ML12166A089

Initial Exam 2011-302 Draft Sim_IN-Plant JPMs

ML12166A089
Person / Time
Site:	Turkey Point
Issue date:	06/14/2012
From:	Division of Reactor Safety II
To:	Florida Power & Light Co
References
50-250/11-302, 50-251/11-302
Download: ML12166A089 (246)

Text

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Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01028016300 JPM: Recover Misaligned Task

Title:

Control Rod JPM No: 01028016303 K/A

Reference:

001 A2.03 RO 3.5 SRO 4.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• While raising power to 100%, a rod misalignment is discovered.

• Reactor Power is 50% and stable

• There has been no rod motion within the last 20 minutes.

• RCC Control Bank D is at 165 steps withdrawn, with the RPI for Control Rod M8 indicating 145 steps.

• The movable gripper fuse for Control Rod M8 has blown.

Initiating Cue:

• The moveable gripper fuse has been replaced.

• The US direct you to align Control Rod M8 using 3-ONOP-028.1, starting at Step 5.9.1.

2011 NRC Exam (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of II Form ES-C-I Task Standard:

• The operator will recover Control Rod M8 and return to required bank alignment.

Required Materials:

• 3-ONOP-028. 1, RCC Misalignment

• Key to Rod Disconnect Switch Cabinet General

References:

• Technical Specifications Time Critical Task: No Validation Time: 20 minutes 2011 NRC(RO)JPM-a NUREG 1021 Rev9AppendixC

I Appendix C Page 3 of II Form ES-C-I SIMULATOR SETUP

1. ResettolCl9l orequivalentiC.

2. Place simulator in RUN.

3. Place Rod Selector in Manual.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place simulator in FREEZE.

6. Provide a copy of 3-ONOP-028.1, RCC Misalignment, marked-up through Step 5.8.3.

7. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of II Form ES-C-I Denote critical steps with a check mark (1) Start Time Obtain 3-ONOP-028. 1, RCC Misalignment.

SAT STEP I UNSAT STANDARD Applicant obtains 3-ONOP-028.1, RCC Misalignment.

CUE Provide Applicant with a copy of 3-ONOP-028.l, RCC Misalignment.

COMMENT Obtain permission from the Reactor Engineering Supervisor or designee. SAT STEP 2 UNSAT (3-ONOP-028.1 Step 5.9.1)

STANDARD Applicant obtains permission from Reactor Engineering and the Shift Manager to align the RCC to its associated bank.

Inform the applicant that the Reactor Engineering Supervisor CUE and the Shift Manager have granted permission to realign Control Rod M8.

COMMENT 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of II Form ES-C-I IF reactor power has been reduced as per Technical Specification 3.1.3.6, THEN do not increase power until the SAT RCCs has been realigned. UNSAT STEP 3 (3-ONOP-028.1 Step 5.9.2)

STANDARD Applicant determines that Reactor Power has not been reduced perT.S. 3.1.3.6.

CUE COMMENT Position the Rod Motion Control Selector switch to the RCC STEP 4 bank which has the misaligned RCC. SAT UNSAT (3-ONOP-028.1 Step 5.9.3)

STANDARD Applicant rotates the Rod Motion Control Selector switch in the clockwise direction to the CBD position.

CUE COMMENT 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of II Form ES-C-I Place all the lift coil disconnect switches for the misaligned rod bank to the disconnect position (toggle switch down) EXCEPT SAT STEP 5 the misaligned RCC switch which is left in the connect position UNSAT (toggle switch up).

(3-ONOP-028.1 Step 5.9.4)

Applicant obtains the key to the Lift Coil Disconnect Box from the SM/US/ES.

STANDARD Applicant then places the lift disconnect switches for Bank D to the disconnect position (down), EXCEPT for RCC M8.

CUE COMMENT Record the step position for the misaligned RCC group demand step counter in the Unit Narrative Log as follows: SAT UNSAT

1. Bank STEP6 2. Group

3. Position steps (3-ONOP-028.1 Step 5.9.5)

Applicant records the information as follows:

1. Bank D STANDARD 2. Group 1

3. Position steps 165 EVALUATOR CUE:

CUE US records supplied information in the Unit Narrative Log.

COMMENT 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of II Form ES-C-I Manually set the associated group demand step counter to the STEP 7 position the misaligned RCC is determined to be in. SAT UNSAT (3-ONOP-028.1 Step 5.9.6)

STANDARD Applicant depresses the middle pushbutton on BANK D, GROUP 1 step counter to set the counter to 145 steps.

CUE COMMENT EVALUATOR NOTE:

There are three pushbuttons on the Group Step Demand Counters.

NOTE UPPER: Raises indication MIDDLE: Lowers indication LOWER: Resets indication to ZERO (0) 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of II Form ES-C-I IF the misaligned RCC is in a control bank, THEN reset the bank demand step counters from the DCS as follows: SAT UNSAT

1. Navigate to the RPI BANK DEMAND ALIGNMENT screen.

2. Select INITIATE ALIGNMENT for the affected control bank.

STEP 8 3. Select NEW VALUE in the overlay.

4. Type in the desired bank demand step value, using the keyboard.

5. Press ENTER.

6. Select INITIATE RE ALIGNMENT in the overlay.

7. Select YES in the save changes overlay.

8. Select CLOSE OVERLAY.

(3-ONOP-028.1 Step 5.9.7)

Applicant determines that RCC M8 is in a control bank and proceeds as follows:

1. Navigates to the RPI BANK DEMAND ALIGNMENT screen.

2. Selects INITIATE ALIGNMENT for the affected control bank.

STANDARD

3. Selects NEW VALUE in the overlay.

4. Type in 145 steps, using the keyboard.

5. Presses Enter.

6. Selects INITIATE RE ALIGNMENT in the overlay.

7. Selects YES in the save changes overlay.

8. Selects CLOSE CUE COMMENT 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 11 Form ES-C-CAUTION Failure to follow instructions provided by the Reactor Engineering Supervisor could affect fuel integrity caused by power peaking.

NOTE I NOTE Annunciator B9/4. ROD CONTROL URGENT FAILURE, and the RCC power cabinet URGENT FAILURE will alarm for the group with the lift coils disconnected.

Place the Rod Motion Lever to the IN/OUT position, as applicable. SAT STEP 9 UNSAT (3-ONOP-028.1 Step 5.9.8.1)

Applicant places the Rod Motion Lever in the OUT position, STANDARD withdraws Control Rod M8 to match the rest of Control Bank D (165 Steps).

BOOTH OPERATOR CUE:

Tell the operator the Reactor Engineering Supervisors directions are to borate as required to maintain Tavg within 1°F of Tref.

BOOTH OPERATOR CUE:

CUE If asked, as Rx Engineering, tell operator that rod withdrawal rate should be 1015 steps per minute (per Step 5.9.8.3).

TERMINATING CUE:

Evaluator informs Applicant that another operator will complete the remaining steps of this procedure. This completes the JPM.

COMMENT EVALUATOR NOTE:

NOTE Annunciator SHUTDOWN ROD OFF TOP DEVIATION (B 9/3) may actuate and Applicant may explain that this is due to CAUSE #2.

Stop Time 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of II Form ES-C-I Verification of Completion:

Job Performance Measure No. 01028016303 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET

[will explain the initial condftioris, which steps te slriiuIte or discuss, M 5rOvide [nitiating cues. -

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

Initial Conditions:

• While raising power to 100%, a rod misalignment is discovered.

• Reactor Power is 50% and stable

• There has been no rod motion within the last 20 minutes.

• RCC Control Bank D is at 165 steps withdrawn, with the RPI for Control Rod M8 indicating 145 steps.

o The movable gripper fuse for Control Rod M8 has blown.

Initiating Cue:

• The moveable gripper fuse has been replaced.

• The US direct you to align Control Rod M8 using 3-ONOP-028.1, starting at Step 5.9.1.

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.

2011 NRC Exam (RO) JPM-a NUREG 1021 Rev 9 Appendix C

Florida Power & Light Company Turkey Point Nuclear Plant Unit 3

Title:

RCC Misalignment (Continuous Use)

Safety Related Procedure Responsible Department: Operations Revision Number: 1 Issue Date: 10/27/10 Revision Approval Date: 8/2/10 PCRs 08-1972, 09-0987, 10-0929 PC/Ms92-031, 93-005, 01-0796P,09-006 W97/JWB/emc/cls/nw n }

LIST OF EFFECTWE PAGES (Rev. 1)

Revision Date 1 08/02/10 2 08/02/10 3 04/07/09 4 04/07/09 5 04/07/09 6 04/07/09 7 04/07/09 8 04/07/09 9 08/02/10 10 04/07/09 11 04/07/09 12 08/02/10 13 04/07/0 9 AIO7!

TABLE OF CONTENTS Section 1.0 PURPOSE 4 2.0 SYMPTOMS 4 3.0 AUTOMATIC ACTIONS 5 4.0 IMMEDIATE ACTIONS 5 5.0 SUBSEQUENT ACTIONS 6

6.0 REFERENCES

/RECORDS REQUIRED!

COMMITMENT DOCUMENTS 12 ENCLOSURE Enclosure 1 Accident Analyses Requiring Re-Evaluation in the Event of an Inoperable RCC 13 AI71 IAIIII-I.,i.,.,

Procedure No.: Procedure

Title:

Page:

. Approva[Date:

3-ONOP-028.1 RCC Misalignment 4/7/09 1.0 PURPOSE 1.1 This procedure provides instructions to be followed in the event one or more RCC is misaligned with the associated bank. This procedure is also initially used for an RCC position indication malfunction to verify the RCCs are aligned with the associated bank.

2.0 SYMPTOMS 2.1 Power range nuclear instrumentation variation of greater than 3 percent difference between any two detectors at the same elevation.

2.2 Axial flux difference indicators difference of 3 percent between any two channels.

2.3 Significant axial power shape difference from symmetric assemblies, as determined by the Reactor Engineering Supervisor.

=

After RCC motion, one hour is provided to allow time for thermal soak, so that proper RCC indication is obtained.

I 2.4 With no RCC motion within the last hour, an individual RPI indicates greater than the Allowed Rod Misalignment of Technical Specification 3.1.3.1.

2.5 Difference of greater than 2 steps between group step counters in the same bank.

2.6 Core exit thermocouple difference of 10°F relative to symmetric thermocouples.

2.7 Nuclear Instrumentation Detector Current Comparator Drawer UPPER SECTION DEVIATION or LOWER SECTION DEVIATION light on above 50 percent power.

2.8 Nuclear Instrumentation Comparator and Rate Drawer CHANNEL DEVIATION Light on.

2.9 Annunciators 2.9.1 B 2/2, POWER RANGE UPPER DET HI FLUX DEV/AUTO DEFEAT (Normally lit less than 50 percent power) 2.9.2 B 2/3, POWER RANGE LOWER DET HI FLUX DEV/AUTO DEFEAT (Normally lit less than 50 percent power) 2.9.3 B 6/4, POWER RANGE CHANNEL DEVIATION 2.9.4 B 9/2, AXIAL FLUX TILT 2.9.5 B 9/3, SHUTDOWN ROD OFF TOP/DEVIATION 3.0 AUTOMATIC ACTIONS 3.1 IF the axial flux difference exceeds +2 percent, THEN the OTAT trip setpoint will be lowered.

IMMEDIATE ACTIONS 4.1 None

5.0 SUBSEQUENT ACTIONS Place the Rod Motion Control Selector to the MAN position.

,iroceed as follows:

reactor power is greater than 75 per ent OR more than one RCC is misaligned, THEN:

1. Borate/dilute AND/OR change Turbine load to maintain Tavg within 3°F of Tref.

2. Use RCC motion only to control axial flux within the target band.

. I If increasing Reactor power to approximately 3 percent (stay in Mode 2) for a flux map, rod motion may be used. I

3. Do NOT withdraw control rods to increase power until the affected RCCs have been aligned, except as noted above.

j reactor power is less than 75 percent AND one RCC is misaligned, TifEN at the discretion of the Reactor Engineering Supervisor, use rod motion OR boration/dilution to limit reactor power to less than 75 percent.

Notify the Reactor Engineering Supervisor or designee AND provide the following information:

Amount of time the RCCs has (have) been misaligned.

Degree of misalignment.

Current reactor status (i.e., rods in manual, reactor power, and RCC position).

RPI gain adjustments should be delaO-O59. 14 Rod Position Indication (RPI) I i verification is performed. I the I&C Supervisor to verify RPI indication to investigate CM System for possible failure.

CAJJF1N When more than one RCCA in the same ank is suspected of being misaligned from its step demand counter, flux traces are required to be performed separately for each RCCA. Upon declaring the RCCA not misaligned, the associated RPI must be declared operable prior to performing the next flux trace to prevent an unnecessary entry into Tech Spec action 3.0.3.

ve the Reactor Engineering Supervisor perform one or more of the following, at the discretion of the Reactor Engineering Supervisor, to confirm RCC misalignment or RCC position indication malfunction:

5.5.1 Perform 3-OSP-059.1O, Determination of Quadrant Power Tilt Ratio.

5.5.2 Check z Flux meters.

5.5.3 Check core exit thermocouples.

5.5.4 Two Thimble Flux Map for symmetry check OR to estimate RCC position

1. Visual

2. Computer check of digital data 5.5.5 Full Core Flux Map for verification of core power distribution.

5.5.6 Stepping of RCCs that are nearly or fully withdrawn.

5.5.7 Rod DeviationlAxial Flux Panel the RCC is determined to be aligned with the associated bank AND an RCC position indicator is failed, ThEN go tok$NOPO28.2, RCC Position Indication Malfunction.

more tha o CC is inoperable or misaligned from the group demand step counter LIEF position by ore an the Allowed Rod Misalignment of Technical Specification 3.1.3.1, ThEN comp y with the actions of Technical Specification 3.1.3.1.

AIfl7I

3-ONOP-028.1 one RCC is misaligned from the associated group demand step counter height by more than the Allowed Rod Misalignment of Specification 3.1.3.1, ThEN power operation may continue provided within 1 hour:

The RCC is restored to operable status within the Allowed Rod Misalignment of Technical Specification 3.1.3.1, The RCC is declared inoperable and the remainder of the RCCs in the bank with the inoperable RCC are aligned to within the Allowed Rod Misalignment of Technical Specification 3.1.3.1 of the inoperable RCC while NOT exceeding the RCC insertion limits in accordance with the Plant Curve Book,Section VII Figure 3, AND

1. The thermal power level shall be restricted in accordance with Technical Specification 3.1.3.6 during subsequent operation, OR

5. . The RCC is declared inoperable AND the shutdown margin requirement of Technical Specification 3.1.1.1 is satisfied. Power operation may then continue provided that:

1. The thermal power level is reduced to less than or equal to 75 percent within the next hour, and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85 percent of rated thermal power AND

2. The shutdown margin requirement of Technical Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND

3. A power distribution map is obtained from movable incore detectors and FQ(Z) and FH are verified to be within the limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 1

4. A re-evaluation of each accident analysis listed in Enclosure 1 is performed within 5 days, to confirm that the previously analyzed results of the accidents listed in Enclosure 1 remain valid under the present conditions AND

5. The rod worth of the inoperable RCC is determined within 4 weeks.

a. j. the RCC is determined to have a potential reactivity insertion of greater than 300 PCM upon ejection at rated power, ThEN be in Mode 3, Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

6. AFTER performing re-evaluation of each accident analysis (Substep 5.8.3.4) and verification of the Hot Channel Factors to be within the limits (Substep 5.8.3.3), THEN maintain reactor power less than the high neutron flux trip setpoint (85 percent).

5.9 Align one RCC at a time with the associated bank as follows:

5.9.1 Obtain permission from the Reactor Engineering Supervisor or designee.

5.9.2 IF reactor power has been reduced as per Technical Specification 3.1.3.6, ThEN do not increase power until the RCCs has been realigned.

5.9.3 Position the Rod Motion Control Selector switch to the RCC bank which has the misaligned RCC.

5.9.4 Place all the lift coil disconnect switches for the misaligned rod bank to the disconnect position (toggle switch down) EXCEPT the misaligned RCC switch which is left in the connect position (toggle switch up).

5.9.5 Record the step position for the misaligned RCC group demand step counter in the Unit Narrative Log as follows:

1. Bank

2. Group

3. Position 5.9.6 Manually set the associated group demand step counter to the position the misaligned RCC is determined to be in.

5.9.7 IF the misaligned RCC is in a control bank, THEN reset the bank demand step counters from the DCS as follows:

1. Navigate to the RPI BANK DEMAND ALIGNMENT screen.

2. Select INITIATE ALIGNMENT for the affected control bank.

3. Select NEW VALUE in the overlay.

4. Type in the desired bank demand step value, using the keyboard.

5. Press Enter.

6. Select INITIATE RE ALIGNMENT in the overlay.

7. Select YES in the save changes overlay.

8. Select CLOSE OVERLAY.

AIO7! IAIQI ,.lI., I.,.,

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-028. 1 RCC Misalignment 4/7/09 CAUTION Failure to follow instructions provided by the Reactor Engineering Supervisor could affect fuel integrity caused by power peaking.

NOTE I Annunciator 89/4, ROD CONTROL URGENT FAILURE, and the RCC power cabinet URGENT FAILURE will alarm for the group with the lift coils disconnected.

n = _ = a a a = = a = a = n I

I 5.9.8 Align the misaligned RCC using guidance provided by the Reactor Engineering Supervisor as follows:

1. Place the Rod Motion Lever to the fN/OUT position, as applicable.

2. Maintain Reactor Power at the level determined by the Reactor Engineering Supervisor as follows:

a. IF misaligned RCC must be inserted, THEN adjust Turbine load to maintain Tref equal to Tavg.

b. IF misaligned RCC must be withdrawn, THEN borate at less than or equal to 10 gpm, as directed by the Reactor Engineering Supervisor.

3. Withdraw or insert the misaligned RCC at 10 to 15 steps per minute to align the control rod.

4. Monitor Power Range Nuclear Instrumentation for abnormal flux tilts (greater than 3 percent difference between any two detectors at the same elevation).

5. DO NOT increase reactor power without permission from the Reactor Engineering Supervisor AND the Shift Manager.

6. Continue to move the misaligned RCC until the group step counter indicates the position recorded in Step 5.9.5.

5.9.9 Place all lift coil disconnect switches to the connect position (toggle switch up).

5.9.10 Depress the Rod Control Alarm Reset AND verify the following:

1. Annunciator B 9/4, ROD CONTROL URGENT FAILURE, clears.

2. The RCC power cabinet URGENT FAILURE light is off.

5.9.11 IF other RCCs are misaligned, ThEN return to Steps 5.9.1 through 5.9.10.

5.10 AFTER the malfunction has been corrected AND before increasing power, THEN monitor the following parameters to ensure the flux distribution is normal:

5.10.1 Power range nuclear instrumentation - less than 3 percent difference between any two detectors at the same elevation 5.10.2 Core exit thermocouples - less than 10°F difference between any two channels at like symmetric locations 1

An Incore Flux Map is optional, at the discretion of the Reactor Engineering Supeivisor.

5.10.3 No significant axial power shape difference from symmetric assemblies as determined by the Reactor Engineering Supervisor 5.10.4 Axial flux indicators less than 3 percent difference between any two channels 5.11 Place Rod Control Selector Switch to MANUAL or AUTOMATIC position.

AIfl7I

6.0 REFERENCES

/RECORDS REQUIRED! COMMITMENT DOCUMENTS 6.1 References 6.1.1 Technical Specifications:

1. Section 3.2, Power Distribution Limits

2. Section 3/4.1.3, Reactivity Control Systems 6.1.2 Procedures

1. 3-ONOP-028.2, Control Rod Position Indication Malfunction

2. 3-OSP-059.10, Determination of Quadrant Power Tilt Ratio

3. 3-PMI-028.3, RPI Hot Calibration, CRDM Stepping Test and Rod Drop Test 6.1.3 Plant Curve Book, Unit 3

1.Section VII, Figure 3, Rod Insertion Limits vs Thermal Power 6.1.4 1NPOSOERs

1. SOER 84-2 (1, 2 and 8) Control Rod Mispositioning

2. SOER 84-2, Control Rod Mispositioning-Addendum 6.1.5 Miscellaneous Documents (i.e., PC/M, Correspondence)

1. PC/M 93-005, Elimination of Turbine Runback

2. PC/M 09-006, Rod Position Indication System Replacement 6.2 Records Required 6.2.1 None 6.3 Commitment Documents 6.3.1 None END OF TEXT A!O7I

ENCLOSURE 1 (Page 1 of 1)

ACCIDENT ANALYSES REQUIRING RE-EVALUATION IN TUE EVENT OF AN INOPERABLE RCC Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in Large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident)

Major Secondary Coolant System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)

FINAL PAGE AIQ7i IAIi,.IkI,

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01005014300 JPM: Recover from a Loss Task

Title:

of Offsite Power JPM No: 01005014303 K/A

Reference:

062 A4.07 RO 3.1 SRO 3.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

o Unit 3 is in MODE 3.

• A loss of offsite power has occurred.

• The 3A and 3B Emergency Diesel Generators are supplying their respective buses.

o Notification has been received that the System is stable and offsite power is available to the Unit 3 Startup Transformer.

o The SM has determined that offsite power should be restored to the 3A 4KV Bus.

Initiating Cues:

• 3-ONOP-004. 1, System Restoration Following a Loss of Offsite Power, has been completed up through Step 7.

• The Unit Supervisor directs you to restore offsite power to the 3A 4KV Bus and shutdown the 3A EDG per 3-ONOP-004.1, starting with Step 8.

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page2ofll Form ES-C-I Task Standard:

o The 3A 4KV Bus is energized from offsite power and the 3A EDO is shutdown.

Required Materials:

• 3-ONOP-004. 1, System Restoration Following a Loss of Offsite Power

• SYNC PLUG

References:

• 3-ONOP-004. 1, System Restoration Following a Loss of Offsite Power General

References:

• None Time Critical Task: No Validation Time: 20 minutes 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of II I Form ES-C-I SIMULATOR SETUP

1. Reset to IC-192, or equivalent IC.

2. Place simulator in RUN.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place simulator in FREEZE.

6. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of II Form ES-C-I Denote critical steps with a check mark ( Start Time:

SAT STEP I Obtain required materials.

UNSAT STANDARD Applicant obtains a copy of 3-ONOP-004.1, System Restoration Following a Loss of Offsite Power, and a Sync Plug.

Provide Applicant with a copy of 3-ONOP-004. 1, System Restoration Following a Loss of Offsite Power, marked up CUE through Step 7, and a Sync Plug.

COMMENT 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of I I I Form ES-C-Il CAUT 0N NOTE When the Star1ip Transformer breaker is closed, the EDG load wi!f drop to zero. To prevent potential damage to the EDG. the EDG output breaker should be opened as soon as the Startup Transformer is verilied to be carry#ncj 4KV b415 load.

Synchronize Unit 3 Startup Transformer To 3A 4KV Bus.

STEP 2 SAT Place Startup Transformer Sync to 3A 4KV Bus 3AA05 to ON.

q (3-ONOP-004.1, Step 8 and Step 8.a)

UNSAT Applicant inserts the sync plug in S/U TRANSFORMER SYNC TO 3A KV BUS 3AA05 and rotates the control switch clockwise STANDARD to the ON position.

CUE EVLAUATOR NOTE:

COMMENT Applicant may check voltage on all three phases.

Verify running voltage matched incoming voltage. SAT STEP 3 UNSAT (3-ONOP-004.1, Step 8.b)

Applicant observes the RUNNING VOLTS and INCOMING STANDARD VOLTS meters and notes that they are approximately equal.

CUE COMMENT 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of II Form ES-C-I Verify synchroscope ROTATING SLOWLY IN FAST DIRECTION. SAT STEP 4 UNSAT (3-ONOP-004.1, Step 8.c)

Applicant may adjust EDG speed using the 3A Diesel Generator STANDARD Speed Changer to achieve a satisfactory rate of rotation in the FAST direction.

CUE COMMENT STEP 5 WHEN synchroscope pointer reaches 12 oclock position, THEN close Startup Transformer 3A 4KV Bus Supply, 3AA05 (3-ONOP-004.1, Step 8.d)

Applicant places the control switch for START-UP XFMR 3A STANDARD 4KV BUS SUPPLY 3AA05, to the CLOSE position and releases the switch. Observes the green OPEN light is OFF and the red CLOSE light is LIT. Also observes that the red flag is showing.

CUE EVALUATOR NOTE:

COMMENT SEQUENCER 3A TROUBLE (X 1/3) will actuate.

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 11 Form ES-C-I Place Startup Transformer Sync fó 3A 4KV us 3AAO5 to OFF AND remove handle. SAT STEP 6 UNSAT (3-ONOP-004.1, Step 8.e)

Applicant rotates the S/U TRANSFORMER SYNC TO 3A KV BUS 3AA05 control switch counterclockwise to the OFF position STANDARD Applicant removes the sync plug.

CUE COMMENT Shutdown 3A Emergency Diesel Generator ST EP SAT Open 3A Emergency Diesel to 3A 4KV Bus, 3AA20.

UNSAT (3-ONOP-004.1, Step 9 and Step 9.a)

Applicant rotates the A EDG TO 3A 4KV BUS control switch counterclockwise to the TRIP position. Note the green OPEN STANDARD light is ON and the red CLOSE light is ON.

CUE COMMENT 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of II Form ES-C-I Adjust 3A Emergency Diesel Generator frequency to 60 Hz SAT S TEP 8 using Diesel Generator Speed Changer. UNSAT 1

(3-ONOP-004.1, Step 9.b)

Applicant positions the A DIESEL GEN SPEED CHANGER to STANDARD adjust the 3A EDG frequency to between 59.4 and 60.6 Hz on the A DIESEL HERTZ meter.

CUE EVALUATOR NOTE:

COMMENT Tolerance based on 3-OSP-023 allowances.

Adjust 3A Emergency Diesel Generator voltage to 4160 volts SAT STEP 9 using Diesel Generator Voltage Regulator. UNSAT

,,J (3-ONOP-004.1, Step 9.c)

Applicant positions the A DIESEL GEN VOLTAGE STANDARD REGULATOR switch to adjust the 3A EDG voltage to approximately between 3950 and 4370 volts on the A DIESEL KILOVOLTS meter.

CUE EVALUATOR NOTE:

COMMENT Tolerance based on 3-OSP-023 allowances.

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of II Form ES-C-I Stop 3A Emergency Diesel Generator by placing the Diesel SAT STEP 10 Generator 3A Normal Start/Normal Stop switch in NORMAL UNSAT I STOP (3-ONOP-004.1, Step 9.c)

Applicant positions the 3A DIESEL GENERATOR NORMAL STOP/NORMAL START switch counterclockwise to the NORMAL STOP position and allows the switch to spring-return STANDARD to the mid position.

Applicant notes that 3A EDG frequency and voltage drop to zero.

TERMINATING CUE:

CUE Inform the Applicant that another operator will restore the EDG to a normal lineup. This completes the JPM.

COMMENT Stop Time 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 11 Form ES-C-I Verification of Completion: - -

Job Performance Measure No. 01005014303 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Resu It: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I will explain the initial conditions, which steps to s[mulafe or discuss, and provide initiatng cues.

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

Initial Conditions:

• Unit 3 is in MODE 3.

• A loss of offsite power has occurred.

• The 3A and 3B Emergency Diesel Generators are supplying their respective buses.

• Notification has been received that the System is stable and offsite power is available to the Unit 3 Startup Transformer.

• The SM has determined that offsite power should be restored to the 3A 4KV Bus.

Initiating Cues:

• 3-ONOP-004.1, System Restoration Following a Loss of Offsite Power, has been completed up through Step 7.

• The Unit Supervisor directs you to restore offsite power to the 3A 4KV Bus and shutdown the 3A EDG per 3-ONOP-004.1 starting with Step 8.

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.

2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

Florida Power & Light Company Turkey Point Nuclear Plant Unit 3

Title:

System Restoration Following Loss of Offsite Power (Continuous Use)

Safety Related Procedure Responsible Department: Operations Revision Approval Date: 9/4/07 RTSs 91-1561P, 91-2743P, 93-0173P, 93-1679P, 95-0234P, 95-0498P, 95-0918P, 97-1375P, 01-0529P, 01-0695P, 03-0204P, 04-0967P, 07-0478P PC/M 87-258,87-263, 8 7-264,87-265, 94-059,01-009 W97:DH/ev/mrglln Th

LIST OF EFFECTIVE PAGES Revision Revision Date Date 1 09/04/07 21 09/04/07 2 09/04/07 22 09/04/07 3 09/04/07 23 09/04/07 4 09/04/07 24 09/04/07 5 09/04/07 25 09/04/07 6 09/04/07 26 09/04/07 7 09/04/07 27 09/04/07 8 09/04/07 28 09/04/07 9 09/04/07 29 09/04/07 10 09/04/07 30 09/04/07 11 09/04/07 31 09/04/07 12 09/04/07 32 09/04/07 13 09/04/07 33 09/04/07 14 09/04/07 34 09/04/07 15 09/04/07 35 09/04/07 16 09/04/07 36 09/04/07 17 09/04/07 18 0 9/04/07 19 09/04/07 20 09/04/07 W97:DH/ev/mrci/In

1.0 PURPOSE This procedure provides instructions to be followed in order to restore electrical systems to a normal configuration when offsite power has been lost and subsequently restored.

