ML12166A520

Initial Exam 2011-302 Final Sim_IN-Plant JPMs

ML12166A520
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: ML12166A520 (307)

Text

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• RCC Control Bank D is at 165 steps withdrawn, with the RPI for Control Rod M8 indicating 145 steps.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 directs you as the Unit 3 Reactor Operator to align Control Rod M8 using 3-ONOP-028. 1, starting at Step 5.9.1.

• Reactor Engineering Supervisors recommends 1) Borate as required to maintain Tavg within 1°F of Tref.

2) Rod withdrawal rate should be 1015 steps per minute (per Step 5.9.8.3).

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

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

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

Required Materials:

• 3-ONOP-028. 1, RCC Misalignment

• Key for Rod Disconnect Switch Cabinet General

References:

• 3-ONOP-028.1, RCC Misalignment

• Technical Specifications Time Critical Task: No Validation Time: 20 minutes 2011 NRC (RO) JPM-a NUREG 1021 Rev 9 Appendix C

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

1. Reset to IC 191 or equivalent IC.

2. Place Simulator in RUN.

3. Place Rod Selector in Manual.

4. Ensure Simulator Operator Checklist is complete.

5. Check Control Key Log to ensure information is removed from previous JPMs.

6. Acknowledge alarms and place Simulator in FREEZE.

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

8. 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.

9. When ready to begin, then place Simulator in RUN.

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 (q) Start Time If the applicant desires to borate prior to the withdrawl of the EVALUATOR misaligned rod, then inform the applicant that the Unit Supervisor NOTE has directed the Admin Reactor Operator to calculate for a boration following the rod pull.

Obtain 3-ONOP-028. 1, RCC Misalignment.

SAT STEP I U NSAT STANDARD Applicant obtains 3-ONOP-028. 1, RCC Misalignment.

CUE Provide Applicant with a copy of 3-ONOP-028. 1, 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 bank which has the misaligned RCC. SAT STEP 4 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 alI.the lift coil disconnect Sw hes-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 Applicant may sign out key from Locker in Key Log. It is COMMENT acceptable to simulate or perform. If performed, replace the page from the key log for exam security purposes.

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

1. Bank STEP 6 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 q UNSAT (3-ONOP-028.1 Step 5.9.6)

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

CUE COMMENT May use a pointy device to push buttons (Example-pen/pencil).

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 STANDARD bank.

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

rAppendix C Page 9 of II Form ES-C-I

- CAUTION Failure to follow instructions provided by the Reactor Engineering Supervisor could affect fuel integrity caused by power peaking.

NOTE I NOTE T

L Annunciator 89/4, ROD CONTROL URGENT FAILURE and the RCC power cabinet will alarm for the group with the lift coils dco:ecd. - -!

Place the Rod Motion Lever to the IN/OUT position, as STEP 9 applicable. SAT 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).

CUE COMMENT EVALUATOR NOTE:

Annunciator SHUTDOWN ROD OFF TOP DEVIATION (B 9/3)

NOTE may actuate.

This is due to the Difference in RPI between any two rods in the same bank greater than 12 steps or 24 steps while moving.

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

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 Campletiori:

Job Performance Measure No. 01028016303 - JPM: Recover Misaligned Control Rod Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

TimetoCompete:

Question Documentation:

Question:

Response

Resuft Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC (RO) JPM-a 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:

• 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.

o The US directs you as the Unit 3 Reactor Operator to align Control Rod M8 using 3-ONOP-028.1, starting at Step 5.9.1.

• Reactor Engineering Supervisors recommends 1) Borate as required to maintain Tavg within 1°F of Tref.

2) Rod withdrawal rate should be 1015 steps per minute (per Step 5.9.8.3).

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-a 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:

• 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 directs you as the Unit 3 Reactor Operator to align Control Rod M8 using 3-ONOP-028.1, starting at Step 5.9.1.

• Reactor Engineering Supervisors recommends 1) Borate as required to maintain Tavg within 1°F of Tref.

2) Rod withdrawal rate should be 1015 steps per minute (per Step 5.9.8.3).

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-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, 01-0796F 09-006 W97/JWB/emc/cls/nw

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 04/07/0 9 11 04/07/09 12 08/02/10 13 04/07/09 W971. WB!em IrJsInw

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

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.

a a a = a a a a a 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.

Ai(1i

2.9 Annunciators 2.9.1 B 2/2, POWER RANGE UPPER DET HI FLUX DEV/AIJTO 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 fIQ7/. IMR!pmcIrhinw

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

Proceed as follows:

.2.1 reactor power is greater than 75 percent more than one RCC is misaligned, THEN:

A Borate/dilute AND/OR change Turbine load to maintain Tavg within 3°F of Use RCC motion only to control axial flux within the target band.

If increasing Reactor power to approximately 3 percent (stay in Mode 2) for a flux map, rod I motion may be used. I Do NOT withdraw control rods to increase power until the affected RCCs 1 have been aligned, except as noted above.

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

oti 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).

I RPI gain adjustments should be delayed until O-OSP-059 14 Rod Position Indication (RPI) I i verification is performed.

ti: t I;C per:or:

possible failure.

indti o

vti; CRDM System for

AIn1,

c;)

When more than one RCCA in the same bank 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.

Have 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:

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

Check A Flux meters.

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 Deviation/Axial Flux Panel IF the RCC is determined to be aligned with the associated bank AND an RCC position indicator is failed, THEN go to 3-ONOP-028.2, RCC Position Indication Malfunction.

IF more than one RCC is inoperable or misaligned from the group demand step counter position by more than the Allowed Rod Misalignment of Technical Specification 3.1.3.1, THEN comply with the actions of Technical Specification 3.1.3.1.

M(r7I

© 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

1. 7 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 A

/V1 1/ 5.8.3 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 FAHN 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

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. jj 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).

\A1fl71 IQII,-I.,i.-.

Procedure No.: Procedure

Title:

Page:

9 Approval Date:

3-ONOP-028.1 RCC Misalignment 8/2/10 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 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.

AIO7I

CAUTION Failure to follow instructions provided by the Reactor Engineering Supervisor could affect fuel integrity caused by power peaking.

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

= = = = = = = = = = = a = a a = a 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 TN/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 Shifi 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 verif 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 r c C C C An Incore Flux Map is optiona at the discretion of the Reactor Engineering Supeisor 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.

A!O7I

Procedure No.: Procedure

Title:

Page:

12 Approval Date:

3-ONOP-028.1 RCC Misalignment 8/2/10

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 INPO SOERs

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 EN1 OF TEXT AIfl7I

Procedure No.: Procedure

Title:

13 Approval Dat&

3-ONOP-028.1 RCC Misalignment 4/7/09 ENCLOSURE 1 (Page 1 of 1)

ACCIDENT ANALYSES REQUIRING RE-EVALUATION IN THE 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

\A1071. ItA!Rimr/rIirw

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 KJA

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 J PM 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.

• A loss of offsite power has occurred.

o 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.

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.

o 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 Page 2 of II Form ES-C-I TaskStandard:

• The 3A 4KV Bus is energized from offsite power and the 3A EDG 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:

o None Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO) JPM-b NUREG 1021 Rev 9 Appendix C

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

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

2. Place Simulator in RUN.

3. Ensure Simulator Operator Checklist is complete.

4. Acknowledge alarms and place simulator in FREEZE.

5. 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.

6. When ready to begin, then place the Simulator in RUN.

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 (i4 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 Pug.

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 Rev9AppendixC

Appendix C Page 5 of II Form ES-C-I CAUTION Vi7ien the Startup Transformer breaker is closed, the EDG load will drop to ze. To NOTE prevent potentla damage to the EDG. the EDG.output breaker should be opened as soon as the Startup Tranaformer is veried to be carrying 41W bus toad.

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

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

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

AppNcant 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 SAT close Startup Transformer 3A 4KV Bus Supply, 3AA05 UNSAT (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 0 SEQUENCER 3A TROUBLE (X 1/3) will actuate.

EVALUATOR . . .

NOTE

• The applicant may exercise the Caution prior to 3-ONOP-004.1, Step 8 and open the 3A Emergency Diesel Bkr to 3A_4KV_Bus,_3AA20,_prior to_performing_Step_8.e.

