Text

Initial Exam 2012-302 Final Sim IN-Plant JPMs
	ML13275A055
Person / Time
Site:	Sequoyah
Issue date:	09/27/2013
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
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Sequoyah Initial Exam 302 December 2012 Final Material

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMG

ROISRO JOB PERFORMANCE MEASURE Task: Restore Offsite Power to the Shutdown Board From Offsite Power Task#: 3110510501 Task Standard: Examinee transfers the 1A 6.9 Ky Shutdown Board from diesel power to offsite power while maintaining power to the board.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA Reference!Ratings: 056 AAI .04 (3.2/3.1)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettoIC325.

3. If IC 325 is not available perform the following.

4. ResettolC7

Insert malfunction EDO7B (loss of 1 B Unit Board)

Delete malfunction EDO7B.

IRE EDRI 0 to reset the differential lockout.

Use EDR68 to close breaker 1714.

IRF EGR 11 to test

IRF EGR 11 to normal

lRFEGl2totest

IRE EGR 12 to normal

IRF EGRO7 to reset

5. An extra operator will be required to acknowledge alarms.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR.

8. Provide an in-progress copy of EA-202-1, Restoring Offsite Power to 6900V Shutdown Boards.

9. Save as a temporary IC, if repeat runs of JPM will be desired.

10. PLACE SIMULATOR IN RUN

11. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

ToolslEquipmentlProcedures Needed:

References:

Reference Title Rev No.

1. EA-202- 1 Restoring Offsite Power to 6900V Shutdown Boards 13 2.

DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job perform ance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicat e that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. The differential relay on 1 B Unit Board was inadvertently actuated and has been reset.

3. The IA-A 6900V Shutdown Board has been energized by the 1A EDG.

4. EA-202-1, Restoring Offsite Power to 6.9 kV Shutdown Boards Section 4.13 is in progre ss, completed through step 7.

INITIATING CUES:

1. Transfer lA-A 6.9 KV Shutdown Board to offsite power from the normal power supply (lB-B Unit Board) using EA-202-1, Restoring Offsite Power to 6.9 kV Shutdown Boards Sectio n 4.13 starting at step 8.

2. An AUO has been briefed and is standing by to perform local operations.

3. Inform the SRO when complete.

Start Time STEP 1

. Obtain a copy of EA-202-1, Restoring Offsite Power to 6900V Shutdown Boards Section 4.13.

SAT UNSAT Standard: Examinee obtains a copy of EA-202-1, Restoring Offsite Power to 6900V Shutdown Boards Section 4.13.

CU Provide an in progress copy of EA-202-1, Restoring Offsite Power to 6900V Shutdown Boards Section 4.13.

Comment

STEP 4 :

10. ADJUST [0-HS-82-131 DO lA-A Speed Control swftch SAT UNTIL [0-XI-82-11 Synchroscope DG lA-A is rotating slowly in the FAST direction. LI UNSAT Examinee adjusts O-HS-82-13 DG lA-A Speed Control Switch such Standard: that synchroscope (Xl-82-1) is moving slowly in the fast direction (slowly clockwise).

Comment STEP 5 : SAT 11 ENSURE [0-HS-82-12] OG IA-A Voltage Regulator 1nPULLPAUTO. LI UNSAT Standar& Examinee verifies [O-HS-82-12] DG lA-A Voltage Regulator in PULL P AUTO.

Comment STEP 6 :

12. ADJUST DG IA-A VOLTAGE REGULATOR switch to match SAT fO-EI.82-5] DG lA-A Running Voltage and [0-El.82-41 DO IA-A Incoming Voltage. LI UNSAT Examinee adjusts DG lA-A VOLTAGE REGULATOR switch to match Standard: O-El-82-5 DG IA-A Running Voltage and O-El-82-4 DG IA-A Incoming Voltage.

Comment

CAUTiON Dropping load too quickly OR failing to open DIG breaker promptly when DIG is unloaded may result in a reverse power condition.

NOTE Breaker 1718 switch should be operated so that breaker closes at 12 oclock position, considering speed of rotation of synchroscope needle and delay time for breaker closure.

STEP 7 13. WHEN the synchroscope needle approaches 12 Oclock position, SAT THEN CLOSE (jjj] 6.9kV Unit fld lB to SD Sd IA-A NOR supply USING tl-HS.57-44B1 [O-M-26A]. UNSAT

. .:su.yCLOSES.

Comment STEP 8 : SAT

14. ADJUST [0-HS-82-131 DG IA-A Speed Control switch UNTIL [0.EI.82-IOAI DG lA-A Megawatts indicates 500kW (0.5MW> or less. UNSAT Standard Examinee places O-HS-82-13 DG IA-A Speed Control switch CCW until DG lA-A MW loading is between 500KW and 0KW.

Corn ment

STEP 9

15. ADJUST [O-HS-82-121 DG 1AA Voltage Regulator UNTIL fO-EI-82-IIAI OG lA-A Megavars indicates near zero.

LI Standard Examinee places 0-HS-82-13 DG lA-A Speed Control switch CCW until DC lA-A MW loading is near 0KW.

Comment STEP 10 : SAT

17. PLACE [j_-HS-57-45j 6.9kV Unit Bd lB Synchronize switch to OFF position. El UNSAT Standard: Examinee places 6.9kV Unit Bd lB Synchronize switch to OFF.

Corn ment:

Cue Provide the following cue, Another operator will complete the

. remaining steps of this procedure.

Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. The differential relay on 1 B Unit Board was inadvertently actuated and has been reset.

3. The lA-A 6900V Shutdown Board has been energized by the 1A EDG.

4. EA-202-1, Restoring Offsite Power to 6.9 kV Shutdown Boards Section 4.13 is in progress, completed through step 7.

INITIATING CUES:

1. Transfer lA-A 6.9 KV Shutdown Board to offsite power from the normal power supply (1 B-B Unit Board) using EA-202-1, Restoring Offsite Power to 6.9 kV Shutdown Boards Section 4.13 starting at step 8.

2. An AUO has been briefed and is standing by to perform local operations.

3. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMA

SIM JPM A Page 2 of 11 ROISRO JOB PERFORMANCE MEASURE Task: Initiate Emergency Boration During an ATWS Task#: 0000290501 Task Standard: Examinee initiates an emergency boration of at least 35 gpm to the RCS using the normal boration flowpath using EA-68-4 section 4.2.

Alternate Path: YES: X NO:

Time Critical Task: YES: NO: X KIA ReferencelRatings: EPE 029 EA 1.02 (3.613.3)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 8 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM A Page 3 of 11 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettolCl6

IMFRPO1Cf:1

IMFRDO8f:1

IMF CVCOHS62138A f:3 (CLOSE FAIL)

3. PLACE SIMULATOR IN RUN

4. Manually trip a RCP.

5. An extra operator will be required to acknowledge alarms.

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR.

8. Save as a temporary IC, if repeat runs of JPM will be desired.

9. PLACE SIMULATOR IN RUN

10. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

ToolslEquipmentlProcedures Needed:

References:

L 1.

Reference EA-68-4 Title Rev No.

H 2.

Emergency Boration 11

SIM JPM A Page 4 of 11 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 1.

2. An ATWS is in progress.

3. Boric Acid Tank (BAT) A is in service.

INITIATING CUES:

1. The SRO has directed you to initiate emergency boration from the A BAT using EA-68-4 Emergency Boration section 4.2

2. Inform the SRO when complete.

SIM JPM A Page 5 of 11 Start Time STEP 1 : SAT Obtain a copy of EA-68-4, EMERGENCY BORATION.

UNSAT Standard: Examinee obtains a copy of EA-68-.4, EMERGENCY BORATION.

Corn rnent STEP 2 SAT

1. ENSURE boric acid transfer pump aligned to the blender is running in fast speed. UNSAT Examiner The examinee must perform either JPM step 2 or 3, performing both 2 Note and 3 is allowed.

Comment

SIM JPM A Page 6 of 11 STEP 3 : SAT

1. ENSURE boric acid transfer pump aligned to the blender is running in fast speed. UNSAT Exam inee places HS-62-232A to BA Transfer Pump 1 B to STOP CRITICAL AND Standard: HS-62-232D BA Transfer Pump 1 B Speed Select to FAST CRITICAL AND HS-62-232A to BA Transfer Pump 1 B to START. CRITICAL STEP 4 : SAT

2. ADJUST emergency borate valve [FCV-62-1381 to obtain boric acid flow between 35 gpm and 150 gpm on [Fl-62-137A]. UNSAT Standard: Examinee attempts to open emergency borate valve FCV-62-138.

Examiner Note The examinee may not perform this step..

Comment

SIM JPM A Page 7 of 11 STEP 3. MONITOR emergency boration flow:

5 SAT

a. CHECK emergency boration flow established UNSAT on [FI-62-137A].

Standard: Examinee recognizes emergency boration flow NOT established.

Comment ALTERNATE PATH STEP 6 : SAT

3. MONITOR emergency boration flow:

UN SAT

b. IF boric acid flow less than 35 gpm, THEN CLOSE recirculation valve for the BAT aligned to the blender:

. 1FCV62-237 for BAT A.

Standard: Examinee places HIC 62-237 BAT RECIRC to CLOSE (fully CW)

Comment

SIM JPM A Page 8 of 11 STEP 7 : 4. IF emergency boration flow NOT established, SAT THEN ALIGN normal boration path: UNSAT

a. VERIFY VCT outlet valves LCV-62-1 32 and LCV-62-1 33 OPEN.

Standard Examinee verifies [LCV-62-1 321 and [LCV-62-1 33] OPEN by observing red lights above HS 62-132A and HS 62-133A ON.

Comment STEP 8 : 4. IF emergency boration flow NOT established, SAT THEN ALIGN normal boration path:

UNSAT

b. ALIGN normal boration to VCT outlet:

. OPEN FCV-62-140.

Standard: Examinee observes red lights above HS-62-140D ON.

Comment STEP 9 : 4. IF emergency boration flow NOT established, SAT THEN ALIGN normal boration path:

UNSAT

b. ALIGN normal boration to VCT outlet:

. OPEN FCV-62144.

Comment

SIM JPM A Page 9 of 11 STEP 10 : 4. IF emergency boration flow NOT established, SAT THEN ALIGN normal boration path:

UNSAT

c. CHECK boration flow greater than 35 gpm on Fl-62-139.

Standard: Examinee observes boration flow on Fl-62-139 greater than 35 gpm.

Comment STEP 11 : 5. IF boration flow greater than 35 gpm is NOT established. SAT THEN PERFORM one of the following: UNSAT Standard: Examinee addresses the step as N/A.

Comment STEP 12 : SAT

6. VERIFY charging flow established.

UNSAT Standard Examinee verifies Charging Flow by observing installed plant instrumentation.

Comment

SIM JPM A Page lOof 11 CAUTION Boration flowrate greater than charging flow (minus seal return STEP 13 : flow> will result in overfilling VCT. SAT

7. MAINTAIN boric acid flow between 35 gpm and 150 gpm.

UNSAT Standard: Examinee observes boration flow on Fl-62-1 39 greater than 35 gpm.

Comment STEP 14 : SAT

8. MONITOR BAT level.

UNSAT Standard: Exam inee monitors A BAT level by observing LI-62-238.

Comment STEP 15 : 9. IF FR-SI (ATWS) or FR-S.2 (Loss of Core Shutdown) condition exists, SAT THEN RETURN TO procedure and step in effect. UNSAT Standard: Examinee addresses the procedure step.

Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue: STOP the Examiner.

Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. UnitlisinMODEl.

2. An ATWS is in progress.

3. Boric Acid Tank (BAT) A is in service.

INITIATING CUES:

1. The SRO has directed you to initiate emergency boration from the A BAT using EA-68-4 Emergency Boration section 4.2

2. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMB

SIM JPM B Page 2 of 10 RO/SRO JOB PERFORMANCE MEASURE Task: Place excess letdown in service to the VCT /RCDT Task#: 0040160101 Task Standard: Excess letdown is removed from service using 1 -SO-62-6, Excess Letdown, section 7.0 Alternate Path: YES: NO: X Time Critical Task: YES: NO: X K1A ReferencelRatings: 004 A4.06 (3.6/3.1)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 7 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM B Page 3 of 10 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettolC-316.

3. If IC 316 is not available perform the following:

a) Resetto IC 16 b) Place Excess Letdown in service.

4. Place a Pink Tag on 1-HIC-62-93, which is in manual.

5. An extra operator will be required to acknowledge alarms.

6. PLACE SIMULATOR IN RUN

7. ACKNOWLEDGE ALARMS

8. FREEZE SIMULATOR.

9. Provide an in-progress copy of 1 -SO-62-6, Excess Letdown

10. Save as a temporary IC, if repeat runs of JPM will be desired.

11. PLACE SIMULATOR IN RUN

12. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.

2. Any UNSAT requires comments.

ToolslEquipment!Procedures Needed:

I -SO-62-6, Excess Letdown

References:

Reference Title Rev No.

1. 1-SO-62-6 Excess Letdown 18

2. 1-AR-M5-B Annunciator Response

SIM JPM B Page 4 of 10 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 in MODEl.

2. Excess letdown is in service.

3. Normal Letdown has been restored to service.

4. l-HIC-62-93 is in manual, per section 5.0 of l-SO-62-6, Excess Letdown.

5. 1-SO-62-6, Sections 4.0, 5.0 and 7.0 Step I are complete.

INITIATING CUES:

1. You have been directed to remove excess letdown from service using l-S0-62-6, Excess Letdown Section 7.0, starting at step 2.

2. Inform the SRO when complete.

SIM JPM B Page 5 of 10 Start Time STEP Obtain a copy of 1 -SO-62-6, Excess Letdown 1 : SAT UNSAT Standard: Operator obtains a copy of 1-SO-62-6, Excess Letdown Provide a marked up copy of 1 -SO-62-6, Excess Letdown Comment STEP 2 : [2] CLOSE [1 -FC V.62-56] Excess Letdown Heat Exchanger SAT outlet valve.

UNSAT Standard Operator turns the potentiometer HIC-62-56A in the clockwise direction until the pointer (needle) is in the CLOSE or ZERO position. CRITICAL Examiner Operator may verify a decrease in temperature on Tl-62-58 and Note pressure decrease on P1-62-57. (NOT CRITICAL)

Corn ment

. [3j VERIFY [I-FCV-62-59] Excess Letdown 3-way valve STEP 3 SAT

. NORMAL UNSAT Standard Operator observes the left red light above Excess Letdown 3-way valve HS-62-54A is ON.

Comment

SIM JPM B Page 6 of 10 STEP 4 41 CLOSE tjFCV-62-551 Excess Letdown containment isolation valve. SAT U N SAT Corn ment STEP 5 : [5J CLOSE Y1-FCV-62-541 Cold Leg Loop #3 Excess Letdown SAT vah,e.

UNSAT Standard Operator places COLD LEG Loop #3 Excess Letdown valve HS62-54A to CLOSE.

Examiner This step becomes critical if Excess Letdown Heat Exchanger Note: outlet valve HS-62-55A is NOT closed.

Corn rnent STEP 6 : [6] iF charging is in service, THEN SAT ADJUST seal injection flow to 6-li gpm using [1-FCV-629i UNSAT Operator turns potentiometer CCW to close (demand moves to the Standard: right toward 100% or CLOSE) to reduce seal injection flow to between 6and 11 gpm.

Examiner . .

If no adjustment is needed operator may leave seal injection flow as is.

. .

Note Comment

SIM JPM B Page 7 of 10

[11 IFinmodes 1,2,or3,THEN STEP 7 : ENSURE total seal injection flow greater than or equal to SAT 28 gprn.

UNSAT Standard Operator observes total seal injection flow greater than or equal to 28 gpm by installed instrumentation.

Comment STEP 8 [8] IF auto operation is desired and system conditions will allow it,

. THEN SAT PLACE [1-FCV-62-93] in AUTO UNSAT Standard: Operator places HIC-62-93A to AUTO.

Prior to placing charging in automatic, the Operator should adjust Pressurizer level, by taking the lever to the right to decrease charging Examiner flow (or to the left to increase charging flow) as needed to match Pzr Note Level and Program Level. When program level and actual level are matched, the Auto/Manual Toggle should be placed in the Auto (Down) position.

Comment STEP 9 (9] NOTIFY Radiation Protection that Excess Letdown is SAT

. REMOVED from SERVICE.

UNSAT Standard: Operator addresses the procedure step.

Q1 If asked acknowledge the notification.

Comment

SIM JPM B Page 8 of 10 STEP 10 [10] ENSURE F1-FCV-70-851 Excess Letdown HX CCS Flow Control Valve is CLOSED SAT UNSAT Examiner Operator should address the need to have a CV (Concurrent Verifier)

Note present prior to operating the valve.

Comment

SIM JPM B Page 9 of 10 STEP 1121 INDEPENDENTLY VERIFY [1-FCV-62-561 Excess Letdown 12 SAT Heat Exchanger outlet valve CLOSED.

UNSAT

[131 INDEPENDENTLY VERIFY (1 -FCV-62-59] Excess Letdown 3-way valve in NORMAL.

[141 INDEPENDENTLY VERIFY 11 -FCV-62-55] Excess Letdown containment isolation valve CLOSED.

[151 INDEPENDENTLY VERIFY [1-FCV-62-54] Cold Lag Loop #3 Excess Letdown valve CLOSED.

[161 IF operation at greater than 200 °F has occurred. THEN CONTACT Systems Engineering to evaluate Grinnell valve maintenance requirements.

Standard: Operator addresses the procedure steps.

Cue If asked, acknowledge the request for IV and provide the following cue, All IVS have been completed.

Cue If asked, provide the following cue, Temperature never exceeded 200°F.

Comment Terminating The task is complete when the Operator returns the cue sheet to ue: the examiner Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit I in MODEl.

2. Excess letdown is in service.

3. Normal Letdown has been restored to service.

4. 1-HIC-62-93 is in manual, per section 5.0 of 1-SO-62-6, Excess Letdown.

5. 1-SO-62-6, Sections 4.0, 5.0 and 7.0 Step 1 are complete.

INITIATING CUES:

1. You have been directed to remove excess letdown from service using 1-SO-62-6, Excess Letdown Section 7.0, starting at step 2.

2. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SQN EXCESS LETDOWN 1-80-62-6 Unit I Rev. 0018 Page II ofl5 Date______

7.0 SHUTDOWN IF letdown is to be placed in service, THEN RETURN to service per 1-SO-62-1.

[2] CLOSE [1-FCV-62-56] Excess Letdown Heat Exchanger outlet valve.

[3] VERiFY [1 -FCV-62-59] Excess Letdown 3-way valve in NORMAL.

t41 CLOSE [1 -FCV-62-65] Excess Letdown containment isolation valve.

[5] CLOSE [1 -FCV-62-541 Cold Leg Loop #3 Excess Letdown valve.

[6] IF charging is in service, THEN ADJUST seal injection flow to 6-11 gpm using t1-FCV-62-89].

[7] IF in modes 1,2, or 3, THEN ENSURE total seal injection flow greater than or equal to 28 gpm.

[8] IF auto operation is desired and system conditions will allow it, THEN PLACE [1-FCV-62-93] in AUTO.

[9] NOTIFY Radiation Protection that Excess Letdown is REMOVED from SERVICE.

[101 ENSURE [1 -FCV-70-851 Excess Letdown HX CCS Flow Control Valve is CLOSED.

I St CV

[11] ENSURE Ii-HS-70-85A1 is in the A-AUTO position.

I St Cv

____

_

SON EXCESS LETDOWN Unit I 1-SO-62-6 Rev. 0018 Page 12 of 15 Date 7.0 SHUTDOWN (continued)

[12] INDEPENDENTLY VERIFY [1 .FCV-62-561 Excess Letd own Heat Exchanger outlet valve CLOSED.

Iv

[13] INDEPENDENTLY VERIFY [1 -FCV-62-591 Excess Letd own 3-way valve in NORMAL.

IV

[14] INDEPENDENTLY VERIFY 11-FCV-62-551 Excess Letdown containment isolation valve CLOSED.

IV

[15] INDEPENDENTLY VERIFY i1-FCV-624] Cold Leg Loop

3 Excess Letdown valve CLOSED.

IV

[16] IF operation at greater than 200 °F has occurred, THEN CONTACT Systems Engineering to evaluate Grinnell valve maintenance requirements.

End of Section

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMC

SIM JPM C Page 2 of 16 ROISRO JOB PERFORMANCE MEASURE Task: Transfer to Hot Leg Recirculation Task#: 0000790501 Task Standard: Successful alignment of ONE train of RHR and B Train Safety Injection to the hot leg recirculation flow path.