2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 System Dispatcher has notified Operations personnel that offsite power is stable and the Unit 3 Startup Transformer has been reenergized by offsite power.

2.2 System Dispatcher has notified Operations personnel that offsite power is stable and the 3C Transformer has been reenergized by offsite power.

3.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 3.1 References 3.1.1 Technical Specifications

1. Section 3/4.8.1, AC Sources

2. Section 3/4.8.3, Onsite Power Distribution 3.1.2 FSAR

1. Section 8.2, Emergency Power

2. Section 14.1.12, Loss of A.C. Power 3.1.3 Plant Drawings

1. 5610-E-855, Breaker List

2. 5610-T-E-1591, Sheet 1 Electrical Distribution

3. 5610-T-L1, Sheet 2 Reactor Trip Signals

4. 5610-T-L1, Sheet 6C Generator Details

5. 5610-T-L1, Sheet 12A Emergency Load Sequencer

6. 5613-T-Ll, Sheet 13 Bus 3A Loss of Voltage and Bus Stripping

7. 5613-T-L1, Sheet 13A Bus 3B Loss of Voltage and Bus Stripping W97:DH/ev/mrq/In

Procedure No.: Procedure

Title:

Page:

4 Approval Date:

3-ONOP-004.1 System Restoration FolLowing Loss of Offsite Power 9/4/07 3.1.4 Plant Procedures

1. 3-ONOP-004.2, LOSS OF 3A 4KV BUS

2. 3-ONOP-004.3, LOSS OF 3B 4KV BUS

3. 3-ONOP-004.4, LOSS OF 3C 4KV BUS

4. 3-ONOP-004.5, LOSS OF 3D 4KV BUS

5. 3-ONOP-041.7, SHUTDOWN LOCA [MODE 3 (LESS THAN 1000 PSIG) 0R4]

6. 3-ONOP-041.8, SHUTDOWN LOCA [MODE 5 OR 6]

7. 3-ONOP-092.3, STARTUP TRANSFORMER MALFUNCTION

8. 3-ONOP-092.4, C BUS TRANSFORMER MALFUNCTION

9. 3-OP-005, 4160 VOLT BUSES A, B ANI D

10. 3-OP-006, 480 VOLT SWITCHGEAR SYSTEM

11. 3-OP-007, 480 VOLT MOTOR CONTROL CENTER

12. 3-OP-023, EMERGENCY DIESEL GENERATOR

13. 3-OP-030, COMPONENT COOLING WATER SYSTEM 3.1.5 Plant Change/Modifications

1. PC/M 87-258, Load Center 3H, MCC 3D and Transfer of Loads

2. PC/M 87-263, New EDG Installation

3. PCIM 87-264, EDG 3B/4B, EDG 3A/4A and New EDG Building Tie-Ins

4. PC/M 87-265, Swing Switchgear 3D and Transfer of ICW & CCW 3C Pumps

5. PC/M 94-059, Diesel Engine Driver for Standby Steam Generator Feedwater Pump P82B W97:DH/ev/mro/In

Procedure No.: Procedure

Title:

Page:

5 Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 3.1.6 Miscellaneous

1. JPN-PTN-SEMP-93-010, Turlcey Point Units 3 & 4 Safety Evaluation for Control Building Annex Cooling

2. IPN-PTN-SENP-95-026, Safety Evaluation for CCW Flow Balance and PostAccident Alignment Requirements to Support Thermal Up-Rate.

(LER 250/95-006) 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 JPN-PTN-SENP-95-026, Safety Evaluation for CCW Flow Balance and PostAccident Alignment Requirements to Support Thermal Up-Rate.

(LER 25 0/95-006)

W97:DHlevimra/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAIJ-T-I1N1 CCW System load requirements for the EOP network, 3-ONOP-041.7, SHUTDOWN LOCA [MODE 3 (LESS THAN I000PSIG) OR MODE 4J and 3-ONOP..-041.8, SHUTDOWN LOCA [MODE 5 OR 6J, SHALL NOT exceed the limits specified in 3-OP-030, COMPONENT COOLING WATER SYSTEM.

Momentaiy High Flow due to swapping CCW Pumps is acceptable.

Verify SI - RESET Check Unit 3 Startup Transformer Potential Go to Step 65.

White LightOnVPA-ON Check Unit 3 Startup Transformer Lockout Perform the following:

Relay RESET

a. Try to determine and correct cause of Unit 3 startup transformer lockout relay actuation using 3-ONOP-092.3, STARTUP TRANSFORMER MALFUNCTION.

b. WHEN the Unit 3 Startup Transformer Lockout Relay is reset, THEN return to Step 4.

c. GotoStep65.

Check Startup Transformer 3A 4KV Bus Go to Step 35.

Supply, 3AA05 OPEN W97:DH/ev/mrg/In

STEP EAoNxPECTED RESPONSE I I RESPONSE NOT OBTAINED 1 Check If Offsite Power Should Be Restored To 3A 4KV Bus At This Time onsult with the Shift Manager to etermine desired order of offsite power res ora ion 4KV bowed by 3B 4KV bus 3B 4KV bus followed by 3A 4KV bus

• Check desired order of offsite power b. GotoStep35.

restoration 3A 4KV BUS FOLLOWED BY 3B 4KV BUS Check 3A 4KV Bus ENERGIZED

- Go to Step 28.

Check 3A 4KV Bus ENERGIZED BY 3A

- Go to Step 11.

EMERGENCY DIESEL GENERATOR W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I ISPONSENOTOBTAINED I CAUTION When the Startup Transformer breaker is closed, the EDG load will drop to zero. To prevent potential damage to the EDO, the EDG output breaker should be opened as soon as the Startup Transformer is verified to be carrying 4KV bus load.

8 Synchronize Unit 3 Startup Transformer To 3A4KV Bus

a. Place Startup Transformer Sync to 3A 4KV Bus 3AA05 to ON

b. Verify running voltage matched incoming b. Adjust 3A Diesel Generator Voltage voltage Regulator.

c. Verify synchroscope ROTATING

- c. Adjust 3A Diesel Generator Speed SLOWLY IN FAST DIRECTION Changer.

d. WHEN synchroscope pointer reaches 12 d. if Startup Transformer 3A 4KV Bus oclock position, THEN close Startup Supply, 3AA05, can !] be closed, Transformer 3A 4KV Bus Supply, 3AA05 THEN perform the following:

1) Place Startup Transformer Sync To 3A 4KV Bus 3AA05 to OFF AND remove handle.

2) Direct Electrical Maintenance to determine cause of breaker failure.

3) Go to Step 35.

e. Place Startup Transformer Sync to 3A 4KV Bus 3AA05 to OFF AND remove handle W97:DH/ev/mrg/In

Procedure No.: Procedure

Title:

Page:

. Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 9 Shutdown 3A Emergency Diesel Generator

a. Open 3A Emergency Diesel to 3A 4KV Bus, 3AA20 a. Locally open breaker.

b. Adjust 3A Emergency Diesel Generator b. Locally adjust frequency.

frequency to 60 Hz using Diesel Generator Speed Changer

c. Adjust 3A Emergency Diesel Generator c. Locally adjust voltage.

voltage to 4160 volts using Diesel Generator Voltage Regulator

d. Stop 3A Emergency Diesel Generator by d. Locally stop 3A Emergency Diesel placing the Diesel Generator 3A Normal Generator.

StartlNormal Stop switch in NORMAL STOP

e. Place 3A Emergency Diesel Generator in normal standby alignment using 3OP023, Emergency Diesel Generator 10 GoToStep35 11 Check 3B 4KV Bus ENERGIZED - Perform the following:

a. Try to energize 3B 4KV bus using one of the following:

3-ONOP-004.3, LOSS OF 3 4KV BUS OR 3-.OP-005, 4160 VOLT BUSES A, B, AND D

b. IF 3B 4KV bus can QI be energized, THEN go to Step 65.

12 Check Intake Cooling Water Headers - Perform the following:

TIED TOGETHER

a. IF both Intake Cooling Water Headers are intact, THEN tie headers together.

b. IF Intake Cooling Water Headers can NOT be tied together, THEN go to Step 35.

W97:DH/ev/mrglln

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

13 Check CCW Headers TIED TOGETHER

- Perform the following:

a. IF both CCW headers are intact, THEN tie headers together.

b. IF CCW headers can NOT be tied together, THEN go to Step 35.

14 Direct Operator To Place 3A Emergency Diesel Master Control Switch To OFF 15 Check 3D 4KV Bus ALIGNED TO 3A 4KV

- Go to Step 20.

BUS

• Supply From 4KV Bus 3A, 3ADO1 -

CLOSED

• Feeder To 4KV Bus 3D, 3AAI 7 CLOSED 16 Check Station Blackout Breaker, 3AD07 - Perform the following:

OPEN

a. jf Unit 3 is supplying power to Unit 4 4KV buses using station blackout tie line, THEN go to Step 33.

b. Start 3B Intake Cooling Water Pump.

c. Start 3B Component Cooling Water Pump.

d. IF either pump can JQI be started, THEN go to Step 33.

17 Check 3C Intake Cooling Water Pump - Perform the following:

STOPPED

a. Start 3B Intake Cooling Water Pump.

b. E 3B Intake Cooling Water Pump can NOT be started, THEN start 3A Intake Cooling Water Pump. ffl neither pump can be started, THEN go to Step 33.

c. Stop 3C Intake Cooling Water Pump.

W97:DH/evlmrglln

Procedure No.: Procedure

Title:

Page:

. Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED a

I FIo*T 1

When only one component coo/mg water pump is running, a MAXIMUM of TWO emergency containment coolers are allowed to be running.

18 Check 3C Component Cooling Water Pump Perform the following:

- STOPPED

a. Start 3B Component Cooling Water Pump.

b. IF 3B Component Cooling Water Pump can NOT be started, THEN start 3A Component Cooling Water Pump. IF neither pump can be started, THEN go to Step 33.

c. Stop 3C Component Cooling Water Pump.

19 Check If 3D 4KV Bus Should Be Aligned To 3B 4KV Bus

a. Check Station Blackout Breaker, 3AD07 a. Go to Step 20.

OPEN

b. Open Feeder To 4KV Bus 3D, 3AAI 7

c. Open Supply From 4KV Bus 3A, 3ADO1

d. Close Supply From 4KV Bus 3B, 3AD06

e. Close Feeder To 4KV Bus 3D, 3AB19 20 Check 3A Intake Cooling Water Pump - Perform the following:

STOPPED

a. Start 3B Intake Cooling Water Pump.

b. jf 3B Intake Cooling Water Pump can NOT be started, THEN start 3C Intake Cooling Water Pump. jf neither pump can be started, THEN go to Step 33.

c. Stop 3A Intake Cooling Water Pump.

W97:DH/evlmrglln

Procedure No.: Procedure

Title:

Page:

12 Apptoval Dát:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED a

When only one Component Cooling Water Pump is running, a MAXIMUM of TWO Emergency Containment Coolers are allowed to be running.

j 21 Check 3A Component Cooling Water Pump Perform the following:

- STOPPED

a. Start 3B Component Cooling Water Pump.

b. jf 3B Component Cooling Water Pump can NOT be started, THEN start 3C Component Cooling Water Pump. ffl neither pump can be started, THEN go to Step 33.

c. Stop 3A Component Cooling Water Pump.

22 Check Charging Pumps Perform the following:

• 3B Charging Pump RUNNING a. Start 3B Charging Pump.

• 3A Charging Pump STOPPED b. if 3B Charging Pump can NOT be started, THEN go to Step 33.

• 3C Charging Pump STOPPED-

c. Stop 3A Charging Pump.

d. Stop 3C Charging Pump.

23 Check 3A RHR Pump STOPPED - Perform the following:

a. Start 3B RHR pump and align valves as directed by the Shift Manager to allow stopping of 3A RHR pump.

b. Consult with the Shift Manager to determine if 3A RHR pump can be stopped.

c. IF 3A RHR pump can QI be stopped, THEN go to Step 33.

d. Stop 3A RHR pump.

W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION Injection to the RCS from at least two High-Head SI Pumps is required to be maintained during the injection phase of a large loss of reactor coolant accident.

24 Check 3A High-Head SI Pump STOPPED

- Perform the following:

a. Start 3B, 4A, or 4B High-Head SI Pump(s) JQ align valves as directed by the Shift Manager to allow stopping of 3A High-Head SI Pump.

b. Consult with the Shift Manager to determine if 3A High-Head SI Pump can be stopped.

c. if 3A High-Head SI Pump can LQI be stopped, THEN go to Step 33.

d. Stop 3A High-Head SI Pump.

25 Check 3A Turbine Plant Cooling Water Perform the following:

Pump STOPPED

a. Start 3B Turbine Plant Cooling Water Pump.

b. jf 3B Turbine Plant Cooling Water Pump can .QI be started, THEN consult with the Shift Manager to determine if 3A Turbine Plant Cooling Water Pump can be stopped.

c. if 3A Turbine Plant Cooling Water Pump can JQI be stopped, THEN go to Step 33.

d. Stop 3A Turbine Plant Cooling Water Pump.

W97:DH/evlmrg/In

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I iioF 3A 4KV bus is deenergized, the bearing oil lift pump will stop.

=

When

= = = = =

I

= A 26 Check Main Turbine Components

a. Check seal oil system - IN SERVICE a. Go to Step 26e.

b. Locally start Backup Air Side Seal Oil Pump

c. Check Auxiliary Oil Pump STOPPED-

c. Perform the following:

1) Start Emergency Bearing Oil Pump.

2) Stop Auxiliary Oil Pump.

d. Check turning gear STOPPED

d. Determine if main turbine turning gear can be stopped.

e. Verify main turbine READY FOR LOSS

e. ffl loss of power to 3A 4KV bus will OF 3A 4KV BUS result in damage to main turbine, THEN go to Step 33.

CAUTIONS

• Continuing with this procedure without defeating the 3A Emergency Diesel Auto Start capability by placing the Master Control Switch to OFF (Step 14) will result in a restart of the EDG.

• Steps 27 and 28 will deenergize 3A 4KV bus.

27 Check Station Blackout Breaker, 3AD07 - IF 3A 4KV bus is being energized using OPEN station blackout tie line, THEN perform the following:

a. Open Station Blackout Breaker, 3AD07.

b. Direct Unit 4 Reactor Operator to open Station Blackout Breaker, 4AD07.

W97:DH/ev/mrg/ln

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 28 Transfer 3A 4KV Bus To Unit 3 Startup Transformer

a. Open or verify open all alternate supply breakers to 3A 4KV bus

• 3AA02, Auxiliary Transformer 3A 4KV Bus Supply

• 3AA09, 3A 4KV Bus Tie to 3B or 3C 4KV Bus

• 3AA20, 3A Emergency Diesel to 3A 4KV Bus

• 3AA22, 3A 4KV Bus Emergency Tie to Unit 4 Startup Transformer

b. Verify 3A 4KV bus stripping using ATTACHMENT 1

c. Place Startup Transformer Sync to 3A 4KV Bus 3AA05 to ON

d. Close Startup Transformer 3A 4KV Bus d. ffl Startup Transformer 3A 4KV Bus Supply, 3AA05 Supply, 3AA05, can NOT be closed, THEN perform the following:

1) Place Startup Transformer Sync To 3A 4KV Bus 3AA05 to OFF AND remove handle.

2) Direct Electrical Maintenance to determine cause of breaker failure.

3) Try to reenergize 3A 4KV bus using 3-ONOP-004.2, LOSS OF 3A 4KV BUS, while continuing with this procedure.

4) Go to Step 33.

e. Place Startup Transformer Sync to 3A 4KV Bus 3AA05 to OFF AND remove handle W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

29 Reenergize 3A Load Center

a. Close 3A Load Center breaker, 3AA08

b. Check 3A Load Center ENERGIZED

- b. Perform the following:

1) Locally verify 3A Feed From 3A 4KV Bus breaker, 30102 -

CLOSED.

2) IF 3A Load Center can NOT be reenergized, THEN consult with the Shift Manager to determine if 3A Load Center should be reenergized from opposite train source using 3 OP-006, 480 Volt Switchgear System.

30 Reenergize 3C Load Center

a. Close 3C Load Center breaker, 3AA14

b. Check 3C Load Center ENERGIZED

- b. Perform the following:

1) Locally verify 3C Feed From 3A 4KV Bus breaker, 30302 -

CLOSED.

2) IF 3C Load Center can NOT be reenergized, THEN consult with the Shift Manager to determine if 3C Load Center should be reenergized from opposite train source using 3-OP-006, 480 Volt Switchgear System.

31 Check 3H Load Center ALIGNED TO AN

- Manually align 3H Load Center to an ENERGIZED LOAD CENTER energized load center.

W97:DH/ev/mrglln

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I CAUTIONS CCW System loads for the EOP network, 3-ONOP-041.7, Shutdown LOCA

[Mode 3 (Less than 1000 PSIG) or Mode 4J and 3-ONOP-041.8, Shutdown LOCA

[Mode 5 or 6J, shall not exceed the limits specified in 3OP-030, COMPONENT COOLING WATER SYSTEM.

Ensuring the operation of Spent Fuel Pit cooling should be given a high priority during restoration from a Loss of Offsite Power.

a a a a iaa = Iio1j1

/f any component powered from a deenergized motor control center must be started, the I affected motor control center needs to be reenergized using 3-OP-007, 480 VOLT MOTOR CONTROL CENTERS.

a a S a a a a a a a a 32 Restart Components Supplied By 3A 4KV Bus As Directed By The Shift Manager 3A Intake Cooling Water Pump 3A Component Cooling Water Pump 3A High-head SI Pump 3A Residual Heat Removal Pump 3A Turbine Plant Cooling Water Pump Auxiliary Oil Pump Bearing Oil Lift Pumps Main Turbine Turning Gear SFP Cooling Water Pump SFP Exhaust Fan Notify Chemistry to verify proper operation of the plant SPING units Other plant equipment required to stabilize unit operation as determined by the Shift Manager W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

33 Locally Verify The Following Breakers -

OPEN, RACKED OUT, AND LOCKED 3A 4KV Bus Emergency Tie to Unit 4 Startup Transformer, 3AA22 3A 4KV Bus Tie to 3B or 3C 4KV Bus, 3AA09 34 Direct Operator To Place 3A Emergency Diesel Master Control Switch To NORMAL 35 Check Startup Transformer 3B 4KV Bus Go to Step 64.

Supply, 3AB05 OPEN 36 Check 3B 4KV Bus ENERGIZED

- Go to Step 57.

37 Check 3B 4KV Bus ENERGIZED BY 3B

- Go to Step 41.

EMERGENCY DIESEL GENERATOR W97:DH/evimrg/n

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION When the Startup Transformer breaker is closed, the EDG load will drop to zero. To prevent potential damage to the EDG, the EDO output breaker should be opened as soon as the Startup Transformer is verified to be cariying 4KV bus load.

38 Synchronize Unit 3 Startup Transformer To 3B 4KV Bus

a. Place Startup Transformer Sync to 3B 4KV Bus 3AB05 to ON

b. Verify running voltage matched incoming b. Adjust 3B Diesel Generator Voltage voltage Regulator.

c. Verify synchroscope ROTATING

- c. Adjust 3B Diesel Generator Speed SLOWLY IN FAST DIRECTION Changer.

d. WHEN synchroscope pointer reaches d. jf Startup Transformer 3B 4KV Bus 12 oclock position, THEN close Startup Supply, 3AB05, can !QI be closed, Transformer 3B 4KV Bus Supply, 3AB05 THEN perform the following:

1) Place Startup Transformer Sync to 3B 4KV Bus 3AB05 to OFF AND remove handle.

2) Direct Electrical Maintenance to determine cause of breaker failure.

3) Go to Step 64.

e. Place Startup Transformer Sync to 38 4KV Bus 3AB05 to OFF AND remove handle W97:DH/ev/mrg/In

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I 39 Shutdown 3B Emergency Diesel Generator

a. Open 3B Emergency Diesel to 3B 4KV Bus, 3AB20 a. Locally open breaker.

b. Adjust 3B Emergency Diesel Generator b. Locally adjust frequency.

frequency to 60 Hz using Diesel Generator Speed Changer

c. Adjust 3B Emergency Diesel Generator c. Locally adjust voltage.

voltage to 4160 volts using Diesel Generator Voltage Regulator

d. Stop 3B Emergency Diesel Generator by d. Locally stop 3B Emergency Diesel placing the Diesel Generator 3B Normal Generator.

Start/Normal Stop switch in NORMAL STOP

e. Place 3B Emergency Diesel Generator in normal standby alignment using 3OP023, Emergency Diesel Generator 40 Go To Step 64 41 Check 3A 4KV Bus ENERGIZED

- Perform the following:

a. Try to energize 3A 4KV bus using one of the following:

3-ONOP-004.2, LOSS OF 3A 4KV BUS OR 3-OP-005, 4160 Volt Buses A, B, and D

b. jf 3A 4KV bus can QI be energized, THEN go to Step 64.

42 Check Intake Cooling Water Headers- TIED Perform the following:

TOGETHER

a. if both intake cooling water headers are intact, THEN tie headers together.

b. IF intake cooling water headers can 4.QI be tied together, THEN go to Step 64.

W97:DH/ev/mrglln

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

43 Check CCW Headers TIED TOGETHER

- Perform the following:

a. if both CCW headers are intact, THEN tie headers together.

b. IF COW headers can NOT be tied together, THEN go to Step 64.

44 Direct Operator To Place 38 Emergency Diesel Master Control Switch To OFF 45 Check 3D 4KV Bus ALIGNED TO

- Go to Step 50.

3B 4KV BUS o Supply from 4KV Bus 3B, 3AD06 -

CLOSED

• Feeder to 4KV Bus 3D, 3AB19 CLOSED 46 Check Station Blackout Breaker, 3AD07 - Perform the following:

OPEN

a. IE Unit 4 4KV buses are being supplied from Unit 3 using station blackout tie line, THEN go to Step 62.

V

b. Start 3A Intake Cooling Water Pump.

V c. Start 3A Component Cooling Water Pump.

d. IF either pump can MQI be started, THEN go to Step 62.

47 Check 3C Intake Cooling Water Pump- Perform the following:

STOPPED

a. Start 3A Intake Cooling Water Pump.

b. IF 3A Intake Cooling Water Pump can NOT be started, THEN start 3B Intake Cooling Water Pump. neither pump V can be started, THEN go to Step 62.

c. Stop 30 Intake Cooling Water Pump.

W97:DHlevlmrg/In

Procedure No.: Procedure

Title:

I Page:

22 Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

a a a a a t a NO When only one Component Cooling Water Pump is running, a MAXIMUM of TWO Emergency Containment Coolers are allowed to be running.

48 Check 3C Component Cooling Water Pump Perform the following:

- STOPPED

a. Start 3A Component Cooling Water Pump.

b. ffl 3A Component Cooling Water Pump can NOT be started, THEN start 3B Component Cooling Water Pump. jf neither pump can be started, THEN go to Step 62.

c. Stop 3C Component Cooling Water Pump.

49 Check If 3D 4KV Bus Should Be Aligned To 3A 4KV Bus

a. Check Station Blackout Breaker, 3AD07 a. Go to Step 50.

OPEN

b. Open Feeder to 4KV Bus 3D, 3AB1 9

c. Open Supply from 4KV Bus 3B, 3AD06

d. Close Supply from 4KV Bus 3A, 3ADO1

e. Close Feeder to 4KV Bus 3D, 3AA17 50 Check 3B Intake Cooling Water Pump - Perform the following:

STOPPED

a. Start 3A Intake Cooling Water Pump.

b. IF 3A Intake Cooling Water Pump can NOT be started, THEN start 3C Intake Cooling Water Pump. jf neither pump can be started, THEN go to Step 62.

c. Stop 3B Intake Cooling Water Pump.

W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

fO When only one Component Cooling Water Pump is running, a MAXIMUM of TWO Emergency Containment Coolers are allowed to be running.

51 Check 3B Component Cooling Water Pump Perform the following:

- STOPPED

a. Start 3A Component Cooling Water Pump.

b. jf 3A Component Cooling Water Pump can NOT be started, THEN start 3C Component Cooling Water Pump. IF neither pump can be started, THEN go to Step 62.

c. Stop 3B Component Cooling Water Pump.

52 Check Charging Pumps Perform the following:

• 3A Charging Pump RUNNING a. Start 3A Charging Pump.

• 3B Charging Pump STOPPED b. I 3A Charging Pump can QI be started, THEN go to Step 62.

• 3C Charging Pump STOPPED

c. Stop 3B Charging Pump.

d. Stop 3C Charging Pump.

53 Check 3B RHR Pump STOPPED

- Perform the following:

a. Start 3A RHR pump and align valves as directed by the Shift Manager to allow stopping of 3B RHR pump.

b. Consult with the Shift Manager to determine if 3B RHR pump can be stopped.

c. ffl 3B RHR pump can QI be stopped, THEN go to Step 62.

d. Stop 3B RHR pump.

W97:DH/evlmrg/In

STEP ACTIONIEXPECTED RESPONSE I f RESPONSE NOT OBTAINED I

CAUTION Injection into the RCS from at least two High-Head SI Pumps is required to be maintained during the injection phase of a large loss of reactor coolant accident.

54 Check 3B High-Head SI Pump STOPPED

- Perform the following:

a. Start 3A, 4A, or 4B High-Head SI Pump(s) AND align valves as directed by the Shift Manager to allow stopping of 3B High-Head SI Pump.

b. Consult with the Shift Manager to determine if 3B High-Head SI Pump can be stopped.

c. IF 3B High-Head SI Pump can jQ] be stopped, THEN go to Step 62.

d. Stop 3B High-Head SI Pump.

55 Check 3B Turbine Plant Cooling Water Perform the following:

Pump STOPPED

a. Start 3A Turbine Plant Cooling Water Pump.

b. ffl 3A Turbine Plant Cooling Water Pump can Qjbe started, THEN consult with the Shift Manager to determine if 3B Turbine Plant Cooling Water Pump can be stopped.

c. !f 3B Turbine Plant Cooling Water Pump can QI be stopped, THEN go to Step 62.

d. Stop 3B Turbine Plant Cooling Water Pump.

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STEP f ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTIONS Continuing with this procedure without defeating 3B Emergency Diesel Auto Start capability as outlined in Step 44 will result in a restart of the EDO.

Steps 56 and 57 will deenergize 3B 4KV bus.

56 Check Station Blackout Breaker, 3AD07 -

LE 3B 4KV bus is being energized using OPEN station blackout tie line, THEN perform the following:

a. Open Station Blackout Breaker, 3AD07.

b. Direct Unit 4 Reactor Operator to open Station Blackout Breaker, 4AD07.

W97:DH/ev/mrg/In

Procedure No.: Procedure

Title:

Page:

- Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 57 Transfer 3B 4KV Bus To Unit 3 Startup Transformer

a. Open or verify open all alternate supply breakers to 3B 4KV bus

• 3AB02, Auxiliary Transformer 3A 4KV Bus Supply

• 3AB20, 3B Emergency Diesel to 3B4KV Bus

• 3AB22, 3B 4KV Bus Tie to 3A or 3C 4KV Bus

b. Verify 3B 4KV bus stripping using ATTACHMENT 2

c. Place Startup Transformer Sync to 3B 4KV Bus 3AB05 to ON

d. Close Startup Transformer 3B 4KV Bus d. jf Startup Transformer 3B 4KV Bus Supply, 3AB05 Supply, 3AB05, can {QI be closed, THEN perform the following:

1) Place Startup Transformer Sync to 3B 4KV Bus 3AB05 to OFF AND remove handle.

2) Direct Electrical Maintenance to determine cause of breaker failure.

3) Try to energize 3B 4KV bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS, while continuing with this procedure.

4) GotoStep62.

e. Place Startup Transformer Sync to 3B 4KV Bus 3AB05 to OFF AND remove handle W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

58 Reenergize 3B Load Center

a. Close 3B Load Center Breaker, 3AB09

b. Check 3B Load Center ENERGIZED

b. Perform the following:

1) Locally verify 3B Feed from 3B 4KV Bus breaker, 30210 -

CLOSED.

2) IF 3B Load Center can NOT be reenergized, THEN consult with the Shift Manager to determine if 3B Load Center should be reenergized from opposite train source using 3OP006, 480 VOLT SWITCHGEAR SYSTEM.

59 Reenergize 3D Load Center

a. Close 3D Load Center Breaker, 3AB14

b. Check 3D Load Center ENERGIZED

b. Perform the following:

1) Locally verify 3D Feed from 3B 4KV Bus breaker, 30410-CLOSED.

2) IF 3D Load Center can NOT be reenergized, THEN consult with the Shift Manager to determine if 3D Load Center should be reenergized from opposite train source using 3OP006, 480 VOLT SWITCHGEAR SYSTEM.

60 Check 3H Load Center ALIGNED TO AN Manually align 3H Load Center to an ENERGIZED LOAD CENTER energized load center.

W97:DH/ev/mrg/In

F1 I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION CCW System load requirements for the EOP network, 3-ONOP-041.7, SHUTDOWN LOCA [MODE 3 (LESS THAN 1000 PSIGJ OR MODE 4J and 3-ONOP-041.