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

Appendix C Page 7 of II I Form ES-C-I Place Startup Transformer Sync to 3A 4KV Bus 3AA05 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 STEP 7 Open 3A Emergency Diesel to 3A 4KV Bus, 3AA20.

q (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 OFF.

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 STEP 8 using Diesel Generator Speed Changer. UNSAT J

(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 q

(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

/ STOP (3-ONOP-004.1, Step 9d)

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 Inform the Applicant that another operator will restore the CUE 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- JPM: Recover from a Loss of Offsite Power 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-b NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET I wiN 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.

• 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 u through Step 7.

o 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

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:

• 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, 91-2743F 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, 8 7-263,87-264, 87-265 94-059,01-009 W97:DH/ev/mrg/In

LIST OF EFFECTIVE PAGES Revision Revision Date Date 1 09/04/07 21 09/04/07 2 09/04/07 22 0 9/04/07 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 0 9/04/07 36 09/04/07 17 09/04/07 18 09/04/0 7 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-Ll, 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-L1, 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

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)

OR4]

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 AND 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. PC/M 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 94-05 9, Diesel Engine Driver for Standby Steam Generator Feedwater Pump P82B W97:DH/evlmra/In

3.1.6 Miscellaneous

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

2. JPN-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 250/95-006)

W97:DH/ev/mrq/In

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CCW System load requirements for the EOP network, 3-ONOP-0413, SHUTDOWN LOCA [MODE 3 (LESS THAN I000PSIG) OR MODE 4) 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 Light On VPA 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. Go to Step 65.

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

Supply, 3AA05 OPEN W97:DH/ev/mrgIln

Procedure No.: Procedure

Title:

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

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 restoration 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

- Goto Step 11.

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

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION When the Startup Transformer breaker is closed the EDO 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 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 NOT 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/evfmrglln

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

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.

Start/Normal 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 NOT 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/mrg/ln

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 13 Check CCW Headers TIED TOGETHER

- Perform the following:

a. IF both COW 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

• FeederTo4KVBus3D, 3AA17-CLOSED 16 Check Station Blackout Breaker, 3AD07 - Perform the following:

OPEN

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

c. Stop 3C Intake Cooling Water Pump.

W97:DH/evlmrg/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 I

a =

When only one component cooling water pump is runnhg, 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 304KV 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, 3AA1 7

c. Open Supply From 4KV Bus 3A, 3AD01

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

e. Close Feeder To 4KV Bus 3D, 3AB1 9 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. IF neither pump can be started, THEN go to Step 33.

c. Stop 3A Intake Cooling Water Pump.

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 I STEPJ ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED a liii a

=

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

21 Check 3A 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 3C Component Cooling Water Pump. IF 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. jf 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 NOT be stopped, THEN go to Step 33.

d. Stop 3A RHR pump.

W97:DH/ev/mrg/ln

STEP ACTION/EXPECTED RESPONSE I 1 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) AND 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 NOT 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. 3B Turbine Plant Cooling Water Pump can NOT 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 NOT be stopped, THEN go to Step 33.

d. Stop 3A Turbine Plant Cooling Water Pump.

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 f STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I a a a a a a a ioF When 3A 4KV bus is deenergizecJ the bearing oil lift pump will stop.

a a a I

fl c I 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. IF 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

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

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 o 3AO9, 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. IF 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 ACTION/EXPECTED 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. Performthe 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/evJmrg/n

STEP ACTION/EXPECTED 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 3OP030, 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.

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

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:DHJev/mrglln

I5TEP I I ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 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 4K! 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

- Goto Step 41.

EMERGENCY DIESEL GENERATOR 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 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 EDG output breaker should be opened as soon as the Startup Transformer is verified to be carrying 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. IF Startup Transformer 3B 4KV Bus 12 oclock position, THEN close Startup Supply, 3AB05, can NOT 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 3B 4KV Bus 3AB05 to OFF AND remove handle W97:DH/ev/mrg/In

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-004.J. System Restoration Following Loss of Offsite Power 9/4/07 STEP 1 I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 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 GoToStep64 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. IF 3A 4KV bus can NOT 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. f intake cooling water headers can NOT 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 COW headers are intact, THEN tie headers together.

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

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

- Go to Step 50.

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

CLOSED Feederto4KVBus3D, 3AB19-CLOSED 46 Check Station Blackout Breaker, 3AD07 - Perform the following:

OPEN

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

b. Start 3A Intake Cooling Water Pump.

c. Start 3A Component Cooling Water Pump.

d. IF either pump can Qj 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. j 3A Intake Cooling Water Pump can NOT be started, THEN start 3B Intake Cooling Water Pump. IF neither pump can be started, THEN go to Step 62.

c. Stop 3C Intake Cooling Water Pump.

W97:DH/ev/mrg/In

Procedure No. Procedure

Title:

Page:

Approval Date:

3-ONOP004.1 System Restoration Following Loss of Offsite Power 9/4/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

=

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 foflowing:

- STOPPED

a. Start 3A Component Cooling Water Pump.

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

c. Stop 3B Intake Cooling Water Pump.

W97:DH/ev/mrg/ln

Procedure No. Procedure

Title:

Page:

23 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

r I I 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. IF 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. IF 3A Charging Pump can NOT 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. IF 3B RHR pump can NOT be stopped, THEN go to Step 62.

d. Stop 3B RHR pump.

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STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 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 48 High-Head SI Pump(s) Jfl align valves as directed by the Shift Manager to allow stopping of 38 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 QJ 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. IF 3A Turbine Plant Cooling Water Pump can NOT be started, THEN consult with the Shift Manager to determine if 3B Turbine Plant Cooling Water Pump can be stopped.

c. jf 38 Turbine Plant Cooling Water Pump can Q] be stopped, THEN go to Step 62.

d. Stop 3B Turbine Plant Cooling Water Pump.

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STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTIONS

• Continuing with this procedure without defeating 38 Emergency Diesel Auto Start capability as outlined in Step 44 will result in a restart of the EDG.

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

56 Check Station Blackout Breaker, 3AD07 -

if 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

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I 57 Transfer 3B 4KV Bus To Unit 3 Startup Transformer

a. Open or verify open all alternate supply breakers to 38 4KV bus o 3A802, Auxiliary Transformer 3A 4KV Bus Supply

• 3AB20, 3B Emergency Diesel to 3B 4KV Bus o 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 38 4KV Bus 3AB05 to ON

d. Close Startup Transformer 3B 4KV Bus d. IF Startup Transformer 3B 4KV Bus Supply, 3AB05 Supply, 3AB05, can NOT 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 38 4KV Bus 3AB05 to OFF AND remove handle W97:DH/ev/mrg/In

STEP ACTION/EXPECTED RESPONSE I LRESPONSE 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

STEP ACTION/EXPECTED 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 PSIG) OR MODE 4J and 3-ONOP-041.8, SHUTDOWN LOCA [MODE 5 OR 6), SHALL NOT exceed the limits specified in 3-OP--030, COMPONENT COOLING WATER SYSTEM.

If 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-0Q7, 480 VOLT MOTOR CONTROL CENTERS.

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

a. Safety Related Components

a. Sequencer failure may have occurred;

• 38 Intake Cooling Water Pump perform the following:

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

• 38 High-head SI Pump

2) Attempt to close the breaker.

• 3B Residual Heat Removal Pump

• 38 Turbine Plant Cooling Water Pump

• Verify one Auxiliary Building Exhaust Fan RUNNING

• SFP Exhaust Fan

b. HVAC Equipment Computer Room Chiller

• Battery Room Air Conditioner E16E (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 ACTION/EXPECTED 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. IF previous attempts to close Startup Transformer 3A 4KV Bus Supply, 3AA05, in Steps 8 or 28 were QI successful, THEN go to Step 65.

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

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

d. ffl 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 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

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 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. IF offsite power is NOT available, o 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. jf at least one 3C Transformer Supply Breaker can not be closed, THEN go to Step 76.