Alternate Path: YES: X NO:

Time Critical Task: YES: NO: X KIA ReferencelRatings: EPE 011 EA1.11 (4.2/4.2)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 18 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM C Page 3 of 16 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettoIC3il

3. If IC 311 is not available, perform the following.

4. ResettolC24 a) Place operating power on FCV-63-1 (remote function IRF RHRI4 f:O) b) after automatic containment sump swapover is initiated, perform required alignment of ECCS to Containment Sump per ES-i .3.

c) Place the #3 HDP HS in PTL.

5. If IC 24 is not available then reset to IC 16 and complete the following setup:

a) Insert IMF THO1A f:10 (10% LOCA on Loop #1 Hot Leg), and Trip RCPs.

-

b) Place operating power on FCV-63-i (remote function IRF RHR14 f:1) c) after automatic containment sump swapover is initiated, perform required alignment of ECCS to Containment Sump per ES-i .3.

d) Place operating power on FCV-63-22 (remote function IRF SIRO6 f:O).

6. To keep out nuisance alarms: insert overrides on following alarms

IMF AN_OV_304 f:3 (Containment Moisture High)

IMF AN_OV_420 f:3 (Saturation Monitor)

IMF AN_OV_96 f:3 (Turbine Zero Speed)

7. PLACE SIMULATOR IN RUN

8. An extra operator will be required to acknowledge alarms.

9. ACKNOWLEDGE ALARMS

10. FREEZE SIMULATOR.

ii. Save as a temporary IC, if repeat runs of JPM will be desired.

12. PLACE SIMULATOR IN RUN

13. When directed insert malfunction SIOIAf:1, trip 1A SI pump.

14. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

SIM JPM C Page 4 of 16 ToolslEquipmentlProcedures Needed:

References:

Reference H. TES-t4 Title Transfer to Hot Leg Recirculation Rev No 6

SIMJPMC Page 5 of 16 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand yoUr assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE 5 following an event that occurred 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago.

2. All ECCS components and Containment Spray pumps are aligned and taking suction from Containment sump using ES-i .3.

3. RCS pressure is less than 180 psig.

4. Both RHR pumps are in service.

INITIATING CUES:

i. The SRO has directed you to transfer to Hot Leg Recirculation using ES-i .4, Transfer to Hot Leg Recirculation, starting at step 1.

2. Inform the SRO when complete.

SIM JPM C Page 6 of 16 Start Time STEP Obtain a copy of ES-i .4, Transfer to Hot Leg Recirculation.

1 : SAT UNSAT Standard: Operator obtains a copy of ES-i .4, Transfer to Hot Leg Recirculation.

ci Provide a copy of ES-i .4, Transfer to Hot Leg Recirculation.

Comment STEP 2 : 1. DETERMINE it RHR should be isolated:

SAT

a. CHECK RHR spray IN SERVICE:

UNSAT

a. SO TO Step 2

Train A RHR spray valve FCV-72-40 OPEN OR

Train B RHR spray valve FCV-72-41 OPEN.

Standard: Operator verifies FCV-72-40 and 41 are closed and goes to step 2 Cam ment STEP 3 : Z CHECK RfR pump A-A RUNNING. SAT UNSAT Standard Operator observes A train RHR running by RED lights above HS IOAON Cam ment

SIM JPM C Page 7 of 16 STEP 4 : 3. ALIGN RHR Train A for hot leg SAT recirculation:

U NSAT

a. CLOSE RHR Train A cold leg isolation valve FCV-63-93.

Standard Operator places RHR Train A cold leg isolation valve HS-63-93A to CLOSE CRITICAL Comment STEP 5 3. ALIGN RHR Train A for hot leg SAT recirculation:

UNSAT

b. ENSURE RHR Train B discharge crosstie valve FCV-74-35 CLOSED Standard Operator observes green lights above RHR Train B discharge crosstie valve FCV-74-35 ON.

Corn ment STEP 6 : 3. ALIGN RHR Train A for hot leg SAT recirculation:

U N SAT

c. OPEN RHR Train A discharge crosstie valve FCV-74-33 Comment

SIM JPM C Page 8 of 16 STEP 7 3. AUGN RHR Train A for hot leg SAT recirculation:

UNSAT

d. OPEN RHR hot leg injection valve FCV 172.

Operator places RHR hot leg injection valve HS-63-172A to OPEN. CRITICAL STEP 8 VERIFY RHR hot leg injection flow SAT

.

on Fi-63-173.

UNSAT Standard: Operator observes RHR HL flow established as indicated on control room indicator [Fl-63-1 73].

Examiner Note No minimum flow specified Corn ment STEP 9 5. ENSURE RHR Train B cold leg isolation SAT valve FCV-63-94 CLOSED.

UNSAT

SIM JPM C Page 9 of 16 STEP 10 : 6. GO TO Step ii SAT

.

UNSAT Standard: Operator transitions to step 11.

Comment STEP 11 : 11 CHECK SI pump A-A RUNNING.

SAT UNSAT Operator observes SI Pump A-A running as indicated by red indicating Standard: light above HS-63-1OA ON.

Comment STEP 12 : 12. ALIGN SI pump A-A for hot leg SAT recirculation

a. ENSURE SI pump A-A STOPPED UNSAT Standard: Operator places SI pump A-A HS-63-1OA STOP.

Examiner Direct booth operator to insert the malfunction to trip the IA SI pump after Note: the pump has been stopped.

Comment

SIM JPM C Page 10 of 16 Comment STEP 14 : 12. ALIGN SI pump A-A for hot leg SAT recirculation:

UNSAT c WHEN FCV-63-1 52 closed

,

1 THEN PERFORM the following:

1) OPEN SI Train A hot leg injection FCV-63-1 56.

Comment

SIM JPM C Page 11 of 16 STEP 15 12. ALIGN SI pump A-A for hot leg SAT recirculation:

UN SAT c WHEN FCV-63-1 52 dosed THEN PERFORM the following:

2) SIART Sl pump A-A.

Standard: Operator attempts to start SI pump A-A and transitions to the RNO Acknowledge direction to locally inspect the IA SI pump.

Comment ALTERNATE PATH STEP 16 : SAT IF SI pump A-A CANNOT be aligned for hot leg recirc, UNSAT THEN PERFORM the following:

1) ENSURE SI pump A-A STOPPED Standard Examinee verifies 1A SI pump is stopped by observing HS-63-1OA in PTL.

Comment

SIM JPM C Page 12 of 16 STEP 17 : SrnP1rOT be aligned SAT THEN PERFORM the following: UNSAT

2) ENSURE Si Train A hot leg injection FCV-63-156 CLOSED Standar& Examinee places SI Pump IA hot leg injection to Loop 1 & 3 HS 156 to CLOSE. CRITICAL Comment STEP IF Si pump A-A CANNOT be iigned 18 SAT for hot leg recirc, THEN PERFORM the following: UNSAT

3) ENSURE SI Train A crosslie FCV-63-152 OPEN Comment STEP IF SI pump A-A CANNOT be aligned 19 : SAT for hot leg recwc, THEN PERFORM the following: UNSAT

4) START S[ pump A-A.

Standard: Examinee recognizes 1A SI pump has tripped and proceeds to the next step.

Comment

SIM JPM C Page 13 of 16 IF SI pump A-A CANNOT be aligned STEP 20 SAT for hot leg recirc, THEN PERFORM the fbllowing: U NSAT

5) IF any of the following conditions met:

SI pump B-B RUNNING OR

SI pump B-B is stopped AND is available for hot leg recirc THEN GO TO Step 1 5 Standard: Examinee transitions to procedure step 15 Comment STEP 21 : 15. ALIGN SI pump B-B for hot leg SAT recirculation:

UNSAT a STOP SI pump B-B Comment 15 ALIGN SI pump B-B for hot leg SAT recirculation:

b. CLOSE SI Train B crosstie U NSAT FCV-63-1 53.

Standard: Operator places SI Train B crosstie HS-63-1 53A to CLOSE. CRITICAL

SIM JPM C Page 14 of 16 STEP 23 15 ALIGN SI pump B-B for hot leg SAT recirculation:

UNSAT c WHEN FCV-63-1 53 closed, THEN PERFORM the following:

1) OPEN SI Train B hot leg injection FCV-63-1 5L Comment STEP 24 I5 ALIGN SI pump 8-B for hot leg SAT recirculation:

U N SAT c WHEN FCV-63-i 53 closed1 THEN PERFORM the following:

2) START SI pump BB.

Cue: If asked provide the following cue, The I B SI pump is ready for start.

Comment

SIM JPM C Page 15 of 16 STEP 25 16. VERIFY SI Train B discharge flow SAT on FI-632O.

U N SAT Standard Operator observes SI Train B discharge flow on control room indicator

[Fl-63-20}.

Comment No minimum flow specified Terminating Provide the following cue, Another operator will complete the Cue: remaining steps of this procedure. STOP Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

I. Unit I is in MODE 5 following an event that occurred 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago.

2. All ECCS components and Containment Spray pumps are aligned and taking suction from Containment sump using ES-I .3.

3. RCS pressure is less than 180 psig.

4. Both RHR pumps are in service.

INITIATING CUES:

1. The SRO has directed you to transfer to Hot Leg Recirculation using ES-i .4, Transfer to Hot Leg Recirculation, starting at step 1.

2. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMD

SIM JPM D Page 2 of 13 ROISRO JOB PERFORMANCE MEASURE Task: Respond to loss of RHR Task#: - 050030101 Task Standard: Examinee restores RHR flow using the B Train RHR pump.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA ReferencelRatings: APE 025 AK1.01 (3.9/4.3)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 14 Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM D Page 3 of 13 SPECIAL INSTRUCTIONS:

1 Ensure Simulator Operator Checklist is complete

2. ResettoIC32Q.

3. If IC 320 is not available perform the following:

a) ResettolC20 b) Complete all steps in 0-SO-74-1, RESIDUAL HEAT REMOVAL SYSTEM to place A Train RHR in service C) IRFRHR14f:

d) IRE RHR1Of:1 e) IMF RHCOHS7412Af:1 f) IRFRHRO3f:100 g) IRF RHRO6f:100

4. An extra operator will be required to acknowledge alarms.

5. PLACE SIMULATOR IN RUN

6. ACKNOWLEDGE ALARMS

7. FREEZE SIMULATOR.

8. Save as a temporary IC, if repeat runs of JPM will be desired.

9. PLACE SIMULATOR IN RUN

10. When directed insert malfunction RHOIAf:1, trip A RHR pump.

11. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

Tools/EquipmentlProcedures Needed:

References:

L 1. Reference Title Rev No.

I AOP-R.03 RHR SYSTEM MALFUNCTION 28

SIM JPM D Page 4 of 13 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 is in MODE4

2. A Train RHR Pump is in service.

3. The SRO is evaluating plant conditions to determine if the B Train of RHR is to be placed in service.

INITIATING CUES:

1. You are the OATC.

2. Respond to plant conditions.

SIM JPM D Page 5 of 13 Start Time MOTOR TRIPOIJT PNL iM-1 THRU 1-M-$

t21 DETERMINE compone,ttht tnpped. A STEP 1

PLACE handswiich n PULL-TO-LOCK posion. SAT U N SAT Standard: Examinee places HS-74 1OA in P-T-L.

Exarrnner Direct booth operator to insert the malfunction to trip the 1A RHR pump Examner Examinee transitions to AOP-R.03, RHR SYSTEM MALFUNCTION.

Comment NOTE: If this procedure is entered from AOP-R05 or AOP-P.06 due to loss of shutdown board(s), then Section Z3 is the applicable section DIAGNOSEthe failure:

STEP 2 : SAT U N SAT Standard: Examinee transitions to section 2.3.

Comment

SIM JPM D Page 6 of 13 STEP . t PLACE affected pump

. PUL[ TO LOCK. SAT U N SAT Standard: Examinee places HS-74 1OA in P-T-L. (if not already performed.)

Comment NOTE Severe cavitation clue to low RCS water level could result in pump trip.

STEP 4 : 2. VERIFY RCS leve greater than 695 6.

SAT UNSAT Standard Examinee addresses the procedure step by observing installed plant instrumentation and from the initiating cue.

Comment STEP 5 : a CHECK NO RHR purr RUNNING. SAT U N SAT Standard Examinee observes red lights above HS-74-1OA and 20A RHR Pump A&BOFF.

Comment

SIM JPM D Page 7 of 13 STEP 6 : INITIATE actions to establish containment closure: SAT UNSAT Standard- Examinee addresses the procedure step as N/A from direction in the initiating cue.

Cue: If asked provide the following cue, Containment is closed.

Comment

5. IF Die] movement is in progress, STOP all fuel movement which would raise core decay heat. UNSAT Standard- Examinee addresses the procedure step as N/A from direction in the initiating cue.

Comment

& ENSURE all RCS dilution activities STEP 8 STOPPED SAT U N SAT Standard: Examinee observes RCS dilution not in progress.

Comment

SIM JPM D Page 8 of 13 STEP 9 :

EVALUATE EPIRI, Enrgency Plan classification Matnx. SAT UNSAT Standard: Examinee addresses the procedure step.

c Provide the following cue, The SM will address EPIP-1.

Corn ment

8. CHECK power available STEP 10 . to RHR pumpto be started: SAT

. &9 Ky Shutdown Board ENERGIZED. UNSAT StandardS Examinee observes Panel M-1 to verify Shutdown Board I B energized.

Comment NOTE FCV-74-16, -28, and -32 fail open on loss of non-essential control air. Later steps provide contingency actions ii valves cannot be controlled from MCR STEP 11 9. ADJUST the following RHR flow controllers to the CLOSE position: SAT

Hlc-62-83, RHR letdown to eves U NSAT

SIM JPM D Page 9 of 13 STEP 12 : ADJUST the following RHR flow controllers to the CLOSE position: SAT

-

a HIC-74-iG, RHR heat exchanger A UNSAT outlet Standard: HX IA Outlet Flow Control fully CRITICAL Comment STEP 13 : 9 ADJUST the following RHR flow controllers to the CLOSE position: SAT a HICJ4.-28, RHR heat exchanger B UNSAT outlet Standard Examinee places HIC-74-28 RHR HX 1 B Outlet Flow Control fully CCW to obtain maximum output.

Comment STEP 14 : 9. ADJUST the rollowing RHR flow controllers to the CLOSE position SAT

-

. HIC-74-32. RHR heat exchanger UNSAT bypass Standard: Examinee verifies HIC-74-32 RHR HX 1A & 1 B Bypass Flow Control fully CCW to obtain maximum output. CRITICAL Comment

SIM JPM D Page 10 of 13

10. DETERMINE if contingency actions are STEP 15 needed to prevent vortexing: SAT

a. CHECK for all of the foowing conditions a GOTOSteplI.

met: UNSAT

RCS in reduced inventory or midloop (level less than 699)

RHR train which will be placed in service does NOT have flow blocking device installed on 1-IX outlet valve (FCV-74-1 6 or 28)

Control of RHR HX outlet FCV has been lost Standard: Exam inee transitions to step 1 1.

Comment

11. ENSURE adequate COS flow on RHR beat STEP 16 : excnaner for RHR pump to be started. SAT U N SAT Standard: Examinee observes CCS flow as indicated on Fl-70-165A.

Comment

12. CHECK RCS NOT n sotid water STEP 17 operations. SAT UNSAT Standard: Examinee addresses the procedure step by observing instaNed plant instrumentation and from the initiating cue.

Comment

SIM JPM D Page 11 of 13 13.. CHECK RHR suction from loop 4 hot leg STEP 18 isoation valves OPEN: SAT

FCV74-1 UNSAT

FCV-74-2 Standard Examinee observes red lights above HS-74-1A and 74-2A RHR Suction From Loop 4 Hot Leg ON.

Comment 14 ENSURE suction valve OPEN STEP 19 : foi RHR pump to be started: SAT

FCV-74-21 (Train Bl UNSAT Standard: Examinee places HS-74-21A RHR Pump lB Suction Isolation to CRITICAL Comment

. 15. CHECK ofisite power supplying STEP 20

. shutdown boards.

UNSAT Standard Examinee observes Panel M-1 to verify offsite power supplying shutdown boards.

Comment

SIM JPM D Page 12 of 13 16.. START selected RHR pump.

STEP 21 SAT U NSAT Cue If asked provide the following cue, lB RHR pump is ready for start Comment Terminating Provide the following cue, Another operator will complete the Cue: remaining steps of this procedure..

Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE4

2. A Train RHR Pump is in service.

3. The SRO is evaluating plant conditions to determine if the B Train of RHR is to be placed in service.

INITIATING CUES:

1. You are the OATC.

2. Respond to plant conditions.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SQN RESIDUAL HEAT REMOVAL Unit 0 SYSTEM O-SO74-1 Rev. 0084 Page 9 of 335 L2 3.0 PRECAUTIONS AND LIMITATIO NS The boron concentration of an RH R train must be verified minim boron concentration required for um RCS shutdown margin before being pla service for shutdown cooling. Th ced in is verification must be made before level is lowered to Mid Loop. [C. the RCS 16]

Failure to observe all posted rad iation control requirements may res unnecessary radiation absorbed ult in doses.

RCS temperature and pressure limits O-SI-SXX-068-127.0, RCS and Pre in TI-28, Figure 4, and requirements in ssurizer Temperature and Pressure applicable), must be observed dur Limits (if ing cooldowa on RHR, Component cooling water must be aligned to RHR heat exchanger starting:an RHR pump and when (Hx) prior to RCS temperature Is greater than 190

°F.

Operating RHR pumps in paralle l (HCV-74-36 and HCV-74-37 OPEN and 74-531 OPEN) and on miniflo ) (74-530 w for> 10 minutes may result in pum damage due to one pump dead-h p eading. [C.2] [C.13]

Except as specified in precaution G, RHR pumps should NOT be operat extended periods without CCS flow ed for on HX or when there is no injection int core. Either condition may lead to o pump damage from overheating.

If necessary to run an RHR pump wit h CCS out of service to the RHR HX and/or mechanical seal HX for outage activities, the following limitations apply:

the core shall be defueled RCS temperature shall be less than 110

°F 49 the affected RHR pump shall NOT be ope minutes.

rated on miniflow for more than 5 Failure to maintain FCV-74-33 and FCV-74-35 (RHR Crosstie Valves) and FCV-63-93 and FCV-63-94 (Cold Leg Inj ection Valves) OPEN and FCV-63-1 72 (Hot Leg Injection Isolation Valve) CLOS ED while applicable unit is in modes 1, 2, or 3 will result in entering LCO 3.0.3. [C.1]

Failure to maintain shutdown cooling flow rat e for an RHR pump at the maximum possible could result in reduced mo tor thrust bearing life. [C.3 3 When fuel is in the Reactor vessel, two RHR pum ps must be operable and either a RCP or RHR pump operating except as allowed by Tech Specs.

SQN RESIDUAL HEAT REMOVAL UnitO SYSTEM 0-SO-74-1 Rev. 0084 Page 10 of 335 3.0 PRECAUTiONS AND LIMITA TIONS (continued) 4 To reduce vibration across FC V RHR must be aligned to only two 1 6 and FCV-74-28 (RHR Hx Outlet Valves),

cold legs with one train in servic e.

RHR Hx CCS outlet temperature

,Y- shalt NOT exceed 145°F due piping and support analyses. to limitations on (Ref: 47W859-4) CCS flow rat through the RHR HX shall be e or RHR flow rate adjusted as necessary to meet thi s limitation.

The following reduced inventory

/mid-loop precautions are applica

/ level is el 699: ble when RCS Procedures and administrative controls that assure Containment shalt be implemented prior to the closure time that core uncovery could res a loss of RHR coupled with the ina ult from bility to initiate alternate cooling addition of water to RCS invent or ory. [C.6]

At least two independent, con

,/ tinuous temperature indications representative of core exit con ditions are required during mid-l reactor vessel head is in place oop when with irradiated fuel in vessel. [C l]

At least two independent, contin uous RCS water level indicatio periodically checked and record ns mu ed or automatically monitored and st be in control room. [C.8] alarmed Operations must be avoided that deliberately or knowingly lead to 7 perturbations to RCS and/or sys tems necessary to maintain RCS stable and controlled condition. If in a such operations must be conducted additional measures shall be tak ,

en to prevent loss of RHR and to en monitoring requirements to ensu hance re a timely response should a loss of occur. [C.9] RHR In addition to RHR. two means of add ing inventory to RCS shall be available or operable. [C..10]

If RHR cooling is lost while performing this Instruction, RCS level may appear to be higher than actual due to RCS pressure changes as a result of boiling in the core.