8, SHUTDOWN LOCA [MODE 5 OR 6), SHALL NOT exceed the limits specifi ed in 3-OP-030, COMPONENT COOLING WATER SYSTEM.

FO If any component powered from a deenergized motor control center must be started I I affected motor control center needs to be reenergized using 3-OP-007, 480 VOLT

, the MOTOR i CONTROL CENTERS.

a a a I 61 Restart Components Supplied By 3B 4KV Bus As Directed By The Shift Manager

a. Safety Related Components

a. Sequencer failure may have occurred;

• 3B Intake Cooling Water Pump perform the following:

• 3B Component Cooling Water Pump I) Place the Sequencer XS-1 Enable key switch to OFF.

• 3B High-head SI Pump

2) Attempt to close the breaker.

a 3B Residual Heat Removal Pump a 3B Turbine Plant Cooling Water Pump a Verify one Auxiliary Building Exhaust Fan RUNNING a SEP Exhaust Fan

b. HVAC Equipment a Computer Room Chiller

• Battery Room Air Conditioner El 6E (30609)

c. Other plant equipment required to stabilize unit operation as determined by the Shift Manager

d. Notify Chemistry to verify proper operation of the plant SPING units 62 Locally Verify 3B 4KV Bus Tie To 3A Or 3C 4KV Bus 3AB22 -OPEN, RACKED OUT, AND LOCKED W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

63 Direct Operator To Place 3B Emergency Diesel Master Control Switch To NORMAL 64 Check Startup Transformer 3A 4KV Bus Perform the following:

Supply, 3AA05 CLOSED

a. jf previous attempts to close Startup Transformer 3A 4KV Bus Supply, 3AA05, in Steps 8 or 28 were NOT successful, THEN go to Step 65.

b. jf 3A 4KV bus is deenergized, THEN return to Step 28.

c. ffl 3A 4KV bus is energized by a source other than 3A Emergency Diesel, THEN return to Step 11.

d. E 3A 4KV bus is energized by 3A Emergency Diesel, THEN return to Step 8.

65 Check 3C Bus Supply From 3C Go to Step 76.

Transformer, 3AC16 OPEN 66 Check Tie Breakers To 3A and 3B 4KV Go to Step 76.

Buses OPEN 3A 4KV Bus Tie to 3B or 3C 4KV Bus, 3AA09 a 3B 4KV Bus Tie to 3A or 3C 4KV Bus, 3AB22 67 Check 3C 4KV Bus Lockout Perform the following:

Relay Reset

a. Direct Electrical Maintenance to determine and correct cause of 3C 4KV Bus Lockout Relay actuation.

b. WHEN cause of 3C 4KV Bus Lockout Relay actuation has been determined and corrected, THEN locally reset Bus Lockout Relay.

c. WHEN 3C 4KV Bus Lockout Relay has been reset, THEN do Steps 68 through 76.

d. Continue with Step 76.

W97:DH/ev/mrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 68 Check 3C Transformer Lockout Relay - Perform the following:

RESET

a. Try to determine and correct cause of 3C 4KV transformer lockout relay using 3-ONOP-092.4, C BUS TRANSFORMER MALFUNCTION

b. WHEN cause of 3C 4KV transformer lockout relay actuation has been determined and corrected, THEN locally reset lockout relay.

c. WHEN 3C 4KV transformer lockout relay has been reset, THEN do Steps 69 through 76.

d. Continue with Step 76.

69 Check 3C Transformer Supply Breakers - Perform the following:

AT LEAST ONE CLOSED

a. jf offsite power is QI available,

• 8W1 18 THEN go to Step 76.

OR b. IF offsite power is available, THEN locally close at least one 3C

• 8W154 Transformer Supply Breaker:

• 8W118 OR

• 8W154

c. ffl at least one 3C Transformer Supply Breaker can not be closed, THEN go to Step 76.

W97:DH/ev/mrg/In

STEP ACTION1EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

70 Stop Components Supplied By 3C 4KV jf any component supplied by 3C 4KV bus Bus can jQ[ be stopped, THEN go to Step 76.

• 3B Steam Generator Feedwater Pump

• 3C Condensate Pump

• A Standby Steam Generator Feedwater Pump

• 3B RCP Oil Lift Pump o 3C RCP Oil Lift Pump

• Water Treatment Plant

• Traveling Screens 71 Deenergize Load Centers Supplied By 3C 4KV

• Open 3E Load Center Supply Breaker (Polishing Area), 3AC04 a Open 3F13G Load Center Supply Breaker (Intake Area), 3AC1 1 W97:DH/ev/mrg/{n

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

72 Transfer 3C 4KV Bus To 3C Transformer

a. Open 3C Bus Alternate Supply from 4C Transformer, 3ACO1

b. Open 3C 4KV Bus Tie to 3A or 3B 4KV Bus, 3AC13

c. Locally verify all breakers on 3C 4KV Bus

- OPEN

d. Place 3C Bus Sync from 3C Transformer, 3AC16 to ON

e. Close 3C Bus Supply from 3C e. IF 3C Bus Supply from 3C Transformer, 3AC16 Transformer, 3AC16, can NOT be closed, THEN perform the following:

1) Place 3C Bus Sync from 30 Transformer, 3AC16 to OFF AND remove handle.

2) Direct Electrical Maintenance to determine cause of breaker failure.

3) Try to reenergize 3C 4KV Bus using 3-ONOP.-004.4, LOSS OF 3C 4KV BUS, while continuing with this procedure.

4) GotoStep76.

f. Place 30 Bus Sync from 30 Transformer, 3AC16 to OFF AND remove handle 73 Locally Verify No Breaker Targets Exist On if any 30 4KV bus breaker target is in, 3C 4KV Bus Breakers THEN do Q] energize the associated component until cause of breaker target has been determined and corrected.

W97:DH/evlmrgllri

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 74 Reenergize Load Centers Supplied By Perform the following:

3C 4KV Bus

a. Restore affected load center(s) to

• Close 3E Load Center Supply Breaker normal alignment using 3-OP-006, 480 (Polishing Area), 3AC04 VOLT SWITCHGEAR SYSTEM.

• Close 3F13G Load Center Supply Breaker b. Jf any load center can NOT be (Intake Area), 3AC1 1 reenergized from 3C 4KV bus, THEN reenergize affected load center(s) from Unit 4 using 3-OP-006, 480 VOLT SWITCHGEAR SYSTEM.

If any component powered from a deenergize motor control center must be started, the affected motor control center needs to be reenergized using 3-OP-007, 480 VOLT MOTOR CONTROL CENTER.

La. a a C C a I 75 Restart Components Supplied By 3C 4KV Bus As Directed By The Shift Manager

• 3C Condensate Pump

• 3B Steam Generator Feedwater Pump o A Standby Steam Generator Feedwater Pump

• 3B RCP Oil Lift Pump

• 3C RCP Oil Lift Pump

• Water Treatment Plant

• Other Plant equipment required to stabilize unit operation as determined by the Shift Manager 76 Check 3D 4KV Bus ALIGNED TO AN Try to reenergize 3D 4KV bus using ENERGIZED BUS 3-ONOP-004.5, LOSS OF 3D 4KV BUS, while continuing with this procedure.

• 3A4KVbus OR

• 3B4KVbus W97:DH/ev!mrg/ln

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

77 Verify All 4KV Buses ENERGIZED BY

- Perform the following:

OFFSITE POWER

a. Direct System Dispatcher to continue

• A 4KV bus efforts to restore offsite power to Unit 3 Startup Transformer and

• B 4KV bus 3C Transformer.

• D 4KV bus b. WHEN offsite power has been restored to Unit 3 Startup Transformer, THEN

• C 4KV bus return to 3-ONOP-004.1, SYSTEM RESTORATION FOLLOWING LOSS OF OFFSITE POWER.

c. WHEN offsite power has been restored to 3C Bus Transformer, THEN return to 3-ONOP-004.1, SYSTEM RESTORATION FOLLOWING LOSS OF OFFSITE POWER.

78 Return To Procedure And Step In Effect END OF TEXT W97:DH/ev/mrg/In

ATTACHMENT I (Page 1 of 1) 3A 4KV BUS STRIPPING

1. Verify the following breakers open:

• 3AA22, 3A 4KV Bus Emergency Tie To Unit 4 Startup Transformer

• 3AA09, 3A 4KV Bus Tie To 3B Or 3C 4KV Bus

• 3AA05, Startup Transformer 3A 4KV Bus Supply

• 3AA02, Auxiliary Transformer 3A Bus Supply

• 3AA03, Steam Generator Feed Pump 3A

• 3AA07, Heater Drain Pump 3A o 3AA21, Condensate Pump 3A

• 3AA13, Safety Injection Pump 3A

• 3AA15, Residual Heat Removal Pump 3A

• 3AA12, Component Cooling Water Pump 3A

• 3AAOI, Reactor Coolant Pump 3A

• 3AA19, Intake Cooling Water Pump 3A

• 3AAI I Turbine Plant Cooling Water Pump 3A

• 3AAI 6, Circulating Water Pump 3A1

• 3AA1 8, Circulating Water Pump 3A2

• 3AA08, 3A Load Center

• 3AA14, 3C Load Center

2. IF Supply From 4KV Bus 3A, 3ADO1, is open, THEN verify Feeder To 4KV Bus 3D, 3AA17, is open.

ffl Supply From 4KV Bus 3A, 3ADOI, is closed, THEN perform the following:

a. IF Station Blackout Breaker, 3AD07, is closed, THEN perform the following:

1) Open Station Blackout Breaker, 3AD07.

2) Direct Unit 4 RCO to open Station Blackout Breaker, 4AD07.

b. Verify breaker for Intake Cooling Water Pump 3C, 3AD05, is open.

c. Verify breaker for Component Cooling Water Pump 3C, 3AD04, is open.

d. IF breaker for Intake Cooling Water Pump 3C, 3AD05, Q breaker for Component Cooling Water Pump 3C, 3AD04, can NQI be opened, THEN open Feeder To 4KV Bus 3D, 3AA1 7, Supply From 4KV Bus 3A. 3ADOI.

4. Notify Unit 3 Reactor Operator that 3A 4KV bus stripping has been completed.

W97:DH/ev/mrci/In

ATTACHMENT 2 (Page 1 of 1) 3B 4KV BUS STRIPPING

1. Verify the following breakers open:

• 3AB22, 3B 4KV Bus Tie To 3A Or 3C 4KV Bus

• 3AB05, Startup Transformer 3B 4KV Bus Supply

• 3AB02, Auxiliary Transformer 3B Bus Supply

• 3AB1O, Heater Drain Pump 3B

• 3AB21, Condensate Pump 3B

• 3AB12, Safety Injection Pump 3B

• 3AB1 5, Residual Heat Removal Pump 3B

• 3ABI 3, Component Cooling Water Pump 38

• 3ABOI, Reactor Coolant Pump 3B

• 3AB06, Reactor Coolant Pump 3C

• 3AB17, Intake Cooling Water Pump 3B

• 3AB1 1, Turbine Plant Cooling Water Pump 3B

• 3AB16, Circulating Water Pump 3B1

• 3AB18, Circulating Water Pump 3B2

• 3AB09, 3B Load Center

• 3AB14, 3D Load Center

2. IF Supply From 4KV Bus 3B, 3AD06, is open, THEN verify Feeder To 4KV Bus 3D, 3AA19, is open.

3. IF Supply From 4KV Bus 38, 3AD06, is closed, THEN perform the following:

a. IF Station Blackout Breaker, 3AD07, is closed, THEN perform the following:

1) Open Station Blackout Breaker, 3AD07.

2) Direct Unit 4 RCO to open Station Blackout Breaker, 4AD07.

b. Verify breaker for Intake Cooling Water Pump 3C, 3AD05, is open.

c. Verify breaker for Component Cooling Water Pump 3C, 3AD04, is open.

d. IF breaker for Intake Cooling Water Pump 3C, 3AD05, Q breaker for Component Cooling Water Pump 3C, 3AD04, can NOT be opened, THEN open Feeder To 4KV Bus 3D, 3AB19, SuppIy From 4KV Bus 38, 3AD06.

4. Notify Unit 3 Reactor Operator that 38 4KV bus stripping has been completed.

FINAL PAGE W97:DH/ev/mrQ/In

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01041003200 JPM: Preparation for OMS Task

Title:

Operation JPM No: 01041003201 K/A

Reference:

010 A4.03 RO 4.0 SRO 3.8 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• Unit 3 is in Mode 3.

• The plant is being shut down to Cold Shutdown in accordance with 3-GOP-305, Hot Standby to Cold Shutdown.

• Actions in 3-GOP-305, up through Step 5.2.9, have been complete.

• 3-NOP-041.04, Overpressure Mitigating System, Section 4.1.1, is complete; up through Step 4.1.1.6.E.

• Attachment 1, OMS Valve Alignment, of 3-NOP-041 .04 has been completed.

• 3-OSP-041 .4, Overpressure Mitigating System Nitrogen Backup Leak and Functional Test, has been completed within the past 31 days.

• 3-OSP-206.2, Quarterly Inservice Valve Testing, has been performed within the last 31 days.

Initiating Cue:

• Per 3-GOP-305, Step 5.2.10, you have been directed to complete 3-NOP-041.04, Overpressure Mitigating System, Section 4.1.1, starting with Step 4.1.1.7.

2011 NRC Exam(R0)JPM-c NUREG 1021 Rev9AppendixC

Appendix C Page 2 of 12 Form ES-C-I Task Standard:

• Applicant cycles MOV-3-535 and PCV-3-456 in accordance with 3-NOP-041 .04, Section 4.l.l.B-E.

• Applicant initiates a manual Safety Injection within 16 minutes (see ADM-232, Time Critical Action Program, Attachment 2, Time Critical Operator Actions in the PTN PSA Model, Event ID RHFPACTSIM, Page 6 of 7) after the automatic SI setpoint of 1730 psig has been exceeded.

Required Materials:

• 3-NOP-041 .04, Overpressure Mitigating System, Section 4.1.1, marked up through Step 4.1.1.6.E.

General

References:

• 3-NOP-041 .04, Overpressure Mitigating System

• 3-GOP-305, Hot Standby to Cold Shutdown Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

rApendix C Page 3 of 12 Form ES-C-I SIMULATOR SETUP

1. Reset to IC 193 for JPM or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-01041003201 and Execute.

4. Ensure Simulator Operator Checklist is complete.

6. Acknowledge alarms and place simulator in FREEZE.

7. Provide the Applicant with a copy of 3-NOP-041 .04, Overpressure Mitigating System.

8. When the last performance of this JPM is completed for the day, delete any temporary lCs that were created and delete the contents of the Recycle Bin.

2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 12 Form ES-C-I Denote critical steps with a check mark (i4 Start Time SAT STEP I Obtain required reference materials.

UNSAT STANDARD Applicant obtains a copy of 3-NOP-041 .04, Overpressure Mitigating System.

CUE Provide the Applicant with a copy of 3-NOP-041 .04, Overpressure Mitigating System, marked up through Step 4.1.1.6.E.

COMMENT 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 12 Form ES-C-I NOTE

• OMS Loop OperabiIiy Test is required to be completed prior to placing NOTE OMS in seivce if NOT cFone within the last 31 day&

• Only one loop of OMS shall be tested a a time.

PERFORM the following in the Control Room SAT UNSAT IF OMS N2 Backup leak and functional testing was NOT STEP 2 performed within the last 31 days, THEN PERFORM 3-OS P 041.4, Overpressure Mitigating System Nitrogen Backup Leak and Functional Test.

(3-NOP-041.04, Step 4.1.1.7 and 4.1.1.7.A)

Applicant notes that, per the Initial Conditions, 3-OSP-041 .4, STANDARD Overpressure Mitigating System Nitrogen Backup Leak and Functional Test, has been performed within 31 days.

CUE COMMENT 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-I CYCLE MOV-3-535, PRZ PORV BLOCK VALVE, as follows: SAT U NSAT IF OMS 1ST Valve testing NOT performed within the last 31 STEP 3 days, THEN PERFORM 3-OSP-206.2, Quarterly Inservice Valve Testing.

(3-NOP-041.04, Step 4.1.1.7.B and 4.1.1.7.B.(1)

Applicant notes that, per the Initial Conditions, 3-OSP-206.2, STANDARD Quarterly Inservice Valve Testing, has been performed within the last 31 days.

CUE COMMENT STEP 4 CLOSE MOV-3-535, PRZ PORV BLOCK VALVE.

(3-NOP-041.04, Step 4.1.1.7.B.(2)

Applicant places the control switch for MOV-3-535, PRZ PORV STANDARD BLOCK VALVE, to the CLOSE position. Notes that the green CLOSE light is ON and the red OPEN light is OFF.

CUE COMMENT 2011 NRC Exam(RO)JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 12 Form ES-C-I NOTE NOTE UNSAT resuts should he recorded in the Unit Narrauve L0Q.

STEP 5 CYCLE PCV-3-456, PRZ PORV, full OPEN then CLOSED. SAT j UNSAT (3-NOR.041.04, Step 4.1.1.7.C.)

Applicant places the control switch for PCV-3-456, PRZ PORV, to the OPEN position. Notes that the green CLOSE light is OFF and the red OPEN light is ON.

STANDARD Applicant places the control switch for PCV-3-456, PRZ PORV, to the CLOSE position. Notes that the green CLOSE light is ON and the red OPEN light is OFF.

Applicant marks SAT in the table.

CUE COMMENT SAT STEP 6 ENSURE PCV-3-456, PRZ PORV, is in AUTO.

, UNSAT (3-NOP-041.04, Step 4.1 .1 .7.D.)

STANDARD Applicant checks that the control switch for PCV-3-456, PRZ PORV is in the AUTO (mid) position.

CUE COMMENT 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 Form ES-C-I OPEN MOV-3-535, PRZ PORV BLOCK VALVE.

STEP 7 SAT

.q UNSAT (3-NOP-041.04, Step 4.1 .1 .7 .E.)

Applicant places the control switch for MOV-3-535, PRZ PORV STANDARD BLOCK VALVE, to the OPEN position. Notes that the green CLOSE light is OFF and the red OPEN light is ON.

CUE COMMENT CYCLE MOV-3-536, PRZ PORV BLOCK VALVE, as follows: SAT UNSAT IF OMS 1ST Valve testing NOT performed within the last 31 STEP 8 days, THEN PERFORM 3-OSP-206.2, Quarterly Inservice Valve Testing.

(3-NOP-041.04, Step 4.1.1.7.F and 4.1.1.F.(1)

Applicant notes that, per the Initial Conditions, 3-OSP-206.2, Quarterly Inservice Valve Testing, has been performed within STANDARD the last 31 days.

CUE COMMENT 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 12 Form ES-C-I STEP 9 CLOSE MOV-3-536, PRZ PORV BLOCK VALVE. SAT q UNSAT (3-NOP-041.04, Step 4.1.1.7.F.(2)

Applicant places the control switch for MOV-3-536, PRZ PORV STANDARD BLOCK VALVE, to the CLOSE position. Notes that the green CLOSE light is ON and the red OPEN light is OFF.

CUE COMMENT 2011 NRC Exam (RO) JPM-c NUREG 1021 Rev9AppendixC

Appendix C Page 10 of 12 Form ES-C-I NOTE NOTE UNSAT resuts snould be recorded in the Unit Narrative Lo STEP 10 CYCLE PCV-3-455C, PRZ PORV, full OPEN then CLOSED. SAT j UNSAT (3-NOP-041.04, Step 4.1.1.7.G.)

Applicant places the control switch for PCV-3-455C, PRZ PORV, to the OPEN position. Notes that the green CLOSE light is OFF and the red OPEN light is ON.

Applicant notes indications of a leak, including, but not limited to:

. PZRIRCS pressure decreasing

. PZR level decreasing

. Annunciators:

o A4/1 PORV/SAFETYVALVE OPEN o A 9/2 PRZ CONTROL HI/LOW PRESSURE o A7/2 PZRPORVHITEMP Applicant places the control switch for PCV-3-456, PRZ PORV, STANDARD to the CLOSE position. Notes that the green CLOSE light remains OFF and the red OPEN light remains OFF. (Valve does NOT close)

Within 16 minutes (per PSA), Applicant initiates a manual SI by depressing at least one of the two SAFETY INJECTION INITIATION pushbuttons.

Manual SI is warranted per the following:

. O-ADM-21 1, Emergency and Off-Normal Procedure Usage, which allows manual action when an automatic action fails.

. 3-EOP-E-O Entry Conditions.

. Annunciator C 3/6 PZR LO PRESS SI, Operator Actions.

TERMINATING CUE:

CUE Evaluator informs the Applicant that another operator will perform subsequent actions. The JPM is complete.

COMMENT Stop Time 2011 NRCExam(RO)JPM-c NUREG 1021 Rev9AppendixC

• Appendix C Page II of 12 Form ES-C-I Verification of Completion:

Job Performance Measure No. 01041003201 Examinees Name:

Examiners Name:

Date Performed:

Facihty Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Resu It: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-c NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET I will explain the initial condtons, whIch steps to simulate or discuss, and provide ini{iatihg cues.

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

Initial Conditions:

• Unit3isinMode3.

The plant is being shut down to Cold Shutdown in accordance with 3-GOP-305, Hot Standby to Cold Shutdown.

o Actions in 3-GOP-305, up through Step 5.2.9, have been complete.

o 3-NOP-041.04, Overpressure Mitigating System, is complete, up through Step 4.1 .1 .6 .E.

o Attachment 1, OMS Valve Alignment, of 3-NOP-041 .04 has been completed.

o 3-OSP-041 .4, Overpressure Mitigating System Nitrogen Backup Leak and Functional Test, has been completed within the past 31 days.

• 3-OSP-206.2, Quarterly lnservice Valve Testing, has been performed within the last 31 days.

Initiating Cue:

o Per 3-GOP-305, Step 5.2.10, you have been directed to complete 3-NOP-041.04, Overpressure Mitigating System, Section 4.1.1, starting with Step 4.1.1.7.

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.

2011 NRC Exam (RO) JPM-c NUREG 1021 Rev 9 Appendix C

Procedure No.

TURKEY POINT UNIT 3 3-NO P-041 .04.

NORMAL OPERATING PROCEDURE Revision No.

FPL SAFETY RELATED 3 CONTINUOUS USE

Title:

OVERPRESSURE MITIGATING SYSTEM Responsible Department: OPERATIONS Special Considerations:

This is an Upgraded Procedure. Initial use should include increased awareness because of potential technical and/or sequential changes to the procedure. After initial use of this procedure, provide comments back to the Procedure Upgrade Project.

FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document.

DATE VERIFIED________ INITIAL_________

Revision Approved By Approval Date UNIT # UNIT 3 DATE DOCT PROCEDURE 0 Frank Wurster 12/14/08 DOCN 3-NOP-041 .04 SYS STATUS COMPLETED 3 Tom Wall 04/26/11 REV 3

1. OFPGS

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 2 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 REVISION

SUMMARY

Rev. No. Description 3 AR 1644653, 04126111, David Dagitz Revised Attachment 1 to change the normal position of Valves 3-40-2322, 3-40-2323, 3-40-248, 3-40-249, 3-40-258, and 3-40-259 from CLOSED to CLOSED & CAPPED. (CR 460181) Change PI-4-4886A to PI-3-4886A, Section 4.1.1 Step 6.0(7).

2 AR 589449589449 10123110, David Dagitz This expedited revision is to add Attachments 2 and 3 to the procedure to allow using temporary nitrogen bottles for the OMS in Modes 5, 6, or defueled and to ensure the proper coated bottles are back in place prior to entering Mode 4 from Mode 5.

PCR 08-5983, 03124109, Dennis Bonsall Revised procedure for implementation of PC/M 07-044, which adds a nitrogen bottle rack for additional nitrogen bottles and tubing for nitrogen bottle connection.

0 This procedure upgraded per PCR 08-1 653, 12113I08, Frank Wurster.

Upgraded entire procedure to Writers Guide standards.

Moved Prerequisites into applicable sections.

Deleted QA Pages and references to them throughout. Logging the activity satisfies all QA record requirements. Deleted logging statements throughout.

• The requirements on what to log are covered in Conduct of Operations, 0-ADM-200 and Operations Narrative Logbooks, 0-ADM-204.

Added specific guidance for checking N 2 bottles in containment.

Added additional guidance for changing 2 N bottles.

This procedure supersedes 3-OP-41 .4 approved 2/21/05.

REVISION NO: PROCEDURETITLE: - PAGE:

OVERPRESSURE MITIGATING SYSTEM 3 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 4 2.0 PRECAUTIONS AND LIMITATIONS 4 3.0 PREREQUISITES 4 4.0 NORMAL OPERATION 5 4.1 Startup 5 4.1.1 Preparation for OMS Operation 5 4.2 Operation 12 4.2.1 Establishing and Checking OMS Operation 12 4.3 Shutdown 13 4.3.1 Transferring OMS to Normal 13 5.0 INFREQUENT OPERATIONS 14 6.0 RECORDS 14

7.0 REFERENCES

AND COMMITMENTS 14 ATTACHMENTS ATTACHMENT 1 DM5 Valve Alignment 16 ATTACHMENT 2 OMS Backup Nitrogen Cylinder Verification Modes 5, 6, and Defueled 20 ATTACHMENT 3 OMS Backup Nitrogen Cylinder Verification - Prior to Mode 4 from Mode 5 21

REViSION NO.: - POCEbURE TiTLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 4 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 1.0 PURPOSE This procedure provides guidance for aligning and placing the Overpressure Mitigating System (OMS) in service and removing from service.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions

1. Compressed gas cylinders shall always be stored upright, with their caps in place, in approved safe areas away from radiators, furnaces, and other sources of heat.

2. Stored cylinders must be restrained at all times.

3. Compressed gas cylinders should never be subjected to temperatures above 125°F.

4. Pressure shall be relieved before dismantling valves, gauges, or similar equipment associated with compressed gas.

2.2 Limitations

1. Extreme care should be used to prevent damage to adjacent equipment when working on top of the Pressurizer.

3.0 PREREQUISITES None

ViSiOUO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 5 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.0 NORMAL OPERATION 4.1 Startup 4.1.1 Preparation for OMS Operation (9

Section 4.1.1 Step I through Section 4.1.1 Step 4 may be performed out of order.

CHECK Instrument Air System available.

Previous performance of Attach en MS Valve Alignment, may be verified by the Shift Manager file if NO work has been performed on PORVs, PORV Back-up N 2 System, Instrument Air to PORVs, or in upper area of the Pressurizer cubicle and personnel safety is a concern. Use of a prevjos

.Attachment j.,Q.M.S.XLalve Alignment, II hc rriirdedjn the U nit Narrative jQg CHECK OMS valve alignment by completion of Attachment 1, OMS Valve Alignment.

ENSURE nitrogen regulator outlet pressure for PCV-3-4885 and PCV-3-4886 is established in accordance with 3-PM 1-041.39, Reactor Coolant System Power Operated Relief Valve Actuator Overhaul/Maintenance.

Exercising the PORV Block Valve is NOT required per T.S. 4.4.4 if the PORV Block Valve is closed due to a leaky or inoperable PORV.

94 IF PORV B,jp \AIve operability has NOT been demonstrated within

--- the last 92 days, THEN ENSURE operability using 3-OSP-206.2, Quarterly Inservice Valve Testing, prior to placing OMS in service.

VISION I4OJ PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 6 of 21 PROCEDURE NO.:

3-NOP-041.04 TURKEY POINT UNIT 3 4.1.1 Preparation for OMS Operation (continued)

If there is an adequate supply of charge itrogen bottles that meet SPEC-C-034, Protective Coatings for Service Level I Applications Inside the Reactor Containment Building, as indicated by being marked Nitrogen for PRZ PORVs Only, then Attachment 3, OMS Backup Nitrogen Cylinder Verification Prior to Mode 4 from Mode 5, should be performed.

CHECK N 2 bottles inside Containment using either Attachment 2, OMS Backup Nitrogen Cylinder Verification Modes 5, 6, and Defueled, OR Attachment 3, OMS Backup Nitrogen Cylinder Verification Prior to Mode 4 from Mode 5.

Section 4.1.1 Step 6 and Section 4Ttep 7 may be performed concurrently.

PERFORM the following in Containment:

N6T The nitrogen cylinder isolation val is considered 3-40-2443, PORV NITROGEN CYLINDER ISOLATION, when in-service. The valve tag for 3-40-2443 is moved with the flex hose connection when the cylinder is replaced.

1!

IF N 1-s/fr 2 pressul(e is less than 2000 psig as indicated on P I-3-4885A, PCV-3-4885 UPSTREAM PRESSU RE INDICATOR, THEN CHANGE the N 2 bottle as follows:

CLOSE 3-40-2443, PORV NITROGEN CYLINDER ISOLATION.

No vent valve exists in the N 2 cyli]

as the flex hose is disconnected.

Slowly DISCONNECT flex hose from in-service N 2 bottle.

CONNECT flex hose to new N 2 bottle.

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 7 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4A.1 Preparation for OMS Operation (continued)

(continued)

(4) ENSURE the valve label for 3-40-2443 is moved from the nitrogen cylinder just removed from service to the nitrogen cylinder being placed in service.

Slowly OPEN new in-service cylinder isolation valve 3-40-2443.

/..(6) ENSURE connection NOT leaking.