W97:DH/evimrg/In

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

70 Stop Components Supplied By 3C 4KV jf any component supplied by 3C 4KV bus Bus can NOT 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

• 3CRCPOilLiftPump

• Water Treatment Plant

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

• Open 3E Load Center Supply Breaker (Polishing Area), 3AC04

• Open 3F13G Load Center Supply Breaker (Intake Area), 3AC1 1 W97;DHIev/mrg/In

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 30 Transformer, 3AC16 to ON

e. Close 30 Bus Supply from 30 e. IF 30 Bus Supply from 30 Transformer, 3AC1 6 Transformer, 3AC1 6, can NOT be closed, THEN perform the following:

1) Place 30 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 30 4KV Bus using 3-ONOP-004.4, LOSS OF 30 4KV BUS, while continuing with this procedure.

4) Go to Step 76.

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

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 ACTIONIEXPECTED RESPONSE

] RESPONSE NOT OBTAINED I

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. ffi any load center can NOT be (Intake Area), 3ACI I 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.

L__J 75 Restart Components Supplied By 3C 4KV Bus As Directed By The Shift Manager

• 3C Condensate Pump

• 3B Steam Generator Feedwater Pump

• 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:DHfevfmrg/In

STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOTOBTAINED I

77 Verify All 4KV Buses ENERGIZED BY

- Perform the following:

OFFSITE POWER

a. Direct System Dispatcher to continue

• A4KVbus efforts to restore offsite power to Unit 3 Startup Transformer and

• B4KVbus 3C Transformer.

• D4KVbus b. WHEN offsite power has been restored to Unit 3 Startup Transformer, THEN

• C4KVbus return to 3-ONOPOO4.1 SYSTEM RESTORATION FOLLOWING LOSS OF OFFSITE POWER.

c. WHEN offsite power has been restored to 30 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

• 3AA,09, 3A 4KV Bus Tie To 3B Or 3C 4KV Bus

• 3AO5, Startup Transformer 3A 4KV Bus Supply a 3AO2, Auxiliary Transformer 3A Bus Supply

• 3AA,03, Steam Generator Feed Pump 3A a 3AA07, Heater Drain Pump 3A

• 3AA21 Condensate Pump 3A

• 3AA1 3, Safety Injection Pump 3A a 34A15, Residual Heat Removal Pump 3A a 3AA12, Component Cooling Water Pump 3A a 3AAO1 Reactor Coolant Pump 3A

• 3AA19, Intake Cooling Water Pump 3A

• 3AAI 1, Turbine Plant Cooling Water Pump 3A

• 3AA16, Circulating Water Pump 3A1 a 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.

3. IF Supply From 4KV Bus 3A, 3ADO1, 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, breaker for Component Cooling Water Pump 3C, 3AD04, can NOT be opened, THEN open Feeder To 4KV Bus 3D, 3AA17, AND Supply From 4KV Bus 3A. 3ADO1.

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

W97DH/v!mra/In

Ptocedute Nb.: - Procedure

Title:

- Pig 36 Approval Date:

3-ONOP-004.1 System Restoration Following Loss of Offsite Power 9/4/07 ATTACHMENT 2 (Page 1 of 1) 38 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 o 3AB02, Auxiliary Transformer 3B Bus Supply

• 3ABI 0, Heater Drain Pump 3B

• 3AB21, Condensate Pump 3B

• 3AB12, Safety Injection Pump 3B o 3AB15, Residual Heat Removal Pump 3B

• 3AB13, Component Cooling Water Pump 3B

• 3ABO1 Reactor Coolant Pump 3B

• 3AB06, Reactor Coolant Pump 3C

• 3AB17, Intake Cooling Water Pump 3B

• 3ABI 1 Turbine Plant Cooling Water Pump 3B

• 3AB16, Circulating Water Pump 3B1 o 3A81 8, 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, 3AA1 9, is open.

3. IF Supply From 4KV Bus 3B, 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, OR breaker for Component Cooling Water Pump 3C, 3AD04, can NOT be opened, THEN open Feeder To 4KV Bus 3D, 3A819, AND Supply From 4KV Bus 3B, 3AD06.

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

FINAL PAGE W97:DH/ev/mro/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.

• 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:

• 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 (RO) JPM-c NUREG 1021 Rev 9 Appendix C

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 4.1.1.B-E.

• Applicant actuates 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:

o 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-GO P-305, Hot Standby to Cold Shutdown Time Critical Task: Yes*

Validation Time: 10 minutes Time critical portion of this JPM is after the automatic SI setpoint of 1730 psig has been exceeded. The applicant has 16 minutes to actuate a Manual SI.

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

[Apendix C Page 3 of 12 Form ES-C-I SIMIJ LATQR SETUP

1. Reset to IC 193 forJPM or equivalent IC.

2. Place Simulator in RUN.

3. Open Lesson JPM - 01041003201 and Execute.

4. Ensure Simulator Operator Checklist is complete.

5. Acknowledge alarms and place Simulator in FREEZE.

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

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.

8. When ready to begin, then place Simulator in RUN.

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 (4 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 4.11.6.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 Operabilitj Test is required to be completed pflorto placing NOTE OMS in seniice if NOT done wIin the last 31 days.

• Only one loop of OMS shall be tested at 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-DSP-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 Rev9AppendixC

Appendix C Page 6 of 12 Form ES-C-I CYCLE MOV-3-535, PRZ PORV BLOCK VALVE, as follows: SAT UNSAT 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. SAT UNSAT (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 results shouid be recorded in me Un[t N3rrauva Log.

STEP 5 CYCLE PCV-3-456, PRZ PORV, full OPEN then CLOSED. SAT

.q UNSAT (3-NOP-041.04, Step 4.1.1.7.C.)

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

3) Applicant marks SAT in the table.

CUE COMMENT T

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

UNSAT q

(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.

EXAMINER If PCV-3-456, PRZ PORV, is placed in AUTO during STEP 5 NOTE of this JPM, then this step becomes non-critical.

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-3-53 PRZ PORV LOK 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 STAN DARD 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, PRZPORV 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 Rev 9 Appendix C

ApQendix C Paqe 10 of 12 Form ES-C-I NOTE NOTE UNSAT results shou be recorded in me Unit Narrstwe Loq.

STEP 10 CYCLE PCV-3-455C, PRZ PORV, full OPEN then CLOSED.

(3-NOP-041.04, Step4.1.1.7.G.)

1) 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:

• PZRJRCS pressure decreasing

• PZR level decreasing o Annunciators:

o A4/1 PORV/SAFETYVALVE OPEN o A 9/2 PRZ CONTROL HI/LOW PRESSURE o A712 PZRPORVHITEMP

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

(Valve does NOT close)

Time at 1730 psig Pzr Pressure [liME CRITICAL].

Time of Manual Safety Injection [TIME CRITICAL].

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

Manual SI is required by

• 0-ADM-21 1, Emergency and Off-Normal Procedure Usage, 3-EOP-E-0 Reactor Trip or Safety Injection, or annunciator C 3/6 PZR LO PRESS SI TERMINATiNG Evaluator informs the Applicant that another operator will CUE perform subsequent actions. The JPM is complete.

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

Appendix C Page 11 of 12 Form ES-C-I Verification of CompLetion:

Job Performance Measure No. 01041003201 - JPM: Preparation for OMS Operation Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number Attempts:

of Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

2011 NRC Exam (RO) JPM-c 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:

o Unit3isin MODE 3.

• The plant is being shut down to Cold Shutdown.

• 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 N[trogen 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:

• 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 NRCExam(R0)JPM-c 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.

Initial Conditions:

• Unit 3 is in MODE 3.

• The plant is being shut down to Cold Shutdown. V

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

o Attachment 1 OMS Valve Alignment, of 3-NORO4I .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:

• You have been directed to complete 3-NOP-041 .04, Overpressure Mitigating System, Section 4.1.1, starting with Step 4.1.1.7. V 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 V NUREG 1021 Rev 9 Appendix C

Procedure No.

TURKEY POINT UNIT 3 3-NO P-041 M4 NORMAL OPERATING PROCEDURE Revision No.