A failure of FCV-74-16, -28, or -32 to the open position will result in high flow rates which may result in a departure from stable and controlled conditions. [C.12]

It may be necessary to throttle CCS flow to RH R heat exchangers to control RCS temperatures and maintain RC S temperatures greater than 70°F. tC.15]

SQN RESIDUAL HEAT REMOVA Unit 0 L SYSTEM O-SO-74-i

.

Rev. 0084 Pagellof33B 3.0 PRECAUTIONS AND LIMITA TIONS (continued)

If flow rates are reduced below 2000 gpm, piping downstream of 16, FCV-74-28 and FCV-74-32 FCV74-(whichever is providing flow pat service RHR train) must be monit h for in ored for signs of valve cavitation

. [C.14]

The following precautions must be observed during solid water ope ration:

The residual heat removal inlet lines remain in service unless condition from the reactor coolant loop should s

overpressurization of the RHR sys exist that could result in tem.

COPS must be operable when RC closed if both trains of COPS are S 350°F. Letdown orifices may be operable. [C.11]

When plant is solid water with letdow FCV-62-83 should be full open wit n from RHR, letdown control valve h

pressure letdown control valve PC RCS pressure being maintained by low V-62-81.

When RCS pressure is being ma int through the RHR loop due to thr ained by PCV-62-81, flow rate changes ottling valves or starting and sto pumps will result in changes to pping RHR RC caUse letdown controller in auto S pressure. Starting an RFIR pump will to letdown valve to reduce RCS pre sense a higher pressure and reposition ssu will cause letdown controller in aut re 30 psig. Stopping an RHR pump o to sense a lower pressure and reposition letdown valve to raise RCS pressure 100 psig.

Opening FCV-74-1, 2, 3 or 21 wh ile the RCS is solid with RCPs runnin could lead to RCP seal damage g due to the RCS pressure drop. Da may occur during pump coastdow ma ge n even if the RCP is stopped immediately.

RCS temperature shall be maintained greater than 70°F, the minimum operational analysis limit. [CI 5]

RHR heat exchanger outlet and bypass valves leak through, therefore; the RH mini-flow valve may NOT open due to R leakage through FCV-74-16, 28, or 32if a downstream injection path exists. Lo cal flow indicators Fl-74-12 & 24 provide positive indication of pump flow. Minim um required flow to ensure pump protection is greater than 500 gpm.

43 If RHR is aligned to the RCS with RCS >2 00°F and no RCPs running, then a RCP cannot be started unless pressuriz er level is <60%.

if RHR is aligned to the RCS with RCS >300° F and no RCPs running, then a RCP cannot be started regardless of pressu rizer level.

[ SQN Unit 0 RESiDUAL HEAT REMOVA L SYSTEM 0-SO-74-1 Rev. 0084 Page 12 of 335 30 PRECAUTIONS AND LIMITA TIONS (continued)

If RI-IR pressure downstream of pumps exceeds 600 psig shutdown cooling, RHR discha with RHR aligned for rge pressure must be reduced RI-IR isOlated from RCS within below 600 psig or 1 hr.

Engineering must be contacted for time/piping analysis whenever pressure exceeds 600 psig. RHR system If RHR pressure downstream of pum 6, 18 & 22 must be inspected and ps exceeds 600 psig, gauges I (2)-Pi-74-4, recalibrated.

/) On receipt of RHRciischarge pressure hig monitored to ensure the dis h annunciation, RHR must be charge pressure remains below 600 psig.

In order to prevent introducing hot water into the ECCS pump which could cause steam voi suction piping ds, the following valves shall NO on RHR shutdown cooling wit T be opened while h RCS temperature greater tha 34}, [FCV-63-8], [FCV63-1 1], n 200°F: [HCV [FV-63-61, or [FCV-63-7j.[ref.: GL 98-

91 02, item 4j, If RHR cooling is initiated in Mode 4, RHR pumps may not

>1. NPSH during a LOCA. The have adequate following temperature limits (ob calculation SQS2-0*1 55) apply: tained from 238°F is the maximum RCS/R HR temperature at which the RH adequate NPSH when aligned to R pump has the RWST with level at 8%.

213°F is the maximum RCS/RHR temperature at which the RHR pum adequate NPSH when aligned p has to the containment sump with level at To minimize the risk associated wit 11 %.

h a shutdown LOCA, only one RH shall be operated during cooldo R pump wn above 213°F and RHR should be from service during plant heatup removed prior to exceeding 21 3°F.

AOP-R.02, Shutdown LOCA, provid es manual actions for cooling and rea the RHR system to maintain functio ligning nality.

Y. Due to the fact that the containment sum p suction piping is shared between RHR and containment spray, operat ion of RHR above 196°F could impact containment spray pump NPSH if ali gned for sump recirculation during a LOCA To avoid this concern, the running RH .

R pump(s) shall have the miniflow valve open and the idle RHR pump shall hav e its suction valve closed when RHR is in service above 190°F.

SQN RESIDUAL HEAT REMOVA UflitO L SYSTEM 0-SO-74-1 Rev 0084 Page 13 of 335 3.0 PRECAUTIONS AND LIMITA TIONS (continued)

RHR may be placed in service wit boron concentration is greater thanh a CB less than RCS CB provided the RHR required for shutdown margin and the minim um RCS boron concentration prohibited by Tech pos itiv e reactivity changes are NOT Spec action requirements.

7Test Header piping tem perature is limited to 120°F.

RHR must be capable of 4 Loop Cold Leg injection while in Mo de 4.

Care should be taken when per forming venting activities to pre 7 of contamination. vent the spread Changing RHR alignment during fue at all possible. If such operation l handling operations should be avoided if s must be conducted, FHS should prior to altering RHR alignment

. This does NOT preclude equipm be notified in response to an equipment ent operation malfunction or emergency.

Engineering evaluation for air rem oval is required anytime a segme ECCS system is drained. Ultras nt of the air removal or to quantify any voi oni c tes tin g ma y be req uir ed in ord d volume that remains. This evaluaer to validate consider whether or not the exi tion should sting vent valves can completely pockets frQm the piping. If voids rem ove all air will NOT be removed, then the eff system of the remaining void in ect on the concert with other existing voids evaluated. During outages, the should be fill and vent can be verified by the performance of full flow testing. subsequent Ev performed in advance of actual use aluation of procedure sections can be

.

The number of MOV motor starts is limited to 5 within a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period MOV motor must be allowed to coo . The l for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months before subsequent res tarting.

___

__

F SON RESIDUAL HEAT REMOVA L SYSTEM O-SO-74..1 Unit 0

[ Rev. 0084 Page I4of 335 Unit 1 Date 4.0 PREREQUISITE ACTIONS Throughout this instruction wh ere an IFITHEN statement exi condition does NOT exist. sts, the step should be NIA if 4 ENSURE Instruction to be used is a copy of the effective version.

() ENSURE that Precautions and Limitations, Section 3.0, has 7 been reviewed.

IF segment(s) of RHR system wil l be refilled following draining, THEN NOTIFY System Engineering to initIate system void volume evaluation.

IF performing Fill and Vent of the RHR system, i)4 THEN

[4.1] COMPLETE applicable sections of Power Checklist 1 (2)63-5.O1.

[4.2] COMPLETE applicable sections of Valve Checklist I (2)-63-5.02.

[4.3] OBTAIN Door Breaching Permi ts for RHR Valve Vault and 669 Pen Rm, and Confined Space Entry Permit for RHR Valve Vault, if required.

[4.4] GO TO step 4.O[7] (N/A Steps 4.0[5]

& 4.0[6]). C ENSURE Power Checklist I(2)-63-5.O1 has been completed.

ENSURE Valve Checklist 1 (2)-63-5.02 has been completed.

___

__

SQN RESIDUAL HEAT REMOVAL SY Unit 0 STEM 0-SO-74-l Rev. 0084 Page 15 of 335 Un it 1

Date 40 PREREQUISITE ACTiONS (co ntinued)

CØN RHR pump shall NOT be run on miniflow for more than 5 minutes cooling water to RHR HX. with no CCS IF RHR pump will be started in sec tion to be performed, THEN PERFORM one of the following:

VERIFY Component Cooling Water Sy service for applicable unit and train( stem (CCS) in s).

IFRHR pump will be run with CCS flow NOT available to RHR HX and/or mechanical seal HX

,

f-2. THEN VERIFY the following conditions me t:

core is defueled

RCS temperature is less than 110°F

caution order placed to remind operators that CCS is unavailable and caution above.

7 1

I INDICATE below which performance sec L/ tion of this Instruction will be used and the reason for this perfor mance:

STARTUP/STANDBY READINESS D6.O NORMAL OPERATION D7.0 SHUTDOWN D8.0 INFREQUENT OPERATION Reason:

__

SQN RESIDUAL HEAT REMOVAL Unit 0 SYSTEM O-S044-1 Rev. 0084 Page 16 of 335 Unit_______

Date 4.0 PREREQUISITE ACTIONS (co ntinued)

[91 ENSURE each performer docum ents their name and initials:

Print Name Initials

--

End of Section

__

_

SQN RESiDUAL HEAT REMOVA Unit 0 L SYSTEM 0-50-74-1 Rev., 0084 Page 94 of 335 Unit I Date I Placing RHR in Service for No rmal Shutdown Cooling CAUNS RCS temperature and pressure limits in 11-28, Figure 4, and req SI-I 27, RCS and Pressurizer uirements in Temperature and Pressure Lim must be observed. its, (if applicable)

The following cautions apply when placing RHR cooling in service in Mode 4:

If Loop 4 hot leg temp is gre ater than 238 F, RHR pumps NPSH if suction is realigne could have insufficIent d to RWST during a LOCk If Loop 4 hot leg temp is gre ater than 213 F, RHR and Cn could have insufflcient NPSH tmnt Spray pumps if suction is realigned to sump AOP-R.02 provides actions during a LOCk r functionality if a LOCA occu to cool RHR suction piping to en rs.

sure RHR This section is applicable und er either of the following condit ions:

When RI-IR will be placed in service with RCS T-hot less tha n 235 F OR When RHR will be placed in ser vice with RCS T-hot between 235 less than 15 F/hr. -285 F with cooldown rate ENSURE Section 5.5.1 comple ted to prepare for placing RHR in service.

2) IF placing RHR in service with Lo op 4 hot leg temperature greater than 200°F, THEN PERFORM the following:

jgij ENSURE Appendix D, Actions to Pre pare for Placing RHR In Service in Mode 4, COMPLE TED

SQN RESIDUAL HEAT REMOVAL Unit 0 SYSTEM 0-SO-74-1 Rev. 0084 Page 95 of 335 Unit )

Date 5.5.2 Placing RHR in Service for No rmal Shutdown Cooling (continued)

If only one RI-IR pump is operab le, the following substep ensure protected from damage due to s that the operable pump is steam-binding if a LOCA occurs.

ENSURE at least one of following conditions met:

both RHR pumps operable.

[2.2.2] dedicated operator assigned to monitor running RHR pump at M-6 and stop pum p if suction is lost.

If Loop 4 hot leg temp is greate r than 190°F, the idle RHR pum TO LOCK with suction valve p is required to be in PULL closed. This ensures that this RH train Containment Spray pum R pump (and the associated p) will remain isolated from hot wa sump recirc if LOCA occurs. ter and will be available for IF RHR Train A will be placed in ser vice, AND Loop 4 hot leg temperature is greater than 190°F or heatup above 190°F is planned, THEN PERFORM the following:

ENSURE Train B RHR pump placed in PULL TO LOCK. 7f%

I St Cv CLOSE IFCV-74-211, RHR Pump B Sucti on Iso!.

I St Cv

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_

SQN RESIDUAL HEAT REMOVAL SYSTE Unit 0 M 0-SO-74-1 Rev. 0084 Page 97 of 335 Unit______

Date 5.5.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

CØON Opening FCV-74-1 and 2 with the pressurizer solid may cause a large pressure. Do NOT continue this sec drop in RCS tion if the pressurizer is solid with running. RCPs

Ø OPEN the following:

VALVE NO. FUNCTION INITIALS FCV74-1 RHR Pump Suction from Loop 4 Hot Leg FCV-74-2 RHR Pump Suction from Loop 4 Hot Leg FCV-74-1 6 and FCV-74-28 may NO T close without being reset.

ENSURE FCV-74-16 and FCV-74-28 are RESET:

VERIFY St NOT actuated.

TURN IHS-74-1 61281 to the left to reset FCV 74-1 6.

TURN IHS-74-1 61281 to the right to reset FCV 28.

ENSURE the following valves are CLOSED

VALVE NO. FUNCTION INITIALS FCV-74-16 RHR Hx A Outlet FCV-74-28 RHR Hx B Outlet (9-FCV-74-32 RHR Hx Bypass -

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{ SON RESiDUAL HEAT REMOVAL SYSTEM f Unit 0 0-SO-74-l

[ Rev. 0084 Page 98 of 335 Unit I Date 14()-4 5.5.2 Placing RHR in Service for Nor mal Shutdown Cooling (continued)

The following step ensures that RH R systeni pressure (with RHR pum enough to help prevent relief valve ps sto setpoints from being approached whe pped) is tow is started. n the RHR pump

,37 WHILE maintaining RCP operating criteria, ENSURE RHR pump discharge pre ssure is as close to 350 psig as possible (preferably less than 350 psig) on P1-74-13 or P1-74-26. [M-6]

CON When initially placing RHR in ser vice, CS flow should be adjusted adequate flow through the RHR to provide Hx to prevent RHR Hx CCS outlet exceeding 145°F. The RHR Hx temperature from CCS outlet temperature alarm will com e in at 115°F.

N CCS valves in next step may be period icaI1yldjusted as needed to maintain RC temperature. Adjusting these valves S may potentially affect CCS Surge Tank leve Adjusting an RHR Hx CCS valve on one ls.

unit may require the same train valve to on the opposite unit to maintain desire be throttle d CCS pressures and levels on both uni ts.

IF adjustment is required on CCS flow

&K through RHR Hxs, THEN THROTTLE valves as necessary for train bein g placed in service: (NA table for train not adjusted)

TRAIN VALVE NO. FUNCTION INITIALS A 1-FCV-70-156 RHR lix 1A Comp Cooling Water Outlet 2-FCV-70-156 RI-IR lix 2A Comp Cooling Water Outlet B 1-FCV-70-153 RHR Hx 18 Comp Cooling Water Outlet 1L4Z 2-FCV-70-1 53 RHR lix 28 Comp Cooling Water Outlet ti O

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SQN RESIDUAL HEAT REMOVAL SYSTE UnitO M O-SO-74-l Rev. 0084 Page .9 of 335

. *1 Unit_____ __

Date I 4*41 5.5.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

INDEPENDENTLY VERIFY the following valves:

VALVE NO. FUNCTION POSITION INiTIALS FCV-74-1 RHR System Isolation Valve OPEN FCV-74-2 RHR System Isolation Valve OPEN FCV-74-16 RHR Hx A Outlet CLOSED FCV-74-28 RHR Hx B Outlet CLOSED FCV-74-32 RHR Hx Bypass CLOSED CANS If Loop 4 hot leg temperature is gre ater than 213°F, then only one RHR 7 may be placed in service. pump Failure to maintain steady-state RH R flow rate at the maximum possible cou result in reduced motor thrust bearing ld life. [C.3]

Es RHR pump protection is ensured if mini flow valves are open when injection flow is less I than 780 gpm or when greater than 500 gpm indicated on FI-74-12 or -24.

9 If Tra in A RHR is placed in service with Loop 4 hot leg temperature greater than T 190°F, FCV-74-i2 is required to be de-energized in the OPEN position. This ensures that containment sump suction piping temper ature remains below the 196°F limit for containment spray pump NPSH.

7 RHR motor lower bearing oil leve l will rise after pum C sightglass. The presence of .011 02fl be verified by a pgolisden started and may rise above different oils approved) in sightglass. tint or a milk color (two IF RHR Train A is being placed in service, f AND Loop 4 hot leg temperature is greater than 190

°F or heat-up above 190°F is planned, THEN PERFORM the following:

START RHR Pump A-A with IHS-74-IOAI.

ENSURE [FCV-74-121 RHR Pump A-A miniflow OPENS.

SQN RESIDUAL HEAT REMOVAL SYSTE Unit 0 M 0-50-74-i Rev. 0084 Page 100 of 335 Unit 1 Date 5.5.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

DISPATCH operators to de-energize FCV

> with valve in OPEN position: (N/A bre 12 aker for other unit)

UNIT BREAKER LOCATION POSITION 1st CV 1 1-BCTD-74-12-A Rx MOV Bd 1AI-A OFF Compt 7C2 2 2-BCTD-74-12-A Rx MOV Rd 2A1-A Compt7C2 OFF f<ffr. /-

PLACE caution order on handswitch and breaker for FCV-74-1 2 to notify operators of the reas on for breaker in OFF.

j NOTE

[ The following step may be marked N/A if RHR pump A-A was started in Step 5.5.2[10].

pj [11] IF RHR Train A is being placed in serv ice, I AND Loop 4 hot leg temperature is less than 190°F, THEN:

[11.1] START RI-IR Pump A-A with EHS-74-IO AI.

[11.2] VERIFY IFCV-74-121 RHR Pump A-A min iflow OP or greater than 500 gpm is indicated on Fl-74-1 ENS 2.

[ SQN Unit 0 RESIDUAL HEAT REMOVAL SYSTEM 0-SO-74-i Rev. 0084 Page 101 of 335 Unit I Date 55.2 Placing RHR in Service for Normal Shu tdown Cooling (continued)

CANS If Loop 4 hot leg temperature is greater than 213°F, then only one RHR pump may be placed in service.

7 Failure to maintain steady-state RHR flow rate at the maximum possible could 7 result in reduced motor thrust bearing life. [C.3]

) RHR pump protection is ensured if miniflo w valve is open when injection flow is less f than 780 gpm or when greater than 500 gpm indicated on Fl-74-12.

If Train B RHR is placed in service with Loo p 4 hot leg temperature greater than 190°F, FCV-74-24 is required to be de-energized in the OPEN position. This ensure that containment sump suction piping tem s perature remains below the 196°F limit for containment spray pump NPSR j2 RHR motor lower bearing oil level will rise afte sightglass. The presence of oil can be verifie r pump is started and may rise above d by a golden tint or a milk color (two different oils approved) in sightglass.

L [12] IF RHR Train B is being placed in service, AND Loop 4 hot leg temperature is greater than 190°F or heat-up above 190°F is planned, THEN PERFORM the following:

[12.1] START RHR Pump B-B with [HS-74-20A1.

[12.2] ENSURE IFCV-74-241 RHR Pump B-B miniflow OPEN.

[12.3] DISPATCH operators to de-energize FCV-74-24 with valve in OPEN position: (N/A breaker for other uni t)

UNIT BREAKER LOCATION POSITION 1st CV I 1-BCTD-74-24-B Rx MOV Bd IBI-B OFF Comptl4E 2 2-BCTD-74-24-B Rx MOV Bd 2B1-B OFF Comptl4E

T SQN Unit 0 RESIDUAL SEAT REMOVAL SYSTE M 0-SO-74-1 Rev. 0084 Page 102 of 335 Unit 1 Date l--1 5.5.2 Placing RKR in Service for Normal Shutdown Cooling (continued)

[12.4] PLACE caution order on handwitch and I breaker for FCV-74-24 to notify operators of the reas on for breaker in OFF.

D The following step may be marked N/A if Rmp B-B was staed in Step 5.5.2(1 2].

[13] IF RHR Train B is being placed in service,

AND Loop 4 hot leg temperature is less than 190°F, THEN:

[13.1] START RHR Pump B-B with [HS-74-20 A1.

[13.2] VERIFY FFCV-74-241 RHR Pump B-B miniflow OPENS or greater than 500 gpm is indicated on Fl-7 4-24.

NOTE The following step is a continuous action which applies while in Mode 4 with RHR pump running.

MONITOR running RHR pump:

[14.1] IF unit is in Mode 4 AND only one RHR pump is operable, THEN ENSURE dedicated operator stationed at M-6 to mo nitor running RHR pump.

iF running RHR pump loses suction.

THEN STOP running RHR pump.

[12] GO TO applicable AOP:

AOP-R.02, Shutdown LOA OR

AOP-R.03, RHR Malfunction.

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F SQN RESIDUAL HEAT REMOVAL SYSTEM O-SO-74-1 IJnitO Rev 0084 Page 103 of 335 Unit I Date I ---/

5.5.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

LPRT level rising following RHR pump stan indicate an open RHR relief valve.

fr1) IF PRT level is rising due to open relief valve, L.Z THEN

[15.1) STOP operating RHR pump and PLACE in PULLTO LOCK.