/7 Maximum design inlet pressure forc ator is 3000 psig.

jJ/ (7) CHECK N 2 pressure greater than 2000 psig on J( PI-3-4885A.

&j / (8) IF PI-3-4885A reads less than 2000 psig, THEN REPEAT Section 4.1.1 Step 6.A(1) through

/

/fk Section 4.1.1 Step 6.A(7).

The operating pressure range for he gulator is between 2000 and 2400 psig with an output pressure range of 90 to 96 psig.

ENSURE PCV-3-4885 set to maintain 90 to 96 psig on

_)L/ PI-3-4885B, PCV-3-4885 DOWNSTREAM PRESSURE INDICATOR.

REVISION NO.: - PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 8 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.1.1 Preparation for OMS Operation (continued)

(continued)

The nitrogen cylinder isolation valvidered 3-40-2444, PORV NITROGEN CYLINDER ISOLATION, when in-service. The valve tag for 3-40-2444 is moved with the flex hose connection when the cylinder is laced.

NIb >O(O IF N2 pressure is Ys tt1n 2000 psig, as indicated on PI-3-4886A, PCV-3-4886 UPSTREAM PRESSURE INDICATOR, THEN CHANGE the N 2 bottle as follows:

(1) CLOSE 3-40-2444, PORV NITROGEN CYLINDER in ISOLATION.

NO vent valve exists in the N 2 cylir i header. Pressure will be relieved as the flex hose is disconnected.

(Vfk (2) Slowly DISCONNECT flex hose from in-service N 2

/ bottle.

tO/Pc (3) CONNECT flex hose to new N 2 bottle.

t/ (4) ENSURE valve label 3-40-2444 moved from nitrogen I /f cylinder just removed from service to nitrogen cylinder being placed in service.

Slowly OPEN new in-service cylinder stop valve

/ 3-40-2444, AND ENSURE connection NOT leaking.

2 Maximum design inlet pressure for the regulator is 3000 psig.

CHECK N 2 pressure greater than 2000 psig on PI-3-4886A.

IF PI-3-4886A reads less than 2000 psig, THEN REPEAT Section 4.1.1 Step 6.0(1) through Section 4.1.1 Step 6.C(6).

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 9 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4t1 Preparation for OMS Operation (continued) 1(continued)

The operating pressure range forulator is beeen 2000 and 2400 PSIG with an output pressure range of 90 to 96 PSIG.

CHECK PCV-3-4886 set to maintain 90 to 96 PSIG on PI-3-4886B, PCV-3-4886 DOWNSTREAM PRESSURE INDICATOR.

N Operating Experience has demonstra e that cycling SV-3-6427A, REACTOR COOLANT SYSTEM HOT LEG LOOP A SAMPLE LINE SOLENOID VALVE, during OMS operation can cause a pressure event resulting in PORV actuation. This is due to the common instrument tap used by OMS pressure sensing line for PT-3-405, RCS Wide Range Pressure to OMS, and the sample line.

INITIATE a clearance on fuses for SV-3-6427A, REACTOR COOLANT SYSTEM HOT LEG LOOP A SAMPLE LINE SOLENOID VALVE, to Assistant Operations Manager per 0-ADM-21 2.

VION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 10 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.1.1 Preparation for OMS Operation (continued) INITIAL

7. PERFORM the foflowing in the Control Room NOTE

• OMS Loop Operability Test is required to be completed prior to placing OMS in service if NOT done within the last 31 days.

Only one loop of OMS shall be tested at a time.

A. IF OMS N 2 Backup leak and functional testing was NOT performed within the last 31 days, THEN PERFORM 3-OSP-041 .4, Overpressure Mitigating System Nitrogen Backup Leak and Functional Test.

B. CYCLE MOV-3-535, PRZ PORV BLOCK VALVE, as follows:

(1) IF OMS 1ST Valve testing NOT performed within the last 31 days, THEN PERFORM 3-OSP-206.2, Quarterly Inservice Valve Testing.

(2) CLOSE MOV-3-535, PRZ PORV BLOCK VALVE.

IV NOTE UNSAT results should be recorded in the Unit Narrative Log.

C. CYCLE PCV-3-456, PRZ PORV, full OPEN then CLOSED.

D. ENSURE PCV-3-456, PRZ PORV, is in AUTO.

IV E. OPEN MOV-3-535, PRZ PORV BLOCK VALVE.

IV

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 11 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.1.1 Preparation for OMS Operation (continued) INITIAL

7. (continued)

F. CYCLE MOV-3-536, PRZ PORV BLOCK VALVE, as follows:

(1) IF OMS 1ST Valve testing NOT done within the last 31 days, THEN PERFORM 3-OSP-206.2, Quarterly Inservice Valve Testing.

(2) CLOSE MOV-3-536, PRZ PORV BLOCK VALVE.

IV NOTE UNSAT results should be recorded in the Unit Narrative Log.

G. CYCLE PCV-3-455C, PRZ PORV, full OPEN then CLOSED.

PORV SAT UNSAT PCV-3-455C H. ENSURE PCV-3-455C, PRZ PORV, is in AUTO.

IV I. OPEN MOV.-3-536, PRZ PORV BLOCK VALVE.

IV

4 REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 12 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 42 Operation INITIAL 4.2.1 Establishing and Checking OMS Operation

1. CHECK Section 4.1.1 completed.

NOTE The following values should indicate within 20 psig of each other.

2. COMPARE and RECORD values shown by the following indicators to verify availability of PT-3-403 and PT-3-405:

• P1-3-405 (VPB) psig

• P1-3-403 (VPA) psig o P 1-3-402 (VPA) psig

3. IF values are greater than 20 psig of each other, THEN NOTIFY I&C.

4. WHEN RCS Cold Leg Temperature is less than 300°F, THEN:

A. PLACE Primary OMS Mode Selector Switch in LO PRESS OPS.

IV B. PLACE Backup OMS Mode Selector Switch in LO PRESS OPS.

IV

5. CHECK the following permissive status lights ON:

o PRIMARY ALIGNED

• BACKUP ALIGNED

6. RECORD OMS established and operating in Unit Narrative Log.

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 13 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.3 Shutdown 4.3.1 Transferring OMS to Normal

1. CHECK all RCS cold leg temperatures greater than 275°F, as required by T.S. 3.4.9.3.

2. CHECK RCS pressure less than 415 psig.

3. CHECK OMS operating in LO PRESS OPS.

4. PLACE both OMS Control Switches in NORMAL:

• PCV-3-455C, BACKUP OMS

• PCV-3-456, PRIMARY OMS

5. CHECK the following permissive status lights OFF:

o PRIMARY ALIGNED

• BACKUP ALIGNED NOTE Annunciator should clear when RCS pressure rises above 415 PSIG.

6. CHECK Annunciator A 3/1, OMS LO PRESS OPERATION, in ALARM.

7. REQUEST Assistant Operations Manager release ECO on SV-3-6427A fuses.

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 14 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 5.0 INFREQUENT OPERATIONS None 6.0 RECORDS

1. Date, time, and section completed, shall be entered in Unit Narrative Log.

2. Problems encountered while performing procedure (i.e.,

malfunctioning equipment, delays due to change in plant conditions, etc.) should be entered in Unit Narrative Log.

7.0 REFERENCES

AND COMMITMENTS 7.1 References 7.1.1 Implementing

• O-ADM-212, In-Plant Equipment Clearance Orders

• 3-PMI-041.39, Reactor Coolant System Power Operated Relief Valve Actuator Overhaul/Maintenance o 3-OSP-041 .4, Overpressure Mitigating System Nitrogen Backup Leak and Functional Test

• O-OSP-200.1, Schedule of Plant Checks and Surveillances

• 3-OSP-206.2, Quarterly Inservice Valve Testing 7.1.2 Developmental I. Technical Specifications

• Section 3/4.4.9, Pressure/Temperature Limits e Section 3.4.9.3, Overpressure Mitigating Systems

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 15 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 7.1.2 Developmental (continued)

2. Plant Procedures o 0-ADM-21 5, Plant Surveillance Tracking Program

3. Plant Drawings

• 5610-T-D-16A, Sheet 1, Pressurizer Pressure Protection and Overpressure Mitigation System

• 5613-M-3041 Sheet 4, Reactor Coolant System PORV Control

4. Miscellaneous Documents

• PC/M 89-565, Pressurizer PORV Air and Nitrogen Supply Tubing Enhancement

• PC/M 90-220, RTD Bypass Elimination Modification and Eagle 21 Installation

• CR 99-0508

• PC/M 01-050, AOV Modification and Program Parameter Documentation o PTN-ENG-SENS-03-0046, Enabling the Cold Overpressure Mitigation System at Higher Temperature

• Response to GL 90-06, L-92-285 7.1.3 Management Directives None 7.2 Commitments None

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 16 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 ATTACHMENT I OMS Valve Alignment (Page 1 of 4)

EXCEPTIONS COMPONENT NUMBER COMPONENT DESCRIPTION REMARKS PERSONNEL PERFORMING MANIPULATIONS PRINTED NAME INITIALS COMPLETION OF LINEUP DATE LINEUP (MM/DDIYY): TIME LINEUP (HH:MM, 24 HR CLOCK):

COMPLETED: / COMPLETED:

LINEUP PRINTED NAME / SIGNATURE:

COMPLETED BY:

REVIEW OF LINEUP LINEUP PRINTED NAME I SIGNATURE: DATE (MM/DDJYY):

REVIEWED BY: /

REVISION NO.; PROCEDURE TITLE; PAGE; OVERPRESSURE MITIGATING SYSTEM 17 of 21 PROCEDURE NO.;

3-NOP-041 .04 TURKEY POINT UNIT 3 ATTACHMENT I OMS Valve Alignment (Page 2 of 4)

COMPONENT POSITION ALIGNED VERIFIED NUMBER COMPONENT DESCRIPTION REQUIRED BY BY In Containment entrance to or inside Pressurizer cubicle NOTE I: Position can be verified by Control Room position indication.

MOV-3-536 OPEN PRZ PORV BLOCK VALVE NOTE I PRZ PORV BLOCK VALVE OPEN MOV-3-535 NOTE I LOCKED!

OPENING THROTTLE VALVE LOCKING 3-40-2348 FOR PCV-3-455C DEVICE INTACT LOCKED!

CLOSING THROTTLE VALVE FOR LOCKING 3-40-2349 PCV-3-455C DEVICE INTACT LOCKED!

OPENING THROTTLE VALVE LOCKING 3-40-2350 FOR PCV-3-456 DEVICE I NTACT

. LOCKED!

CLOSING THROTTLE VALVE FOR LOCKING 3-40-2351 PCV-3-456 DEVICE INTACT

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 18 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 ATTACHMENT I OMS Valve Alignment (Page 3 of 4)

COMPONENT POSITION ALIGNED VERIFIED NUMBER COMPONENT DESCRIPTION REQUIRED BY BY In Containment on side of Pressurizer cubicle PORV INSTRUMENT AIR 3-40-247 OPEN ISO LATI 0 N PORV INSTRUMENT AIR LINE CLOSED &

3-40-249 VENT CAPPED PORV INSTRUMENT AIR LINE CLOSED &

3-40-248 VENT CAPPED PORV NITROGEN CYLINDER 3-40-2443 OPEN ISO LATI 0 N PORV NITROGEN REGULATOR 3-40-243 OPEN OUTLET PORV INSTRUMENT AIR 3-40-257 OPEN ISO LATI 0 N PORV INSTRUMENT AIR LINE CLOSED &

3-40-259 VENT CAPPED PORV INSTRUMENT AIR LINE CLOSED &

3-40-258 VENT CAPPED PORV NITROGEN CYLINDER 3-40-2444 OPEN ISO LATI 0 N PORV NITROGEN REGULATOR 3-40-253 OPEN OUTLET 3-40-2322 PORV TEST CONN ISOLATION CLOSED &

CAPPED CLOSED &

3-40-2323 PORV TEST CONN ISOLATION CAPPED

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 19 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 ATTACHMENT I OMS Valve Alignment (Page 4 of 4)

COMPONENT POSITION ALIGNED VERIFIED NUMBER COMPONENT DESCRIPTION REQUIRED BY BY In Containment on side of Pressurizer cubicle (continued)

NOTE 2: Valves with same number appear as two handles on same block. Care should be taken to verify correct alignment.

3-40-2357 PORV N 2 PI-3-4886A VENT NOTE 2 VALVE CLOSED 3-40-2357 PORV N 2 PI-3-4886A ISOLATION NOTE 2 VALVE OPEN 3-40-2358 PORV N 2 PI-3-4886B VENT NOTE 2 VALVE CLOSED 3-40-2358 PORV N 2 PI-3-4886B ISOLATION NOTE 2 VALVE OPEN 3-40-2359 PORV N 2 PI-3-4885A VENT NOTE 2 VALVE CLOSED 3-40-2359 PORV N 2 PI-3-4885A ISOLATION NOTE 2 VALVE OPEN 3-40-2360 PORV N 2 PI-3-4885B VENT NOTE 2 VALVE CLOSED 3-40-2360 PORV N 2 PI-3-4885B ISOLATION NOTE 2 VALVE OPEN

REVISION NO.: PROCEDURE TITLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 20 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3.

ATTACHMENT 2 INITIAL OMS Backup Nitrogen Cylinder Verification

- Modes 5, 6, and Defueled (Page 1 of 1)

1. OMS backup nitrogen cylinders are staged inside Containment as follows:

A. Six fully charged (2200 to 2450 psig) nitrogen cylinders in 58-foot elevation storage rack next to the Pressurizer.

B. All nitrogen cylinders are 300 cu ft cylinders stamped with DOT or ICC #3AA2400.

C. Nitrogen bottles stored as follows:

(1) Upright (2) Restrained (3) Caps in place (4) In approved safe areas away from:

• Radiators

• Furnaces a Other sources of heat

• Temperature above 125 degreesF NITROGEN BOTTLE VERIFICATION DATE VERIFICATION (MM/DDIYY): TIME (HH:MM, 24 HR CLOCK):

COMPLETED: I I VERIFIED:

VERIFICATION PRINTED NAME I SIGNATURE:

COMPLETED BY:

REVIEW OF NITROGEN BOTTLE VERIFICATION VERIFICATION PRINTED NAME I SIGNATURE: (MMIDDIYY):

REVIEWED BY: I DATE:

REVISION 11O.: - - POCEE5UE TitLE: PAGE:

OVERPRESSURE MITIGATING SYSTEM 21 of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 ATTACHMENT 3 INITIAL OMS Backup Nitrogen Cylinder Verification

- Prior to Mode 4 from Mode 5 (Page 1 ofl)

1. OMS backup nitrogen cylinders are staged inside Containment as follows:

A. Six fully charged (2200 to 2450 psig) nitrogen cylinders in 58-foot elevation storage rack next to the Pressurizer.

B. All nitrogen cylinders are 300 cu ft cylinders stamped with DOT or ICC #3AA2400.

C. Gas cylinders are coated per SPEC-C-034 as indicated by being marked Nitrogen for PZR PORVs only.

D. Nitrogen bottles stored as follows:

(1) Upright (2) Restrained (3) Caps in place (4) In approved safe areas away from:

Radiators Furnaces Other sources of heat Temperature above 125 degrees°F NITROGEN BOTTLE VERIFICATION DATE VERIFICATION (MM/DD/YY): TIME (HH:MM, 24 HR CLOCK):

COMPLETED: I I VERIFIED:

VERIFICATION PRINTED NAME I SIGNATURE:

COMPLETED BY: I REVIEW OF NITROGEN BOTTLE VERIFICATION VERIFICATION EPRINTED NAME I SIGNATURE: (MMIDDIYY):

REVIEWED BY: j I DATE:

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01041038100 JPM: Start3ARCPin TaskTitle: Mode 3 JPMNo: 01041038101 K/A

Reference:

003 A2.03 RO 2.7 SRO 3.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• Unit3isinMode3

• 3A RCP is shut down.

• In preparation for startup of 3A RCP, Steps up through 4.1.1.16 of 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, have been completed.

o The initial, 1-minute run is complete.

Initiating Cue:

• You have been directed to start up the 3A RCP, beginning with Step 4.1.1.17 of 3-NOP-041 .O1A.

2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix c

Appendix C Page 2 of 8 Form ES-C-I Task Standard:

• 3A RCP started lAW 3-NOP-041 .O1A.

• 3A RCP secured lAW 3-NOP-041 .O1A prior to the RCP breaker trip on overcurrent.

Required Materials:

• 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations

• Stopwatch General

References:

• 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations Time Critical Task: No Validation Time: 10 minutes 2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 8 Form ES-C-I I SIMULATOR SETUP

1. Reset to IC 194 or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-01041038101 and Execute.

4. Ensure Simulator Operator Checklist is complete.

5. Ensure RCP A MOTOR DETAILS is on one computer screen.

5. Acknowledge alarms and place simulator in FREEZE.

6. Provide a copy of 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, marked-up as complete through Step 16.

7. Provide a stopwatch.

8. When the last performance of this JPM is completed for the day, delete any temporary lCs that were created and delete the contents of the Recycle Bin.

2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 8 Form ES-C-I Denote critical steps with a check mark (14 Start Time Obtain required reference materials.

SAT STEP I UNSAT Applicant obtains a copy of 3-NOP-041 .OIA, 3A Reactor Coolant STANDARD Pump Operations.

Provide the Applicant with a copy 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, up through Section 4.3.1, and marked-CUE up as complete through Step 15.

Provide a stopwatch.

COMMENT START 3A RCP Oil Lift Pump as follows:

SAT START 3A RCP Oil Lift Pump.

UNSAT STEP 2 WHEN 3A RCP Oil Lift Pump has operated for at least two minutes AND prior to starting 3A RCP, THEN CHECK white permissive light ON.

(3-NOP-041.O1A, Step 17)

Applicant places the control switch for 3A RCP Oil Lift Pump in the STANDARD START position. Notes that the green STOP light is OFF and the red ON light is ON.

CUE COMMENT 2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev9AppendixC

Appendix C Page 5 of 8 Form ES-C-I NOTE

• All associated RCP instrumentation (i.e., Seal Leak-oft Flow, #1 Seal Differential Pressure) should be available and indicating properly for current plant conditions.

. If the RCS is NOT vented, 3A RCP should only be operated for as long as directed by 3-OP-041 .8, Filling and Venting the Reactor Coolant Systern

• Sudden changes in VCT temperature can cause the 1 Seal faceplates to warp. This can result in a reduction in #1 seal leakoff flow until seal temperature stabilizes. When possible, changes to VCT temperature should be gradual, approximately 5°F per day.

NOTE CAUTION

. When 3A RCP started with the Overpressure Mitigating System (0MB) is in Low Pressure Operation, RCS pressure should be closely monitored using highest indicating channeL RCS Loops without a RCP running have highest indicated pressure. There is only a 110 psig margin between the RCS operating pressure range of 325 to 35 psig and the PORV lift setpoint of 460 psig.

• 3A RCP #1 Seal Differential Pressure should be monitored during RCP starts at low pressure. 3A RCP shall be stopped if seal differential pressure drops to 225 psid.

• Starting 3A RCP causes a voltage transient that could be enough to adversely affect Containment Air GaseouslParticulate Monitors, Ri 1/R12, sample skid operation.

START 3A RCP while monitoring both of the following:

SAT STEP 3

• Starting current as indicated on 3A RCP motor ammeter UNSAT RCS loop flow rate rise as indicated on Fl-3-414, 415, or 416, A LOOP RCS FLOW.

(3-NOP-041.OIA, Step 17)

Applicant places the control switch for 3A RCP in the START position. Notes that the green STOP light is OFF and the red RUN STANDARD light is ON.

Applicant monitors amps on the 3A RCP ammeter and monitors RCS loop A flow rate on Fl-3-414.

CUE EVALUATOR NOTES:

The following annunciators will alarm on pump start:

COMMENT

• SU XFMRS PANEL TROUBLE (X 3/4)

• RCP NB/C MOTOR OVERLOAD (B 1/5)

. RCP MOTOR/SHAFT HI VIB (F 1/1) 2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 8 Form ES-C-I NOTE NOTE Motor current wUl normally be 637 amps and shall be maintained less than 943 amps, except for starting currenL STEP 4 IF RCP starting current is greater than 943 amps after 25 SAT seconds, THEN STOP 3A RCP. UNSAT_____

(3-NOP-041.O1A, Step 18)

Applicant notes that RCP starting current is greater than 943 amps after 25 seconds.

STANDARD .

Applicant places the control switch for 3A RCP in the STOP position prior to the RCP breaker trip on overcurrent. Notes that the green STOP light is ON and the red RUN light is OFF.

CUE EVALUATOR NOTE:

COMMENT The Applicant may elect to secure the RCP based on increasing stator temperature or high vibration.

Stop Time 2011 PTN NRC (RD & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 8 Form ES-C-I Verification of Completion:

Job Performance Measure No. 01041038101 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Resu It: Satisfactory/Unsatisfactory Examiners signature and date:

2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I 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:

• Unit3isinMode3

• 3A RCP is shut down

• In preparation for startup of 3A RCP, Steps up through 4.1.1.16 of 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, have been completed.

• The initial, 1-minute run is complete.

Initiating Cue:

o You have been directed to start up the 3A RCP, beginning with Step 4.1.1.17 of 3-NOP-041 .O1A.

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.

2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Proóedure 1o.

TURKEY POINT UNIT 3 3-NOP-O4tOlA Revision No.

NORMAL OPERATING PROCEDURE FPL Effective Date SAFETY RELATED 08106110 CONTINUOUS USE

Title:

3A REACTOR COOLANT PUMP OPERATIONS Responsible Department: OPERATIONS Special Considerations:

This is an Upgraded Procedure. Initial use should include increased awareness because of potential technical and/or sequential changes to the procedure. After initial use of this procedure, provide comments back to the Procedure Upgrade Project.

Performance of this procedure may affect core reactivity.

FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document.

DATE VERIFIED_______ INITIAL________

Revision Approved By Approval Date UNIT # UNIT 3 DATE DOCT PROCEDURE 0 Frank Wurster 12/19/08 DOCN 3-NOP-041G1A SYS STATUS COMPLETED Brian Stamp 08/02/10 REV 1

1. OF PGS

\f

\

REVISION NO. - PROCEDURE TITLE: -

FAOE:

1 3A REACTOR COOLANT PUMP OPERATIONS 2 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 REVISION

SUMMARY

Rev. No. Description 1 PCR 10-1 222, 08102110, David Dagitz Removed unnecessary Caution about preceding Steps 4.1.1.10 and 5.1.4.

REVISION NO: PROCEDURE TflLE: -

PAG:

1 3A REACTOR COOLANT PUMP OPERATIONS 3 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 4 2.0 PRECAUTIONSAND LIMITATIONS 4 3.0 PREREQUISITES 6 4.0 NORMAL OPERATIONS 7 4.1 Startup 7 4.1.1 Starting 3A Reactor Coolant Pump 7 4.2 Operation 14 4.3 Shutdown 14 4.3.1 Stopping 3A Reactor Coolant Pump 14 5.0 INFREQUENT OPERATIONS 15 5.1 Starting 3A RCP Motor With Pump Uncoupled 15 5.2 Stopping Uncoupled 3A Reactor Coolant Pump Motor 17 5.3 Adjustment of 3A RCP Seal Injection Flow 18 5.4 Resetting Unresponsive 3A RCP Partial Discharge Monitor 20 5.5 Response to High/Low 3A RCP #1 Seal Leak-off Flow 21 5.5.1 Response to Low 3A RCP #1 Seal Leak-off Flow 21 5.5.2 Response to High 3A RCP #1 Seal Leak-off Flow 24 5.6 Steam Generator Secondary Water Temperature Measurement 26 5.7 Filling 3A RCP Standpipe 28 6.0 RECORDS 29

7.0 REFERENCES

AND COMMITMENTS 29 ATTACHM ENTS ATTACHMENT I 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP SWITCH ALIGNMENT 32 ATTACHMENT 2 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP BREAKER ALIGNMENT 34 ATTACHMENT 3 UNIT 3 REACTOR COOLANT PUMP OPERATION FIGURE 36

REVISiON NO: PROCEDURE TITLE: - -

- AGE:

3 I

1 3A REACTOR COOLANT PUMP OPERATIONS 4 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 1.0 PURPOSE This procedure provides guidance for starting and stopping 3A Reactor Coolant Pump (RCP). This procedure also provides guidance for 3A RCP infrequent operations such as uncoupled pump operation, adjusting Seal Injection flow, filling the RCP standpipe, and resetting an unresponsive 3A RCP Partial Discharge Monitor.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions

1. Personnel entering 3A RCP area should wear ear protection during RCP operation.

2. Reactor shall be shutdown prior to restart of 3A RCP.

3. Tech Spec 3.4.1.1 requires all loops be in operation in MODES 1 and 2.

4. 0-ring seals deteriorate rapidly as temperature approaches 350°F.

2.2 Limitations

1. 3A RCP shall NOT be started if Reactor Coolant Loops could potentially be at significantly lower boron concentration than the Reactor Vessel. 0-ONOP-041 .9, Potential Dilution of Reactor Coolant Loop(s), provides instructions for ensuring required boron concentrations are achieved prior to RCP operation.

2. Unless 3A RCP oil reservoir level is checked locally, 3A RCP motor shall only be started when oil reservoir high/low level alarm is clear.

3. 3A RCP Oil Lift Pump should NOT be operated when CCW is isolated from oil coolers. Momentary operation of the Oil Lift Pump without CCW, such as for uncoupled motor bump for rotation check, is acceptable.

4. If Component Cooling Water (CCW) to 3A RCP is lost, 3A RCP shall be stopped before either upper or lower bearing temperature has risen to 195°F and the Oil Lift Pump shall be stopped.

5. 3A RCP shall NOT be started with or more RCS cold leg temperatures less than or equal to 275°F unless secondary water temperature of each steam generator is less than 50°F above each RCS cold leg temperature. (Tech. Spec. 3/4.4.1.3)

REVISION NO.: PROCEDURET1TLE: .

EAO: -

1 3A REACTOR COOLANT PUMP OPERATIONS 5 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 22 Limitations (continued)

6. If Reactor Coolant System (RCS) is solid, of the following apply:

• If all RCPs are stopped for 10 minutes, running Residual Heat Removal (RHR) pump outlet temperature should be determined and RHR Hx flow adjusted to maintain that temperature.

• If the two-pump RCS fill and vent method is used and SG U-tubes were drained, a pressurizer bubble should be formed before the last RCP is started to prevent an RCS pressure event.

7. RCP motor starting duty limits are:

• With the motor at ambient temperature, successive starts are allowed. The motor shall be allowed to coast to rest between starts.

• With the motor at operating temperature, one start is allowed.

Subsequent starts require the motor be allowed to cool by standing idle for one hour or by running for half hour.

• Starts are limited to three within a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period. Subsequent starts are allowed only after standing idle for hour.

8. If any of the following limits are reached:

• Motor vibration 4 mils or shaft vibration 15 mils.

• Motor upper bearing or lower bearing temperature 195°F.

• Motor bearing oil reservoir high/low level alarm, unless level verified locally.

NOTE Stator winding temperature limit may be exceeded for a short time during cold RCP operation.

a Stator winding temperature 248°F.

a Pump bearing temperature 225° F.

• #1 seal leak-off temperature 235°F.

REVfS1ONTO.: PROCEOUFETITLE: -

PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 6 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 2.2 Limitations (continued)

8. (continued) o #1 seal leak-off on narrow range recorder is less than 0.2 gpm at low pressure conditions, unless visual inspection shows satisfactory leak-off, or less than 1.0 gpm at normal system pressure per Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure.

• #1 seal leak-off flow greater than 5.0 gpm.

• #1 seal AP less than 200 psid.

• Seal injection water is NOT required to a running RCP in either of the following conditions:

• All #1 seal leak-off RCP bearing and CCW temperatures are within limits specified in this procedure and RCS temperature less than 150°F.

o #1 seal leak-off rate is less than 5 gpm and at least 25 gpm CCW flow at an inlet temperature of less than 105°F flowing through thermal, barrier cooling coil.

o Seal injection water temperature 130°F as indicated on TI-3-1 16, VCT. Temperature may rise to 150°F if RCS temperature is less than 400°F.

3-ONOP-041.1, Reactor Coolant Pump Off-Normal, provides necessary guidance for restoration.

3.0 PREREQUISITES None

REVISION N0: PROCEDURE TITLE: -

PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 7 f 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.0 NORMAL OPERATIONS 4.1 Startup 4.1.1 Starting 3A Reactor Coolant Pump Section 4.1.1 Step I through order.

CHECK the following systems available or in operation as necessary

,97 to support RCP operation:

Component Cooling Water System Chemical and Volume Control System Primary Water System Instrument Air System Waste Disposal System Reactor Coolant System CHECK the following plant electrical systems energized to support 4/ RCP operation:

JY 3A416OVBus 3A MCC LP-34 ENSURE 3A RCP switch and breaker alignments per:

Attachment 1, 3A Reactor Coolant Pump And Oil Lift Pump Switch Alignment Attachment 2, 3A Reactor Coolant Pump And Oil Lift Pump Breaker Alignment

REVIS1ONNO.: PROCEDURETITLE: - -

PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 8 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.1.1 Starting 3A actor Coolant Pump (continued) 5 IF tarting the first RCP, THEN CHECK the following conditions have NOT occurred that would indicate a RCS loop or portion thereof may have been diluted during the time RCPs were secured:

Steam Generator tube(s) ruptured.