FP*L SAFETY RELATED 3A 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 3A Michael Coen 10/10/11 REV 3A

1. OF PGS

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 2 of 21 PROCEDURE NO.:

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

SUMMARY

Rev. No. Description 3A AR 1694429, 10110/11, Adrian Gonzalez Editorial correction to include additional sign off of nitrogen bottle and regulator pressures in the Unit Narrative Logs. (Pages 7 and 8, Section 4.1.1 Step 6.A(9) and Section 4.1.1 Step 6.C(8).

3 AR 1644653, 04126111, David Dagitz Revised Attachment I 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 Pl-4-4886Ato Pl-3-4886A, Section 4.1.1 Step 6.C(7).

2 AR 589449, 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, 03124I09, 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, 1211 3I08, 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 2 N bottles in containment.

Added additional guidance for changing N 2 bottles.

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

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 I OMS 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.: PROCEDURE TITLE: PAGE:

3A 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

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 5 Of 21 PROCEDURE NO.:

3-NOP-041.04 TURKEY POINT UNIT 3 NORMAL OPERATION Startup Preparation for OMS Operation 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 Attachment 1, OMS 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 upp of the Pressurizer cubicle and personnel safet is a concern. Use of a previous Attachmen , MS Valve Alignment, shall be recor in the Unit Narrative 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-PMI-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.

IF PORV Block Valve operability has NOT been demonstrated within the last 92 days, THEN ENSURE operability using 3-OSP-206.2, Quarterly lnservice Valve Testing, prior to placing OMS in service.

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 charged Nitrogen bottles that meet SPEC-C-034, Protective Coatings for Service Level 1 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 ttachment 2, MS Backu er Veri ica I n Modes 5 6, and efuele OR Attachment 3, OMS Backup Nitrogen Cylinder Veri ication Prior to Mode 4 from Mode 5.

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

PERFORM the following in Containment:

The nitrogen cylinder isolation valve 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.

MIA 9 IF N 2 pressure is less than 2000 psig as indicated on

/ VJ/ Pl-3-4885A, PCV-3-4885 UPSTREAM PRESSURE INDICATOR, THEN CHANGE the N 2 bottle as follows:

CLOSE 3-40-2443, PORV NITROGEN CYLINDER 1/ ISOLATION.

No vent valve exists in the N 2 cylinder supply header. Pressure will be relieved as the flex hose is disconnected.

(\) I14 , Slowly DISCONNECT flex hose from in-service N bottle.

2 N I\ CONNECT flex hose to new N 2 bottle.

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 7 of 21 PROCEDURE NO.:

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

(continued) r) 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.

ENSURE connection NOT leaking NOTE Maximum design inlet pressure for the regulator is 3000 psig.

CHECK N 2 pressure greater than 2000 psig on Pl-3-4885A.

IF PI-3-4885A reads less than 2000 psig, THEN REPEAT Section 4.1.1 Step 6.A(1) through Section 4.1.1 Step 6.A(7).

Log bottle and regulator pressure in the Unit Narrative Logs.

The operating pressure range for the regulator 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 PI-3-4885B, PCV-3-4885 DOWNSTREAM PRESSURE INDICATOR.

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 8 of 21 PROCEDURE NO.:

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

6. (continued)

NOTE The nitrogen cylinder isolation valve is considered 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 replaced.

C. IF N 2 pressure is less than 2000 psig, as indicated on i \. P I-3-4886A, PCV-3-4886 UPSTREAM PRESSU RE INDICATOR, THEN CHANGE the N 2 bottle as follows:

CLOSE 3-40-2444, PORV NITROGEN CYLINDER (WL/ ISOLATION.

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

A] Slowly DISCONNECT flex hose from in-service N bottle.

2

/J(J CONNECT flex hose to new N 2 bottle.

ENSURE valve label 3-40-2444 moved from nitrogen A

IN cylinder just removed from service to nitrogen cylinder being placed in service.

Nf I

i) 1-Slowly OPEN new in-service cylinder stop valve 3-40-2444, AND ENSURE connection NOT leaking.

Maximum design inlet pressure for the regulator is 3000 psig.

I

\ I CHECK N PI-3-4886A.

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

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 9 of 21 PROCEDURE NO.:

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

(continued)

A1 8) Log bottle and regulator pressure in the Unit Narrative Logs.

The operating pressure range for the regulator is between 2000 and 2400 PSIG with an output pressure range of 90 to 96 PS 1G.

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

Operating Experience has demonstrated 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-212. In-plant Equipment Clearance Orders.

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 following in the Control Room NOTE o OMS Loop Operability Test is required to be completed prior to placing OMS in service if NOT done within the last 31 days.

o 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-OS P-206.2, Quarterly Inservice Valve Testing.

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

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

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

PORV SAT UNSAT PCV-3-456 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:

3A 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:

(I) 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

REVISION NO.: PROCEDURE ]1TLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 12 Of 21 PROCEDURE NO.:

3-NOP-041 .04 TURKEY POINT UNIT 3 4.2 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:

o P1-3-405 (VPB) psig

• P1-3-403 (VPA) psig

• P1-3-402 (VPA) psig

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

• PRIMARY ALIGNED o BACKUP ALIGNED

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

REVISION NO.: PROCEDURE TiTLE: PAGE:

3A 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:

o PCV-.3-455C, BACKUP OMS

• PCV-3-456, PRIMARY OMS.

5. CHECK the following permissive status lights OFF:

o PRIMARY ALIGNED o 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:

3A 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

• 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

1. Technical Specifications

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

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MITIGATING SYSTEM 15 of 21 PROCEDURE NO.:

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

2. Plant Procedures 0-ADM-215, Plant Surveillance Tracking Program

3. Plant Drawings o 5610-T-D-16A, Sheet 1, Pressurizer Pressure Protection and Overpressure Mitigation System o 561 3-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 o 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:

3A 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 COMPONENT DESCRIPTION REMARKS NUMBER PERSONNEL PERFORMING MANIPULATIONS PRINTED NAME INITIALS COMPLETION OF LINEUP DATE LINEUP (MM/DD/YY): TIME LINEUP (HH:MM, 24 HR CLOCK):

COMPLETED: ,i / COMPLETED:  :

LINEUP PRINTED NAME / SIGNATURE:

COMPLETED BY: I REVIEW OF LINEUP LINEUP PRINTED NAME / SIGNATURE: DATE (MM/DD/YY):

REVIEWED BY: /

REVISION NO.: PROCEDURE TITLE: PAGE:

3A OVERPRESSURE MIT(GATING 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 COMPONENT DESCRIPTION NUMBER 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 PRZ PORV BLOCK VALVE OPEN (NOTE 1)

MOV-3-535 PRZ PORV BLOCK VALVE OPEN (NOTE 1)

LOCKED!

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

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

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 ALIGNEDJ VERIFIED COMPONENT DESCRIPTION NUMBER REQUIRED BY BY

In Containment o.n side of Pressurizer cubicle PORV INSTRUMENT AIR 3-40-247 OPEN I SO 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 I SOLATI 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 ISOLATION PORV NITROGEN REGULATOR 3-40-253 OPEN OUTLET PORV TEST CONN ISOLATION CLOSED &

3-40-2322 CAPPED 3-40-2323 PORV TEST CONN ISOLATION CLOSED &

CAPPED

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 COMPONENT DESCRIPTION NUMBER 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 Pl-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 Pl-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 P1-3-4885 B ISOLATION (NOTE 2)

VALVE OPEN

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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)

OMS backup nitrogen cylinders are staged inside Containment as follows:

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

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

Nitrogen bottles stored as follows:

Upright Restrained Caps in place In approved safe areas away from:

Radiators Furnaces Other sources of heat Temperature above 125 degrees°F NITROGEN BOTTLE VERIFiCATION DATE VERIFICATION I (MM/DDIYY): 6t I TIME (HH:MM 24 HR CLOCK):

COMPLETED: I I YX I ) VERIFIED:

. )(y VERIFICATION PRINTED NAME I SIGNATURE:

COMPLETED BY: I

(,

REVIEW OF NITROGEN BOTTLE VERIFICATION VERIFICATION I PRINTED NAME I,SIGNATU I (MM/DDIYY): 4ltç,

REVIEWED BY: I DATE: XC I >YI YX

/ F

REVISION NO.: PROCEDURE TITLE: PAGE:

3A 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 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 #3,AA2400.