[15.2] CLOSE [FCV-74-11 AND [FCV-74-21.

[15.3) NOTIFY Unit Supervisor.

CN RCS pressure must also be maintained in accordan ce with the applicable GO procedure. Excessive pressure reduction could result in loss of adequate NPSH and seal DIP for running RCPs. (

Reference:

Tl-28 Figu re 4).

)

4 ff3 MAINTAIN RCS pressure less than 350 psig and RHR 7 discharge pressure less than 550 psig [P1-74-i 3 or P1-74-26]

WHILE RHR is in service.

i7) PERFORM the following to establish RHR letdown on RI-fR 1 train being placed in service:

[] VERIFY normal charging and letdown are in service.

One of the valves in the next substep will be opened.

[p OPEN RHR letdown isolation for RHR train being placed in service: (NIA valve not opened)

VALVE NO. FUNCTION INITIALS IV 74-530 RHR Fix A to Letdown Hx 74-531 RHR Fix B to Letdown Hx PW

SQN RESIDUAL HEAT REMOVAL SYSTEM 0-SO-74-1 Unit 0 Rev. 0084 Page 104 of 335 Unit I Date )2133r%1 5.5.2 Placing RHR in Service for Norma) Shutdown Cooling (continued)

When pressurizer is solid, adjusting PCV-62-81 will affect RCS pressure.

[fl IF manual control of PCV-62-81 is desired, 7 THEN

[1Z PLACE [HIC-62-81A1 CVCS letdown pressure controller in MANUAL,

[11 ADJUST IPCV-62-811 to maintain desired letdown pressure and flow.

IF auto control of PCV62-81 is desired, THEN ENSURE fHlC-6281Aj in AUTO.

MONITOR VCT level maintained in normal band.

1) Maximum letdown flow rate is desireRCS cleanup. Maximum allowed letdown flow is 120 gpm (180 gpm in Mode 5 or 6 as specified in 0-GO-7 Appendix [1).

2) FCV-6283 must be fully open when RCS is water solid with pressure controlled by PCV-62-81.

[1 THROTTLE or OPEN fFCV-62831 to establish letdown r toCVCS.

t One of valves in next step will be opened.

OPEN RHR Hx bypass valve for RHR train being placed in service: (N!A valve not opened)

VALVE NO. FUNCTION INITIALS IV HCV-74-36 RHR Hx A Bypass HCV-74-37 RHR Hx B Bypass ILl )Z

SQN RESIDUAL HEAT REMOVAL SYSTEM 0-SO-74-1 Unit 0 Rev 0084 Page 105 of 335 Unit ( Date 4 it t)4 55.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

CALJNS FCV-74-1 6 and -28 may leak throughin excess of 1100 I gpm when FCV-63-93 or FCV-63-94 are open. This will cause boiling of CCS in RHR Hx unless adequate CCS flow is established through Hx.

To reduce vibration across FCV-74-1 6 or FCV-74-28 (RHR Hx Outlet Valves), RHR must be aligned to only two cold legs when one train is in operation.

9E One of the valves in the next step will be opened. (NIA valve not opened).

OPEN RHR injection valve for RHR train being placed in service:

VALVE NO. FUNCTION INITIALS IV FCV-63-93 RHR Pump A-A Discharge to Loops 2 zZ and 3 Cold Leg FCV-63-94 RHR Pump B-B Discharge to Loops I t bi- I- hz.

and 4 Cold Leg NØ If RHR is in service with the miniflow valve de-energized in the open posi tion (RCS hot leg temperature greater than 190°F), the following step may be marked N/A for the train in service, The following step should be marked N/A for the train which is NOT in service, WHEN RHR injection flow is greater than 1250 gpm, THEN ENSURE miniflow valve for RHR pump in service is CLOSED:

PUMP VALVE NO. INiTIALS IV A-A FCV-74-12 B-B FCV-74-24 tL) ) A) icZ ]

SQN RESIDUAL HEAT REMOVAL SYSTEM 0-SO-74-1 Unit 0 Rev. 0084 Page 106 of a35 Unit I Date TZfl4 5.5.2 Placing RHR in Service for Normal Shutdown Cooling (continued)

CMØN Flow through FCV-74-16, FCV-74-28, and FCV-74-32 should be coordinated to achieve target RCS cooldown rate of 75°F per hour (100°F per hour absolute maximum).

ES

1) The valve for the RHR train in service may be throttled to obtain desired cooling rate.

2) Steps 5.5.2[21 and 5.52[22] should be performed concurrently.

SLOWLY THROTTLE fFCV-74421 RHR Hx bypass to avoid thermal shock.

1 c

]2 THROTTLE the RHR Hx valve for the RHR train being placed 7 in service. (NIA other valve)

VALVE NO. FUNCTION INITIALS FCV-74-1 6 RHR Hx A Outlet FCV-74-28 RHR Hx B Outlet I-CAN RHR must be capable of being manually1aIigned for 4 Loop Cold Leg injection while in Mode 4.

IF required.

7 THEN CLOSE the RI-IR cross-tie valve for the train NOT in service (NIA other valve):

VALVE NO. FUNCTION INITIALS IV FCV-74-33 RHR Fix A Crosstie Isol FCV-74-35 RHR Hx B Crosstie Isol

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_

Unit I Date 5.52 Placing RHR in Service for Normal Shutdown Cooling (continued)

The following step may be marked N/A if 63-800. was closed in Section 5.5.1. If 63-800 was NOT previously closed, then this step must remain open until 0-Sl-SXI-000-201 .0 is completed.

[24 WHEN 0-Sl-SXI-000-201 .0 has been completed on RHR system (during shutdown for refueling outage),

THEN CLOSE IVLV-63-8001 Gate Valve Bypass Isolation.

(#4 Acc. Room near FCV 172) 1 st CV IF Loop 4 hot leg temperature is less than 213°F AND two train RHR cooldown is desired, THEN GO TO Section 6.2.

NOTE The following step may be marked N/A if RCS temperature will remain greater than or equal to 190°F, it heatup above 190°F is planned, or if this action is completed in another section.

[26] WHEN Loop 4 hot leg temperature is less than 190°F, AND cooldown will be continued, THEN PERFORM the following:

[26.1] ENSURE RHR pump suction valves OPEN:

VALVE NO. FUNCTION INiTIALS IV FCV-74-3 RHR Pump A-A suction FcV-74-21 RHR Pump 8-B suction

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPME

SIM JPM E Page 2 of 16 ROISRO JOB PERFORMANCE MEASURE Task: Establishing Secondary Heat sink using Main Feedwater Task#: 3110060601 Task Standard: Secondary Heat Sink is established using a Main Feedwater pump.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA Reference!Ratings: EPE E05 EA2.1 (3.4/4.4)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 20 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM E Page 3 of 16 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettolC3l5.

3. If IC 315 is not available perform the following:

4. ResettolCl6 a) Insert the following on the simulator:

IRE FWR34 OUT.

IMFFWO7Bf:1.

IMFFWO7Cf:1.

Place the HS for lA-A MD AFW pump in PTL.

b) Trip the reactor.

c) Set Steam Dump Pressure Mode Setpoint to 968 psig.

d) Allow SIG narrow range levels to get to <20 e) CLOSE MEW regulating valves.

f) CYCLE reactor trip breakers.

g) RESET FW Isolation signal h) OPEN feedwater isolation valves to #1 S/G.

i) Place Main Eeed Reg Valves in MAN with 0 output.

j) Turn off RCPs.

5. An extra operator will be required to acknowledge alarms.

6. PLACE SIMULATOR IN RUN

7. ACKNOWLEDGE ALARMS

8. FREEZE SIMULATOR.

9. Provide an in-progress copy of EA-2-2, Establishing Secondary Heat sink using Main Feedwater or Condensate.

10. Save as a temporary IC, if repeat runs of JPM will be desired.

11. PLACE SIMULATOR IN RUN

12. When directed open VLV-3-576 by inserting IRF FWRI4A f:1

13. After JPM is complete, delete the temporary IC, if used.

SIM JPM E Page 4 of 16 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.

2. Any UNSAT requires comments.

ToolslEquipmentlProcedures Needed:

EA-2-2, Establishing Secondary Heat sink using Main Feedwater or Condensate Section 4.4.

References:

Reference Title Rev No.

1. EA-2-2 Establishing Secondary Heat sink using Main Feedwater or 10 Condensate 2.

SIM JPM E Page 5 of 16 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

1. Unit 1 is in MODE 3 following an event.

2. No AFW pumps are available.

3. EA-22, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System, section 4.4 has been completed up to step 8.

INITIATING CUES:

1. The US directed you to establish Main Feedwater flow to #1 SIG with the A Main Feed Pump using EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater, section 4.4, starting at step 9.

2. Inform the US when Main Feedwater flow has been established to one SIG.

SIM JPM E Page 6 of 16 Start Time STEP

Obtain a copy of EA-2-2, Establishing Secondary Heat Sink Using 1 SAT Main Feedwater or Condensate System, section 4.4.

UNSAT Standard: Operator obtains a copy of EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System, section 4.4.

CU Provide a marked up copy of EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System, section 4.4.

Comment

SIM JPM E Page 7 of 16

9. IF starting MEW pump A, STEP 3 THEN SAT PERFORM the following:

UNSAT

b. ENSURE the following valves OPEN:

VALVE DESCRIPTION OPEN I FCV-2-205 MFPT condenser A inlet isol [M-2] LI FCV-2-210 MFPT condenser A outlet isol [M-2] LI FCV-2-221 MFWP A inlet valve [M-2] LI FCV-3-67 MFWP A outlet valve [M-31 LI Standard: Operator addresses the procedure steps.

Corn ment

9. IF starting MEW pump A, STEP 4 . THEN SAT PERFORM the following:

UNSAT

c. DISPATCH operator to perform the following: [TB el. 7061

1) OPEN [VLV-3-576] FDWTR Pmp Mm lsol valve.

2) IF [VLV-1 -6111 MEW Pump A HP steam isolation valve CLOSED, THEN OPEN IVLV-1-6111.

Standard: Operator addresses the procedure steps.

Examiner Note: Direct booth operator to open VLV-3-576 Cue If asked to perform steps as the AUO, acknowledge the communication and report all steps complete.

Comment

SIM JPM E Page 8 of 16

9. IF starting MFW pump A, STEP 5 THEN PERFORM the following:

SAT RESET MFPT A USING [HS-46-9A1 UNSAT Comment 9- IF starting MFW pump A THEN SAT PERFORM the following:

UNSAT e PLACE MFPT A [S1C46-20A] in MANUAL with ZERO output Operator depresses MFPT 1A MFPT Speed Control [SIC-46-20A]

Standard MANUAL/AUTO PB to get an AMBER light ON and obtains ZERO output by pressing LOWER (<<) or RAMP and LOWER (<<) using the CRITICAL controller or the DCS Display. .

Comment STEP 9- IF starting MFW pump A, 7 SAT THEN PERFORM the following:

UNSAT L ENSURE MFPT A and B master speed controller [PC-46O1 in MANUAL with c at ZERO Comment

SIM JPM E Page 9 of 16 9 IF starting MEW pump A, STEP 8 SAT

. THEN PERFORM the following:

UNSAT

g. DO NOT CONTINUE until suction flowpath estamished to MFP Standard: Operator addresses the procedure step.

Provide the following cue, A suction flow path is established to the Cue MFP.

Comment

9. IF starting MEW pump A, STEP 9 PERFORM the following:

UNSAT h.. ENSURE fVLV-3-576] FDWTR Pmp Mm Isol valve OPEN Standard:

Provide the following cue, Valve-3-576 Feed water Pump Mm Cue Isolation valve is OPEN Comment 9 IF starting MEW pump A, STEP 10

. THEN PERFORM the following:

UNSAT i ENSURE [FIC-3-70] TrWPT A re:irc valve in MANUAL and OPEN.

Operator places FlG-3-70 slide sw to OPEN (left) until minimum output Standard: CRITICAL Corn ment

SIM JPM E Page 10 of 16 9 IF starting MFW pump A, THEN SAT PERFORM the following:

UNSAT

j. PLACE MFPT A speed controller [S1C46-20A] in AUTO.

Operator depresses MFPT 1A Speed Control [SIC-46-20A]

Standard: MANUAL/AUTO PB to get a BLUE light ON using the controller or the CRITICAL DCS Display.

Comment STEP 9. IF starting MEW pump A, 12

. THEN PERFORM the following:

UNSAT

k. VERIFY MFPT governor valve positioner is indicating CLOSED.

Standard: Operator observes green light above 1-HS-46-13A ON.

Comment 9 IF starting MFW pump A, STEP 13

.

THEN PERFORM the following:

UNSAT I. IF MFPT governor valve positioner is NOT indicating CLOSED THEN Standard: Operator addresses the step as N/A.

Comment

SIM JPM E Page 11 ofl6 W IF starting MEW pump A STEP 14 SAT THEN PERFORM the following:

UNSAT rn. OPEN FPT A stop valves by placing HP stop valve switch

[HS-46-i5Al to RAISE.

HP and LP stop valve will open when the HS is placed in raise. Either Examiner HS placed in raise will open the valves. If HS-46-16A is used to open Note stop valves then make a comment. Critical task is also SAT if HS 16A is used.

Comment NOTE MFPT speed controller should take over speed control when MFPT accelerates to approximately 3300 rpm.

9. IF starting MFW pump A, STEP 15

. ThEN PERFORM the following:

UNSAT n RAISE MFPT A speed by performing one of the following:

1) IF MCR operation of qovemor valve postioner is available.

THEN PLACE [HS-46-13A1 to RAISE to open the s1eim chest valves OPERATOR places HS-47-1 3A in RAISE to open GV fully and attain Standard: CRITICAL Comment Examiner Note MFP speed should stabilize at -P3300 rpm as seen on 1-SI-46-20A.

SIM JPM E Page 12 of 16

9. IF starting MEW pump A, STEP 16 AT

. THEN PERFORM the following:

UNSAT

0. WHEN MFPT speed controller controlling MFPT speed, THEN ENSURE governor valve positioner is fuLly RAISED.

Operator observes red light above I -HS-46-1 3A Governor Valves Standard Positioner MFPT A is ON.

Comment

9. IF starting MEW pump A, STEP 17 SAT

. THEN PERFORM the following:

UNSAT

p. ADJUST MFPT speed USING master controller 1PC46-201 UNTIL feedwater header pressure is approximateLy 80 psid greater than steam header pressure.

Operator raises FW header pressure greater than steam header Standard: pressure using the RAISE (>>)or RAMP and RAISE (>>)on either CRITICAL PC-46-20 or the DCS Control Display.

The operator successfully achieves the Critical Step by raising FW Examiner header pressure sufficiently to initiate Main Feed flow to the Steam Note Generators.

Operator may monitor P1-3-i # 1 HTR Inlet Pressure (on M-3), and P1-Examiner 1-33, Main Steam Header Pressure (on M-4). Operator may also Note monitor FW/SG delta P on ICS/Secondary Mimics/Feedwater screen or monitor using the DCS Control Display.

Comment

SIM JPM E Page 13 of 16 lO IF starting MEW pump B, STEP 18 : THEN SAT PERFORM the following; UNSAT Standard: Operator addresses the step as N/A and goes to step 1 1.

Comment STEP 19 : 11. IF RCS temperature is less than 55O°F SAT THEN GO TO Step 13 UNSAT Standard: OPERATOR verifies temperature is >550°F and goes to step 12.

Comment

SI M JPM E Page 14 of 16 CAUTION Restoration otfeedwater flow will result in an RCS cooldown.

FW Isolation will occur it PM signal is not defeated by depressing FWI reset pushbuttons prior to RCS temperature falling below 550°F.

12. IF RCS temperature is greater than 550°F STEP 20 AND Feedwater isolation Valves are OPEN, SAT THEN PERFORM the following when feeciwater is established: UNSAT

a. WHEN Tavg approaches 550°F, THEN DEPRESS and HOLD both FWI reset pushbuttons [M-3]

b. WHEN 7-avg is less than 550°F, THEN RELEASE FWI reset pushbuttons.

Standard: Operator addresses the procedure step.

Cue Provide the following cue, Another operator will monitor Tave.

Comment

SIM JPM E Page 15 of 16 CAUTION if automatic Si signals are NOT blocked, feed flow should be carefully controlled to prevent rapid cooldown which could result in low steam line pressure Si actuation (and subsequent feedwater isolation).

NOTE 0.2 x 108 lbrnihr feed flow is equivalent to approximately 440 gpnt Due to inaccuracy of flow indication at low end of scale, feed flow should be determined based on a rise in indicated flow.

STEP 21 13 ADJUST MFW regulating bypass valve controller SAT to establish required feed flow..

UNSAT Examiner The operator successfully achieves the Critical Step by opening the Note Feed Reg Bypass valve(s) sufficiently to initiate Main Feed flow to a Steam Generator.

Corn ment Terminating Provide the following cue when feed flow is established to a SIG Cue: Another operator will complete the remaining steps of this STOP procedure.

Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3 following an event.

2. No AFW pumps are available.

3. EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater or Condensate System, section 4.4 has been completed up to step 8.

INITIATING CUES:

1. The US directed you to establish Main Feedwater flow to #1 SIG with the A Main Feed Pump using EA-2-2, Establishing Secondary Heat Sink Using Main Feedwater, section 4.4, starting at step 9.

2. Inform the US when Main Feedwater flow has been established to one SIG.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SQN ESTABLISHiNG SECONDARY HEAT SINK 22 1, 2 USING MAIN FEEDWATER OR CONDENSATE SYSTEM Rev. 10 Page 7 of 44 4.4 Establishing Main Feedwater Flow to SIGs Removal of fuses should be performed in parallel with subsequent steps.

DISPATCH operator to perform Appendix E, Part I to remove fuses

)( to disable intermediate heater string isolation.

,4?7 ENSURE Condensate inlet and outlet valves for at least one LP heater 4- string are OPEN. [M-3]

CI,4lON Condensate flowpath through at least one LP heater string U. must be established prior to starting a Condensate Booster Pump.

ENSURE the following condensate pumps RUNNING:

0 At least two Hotwell pumps At least one Condensate Booster Pump (with suction valve OPEN)

At least one Injection water pump.

ENSURE MFPT Recirc Valves in MANUAL and CLOSED:

[FIC-3-70] MFPT A

[FIC-3-84] MFPT B.

(ENSURE MFW reg controllers in MANUAL and output ZERO.

ENSURE MFW bypass reg valve controllers in MANUAL and output ZERO.

SQN ESTABLISHING SECONDARY HEAT SINK EA-2-2 1,2 USING MAIN FEEDWATER OR CONDENSATE SYS Rev, 10 TEM Page 8 of 44 4.4 Establishing Main Feedwater Flow to SIGs (Continue d)

Condensate isolation valves for intermediate pressure heater strings may have closed due to high-high level condition.

iD IF a flowpath is NOT available through at least one intermediate heater string, THEN NOTIFY personnel to PERFORM Appendix E Part II to establish a flow path.

ENSURE Inlet and Outlet valves for at least one string of Intermed iate and High pressure heaters OPEN:

High Pressure Feedwater Heaters Intermediate Pressure Feedwater Heaters.

ESTABLISHING SECONDARY HEAT SINK EA-2-2 USiNG MAIN FEEDWATER OR CONDENSATE SYSTE Rev. 10 M

Page 9 of 44 44 Establishing Main Feedwater Flow to SIGs (Continued)

9. IF starting MFW pump A, THEN PERFORM the following:

a. ENSURE MFW pump A drain handswitch IHS-46-141 in OPEN position IM-3].

LI

b. ENSURE the following valves OPEN:

VALVE DESCRIPTION OPEN f FCV-2-205 MFPT condenser A inlet isol [M-21 LI FCV-2-21 0 MFPT condenser A outlet isol [M-2] LI FCV-2-221 MFWP A inlet valve [M-2] LI FCV-3-67 MFWP A outlet valve [M-3] LI NOTE HP steam to MFW pump may be isolated if 0-GO-12, Appendix A has been performed or MEW pump was out of service at time of trip.

c. DISPATCH operator to perform the following: [TB el. 706]

1) OPEN [VLV-3-576] FDWTR Pmp Mm lsol valve.