• Large boration of the RCS occurred after the RCPs were shutdown.

Reported or observed activity which may have diluted the water in the RCS.

Sample indicates a loop has been diluted.

dCS IF RCS loop or portion thereof was diluted, THEN GO TO O-ONOP-041 .9, Potential Dilution of Reactor Coolant Loop(s).

Starting 3A RCP may cause 3A Egencyóiesel Generator (EDG), if paralleled to 3A 4160V bus, to trip, and could damage 3A EDG.

ENSURE 3A EDG is NOT paralleled to 3A4160V Bus.

ENSURE VCT pressure is controlled to maintain one of the following

• In the normal range of 16 to 25 psig

• As required to maintain RCP seal leak-off and as specified by Chemistry 0 IF FI-3-130, RCP A SEAL INJECTION FLOW INDICATOR, does NOT indicate 6 to 13 gpm, THEN ADJUST seal injection flow per Section 5.3.

REVISIOJNO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 9 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.1.1 Starting 3A r Coolant Pump (continued)

Rea.t IF thrrier differential pressure is less than inches of water, as indicated on P1-3-I 31A, A RCP THERMAL BARRIER DIP, THEN:

A minimum of pm required for R eal Injection.

While RCO monitors DCS RCP Detailed Data Summary display for flow changes, SNPO locally ADJUST 3-297A, 3A RCP SEAL WATER SUPPLY, to obtain 6 to 13 gpm.

IF 3-297A is full OPEN AND seal injection flow is less than 6 gpm, THEN, while SNPO monitors RCP seal injection flow locally, RCO ADJUST HCV-3-121, CHARGING FLOWTO REGEN HX, CLOSED to maximize seal injection flow.

Following initial verification of RC flows and S/G temperatures, re-verification is NIA for subsequent RCP starts if, at discretion of the Shift Manager, NO intervening activities occurred to adversely impact those flows or temperatures.

CHECK the following CCW flows:

0- Fl-3-630, RCP A THERMAL BARRIER CCW RETURN FLOW INDICATOR, indicates 21 to 30 gpm.

fjk Fl-3-628, RCP A LOWER BEARING CCW RETURN FLOW

/ INDICATOR, indicates 5 to 10 gpm.

FIC-3-629, RCP A CCW RETURN FLOW, indicates 150 to 1 163 gpm or, when on RHR, 138 to 145g.

RCS cold leg temperature iscjn oreu5°F AND NO RCPs are RUNNING, THEN CHECK Steam Generator secondary water temperature less than 10°F above RCS temperature in 3A, 3B, and 3C Steam Generators using Section 5.6.

3A RCP #1 seal leak-off flow, as indicated on FR-3-1 54A or CHEC K FR-3-154B, within limits shown in Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure.

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 10 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.1.1 Starting 3A Reactor Coolant Pump (continued)

12. (continued)

IF #1 seal t-off flow less than lower limit of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure, THEN REFER TO Section 5.5.1.

IF #1 se?lQak-off flow greater than upper limit of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure, THEN REFER TO Section 5.5.2.

RCS pressure range is 325 to 3 psig for solid plant condition.

IF PI-/(, A RCP #1 SEAL AP, indicates less than 225 psid across

1. 1 seal, THEN ENSURE RCS pressure greater than 325 psig.

IF A/ator G 2/1 RCP A STANDPIPE HI LEVEL, is in ALARM, THEN GO TO 3-ONOP-041 .1, Reactor Coolant Pump Off-Normal.

IF AnIriator G 3/1 RCP A STANDPIPE LO LEVEL, is in ALARM, A/ THEN FILL the standpipe per Section 5.7.

o 3A RCP Oil Lift Pump operation be limited to 15 minutes during normal RCP starting evolutions. Exception may be taken during off-normal operation or troubleshooting.

• Prolonged operation of 3A RCP Oil Lift Pump may cause air entrainment in the oil resulting in the inability to achieve RCP prestart oil pressure.

16. START 3A RCP Oil Lift Pump as follows:

A. START 3A RCP Oil Lift Pump.

B. WHEN 3A RCP Oil Lift Pump has operated for at least minutes AND prior to starting 3A RCP, THEN CHECK white permissive light ON.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 11 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 41 .1 Starting 3A Reactor Coolant Pump (continued)

NOTE

• All associated RCP instrumentation (i.e., Seal Leak-off Flow, #1 Seal Differential Pressure) should be available and indicating properly for current plant conditions.

• If the RCS is NOT vented, 3A RCP should only be operated for as long as directed by 3-OP-041 .8, Filling and Venting the Reactor Coolant System.

• Sudden changes in VCT temperature can cause the #1 Seal faceplates to warp. This can result in a reduction in #1 seal leakoff flow until seal temperature stabilizes. When possible, changes to VCT temperature should be gradual, approximately 5°F per day.

CAUTION

• When 3A RCP started with the Overpressure Mitigating System (OMS) is in Low Pressure Operation, RCS pressure should be closely monitored using highest indicating channel. RCS Loops without a RCP running have highest indicated pressure. There is only a 110 psig margin between the RCS operating pressure range of 325 to 350 psig and the PORV lift setpoint of 460 psig.

• 3A RCP #1 Seal Differential Pressure should be monitored during RCP starts at low pressure. 3A RCP shall be stopped if seal differential pressure drops to 225 psid.

• Starting 3A RCP causes a voltage transient that could be enough to adversely affect Containment Air Gaseous/Particulate Monitors, R11/R12, sample skid operation.

17. START 3A RCP while monitoring J22Ji of the following:

• Starting current as indicated on 3A RCP motor ammeter o RCS loop flow rate rise as indicated on FI-3-414, 415, or 416, A LOOP RCS FLOW NOTE Motor current will normally be 637 amps and shall be maintained less than 943 amps, except for starting current.

18. IF RCP starting current is greater than 943 amps after 25 seconds, THEN STOP 3A RCP.

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 12 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 4.1.1 Starting 3A Reactor Coolant Pump (continued)

19. WHEN 3A RCP has operated for at least one minute, THEN STOP 3A RCP Oil Lift Pump.

20. IF 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, is NOT within limits of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure, within three minutes of starting 3A RCP, THEN STOP 3A RCP.

21. IF indication on R1IIRI2 sample skid does NOT return, THEN REQUEST I&C start sample pumps in MANUAL MODE locally at skid.

22. ENSURE VCT pressure is controlled to maintain one of the following:

In the normal range of 16 and 25 psig.

As required to maintain RCP seal leak-off and as specified by Chemistry.

REVISION NO. PROCEDURE TriTE:

PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 13 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.11 Starting 3A Reactor Coolant Pump (continued)

23. WHEN 3A RCP has operated for more than 10 minutes, THEN CHECK conditions on DOS stabilized less than maximum values listed below:

NOTE Stator Winding maximum temperature may be exceeded during RCP cold operation (i.e., first start attempt).

Table I - RCP Startup Temperature Ranges STABLE MAX NORM PARAMETER °F °F YES NO

1. 1 Seal Leak-off 235 100-190 Pump Bearing 225 160 Upper Thrust Bearing 190 150 Lower Thrust Bearing 190 150 Upper Guide Bearing 190 150 Lower Guide Bearing 190 125 Stator Winding 248 200 A. CHECK seal water injection flow on Fl-3-130 between 6 and 13 gpm.

NOTE RCP Vibration indicated on Recorder 369 and on DOS.

B. CHECK RCP shaft vibration less than 15 mils.

C. CHECK RCP motor vibration less than 4 mils.

REVISION-NO.: -- PROCEDURETITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 14 of 36 PROCEDURE NO.:

3-NOP-041 OIA TURKEY POINT UNIT 3 4.2 Operafion None 4.3 Shutdown 4.3.1 Stopping 3A Reactor Coolant Pump

1. STOP 3A RCP.

CAUTION

• CCWto 3A RCP is required until RCS temperature is less than 150°F and 3A RCP is idle for at least a half hour.

• Seal Injection water to 3A RCP is required when RCS temperature is greater than 150°F and RCS pressure is greater than 100 psig, or when CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION, is OPEN.

2. MAINTAIN CCW to 3A RCP motor bearing oil cooler for at least one half hour or until RCS temperature is less than 150°F after stopping the RCP.

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01067013200 JPM: Manually Initiate Containment Spray and Control Room Ventilation Task

Title:

Isolation JPM No: 01067013201 K/A

Reference:

013A4.01 R04.5SR04.8 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• The Unit 3 Reactor has tripped due to a LOCA inside of Containment.

• Safety Injection has occurred.

• Containment Isolation Phase A has occurred.

Initiating Cue:

• You have been directed to complete 3-EOP-E-0, Reactor Trip or Safety Injection, Attachment 3, starting at Step 15.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of II Form ES-C-I Task Standard:

• The Applicant manually initiates at least ONE train of Containment Spray

• The Applicant manually isolates Containment Isolation Phase B components.

• The Applicant manually starts at least one train of CR Emergency Recirculation.

Required Materials:

• 3-EOP-E-0, Reactor Trip or Safety Injection, Attachment 3 General

References:

• 3-EOP-E-O, Reactor Trip or Safety Injection, Attachment 3 Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 11 Form ES-C-I SIMULATOR SETUP

1. Reset to IC 195 or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-01067013201 and Execute.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place simulator in FREEZE.

6. Provide a copy of 3-EOP-E-O, Reactor Trip or Safety Injection, Attachment 3, marked up as complete through Step 14.

7. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRC Exam (RO & SRO) JPM-.e NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of II Form ES-C-I Denote critical steps with a check mark (i Start Time Obtain required materials.

SAT STEP I U NSAT Applicant obtains a copy of 3-EOP-E-0, Reactor Trip or Safety STANDARD Injection.

Provide the Applicant with a copy 3-EOP-E-0, Reactor Trip or CUE Safety Injection, Attachment 3, marked up as complete through Step 14.

COMMENT Monitor Containment Pressure To Verify Containment Spray SAT NOT Required.

. UNSAT Containment pressure - HAS REMAINED LESS THAN 20 PSIG STEP 2

• PR-3-6306A AND

• PR-3-6306B (3-EOP-E-0, Attachment 3, Step 15.a)

Applicant observes Containment pressure is greater than 20 STANDARD psig on Containment pressure recorders. Transitions to the RNO column.

CUE COMMENT EVALUATOR NOTE:

NOTE This is one of the Alternate Path aspects of this JPM.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 11 Form ES-C-I IF containment spray NOT initiated, THEN manually initiate SAT STEP 3 containment spray.

UNSAT

-1 (3-EOP-E-O, Attachment 3, Step 15 RNO a.1)

Applicant initiates two complete Trains of Containment Spray by performing the following:

Applicant Notes that MOV-3-880A and MOV-3-880B did not open and that Containment Spray Pumps A and B did not start.

Applicant places BOTH CNTMT SPRAY ISOLATION MOV STANDARD 880A and MOV-3-880B handswitches to OPEN. Notes that the green CLOSED lights are OFF and the red OPEN lights are ON.

AND Applicant places the 3A and 3B Containment Spray Pumps handswitches to START. Notes the red RUN lights are ON and the green STOP lights are OFF.

CUE COMMENT EVALUATOR NOTE:

NOTE This is one of the Alternate Path aspects of this JPM.

Sequence of opening valves, compared to starting pumps, is not critical.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of II Form ES-C-I Verify Containment Isolation Phase B ACTUATED.

SAT STEP 4 UNSAT____

(3-EOP-E-O, Attachment 3, Step 15 RNO a.2)

Applicant notes that Containment Isolation Phase B has not actuated by noting that all of the white, PHASE B lights are STANDARD NOT BRIGHT.

Applicant Goes to 15 RNO Step a.3).

CUE COMMENT Verify Containment Isolation Phase B valve white lights on VPB

- ALL BRIGHT.

STEP 5 (3-EOP-E-O, Attachment 3, Step 15 RNO a.3)

Applicant notes that the white Phase B lights on VPB are NOT BRIGHT. Goes to Step 15 RNO Step a.4).

STANDARD Applicant may attempt to manually initiate Phase B Isolation by simultaneously depressing BOTH Phase B Isolation phbuttons.

CUE EVALUATOR NOTE:

COMMENT Phase B pushbuttons are disabled; therefore, depressing the pushbuttons is not critical.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev9AppendixC

Appendix C Page 7 of II Form ES-C-Il IF any Containment Isolation Phase B valve did NOT close, SAT THEN manually or locally isolate affected containment STEP 6 penetration. UNSAT J

(3-EOP-E-O, Affachment 3, Step 15 RNO a.4)

Notes that the white lights for the Phase B Isolation valves are NOT BRIGHT.

Applicant takes control switch for the flowing valves to the CLOSE position:

e RCP CLG WTR MOV-3-716B

. RCP CLG WTR FCV-3-626 STANDARD

• RCP CLG WTR MOV-3-730 Applicant notes the white lights for the following valves are BRIGHT:

• RCP CLG WTR MOV-3-716B CLOSED

• RCP CLG WTR FCV-3-626 CLOSED

• RCP CLG WTR MOV-3-730 CLOSED CUE COMMENT EVALUATOR NOTE:

NOTE Containment Isolation Phase B is disabled as a part of the setup.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of II Form ES-C-I Stop all RCPs SAT STEP 7 UNSAT (3-EOP-E-O, Attachment 3, Step 15 RNO a.5)

Applicant notes that all RCPs have already been stopped by STANDARD observing the green STOP lights ON and the red START lights OFF for the three RCPs.

CUE COMMENT Verify Containment and Control Room Ventilation Isolation SAT Unit 3 containment purge exhaust and supply fans OFF UNSAT STEP 8 (3-EOP-E-O, Attachment 3, Step 16.a)

Applicant notes that the green STOP light is ON and the red RUN light is OFF for the U-3 CNTMT PURGE SUPPLY FAN and STANDARD the U-3 CNTMT. PURGE EXHAUST FAN on VPB.

CUE COMMENT 2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of II Form ES-C-I Verify Control Room ventilation status panel PROPER SAT EMERGENCY RECIRCULATION ALIGNMENT STEP 9 UNSAT (3-EOP-E-O, Attachment 3, Step 16.b)

STANDARD Applicant notes the EMER. AIR SUPPLY FAN SF-lB (V-29B) did NOT start. Transitions to the RNO column.

CUE COMMENT EVALUATOR NOTE:

NOTE This is one of the Alternate Path aspects of this JPM.

Manually align equipment for Control Room emergency SAT STEP 10 recirculation.

UNSAT q

(3-EOP-E-O, Attachment 3, RNO Step 16.b)

Applicant places handswitch for the EM ER. AIR SUPPLY FAN STANDARD SF-i B (V-29B) in the START position. Notes the green OFF light is OFF and the red RECIRC ON light is ON.

TERMINATING CUE:

CUE Evaluator informs Applicant that another operator will complete Attachment 3. This completes the JPM.

COMMENT Stop Time 2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of II Form ES-C-I Verification of Completion:

Job Performance Measure No. 01067013201 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I will explain the initial conditions, which steps to simulate or discuss, and provide iniliating cues.

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

Initial Conditions:

• The Unit 3 Reactor has tripped due to a LOCA inside of Containment.

• Safety Injection has occurred.

• Containment Isolation Phase A has occurred.

Initiating Cue:

• You have been directed to complete 3-EOP-E-0, Reactor Trip or Safety Injection, Attachment 3, starting at Step 15.

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.

2011 NRC Exam (RO & SRO) JPM-e NUREG 1021 Rev 9 Appendix C

Procedure No.: Procedure

Title:

I Page:

[ 24 I Approval Date:

3-EOP-E-0 Reactor Trip or Safety Injection 8/10/06 STEP ACTIONIEXPECTED RESPONSE I LRESPONSE NOT OBTAINED I ATTACHMENT 3 (Page 1 of 7)

PROMPT ACTION VERIFICATIONS eck The Load Centers Associated With Close the Load Center supply breakers.

The Energized 4 KV Buses ENERGIZED LC LC 3C LC 3DLC LC Check If Main Steamlines Should Be Isolated main steamline isolation and a. GotoStep3.

bypass valves ANY OPEN heck if either main steam isolation b. GotoStep3.

signal has actuated

• High steam flow with either low SIG pressure 614 psig Q low Tavg 543 F OR

• Hi-Hi containment pressure 20 PSIG main steam isolation and bypass c. Push manual Steamline Isolation push valves CLOSED

- buttons on VPB QE manually close valves.

Verify Feedwater Isolation lace main feedwater pump switches in STOP eedwater control valves CLOSED b. Manually close valves.

eedwater bypass valves CLOSED c. Manually close valves.

Close feedwater isolation MOVs d. Locally close valves.

erify standby feedwater pumps OFF e. IF standby feedwater is aligned to Unit 3, THEN stop standby feedwater pump(s).

W97/InfcIs/nw/mr

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-EOP-E-0 Reactor Trip or Safety Injection 8/10/06 STEP ACTIONIEXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page 2 of 7)

PROMPT ACTION VERIFICATIONS Verify Proper ICW System Operation

/erify ICW pumps AT LEAST TWO- a. Start OW pump(s) to establish at least RUNNING two running.

/erify ICW to TPCW Heat Exchanger b. Manually close valve(s). jf valve(s) can ISOLATED NOT be closed, THEN locally close the following valves:

_POV-3-4882 CLOSED

• 3-50-319 for POV-3-4882

&POV-3-4883 CLOSED

• 3-50-339 for POV-3-4883

,,@bheck ICW headers TIED TOGETHER

- c. IF both ICW headers are intact, THEN direct operator to tie headers together.

Verify Proper CCW System Operation CCW Heat Exchangers THREE IN a. Perform the following:

SERVICE

1) Start or stop COW pumps as necessary to establish ONLY ONE RUNNING CCW PUMP.

2) Verify Emergency Containment Coolers ONLY TWO RUNNING

3) Go to Step 5c.

pumps ONLY TWO RUNNING

b. Start or stop CCW pumps as necessary to establish ONLY TWO RUNNING CCW PUMPS.

cCCW headers TIED TOGETHER

c. jf both CCW headers are intact, THEN direct a field operator to tie the headers together.

Thermal Barrier CCW Outlet, d. IF containment isolation phase B Qj MOV-3-626 OPEN actuated AND CCW radiation levels are normal, AND RCP number one seal leak-off temperature is less than 235F, THEN manually open MOV-3-626. I.E MOV-3-626 can I2I be manually opened, THEN direct operator to open MOV-3-626 locally.

W97/lnIcIs/nw/mr

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I ATTACHMENT 3 (Page 3 of 7)

PROMPT ACTION VERIFICATIONS

_Verify Containment Cooling emergency containment coolers - a. Manually start or stop emergency ONLY TWO RUNNING containment coolers to establish ONLY iWO RUNNING.

erify emergency containment filter fans - b. Manually start emergency containment AT LEAST TWO RUNNING filter fans.

Verify Pump Operation least two high head SI pumps running a. Manually start high-head pump(s).

Both RHR pumps running b. Manually start RHR pump(s).

@Verify SI Flow pressure LESS THAN 1600 PSIG

- a. Go to Step 9.

[2000 PSIG]

iigh-head SI pump flow indicator b. Manually start pumps NQ align valves to CHECK FOR FLOW establish an injection flowpath.

,RCS pressure LESS THAN 250 PSIG

c. Go to Step 9.

[650 PSIG]

pump flow indicator - d. Manually start pumps align valves to CHECK FOR FLOW establish an injection flowpath.

W97/In/cls/nw/mr

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-EOP-E-0 Reactor Trip or Safety Injection 8/10/06 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I ATTACHMENT 3 (Page 4 of 7)

PROMPT ACTION VERIFICATIONS

_ReaIign SI System Unit 3 high-head SI pumps TWO

- a. Perform the following:

VerifyRUNNING

1) Operate Unit 3 and Unit 4 high-head SI pumps to establish injection to Unit 3 from two high-head SI pumps.

2) Direct Unit 4 Reactor Operator to align Unit 4 high-head SI pump suction to Unit 3 RWST using ATTACHMENT I of this procedure.

3) GotoSteplo.

both Unit 4 high-head SI pumps A4.Q place in standby Verify Containment Isolation Phase A Valve Perform the following:

White Lights On VPB ALL BRIGHT

a. Manually actuate Containment Isolation Phase A.

b. IF any Containment Isolation Phase A valve is QJ closed, THEN manually close valve. IF valve(s) can NOT be manually closed, THEN manually or locally isolate affected containment penetration.

Verify SI Valve Amber Lights On VPB - Manually align valves to establish proper SI ALL BRIGHT alignment for an injection flowpath.

Verify SI RESET Reset SI Verify Containment Phase A RESET Reset Phase A W97/lnfcIs/nw/mr

STEP ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page 5 of 7)

PROMPT ACTION VERIFICATIONS Reestablish RCP Cooling Check RCPs AT LEAST ONE a. Go to Step 15.

Z RUNN ING 0

b. Open CCWto normal containment cooler b. Stop all RCPs valves

• MOV-3-1417

• MOV-3-1418

c. Reset and start normal containment c. Stop all RCPs coolers

15. Monitor Containment Pressure To Verify Containment Spray Qj Required

a. Containment pressure HAS REMAINED

- a. Perform the following:

LESS THAN 20 PSIG

1) i.E containment spray N.QI initiated,

• PR-3-6306A THEN manually initiate containment spray.

AND

2) Verify Containment Isolation Phase B

• PR-3-6306B - ACTUATED.

3) Verify Containment Isolation Phase B valve white lights on VPB ALL BRIGHT.

4) f any Containment Isolation Phase B valve did Q] close, THEN manually or locally isolate affected containment penetration.

5) Stop all RCPs.

W97/Inlclslnw/mr

Procedure No.: Procedure

Title:

Page:

- Approval Date:

3-EOP-E-O Reactor Trip or Safety Injection 7/27/11 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I ATTACHMENT 3 (Page 6 of 7)

PROMPT ACTION VERIFICATIONS

16. Verify Containment and Control Room Ventilation Isolation

a. Unit 3 containment purge exhaust and a. Manually stop fans.

supply fans OFF

b. Verify Control Room ventilation status b. Manually align equipment for Control panel PROPER EMERGENCY

- Room emergency recirculation.

RECIRCULATION ALIGNMENT a a a a a a a a 1. a a a a a a a II Hydrogen Monitors should be in service within 30 minutes of a valid SI signal. They should be available in a timely manner to support decision-making related to hydrogen generation in containment.

I a a a a a a a a a a a a a a

17. Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM

18. Verify All Four EDGs RUNNING EMERGENCY START any available EDG NOT running.

W97/In/cls/nw/mr

STEP ACTIONIEXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page7of 7)

PROMPT ACTION VERIFICATIONS

19. Verify Power To Emergency 4 Ky Buses and Load Centers

a. Check the 3A, 3B and 3D 4 KV buses - a. Perform the following:

ALL ENERGIZED

1) Inform the Unit Supervisor that ATTACHMENT 3 is complete with the exception of the de-energized bus or buses.

2) IF the Unit Supervisor decides not to energize the de-energized bus or buses, THEN go to Step 20.

3) IE the Unit Supervisor decides to energize 3A, 3B, or 3D bus, THEN perform the following:

a) ffl 3A 4 Ky bus de-energized, THEN restore power to bus using 3-ONOP-0042, LOSS OF 3A 4KV BUS.

b) IF 3B 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.

c) jf 3D 4 Ky bus de-energized, THEN restore power to bus using 3-ONOP-004.5, LOSS OF 3D 4KV BUS.

20. Notify The Unit Supervisor That The PROMPT ACTION VERIFICATIONS Attachment Is Complete And Discuss Any Safeguards Equipment That Is Not In The Required Condition W97/In/cls/nw/mr

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01002002100 JPM: Manually Synchronize Main Task

Title:

Generator JPM No: 01002002100 K/A

Reference:

045 A4.02 RO 2.7 SRO 2.6 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• Unit 3 is in MODE 1, 5-6% power.

o The plant is being started up per 3-GOP-301, Hot Standby to Power Operation. Actions are complete up through Step 5.54.

• Main turbine speed is approximately 1794 rpm

• The voltage regulator is in service.

o The Main Generator AUTO Synchronizing Circuit is NOT available.

• The Shift Manager has given authorization to perform a manual synchronization of the main generator.

• The RCO is monitoring Reactor power and the RCS.

Initiating Cue:

• You have been directed to manually synchronize the generator using 3-GOP-301, Hot Standby to Power Operation, starting with Step 5.55; and raise load to 10 MW.

• All prerequisites and job briefings have already been completed.

2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 10 Form ES-C-I Task Standard:

o The main generator has been synchronized to the grid and main generator load is raised to at least 10 MWe with no reverse power trip.

Required Materials:

o 3-GOP-301, Hot Standby to Power Operation o Sync plug General

References:

o 3-GOP-301, Hot Standby to Power Operation Time Critical Task: No Validation Time: 20 minutes 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 10 Form ES-C-I SIMULATOR SETUP

1. Reset to IC 196 or equivalent IC.

2. Place simulator in RUN.

3. Ensure Simulator Operator Checklist is complete.

4. Acknowledge alarms and place simulator in FREEZE.

5. Provide a copy of 3-GOP-301, Hot Standby to Power Operation, marked up as complete through step 5.54.

6. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 10 Form ES-C-I Denote critical steps with a check mark (Yi Start Time SAT STEP I Obtain required materials.

UNSAT Applicant obtains a copy of 3-GOP-301, Hot Standby to Power STANDARD Operation.

Provide the Applicant with a copy 3-GOP-301, Hot Standby to CUE Power Operation. Include Cover Page, Precautions and Limitations, and Steps 5.53 through 5.56; with Steps 5.53 and 5.54 marked-up.

COMMENT

. NOTE I NOTE The Manua? Mode l only be med by autho dza don Gf The Stiff Menager.

Manually synchronize the generator as follows (N/A if Auto SAT Synchronization was used):

UNSAT STEP 2 Place the Gen Synchronizing East Bus Control in the MAN q position.

(3-GOP-301, Steps 5.55 & 5.55.1)

Applicant places the GENERATOR SYNC EAST BUS BW33 STANDARD control switch in the MAN position.

CUE COMMENT 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 10 Form ES-C-17 Verify the Inadvertent Protection Scheme Armed amber light above SAT STEP 3 the synchroscope is LIT.

UNSAT (3-GOP-301 step 5.55.2)

STANDARD Applicant observes the Inadvertent Protection Scheme Armed amber light (unlabeled) above the synchroscope is LIT.

CUE COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical because there are NO verifiable operator actions.

Ensure synchroscope is rotating slowly in the FAST direction.

STEP 4 SAT (3-GOP-301 step 5.55.3) UNSAT Applicant adjusts turbine speed by placing the GENERATOR STANDARD GOVERNOR XJAN speed changer control switch to the RAISE position, until the synchroscope is rotating slowly in the FAST (clockwise) direction.

CUE COMMENT 2011 NRCExam(RO)JPM-f NUREG 1021 Rev9AppendixC

Appendix C Page 6 of 10 Form ES-C-I NOTE WHEN the synchroscope is approximately 11 oclock, THEN STEP 5 SAT manually hold closed the GCB Control Switch until either the GCB j is closed or the 12 oclock position is reached. UNSAT (3-GOP-301 step 5.55.4)

Applicant places and holds the handswitch for the EAST BUS STANDARD GENERATOR OCB to CLOSE when the synchroscope is between the 11 oclock and 12 oclock position on the synchroscope until either the GCB is closed or the 12 oclock position is reached.

CUE COMMENT 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev9AppendixC

Appendix C Page 7 of 10 Form ES-C-I

- -- - - -= - - . =- = =- I 4OTES If Eerr bz breaker failo to cboa the Power Coordiratorin Syotem Operahono needo to be robfted pntor to a+/-tempting to oyrthroni.ze with the Mid Bu reakeç since rgnmerE of the w(tehyard mey be raqred (The Systems Operator/Power NOTE CcimtQnator evaluates system conditiono to detamiine if the Ngb line tho.ukl be tooleted before closing the Mid Bus reake,. end will oi* with the plate to expedite eny neceosely coltcIi?ng (Commitment Step 2. 3 lj

• If the generator to motored at 2 MW or more for 30 econdo the reueroe power relay will initiate generator lockouL WHEN the GCB closes, THEN perform the following:

SAT STEP 6 Observe the East Bus Breaker indicating lights to verify breaker UNSAT is closed (red on, green off).

(3-GOP-301 step 5.55.5 & 5.55.5.1.)

STANDARD Applicant ensures the East GCB closes by observing that the EAST BUS GENERATOR OCB red CLOSED light is ON.

CUE COMMENT 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 10 Form ES-C-I IF main generator load is less than 10 MWe, THEN increase SAT load to approximately 10 MWe using the Generator Governor STEP 7 UNSAT Speed Changer Control.

I (3-GOP-301 step 5.55.5.2)

Applicant raises Main Generator load to approximately 10 MWe, by placing the GENERATOR GOVERNOR speed changer control STANDARD switch to the RAISE position.