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:

o Radiators o Furnaces

• Other sources of heat

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

COMPLETED: I I VERIFIED:

VERIFICATION PRINTED NAME I SIGNATURE:

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

REVIEWED BY: I DATE:

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01041038100 JPM: Start3ARCPin Task

Title:

Mode 3 JPM No: 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:

• Unit 3 is in Mode 3 with Shutdown Banks withdrawn in preparation for a plant startup.

• 3A RCP was shut down twenty minutes ago for maintenance.

o The Unit Supervisor has entered TS 3.4.1.2, LCO Action b for 2 Reactor Coolant Loops in service. (40 minutes remains prior to direction to open Reactor Trip Breakers)

• 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, has been completed through Step 4.1.1.15.

• Electrical Maintenance Supervisor or Component Engineering Supervisor have NOT authorized any higher limits for continued RCP operations.

• Personnel are in Containment.

Initiating Cue:

• You have been directed to start the 3A RCP, beginning with Step 4.1.1.16 of 3-NOP-041 .O1A.

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

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

• 3A RCP started lAW 3-NOP-041 .O1A.

• 3B RCP secured lAW 3-ONOP-041.1 per the foldout page.

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

Appendix C Page 3 of 12 Form ES-C-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 DCS.

6. Acknowledge alarms and place simulator in FREEZE.

7. Provide a copy of 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, marked-up as complete through Step 15.

8. Provide a stopwatch.

9. 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.

10. When ready to begin, then place the Simulator in RUN.

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

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

SAT STEP I U NSAT Applicant obtains a copy of 3-NOP-041 .O1A, 3A Reactor Coolant STANDARD Pump Operations.

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

Provide a stopwatch.

CAUTION

. 3A RCP Oil Lift Pump operation should be limited to 15 minutes during normal RCP starting evolutions. Exception may be taken during off-normal NOTE 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.

SAT START 3A RCP Oil Lift Pump.

UNSAT_____

STEP 2 WHEN 3A RCP Oil Lift Pump has operated for at least two

,J minutes AND prior to starting 3A RCP, THEN CHECK white permissive light ON.

(3-NOP-041.O1A, Step 16)

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 If Reactor Operator informs Unit Supervisor, then acknowledge the report.

COMMENT White permissive light takes about 2 minutes after Lift Oil Pump start.

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

Appendix C Page 5 of 12 NOTE

• All associated RCP instrumentation (Le.. Seal Leak-off Flow. #1 Seal Differential Pressure) should be available and indicating properly far 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 Systerm

• Sudden chances 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 stabilize& When possible, changes to VCT temperature should be gradual, approximately 5F per day.

NOTE CAUIION

• 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 setpointof4sa 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 voltae transient that could be enough to adversely affect Containment Air GaseouslParticulate Monitors, R1I1RI2.

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 If Reactor Operator informs Unit Supervisor, then acknowledge the report.

EVALUATOR NOTES:

The following annunciators will alarm on pump start:

COMMENT

. SU XFMRS PANEL TROUBLE (X 3/4)

. RCP A/B/C MOTOR OVERLOAD (B 1/5) 2011 PTN NRC (RO & SRO) JPM-d NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of II Form ES-C-I SAT STEP 4 WHEN 3A RCP has operated for at least one minute, THEN UNSAT STOP 3A RCP Oil Lift Pump. (3-NOP-041.OIA, Step 19)

STANDARD .

Applicant stops 3A Oil Lift Pump RCP after one minute.

CUE If Reactor Operator informs Unit Supervisor, then acknowledge the report.

EVALUATOR NOTE:

The following annunciator will alarm on 3A RCP start for COMMENT 3B RCP:

. RCP MOTOR/SHAFT HI VIB (F 1/1) [90 seconds after start of 3A RCP]

IF 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or SAT FR-3-1 54B, is NOT within limits of Attachment 3, Unit 3 Reactor UNSAT STEP 5 Coolant Pump Operation Figure, within three minutes of starting 3A RCP, THEN STOP 3A RCP.

(3-NOP-041.O1A, Step 20)

STANDARD Applicant observes 3A RCP #1 seal leak-off flow on FR-3-154A.

CUE EVALUATOR NOTE:

The following annunciator will alarm on 3A RCP start for COMMENT 3B RCP:

. RCP MOTOR/SHAFT HI VIB (F 1/1) [90 seconds after start of 3A RCP]

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

Appendix C Page 7 of 12 Form ES-C-I CAUSES: t RCP high vibration

2. Failed probe or spiking due to electrical transients Fl RCP MOTOPJSHAFT HI VIB DEVICE: SETPOINT: LOCATION:

Bracket mounted probes 15 rn/s on shaft N/A 4 rnils on motor NOTE Local DANGER indication lights on Cabinet 95 in Cable Spreading Room are set at:

. 20 mils on shaft

. 5 mils on meter (motor)

NOTE STEP 6 ALARM CONFIRMATION SAT CHECK RCP Vibration recorder R-3-369.

UNSAT (3-ARP-097.CR.F, F ill)

STANDARD Applicant checks RCP Vibration recorder R-3-369.

If Reactor Operator informs Unit Supervisor, then CUE acknowledge the report.

COMMENT OPERATORACTIONS STEP 7 SAT

1. DISPATCH operator to check vibration indications in Cable UNSAT Spreading Room. (3-ARP-097.CR.F, F Ill)

STANDARD Applicant directs Field Supervisor or Unit 3 Turbine Operator to check vibration indications in Cable Spreading Room.

CUE Booth Operator acknowledges direction.

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

Appendix C Page 8 of 11 Form ES-C-I OPERATOR ACTIONS STEP 8 SAT

2. IF vibration is above alarm setpoint, THEN GO TO 3-ONOP-041.1, UNSAT Reactor Coolant Pump Off-Normal. (3-ARP-097.CR.F, F 1/1)

STANDARD Applicant enters 3-ONOP-041.1, Reactor Coolant Pump Off-Normal.

CUE If Reactor Operator informs Unit Supervisor, then acknowledge the report.

COMMENT CAUTION Containment entries shall NOT be performed when there are indications of an RCP seal package failure until the reactor is shutdown and RCS pressure/temperature is reduced to minimize leakage.

NOTES NOTE I

• Foldout Page is required to be monitored throughout this procedure. I I

• Off-norma? RCP conditions that require shutdown of an RCP shall be verified by I I cross-checking all RCP parameters. I I

• If either 3B or 3C RCP is stopped by the performance of this procedure, then the I I associated RCS loop pressurizer spray valve should be closed to prevent backflow I through the valve.

STEP 9 Foldout Page is required to be monitored throughout this SAT procedure. UNSAT (3-ONOP-041.1, Page 7)

STANDARD Applicant monitors Foldout Page.

CUE If Reactor Operator informs Unit Supervisor, then acknowledge the report.

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

Appendix C Page 9 of 11 Form ES-C-17 FOLDOUT PAGE FOR PROCEDURE 3-ONOP-04I.l SAT UNSAT

2. REP STOPPING CRITERIA IF any of the following RCP limits are reached. THEN manually trip tie reactor and verify reactor trip using the EOP network AND then stop the affected RCP, and close PCV-3-455A, PZR Spray Valve Loop C, or PCV 455B, PZR Spray Valve Loop B, if applicable.

. RCP number one seal P - LESS THAN 200 paid.

STEP 10 . RCP number one seal leakoff temperatures on DCS - GREATER THAN OR EQUAL TO 235F.

s.J . RCP pump bearing temperature on DCS - GREATER THAN OR EQUAL TO 225F.

. RCP motor bearing temperature on DCS - GREATER THAN OR EQUAL TO 195F.

. RCP stator winding temperature on DCS - GREATER THAN OR EQUAL TO 248F.

Note exception in Foldout Page Item 4.

. Motor frame vibration. R-3-369 (Points 1 2, 5, 6, 9, 10)- GREATER THAN OR EQUAL TO 5 MILS.

Note exception in Foldout Page Item 4.

. RCP shaft vibration, R-3-369 (Points 3,4,7, 8, 11, 12)- GREATER THAN OR EQUAL TO 20 MILS.

Note exception in Foldout Pege Item 4.