2) IF [VLV-1 -61 1] MFW Pump A HP steam isolation valve CLOSED, THEN OPEN [VLV-l -61 1].

d. RESET MFPT A USING [HS-46-$AJ. LI

e. PLACE MFPT A [SIC-46-20A] in MANUAL with ZERO output.

f. ENSURE MFPT A and B master speed controller [PC-46-201 in MANUAL with output at ZERO. LI (step continued on next page)

I SQN ESTABLISHING SECONDARY HEAT SINK I EA-2-2 1 1,2 USING MAIN FEEDWATER OR CONDENSATE SYSTE M Rev.1O I I PagelOof44 4.4 Establishing Main Feedwater Flow to SIGs (Continued)

9. (Continued)

g. DO NOT CONTINUE until suction flowpath established to MFP LI

h. ENSURE [VLV-3-576] FDWTR Pmp Mm Isol valve OPEN.

i. ENSURE [FIC-3-701 MFPT A recirc valve in MANUAL and OPEN.

Li

j. PLACE MFPT A speed controller [SIC-46-20A1 in AUTO.

LI

k. VERIFY MFPT governor valve positioner is indicating CLOSED.

LI

1. IF MFPT governor valve positioner is NOT indicating CLOSED, THEN

1) IF MCR operation of governor valve positioner is available, THEN PLACE [HS-46-l 3A] to LOWER to close the steam chest valves. LI

2) IF MCR operation of governor valve positioner is NOT available, THEN a) ESTABLISH direct communications between I&C personnel to operate the MFP speed control locally and the Main Control Room. LI b) DIRECT l&C to adjust MFP Speed Control using local manual control of the MFP governor valve positioner to close steam chest valves. LI

m. OPEN MFPT A stop valves by placing HP stop valve switch

[S-46-15A] to RAISE. LI (step continued on next page)

$QN ESTABLISHING SECONDARY HEAT SINK EA-2-2 1, 2 USING MAIN FEEDWATER OR CONDENSATE SYSTEM Rev. 10 Page II of44 4.4 Establishing Main Feedwater Flow to SIGs (Continued)

9. (Continued)

NOTE MFPT speed controller should take over speed control when MFPT accelerates to approximately 3300 rpm.

n. RAISE MFPT A speed by performing one of the following:

1) IF MCR operation of governor valve positioner is available, THEN PLACE EHS-46-13A] to RAISE to open the steam chest valves.

2) IF MCR operation of governor valve positioner is NOT available, THEN a) ESTABLISH direct communications between l&C personnel to operate the MFP speed control locally and the Main Control Room.

b) DIRECT I&C to slowly adjust MFP Speed Control using local manual control of the MFP governor valve positloner to open steam chest valves. LI

o. WHEN MFPT speed controller controlling MFPT speed, THEN ENSURE governor valve positioner is fully RAISED.

p. ADJUST MFPT speed USING master controller [PC-4620i UNTIL feedwater header pressure is approximately 80 psid greater than steam header pressure.

SQN ESTABLISHING SECONDARY HEAT SINK I EA-2-2 t2 USING MAIN FEEDWATER OR CONDENSAT E SYSTEM lRev.1O Page 12 of 44 4.4 Establishing Main Feedwater Flow to SIGs (Continue d)

10. IF starting MFW pump B, THEN PERFORM the following:

a. ENSURE MFW pump B drain handswitch LHS-46-41]

in OPEN position. IM..31

b. ENSURE the following valves OPEN:

VALVE DESCRIPTION OPEN FCV2-211 MFPT condenser B inlet isol [M2] Li FCV-2-216 MFPT condenser B outlet isol (M-3] LI FCV-2-224 MFWP B inlet valve [M2] LI FCV-3-81 MFWP B outlet valve [M-3] LI NOTE HP steam to MEW pump may be isolated if 0-GO-12, Appendix A has been performed or MFW pump was out of service at time of trip.

c. DISPATCH operator to perform the following: [TB el. 7061

1) OPEN [VLV-3-5771 FDWTR Pmp Mm Isol valve.

2) IF [VLV1 -6121 MEW Pump B HP steam isolation valve CLOSED, THEN OPEN [VLV.4-61Z1.

d. RESET MFPT B USING [HS-46-31A1. Li

e. PLACE MFPT B [SIC-46-20B1 in MANUAL with ZERO output. LI

f. ENSURE MFPT A and B master speed controller [PC-46-201 in MANUAL with output at ZERO.

(step continued on next page)

SON 1,2 I ESTABLISHING SECONDARY HEAT SINK USING MAIN FEEDWATER OR CONDENSATE SYSTEM I EA-2-2 I

Rev. 10 Page 13 of 44 i

4.4 Establishing Main Feedwater Flow to SIGs (Continued)

10. (Continued)

g. DO NOT CONTiNUE until suction fiowpath established to MFP.

h. ENSURE [VLV-3-5771 FDWTR Pmp Mm lsol Valve OPEN.

i. ENSURE [FIC-3-84] MFP B recirc valve in MANUAL and OPEN.

LI

j. PLACE MFPT B speed controller [SJC-46-2061 in AUTO.

k, VERIFY MFPT governor valve positioner is indicating CLOSED.

El I. IF MFPT governor valve positioner is NOT indicating CLOSED THEN

1) IF MCR operation of governor valve positioner is available, THEN PLACE [HS-4640A1 to LOWER to close the steam chest valves. El

2) IF MCR operation of governor valve positioner is NOT available, THEN a) ESTABLISH direct communications between I&C personnel to operate the MFP speed control locally and the Main Control Room. LI b) DIRECT l&C to adjust MFP Speed Control using local manual control of the MFP Governor Valve Positioner to close steam chest valves.

m. OPEN MFPT B stop valves by placing HP stop valve switch IHS-46-43A1 to RAISE.

(step continued on next page)

I SQN ESTABLISHING SECONDARY HEAT SINK I EA-2-2 Rev. 10 I

1 1, 2 USING MAIN FEEDWATER OR CONDENSATE SYSTEM j Pagel4of44 I

4.4 Establishing Main Feedwater Flow to SIGs (Continued)

10. (Continued)

NOTE MFPT speed controller should take over speed control when MFPT accelerates to approximately 3300 rpm.

n, RAISE tAFPT B speed by performing one of the following:

1) IF MCR operation of governor vvalve positioner is available, THEN PLACE tHS-46-40A1 to RAISE to open steam chest valves.

2) IF MCR operation of governor valve positioner is NOT available, THEN a) ESTABLISH direct communications between i&C personnel to operate the MFP speed control locally and the Main Control Room. LI b) DIRECT l&C to slowly adjust MFP Speed Control using local manual control of the MFP Governor Valve Positioner to open steam chest valves.

o. WHEN MFPT speed controller controlling MFPT speed, THEN ENSURE governor valve positioner is fully RAISED. LI

p. ADJUST MFPT speed USING master controller IPC-4620 UNTIL feedwater header pressure is approximately 80 psid greater than steam header pressure.

SON ESTABLISHiNG SECONDARY HEAT SINK EA-2-2 1,2 USING MAIN FEEDWATER OR CONDENSATE SYSTEM Rev. 10 Page 15 of 44 4.4 Estabhshing Main Feedwater Flow to SIGs (Continued)

11. IF RCS temperature is less than 550°F, THEN GO TO Step 13.

CAUTION Restoration of feedwater flow will result in an RCS cooldown.

FW Isolation will occur if FWI signal is not defeated by depressing FWI reset pushbuttons prior to RCS temperature falling below 550°F.

12. IF RCS temperature is greaterthan 550°F AND Feedwater Isolation Valves are OPEN, THEN PERFORM the following when feedwater is established:

a. WHEN Tavg approaches 550°F, THEN DEPRESS and HOLD both FWI reset pushbuttons (M-3].

El

b. WHEN i-avg is less than 550°F, THEN RELEASE FWI reset pushbuttons. El CAUTION If automatic SI signals are NOT blocked, feed flow should be carefully controlled to prevent rapid cooldown which could result in low steam line pressure Si actuation (and subsequent feedwater isolation).

NOTE 0.2 x 106 Ibm/hr feed flow is equivalent to approximately 440 gpm.

Due to inaccuracy of flow indication at low end of scale, feed flow should be determined based on a rise in indicated flow.

13. ADJUST MEW regulating bypass valve controller to establish required feed flow.

SQN ESTABLISHING SECONDARY HEAT SINK EA-2-2 I 1,2 USING MAIN FEEDWATER OR CONDENSATE SYSTEM Rev. 10 L Pagel6of44 4.4 Establishing Main Feedwater Flow to S1Gs (Continued)

14. MONITOR Hotweil level and CONTROL as necessary.

El

15. RETURN TO procedure and step in effect.

END OF TEXT

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMF

SIM JPM F Page 2 of 10 ROISRO JOB PERFORMANCE MEASURE Task: Respond to High Containment Pressure, Place RHR Spray in Service Task#: 3110160601 Task Standard:

Alternate Path: YES: X NO:

Time Critical Task: YES: NO: X KIA ReferencelRatings: EPE E14 EA 1.1 (3.7/3.7)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 8 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM F Page 3 of 10 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettolC326.

3. If IC 326 is not available perform the following, reset to IC 24 and perform the following.

a) IMFTHO1Af:35 b) IMFCHO1Af:70 c) IMFCHOIBf:70 d) IMF CHO1C f:70 e) IMF CHOI D f:70 f) ICR ZDIHS724IA f:0, to prevent FCV-72-41 from opening.

g) IRE RHR14f:i h) Then perform actions of ES-i .3.

4. An extra operator will be required to acknowledge alarms.

5. ACKNOWLEDGE ALARMS

6. FREEZE SIMULATOR.

7. Provide an in-progress copy of FR-Z.1 High Containment Pressure

8. Save as a temporary IC, if repeat runs of JPM will be desired.

9. PLACE SIMULATOR IN RUN.

10. At JPM step 11, when examinee opens 1 -FCV-72-40:

a) Modify malfunction CHOIA f:O r:240 k:i b) Modify malfunction CHOI B f:O r:240 k: I c) Modify malfunction CHO1B f:O r:240 k:i d) Modify malfunction CHOID f:O r:240 k:i

11. After JPM is complete, delete the temporary IC, if used. Delete the contents of the recycle bin, If a temporary IC has been deleted.

ToolslEquipmentlProcedures Needed:

References:

L f Reference Title Rev No.

I FR-Z. 1 F 1.

2.

High Containment Pressure 19

SIM JPM F Page 4 of 10 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit 1 has experienced an event that has resulted in a Reactor Trip and Safety Injection.

2. FR-Z.1 High Containment Pressure is in progress.

3. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.1 was implemented.

4. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months has elapsed since the accident.

INITIATING CUES:

1. You have been directed to start RHR spray using FR-Z.1 High Containment Pressure starting at step 13 b.

2. Inform the SRO when complete.

SIM JPM F Page 5 of 10 Start Time STEP i Obtain a copy of FR-Z. 1 High Containment Pressure.

SAT U N SAT Standard: Exarninee obtains a copy of FR-Z.1 High Containment Pressure.

Provide a marked up copy of FR-Z.1 High Containment Pressure.

Corn ment STEP 2 : 1& MONITOR t RHR spray should be placed SAT in service:

U N SAT b CHECK both RHR pumps RUNNING.

Standard Exarninee checks both RHR pumps are running by observing red lights above HS-74-1OA and 20A ON.

Comment STEP 3 : 13. MONITOR it RHR spray should be placed SAT in seivice:

C. ESTABLISH Train B RHR spray: UNSAT

1) CHECK Train B RHR pump RUNNING Standard Examinee checks that 1 B-B RHR pump is running by observing red light above HS-74-20A ON.

Comment

SIM JPM F Page 6 of 10 STEP 4 13, MONITOR if RHR spray should be placed SAT in service:

c. ESTABLISH Train B RHR spray:

U N SAT 2> ENSURE Ri-IR crosstie FCV-74-35 CLOSED.

Standard Examinee ensures FCV-74-35 is CLOSED by observing HS green light above HS-74-35A ON and red light OFF.

Comment STEP 5 13. MONITOR if RHR spray should be placed SAT in service:

U N SAT C. ESTABLISH Train B RHR spray:

3) CLOSE RHR injection FCV-63--94.

Comment STEP 6 : 13. MONITOR f RHR spray should be placed SAT in service:

UNSAT

c. ESTABLISH Train B RHR spray:

4) OPEN RHR spray FCV-72-41.

Standard Examinee places HS-72-41A RHR Containment Spray 18 Isolto OPEN and observes valve does not OPEN.

Comment

SIM JPM F Page 7 of 10 STEP ALTERNATE PATH 7 : SAT c IF Train B RHR spray UNSAT CANNOT be established, THEN PERFORM the foIloing:

a) ENSURE RHR spray FCV-72-41 CLOSED.

Standard Exam inee ensures FCV-72-41A RHR Containment Spray I B Isol closed by observing green lights above HS-72-41 ON.

Comment STEP 8 c IFTrainBRHRspray

. CANNOT be established. SAT THEN PERFORM the follong: UNSAT b) IF RHR aligned for cold leg recirculation.

THEN ENSURE FCV-63-94 OPEN.

Standard: Examinee places HS-63-94A RHR injection to Loop 1 & 4 to OPEN. CRITICAL Comment

SIM JPM F Page 8 of 10 STEP 9 C IF Train B RHR spray

. CANNOT be established, SAT

THEN PERFORM the rollowing: UNSAT C) ESTABLISH Train A RHR spray.

(1) ENSURE RHR crosstie FCV-74-33 CLOSED Standard Examinee ensures FCV-74-33 RHR crosstie closed by observing green lights above HS-74-33 ON.

Comment STEP 10 C. IF Train B RHR spray CANNOT be estabIshed. SAT THEN PERFORM the following: UNSAT C) ESTABLISH Train A RHR spraY:

) CLOSE RHR injection 2

k FCV-63-93.

Standard: Examinee places HS-63-93 RHR injection to Loop 2 & 3 to CLOSE. CRITICAL Comment Simulator Operator Note: When examinee starts to open FCV-72-40, initate a 240 sec ramp on CHOI A thru D to reduce CNMT pressure from 10.2 to zero (0).

SIM JPM F Page 9 of 10 STEP 11 c IF Train B RHR spray CANNOT be established, SAT THEN PERFORM the following: U NSAT c) ESTABUSH Train A RHR spray:

(3) OPEN RHR spray FCV-72-40.

STEP cL MONITOR containment pressure d WHEN containment pressure is 12 : greater than 4 psig SAT less than 4 psig, THEN PERFORM tte following: UNSAT Standard: Examinee verifies system response by observing installed instrumentation.

Comment Terminating Provide the following cue, Another operator will complete the Cue: remaining steps of this procedure. STOP Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit 1 has experienced an event that has resulted in a Reactor Trip and Safety Injection.

2. FR-Z.1 High Containment Pressure is in progress.

3. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.1 was implemented.

4. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months has elapsed since the accident.

INITIATING CUES:

1. You have been directed to start RHR spray using FR-Z. 1 High Containment Pressure starting at step 13 b.

2. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

SON HIGH CONTAINMENT PRESSURE FR-LI

[ Rev. 19 LSTEP [ATIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED If this procedure has been entered for an orange path and perfo rmance of ECA-1 .1 (Loss of RHR Sump Recirculation) is required, FR-Z.1 may be performed concurrently with ECA-1 .1.

MONITOR RWST level IF ES-i .3 has NOT been entered, greater than 27%. THEN GO TO ES-I .3, Transfer to RHR Containment Sump.

VERIFY Phase B valves CLOSED: IF I -FCV-32-1 10 (2-FCV-32-1 11) is NOT closed,

Panel 6K PHASE B GREEN THEN PERFORM EA-32-3, Isolating

Panel 6L PHASE B GREEN. Non-Essential Air to Containment.

IF other valves NOT closed AND flow path is NOT necessary, THEN CLOSE valves.

ENSURE RCPs STOPPED.

Page 3 of 13

SQN HIGH CONTAINMENT PRESSURE FR-Z1 Rev. 19 TJ IACTION!EXPECTED RESPONSE [iEPONSE NOT OBTAINED DETERMINE if this procedure should be exited:

CHECK for faulted S/G: (TO Step 5.

Any SIG pressure DROPPING in an uncontrolled manner OR Any S/G pressure less than 140 psig.

b. CHECK containment pressure b. GO TO Step 5.

less than 12 psig.

c. CHECK at least one containment c. IF containment pressure is greater than 2.8 psig, spray pump RUNNING and THEN delivering flow.

GO TO Step 5.

d. WHEN 10 minutes have elapsed

d. CHECK at least one containment from Phase B actuation, air return fan RUNNING. THEN ENSURE air return fans RUNNING.

a. RETURN to procedure and step in effect.

Page 4 of 13

L I STEP SQN HIGH CONTAINMENT PRESSURE ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED VERIFY containment spray operation:

a. IF ECA-1 .1, Loss of RHR Sump Recirculation, is IN EFFECT, j.)j? THEN PERFORM the following:

1) OPERATE containment spray as directed by ECA-1.l.

2) GO TO Step 6.

VERIFY containment spray pumps b. IF containment pressure is RUNNING. greater than 2.8 psig, THEN START containment spray pumps.

CHECK RWST level c. IF any of following conditIons met:

greater than 27%.

RWST level less than or equal to 8%

OR

containment sump level greater than 56%,

THEN PERFORM the following:

1) ENSURE cntmt spray pump suction aligned for sump recirc USING ES-i .3, Transfer to RHR Containment Sump, Step 21.

2) GO TO Substep 5.e.

(step continued on next page)

Page 5 of 13

SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 ISTEPI IACTION1EXPECTED RESPONSE j RESPONSE NOTOBTAINED

5. ,

VERIFY containment spray suction d. ALIGN valves as necessary.

ALIGNED to RWST:

FCV72-22 OPEN

FCV-72-21 OPEN.

VERiFY containment spray discharge e. OPEN valves for running valves OPEN: containment spray pumps.

FCV-72-39

FCV-72-2.

VERIFY containment spray recirc f. CLOSE valves as necessary.

valves CLOSED:

FCV-72-34

FCV-72-1 3.

VERIFY containment spray flow g. IF NO train of containment spray greater than 4750 gpm is available, on each train. THEN PERFORM the following:

1) CONTINUE efforts to restore at least one train of containment spray.

2) NOTIFY TSC to evaluate restoring normal containment cooling USING EA-30-4, Restoring Containment Coolers Page 6 of 13

SQN HIGH CONTAINMENT PRESSURE FR-LI Rev. 19

[TEP ACTIONIEXPECTED RESPONSE J I RESPONSE NOT OBTAINED MONITOR containment air return fans:

WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment air return fans RUNNING.

VERIFY containment ventilation dampers CLOSE dampers.

CLOSED:

Panel 6K CNTMT VENT GREEN Panel 6L CNTMT VENT GREEN.

VERIFY Phase A valves CLOSED: IF flow path NOT necessary, Panel K PHASE A GREEN THEN CLOSE valves.

Panel 6L PHASE A GREEN.

VERIFY cntmnt vacuum relief isolation IF containment pressure is valves CLOSED: [Pnl 6K MANUAL] greater than 1.5 psig, FCV4046 THEN CLOSE valves. [M-9]

FCV-30-47 FcV-30-48.

VERIFY MSIVs and MSIV bypass valves CLOSE valves.

CLOSED.

IF any MSIV CANNOT be closed, THEN CLOSE MSIV locally USING EA-1 -1, Closing MSIVs Locally.

Page 7 of 13

L SON HIGH CONTAINMENT PRESSURE

[STEP I I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAiNED DETERMINE if any SIG Intact: IF all S/Gs Faulted, THEN CHECK at least one S/G pressure: PERFORM the following:

5CONTROLLED or RISING 1) CONTROL feed flow at greater than or equal to 50 gpm to each S1G.

AND

2) OPEN MD AFW pump recirc valves 7Greater than 140 psig. FCV-3-400 and -401 as necessary.

3) GO TO Step 13.

Isolating all S!Gs will result in a loss of secondary heat sink.

DETERMINE if any S/G Faulted:

CHECK S!G pressures: GO TO Step 13.

Any S/G pressure DROPPING in an uncontrolled manner OR

Any S/G pressure less than 140 psig.

b. ISOLATE feed flow to affected S/G:

MFW

AFW Page 8 of 13

SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 ISTEI1 IACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 1

MONITOR if RHR spray should be placed in service:

CHECK the following: a. GO TO Step 14.

4315 Containment pressure St greater than 9.5 psig AND At least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months has elapsed since begInnin9 of accident AND (RHR suction ALIGNED to containment sump AND least one CCP AND one SI pump RUNNING.

HECK both RI-IR pumps RUNNING. b. IF only one RHR pump running, THEN PERFORM the following:

1) ENSURE only one CCP RUNNING (same train as running RHR pump preferred).

2) PLACE non-operating CCP in PULL TO LOCK.