AND A reverse power trip does NOT occur TERMINATING CUE:

CUE When the Applicant has attained a load of 10 to 20 MWE, Evaluator informs the Applicant that another operator will complete the procedure. The JPM is complete.

COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical if load is >10 MWe after the EAST BUS GENERATOR OCB closes and no adjustments are required.

Stop Time 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 10 Form ES-C-I Verification of Completion:

Job Performance Measure No. 01002002100 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I 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.

I 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:

e Unit 3 is in MODE 1, 5-6% power.

The plant is being started up per 3-GOP-301, Hot Standby to Power Operation. Actions are complete up through Step 5.54.

e Main turbine speed is approximately 1794 rpm o The voltage regulator is in service.

o The Main Generator AUTO Synchronizing Circuit is NOT available.

o The Shift Manager has given authorization to perform a manual synchronization of the main generator.

o The RCO is monitoring Reactor power and the RCS.

Initiating Cue:

o You have been directed to manually synchronize the generator using 3-GOP-301 HOT STANDBY TO POWER OPERATION, step 5.55, and raise load to 10 MW.

o All prerequisites and job briefings have already been completed.

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.

2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Florida Power & Light Company Turkey Point Nuclear Plant Unit 3 0

ci cj

-0 ci -i N -

Title:

Hot Standby to Power Operation (Continuous Use)

Safety Related Procedure Responsible Department: Operations Revision Number: 5 Issue Date: 4/20/11 Revision Approval Date: 4/19/11 ARs 574481, 591180, 565217, 01600749, 581376, 1614036, 1639210 PCRs 08-1439, 08-4 134, 08-4078, 08-5327, 08-3671, 08-3795, 08-4230, 08-4090, 09-0644, 09-0982, 08-4392, 09-1114, 09-1350, 09-1288, 09-2944, 09-3802, 09-3880 PC/Ms83-199, 86-06,86-200, 87-258,87-263, 87-264,87-265, 88-178,88-486, 89-168,90-440, 92-040,92-018, 92-178,93-032, 93-053,95-027, 95-047,95-057, 96-022,96-086, 99-016,99-045, 02-031,02-085, 04-026,04-112, 04-163,06-002, 07-019,08-025, 09-052,09-051 W2003:TNM/mrlds/mr

\j

\c \

Procedure No.: Procedure

Title:

Page:

24 Approval Date:

3-GOP-301 Hot Standby to Power Operation 12/19/10 4.0 PRECAUTIONS/LIMITATIONS 4.1 Criticality should be anticipated anytime when shutdown or control rod banks are being withdrawn or boron dilution is in progress.

4.2 All shutdown rods shall be fully withdrawn before the reactor is made critical.

4.3 Do not make the reactor critical with a moderator temperature coefficient of reactivity more positive than +5 pcml°F (except as permitted for low power physics tests).

4.4 The approach to criticality shall be guided by plotting inverse count rate ratio versus control rod position. Observe the 1/rn plot to assure criticality will not occur below the insertion limit for zero power.

4.5 Before withdrawing any rod bank from the fully inserted position, the group step counters and the rod position indicators for that bank shall meet the control rod position acceptance criteria in 3-OSP-201.1, RO Daily Logs.

4.6 When moving shutdown or control rod banks; the group step counters, RPIs, and all Nuclear Instrumentation Channels shall be closely monitored to verify proper bank movement and bank overlap for control rods.

4.7 The Reactor Coolant System lowest operating loop temperature (Tavg) shall be greater than or equal to 541°F with Keff greater than or equal to 1.0.

4.8 All Reactor coolant loops shall be in operation prior to making the reactor critical, Mode 2.

With less than 3 Loops in operation, restore all Loops to operable status or be in hot standby within six (6) hours.

4.9 Before transferring the Rod Control selector from manual to AUTO mode, the control rod banks shall be positioned as required to adjust Tavg within 1.0°F of Tref.

4.10 At power, all rod position indicators and Power Range Nuclear channels shall be periodically monitored for control rod misalignment and abnormal power distribution.

4.11 Every attempt should be made to maintain the Axial Flux Difference within the Operational Space to avoid otherwise unnecessary power reductions; reference 0NOP059.09, Operation within the Axial Flux Difference Operational Space.

4.12 Control banks shall be maintained above the respective Rod Bank A-B-C or D Low Limit Alarm by maintaining the required RCS boron concentration.

W2003:TNM/mrlcls/mr

4.13 When any control rod bank is below the Rod Bank A-B-C or D Extra Low Limit Alarm for greater than one hour, emergency boration shall be initiated using 3-ONOP-046.1, Emergency Boration.

4.14 STiR should not be permitted to exceed a steady state value of 1.0 dpm below the POAH and 0.5 dpm above the POAH.

4.15 If the Steam Dump System is automatically armed by a load rejection and equilibrium conditions are re-established, the Steam Dump Control shall be reset by placing the steam dump to condenser Mode Selector switch to RESET.

4.16 The Steam Pressure Control Dump to Condenser Auto/Manual station shall have a zero output signal prior to placing the Steam Dump to Condenser Mode Selector in MANTJAL.

4.17 When the steam dump is in the Manual Mode of operation, then reactor power, Tavg, S/G pressure, and indicated valve position shall be closely monitored.

4.18 When adjusting the Steam Dump Control, adjustments shall be made in small increments, allowing sufficient time between adjustments for valve response.

4.18.1 The valves require approximately 18 seconds to travel full stroke, 0 to 100 percent, when given a modulation signal, and are required to travel 0 to 100 percent open in less than 7 seconds when given a quick-open signal.

4.18.2 All changes should result in an equivalent change in steam demand and reactor power.

4.18.3 Any control adjustment that does not change the demand should be investigated and use of the dump valves discontinued until the problem is resolved.

4.19 When any instrumentation channel is removed from service, the channel shall be removed from control, if required, by use of the appropriate selector switch. Associated bistables shall be tripped as necessary to satisfy the requirements of Technical Specification Table 3.3-1; reference 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

4.20 During secondary plant warmup, steam should be drawn from the steam generator slowly and feedwater additions should be carefully regulated to avoid uncontrolled cooldown of the Reactor Coolant System.

4.21 Main Turbine speed should not be increased above 600 RPM until the RCS temperature is between 544°F and 550°F.

4.22 The operability of Main Feedwater Control Valves, FCV-3-478, 488, and 498, should be checked by stroking through one complete cycle prior to placing the Turbine/Generator on line.

4.23 Serious damage to the Main Generator windings can result from operation of the generator at a terminal voltage greater than 23,100 volts.

W2003:TNM/mr/cls/mr

4.24 Safety Injection Signals shall not be in a blocked status for any reason other than for intentional, controlled depressurization and cooldown of the Reactor Coolant System as per approved plant procedures.

4.25 During a Post Trip Recovery at EOL, Reactor Engineering Department shall be contacted for startup guidelines when startup is within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of criticality.

4.26 The following guidelines shall be used after the third (3rd) doubling (i.e., 1/rn approximately 0.125) while approaching criticality using the 1/rn plot.

4.26.1 If the projected critical rod position is below the insertion limit (105 steps on Bank C), then the control banks should be inserted and the RCS borated as necessary.

4.26.2 If the projected critical rod position deviates from the ECC rod position by more than 300 PCM but less than or equal to 400 PCM, then permission to pull the Reactor critical shall be obtained from the Shift Manager or designee after a review of the ECC calculations.

4.26.3 If the projected critical rod position deviates from the ECC rod position by greater than 400 PCM, but less than or equal to 500 PCM, then permission to pull to criticality shall be obtained from the Reactor Engineering Supervisor or designee.

4.26.4 If the projected critical rod position deviates from the ECC rod position by greater than 500 PCM, then the control banks shall be reinserted and the ECC reevaluated.

1. If the error cannot be determined, permission of the Operations Manager and Reactor Supervisor (or designee) shall be obtained prior to making the reactor critical under the guidance of the 1/rn plot.

2. The Reactor shall not be made critical with a difference of greater than or equal to 1000 PCM between the projected critical height and the ECC rod position.

4.27 If all of the following conditions exist, power increases performed under the direction of this procedure should be limited to 3 percent/hour for fuel conditioning:

4.27.1 The plant has not operated with the existing core at or above the intended power level in the last 27 days. Time spent with the unit at zero power does not count towards the 27-day time limit.

4.27.2 Reactor power is between 40 percent and 100 percent of full power.

4.27.3 The plant has not operated at or above the intended power level for at least 72 cumulative hours in any 7-day period.

4.28 Rod withdrawals performed above 50 percent power after a reload and during the fuel conditioning period (Precaution/Limitation 4.27) should be limited to three rod steps/hour.

This withdrawal rate is based upon a Westinghouse recommendation and may be relaxed specifically to control axial offset or to perform an incore/excore calibration.

AI)flflTKu1Ir.,rI.-k,h,,r

Procedure No.: Procedure

Title:

Page:

27 Approval Date:

3-GOP-301 Hot Standby to Power Operation 1125/10 4.29 All work in the Radiation Controlled Area shall be performed in accordance with the requirements of the Radiation Work Permit and ALARA program.

4.30 The Reactor Coolant System hydrogen concentration shall be greater than 15 cc/kg prior to entering Mode 2. If RCS hydrogen is not between 25 and 50 cc/kg within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering Mode 2, then Action Level 1 of 0-ONOP-04 1.10, Primary Chemistry Deviation from Limits, applies.

4.31 With reactor power below the POAH, reactivity shall not be changed by rod withdrawal and boron dilution at the same time.

4.32 Per Reference Substep 2.1.5.36, Limitation and Conditions for Westinghouse Fuel Operation, the following apply to load increases:

4.32.1 During the initial return to power following a refueling shutdown or following a cold shutdown where fuel assemblies have been handled (e.g., inspection), the following apply:

1. The rate of reactor power increase between 40 percent and 100 percent of full power should be less than or equal 3 percent full power/hour, but shall not exceed an increase of:

a. 4 percent over any 1-hour period

b. 7 percent over any 2-hour period

c. 10 percent over any 3-hour period

2. No single step increase in power shall exceed 3 percent full reactor power.

This ramp rate requirement applies during the initial startup of a reload cycle for that period of time until full power is achieved for 72 cumulative hours out of any seven-day operating period at power. It may also apply for any other power increases during that time period, depending on the maximum power level achieved and length of operation at that power level.

Specifically this requirement may be removed for reactor power levels at or below a given P (40 percent <P100 percent) provided the plant has operated at or above level P for at least 72 cumulative hours out of any seven-day (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) operating period at power (fuel is preconditioned).

Down time or time at zero power is not considered as operating time.

4.32.2 Once the plant has attained some steady state power level for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then load follow operation may be conducted in that cycle up to that power level without fuel related limitations on ramp rate. In other words, there are no fuel-related limitations on ramp rates on preconditioned fuel.

4.32.3 Other administrative limitations on ramp rate may be imposed at the discretion of Operations or Reactor Engineering depending on other factors (i.e., possible leaking fuel, time in core life, etc.).

W2flfl-TNM/mr!rls/mr

4.33 The following guidelines shall be employed for reduced power operation.

4.33.1 Operation at reduced power levels for greater than 27 days establishes a reduced power threshold.

1. The reduced power threshold is the highest power level at which the reactor has experienced 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of operation in the preceding 30 days.

2. Power increases above the reduced power threshold are limited to 3 percent per hour.

3. Down time or time at zero power is not considered as operating time.

4.34 During Mode 2 operation and at reduced power levels (less than 30 percent) in Mode 1, caution shall be exercised when making Secondary System adjustments which would affect power/reactivity levels.

4.35 Reactor power changes shall be monitored as follows:

4.35.1 Attachment 4, Power Data Sheet, shall be completed during all power changes.

4.35.2 If Reactor Power changes by greater than or equal to 15 percent in a 1-hour period, Chemistry shall be notified to begin sampling the RCS per Technical Specification 4.4.8, Table 4.4-4, Item 6.

4.36 Prior to closing the Reactor Trip Breakers, the DCS Reactor Protection SOE Group shall be checked for abnormalities in the system that may not be indicated on status lights.

However, if the DCS Reactor Protection SOE Group is out of service and cannot readily be restored, then I&C shall perform a visual check of reactor trip relays in the reactor protection racks to verif none of the reactor trip relays are in the tripped mode.

4.37 The RCS and pressurizer boron concentration may be equalized at any time using Pressurizer spray and heaters.

4.38 Prior to admitting steam to the turbine, all feedwater heater alarms are required to be cleared or the feedwater heater isolated if the System Engineer suspects tube leakage. This does not apply to the #1 and #2 Heaters up to 50 percent power because high level is expected due to the plant design. [Commitment Step 2.3.9]

4.39 Heater drain pump and condensate pump operation should be optimized to maximize unit efficiency and minimize rejection of heater drains to the condenser, thus minimizing the potential for damage to condenser tubes as a result of impingement. For example, it is desirable to operate as many heater drain pumps as possible and to minimize the number of condensate pumps being run.

AI9flflTNMImrIrjqImr

4.40 The SGFPs are equipped with recirculation valves that are designed to protect the pump under low demand conditions. The SGFPs are started with respective control switch in OPEN and the recirculation valves open. The recirculation valves operate as follows:

4.40.1 The SGFP recirculation valves will automatically open when flow rate on an operating SGFP reaches the low flow setpoint.

4.40.2 If the SGFP recirculation valves open automatically, the respective control switch must be placed in OPEN/RESET (resets seal-in circuit) and then returned to the CLOSE/AUTO position in order to close the valves.

4.40.3 Opening of a SGFP breaker will close the associated recirculation valves provided their control switch is in the CLOSE/AUTO position.

4.41 The Shift Manager may designate operating bands as necessary based on current plant mode and equipment conditions as needed to allow the operating crew more flexibility.

This guidance on operating bands does not allow the violation of Tech Specs or allow the operation near automatic trip setpoints. One example is S/G levels while not in Mode 1 or in unit startup. The program level is 50 percent, so the operating band is set at 45 to 55 percent. This allows the deviation alarm to remain clear, yet still alert the operator when a 5 percent deviation from program occurs, which is the system design.

4.42 For power ascension above 75% during the fuel preconditioning period as defmed in Precaution/Limitation 4.27, Axial Flux Difference shall be limited to within +/-3% of the target value provided by Reactor Engineering.

4.43 If Turbine Power is greater than or equal to 150 MW and the Power System Stabilizer (PSS) is not in service or becomes disabled, then the Transmission System Operator (TSO) shall be notified within 30 minutes.

4.44 All communications with the Transmission System Operation (TSO) are required to be logged in the Unit Narrative Log. In addition, the log entry for any request from the TSO to adjust Main Generator VARS must either indicate that the request was complied with or give an explanation of why the schedule could not be met.

W2003:TNMImr/cls/mr

ALL PREVIOUS STEPS HAVE BEEN INTENTIONALLY OMMITTED.

PLEASE REFER TO THE INITIAL CONDITIONS AND INITIATING CUES.

NIT a.i a a a a a a a a a a a a I The following step may be performed as SDTA controllers are adjusted and steam generator levels are stabilized.

I erform the following in preparation for synchronizing the main generator:

Verify that the Main Exciter DC Regulator Control is in the full lower position (approximately 10 percent on DC Regulator Control Indicator).

a a a a a a a a a The generator leads backup distance relay is susceptible to vibration with the generator I field circuit breaker open and may cause a generator lockout and subsequent turbine trip.

To prevent this occurrence, the paddle is removed from this relay during the Main Turbine i

Startup and is installed prior to closing the generator field circuit breaker.

Direct SOA to install the relay paddle to restore the generator leads backup distance (LTD) SAM timer relay in Cabinet 3C106 in the Cable Spreading Room.

a a a a a a a a a a a a a a Annunciator E 8/2, GEN FIEL I .

and clear.

RCINGNOLT REG LIMITING, may come in I I When the exciter field breaker is closed, the exciter amps and generator voltage may I .

vaiy based on generator conditions, i.e. cold from a refueling outage or relatively hot from a SNO. If exciter amps or generator voltage are not within the specified band, I System Engineering shall be contacted for further guidance.

I I gClose the exciter field breaker and verify response on Control Room or local exciter field ammeter between greater than 0 and 90 amps.

Verify three generator voltmeter readings are indicating between greater than Oand 17KV.

-. Slowly increase generator voltage by raising the DC regulator control in small step changes.

a. Verify exciter field ammeter responds with each adjustment.

b. Verify all three generator voltmeters are indicating equal values.

APflflQTNIAI.,-,.I,,k,-,.

1NIT 5.53.3 (Contd)

(c AJ-T1O N)

Generator operation greater than 23,100 volts may damage the generator windings.

Exciter field current is limited to 135 amps at no-load to ensure acceptable generator voltage.

r @aise generator voltage until voltage is between 21.5 KV and 22.5 KV on all three phases with exciter field amps between 100 amps and 130 amps on the generator voltmeters and exciter field ammeter. (The Control Room or local exciter field ammeter may be used.)

Place the Voltage Regulator Control Switch in the TEST position.

r 1

The regulator mismatch meter may oscillate about the zero point due to minor speed I changes. I the AC reguintor control turnill the AC-DC :guint; mismatch

, Place the Voltage Regulator Control Switch in the ON position.

lace the Generator Synchronizing East Bus Control in the MANUAL position.

Adjust the turbine speed using the Generator Governor Speed Changer Control until the synchroscope Indicator is rotating slowly in the FAST direction.

just the AC regulator control to set the incoming voltage equal to the running voltage.

WHEN reactor power is between 5 and 7 percent, THEN verif, the following parameters are stable or indicate a very slow rate of change:

[Commitment Step 2.3.11 CAPR]

• Tavg (549° to 55 1°F)

• PRZ level (on program for Tavg)

• Steam Generator levels (46 to 54 percent)

\AIflflTKIMknrIr/n,r

a a

( N S

• If auto synchronizing is inoper6 Or-tifld sirable, the Shift Manager may authorize the use of Manual Synchronizing Mode.

I ft a In Auto Mode, the turbine speed and generator voltage are automatically adjusted, which may require several minutes to satislij the system logic.

If the auto synchronizing pushbutton is held for greater than 10 seconds, the I .

auto-synchronizing logic will be disabled before a second auto-synchronizing attempt I at breaker closure is initiated. I

__.__=-z_____ - - - I auto synchronization as follows: (N/A if manual mode is used.)

5.54.1 Place the Gen Synchronizing East Bus Control to the AUTO position.

ti/Ic 5.54.2 Verify East Bus Breaker white light above synchroscope flashes at 12 oclock position, indicating synchronized conditions.

Jpc 5.54.3 Verify the Inadvertent Protection Scheme Armed amber light above the synchroscope is LIT.

= a 1 a fl a I.m. a a

• If East Bus Breaker fails to close, the Power Coordinator in Systems Operations needs I to be notified prior to attempting to synchronize with the Mid Bus Breaker, since I realignment of the switchyard may be required. (The Systems Operator/Power I Coordinator evaluates system conditions to determine if the high fine should be I isolated before closing the Mid Bus Breaker, and will work with the plant to expedite I any necessaiy switching.) [Commitment Step 2.3.1]

If the generator is motored at 2 MW or more incoming for 30 seconds, the reverse I power relay will initiate generator lockout.

a I 5.54.4 Before the synchroscope reaches the 11 oclock position, depress and hold the AUTO Synchronizing Button.

W2003:TNM/mr/clslmr

Procedure No.: Procedure

Title:

Page:

55-.

Approval Date:

3-GOP-301 Hot Standby to Power Operation 12/14/10 NIT 5.54.5 WREN the GCB closes, THEN perform the following:

1. Observe the East Bus Breaker indicating lights to verify breaker closure (red on; green off).

2. II? main generator load is less then 10 MWe, ThEN increase load to approximately 10 MWe using the Generator Governor Speed Changer Control.

3. Place synchroscope in the OFF position.

4. Match the flag on the East Bus Generator GCB Control Switch by taking the switch to CLOSE.

5. Verify the Inadvertent Protection Scheme Armed amber light above the synchroscope is OFF.

6. Verify Generator Amps are within 2 percent on all three phases.

NOTE 1

The Manual Mode is only to be used by authorization of the Shift Manager.

5.55 Manually synchronize the generator as follows (N/A if Auto Synchronization was used):

5.55.1 Place the Gen Synchronizing East Bus Control in the MAN position.

5.55.2 Verify the Inadvertent Protection Scheme Armed amber light above the synchroscope is LIT.

5.55.3 Ensure synchroscope is rotating slowly in the FAST direction.

CAUTION DO NOT hold GCB control switch in CLOSED position beyond the 12 oclock posItion.

5.55.4 WHEN the synchroscope is approximately 11 oclock, THEN manually hold closed the GCB Control Switch until either the GCB is closed or the 12 oclock position is reached.

1NIT N OTES I If East bus breaker falls to close, the Power Coordinator in Systems Operations needs to be notified prior to attempting to synchronize with the Mid Bus Breaker, since I

realignment of the switchyard may be required. (The Systems Operator/Power I Coordinator evaluates system conditions to determine if the high line should be isolated before closing the Mid Bus Breaker, and wlll work with the plant to expedite any necessaty switching). [Commitment Step 2.3.1]

• If the generator is motored at 2 MW or more for 30 seconds, the reverse power relay will initiate generator lockout.

1.IIIII_ a a a I 5.55.5 WhEN the GCB closes, THEN perform the following:

1. Observe the East Bus Breaker indicating lights to verify breaker is closed (red on, green off).

2. IF main generator load is less than 10 MWe, THEN increase load to approximately 10 MWe using the Generator Governor Speed Changer Control.

3. Place syncbroscope in the OFF position.

4. Verify the Inadvertent Protection Scheme Armed amber light above the synchroscope is OFF.

5. Verify Generator Amps are within 2 percent on all three phases.

H II To prevent excessive changes in S/G pressure and level, the SDTA valves should be I checked to verify that they are responding prior to each additional load step.

I I Increasing main generator load shall be coordinated with the operator controlling I steam generator levels.

L.a. a a a a a a a a I 5.56 Perform the following to increase turbine load: [Commitment Step 2.3.11 - CAPR]

5.56.1 Monitor automatic control program values using the Plant Curve Book Section IV, Figure 5, AND notify the Shift Manager of any unexpected deviations.

AJ9fl(YTIJ,JlImr1ck1mr

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01059017200 JPM: Test Source Range Task

Title:

Nuclear Instrument JPM No: 01059017201 K/A

Reference:

015A4.01 R03.9SR03.9 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• The Unit is in MODE 3.

• The SM has authorized performance of 3-OSP-059.1, Source Range Nuclear Instrumentation Analog Channel Operational Test, for N-32.

The previous shift operator has completed Steps 7.3.2 through 7.3.2.25.e.

• l&C support is no longer required.

o At the start of the test, N-32 read 110 cps.

• Containment is closed with no personnel inside containment.

• The control rod drive system is NOT capable of withdrawal at this time.

Initiating Cue:

• The US has directed you to complete Steps 7.3.2.26 through Step 7.3.2.34 of 3-OSP-059.1.

\:

2011 NRCExam(R0&SRO)JPM-g NUREG 1021 Rev9AppendixC

Appendix C Page 2 of II Form ES-C-I TskStandarth

• Setpoints are verified to be within limits

• Actuation of protection features is verified.

Required Materials:

o 3-OSP-0591, Source Range Nuclear Instrumentation Analog Channel Operational Test, marked-up to show completion up through Step 7.3.2.25.e.

• 3-OSP-059.1, marked-up Attachment 2.

General

References:

o 3-OSP-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test Time Critical Task: No Validation Time: 25 minutes 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of II Form ES-C-I SIMULATOR SETUP

1. Reset to IC 197 or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-01059017201 and Execute.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place simulator in FREEZE.

6. Provide a copy of 3-OS P-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test, marked-up to show completion up through Step 7.3.2.25.

Also provide Applicant with a copy of a marked-up Attachment 2.

7. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of II Form ES-C-I Denote critical steps with a check mark (j Start Time:

SAT STEP I Obtain required materials.

UNSAT STANDARD Applicant obtains the marked-up copy of 3-OSP-059.1, Source Range Nuclear Instrumentation Analog Channel Operational Test.

Provide Applicant with a copy of 3-OSP-059. 1, Source Range Nuclear Insfrumentation Analog Channel Operational Test, marked-CUE up to show completion up through Step 7.3.2.25.e.

Also provide Applicant with a copy of a marked-up Attachment 2.

COMMENT Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to SAT STEP 2 BLOCK.

UNSAT (3-OSP-059.1, Step 7.3.2.26)

Applicant rotates the HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) clockwise to the BLOCK position.

STANDARD CUE COMMENT 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev9AppendixC

rAppendix C Page 5 of II Form ES-C-I Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SAT SHUTDOWN BLOCKED, is ON.

STEP 3 UNSAT (3-OSP-059.1, Step 7.3.2.27)

Applicant notes that annunciator B 4/2, SOURCE RANGE HI STANDARD FLUX AT SHUTDOWN BLOCKED, is ON.

CUE COMMENT Announce distinctly over the plant P.A. phone, ATTENTION ALL SAT PERSONNEL, THE CONTAINMENT EVACUATION ALARM TEST IS COMPLETE. (Mark N/A if no personnel are in UNSAT STEP 4 containment).

(3-OSP-059.1, Step 7.3.2.28)

STANDARD Since no personnel are in containment, Applicant marks this step CUE COMMENT 2011 NRC Exam (RO&SRO)JPM-g NUREG 1021 Rev9AppendixC

Appendix C Page 6 of II Form ES-C-I Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly SAT clockwise until LEVEL TRIP status light (NIS panel, N-32) turns STEP 5 UNSAT____

ON.

q (3-OSP-059.1, Step 7.3.2.29)

Applicant rotates the LEVEL ADJ potentiometer (NIS panel, N-32)

STANDARD slowly clockwise until LEVEL TRIP status light (NIS panel, N-32) turns ON.

CUE COMMENT Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N- SAT STEP 6 32) for Level Trip bistable trip point on Attachment 2.

UNSAT J

(3-OSP-059.1, Step 7.3.2.30.a)

Applicant records between 9.3 X and 1.3 X iO in the blank for Step 7.3.2.30 on Affachment 2.

STAN DARD Tolerance based on +/- 1/2 of the smallest increment on a log scale.

CUE COMMENT 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of II Form ES-C-I Verify REACTOR PROTECTION LOGIC status light (VPB),

SAT SOURCE RANGE HI FLUX NC32D is ON.

STEP 7 UNSAT (3-OSP-059.1, Step 7.3.2.30.b)

STANDARD Applicant notes that the REACTOR PROTECTION LOGIC status light (VPB), SOURCE RANGE HI FLUX NC32D is ON CUE COMMENT Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly SAT counterclockwise until LEVEL TRIP status light (NIS panel, N-32)

STEP 8 turns OFF. UNSAT I

(3-OSP-059.1, Step 7.3.2.31)

Applicant rotates the LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until LEVEL TRIP status light (NIS panel, STANDARD N-32) turns OFF.

CUE COMMENT 2011 NRC Exam (RO&SRO)JPM-g NUREG 1021 Rev9AppendixC

Appendix C Page 8 of II Form ES-C-I Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-SAT STEP 9 32) for Level Trip bistable reset point on Attachment 2.

UNSAT q

(3-OSP-059.1, Step 7.3.2.32.a)

Applicant records between 4.3 X IO and 5.3 X i0 4 in the blank for Step 7.3.2.32 on Attachment 2.

STAN DARD Tolerance based on +/- 1/2 of the smallest increment on a log scale.

CUE COMMENT Verify REACTOR PROTECTION LOGIC status light (VPB),

SAT SOURCE RANGE HI FLUX NC32D is OFF.

STEP 10 UNSAT (3-OSP-059.1, Step 7.3.2.32.b)

Applicant notes that the REACTOR PROTECTION LOGIC status STANDARD light (VPB), SOURCE RANGE HI FLUX NC32D is OFF.

CUE COMMENT 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of II Form ES-C-I Adjust LEVEL ADJ potentiometer (NIS panel, N-32) fully SAT STEP 11 counterclockwise.

UN SAT

,J (3-OSP-059.1, Step 7.3.2.33)

Applicant rotates the LEVEL ADJ potentiometer (NIS panel, N-32) fully counterclockwise. Also may note that the potentiometer STANDARD reading is near 0.0.

CUE COMMENT Place OPERATION SELECTOR switch (NIS panel, N-32) to SAT STEP 12 NORMAL.

UNSAT

.J (3-OSP-059.1, Step 7.3.2.34)

Applicant rotates the OPERATION SELECTOR switch (NIS STANDARD panel, N-32) counterclockwise to the NORMAL position.

CUE COMMENT Stop Time 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 11 Form Verification of Completion:

Job Performance Measure No. 01059017201 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I 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:

• The Unit is in MODE 3.

• The SM has authorized performance of 3-OSP-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test, for N-32.

• The previous shift operator has completed Steps 7.3.2 through 7.3.2.25.

• l&C support is no longer required.

o At the start of the test, N-32 read 110 cps.

• Containment is closed with no personnel inside containment.

• The control rod drive system is NOT capable of withdrawal at this time.

Initiating Cue:

• The US has directed you to complete Steps 7.3.2.26 through Step 7.3.2.34 of 3-OSP-059.1 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.