(3-ONOP-041 .1, Foldout Page)

Applicant verifies 3B RCP has shaft vibration, R-3-369 (Points 3,4,7,8, 11, 12)-GREATER THAN OR EQUAL TO 20 MILS and performs the following:

STANDARD 1. Manually trips the Reactor

2. Verifies Reactor Trip using the 3-EOP-E-0

3. Stops 3B RCP CRITICAL STEP

4. Closes PCV-3-455B, PZR Spray Valve Loop B After 3B RCP is tripped and PCV-3-455B is closed, then the TERMINATING CUE Evaluator informs Applicant that another operator will complete the remaining steps of this procedure. This completes the JPM.

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

Appendix C Page 10 of 11 Form ES-C-I Verification of Completion; Job Performance Measure No. 01041038101 - JPM: Start 3A RCP in Mode 3 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:

• Unit 3 is in Mode 3 with Shutdown Banks withdrawn in preparation for a plant startup.

• 3A RCP was shut down twenty minutes ago for maintenance.

• The Unit Supervisor has entered TS 3.4.1.2, LCO Action b for 2 Reactor Coolant Loops in service. (40 minutes remains prior to direction to open Reactor Trip Breakers)

• 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, has been completed through Step 4.1.1.15.

• Electrical Maintenance Supervisor or Component Engineering Supervisor have NOT authorized any higher limits for continued RCP operations.

• Personnel are in Containment.

Initiating Cue:

• You have been directed to start the 3A RCP, beginning with Step 4.1.1.16 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

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:

• Unit 3 is in Mode 3 with Shutdown Banks withdrawn in preparation for a plant startup.

• 3A RCP was shut down twenty minutes ago for maintenance.

• The Unit Supervisor has entered TS 3.4.1.2, LCO Action b for 2 Reactor Coolant Loops in service. (40 minutes remains prior to direction to open Reactor Trip Breakers)

• 3-NOP-041 .O1A, 3A Reactor Coolant Pump Operations, has been completed through Step 4.1.1.15.

• Electrical Maintenance Supervisor or Component Engineering Supervisor have NOT authorized any higher limits for continued RCP operations.

• Personnel are in Containment.

Initiating Cue:

• You have been directed to start the 3A RCP, beginning with Step 4.1.1.16 of 3-NOP-041 .O1A.

Acknowledge to the examiner when you are ready to begin.

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

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

Procedure No.

TURKEY POINT UNIT 3 3-NOP-041 .OIA Revision No.

NORMAL OPERATING PROCEDURE I

FPL SAFETY RELATED Effective Date 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-041.OIA SYS STATUS COMPLETED 1 Brian Stamp 08/02/10 REV

1. OF PGS

REVISION NO.: PROCEDURE TITLE: PAGE:

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

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

SUMMARY

Rev. No. Description 1 PCR 10-1222, 08102110, David Dagitz Removed unnecessary Caution about preceding Steps 4.1.1.10 and 5.1.4.

REVISION NO.: PROCEDURE TITLE: PAGE:

I 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 PRECAUTIONS AND 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 1 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: PAGE:

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 PRECAU11ONS 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 2fl 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.: PROCEDURE TITLE: PAGE:

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

3-NOP-041 O1A TURKEY POINT UNIT 3 2.2 Limitations (continued)

6. If Reactor Coolant System (RCS) is solid, Jth 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, two 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 one 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.

• Stator winding temperature 248° F.

• Pump bearing temperature 225°F.

• #1 seal leak-off temperature 235°F.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 6 of 36 PROCEDURE NO:

3-NOP-041 O1A TURKEY POINT UNIT 3 2.2 Limitations (continued)

8. (continued)

• #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.

o #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.

• #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.

• Seal injection water temperature 130°F as indicated on Tl-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 NO.; PROCEDURE TITLE; PAGE; 1

3A REACTOR COOLANT PUMP OPERATIONS 7 of 36 PROCEDURE NO.;

3-NOP-041 CIA TURKEY POINT UNIT 3 NORMAL OPERATIONS Startup Starting 3A Reactor Coolant Pump Section 4.1.1 Step 1 through Section 4.1.1 Step 15 may be performed in any order.

fHECK the following systems available or in operation as necessary 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 RCP operation:

3A4160V Bus 9

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

REVISION NO.: PROCEDURE TITLE: 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 Reactor Coolant Pump (continued)

IF starting the first RCP, THEN CHECK the following conditions have

/11/4 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.

fJ/,42 I

Reported or observed activity which may have diluted the water in the RCS.

/1.,)fj1( RCS Sample indicates a loop has been diluted.

IF a RCS loop or portion thereof was diluted, THEN GO TO IVff O-ONOP-041 .9, Potential Dilution of Reactor Coolant Loop(s).

Starting 3A RCP may cause 3A Emergency Diesel 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 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 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.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 9 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 4.1.1 Starting 3A Reactor Cooant Pump (continued)

IF thermal barrier differential pressure is less than inches of water, as indicated on P1-3-i 31A, A RCP THERMAL BARRIER DIP, THEN:

A minimum of 6 gpm required for RCP Seal 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 RCP CCW flows and SIG temperatures, re-verification is N/A 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:

FI-3-630, RCP A THERMAL BARRIER CCW RETURN FLOW INDICATOR, indicates 21 to 30 gpm.

FI-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 163 gpm or, when on RHR, 136 to 145 gpm.

IF RCS cold leg temperature is less than or equal to 275°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.

CHECK 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-i 54B, within limits shown in Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 10 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 4.1.1 Starting 3A Reactor Coolant Pump (continued)

12. (continued)

IF #1 seal leak-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 seal leak-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 350 psig for solid plant condition.

IF P1-3-156, A RCP#1 SEALAP, indicates less than 225 psid across

1. 1 seal, THEN ENSURE RCS pressure greater than 325 psig.

IF Annunciator G 2/1 RCP A STANDPIPE HI LEVEL, is in ALARM, THEN GO TO 3-ONOP-041.1, Reactor Coolant Pump Off-Normal.

IF Annunciator G 3/1 RCP A STAN DPIPE LO LEVEL, is in ALARM, THEN FILL the standpipe per Section 5.7.

CAUTION

• 3A RCP Oil Lift Pump operation should 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 Ieast minutes ANJD 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-041.01A TURKEYPOINTUNIT3 4.1.1 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.

o 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.

o 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 th of the following:

Starting current as indicated on 3A RCP motor ammeter o RCS loop flow rate rise as indicated on Fl-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 .O1A 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-3-1 54A or FR-3-1 54B, 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 R11/R12 sample skid does NOT return, THEN REQUEST l&C start sample pumps in MANUAL MODE locally at skid.

22. ENSURE VCT pressure is controlled to maintain one of the following:

o In the normal range of 16 and 25 psig.

o As required to maintain RCP seal leak-off and as specified by Chemistry.

REVISION NO.; PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 13 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.1.1 Starting 3A Reactor Coolant Pump (continued)

23. WHEN 3A RCP has operated for more than 10 minutes, THEN CHECK conditions on DCS 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 1 - RCP Startup Temperature Ranges STABLE MAX NORM -

PARAMETER °F YES NO

1. 1 Seal Leak-off 235 100-1 90 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 FI-3-130 between 6 and 13 gpm.

NOTE RCP Vibration indicated on Recorder 369 and on DCS.

B. CHECK RCP shaft vibration less than 15 mils.

C. CHECK RCP motor vibration less than 4 mils.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 14 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 4.2 Operation None 4.3 Shutdown 4.3.1 Stopping 3A Reactor Coolant Pump

1. STOP3ARCP.

CAUTION CCW to 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 half hour or until RCS temperature is less than 150°F after stopping the RCP.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 15 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 5.0 INFREQUENT OPERATIONS 51 Starting 3A RCP Motor With Pump Uncoupled

1. CHECK 3A RCP motor UNCOUPLED.

2. CHECK the following plant electrical systems energized to support RCP motor operation:

a 3A4160V Bus a 3AMCC a LP-34

3. ENSURE 3A RCP switch and breaker alignments per:

a Attachment 1, 3A Reactor Coolant Pump And Oil Lift Pump Switch Alignment a Attachment 2, 3A Reactor Coolant Pump And Oil Lift Pump Breaker Alignment NOTE CCW is NOT required for rotation check of RCP uncoupled motor.