3) ENSURE only one SI pump RUNNING (same train as running RHR pump preferred).

4) PLACE non-operating SI pump in PULL TO LOCK.

(Step continued on next page.)

Page 9 of 13

I STEP I IACTION1EXPECTED RESPONSE RESPONSE NOT OBTAINED

13. c. ESTABLISH Train B RHR spray: c. IF Train B RHR spray CANNOT be established,

1) CHECK Train B RHR pump THEN RUNNING. PERFORM the following:

2) ENSURE RHR crosstie a) ENSURE RHR spray FCV-72-41 FCV-74-35 CLOSED. CLOSED.

3) CLOSE RHR injection b) IF RHR aligned for cold leg FCV-63-94. recirculation, THEN

4) OPEN RHR spray FCV-7241. ENSURE FCV-63.94 OPEN.

c) ESTABLISH Train A RHR spray:

(1) ENSURE RHR crosstie FCV-74-33 CLOSED.

(2) CLOSE RHR injection FCV-63-93.

(3) OPEN RHR spray FCV-72-40.

IF Train A RHR spray CANNOT be established.

THEN PERFORM the following:

a) CLOSE RHR spray FCV-72-40.

b) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN.

(Step continued on next page.)

Page 10 of 13

SQN HIGH CONTAINMENT PRESSURE I STEP] [AcTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I

13. d. MONiTOR containment pressure d. WHEN containment pressure is greater than 4 psig. less than 4 psig, THEN PERFORM the following:

1> ENSURE FCV-72.-40 and FCV-72-41 CLOSED.

2) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 and FCV..63-94 OPEN.

3) IF ECCS is aligned for hot leg recirculation, THEN ENSURE RHR crosstie valves FCV-74-33 and FCV-74-35 aligned as required by ES-i .4.

Page 11 of 13

____

SON HIGH CONTAINMENT PRESSURE FR-Z.l Rev. 19 I STEP j [ATIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED

14. MONITOR if containment spray should be stopped:

a. CHECK any containment spray pump a. GO TO Step 15.

RUNN ING.

b. CHECK containment pressure b. GO TO Step 15.

less than 2.0 psig.

c. CHECK containment spray suction c. NOTIFY TSC to determine aligned to RWST. when one or both trains of cntmt spray should be stopped.

WHEN directed by TSC, THEN PERFORM Substeps 14.d through 14.f.

GOTOStepl5.

d. RESET Containment Spray.

e. STOP containment spray pumps and PLACE in A-AUTO.

f. CLOSE containment spray discharge valves:

FCV-72-39, Train A

FCV-72-2, Train B.

Page 12 of 13

a) uIX Ui I

[ SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev 13 Page3of 106 3.0 PRECAUTIONS AND LIMITA TIONS 3.1 Precautions If the accountability siren sou nds, the operator should contin procedure. The SM will remain ue performing this aware of procedure progress and performing personnel. location of If power was lost due to fire or electrical fault, resetting lockou power to de-energized busses t relays or restoring prior to evaluating damage cou re-energizing fault. ld result in More than one diesel generator should NOT be operated in par power at the same time. allel with off-site The following alignments result in a single CSST supplying all fou and shall be avoided to preven r shutdown boards t CSST overloading:

Both Unit I 6.91V Shutdow n Boards supplied from Start Bu AND both Unit 2 6.9kV Shutd s IA own Boards supplied from Start Bus 2A.

OR

Both Unit 1 6.9kV Shutdown Boards supplied from Start Bus AND both Unit 2 6.9kV Shutd lB own Boards supplied from Start Bus 2B.

If restoring Off-site power aft er an accident, the following req met. These requirements do not uirement apply if power must be quickly res s should be de-energized shutdown board: tored to a

Only one 6.9kV Shutdown Board should be fed from each CSST Wi This precaution does not apply if nding.

Unit 2 Start Bus Outage alignment DCN 22582 (15E500-3 table 3) is in per place.

Off-site power should be restored from a CCST Winding with tap change in AUTO. r 3.2 Limitations This EAP does NOT satisfy all Tech Spec and procedural requirements for operability of off-site power supplies. Re fer to O-SO-202-4, I 5E500-3 Table 3 and GOl-6 Apparatus Operation for additio nal requirements which must be met if off-sit pOwer supplies are required to be ope e rable.

SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 Page4of 106 4.0 PERFORMANCE 4.1 Section Appilcability 2SELECT appilcable unit:

Jnit I_____

Unit2 This procedure assumes that the start bus ses are energized.

AOP-P.OI, Loss of Off-Site Power, contain s guidance on restoring offsite power to the start busses. If necessa ry, start bus voltage may be adjusted using CSST tap changer.

N2 During (U2C17) outage Unit 2 Start Bus rep lacement modification temporary power feeds are from Unit 1 Start Buses via 6.9KV Unit Bd IA, 113 and IC. The 6.9kV Unit Board IA, ID and IC must be energized prior to energizing Unit 2 temporary pow procedure. er feeds in this 5 DETERMINE start bus availability for applica ble unit:

IF Start Bus available.

THEN ENSURE voltages on available Start Bus between 6800V and 7200V:

(5 11-EI-574] Start Bus 1A Volts [1-M-I].

[1-EI-57-56j, Start Bus lB Volts [I-M-I].

UNIT 2:

12-EI-57-55L Start Bus 2A Volts [2-M-I].

[2-EI-57-5, Start Bus 2B Volts 12-M-I].

SQN RESTORING OFF-SiTE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 Page5of 106 4.1 Section Applicability (Continued

)

t4ji The start bus normally aligned to the associated 6900V shutdown board is indicated in the table below by NORMAL.

3. IF energizing a DE-ENERGIZED 690 0V Shutdown Board, THEN SELECT applicable section:

DEENERGIZED 6.9KV SHUTDOWN BOARD TO BE ENERGIZED FROM: APPLICABLE PAGE

SECTION: NUMBER lA-A Start Bus 1A (ALTERNATE) 4.2 D 8 IA-A Start Bus lB (NORMAL) 4.3 D ii I B-B Start Bus 1 A (NORMAL) 44 D 14 lB-B Start Bus lB (ALTERNATE) 4.5 C 17 2A-A Start Bus 2A (ALTERNATE) 4.6 C 20 2A-A Start Bus 2B (NORMAL 4.7 C 24 28-B Start Bus 2A (NORMAL) 4.8 C 28 28-B Start Bus 28 (ALTERNATE) 4.9 C 32 2A-A 6.9KVUB ID Temporary Power 4.10 C 36 Feeds 2B-B 6.9KV UB IA Temporary Power 4.11 C 39 Feeds

SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 PageBof 106 4.1 Section Applicability (Continued)

IF restoring off-site power to a 6900V Shutdown Board ENERGIZED from the DIG, THEN SELECT applicable section:

SHUTDOWN BOARD OFFSITE POWER ENERGIZED FROM DIG APPLICABLE PAGE TO BE RESTORED FROM: SECTION: NUMBER:

IA-A Start Bus IA (ALTERNATE) 4.12 D 42 IA-A Start Bus lB (NORMAL) 413 t5( 48 lB-B Start Bus IA (NORMAL) 4.14 D 54 lB-B Start Bus lB (ALTERNATE) 4.15 60 2A-A Start Bus 2A (ALTERNATE) 4.16 D 66 2AA Start Bus 2B (NORMAL) 4.17 D 72 2B-B Start Bus 2A (NORMAL) 4.18 78 28-B Start Bus 28 (ALTERNATE) 4.19 D 84 2A-A 6.9KV UB ID Temporary 4.20 D 90 Power Feeds 28.-B 6.9KV UB IA Temporary 4.21 D 96 Power Feeds GO TO applicable section.

SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 Page48of 106 4.13 Restoring Off-Site Power to 6900V Shutdown Board IA-A From Start Bus Unloading DIG IA-A 18 AND If the differential lockout relay is tripped on 6.9kV Unit Bd IB, then the board should NOT be energiz ed until the cause of the differential relay actuation is determi ned and corrected.

IF 6.9kV Unit Board lB is de-energized, THEN PERFORM the following:

ENSURE all breakers on 6.9kV Unit Boa rd lB OPEN.

ENSURE overeurrent lockout relays RE SET (NOT tripped) on 6.9kV Unit Bd 18.

9 86-622, Breaker 1622 overcurrent lockout [Co mpt. 10]

86-1 14, Breaker 1114 overcurrent lockout [Co mpt 2]

VERIFY differential lockout relay on 6.9kV Unit Bd 16 RESET.

86-1 B, 6.9kV Unit I B Differential lockout rela y [Compt. 1] J)

,5 ENSURE 6.9kV Unit Board 1 B auto/manual selector [1 -XS-57-521 in MANUAL position. tl-M-1]

SQN RESTORING OFF-SITE POWER TO 6900V EA-202.1 SHUTDOWN BOARDS Rev. 13 1,2 Page49of 106 4.13 Restoring Off-Site Power to 6900V Shutdown Board IA-A From Start Bus I B AND Unloading DIG IA-A (Continued)

IF any white disagreement lights for breakers in Step 4 are LIT

[1-M-1],

THEN RESET white light by performing the following:

/1 MOMENTARILY PLACE Breaker Handswitch to TRIP positio n.

[1-M-1 0 ENSURE handswitch returns to the mid-position.

I DrawIng lB provides a single line diagram overview.

N 2 The following step will ensure 6.9kV Unit Board I B is energized.

ENSURE the following breaker lineup:

BREAKER DESCRIPTION LOCATION POSITION

[

1716 6.9kV Shutdown Bd IA-A supply OPE,N bkr from Unit Bd 1A 1-HS-57-41A, 1-M-1 Lf 1718 6.9kV Shutdown Bd lA-A supply OPN 1-HS-57-44A, 1-M-1 bkrfromUnitBdlB 1622 Start Bus I B to I -HS-57-51, I -M-1 CLOSED 6.9kV UnitBd lB 6.9kV Unit Sd lB to 1-M-1 indicating light 1714 6.9kV Shutdown Bd IA-A or 6.9kV Unit Board I B, CLOD upstream feeder bkr Compartment 8

SON RESTORING OFF-SITE POWER TO 690 0V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 Page5OoflO6 4.13 Restoring Off-Site Power to 6900V Shu tdown Board IA-A From Start Bus lB AND Unloading DIG IA-A (Continued)

ENSURE SI signal is RESET.

IF DIG emergency start signal has NOT been reset, THEN RESET D/G emergency start signal by perfo rming the following:

[69k V shutdown boar d room]

PLACE all DIG [43T(L)1 switches to TEST:

SHUTDOWN BOARD LOGIC PANEL TEST SWITCH IA-A 43T(L)

I B-B 43T(L) 2A-A 43T(L) 2B-B 43T(L)

VERIFY emergency start signal RESET by observing amb er lights lit:

SHUTDOWN BOARD LOGIC PANEL AMBER LIGHT LIT

-4 IA-A lB-B 2A-A 2B-B PLACE all DIG [43TLL)] switches to NOR:

SHUTDOWN BOARD LOGIC PANEL SWITCH NOR

-4 I A-A 43T(L) LW 1 B-B 43T(L) 2A-A 4T(L) LW 1

28-B 43T(L) EU

SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 1,2 Rev. 13 Page5loflO6 413 Restoring Off-Site Power to 6900V Shu tdown Board IA-A From Start Bus lB Unloading DIG IA-A (Continued) AND PERFORM the foflowing:

VERIFY DIG IA-A [86 LORI red light DAR K

[DIG lA-A Relay Boardi.

RESET D/G lA-A [86 LOR1 relay.

[D/G lA-A Relay Board].

2 PLACE 1O-HS-82-I8] DG IA-A Mode Selector switch c

to PARALLEL

9. PLACE [1 -HS-57-45] 6.9kV Unit Bd 18 Synchronize switch to SYN position.

LI

10. ADJUST 1O-HS-82-1 31 DG IA-A Spe ed Control switch UNTIL 1O-Xl-82-11 Synchroscope DG IA-A is rotating slowly in the FAST direction.

11. ENSURE [0-1-IS-82-121 DG lA-A Voltage Regulator inPULLPAUTO.

El

12. ADJUST DG iA-A VOLTAGE REGULATOR switch to match 1O-EI-82-51 DG IA-A Running Voltage and 1O-El 41 DG lA-A Incoming Voltage.

T SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS 12 Rev. 13 Page52of 106 413 Restoring Off-Site Power to 6900V Shutdown Boar d IA-A From Start Bus lB AND Unloading DIG IA-A (Continued)

CAUTION Dropping load too quickly OR failing to open DIG breaker promptly when DIG is unloaded may result in a reverse pow er condition.

NOTE Breaker 1718 switch should be operated so that brea ker closes at 12 oclock position, considering speed of rotation of synchroscope needle and delay time for breaker closu re.

13. WHEN the synchroscope needle approaches 12 Oclock position, THEN CLOSE 1171$1 6.9kV Unit Bd lB to SD Bd lA-A NOR supply USING [1-HS-57-441 [0-M-26A3.

14. ADJUST 10-HS-82-I 31 DG IA-A Speed Control swit ch UNTIL 1O-El-82-IOAI DG IA-A Megawatts indicates 500kW (0.5MW) or less.

LI

15. ADJUST 1O-HS-82-121 DG IA-A Voltage Regulator UNTIL FO-EI-8241A1 DG IA-A Megavars indicates near zero El

16. PLACE [I -HS-5746A] 191 2-DG IA-A To SD Bd lA-A switch to TRIP position.

LI

17. PLACE [1-HS-57-451 6.9kV Unit Bd lB Synchronize switch to OFF position.

SQN RESTORING OFF-SITE POWER TO 6900V EA-202-1 SHUTDOWN BOARDS Rev. 13 1,2 Page 53 of 106 4.13 Restoring Off-Site Power to 6900V Shutdown Board IA-A From Start Bus lB AND Unloading DIG 1AA (Continued)

18. CHECK Shutdown Board IA-A voltage between 6730V and 7240V.

19. RESET 6.9kV Shutdown Board lA-A blackout relays USING UV RLY BLACKOUT RESET pushbutton.

[Shutdown Board lA-A Logic Panel]

20. GO TO Section 4.1, step in effect. El END OF SECTION

SEQUOYAH NUCLEAR PLANT 1211 NRC SIMULATOR JPMH

SIM JPM H Page 2 of 15 ROISRO JOB PERFORMANCE MEASURE Task: Calibrate the Power Range Nuclear Instrumentation Task#: 0150050201 Task Standard: Examinee adjusts channels N-41 and N-43 of Power Range instrumentation (on its power range A drawer) gain to indicate within 100 +/- 0.5% without tripping due to a power range neutron flux rate trip.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X K!A ReferencelRatings: 015 A4.02 (3.9/3.9)

Method of Testing:

Simulated Performance: Actual Performance: X Evaluation Method:

Simulator X In-Plant Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 20 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

SIM JPM H Page 3 of 15 SPECIAL INSTRUCTIONS:

1. Ensure Simulator Operator Checklist is complete

2. ResettolCl6.

3. MANUALLY ADJUST N-41 and N-43 power to greater than 100.5 and less than 101.0%. ENSURE all other NIS reactor power indications are between 99.5 and 100.5%.

4. After making the adjustments to N-41 and N-43 log the potentiometer settings for each NI:

5. N41

6. N42

7. N43

8. N44

9. Lock the potentiometers for the for the power range gain potentiometers

10. Save as a temporary IC, if repeat runs of JPM will be desired.

11. PLACE SIMULATOR IN RUN

12. After JPM is complete, delete the temporary IC, if used.

ToolslEquipment!Procedures Needed:

References:

SIMJPMH Page 4 of 15 DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

INITIAL CONDITIONS:

1. Unit I is in MODE 1.

2. O-SI-OPS-092-078.O, Power Range Neutron Flux Channel Calibration By Heat Balance Comparison is in progress.

INITIATING CUES:

1. You have been directed to continue performance of O-SI-OPS-092-078.O, Power Range Neutron Flux Channel Calibration By Heat Balance Comparison starting at section 6.1 step 4.

2. Inform the SRO when complete and any necessary adjustments have been made.

SIM JPM H Page 5 of 15 Start Time STEP Obtain a copy of O-Sl-OPS-092-078.O, Power Range Neutron Flux I : SAT Channel Cahbration.

UNSAT Standard Examinee obtains O-Sl-OPS-092-078.O, Power Range Neutron Flux Channel Calibration.

Cue Provide a marked up copy of O-Sl-OPS-092-078.O, Power Range Neutron Flux Channel Calibration.

Corn rnent NOTE Data for an inoperable MS channel may be marked NIA.

STEP 2 : 141 RECORD as-found power level from each of the four NIS power range A channel drawers: SAT

__________

______

UNSAT POWER RANGE ASFOUND CHANNEL NIS POWER (%)

N-41 (Xl-.92-50058)

N-42 (Xl92-5OO6B)

N-43 (Xl-92-5007B)

N-44 (Xl-92-5008B)

Standard Examinee records NIS power range readings from the A channel drawers.

Comment

SIM JPM H Page 6 of 15 STEP 3 :

[51 COMPARE NIS indication with core thermal power level AND SAT CHECK appropriate box to indicate whether the indicated NIS power level recorded in step 6.1[4] is equal to the core thermal UNSAT power level recorded in step G1[3] or as listed on the printed copy to within +/- 2.0 percent:

Standard Examinee determines all NIS channels are within + 2% core thermal power level.

Comment STEP 4 : SAT

[6] VERIFY that all NIS channel indications are within

+/-3 percent of the determined core thermal power level.. UNSAT Standard Examinee determines all NIS channels are within + 3% core thermal power level Comment STEP 5 : SAT

[71 IF a NIS channel was more than 3 percent in error in the non-conservative direction (core thermal power> NIS), UNSAT THEN Standard: Examinee determines step is N/A.

Comment

SIM JPM H Page 7 of 15 STEP 6 (8] CHECK appropriate box to indicate whether the indicated NIS power level recorded in step 61[4]is less than or equal to SAT 10(15 percent:

UNSAT YES (1O(15%) NO (>1:005%) NIA NIS Channel N41 D C C NlSChannelN-42 C C C NIS Channel N-43 C C NIS Channel N-44 C C C STEP 7 : SAT 191 IF any NIS channels were inoperable during the performance of this Instruction, THEN UNSAT Standard: Examinee determines step is N/A.

Comment

SIM JPM H Page 8 of 15 NOTES

1) Consistency between the four NIS Power Range Channels is to be considered when determining if an adjustment is desired. Discretionary adjustments should not be made unless channels are widely divergent or approaching the acceptance criteria in Step 8.i[5] andlor Step 6.1[8].

2) The adjustment of any NIS channel that displays a value with an absolute difference of greater than 2% from core thermal power meets the requirement found in SR 4ai .i1

3) One or both of the bulleted steps below may be marked N/A dependent on specific circumstances.

STEP 8 : [1OJ IF NIS adjustment is desired 81ST NOT required, THEN SAT OBTAIN SRO approval to perform adjustment. UNSAT Standard: Examinee determines step is N/A.

Comment

. [1 1] IF any channel does not meet acceptance criteria STEP 9 SAT

. (Step 6.1[5] and/or Step 6 118]).

OR NIS Channel Adjustment is desired, THEN UNSAT

. PERFORM adjustment using Section 6.2 ANDIOR

. REDUCE reactor power not to exceed 100 percent.

Standard: Examinee determines NI Channel Adjustment is required for channels N-41 and N-43 and proceeds to section 6.2. CRITICAL Cue If asked provide the following cue, Reactor Power will NOT be

. reduced.

Comment

SIM JPM H Paqe 9 of 15 NOTES

1) Performance of this section is required only for those PR channels designated by the Reactor Operator or that did not satisfy the acceptance crileria in Section 61. All other NIS channels may be marked N/A.

2) During the performance of Section 62, data required for an inoperable NIS channel may be marked N/A.

STEP 10 : [1] IF calculated average power in Section 6.1 or on printed copy SAT differs by more than 3% from average RCS delta T, ThEN UNSAT Standard: Examinee determines step is N/A.

Comment STEP 11 : SAT 121 VERIFY reactor power has remained constant

(+/- 05 %) since performance of Section 61 UNSAT Standard Examinee verifies power constant by observing installed instrumentation.

Comment

SIM JPM H Page 10 of 15 NOTE The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels STEP 12 : SAT

[3J IF NIS power range channel is inoperable,

. .

THEN UNSAT Standard: Examinee determines step is N/A.

Comment STEP 13 : SAT

[41 ENSURE all NIS power range channels are operable or bypassed with no bistables tripped.

UNSAT Standard Examinee verifies power range channels operable by observing installed instrumentation.