2011 NRC Exam (RO & SRO) JPM -g NUREG 1021 Rev 9 Appendix C

Procedure No.: Procedure

Title:

Page:

35 Source Range Nuclear Instrumentation Approval Date:

-3MSP-059d Analog Chaimel Operational Test 9/16/OIC ATTACHMENT 2 (Page 1 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (SHUTDOWN)

QA RECORD PAGE (Page 1 of 3)

NIS Drawer Meter is to be used for channel operability requirements. Deficiencies in The console indications should be brought to the attention of the l&C Department, with the i appropriate prioritization with respect to plant mode.

L_. = = = = I Ref.

7. . .14 Operation Selector switch range verification.

a -= a a = a

1= =

The symbol +xxx in the acceptance criteria represents greater than lOx 106 CPS by an amount less than or equal to the meter deflection between 8x10 5 CPS and 6 l.0x10 CPS.

a a a a a I OPERATION NIS CONSOLE* CONSOLE*

SELECTOR Meter Meter Recorder POSITION N-32 N-3-32 NR-3-45, Channel S2 6OCPS 70 Acceptance Criteria: (50 to 75 CPS)

CPS 3

1O Acceptance Criteria: (8 x 102 to 1.2 x i03 CPS) 10 C

5 PS /( )( II c 1

Acceptance Criteria: (8 x to 1.2 x i0 5 CPS) 1O C

6 PS fXft Acceptance Criteria: (8 x 1 to +xxx) 10 CPS PREAMP

/ 0 1( I I (No Acceptance Criteria)

L/ q I 1 i/Ifl 10.24x10 CPS PREAMP 3 -

/)( (0 j, I ) Id 1. r iv (No Acceptance Criteria)

Return to Step 7.3.2.15 Wq7ITNM/nw/ln/cls

Procedure No.: Procedure

Title:

Page:

36 Source Range Nuclear Instrumentation Approval Date:

3-OS-P-O5.1 -Analog Channel Operational Test 9I16/O1C ATTACHMENT 2 (Page 2 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (Shutdown)

QA RECORD PAGE (Page 2 of 3) 7.3.2.23 High Flux at Shutdown bistable trip point, N-32 Source Range CO cps 7.3.2.25 High Flux at Shutdown bistable reset point, N-32 Source Range qC 7.3 .2.30 Level Trip bistable trip point, N-32 Source Range CPS Acceptance Criteria ( 10 CPS)

• FOR REVIEW ONLY 7.3.2.32 Level Trip bistable reset point, N-32 Source Range CPS Acceptance Criteria (4.1 x to 6.2 x 10 CPS)

Acceptance Criteria specified in this Attachment has been satisfied.

Results Satisfactory Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions required by 3-ONOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION.

a a =

If channel(s) did not meet acceptance criteria, then notify I&C to perform O-ADM-724, Instrumentation Protection Channel Determination of Channel Operability, for the failed I

channels. [Commitment Step 2.3.11 W97:ITNM/nw/lnicIs

Procedure No.: Procedure

Title:

Page:

37 Source Range Nuclear Instrumentation Approval Date:

3OSP-059.1 - Analog Channel Operational Test -11/10107 ATTACHMENT 2 (Page 3 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (Shutdown)

QA RECORD PAGE (Page 3 of 3)

REMARKS:_____________________________

PERFORMED BY (Print) INITIALS REVIEWED BY:

ShUI Manager or SRO Designee W97:ITNM/nw/ln/c[s

_ .r.

______ _______e_

_______a_

Procedure No.: Procedure

Title:

Page:

15 Source Range Nuclear Instrumentation Approval Date:

3-OSP-0S9.1* Analog-Channel Operational Test 2/23111

[NIT Date/Time Started: IC 12 Af / X/)( X Perform testing of SOURCE RANGE N-32 as follows:

At NIS panel, N-32 drawer, record the following:

AVERAGE SOURCE RANGE CPS NEUTRON LEVEL 1(0 SOURCE RANGE DETECTOR jOLTS x 100 ( 0 IF in Operational Mode 4, Hot Shutdown; Mode 5, Cold Shutdown or I / Mode 6, Refueling; THEN verify the High Flux at Shutdown alarm setpoint is valid for the existing Source Range Neutron Level as follows:

fr/k a. Multiply CPS by 101/2 (approximately 3.16) to calculate the High Flux at Shutdown setpoint at one-half decade above SOURCE RANGE CPS NEUTRON LEVEL recorded in Substep 7.3.2.1: (Mark N/A if core is off loaded) 3.16 x CPS = Alarm CPS (1) IF core is off loaded, THEN use the High Flux at Shutdown alarm setpoint that was used immediately prior to core off-load AND record below:

High Flux at Shutdown alarm setpoint:

Alarm CPS

b. Record the current High Flux at Shutdown alarm setpoint.

c. Compare the Alarm CPS from above with the current High Flux at Shutdown alarm setpoint utilizing Enclosure 1.

(1) the Alarm CPS is within the currently set ALARM VALUE Acceptance Criteria, THEN the alarm setpoint is satisfactory.

(2) IF the Alarm CPS is NOT within the currently set ALARM VALUE Acceptance Criteria, THEN perform 3-OSP--059.6, High Flux at Shutdown for Source Range Channel N-32, prior to proceeding with this procedure.

d. IF 3-OSP-059.6 was performed due to Step 7.3.2.2.c.(2), THEN perform the following:

(1) Record the new High Flux at Shutdown alarm setpoint.

(2) Compare the Alarm CPS from above with the new High Flux at Shutdown alarm setpoint utilizing Enclosure 1.

(3) the Alarm CPS is within the currently set ALARM VALUE Acceptance Criteria, THEN the alarm setpoint is satisfactory.

W97:ITNMInvv/ln/cls

Procedure No.: Procedure

Title:

Page:

16 Source Range Nuclear Instrumentation Approval Date:

3-OSP-O9.1 - Analog Channel Operational Test 3/26IO3 7.3.2 (Contd)

Position an NIS recorder to monitor source range N-32.

AUDIO COUNT RATE CHANNEL (NIS Panel, N-34), place CHANNEL SELECTOR switch to SR N3 1.

t./, in Operational Mode 6 preparing to enter Mode 6, Refueling;

/ ThEN verify audible indication in the Control Room and Containment.

At NIS Panel, N-32 verify the following:

INSTRUMENT POWER ON status light ON.

CONTROL POWER ON status light ON.

CHANNEL ON TEST status light OFF.

LOSS OF DETECTOR VOLT status light OFF.

LEVEL TRIP status light OFF.

_rj LEVEL TRIP BYPASS status light OFF.

_4 HIGH FLUX AT SHUTDOWN status light OFF.

BISTABLE TRIP SPARE status light OFF.

Place LEVEL TRIP switch (NIS panel, N-32) to BYPASS.

1Verify the following:

LEVEL TRIP BYPASS status light (NIS panel, N-32) ON.

N-32 IN BYPASS status light (VPA) ON.

Annunciator B 8/4, NIS TRIP BYPASSED, is ON.

W97:ITNM/nw/In/cls

Procedure No.: rprocedure

Title:

Page:

17 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Chaimel Operational Test 9/16101 INITIALS CKD VERIF 7.3.2 (Contd)

_47 Place HIGH FLUX AT SHUTDOWN switch NIS panel, N-32) to BLOCK.

Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is ON.

EHave I&C personnel perform the following steps:

Obtain keys for access to rear of rack 60, open rack door.

Install jumper between TB 223-1 and TB 223-2.

I&C: 7 //

Jum$er Installed Print I&C/OPS:__________________ - kJ Indepnduf erfication Print Verify the following:

LOSS OF DETECTOR VOLT status light is ON.

Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is ON.

lace OPERATION SELECTOR switch (NIS panel, N-32) to 60 CPS.

erify the following:

CHANNEL ON TEST status light (NIS panel, N-32) is ON.

Annunciator B 7/3, NIS CHANNEL IN TEST is ON.

Place the OPERATION SELECTOR switch (NIS panel, N-32) in the positions listed in Attachment 2, recording data as indicated.

Procedure No.: Procedure

Title:

Page:

18 Source Range Nuclear Instrumentation Approval Date:

3-OSP-O591 Analog Channel OeratioiiaI Test 11110/07 INITIALS CKD VERIF 7.3.2 (Contd)

Have I&C personnel perform the following:

Remove the jumper installed in Substep 7.3.2.10 between TB 223-1 andTB223-2.

I&C:

/ I Jump/ RAov d 7 Print I&C/OPS:_________________

Indepen en erflcation Print Verify the following:

LOSS OF DETECTOR VOLT status light is OFF.

Annunciator B 4/3, SOURCE RANGE LOSS OF DETECTOR VOLTAGE, is OFF.

Verify LEVEL ADJ potentiometer (NIS panel, N-32) is fully counterclockwise.

Place the OPERATION SELECTOR switch (NIS panel, N-32) to LEVEL ADJ.

NOTE Plant PA. phone announcements concerning the containment Evacuation Alarm actuation during High Flux at Shutdown alarm testing are necessary if personnel are in containment.

I__I a a a = a = I Notify Outage Control Center that containment evacuation alarm will be tested AND announce distinctly over the plant P.A. phone, ATTENTION ALL PERSONNEL, THE CONTAINMENT EVACUATION ALARM IS BEING TESTED. (Mark N/A if no personnel are in containment.)

Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to NORMAL.

W7rrNM/nw/In/nk

Procedure No.: Procedure

Title:

Page:

19 Source Range Nuclear Instrumentation Approval Date:

3OSPrO59.I Analog ChannelOperational Test - 9116/01 INITIALS CKD VERIF 7.3.2 (Contd)

Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF (Mark N/A if Annunciator B 4/2 is ON due to Source Range N-3 1, HIGH FLUX AT SHUTDOWN switch in BLOCK).

_Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly clockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) turns ON.

@Ierform the following:

Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for High Flux at Shutdown bistable trip point on Attachment 2.

Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) is ON.

Verify Annunciator B 4/1, SOURCE RANGE HI FLUX AT SHUTDOWN, is ON.

Verify containment Evacuation Alarm is ON. (Mark N/A if no personnel are in containment).

Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) turns OFF.

Perform the following:

Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for High Flux at Shutdown bistable reset point on Attachment 2.

Verify HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) is OFF.

_i Verify Annunciator B 4/1, SOURCE RANGE HI FLUX AT SHUTDOWN, is OFF.

d. Verify Containment Evacuation Alarm is OFF (Mark N/A if no personnel are in containment).

Verify High Flux at Shutdown bistable reset point is within acceptance criteria range of Enclosure 1.

W97:ITNM/nw/ln/cls

Procedure No.: Procedure

Title:

Page:

20 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.I Analog Channel Operati6nal Test 9/16/01 INITIALS CKD VERIF 7.3.2 (Contd)

26. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to BLOCK.

27. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is ON.

28. Announce distinctly over the plant P.A. phone, ATTENTION ALL PERSONNEL, TIlE CONTAINMENT EVACUATION ALARM TEST IS COMPLETE. (Mark N/A if no personnel are in containment).

29. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) slowly clockwise until LEVEL TRIP status light (NIS panel, N-32) turns ON.

30. Perform the following:

a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for Level Trip bistable trip point on Attachment 2.

b. Verify REACTOR PROTECTION LOGIC status light (VPB),

SOURCE RANGE HI FLUX NC32D is ON.

31. Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until LEVEL TRIP status light (NIS panel, N-32) turns OFF.

32. Perform the following:

a. Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-32) for Level Trip bistable reset point on Attachment 2.

b. Verify REACTOR PROTECTION LOGIC status light (VPB),

SOURCE RANGE HI FLUX NC32D is OFF.

33. Adjust LEVEL ADJ potentiometer (NIS panel, N-32) fully counterclockwise.

34. Place OPERATION SELECTOR switch (NIS panel, N-32) to NORMAL.

W97:ITNM/nw/In/cls

Procedure No.: Procedure Tftle: Page:

21 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 4/1/04 INITIALS CKD VERIF 7.3.2 t (Cont d )

35. Verify SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, N-.32) indication returns to approximately the CPS level recorded in Substep 7.3.2.1 of this test.

36. AtNIS panel, N-32, verify the following:

a. TNSTRUMENT POWER ON status light ON.

b. CONTROL POWER ON status light ON.

c. CHANNEL ON TEST status light OFF.

d. LOSS OF DETECTOR VOLT. status light OFF.

e. LEVEL TRIP status light OFF.

f. HIGH FLUX AT SHUTDOWN status light OFF.

g. BISTABLE TRIP SPARE status light OFF.

37. Verify Annunciator B 7/3, NIS CHANNEL TN TEST, is OFF.

38. Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to NORMAL.

39. Verify Annunciator B 4/2, SOURCE RANGE HI FLUX AT SHUTDOWN BLOCKED, is OFF (Mark N/A if Annunciator B 4/2 is ON due to Source Range N-3 1, HIGH FLUX AT SHUTDOWN switch in BLOCK).

40. Place LEVEL TRIP switch (NIS panel, N-32) to NORMAL.

41. Verify the following:

a. LEVEL TRIP BYPASS status light (NIS panel, N-32) is OFF.

b. N-32 IN BYPASS status light (VPA) is OFF.

c. Annunciator B 8/4, NIS TRIP BYPASSED, is OFF. (Mark N/A if Annunciator B 8/4 is ON due to another NIS channel in BYPASS).

W97:/TNM/nw/In/cls

Procedure No.: Frocedure

Title:

Page:

22 Source Range Nuclear Instrumentation Approval Date:

3MSP-059.i -. Analog Channel Operational Test . 11/I 0107 INITIALS CKD VERIF 7.3.2 (Contd)

42. Position the NIS recorders to monitor the highest reading source range and the highest reading intermediate range channels.

43. in Mode 6, Qjj, preparing to enter Mode 6, THEN place the Audio Count Rate Channel Selector Switch to an operable channel.

7.3.3 IF in Mode 3, 4, or 5 AND reactor trip breakers are closed AND control rod drive system is capable of rod withdrawal, THEN perform Attachment 5.

Date/Time Completed: /____________

PERFORMED BY (Print) INITIALS VERIFIED BY (Print) INITIALS REVIEWED BY:

Shift Manager or SRO Designee W97:/TNM/nw/ln/cls

Procedure No.: Procedure

Title:

35 Source Range Nuclear Instrumentation Approval Date:

3OSPO59;1 Analog Channel Operathna1Test g/16/uIc ATTACHMENT 2 i,rL \J 7

Page 1 of 3) oi( PTP SOURCE RANGE CHANNEL N-32 TEST DATA (SHUTDOWN) jie-c Eyt(/Vi-QA RECORD PAGE 04 56?O f

V (Page 1 of 3) a a a a a _ _

The NIS Drawer Meter is to be used for channel operability requirements. Deficiencies in I the console indications should be brought to the attention of the l&C Department with i appropriate prioritization with respect to plant mode.

a a a a a a a a a a a a i) Operation Selector switch range verification.

f_I.... a a ***** a a a a a The symbol +xxx in the acceptance criteria represents greater than 1.0x10 6 CPS by an amount less than or equal to the meter deflection between 8x10 5 CPS and 1.0x10 6 CPS.

a a a a a a a a a a a I OPERATION NIS CONSOLE* CONSOLE*

S ELECTOR Meter Meter Recorder POSITION N-32 N-3-32 NR-3-45, Channel S2 6OCPS 70 Acceptance Criteria: (50 to 75 CPS) io c

3 ps (9t9C Acceptance Criteria: (8 x 102 to 1.2 x CPS)

CPS 5

1O Acceptance Criteria: (8 x to 1.2 x CPS) 10CPS /,

Acceptance Criteria: (8 x 1 to +xxx) 1 0 (1 j I 10 CPS PREAMP (No Acceptance Criteria) 10.24x10 CPS PREAMP 3 - 1/ (( X r, (I /0 (No Acceptance Criteria)

Return to Step 7.3.2.15 V V W97:/TNM/nw/ln/cls

ATTACHMENT 2 (Page2of3)

SOURCE RANGE CHANNEL N-32 TEST DATA (Shutdown)

If I.

QA RECORD PAGE it, (Page2of3) 7.3.2.23 High Flux at Shutdown bistable trip point, N-32 Source Range 00 cps 7.3.2.25 High Flux at Shutdown bistable reset point, N-32 Source Range 1 1 d70 7.3.2.30 Level Trip bistable trip Poiyf. N-32 3Io tL

). ) (tS 9

Source Range CPS Acceptance Criteria ( 1 ü CPS)

• FOR REVIEW ONLY 7.3.2.32 Level Trip bistable reset oint, N-32 Source Range Acceptance Criteria (4.1 x 1 CPS to 6.2 x 1 CPS)

- (- S /7 Acceptance Criteria specified in this Attachment has been satisfied.

Results Satisfactory Signature Date IF results are unsatisfactory, THEN declare the channel inoperable and perform actions required by 3-ONOP-059.5, SOURCE RANGE NUCLEAR iNSTRUMENTATION MALFUNCTION.

If channel(s) did not meet acceptance criteria, then notify I&C to perform O-ADM-724, Instrumentation Protection Channel Determination of Channel Operability, for the failed channels. [Commitment Step 2.3.1]

I__a a a a a a a a a a a I

i-roceuure i me: Page:

Source Range Nuclear Instrumentation I 37

[provai Date:

3-OSP-059.1 Analog Channel Operational Test 11110/07 ATTACHMENT 2 (Page 3 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (Shutdown)

QA RECORD PAGE (Page 3 of 3)

REMARKS:

PERFORMED BY (Print) INITIALS REVIEWED BY:

S14fl Manager or SRO Designee W97:/TNM/nw/In/cls

Appendix C Job Performance Measure Form ES-C-I Worksheet Facihty: Turkey Point Task No: 01030008300 JPM: Respond to Component Cooling Water Task

Title:

System Malfunctions JPM No: 01030008303 K/A

Reference:

001 A2.03 RO 3.5 SRO 4.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Actual Performance Performance X Classroom Simulator X Plant HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• Unit3isinMode3

• Unit4isinmodel at 100% power

• 3A CCW pump is out of service and breaker is racked out.

Initiating Cue:

• You are to respond to plant conditions as the Unit #3 Reactor Operator.

El 2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 14 Form ES-C-I Task Standards) 3-ONOP-030 completed through stopping RCPs, isolating letdown and directing alignment of emergency cooling to charging pump.

Required Material(s)

• 3-ARP-097.CR.H, Control Room Annunciator Response Panel H

• 3-ON OP-030, Component Cooling Water Malfunction Reference(s)

• 3-ARP-097.CR.H, Control Room Annunciator Response Panel H

• 3-ONOP-030, Component Cooling Water Malfunction Terminating Cue(s)

• 3-ONOP-030, Component Cooling Water Malfunction, Step 3 RNO is complete.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 14 Form ES-C-I SIMULATOR SETUP

1. Reset to IC 198 or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-01030008303 and Execute.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place simulator in FREEZE.

6. Provide a copy of 3-ARP-097.CR.H and 3-ONOP-030, Component Cooling Water Malfunction.

7. When the last performance of this JPM is completed for the day, delete any temporary ICs that were created and delete the contents of the Recycle Bin.

2011 NRCExam(RO)JPM-h NUREG 1021 Rev9AppendixC

Appendix C Page 4 of 14 Form ES-C-I Denote critical steps with a check mark (i4 Start Time SAT STEP I Obtain required reference materials.

UNSAT Applicant acknowledges annunciators and obtains 3-ARP-STANDARD 097.CR.H, for annunciator H-8/1, 2, or 3; OR 3-ONOP-030, Component Cooling Water Malfunction.

CUE Provide a copy of 3-ARP-097.CR.H and 3-ONOP-030, Component Cooling Water Malfunction.

COMMENT EVALUATOR NOTES:

Applicant may directly enter 3-ONOP-030, Component Cooling Water Malfunction. For this reason, use of the ARP is NOT critical.

NOTE Applicant may recognize high amps on 3B CCW pump and manually trip the pump. Otherwise, 3B CCW pump will automatically trip on overcurrent due to the failed bearing. Either behavior is acceptable.

If the ARP is entered, the Applicant may attempt to start 3C CCW pump but the pump will fail to start.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 14 Form ES-C-I I CAUTION if ny RCF bearin9 ternporaure annun,itor tmi actuates AND h as.socted rnoEor bearing ternperture i greater than 195 F trip the reacior and stop the affecled RCPs.

NOTE NOTE I I I FidoLrEpae hcid be rnonored thro hout thi.prcedure. I I..... a a a a a a a a a I Verify Power To 4KV Bus 3D SAT Maintain 4KV Bus 3D energized ALIGNED TO AN -

UNSAT STEP 2 ENERGIZED 4KV BUS (3-ONOP-030, Step 1 & l.a.)

Applicant verifies that 4KV Bus 3D is energized by observing that Bus 3B Load Centers are energized and that the breakers STANDARD from the 3B 4KV bus to the 3D 4KV bus are closed.

CUE COMMENT EVALUATOR NOTE:

NOTE The Applicant may perform actions from the Foldout page, which if completed, would bypass this step, if this occurs, go to step 7.

2011 NRC Exam(RO)JPM-h NUREG 1021 Rev9AppendixC

Appendix C Page 6 of 14 Form ES-C-I Verify Component Cooling Water Pump(s) in service.

SAT STEP 3 UNSAT (3-ONOP-030, Step 2)

STANDARD Applicant notes that NO CCW pumps are in service, then transitions to the RNO column.

BOOTH OPERATOR CUE:

CUE Acknowledge orders I request if required.

COMMENT EVALUATOR NOTES:

The Applicant may have attempted to start the 3C CCW pump using the ARP in step 1.

Applicant may make calls to the field to affempt local start of 3C CCW pump.

NOTE Applicant may also dispatch an operator to investigate the CCW pumps and breakers.

Applicant may also instruct the WCC SRO to attempt to restore 3A CCW pump as soon as possible.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 14 Form ES-C-I IF starting n idle CCW pump will NOT overtoad an EDG, THEN SAT start CCW pumps as necessary to establish flow in both headers. UNSAT STEP 4 (3-ONOP-030, RNO Step 2.a)

STANDARD Applicant attempts to manually start the 3C CCW pump. Notes that the pump will not start and informs the US.

BOOTH OPERATOR CUE:

CUE Acknowledge orders I request if required COMMENT EVALUATOR NOTES:

The Applicant may have attempted to start the 3C CCW pump using the ARP in step 1.

Applicant may make calls to the field to attempt local start of 3C CCW pump.

NOTE Applicant may also dispatch an operator to investigate the CCW pumps and breakers.

Applicant may also instruct the WCC SRO to attempt to restore 3A CCW pump as soon as possible.

This is one of the Alternate Path aspects of this JPM.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 14 Form ES-C-I Verify Flow In Both Component Cooling Water Headers SAT NORMAL UNSAT

• FT-3-61 3A for header A STEP 5 e FT-3-613B for header B (3-ONOP-030, Step 3)

Applicant checks A CCW HDR FLOW FI-3-613A & B CCW HDR STANDARD FLOW FI-3-61 3B and notes that both indicators are reading 0 GPM. Transitions to the RNO column.

CUE COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical since there are no verifiable operator actions.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 14 Form ES-C-I I IF CCW flow to RCPs can NOT be established, THEN manually SAT trip the reactor AND verify reactor trip using the EOP Network, STEP U UNSAT AND then stop all RCPs AND perform the following:

I (3-ONOP-030, RNO Step 3.a.)

Applicant observes that the Reactor is already tripped.

Applicant trips all three RCPs by placing their control switches in the STOP position. Notes that the green STOP light is ON and STANDARD the red RUN light is OFF for all three RCP5.

OR Per 3-ONOP-030, Foldout Page, Item I .A, Applicant may trip RCP5 prior to RNO Step 3.

CUE COMMENT EVALUATOR NOTE:

NOTE Applicant should acknowledge that the Reactor was previously tripped and re-verification of trip is not warranted.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 14 Form ES-C-I Isolate Letdown and ExcessLetdown STEP 7 SAT q UNSAT (3-ONOP-030, RNO Step 3.a.1.)

Applicant isolates Letdown by placing the handswitch for the following valves in the CLOSE position.

EITHER:

• CV-3-204, L/D FROM RHX. ISOL. VALVE OR o LCV-3-460, HIGH PRESS. L/D ISOL. VLV. FROM LOOP B COLD LEG OR

• BOTH CV-3-200A, 45 GPM L/D ISOLATION VALVE and CV-3-200B, 60 GPM L/D ISOLATION VALVE STANDARD Notes that the green CLOSED light is ON and the red OPEN light is OFF for each of the above valves.

Applicant verifies Excess Letdown is already isolated by observing that the green CLOSED light is ON and the red OPEN light is OFF for the following:

• CV-3-387, EXCESS L/D ISOL. VLV. FROM COLD LEG TO EXCESS L/D HX.

• CV-3-389, EXCESS L/D FROM HX. TO VCT OR RCDT.

OR Per 3-ONOP-030, Foldout Page, Item 1 .A, Applicant may isolate Letdown and Excess Letdown (per the above) prior to RNO Step 3.a.1.

CUE COMMENT EVALUATOR NOTE:

NOTE Applicant should verify excess letdown was previously isolated.

Verification of excess letdown being isolated is NOT critical since there are no verifiable operator actions.

2011 NRC Exam(RO)JPM-h NUREG 1021 Rev9AppendixC

Appendix C Page 11 of 14 Form ES-CT IF any charging pump is running, THEN operate at maximum SAT speed until Attachment 1 is completed.

STEP 8 UNSAT (3-ONOP-030, RNO Step 3.a.2.)

Applicant takes the controller(s) for Charging Pumps 3A and 3C to manual by depressing the MAN pushbutton on the controller(s). Notes the white MAN light is LIT and the white AUTO light is OFF.

STANDARD Applicant raises the controller output to maximum by depressing the A pushbutton on the controller until the DEMAND METER is at 100%. Annunciator CHARGING PUMP HI SPEED (C 1/2) will actuate when the pump is at maximum speed.

CUE COMMENT EVALUATOR NOTE:

The Applicant may stop one charging pump based on plant NOTE need. ONLY the Charging pump(s) that are running are operated at a maximum speed.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

AppendixC Page 12 of 14 Form ES-C-I Dispatch an operator to establish emergency cooling water to SAT desired charging pump using Attachment 1.

STEP 9 UNSAT (3-ONOP-030, RNO Step 3.a.3.)

Applicant contacts a field operator and directs the operator to STANDARD perform Attachment 1 of 3-ONOP-030 for the running pump.

TERMINATING CUE:

CUE Evaluator informs the Applicant that another operator will continue in this procedure. The JPM is complete.

COMMENT Stop Time 2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 13 of 14 Form ESCZi1 Verification of Completion:

Job Performance Measure No. 01030008303 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET I 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.

I 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:

• Unit 3 is in Mode 3

• Unit 4 is in model at 100% power

• 3A CCW pump is out of service and breaker is racked out.

Initiating Cue:

• You are to respond to plant conditions as the Unit #3 Reactor Operator.

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.

2011 NRC Exam (RO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 14028009500 JPM: Locally Trip the Task

Title:

Reactor and Main Turbine JPM No: 14028009501 K/A

Reference:

029 EA 1.1 RO 3.9 SRO 4.1 NRC Examinee: Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance X Performance Classroom Simulator Plant X HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

• 4-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS, is in progress on UNIT 4.

Initiating Cues:

• You have been directed to proceed to the Unit 4B MCC room and take local actions to trip the Unit 4 Reactor per 4-EOP-FR-S.1, RNO Step 7.a.

• You are then directed to trip the Main Turbine locally per 4-EOP-FR-S.1, RNO Step 7.b.

1 i

C

\L 2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 10 Form ES-C-I Task StanthrcL

• Unit 4A and 4B Reactor Trip Breakers are open, Unit 4A and Unit 4B generator output breakers are open, and Unit 4A and Unit 4B motor input breakers are open.

• Main Turbine is tripped from the Front Standard.

Required Materials:

4-EOP-FR-S.1, Response to Nuclear Power Generation/A TWS, Step 7.

General

References:

• 4-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 10 Form ES-C-I Denote critical steps with a check mark (4 Start Time SAT STEP I Obtain required reference materials.

UNSAT STANDARD Applicant obtains a copy of 4-EOP-FR-S.1, Response to Nuclear Power Generation/A TWS.

CUE Provide Applicant with a copy of 4-EOP-FR-S.1, Response to Nuclear Power Generation/A TWS, Step 7.

COMMENT 2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 10 Form ES-C-I In 4B MCC room, locally trip reactor as follows:

SAT STEP 2 Open 4A and 4B Reactor Trip Breakers. UNSAT J

(4-EOP-FR-S.1, RNO Step 7.a., Bullet 1)

Applicant proceeds to the Unit 4B MCC Room and locates the RTB5. Explains that the red CLOSED flag should be showing for the RTBs.

STANDARD Applicant opens the Unit 4A and 4B Reactor Trip Breakers by depressing the TRIP button on the front of the Unit 4A and 4B Reactor Trip Breakers. Explains that the green OPEN flag should be showing.

When the Applicant explains expected conditions at the RTBs, inform the Applicant that the red CLOSED flag is showing for the Unit 4 A and 4B Reactor Trip Breakers.

CUE When the Applicant demonstrates opening each of the breakers by depressing the TRIP button on the front of the Unit 4A and 4B Reactor Trip Breakers, inform the Applicant that the green OPEN flag is indicated.