4. IF CCW is required, THEN CHECK the following CCW flows:

a FI-3-628, RCP A LOWER BEARING CCW RETURN FLOW INDICATOR, indicates 5 to 10 gpm a FIC-3-629, RCP A CCW RETURN FLOW, indicates 150 to 163 gpm or 138 to 145 gpm when on RHR

5. START 3A RCP Oil Lift Pump.

6. CHECK white permissive light ON.

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 16 of 36 PROCEDURE NO.:

3NOP-041 .O1A TURKEY POINT UNIT 3 5.1 Starting 3A RCP Motor With Pump Uncoupled (continued)

NOTE e Current reading may be noticeably lower than normal with motor uncoupled.

. Motor run time for RCP uncoupled motor rotation check should be less than 15 seconds.

7. WHEN 3A RCP Oil Lift Pump has run for at least minutes, THEN START 3A RCP motor while monitoring starting current.

8. IF 3A RCP motor starting current is greater than 943 amps after 25 seconds, THEN STOP 3A RCP motor.

9. WHEN 3A RCP motor has operated for at least one minute, THEN STOP 3A RCP Oil Lift Pump.

10. WHEN 3A RCP motor has operated for more than 10 minutes, THEN CHECK conditions stabilized less than maximum values listed below:

Table 2 - RCP Temperature Channel Readings RECORDER PT MAX NORM STABLE PARAMETER A B C °F °F YES NO Upper Thrust Bearing 7 8 9 190 150 LowerThrust Bearing 10 11 12 190 150 UpperGuide Bearing 13 14 15 190 150 Lower Guide Bearing 16 17 18 190 125 Stator Winding 20 21 22 248 200 NOTE RCP Vibration is indicated on recorder 369 and on DCS.

A. CHECK RCP shaft vibration less than 15 mils.

B. CHECK RCP motor vibration less than 4 mils.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 17 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 5.2 Stopping Uncoupled 3A Reactor Coolant Pump Motor

1. STOP 3A RCP motor.

2. IF CCWwas supplied to motor bearing oil cooler during the uncoupled run, THEN MAINTAIN COW to motor bearing oil cooler for at least one half hour after stopping motor.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 18 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 5.3 Adlustment of 3A RCP Seal Injection Flow CAUTION 3-ONOP-041.1, Reactor Coolant Pump Off-Normal, should be used to address loss of seal flow with temperature greater than 170°F.

1. CHECK 3A RCP seal injection flow outside normal range of 6 to 13 gpm as indicated locally or on DCS.

2. NOTIFY Shift Manager of performance of this Section.

NOTE e Performance of this Section requires coordination between the RCO and SNPO to minimize the time seal flow is outside normal range on 3A RCP.

During performance of subsequent steps, Annunciator A 6/5, RCP LABYRINTH SEAL zIP, is an expected alarm.

o Seal injection flow adjustments need to be made in small increments to prevent cocking #1 seal and ensuring seal injection flow is responding on local and DCS instrumentation.

3. ENSURE HCV-3-121, CHARGING FLOWTO REGEN HX, is full OPEN.

NOTE If minimum seal injection flow of 6 gpm can NOT be obtained, the throttle valve should be full OPEN.

4. While the 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.

5. IF Annunciator A 6/6, SEAL WATER INJ FILTER HI AP, is in ALARM, THEN PLACE Standby Seal Injection Filter in service using 3-OP-047, CVCS - Charging and Letdown.

6. IF actions to restore seal injection flow to greater than 6 gpm are NOT successful, THEN GO TO 3-ONOP-041.1, Reactor Coolant Pump Off-Normal.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 19 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 5.3 Adjustment of 3A RCP Seal Injection Flow (continued)

NOTE To minimize potential operating problems, HCV-3-121 should be full OPEN or as close to full OPEN as possible while Annunciator A 6/5, RCP LABYRINTH SEAL LO P, is maintained CLEAR.

7. IF Annunciator A 6/5, RCP LABYRINTH SEAL LO AP, is in ALARM, THEN ADJUST HCV-3-121 CLOSED to clear alarm.

8. IF HCV-3-121, CHARGING FLOW TO REGEN HX, is adjusted to clear Annunciator A 6/5, RCP LABYRINTH SEAL LO z\P, THEN DIRECT SNPO locally ADJUST 3-297A, 3A RCP SEAL WATER SUPPLY, to obtain 6 to 13 gpm.

9. CHECK DCS and local Seal Injection flow indication AGREE.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 20 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 5.4 Resetting Unresponsive 3A RCP Partial Discharge Monitor IF 3A RCP partial discharge monitor is unresponsive, THEN:

A. ENSURE flux map detectors withdrawn to drive unit.

B. OPEN 3C MCC breaker 30768, LIGHTING XFMR NO. 37 CNTMT ELEVATION 14 FT.

C. CLOSE 3C MCC breaker 30768.

D. REQUEST Predictive Maintenance Department check proper operation of 3A RCP partial discharge monitor.

E. ENSURE flux map detectors restored to desired position.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 21 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 5.5 Response to High/Low 3A RCP #1 Seal Leak-off Flow 5.5.1 Response to Low 3A RCP #1 Seal Leak-off Flow

1. IF 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, is less than the lower limit of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure, THEN PERFORM one of the following:

A. IF Hand-Rotating 3A RCP Rotating Element, THEN:

(1) OBTAIN Engineering approval for this option:

Engineering Representative Date (2) REQUEST Maintenance hand-rotate 3A RCP rotating element.

(3) WHEN Maintenance is ready to hand-rotate 3A RCP rotating element, THEN:

a. START 3A RCP Oil Lift Pump.

b. CHECK white permissive light ON.

(4) WHEN hand-rotation of 3A RCP rotating element complete, THEN DETERMINE if 3A RCP #1 seal leak-off flow, as indicated on FR-3-1 54A or FR-3-1 54B, within limits of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure (5) IF 3A RCP #1 seal leak-off flow is within the limits of Attachment 3, THEN RETURN TO Section 4.1.1 Step 12.

(6) IF 3A RCP #1 seal leak-off flow is NOT within the limits of Attachment 3, THEN CONSULT Engineering for another option.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 22 of 36 PROCEDURE NO.:

3-NOP-041.O1A TURKEY POINT UNIT 3 5.5.1 Response to Low 3A RCP #1 Seal Leak-off Flow (continued)

(continued)

B. IF Cycling CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION, THEN:

(1) OBTAIN Engineering approval for this option:

Engineering Representative Date CAUTION CV-3-303A shall remain closed for less than one minute and may be cycled a maximum of three times.

(2) CLOSE CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION.

(3) OPEN CV-3-303A.

(4) DETERMINE if 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, within limits of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure.

(5) IF 3A RCP #1 seal leak-off flow is within the limits of Attachment 3, THEN RETURN TO Section 4.1.1 Step 12.

(6) IF 3A RCP #1 seal leak-off flow is NOT within the limits of Attachment 3, THEN REPEAT Section 5.5.1 Step 1.B(2) through Section 5.5.1 Step 1.B(4) up tomore times.

(7) IF 3A RCP #1 seal leak-off flow is NOT within the limits of Attachment 3, THEN CONSULT Engineering for another option.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 23 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 551 Response to Low 3A RCP #1 Seal Leak-off Flow (continued)

1. (continued)

C. IF visually verifying 3A RCP #1 Seal Leakoff, THEN:

(1) OBTAIN Engineering approval for this option:

Engineering Representative Date (2) CLOSE CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION.

NOTE 3A RCP #3 Seal Leak-off line indication found at containment 14-foot elevation trough.

(3) DETERMINE if flow through 3A RCP #3 Seal Leak-off line within prescribed limits of greater than lower limit of Attachment 3, Unit 3 Reactor Coolant Pump Operation Figure, and less than 5 gpm.

(4) OPEN CV-3-303A.

(5) IF 3A RCP #3 seal leak-off flow is within prescribed limits, THEN RETURN TO Section 4.1.1 Step 12.