Comment

SIM JPM H Page 11 of 15 STEP 14 [51 ENSURE rod control system is in MANUAL in accordance with I 0-SO 1. SAT 6.5 Transferring from Auto to Manual Rod Control UNSAT NOTES

1) A laminated copy of this section can be maintained in the Unit Control Room for repetitive use for routine rod manipulations.

2) Manual rod withdrawal is inhibited by any of the following signals:

A C-i, High Flux Intermediate Range Monitor B. C-2, High Flux Power Range Monitor C. C-3, Overtemperature Delta-T

0. C-4, Overpower Oelta-T

[11 PLACE 1HS45511O1, Rod Control Mode Selector in the MANUAL position 1st CV

[2] VERIFY Rod Speed Indicator ISI-4121. indicates 48 Steps/minute.

1St CV Comment

SIM JPM H Page 12 of 15 NOTES

1) Steps 6.26] through 6.2191 must be completed on one NIS channel before proceeding to the next channel.

2) N1S channels in the following step may be performed out of sequence.

[6J IF a rate thp exists (or occurs) on the NIS channel being STEP 15 calibrated, THEN SAT CLEAR that channels trip signal (momentarily set RATE UNSAT MODE switch to RESET position) and annunciator on panel XA-55-6Af NC-41U orN;C-41K NIS POWER RANGE HIGH NEUTRON RUX RATE before proceeding to the next NIS channel.

Thp Cleared N/A NIS Channel N-41 D C NIS Channel N-42 C C NIS Channel N-43 C C NIS Channel N-44 C C Examinee verifies NO rate trip signals are in on ANY of the PR and the Standard annunciator is clear.

CRITICAL PORTION: If rate trip is present the examinee resets the rate trip by momentarily setting the RATE MODE switch to RESET position prior to continuing to the next channel.

Comment

SIM JPM H Page 13 of 15 NOTE The gain potentiometers have latches which must be disengaged prior to adjustment, and re-engaged following adjustment

[TI,, ADJUST gain potentiometer on associated channel s power 7

STEP 16 range B drawer to bring that channeis indicated power level to SAT within +/-O5% of the calorimetric power recorded in Section 6.1 or as listed on the printed copy. AND UNSAT ENSURE gain potentiometer latch re-engaged. [C.2I, Adjustment N/A Required NIS Channel N-41 C C MS Channel N-42 C C NIS Channel N-43 C C NIS Channel N-44 C C Examiner Note The examinee may adjust channel is step 6.2.9 (JPM step 18)

Comment STEP 17 : [8] IF fine gain potentiometer on power range B drawer will NOT SAT provide enough adjustment to satisfy the calibration requirements of step UNSAT 6217] THEN Standard: Examinee determines the step is N/A.

Cue:

Comment

SIM JPM H Page 14 of 15

[10] WHEN NIS adjustments have been completed THEN STEP 19 SAT RECORD as-IeW power level from MS power range channels. UNSAT POWER RANGE AS-LEFT CHANNEL NIS POWER (%)

N-41 (Xl-92-50058)

N-42 (XI-92-50068)

N-43 (Xi-92-50078)

N-44 (Xl-92-50088)

Standard: Examinee records As-left values of power range Nis.

Corn rnent Terminating Provide the following cue, Another operator will complete the Cue: remaining steps of this procedure. STOP Stop Time

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

1. Unit us in MODEl.

2. O-SI-OPS-092-078.O, Power Range Neutron Flux Channel Calibration By Heat Balance Comparison is in progress.

INITIATING CUES:

1. You have been directed to continue performance of O-Sl-OPS-092-078.O, Power Range Neutron Flux Channel Calibration By Heat Balance Comparison starting at section 6.1 step 4.

2. Inform the SRO when complete and any necessary adjustments have been made.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

1-I 1At J[I SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-Sl-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 6 of 41 3.0 PRECAUTIONS AND LIMITATIONS

( . Reactor power must remain constant (+/- 0.5%) durin Sections 6.1 and 6.2. It is desirable for any requ g the performance of ired NIS adjustment be made promptly during performance of these sections.

Average RCS temperature (Tavg) should be main tained within 0.5°F of RCS reference temperature (Trej).

Caution should be exercised when adjusting NIS power range instrumentation to minimize the potential for a channel trip.

Only one NIS channel shall be adjusted at a time.

If a rate trip occurs, the channels trip signal and annunciator on panel XA-55-6A, NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RAT E must be cleared before proceeding to the next NIS channel.

Operations and Engineering should be notified if large r than normal channel adjustments (as determined by the SRO) are requ ired to bring the power range channels into alignment with calculated core therm al power. [CA] An operability concern may exist if excessive error in the non-conservative direction adversely impacts the NIS high flux trip setpoint. The 3% tolerance for calibration error on the high flux trip setpoints was selected using the extrapolated error from the 30% power level.

The reactor cores have been loaded with a low leaka ge loading pattern which can affect NIS Reactor Power level indication s such that differences greater than the Acceptance Criteria can occur betw een NIS and true power level. The impact of the NIS non-linearity due to low leakage loading pattern is in the conservative direction, since NIS indicated power rises faster than true power during a power increase. 0-GO-5 may direct perfo rmance of this procedure to ensure excessive errors in the non-conserva tive direction do not exist. During plant restarts, Reactor Engineering may perform 0-Pl-NUC-092-082.0 at 4% power to provide an initia l NIS correction for startup.

Technical Specifications require a heat balance calculation for adju stment of the NIS when the Plant is above 15% power withIn 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the Leading Edge Flow Meter (LEFM) is available, LEFM data (from U2118 or LEFM Offln e

Calorimetric screen) is required to be used for the heat balance when grea ter than 15% power (TRM 3.3.3.15). If LEFM is not available, then Loop zT data should be used between 15 and 40% power due to potential inaccuracies in the feedwater flow venturi heat balance below 40%. If LEFM is not available abov e

40%, then venturi-based calorimetric power (UI 118) should be used.

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 7 of 41 3.0 PRECAUTIONS AND LIMITATIONS (co ntinued)

() An Auxiliary Instrument Room Tem perature of approximately 90°F potentially impacts Computer Point Ui 118 accuracy with the DCS Digital Feedwater modification installed. The DCS inputs the Ui 118 venturi calculations and the accuracy of the card providing the input is adv ersely impacted by a card temperature of 95°F.

SON POWER RANGE NEUTRON FLUX Unit I & 2 O-S1-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 8 of 41 Unit______

4.0 PREREQUISITE ACTIONS E

During the performance of this Instruc tion, any IFITHEN statement may be marked N/A when the corresponding stated condition does not occ ur.

Preliminary Actions f1) ENSURE Instruction to be used is a copy of effective version and Data Package Cover Sheet is attached.

Measuring and Test Equipment, Parts, and Supplies None Field Preparations ENSURE reactor power and RCS averag e temperature are stable.

Approvals and Notifications NOTIFY SRO of test performance.

SON POWER RANGE NEUTRON FLUX Unit I & 2 0-Sl-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 9 of 41 5.0 ACCEPTANCE CRITERIA A. If the indicated as found power level from any operable NJS channel differs from core thermal power by greater than

+/-2%, then the affected channel shall be adjusted.

8. The indicated as-left power level from eac h operable MS neutron flux channel that was adjusted must equal the core thermal power level to within

+/-0.5%.

C. If the criteria stated above are NOT satisfie d, the SRO shall be notified and Action Requirement 2 of TS Table 3.3-1 sati sfied.

D. LEFM shall be used for the plant calorimetri c measurement for power range MS calibration by heat balance comparison

. If this criteria is NOT satisfied, the SRO shall be notified and the applicable acti on of TRM 3.3.3.15 shall be entered.

___

_

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-Sl-OPS-092-078.0 CHANNEL CAUBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 10 of 41 6.0 Unit

/

PERFORMANCE 6.1 As-Found Data

1) The following step determines if LEFM, s available to satisfy TRM 3.3.3.15. If LEFM is NOT available, operators should notify US

, document status and continue with next step.

2) Main feedwater temperature must be greater than or equal to 250°F for reliable LEFM data.

VERIFY availability of LEFM calorimetric pow er:

CHECK LEFM status NORMAL on ICS (NSSS and Current Calorimetric Data screen.

D No CHECK LEFM MFW header temperature (IC S point T502MA) greater than or equal to 250°F.

D No Acceptance Criteria: LEFM is available based upon the indications above.

I SQN Unit I & 2 POWER RANGE NEUTRON FLUX 0-Sl-OPS-092-078.0 j CHANNEL CALIBRATION BY HEAT Rev. 0023 L BALANCE COMPARISON Page 11 of 41 Unit 6.1 As-Found Data (continued)

With LEFM unavailable, AFD limit lines in COLR must be made more restrictive by I % and Rod Insertion Limit lines in COLR must be raise d by 3 steps. Rod insertion limit alarms and ICS display are NOT automatically adjusted.

IF LEFM calorimetric power NOT available OR ICS computer NOT available, THEN PERFORM the following:

[2.11 ENTER applicable action of TRM 3.3.3.15.

[2.2] ENSURE Service Request initiated as required.

[2.3] IF LEFM calorimetric power CANNOT be restored in time to complete this surveillance, THEN PERFORM the following:

If current reactor power reading is 3455 Mt, 98.7

% or reactor power will be 3411 MWt.

A. REDUCE reactor power to less than or equal to 98.7% of current power if plant is being maintained near 100% power USING one of the following:

U1118 (preferred)

NIS.

B. WHEN reactor power is less than 98.7%,

THEN CONTINUE this instruction using alternate power indications as specified below.

SQN POWER RANGE NEUTRON FLUX Unit I & 2 O-Sl-OPS-092-078M CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 12 of 41 Unit I 61 As-Found Data (continued)

E If Engineering has performed 0-Pl-SXX-00d022.

2, then the applicable section(s) of 0-PI-SXX000-022.2 may be used in place of App endix C or D to obtain the current calorimetric power.

DETERMINE reactor core power level by performin g the applicable appendix below:

CONDITION APPENDIX v

/

RCS T greater than 15% and LEFM core thermal A

power (U21 18) available (step [1] acceptance criteria met)

RCS tT between 15% and 40% and LEFM core B D thermal power (U21 18) NOT available RCS T greater than 40% C D LEFM core thermal power (U2118) NOT available but ICS point Ull 18 is available RCS \T greater than 40% and ICS computer D D NOT available RCS iT greater than 40% and ICS core thermal E C power indication (Ui 118 and U21 18) NOT available due to bad feedwater pressure input (ICS and LEFM feedwater flow data remain operable)

AND RECORD below (N/A power if using printout from ICS):

% Rated Core Thermal Power = f1 1%

j SON POWER RANGE NEUTRON FLUX Unit I & 2 O-SI-OPS-092-078.0 j CHANNEL CALIBRATION BY HEAT Rev. 0023 L BALANCE COMPARISON Page 13 of 41 Unit 1 6.1 As-Found Data (continued)

Data for an inoperable NIS channel may benark ed N/A.

RECORD as-found power level from each of the four NIS power range A channel drawers:

POWER RANGE AS-FOUND CHANNEL NIS POWER (%)

N-41 (Xl-92-50058)

N-42 (XI-92-5006B)

N-43 (XI-92-5007B)

N-44 (Xl-92-5008B)

[5) COMPARE NIS indication with core thermal power level AND CHECK appropriate box to indicate whether the indicated MS power level recorded in step 6.1[4j is equal to the core therm al power level recorded in step 6.1[31 or as listed on the printed copy to within +/- 2.0 percent:

YES (<2.0%) NO (2.0%) N/A NIS Channel N-41 C C C NIS Channel N-42 C C C NIS Channel N-43 LI C NlSChannelN-44 LI C C ROorSRO

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-SI-OPS-092-0780 CHANNEL CALIBRATION BY HEAT Rev. 0023

.

BALANCE COMPARISON Page 14 of 41 Unit______

6.1 AsFound Data (continued)

[6] VERIFY that all NIS channel indications are within

+/-3 percent of the determined core thermal power level.

DYes D No

[7] IF a NIS channel was more than 3 percen t in error in the non-conservative direction (core thermal pow er> NIS),

THEN NOTIFY Engineering to determine if the cali bration error impacts operability of the NIS high flux trip.

[8] CHECK appropriate box to indicate whether the indicated N1S power level recorded in step 6.1[4]is less than or equal to 100.5 percent.:

YES (100.5%) NO (>100.5%) N/A NIS Channel N-41 C C C NIS Channel N-42 C C C NIS Channel N-43 C C C NIS Channel N-44 C C RO or SRO

[9] IF any NIS channels were inoperable during the performanc e

of this Instruction, THEN NOTIFY applicable unit SRO that this SI must be performed on all inoperable NIS channels when they are returned to service.

SQN POWER RANGE NEUTRON FLUX Unit I & 2 O-SI-OPS-092-078.O CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 15 of 41 Unit______

6.1 As-Found Data (continued)

NOTES

1) Consistency between the four NIS Power Range Channels is to be considered when determining if an adjustment is desired. Dis cretionary adjustments should not be made unless channels are widely divergent or approaching the acceptance criteria in Step 6.1[5] and/or Step 6.1[81.

2) The adjustment of any NIS channel that disp lays a value with an absolute difference of greater than 2% from core thermal power mee ts the requirement found in SR 4.3.1.1.1.

3) One or both of the bulleted steps below may be marked N/A dependent on specific circumstances.

[10] IF NIS adjustment is desired BUT NOT require d, THEN OBTAIN SRO approval to perform adjustment.

[11] IF any channel does not meet acceptance criteria (Step 6.1[5] and/or Step 6.1[8j),

OR NIS Channel Adjustment is desired, THEN

PERFORM adjustment using Section 6.2 AND/OR

REDUCE reactor power not to exceed 100 percent.

END OF TEXT

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 16 of 41 Unit______

62 NIS Channel Adjustment NOTES

1) Performance of this section is required only for those PR channels designated by the Reactor Operator or that did not satisfy the acceptance criteria in Section 6.1. All other NIS channels may be marked N/A.

2) During the performance of Section 6.2, data required for an inoperable NIS channel may be marked N/A.

[1] IF calculated average power in Section 6.1 or on printed copy differs by more than 3% from average RCS delta T,

THEN NOTIFY Engineering to determine the cause.

[2] VERIFY reactor power has remained constant

(+/- 0.5 %) since performance of Section 6.1.

NOTE The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

[3] IF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to Bypass inoperable NIS channel in accordance with 0-PI-IXX092-001 .0.

[4] ENSURE all NIS power range channels are operable or bypassed with no bistables tripped.

[5] ENSURE rod control system is in MANUAL in accordance with 0-SO-85-1.

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-SI-OPS-092-078.O CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 17 of 41 Unit______

6.2 NIS Channel Adjustment (continued)

NOTES

1) Steps 6.2[6} through 6.2[9] must be completed on one NIS channel before proceeding to the next channel.

2) NIS channels in the following step may be performed out of sequence.

[61 IF a rate trip exists (or occurs) on the NIS channel being calibrated, THEN CLEAR that channels trip signal (momentarily set RAT E

MODE switch to RESET position) and annunciator on panel XA-55-6A, NC-41U or NC-41K NIS POWER RAN GE HIGH NEUTRON FLUX RATES before proceeding to the next NIS channel.

Trip Cleared N/A NIS Channel N-41 D NIS Channel N-42 D D NIS Channel N43 D D NIS Channel N-44 C C First Person Cv

SON POWER RANGE NEUTRON FLUX Unit I & 2 0-Sl-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 18 of 41 U nit______

6.2 NIS Channel Adjustment (continued)

NOTE The gain potentiometers have latches which mus t be disengaged prior to adjustment, and re-engaged following adjustment.

[7] ADJUST gain potentiometer on associated channels pow er range B drawer to bring that channels indicated power level to within +/-0.5% of the calorimetric power recorded in Sect ion 6.1 or as listed on the printed copy. AND ENSURE gain potentiometer latch re-engaged. [C.2]

Adjustment Required N/A NIS Channel N-41 C C NIS Channel N-42 C NIS Channel N-43 C C NlSChannelN-44 C C First Person Cv

j SQN POWER RANGE NEUTRON FLUX 0-Sl-OPS-092-07&0 1 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0023

[ BALANCE COMPARISON Page 19 of 41 Unit______

62 MS Channel Adjustment (continued)

[8) IF fine gain potentiometer on power range 8 dra wer will NOT provide enough adjustment to satisfy the cali bration requirements of step 62(7], THEN REQUEST Instrument Maintenance to adjust the coa rse gain (resistor R312, Coarse Level Adjust> inside the applicable power range drawer, AND READJUST fine gain potentiometer to achieve cali bration requirements specified in step 6.2(7].

Adjustment Required N/A NIS Channel N-41 D D NIS Channel N-42 C NIS Channel N-43 C C NIS Channel N-44 C C First Person CV

19) IF additional NIS channel(s) require calibration, THEN RETURN TO step 6.2(6].

r SON Unit I & 2 POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION BY HEAT 0-Sl-OPS-092-07&0 Rev. 0023 BALANCE COMPARISON Page 20 of 41 Unit______

62 NIS Channel Adjustment (continued)

(10) WHEN NIS adjustments have been com pleted, THEN RECORD as-left power level from NIS power range channels.

POWER RANGE ASLEFT CHANNEL NIS POWER (%)

N-41 (XI-92-5005B)

N-42 (Xl-92-5006B)

N-43 (Xl-92-5007B)

N-44 (Xl-92-5008B)

First Person lv

[11] iF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to remove Bypass on inoperable NIS channel in accordance with 0-PI-IXX-092-001 .0.

SQN POWER RANGE NEUTRON FLUX Unit I & 2 0-SI-OPS-092-078.0 CHANNEL CALIBRATION BY HEAT Rev. 0023 BALANCE COMPARISON Page 21 of 41 Unit______

6.2 NIS Channel Adjustment (continued)

[12] CHECK appropriate box to indicate whet her the foflowing asleft acceptance criteria were satisfied.

Acceptance Criteria: The indicated NIS power level recorded in step 6.2[10j is within +/- 0.5 percent the calorimet ric power level recorded in Section 6.1 or as liste d on the printed copy.

YES NO N/A NIS Channel N-41 C C C NIS Channel N-42 C C C NIS Channel N-43 C C C NIS Channel N-44 C C C RO or SRO

[13] IF acceptance criteria were NOT satisfied for any NIS channel, THEN NOTIFY Shift Manager that acceptance crite ria were NOT met and another performance of this test is nece ssary, subsequently action 2 of LCO 3.3.1.1 (Unit 1) or LCO 3.3.1 (Unit 2) must be satisfied if the other performan ce does not meet acceptance criteria.

NOTE NIS channel adjustment may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.

[14] RETURN Rod Control System to AUTO in accordance with 0-50-85-1.

END OF TEXT

SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1211 NRC PLANT JPMI

JPM Plant I Page 2 of 7 RO1SRO JOB PERFORMANCE MEASURE Task: Reset the TD AFW Pump Locally Task#: 0610080104 Task Standard: Manually engage the trip hook with the latch up lever and reset the mechanical trip for the Unit 2 TDAFW Pump.

Alternate Path: YES: X NO:

Time Critical Task: YES: NO: X KIA ReferencelRatings: 061 A2.05 (3.1/3.4)

Method of Testing:

Simulated Performance: X Actual Performance:

Evaluation Method:

Simulator In-Plant X Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 11 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

JPM Plant I Page 3of7 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step

2. Any UNSAT requires comments.

Tools/Equipment/Procedures Needed:

1. In-progress copy of EA-3.-5, LOCAL RESET OF TD AFW PUMP TRIP AND THROTTLE VALVE.

References:

Reference Title Rev No.

1. EA-3-5 LOCAL RESET OF TD AFW PUMP TRIP AND 38 THROTTLE VALVE READ TO OPERATOR HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

DIRECTIONS TO EXAMINEE:

I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM.

WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit2isinMODE3

2. The Turbine Driven Auxiliary Feed Pump has tripped due to mechanical overspeed.

3. EA-3-5, LOCAL RESET OF TD AFW PUMP TRIP AND THROTTLE VALVE has been completed through step 2.

INITIATING CUES:

1. You have been directed to locally reset the Turbine Driven Auxiliary Feed using EA-3-5, LOCAL RESET OF TD AFW PUMP TRIP AND THROTTLE VALVE starting at step 3.

