO SPEED AS DIRECTED BY RCIC FLOW CONTROL
7. ADJUST RCIC FLOW CONTROLLER TO OBTAIN DESIRED FLOW RATE.
8. ENSURE E51-F019 IS CLOSED WITH FLOW ABOVE 80 GPM.
9. ENSURE THE FOLLOWING VALVES ARE CLOSED: E51-F025, E51-F026, E51-F004, AND E51-F005
10. START SBGT (2OP-10)
11. ENSURE BAROMETRIC CNDSR CONDENSATE PUMP OPERATES RCIC PRESSURE CONTROL (2OP-16 SECTION 8.2)
1. ENSURE THE FOLLOWING VALVES ARE OPEN: E51-V8 (VALVE POSITION),

E51-V8 (ACTUATOR POSITION), AND E51-V9.

2. OPEN E51-F046
3. START VACUUM PUMP AND LEAVE SWITCH IN START.
4. ENSURE E51-F013 IS CLOSED
5. ENSURE E41-F011 IS OPEN
6. THROTTLE OPEN E51-F022 UNTIL DUAL INDICATION IS OBTAINED
7. OPEN E51-F045
8. THROTTLE OPEN E51-F022 OR ADJUST RCIC FLOW CONTROL, E51-FIC-R600, TO OBTAIN DESIRED SYSTEM PARAMETERS AND REACTOR PRESSURE.
9. ENSURE E51-F019 IS CLOSED WITH FLOW ABOVE 80 GPM.
10. ENSURE THE FOLLOWING VALVES ARE CLOSED: E51-F025, E51-F026, E51-F004, AND E51-F005.
11. START SBGT (2OP-10)
12. ENSURE BAROMETRIC CNDSR CONDENSATE PUMP OPERATES FOR SHUTDOWN REFER TO 2OP-16 FOR TRANSFER BETWEEN PRESSURE AND LEVEL CONTROL REFER TO 2OP-16 1 2/968 S/969 2OP-16 Rev. 108 Page 86 of 90

PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE SIMULATOR LESSON TITLE: Restore Nitrogen Backup System after an Isolation LESSON NUMBER: LOT-SIM-JP-046-001 REVISION NO: 0

Restore Nitrogen Backup System after an Isolation SIMULATOR SETUP Recommended Initial Conditions IC-11 Rx Pwr 100%

BOC Required Plant Conditions:

Triggers:

Malfunctions:

Insert an inadvertent CS initiation and then remove the malfunction.

Overrides:

Remotes None Special Instructions:

Verify auto actions occurred for the inadvertent CS initiation signal.

Turn both Core Spray pumps off.

Reset the Core Spray logic.

Ensure cooling to the drywell is re-established.

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Restore Nitrogen Backup System after an Isolation SAFETY CONSIDERATIONS:

None EVALUATOR NOTES: (Do not read to trainee)

1. The applicable procedure section WILL be provided to the trainee.
2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.

Read the following to trainee.

TASK CONDITIONS:

1. Core Spray instrumentation was bumped causing an inadvertent initiation signal.
2. Auto actions have been verified.
3. Core Spray has been shutdown IAW 2OP-18.
4. Prerequisites of 0OP-46 are all met.

INITIATING CUE:

You are directed to Restore the Nitrogen Backup System in accordance with 0OP-46.

Inform the Unit SCO when the Nitrogen Backup System is restored to normal.

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Restore Nitrogen Backup System after an Isolation PERFORMANCE CHECKLIST NOTE: Sequence is assumed unless denoted in the Comments.

Step 1 - Obtain copy of 0OP-46 Section 8.10 to restore Nitrogen Backup System to normal.

Section 8.10 of 0OP-46 is obtained.

SAT/UNSAT TIME START: ___________

Step 2 - Ensures the Core Spray / LOCA Logic has been reset.

Verifies that both Initiation Signal Sealed-In white lights for Core Spray are extinguished. (Step 8.10.2.1)

SAT/UNSAT Step 3 - Verifies instrument air header pressure (IA-PI-724-1) is greater than 98 psig.

Verifies air header pressure is normal. (Step 8.10.2.2)

SAT/UNSAT Step 4 -Verifies that the following alarms are clear:

Alarms are clear. (Step 8.10.2.3)

Alarm SAT UNSAT UA-01 1-1 RB Instr Air Receiver 2A Press Low UA-01 1-2 RB Instr Air Receiver 2B Press Low SAT/UNSAT Step 5 - Momentarily place Div I Non-Intrpt RNA, RNA-SV-5262, control switch to the Override/Reset position, then to OPEN.