COMMENT EVALUATOR NOTE:

NOTE The Unit 4A and 4B Reactor Trip Breakers may be opened in any order.

2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 10 Form ES-C-I Open 4A and 4B Reactor Trip Bypass Breakers.

SAT STEP 3 UNSAT (4-EOP-FR-S.1, RNO Step 7.a., Bullet 2)

Applicant describes that the Unit 4A and 4B Reactor Trip Bypass STANDARD Breakers should show a green OPEN flag; therefore, depressing the TRIP button on the front of the Unit 4A and 4B Reactor Trip Breakers is not required.

When the Applicant describes that the Unit 4A and 4B Reactor Trip Bypass Breakers should show a green OPEN flag and CUE should be withdrawn from the cubicle, inform the Applicant that the RTBP is withdrawn from the cubicle and that the green OPEN flag is indicated.

COMMENT EVALUATOR NOTE:

The Unit 4 Reactor Trip Breakers are normally racked out NOTE EVALUATOR NOTE:

This Step is NOT critical because the Initial Conditions indicate that the Reactor Trip Bypass Breakers are already open; therefore, would not require operator actions.

2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 10 Form ES-C-I Open A/B MG set generator output breakers.

STEP 4 SAT

,J UNSAT (4-EOP-FR-S.1, RNO Step 7.a., Bullet 3)

Applicant describes that the green light should be OFF and the red light should be ON initially.

Applicant places the GENERATOR 4A control switch for the 4A STANDARD MG set to the TRIP position. Explains that the green light should be ON and the red light should be OFF.

Applicant places the GENERATOR 4B control switch for the 4A MG set to the TRIP position. Explains that the green light should be ON and the red light should be OFF.

After Applicant explains the initial status of the generator output breaker, inform the Applicant that the green light is OFF and the red light is ON.

CUE When the Applicant explains expected conditions when the GENERATOR 4N4B control switches are operated, inform the Applicant that the green lights are ON and the red lights are OFF.

COMMENT 2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 10 Form ES-C-I Open A/B MG set motor input breakers.

STEP 5 SAT q UNSAT (4-EOP-FR-S.1, RNO Step 7.a., Bullet 4)

Applicant describes that the green light should be OFF and the red light should be ON initially.

Applicant places the MOTOR 4A control switch for the 4A MG set to the TRIP position. Explains that the green light should be STANDARD ON and the red light should be OFF.

Applicant places the MOTOR 4B control switch for the 4A MG set to the TRIP position. Explains that the green light should be ON and the red light should be OFF.

After Applicant explains the initial status of the motor input breaker, inform the Applicant that the green light is OFF and the red light is ON.

CUE When the Applicant explains expected conditions when the MOTOR 4A/4B control switches are operated, inform the Applicant that the green lights are ON and the red lights are OFF.

COMMENT 2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 10 Form ES-C-I STEP 5 Locally trip turbine at turbine front standard. SAT q UNSAT (4-EOP-FR-S.1, RNO Step 7.b)

Applicant describes that, to trip the Main turbine; the orange, RESET/TRIP lever is rotated clockwise to the TRIP position.

Indications of a turbine trip include, but are not limited to:

e Sound of turbine rolling down.

STANDARD

. Indications of lowering shaft rpm.

. Lowering bearing oil pressure.

. Turbine stop and control valves going closed.

EVALUATOR CUE:

After Applicant explains the initial trip method and provides some indications of the trip occurring, inform Applicant that the Main CUE Turbine is slowing down and bearing oil pressure is decreasing.

TERMINATING CUE:

The task is complete when the Applicant returns the JPM Briefing Sheet to the examiner.

COMMENT Stop Time 2011 NRC Exam (RO & SRO) JPM.-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 10 Form ES-C-I Verification of Completion:

Job Performance Measure No. 14028009501 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Resu It: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I 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:

4-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS, is in progress on UNIT 4.

Initiating Cues:

o You have been directed to proceed to the Unit 4B MCC room and take local actions to trip the Unit 4 Reactor per 4-EOP-FR-S.1 RNO Step 7.a.

o You are then directed to trip the Main Turbine locally per 4-EOP-FR-S.1, RNO Step 7.b.

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.

2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

1_STEP_[1_ACTIONIEXPECTED RESPONSE F]_RESPONSE NOT OBTAINED CAUTION If an SI signal exists or occurs and the reactor is subcritical, proper safeguards equipment alignment is required to be verified using Attachment 3 of 4-EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure.

7 Check If The Following Trips Have Occurred

a. Reactor trip a. In 4B MCC room, locally trip reactor as follows:

• Open 4A and 4B Reactor Trip Breakers.

• Open 4A and 4B Reactor Trip Bypass Breakers.

• Open A/B MG set generator output breakers.

• Open A/B MG set motor input breakers.

b. Turbine trip b. Locally trip turbine at turbine front standard.

c. Mid and East GCBs OPEN (Normally c. Perform the following:

30 seconds delay)

1) Manually open breakers.

2) IF breakers do NOT open THEN actuate Emergency Gen Bkr Trip Switch for the affected breaker(s).

3) jf breaker position indication is jQ available Jfl turbine speed is NOT decreasing, THEN direct Field Operator to perform the following:

a) Obtain key 17 from the Shift Manager key locker.

b) Locally trip Mid and East GCBs from the switchyard.

• 8W88

• 8W65 X

W97/daj/ab/nw

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01053002100 JPM: Preparations for Initiating Containment Vent Task

Title:

Alternate Air Pressurization JPM No: 01053002101 K/A

Reference:

103 A1.01 R03.7SR04.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance X Performance Classroom Simulator Plant X HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I 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:

o Unit3isatl00%.

• Containment Pressure is -1.5 psig and must be increased.

o The R-1 1, R-12 Backup Sampler is not installed.

Initiating Cue:

• The US has directed you to make preparations for initiating containment vent alternate air pressurization, per 3-NOP-094, Containment Post Accident Monitoring System, Section 5.3.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 13 Form ES-C-I Task Standard: -

• Containment Vent Alternate Air supply is aligned to pressurize containment.

Required Materials:

• 3-NO P-094, Containment Post Accident Monitoring System.

General

References:

• None Time Critical Task: No Validation Time: 20 minutes 2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 13 Form ES-CT Denote critical steps with a check mark (i1 - Start Time SAT STEP I Obtain the required reference materials.

UNSAT STANDARD Applicant obtains a copy of 3-NOP-094, Containment Post Accident Monitonng Systems.

Provide a copy of 3-NOP-094, Containment Post Accident CUE Monitoring Systems. At a minimum, include the Cover Page, Precautions and Limitations, and Section 5.3.

COMMENT PERFORM one of the following:

SAT Outside the Unit 3 BA Evap Room: UNSAT STEP 2 REMOVE the floor cap for MPAS-OO1, WHT PUMP DISCHARGE TO RADWASTE BUILDING.

(3-NOP-094, 5.3.1.A.(1)

Applicant locates the floor cap for MPAS-OO1 outside of the Unit STANDARD 3A BA Evaporator Room. Rotates the cap counter-clockwise until it is off, and then sets it aside.

Applicant describes obtaining the tools from the wall after unlocking them with the key, normally maintained by operators.

CUE Inform the Applicant that the cap rotates freely and eventually comes loose.

COMMENT 2011 NRC Exam (RO)JPM-j NUREG 1021 Rev9AppendixC

Appendix C Page 4 of 13 Form ES-C-I NOTE NOTE Full travel for valve is provided n parentheses. Turning these values beyond full travel may damage the reach rod assemblies CLOSE MPAS-OO1, WHT PUMP DISCHARGE TO RADWASTE SAT STEP 3 BUILDING (1/4 turn).

UNSAT (3-NOP-094, 53.1 .A.(2)

Applicant rotates the reach-rod operator for MPAS-001 STANDARD clockwise 1/4 turn.

CUE Inform the Applicant that the valve operator rotates freely.

COMMENT EVALUATOR NOTE:

NOTE Because MPAS-OO1 (this step) and valve 1731 (next step) are in series, there is no adverse effect if both are closed by the Applicant.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 13 Form ES-C-I At the Waste Evaporator Feed Pump Room in the Radwaste SAT STEP 4 Bldg, CLOSE valve 1731, WHT TO RWB WHT ISOL.

UNSAT I

(3-NOP-094, 5.3.1 .B.)

Applicant locates valve 1731 in the Waste Evaporator Feed STANDARD Pump Room and rotates the valve clockwise until it will no longer rotate.

CUE Inform the Applicant that the valve operator rotates freely.

COMMENT EVALUATOR NOTE:

NOTE Because MPAS-OO1 (previous step) and valve 1731 (this step) are in series, there is no adverse effect if both are closed by the Applicant.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 13 Form ES-C-I On the AuxiNary Building roof near the Unit 3 containment wall PERFORM the following: SAT STEP 5 UNSAT UNLOCK and OPEN MPAS-3-004, CONTAINMENT PURGE q AIR RETURN ISOL VLV TO MPAS (3-NOP-094, 5.3.2 & 5.2.A.)

Applicant locates MPAS-3-004 on the AB roof near the Unit 3 STANDARD containment wall, removes the locking device, and rotates the valve counter-clockwise until it will no longer rotate. Notes that the handwheel rises.

CUE Inform the Applicant that the valve operator rotates freely.

COMMENT STEP 6 CLOSE MPAS-3-005, CNTMT INST AIR BLEED TO VENT SAT DUCT.

J (3-NOP-094, 5.3.3.)

UNSAT STANDARD Applicant locates MPAS-3-005 and rotates the valve clockwise until it will no longer rotate. Observes the stem retract.

CUE Inform the Applicant that the valve operator rotates freely.

COMMENT 2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 13 Form ES-C-I ALIGN Unit 3 Containment Vent Alternate Air Supply as follows:

SAT STEP 7 OBTAIN Containment Vent Alternate Air Supply Hose from the UNSAT SNPO tool box located in Auxiliary Building Fan Room.

(3-NOP-094, 5.3.3 & 5.3.A.)

Applicant locates the SNPO tool box located in Auxiliary Building Fan Room and removes the red hose with the tag labeled for STANDARD UNIT 3 CONTAINMENT VENT ALTERNATE AIR SUPPLY HOSE.

EVALUATOR CUE:

CUE Inform Applicant that the hose is in the tool box.

COMMENT In the North/South hallway by the North end of the Waste Boron SAT Control Panel, ENSURE 40-946, INST AIR TO N-S HALLWAY STEP 8 UNSAT_____

HOSE CONN ISOLATION, is CLOSED.

(3-NOP-094, 5.3.B.)

Applicant locates40-946 in the North/South hallway by the North STANDARD end of the Waste Boron Control Panel and observes that the valve is closed by attempting to rotate the valve in the clockwise direction and noting that it will not rotate.

EVALUATOR CUE:

CUE Inform Applicant that 40-946 will NOT rotate in the CW direction.

COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical because the valve is already closed.

There would be NO impact on the task if the Applicant failed to check 40-946.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev9AppendixC

Appendix C Page 8 of 13 Form ES-C-I CONNECT Containment Vent Alternate Air Supply Hose to valve 40-946, INST AIR TO N-S HALLWAY HOSE CONN SAT STEP 9 ISOLATION. UNSAT_____

.1 (3-NOP-094, 5.3.C.)

STANDARD Applicant connects the hose to the hallway connection.

CUE Inform the Applicant that there are no problems with connecting the hose.

COMMENT ENSURE R-1 1, R-12 BACKUP AIR SAMPLER is STOPPED.

SAT STEP 10 UNSAT (3-NOP-094, 5.3.D.)

STANDARD Applicant notes that the backup sampler is not installed.

CUE Inform Applicant that the backup sampler is not installed.

COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical because the backup sampler is normally STOPPED. There would be NO effect on this task if the Applicant failed to check the backup sampler.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 13 Form ESCZ ENSURE 3-11-031, CONTAINMENT R-11112 GRAB SAMPLE STEP 11 RETURN ISOL, is LOCKED CLOSED.

(3-NOP-094, 5.3.E.)

Applicant locates 3-11-031 and observes that the valve is STANDARD LOCKED CLOSED by noting that the locking device is properly installed.

EVALUATOR CUE:

CUE Inform the Applicant that the locking device is properly installed.

COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical because 3-1 1-031 is normally LOCKED CLOSED. There would be NO effect on this task if the Applicant failed to check the valve.

2011 NRC Exam(RO)JPM-j NUREG 1021 Rev9AppendixC

Appendix C Page 10 of 13 Form ES-C-I ENSURE 3-11-030, CNMT RAD MON R-3-11 & 12 GRAB SAMPLE SPLY ISOL VLV, is LOCKED CLOSED. SAT STEP 12 UNSAT (3-NOP-094, 5.3.F.)

Applicant locates 3-11-030 and observes that the valve is STANDARD LOCKED CLOSED by noting that the locking device is properly installed.

EVALUATOR CUE:

CUE Inform the Applicant that the locking device is properly installed.

COMMENT EVALUATOR NOTE:

NOTE This Step is NOT critical because 3-1 1-031 is normally LOCKED CLOSED. There would be NO effect on this task if the Applicant failed to check the valve.

CONNECT remaining end of Containment Vent Alternate Air Supply Hose to 3-11-035, PACV ALTERNATE AIR SAT STEP 13 PRESSURIZER valve. UNSAT_____

I (3-NOP-094, 5.3.G.)

STANDARD Applicant connects the hose to 3-11 -035.

EVALUATOR CUE:

CUE Inform the Applicant that there are no problems with connecting the hose.

COMMENT 2011 NRC Exam(RO)JPM-j NUREG 1021 Rev 9 Appendix C

AppendixC Pagellofl3 FormES-OPEN 3-1 1-035, PACV ALTERNATE AIR PRESSURIZER STEP 14 valve. SAT UNSAT

.J (3-NOP-094, 5.3.H.)

Applicant locates 3-1 1-035 and rotates the valve counter-clockwise until it will no longer rotate.

STANDARD Applicant calls the Control Room and informs them that local actions are complete for Section 5.3 of 3-NOP-094.

EVALUATOR CUE:

Inform the Applicant that the valve operator rotates freely.

CUE TERMINATING CUE:

Evaluator informs the Applicant that another operator will complete the task. The JPM is complete.

COMMENT Stop Time 2011 NRC Exam (R0)JPM-j NUREG 1021 Rev9AppendixC

Appendix C Page 12 of 13 Form ES-C-I Verification of Completion:

Job Performance Measure No. 01053002101 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Resu It: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I wiIf explain the ihitial conditions, which steps to simulate or discuss, and provid e initiating cues.

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

Initial Conditions:

• Unit3isatlOO%.

• Containment Pressure is -1.5 psig and must be increased.

• The R-11, R-12 Backup Sampler is not installed.

Initiating Cue:

• The US has directed you to make preparations for initiating containment vent alternate air pressurization, per 3-NOP-094, Containment Post Accident Monitoring System

, Section 5.3.

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.

2011 NRC Exam (RO) JPM-j NUREG 1021 Rev 9 Appendix C

Procedure No.

TURKEY POINT UNIT 3 3-NOP-094 Revision No.

NORMAL OPERATING PROCEDURE 0

FPL Effective Date SAFETY RELATED 02118111 CONTINUOUS USE

Title:

CONTAINMENT POST ACCIDENT MONITORING SYSTEMS Responsible Department: OPERATIONS Special Considerations:

This is an Upgraded Procedure. Initial use should include increased awaren ess because of potential technical and/or sequential changes to the proced ure. After initial use of this procedure, provide comments back to the Procedure Upgrad e

Project.

FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document.

DATE VERIFIED_______ INITIAL________

Revision Approved By Approval Date UNIT# UNIT 3 DATE DOCT PROCEDURE 0 Brian Stamp 12/08/10 DOCN 3-NOP-094 SYS STATUS COMPLETED REV o

1. OF PGS

REVISION NO.: PROCEDURE TITLE:

PAGE:

0 CONTAINMENT POST ACC[DET PROCEDURE NO.: MONITORING SYSTEMS 5 of 58 3-NOP-094 TURKEY POINT UNIT 3 1.0 PURPOSE

1. This procedure provides instructions for operating:

Containment High Radiation Monitors

• Containment Pressure Monitors

• Containment Water Level Monitors

• Post Accident Sample System Heat Tracing

• Post Accident Hydrogen Monitors

2. This procedure provides instructions for alternate air pressurization of containment to support Severe Accident Management Guidance (SAMG).

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions

1. A Neutron Badge may be required by Radiation Protection when performing valve and system alignments in the PASS Sample Room.

2.2 Limitations

1. If the oxygen gas pressure to the Hydrogen Monitors decreases to less than 20 psi, then the monitors will be non-functional.

REVISION NO.: PROCEDURE TITLE:

PAGE:

0 CONTAINMENT POSTACC[DENT - - -

PROCEDURE NO.: MONITORING SYSTEMS 22 of 58 3-NOP-094 TURKEY POINT UNIT 3 5.3 Preparations For Initiating Containment Vent Alternate Air Pressurization PERFORM one of the following:

A. Outside the Unit 3 BA Evap Room:

(1) REMOVE the floor cap for MPAS-O01, WHT PUMP DISCHARGE TO RADWASTE BUILDING.

NOTE Full travel for valve is provided in parentheses. Turning these valves beyond full travel may damage the reach rod assemblies.

(2) CLOSE MPAS-0O1, WHT PUMP DISCHARGE TO RADWASTE BUILDING (1/4 turn).

B. At the Waste Evaporator Feed Pump Room in the Radwaste BIdg, CLOSE valve 1731, WHTTO RWB WHT ISOL.

2. On the Auxiliary Building roof near the Unit 3 containment wall PERFORM the following:

A. UNLOCK and OPEN MPAS-3-004, CONTAINMENT PURGE AIR RETURN ISOL VLV TO MPAS B. CLOSE MPAS-3-005, CNTMT INST AIR BLEED TO VENT DUCT.

3. ALIGN Unit 3 Containment Vent Alternate Air Supply as follows:

A. OBTAIN Containment Vent Alternate Air Supply Hose from the SNPO tool box located in Auxiliary Building Fan Room.

B. In the North/South hallway by the North end of the Waste Boron Control Panel, ENSURE 40-946, INST AIR TO N-S HALLWAY HOSE CONN ISOLATION, is CLOSED.

C. CONNECT Containment Vent Alternate Air Supply Hose to valve 40-946, INST AIR TO N-S HALLWAY HOSE CONN ISOLATION.

0. ENSURE R-11, R-12 BACKUP AIR SAMPLER is STOPPED.

E. ENSURE 3-11-031, CONTAINMENT R-11/12 GRAB SAMPLE RETURN ISOL, is LOCKED CLOSED.

REVISION NO.: PROCEDURE TITLE:

PAGE:

0 CONTAINMENT POST ACCIDENT PROCEDURE NO.: MONITORING SYSTEMS 23 of 5 3-NOP-094 TURKEY POINT UNIT 3 5.3 Preparations For Initiating Containment Vent Alternate Air Pressurization (continued)

3. (continued)

F. ENSURE 3-11-030, CNMT RAD MON R-3-11 & 12 GRAB SAMPLE SPLY ISOL VLV, is LOCKED CLOSED.

G. CONNECT remaining end of Containment Vent Alternate Air Supply Hose to 3-11-035, PACV ALTERNATE AIR PRESSURIZER valve.

H. OPEN 3-11-035, PACV ALTERNATE AIR PRESSURIZER valve.

4. ENSURE CONTAINMENT ISOLATION PHASE A is RESET.

5. At R-1 1 and R-12 drawer, PRESS PUMP ON/OFF button to turn off the Sample Pump. (light out)

6. ENSURE SV-3-2913, SOL VLV FOR CNTMT AIR MONIT INLET ISOL, is CLOSED.

7. PLACE SV-3-291 1, SOL VLV FOR CNTMT AIR MONIT IN LET, hand switch to OPEN.

8. CHECK SV.-3-2912, SOL VLV FOR CNTMT AIR MON IT SAMPLE RETURN, OPEN.

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 14013005300 JPM: l.A. Dryer Operations Task

Title:

During Loss of l.A. JPM No: 14013005301 K/A

Reference:

078 A3.01 RO 3.1 SRO 3.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of Testing:

Simulated Actual Performance X Performance Classr oom Simulator Plant X HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provid e initiating cues.

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

Initial Conditions:

o Reactor Power is 100%

o A loss of Instrument Air is in progress.

• The Unit 3 IA Dryer is in service and is purging excessively.

• The Unit 4 IA Dryer is NOT available.

• The Instrument Air System is in a normal alignment.

Initiating Cue:

• The US has directed you to check the operation of the Instrument Air Dryers per 0ONOP-013, Loss of Instrument Air, Steps 8 and 9.

2011 NRC Exam (RO & SRO) JPM-k

Appendix C Page 2 of 9 Form ES-C-I I Task Standard:

• The Instrument Air Dryers have been aligned per 0-ON OP-Ol 3, Loss of Instrument Air, Steps8and9.

Required Materials:

• 0-ONOP-Ol 3, Loss of Instrument Air General

References:

Time Critical Task: No Validation Time: 7 minutes 2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 9 Form ES-C-I Denote critical steps with an check mark (I)

Start Time STEP I Obtain the required reference materials. SAT UNSAT STANDARD Applicant obtains a copy of 0-ONOP-013, Loss of Instrument Air.

Provide Applicant with a copy of 0-ONOP-013, Loss CUE of Instrument Air.

COMMENT Check Locally That The Instrument Air Dryers Prop erly Aligned SAT STEP 2 And NOT Purging Excessively.

UNSAT STANDARD Applicant determines from the Initial Conditions that the Unit 3 Instrument Air Dryer is purging excessively.

Inform Applicant that the dryer is purging excessive CUE ly.

COMMENT 2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 9 Form ES-C-I Align the Instrument Air Dryers In accordance with 3/4-O P-013.

STEP 3 SAT (0-ONOP-013, RNO Step 8) UNSAT STANDARD Applicant notes from the Initial Conditions that the IA Syst em is in a normal alignment.

CUE Inform Applicant that the l.A. Dryers are in a normal align ment per 3/4-OP-013.

COMMENT IF air dryer is excessively purging, THEN CLOSE the asso ciated purge exhaust block valve: SAT STEP 4 U-3 (3T9): 3-40-380 UNSAT I U-4 (4T9): 4-40-380 (0-ONOP-013, RNO Step 8)

Applicant closes 3-40-380 by rotating the valve handle STANDARD approximately 900 in the clockwise direction until it no long er rotates.

CUE Inform Applicant that 3-40-380 rotates freely in the clock wise direction until it no longer rotates.

COMMENT EVALUATOR NOTE:

NOTE 3-40-380 and 4-40-380 are labeled IA DRYER PURGE EXH BLK VLV.

2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 9 Form ES-C-I NOTE e iis-g..oi nd IAS-4-012 htl be qoened AFTER the SM ha erred that Sy.tecn Opereticr ha erabSed the NERG toad thedding condng enoy re.

Check Locally The Pressure Drop Across The Inservice Instrument Air Dryer To Be Less Than 10 PSID SAT Pl*628O (2 ft off ground back of UNSAT Instrument Air Dryer) minus P1-

• 3423 STEP 5 q OR Pl*628O minus Pl*3424 (0-ONOP-013, Step 9)

Applicant locates P1-3-6280, P1-3-3423, and P1-3-3424 and notes pressure readings. Transitions to the RNO column.

STANDARD This is an Alternate Path aspect of this JPM.

Inform Applicant that P1-3-6280 reads 108 psig by pointing to that value on the gauge.

CUE Inform Applicant that P1-3-3423 reads 85 psig by pointing to that value on the gauge.

COMMENT EVALUATOR NOTE:

NOTE 3-3424 is RIGHT CHAMBER PRESS 3-3423 is LEFT CHAMBER PRESS 2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev9AppendixC

Appendix C Page 6 of 9 Form ES-C-I COhtct System Operatión, ensure NERO load shedding contingency software has been enabled.

STEP 6 SAT UNSAT (O-ONOP-013, RNO Step 9.a)

STANDARD Applicant notes that Systems Operations does NOT need to be contacted since the Unit 4 Air Dryer is out of service.

CUE If Applicant attempts to inform System Operation s, inform applicant that Systems Operations will be notif ied by the SM.

COMMENT IF the air dryer is available on the opposite unit, THEN cross-tie the Instrument Air Systems by opening the Instr ument Air Cross-tie Valves:

IAS-3-O 12 STEP 7 q AND IAS-4-O1 2 (O-ONOP-013, RNO Step 9.b)

Applicant notes from the Initial Conditions that STANDARD the Unit 4 Air Dryer is NOT available. Goes to next step.

EVALUATOR CUE:

CUE Inform Applicant that the Unit 4 Air Dryer is NOT available due to the temporary IA modification. There is a CAUTIO N tag on IAS-4-O1 2.

COMMENT 2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev9AppendixC

Appendix C I Page 7 of 9 Form ES-C-I IF the Air Dryer on the opposite unit is NOT avaHable, THEN peh the Instrument Air ryer Bypass Valve to supp ly air to the affected unit(s).

IAS-3-01 6 STEP 8 OR IAS-4-030 (0-ONOP-013, RNO Step 9.c)

Applicant locates IAS-3-016 and rotates the valve hand STANDARD le approximately 900 in the counterclockwise direction until it stops rotating.

EVALUATOR CUE:

Inform Applicant that IAS-3-016 rotates freely in the counterclockwise direction until it stops rotating.

CUE TERMINATING CUE:

JPM is terminated when the Applicant returns the JPM Briefing Sheet to the Evaluator.

COMMENT Stop Time 2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev 9 Appendix C

L Appendix C Page8of9 Form ES-1 Verification of Completion:

Job Performance Measure No. 14013005301 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO & SRO) JPM-k NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET I willexplain the irltiaI Oonditions, which step to simu late or discuss, and provide initiating cues.

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

Initial Conditions:

• Reactor Power is 100%

o A loss of Instrument Air is in progress.

• The Unit 3 IA Dryer is in service and is purging exce ssively.

• The Unit 4 IA Dryer is NOT available.

• The Instrument Air System is in a normal alignmen t.

Initiating Cue:

• The US has directed you to check the operation of the Instrument Air Dryers per 0-ONOP-Ol Loss of Instrument Air, Steps 8 and 9. 3, Acknowledge to the examiner when you are ready to begin.

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

2011 NRC Exam (RO & SRO) JPM-k

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

6 WHEN It Is Desired To Return An Isola ted Instrument Air Compressor To Service, THEN Perform The Following For 3CM, OPEN IAC 3CM Discharge Isol Vlv IAS-3-058 For 3CD, OPEN lAG 3CD Discharge Isol Vlv IAS-3-059 For 4CM, OPEN AC 4CM Discharge Isol VIv IAS-4-058 For 4CD, OPEN IAC 4CD Discharge Isol VIv IAS-4-059 I.E EC 246991, Unit 4 Instrument Air System Upgrade, is in progress, THEN:

For TC 1 (Unit 3 temporary instrument air compressor)) OPEN IAS-3-037 Supply Line Drain Valve For TC 2 (Unit 4 temporary instrument air compressor) OPEN VC , TC 2 2 Compressor Discharge Isolation Valve For TC 3 (Unit 4 temporary instrument air compressor) OPEN VC , TC 3 3 Compressor Discharge Isolation Valve For TC 4 (Unit 4 temporary instrument air compressor) OPEN VC , TC 4 4 Compressor Discharge Isolation Valve 7 GotoStepil 8 Check Locally That The Instrument Air Align the Instrument Air Dryers In Dryers Properly Aligned And NOT Purg ing accordance with O-NOP-013.

Excessively jf air dryer is excessively purging, THEN CLOSE the associated purge exhaust block valve:

U-3 (3T9): 3-40-380 U-4 (4T9): 4-40-380

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Procedure No.:

Procedure

Title:

Page:

10 Approval Date:

O-ONOP-013 Loss of Instrument Air 7/20/11 j STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 1

icioF

• IAS-3-012 and IAS-4-012 shall be opened AFTER the SM has ensured that System Operations has enabled the NERC load shedding contingency software.

a a a 9 Check Locally The Pressure Drop Across Perform the folbwing:

The Inservice Instrument Air Dryer To Be Less Than 10 PSID a. Contact System Operations, ensure NERC load shedding contingency Pl*628O (2 ft off ground back of software has been enabled.

Instrument Air Dryer) minus Pl*3423

b. IF the air dryer is available on the opposite unit, THEN cross-tie the Pl*628O minus PI*3424 Instrument Air Systems by opening the Instrument Air Cross-tie Valves:

• IAS-3-012 AND

• IAS-4-012

c. jf the Air Dryer on the opposite unit is

!+/-QI available, THEN open the Instrument Air Dryer Bypass Valve to supply air to the affected unit(s).

IAS-3-016 OR IAS-4-030

d. Notify the System Engineer to investigate cause of the high DP to coordinate immediate repairs as required.

e. Refer to 0-ONOP-Ol 3.1, INSTRUMENT AIR DRYER MALFUNCTION, for additional local actions while continuing with this procedure.

f. WHEN IAS-3-012 or IAS-4-012 have been closed, notify System Operations that the NERC load shedding contingency software can be disabled.

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