2. Inform the SRO when complete.

JPM Plant I Page 4 of 7 Start Time STEP 1 : 4.2 Local Reset otTO AFW Pump Thp and Throttle Valve FCV-1-51 SAT 1 OBTAiN handbekl hghting, radios, and goves. UNSAT

2. OBTAIN the following keys: gIass-faced box in 0CC]

. Vital Area key

Protected Area key Standard: Examinee proceeds to the Unit 2 TD AFW PUMP room Upon entry into the TD Aux Feed Pump Room, the examiner will provide Cue the Operator a copy of DRAWING I showing 2-FCV-1-51 latch lever

. disengaged with the trip hook and the overspeed trip mechanism in the TRIPPED condition.

Comment STEP 2 : a ENSURE TD AEW pump trip and throttle valve [FCV-1511 mechanical SAT overspeed mechanism LATCHED.

[Aux Bldg. elev 1 UNSAT

. REFER TO placard displayed on the TO AFW pump room wall or Appendix A for instnictions on latching the mechanical overspeed meChanism.

Standard: Examinee verifies the TD AFW overspeed trip has actuated Examiner The directions for resetting the TD AFW pump are located on the Note Controlled Operator Information Plaque posted on the TD AFW pump room wall.

Comment

JPM Plant I Page 5 of 7 STEP Run the operator to the CLOSE position for 10 seconds.

3 : SAT U N SAT Standard Examinee simulates attempting to close the Trip and Throttle Valve Operator by depressing CLOSE on pushbutton 2-HS-51 B.

After the examinee simulates depressing CLOSE pushbutton 2-HS-Cue: 51B, provide the following cue Both green and red light are OFF, there is NO movement on FCV-1-51.

Comment STEP 4 : Alternate path SAT Manually run down FCV-1-51 to engage the trip hook with the latch UNSAT lever.

..

CAdI1JI[1 IIF1UIdL iiyyiiiy L FTIFIUdI UluLcil iV1 dIlU ,UF1,IiII Standard: down the Trip and Throffle Valve Operator by turning 2-FCV-1 -51 HW CRITICAL in the CW direction After the examinee simulates engaging the manual clutch lever and Cue running down the Trip and Throttle Valve Operator by turning 2-FCV-1-51 in the CW direction provide the Operator a copy of DRAWING 2 showing 2-FCV-1-51 latch up lever engaged with the trip hook.

Comment

JPM Plant I Page 6 of 7 STEP 5 : Alternate path SAT Manually latch the mechanical overspeed trip device.

UNSAT Examinee resets the AFW turbine overspeed trip mechanism by simulating the following.

1. PULL emergency connecting rod the left.

2. RAISE manual trip lever to horizontal position. CRITICAL

3. RELEASE connecting rod.

4. RELEASE manual trip lever

5. VERIFY trip lever remains in horizontal position.

After the Operator successfully simulates latching and resetting the TD Cue AFW Pump overspeed trip mechanism, the examiner will provide the Operator a copy of DRAWING 3 showing 2-FCV-1 -51 overspeed trip mechanism in the RESET condition.

Comment Examiner Only items one and two of this standard are critical, all other items are Note NOT critical.

Terminating Provide the following cue Another operator will perform the Cue: remaining steps of this procedure. STOP Stop Time

JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:

All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit2isinMODE3

2. The Turbine Driven Auxiliary Feed Pump has tripped due to mechanical overspeed.

3. EA-3-5, LOCAL RESET OF TD AFW PUMP TRIP AND THROTTLE VALVE has been completed through step 2.

INITIATING CUES:

1. You have been directed to locally reset the Turbine Driven Auxiliary Feed using EA-3-5, LOCAL RESET OF TD AFW PUMP TRIP AND THROTTLE VALVE starting at step 3.

2. Inform the SRO when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

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SEQUOYAH NUCLEAR PLANT 1211 NRC PLANT JPMJ

PLANT JPM J Page 2 of 8 ROISRO JOB PERFORMANCE MEASURE Task: OPERATE PCV-1-12.

Task#: 0000680501 Task Standard: Examinee establishes local control of PCV-1-12.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X K/A Reference/Ratings: APE 068 AA1 01 (4.3/4.5)

Method of Testing:

Simulated Performance: X Actual Performance:

Evaluation Method:

Simulator In-Plant X Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: /

Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 15 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

PLANT JPM J Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.

2. Any UNSAT requires comments.

ToolslEquipmentlProcedures Needed:

1. AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM Appendix K.1

References:

I Reference Title Rev No.

I AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL 26 L ROOM READ TO EXAMINEE HAND JPM BRIEFING SHEET TO EXAM INEE AT THIS TIME!

DIRECTIONS TO EXAMINEE:

I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 3.

2. AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, is in progress.

INITIATING CUES:

1. The Examinee in the ACR has directed you to take local control of PCV-1-12 (SIG #2) using AOP C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1 starting at step 5.

2. Inform the Examinee in the ACR when complete.

PLANT JPM J Page 4 of 8 Start Time STEP Obtain a copy of AOP-C.04, SHUTDOWN FROM AUXILIARY 1 SAT CONTROL ROOM, Appendix K.1.

UNSAT Standard Examinee obtains a copy of AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1.

Cue Provide an in-progress copy of AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1.

Comment NOTE I Unit I has local control stations in 480V Shutdown Board rooms for operation of SIG #2 and 3 atmospheric reliefs.

NOTE 2 Due to differential pressure across valve, unseating S1G #2 atmospheric relief valve is expected to require -i 5 to 25 p:sig air pressure to valve diaphragm (on outlet pressure indi:calor 1-Pl-i1 2B). After valve is unseated, outlet air pressure of -5 to 55 psig corresponds to 0 to 10.0%

valve opening.

NOTE 3 At minimum SBO air bottle pressure (800 psig), sufficient air supply is available for five full strokes (closed to open) of atmospheric relief.

Valve strokes should be minimized to conserve air supply

5. WHEN directed to operate S/G #2 atmospheric relief valve (1 -PCV-1 .1 2),

ThEN SAT PERFORM the following at emergency control station:

[480V Shutdown Sd Room IA 1, south wall] UN SAT

a. CLOSE ii -VTIV1 -129, Vent Valve.

If asked provide the following cue, Valve turns CW 90 degrees, no further movement noted

PLANT JPM J

5. WHEN directed to operate S/G #2 atmospheric relief valve (1.-PCV-1-12),

THEN SAT PERFORM the following at emergency control station:

1480V Shutdown Rd Room IAI, south wall] UN SAT b ENSURE [1 -PREG-1 -121 Pressure Regulator, is adjusted fully counterclockwise (lower direction)

If asked provide the following cue, Regulator turns CCW several turns until no further movement noted.

STEP 5. WHEN directed to operate S/G #2 atmospheric relief valve (i-PCV-.i-12),

4 SAT THEN PERFORM the following at emergency control station:

[480V Shutdown Rd Room 1A1, south wall] UN SAT

c. OPEN [1-lSlV42-19]. SBOfApp R HP Air Cyl Iso) Valve If asked provide the following cue, Valve turns CCW 90 degrees, no Cue further movement noted.

Comment

PLANT JPM J Page 6 of 8 STEP . 5. WHEN directed to operate SIG #2 atmospheric relief valve (l-PCV-i-12),

THEN SAT PERFORM the following at emergency control station.

1480V Shutdown Rd Room 1AI, south wall] UNSAT

d. OPEN [1-ISIV-32-1969K1, Isolation Valve.

Examinee simulates placing the handle for 1-lSlV-32-1969K, Standard: CRITICAL If asked provide the following cue, Valve turns CCW 90 degrees, no Cue further movement noted Comment STEP 5. WHEN directed to operate SIG #2 atmospheric relief valve (1-PCV-1-12),

6 THEN SAT PERFORM the following at emergency control station:

[480V Shutdown 3d Room IAI, south wall] UNSAT

e. OPEN [1-ISIV-l-12G], Isolation Valve.

If asked provide the following cue, Valve turns CCW 90 degrees, no Cue further movement noted.

Cue If pressure indicator is observed, 1-PI-1-12D is showing no pressure rise.

Comment

PLANTJPMJ Page 7 of 8 STEP 5 WHEN directed to operate S/G #2 atmospheric relief valve (1-PCV-1-12),

7 THEN SAT PERFORM the following at emergency control station:

(480V Shutdown Bd Room 1A1, south wall UNSAT

f. ADJUST 11PREG-1 -121, Pressure Regulator slowly in clockwise direction to throttle open 1 -PCV- -12 as drected by ACR.

Examinee simulates placing the handwheel for (1-PREG-1-12],

Standar& CRITICAL Pressure Regulator, slowly in clockwise direction.

Provide the following cue The ACR directs you to SLOWLY OPEN 1-PCV-1-12 until I direct you to stop.

When the Examinee has simulated opening 1-PCV-12, provide the following cue, ACR Examinee has directed you to maintain 1-PCV-12 in the current position.

Terminating Provide the following cue, another Examinee will complete the Cue: remaining steps of this procedure. STOP Stop Time

JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:

All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is in MODE 3.

2. AOP-C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, is in progress.

INITIATING CUES:

1. The Examinee in the ACR has directed you to take local control of PCV-1-12 (SIG #2) using AOP C.04, SHUTDOWN FROM AUXILIARY CONTROL ROOM, Appendix K.1 starting at step 5.

2. Inform the Examinee in the ACR when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

I J-&) 5 irz/r1Z E

[ SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-C.04 Rev. 26 Page 1 of 4 APPENDIX K.1 LOCAL OPERATION OF UNIT I SIG ATMOSPHERIC RELIEFS RCS cooldown using S/G atmospheric reliefs must be initiated within 60 minutes. Time starts from when any entry condition for AOP-C.04 was met.

çj) OBTAIN flashlight. [AOP-C.04 cabnet]

Valve wrench may be needed to throttle open atmospheric reliefs.

Cheater for Unit 1 ARVs is stored in AOP-C.04 cabinet in 6.9 Shutdown Board Room A.

OBTAIN valve wrench.

ESTABLISH communications with ACR (radio or x6359 or x6170).

ElY Turning dog handwheel clockwise opens SIG atmospheric relief.

Turning dog handwheel counterclockwise allows valve to close.

PCV-1-5 (SIG #1) and PCV-123 (S/G #3) fail closed on loss of Train A essential air.

PCV1-12 (SIG #2) and PCV1-3O (SIG #4) fail closed on loss of Train B essential air.

4. WHEN directed to operate SIG #1 or 4 atmospheric reliefs, THEN OPERATE dog handwheel(s) to throttle open valves as directed by ACR:

S!G UNID DOG HANDWHEEL LOCATION THROTTLED

1 1PCV.1-.5 480V Shutdown Board Rm 1AI (2B1),

Aux Bldg el. 734

4 1-PCV-1-30 480V Shutdown Board Rm 1A2 (282),

Aux Bldg el. 734 Page 78 of 197

SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-C.04 Rev. 26 Page 2 of 4 APPENDIX K1 Unit 1 has local control stations in 480V Shutdown Board rooms fr for operation of SIG #2 and 3 atmospheric reliefs.

Ni)2 Due to differential pressure across valve, unseating SIG #2 atmospheric relief valve is expected to require -15 to 25 psig air pressure to valve diaphragm (on outlet pressure indicator 1-Pl-1-12B). After valve is unseated, outlet air pressure of 5 to 55 psig corresponds to 0 to 100%

valve opening.

NØI At minimum SBO air bottle pressure (800 psig), sufficient air supply is available for five full strokes (closed to open) of atmospheric relief.

Valve strokes should be minimized to conserve air supply.

WHEN directed to operate SIG #2 atmospheric relief valve (1 -PCV-1 -12),

THEN PERFORM the following at emergency control station:

[480V Shutdown Bd Room 1A1, south wall)

a. CLOSE [1-VTIV-1-12F], Vent Valve.

[1

b. ENSURE [1-PREG-1-121, Pressure Regulator, is adjusted fully counterclockwise (lower direction).

c. OPEN Ij-ISIV-32-1969M1, SBO/App. R HP Air Cyl lsol Valve. LI

d. OPEN 11 -ISIV-32-1 9691(1, Isolation Valve. [I

e. OPEN [1-ISIV-1-12G1, Isolation Valve. LI

f. ADJUST 11-PREG-1-1Z1, Pressure Regulator, slowly in clockwise direction to throttle open 1-PCV-1-12 as directed by ACR.

g. OPERATE [iPREG-1 -121 to control 1-PCV--1-12 as directed by ACR.

Page 79 of 197

SON SHUTDOWN FROM AUXILIARY CONTROL ROOM I AOP-C.04 Rev.26 Page 3 of 4 APPENDIX K.1 NOTE I Due to differential pressure across valve, unseating S/G #3 atmospheric relief valve is expected to require 15 to 25 psig air pressure to valve diaphragm (on outlet pressure indicator 1-Pl-.123B). After valve is unseated, outlet air pressure of 5 to 55 psig corresponds to 0 to 100%

valve opening.

NOTE 2 At minimum SBO air bottle pressure (800 psig), sufficient air supply is available for five full strokes (closed to open) of atmospheric relief.

Valve strokes should be minimized to conserve air supply.

6. WHEN directed to operate SIG #3 atmospheric relief (1-PCV1-23),

THEN PERFORM the following at emergency control station:

[480V Shutdown Sd Room 1A2, north wall]

a. CLOSE [1-VTIV-I-f1, Vent Valve.

[1

b. ENSURE fj-PREG-I-231, Pressure Regulator, is adjusted fully counterclockwise (lower direction).

LI

c. OPEN [I-ISV-32-1950M1, SBOIApp. R HP Air Cyl lsol Valve.

d. OPEN [I-ISIV-32-1950K], Isolation Valve.

e. OPEN [I-ISIV-I-23G1, Isolation Valve.

f. ADJUST 1I-PREG-I-231, Pressure Regulator, slowly in clockwise direction to throttle open 1-PCV-1-23 as directed by ACR. LI

g. OPERATE 1I-PREG-I-23] to control 1-PCV-1--23 as directed by ACR. Li Page 80 of 197

SON SHUTDOWN FROM AUXILIARY CONTROL ROOM AOP-C.04 R 26 Page 4 of 4 APPENDIX K.1 NOTE Operator should remain on station until relieved or until ACR deter mines that continuous manning of atmospheric reliefs is no longer needed.

7. NOTIFY ACR of actions taken (radio or x6359 or x6170).

NOTE Steps 8 and 9 are long-term contingency actions which are NOT part of the time critical actions.

8. IF SBO air cylinder supply to SIG #2 atmospheric relief is depleted OR cylinder regulator fails, THEN PERFORM the following:

a. CLOSE fj-ISV-32-1969J1 air cylinder isolation valve.

[AG el. 714, U-I Fan Room, against airlock wall]

El

b. OPEN 11-ISIV-32-1969L1 cross-tie valve to align 1-CYL-32-1 950 to provide air to I-PCV-i-12. [AG el. 714, U-i Fan Room, east wall] El

9. IF SBO air cylinder supply to SIG #3 atmospheric relief is depleted OR cylinder regulator fails, THEN PERFORM the following:

a. CLOSE 11-)SV-32-1950J1 air cylinder isolation valve.

[AG el. 714, U-I Fan Room, against airlock wall] El

b. OPEN f1-ISIV-32-1969L1 cross-tie valve to align 1-CYL-32-1969 to provide air to 1-PCV-1-23. [AG el. 714, U-i Fan Room, east wall]

END OF TEXT Page 81 of 197

SEQUOYAH NUCLEAR PLANT 1211 NRC PLANT JPMK

_____

PLANT JPM K Page 2 of 8 ROISRO JOB PERFORMANCE MEASURE Task: Respond to a loss of all AC power, reset the 1AA EDG Overspeed Trip.

Task#: 0000860501 Task Standard: Examinee resets the lA-A EDG Overspeed Trip device and resets the DIG Lockout Reset using 0-AR-DG-1A-LCL.

Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA ReferencelRatings: EPE 055 EA2.03 (3.9/4.7)

Method of Testing:

Simulated Performance: X Actual Performance:

Evaluation Method:

Simulator In-Plant X Classroom Main Control Room Mock-up Performer:

Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:

Validation Time: 10 mm Total Time:

Performance Time: Start Time: Finish Time:

COMMENTS

PLANT JPM K Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:

1. SM approval will be required to enter the Trip Hazard Zone in backup control room.

2. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.

3. Any UNSAT requires comments.

ToolslEquipmentiProcedures Needed:

1. O-AR-DG-1A-LCL, DIESEL GENERATOR IA-A LOCAL PANEL

References:

Reference Title Rev No.

O-AR-DG-1A-LCL DIESEL GENERATOR lA-A LOCAL PANEL 16 READ TO EXAMINEE HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

DIRECTIONS TO EXAMINEE:

I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I will provide initiating cues and indicate any steps to be discussed.

When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Units 1 and 2 are in MODE 3 following a major grid disturbance.

2. The Unit 1 Control Room has experienced a loss of all AC.

3. The Both Engines for the lA-A EDG have tripped due to overspeed.

4. Maintenance has addressed and corrected the cause of the overspeed trip.

INITIATING CUES:

1. You have been directed to proceed to lA-A EDG room and reset both overspeed trip levers for the IA-A EDG engine #1 and engine #2 using O-AR-DG-1A-LCL, DIESEL GENERATOR lA-A LOCAL PANEL.

2. Inform the US when complete.

PLANT JPM K Page 4 of 8 Start Time STEP Obtain a copy of O-AR-DG-IA-LCL, DIESEL GENERATOR lA-A LOCAL 1

.

PANEL AT U N SAT Standard Examinee obtains a copy of O-AR-DG-1A-LCL, DIESEL GENERATOR lA-A LOCAL PANEL Cue Provide a copy of O-AR-DG-1A-LCL, DIESEL GENERATOR lA-A LOCAL PANEL page 11 for window B-2.

Comment r

v OVERSPEED TRIP ENSURE automatic shutdown of DIG STEP 2 : SAT

[2j INSPECT DIG for mechanical damage.

131 COORDINATE with Maintenance Suppoil to determine cause of U N SAT overspeed trip Standard: Examinee addresses the procedure steps.

Cue: If asked provide the following cue, The RED B-2 and B-5 lights are Examiner The procedure step completion was implied during the Initial Note: Conditions and Initiating Cues.

Comment

PLANT JPM K Page 5 of 8

[4) WHEN overspeed trip is to be reset, THEN STEP 3 RESET OTS :Qjy by moving reset lever counterclockwise from SAT TRIP position to LATCHED position. AND UN SAT When the Examinee observes the engine reset lever prior to resetting provide the following cue, Reset lever is not engaged with the limit switch.

When the Examinee simulates positioning the engine reset lever Cue: counterclockwise from TRIP to LATCHED provide the following cue, Reset lever moved smoothly CCW and is now latched.

Comment Examiner Note The Examinee may reset the overspeed trip for either engine first.

141 WHEN oveispeed trip is to be reset. THEN STEP 4 . DEPRESS IHS-82-281. DIG Lockout Reset. SAT UNSAT Standard: Examinee attempts to reset HS-82-28 DIG Lockout Reset.

When the Examinee simulates depressing reset HS-82-28 D/G Cue: Lockout Reset, provide the following cue, Engine #2 OS trip light is OFF Comment

PLANT JPM K Page 6 of 8 41 WHEN overspeed trip is to be reset. THEN STEP 5 : RESET QT locally by moving reset lever counterclockwise from SAT TRIP positioi to LATCHED position, AND U N SAT a r_

When the Examinee observes the engine reset lever prior to resetting provide the following cue, Reset lever is not engaged with the limit switch.

When the Examinee simulates positioning the engine reset lever Cue: counterclockwise from TRIP to LATCHED provide the following cue, Reset lever moved smoothly CCW and is now latched.

Comment Examiner The Examinee may reset the overspeed trip for either engine second Note but must reset both engine reset levers to successfully achieve the task standard.

WHEN overspeed trip is to be reset. THEN STE P 6 SAT DEPRESS EHS2-28j. D/G Lockout Reset.

U N SAT Cue: Provide the following cue, Both overspeed trip alarms are clear.

Comment

JPM BRIEFING SHEET DIRECTIONS TO EXAMINEE:

All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. You will be provided initiating cues and indicate any steps to be discussed. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Units 1 and 2 are in MODE 3 following a major grid disturbance.

2. The Unit 1 Control Room has experienced a loss of all AC

3. The Both Engines for the IA-A EDG have tripped due to overspeed.

4. Maintenance has addressed and corrected the cause of the overspeed trip.

INITIATING CUES:

1. You have been directed to proceed to lA-A EDG room and reset both overspeed trip levers for the lA-A EDG engine #1 and engine #2 using O-AR-DG-1A-LCL, DIESEL GENERATOR IA-A LOCAL PANEL.

2. Inform the US when complete.

Acknowledge to the examiner when you are ready to begin.

HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

ML13275A055

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