Control switch placed to override/reset then back to open. (Step 8.10.2.4)

    • CRITICAL STEP ** SAT/UNSAT LOT-SIM-JP-046-001 Page 4 of 8 REV. 0

Restore Nitrogen Backup System after an Isolation Step 6 - Ensures the following valve positions:

Valves in their appropriate position. (Step 8.10.2.4a/b)

Valve Position SAT UNSAT Div I Non-Intrpt RNA, RNA-SV-5262 open Div I Backup N2 Rack Isol Vlv, RNA-SV-5482 closed SAT/UNSAT Step 7 - Momentarily place Div II Non-Intrpt RNA, RNA-SV-5261, control switch to the Override/Reset position, then to OPEN.

Control switch placed to override/reset then back to open. (Step 8.10.2.5)

    • CRITICAL STEP ** SAT/UNSAT Step 8 - Ensures the following valve positions:

Valves in their appropriate position. (Step 8.10.2.5a/b)

Valve Position SAT UNSAT Div II Non-Intrpt RNA, RNA-SV-5261 open Div II Backup N2 Rack Isol Vlv, RNA-SV-5481 closed SAT/UNSAT PROMPT: Inform the examinee that another operator will perform Attachment 11.

Step 9 - Inform Unit SCO that Core Spray has been shutdown and Nitrogen Backup System is in normal alignment.

Unit SCO informed.

SAT/UNSAT TERMINATING CUE: When the Nitrogen Backup System has been placed back into normal alignment this JPM is complete.

Comments required for any step evaluated as UNSAT.

Time completed: ___________

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Restore Nitrogen Backup System after an Isolation RELATED TASKS:

278203B101, Restore the Backup Nitrogen System following an Auto Initiation Per OP-46.

K/A REFERENCE AND IMPORTANCE RATING:

223002 A4.03 3.6/3.5 Ability to manually operate and/or monitor in the control room: Reset system isolations.

REFERENCES:

OP-46, Section 8.10 Op-18, Section 7.

TOOLS AND EQUIPMENT:

None.

SAFETY FUNCTION (from NUREG 1123, Rev 2.):

5 - Containment Integrity REASON FOR REVISION:

New JPM.

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Restore Nitrogen Backup System after an Isolation Validation Time: 7 Minutes (approximate).

APPLICABLE METHOD OF TESTING Performance: Simulate Actual Unit: 2 Setting: Control Room Simulator ( Not applicable to In-Plant JPMs )

Time Critical: Yes No Time Limit N/A Alternate Path: Yes No EVALUATION Trainee:

JPM: Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure Revision?: Yes No (Each Student should verify one JPM per evaluation set.)

Comments Comments reviewed with Student Evaluator Signature: Date:

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TASK CONDITIONS:

1. Core Spray instrumentation was bumped causing an inadvertent initiation signal.
2. Auto actions have been verified.
3. Core Spray has been shutdown IAW 2OP-18.
4. Prerequisites of 0OP-46 are all met.

INITIATING CUE:

You are directed to Restore the Nitrogen Backup System in accordance with 0OP-46.

Inform the Unit SCO when the Nitrogen Backup System is restored to normal.

8.10 Restoring the Nitrogen Backup System After A Core Spray/LOCA C Continuous Logic Auto Initiation Use 8.10.1 Initial Conditions

1. All applicable prerequisites as listed in Section 4.0 are met.
2. DIV I BACKUP N2 RACK ISOL VLV, SV-5482 OR DIV II BACKUP N2 RACK ISOL, SV-5481, is open due to Core Spray/LOCA Logic actuation.
3. DIV I NON-INTRPT RNA, SV-5262 OR DIV II NON-INRPT RNA, SV-5261, is closed due to Core Spray/LOCA Logic actuation.

8.10.2 Procedural Steps

1. ENSURE the Core Spray/LOCA Logic has been reset.
2. OBSERVE INSTRUMENT AIR HEADER PRESSURE, IA-PI-724-1, is greater than 98 psig.
3. OBSERVE the following annunciators are clear:
a. RB INSTR AIR RECEIVER 1A(2A) PRESS LOW (UA-01 1-1).
b. RB INSTR AIR RECEIVER 1B(2B) PRESS LOW (UA-01 1-2)
4. MOMENTARILY PLACE DIV I NON-INTRPT RNA, RNA-SV-5262 control switch to OVERRIDE/RESET position, THEN to the OPEN position.
a. ENSURE DIV I NON-INTRPT RNA, RNA-SV-5262 is open.
b. ENSURE DIV I BACKUP N2 RACK ISOL VLV, RNA-SV-5482 is closed.

0OP-46 Rev. 143 Page 65 of 290

8.10.2 Procedural Steps

5. MOMENTARILY PLACE DIV II NON-INTRPT RNA, RNA-SV-5261 control switch to OVERRIDE/RESET position, THEN to the OPEN position.
a. ENSURE DIV II NON-INTRPT RNA, RNA-SV-5261 is open.
b. ENSURE DIV II BACKUP N2 RACK ISOL VLV, RNA-SV-5481 is closed.
6. COMPLETE Attachment 11.

0OP-46 Rev. 143 Page 66 of 290