(6) IF 3A RCP #3 Seal Leak-off flow is NOT within prescribed limits, THEN CONSULT Engineering for another option.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 24 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 5.5.2 Response to High 3A RCP #1 Seal Leak-off Flow

1. IF 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-1 54B, is greater than the upper limit of Attachment 3, Unit 3 Reactor Coolant Pump Operation FigUre, THEN PERFORM one of the following:

A. IF 3A RCP #1 Seal Leak-off is less than 5 gpm, THEN:

(1) OBTAIN Engineering approval to allow continued operation outside the limits .of Attachment 3 and less than 5 gpm:

Engineering Representative Date (2) DETERMINE if 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, within the prescribed limits.

(3) IF 3A RCP #1 seal leak-off flow is within the prescribed limits, THEN RETURN TO Section 4.1.1 Step 12.

B. IF Hand-Rotating 3A RCP Rotating Element, THEN:

(1) OBTAIN Engineering approval for this option:

Engineering Representative Date (2) REQUEST Maintenance hand-rotate 3A RCP rotating element.

(3) WHEN Maintenance is ready to hand-rotate 3A RCP rotating element, THEN:

a. START 3A RCP Oil Lift Pump.

b. CHECK white permissive light ON (4) WHEN hand-rotation of 3A RCP rotating element complete, THEN DETERMINE if 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, is less than the upper limit of Attachment 3.

(5) IF 3A RCP #1 seal leak-off flow is less than the upper limit of Attachment 3, THEN RETURN TO Section 4.1 .1 Step 12.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 25 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 5.5.2 Response to High 3A RCP #1 Seal Leak-off Flow (continued)

B. (continued)

(6) IF 3A RCP #1 seal leak-off flow is greater than the upper limit of Attachment 3, THEN CONSULT Engineering for another option.

C. IF Cycling CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION, THEN:

(1) OBTAIN Engineering approval for this option:

Engineering Representative Date CAUTION CV-3-303A shall remain closed for less than minute and may be cycled a maximum of three times.

(2) CLOSE CV-3-303A, 3A RCP #1 SEAL LEAKOFF ISOLATION.

(3) OPEN CV-3-303A.

(4) DETERMINE if 3A RCP #1 seal leak-off flow, as indicated on FR-3-154A or FR-3-154B, is less than the upper limit of Attachment 3.

(5) IF 3A RCP #1 seal leak-off flow is less than the upper limit of Attachment 3, THEN RETURN TO Section 4.1.1 Step 12.

(6) IF 3A RCP #1 seal leak-off flow is greater than the upper limit of Attachment 3, THEN REPEAT Section 5.5.2 Step 1 .C(2) through Section 5.5.2 Step 1 .C(4) up to more times.

(7) IF 3A RCP #1 seal leak-off flow is greater than the upper limit of Attachment 3, THEN CONSULT Engineering for another option.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 26 of 36 PROCEDURE NO.:

3.-NOP-041 .OIA TURKEY POINT UNIT 3 5.6 Steam Generator Secondary Water Temperature Measurement NOTE Methods NOT used may be NIA, or NIA at Shift Manager discretion for subsequent starts.

1. CHECK Steam Generator secondary water temperature is less than 10°F above RCS temperature in 3A, 3B, and 30 Steam Generators by one of the following methods:

A. Steam Generator blowdown temperature as indicated by the following temperature indicators:

• TI-3-.6562A for 3A Steam Generator

. Tl-3-6562B for 3B Steam Generator

. Tl-3-6562C for 3C Steam Generator NOTE Pyrometer reading may be taken at RCP cubicle. Insulation cover for hand hole is a snap on the unit.

B. Contact pyrometer on uninsulated surface of each steam generator above steam generator tube sheet.

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 27 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 5.6 Steam Generator Secondary Water Temperature Measurement (continued)

(continued)

C. Temperature measurement of representative secondary water sample obtained from çn of the following for each Steam Generator:

• 3A Steam Generator SGB-3-044, 3A S/G TEST CONN ISOLATION SGB-3-047, 3A S/G BLDN HDR TEST CONN SO [AT! ON

• 3B Steam Generator SGB-3-045, 3B S/G TEST CONN ISOLATION SGB-3-048, 3B S/G BLDN HDR TEST CONN ISOLATION

• 3C Steam Generator SGB.-3-046, 30 S/G TEST CONN ISOLATION SGB-.3-049, 3C S/G B[DN HDR TEST CONN ISO [AT! ON D. IF Steam Generator Wet Lay Up (SGWL) is in service per 3-OP-079, THEN OBTAIN temperature measurement of representative secondary water sample from the following:

• SGWL-3-073, TEST CONN BLOWDOWN HDR TO AND FROM 3A SGWL PP, for 3A S/G

• SGWL-3-072, TEST CONN BLOWDOWN HDR TO AND FROM 3B SGWL PP, for 3B S/G

• SGWL-3-071, TEST CONN BLOWDOWN HDR TO AND FROM 3C SGWL PP, for 30 S/G

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 28 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 5.7 Filling 3A RCP Standpipe

1. OPEN CV-3.-519A, PWTO CNTMT ISOLATION VALVE.

2. OPEN CV-3-522A, A RCP STAN DPIPE FILL VALVE, as required to clear low level alarm.

3. WHEN standpipe low level alarm is CLEAR, THEN:

A. CLOSE CV-3-522A, A RCP STAN DPIPE FILL VALVE.

B. CLOSE CV-3-519A, PWTO CNTMT ISOLATION VALVE, and RETURN control switch to AUTO.

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 29 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 6.0 RECORDS I. 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.

3. Completed copies of the below listed Attachments shall be retained in the SHIFT MANAGER FILE until the next performance of the

Attachment:

o Attachment 1, 3A Reactor Coolant Pump And Oil Lift Pump Switch Alignment

• Attachment 2, 3A Reactor Coolant Pump And Oil Lift Pump Breaker Alignment

7.0 REFERENCES

AND COMMITMENTS 7.1 References 7.1.1 Implementing References

1. 3-ONOP-041 .1, Reactor Coolant Pump Off-Normal

2. O-ONOP-041.9, Potential Dilution of Reactor Coolant Loop(s)

3. 3-OP-041 .4, Overpressure Mitigating System

4. 3-OP-041 .8, Filling and Venting the Reactor Coolant System

5. 3-OP-047, CVCS Charging and Letdown

6. 3-OP-079, Steam Generator Wet Lay up System 7.1.2 Developmental References

1. Technical Specifications A. Section 3/4.4, Reactor Coolant System

2. FSAR A. Section 4.2.2, Reactor Coolant System Components

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 30 of 36 PROCEDURE NO.:

3-NOP-04l .OIA TURKEY POINT UNIT 3 7.1.2 Developmental References (continued)

3. Operating Diagrams A. 561 3-M-3041, Sheet 1, Reactor Coolant System Loops B. 5613-M-3041, Sheet 3, Reactor Coolant System Reactor Coolant Pumps C. 561 3-M3047, Sheet 3, Chemical and Volume Control System Seal Water Injection to RCP

4. Operating Procedures A. 0-ADM215, Plant Surveillance Tracking Program B. 3-OP-013, Instrument Air System C. 3-OP-020, Primary Water System D. 3-NOP-030, Component Cooling Water System E. 0-NOP-046, Chemical and Volume Control System F. 3-OP-061 .3, Reactor Coolant Drain Tank G. 0-OSP-200.1, Schedule of Plant Checks and Surveillances

5. Vendor/Technical Manual A. Westinghouse Technical Manual - Model VilOl-Bi, Controlled Leakage Seal RCP

6. Miscellaneous Documents A. PC/M-83-1 54, Alternate Shutdown Capability for Appendix R Modifications Unit 3 B. PCIM-89-574, 3C RCP Motor Refurbishment/Upgrade C. PC/M-87-258, Loadcenter 3H and Repowering of MCC-D (3D)

D. NCR-N-92-0194, 4B EDG Trip E. Westinghouse Letter 92-TP-TD-5513, dated December 4, 1992

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 31 of 36 PROCEDURE NO.:

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

6. (continued)

F. Special Report L-93-28, Overpressure Mitigating Systems, PORV Actuation G. PC/M-OO-027, Cold Overpressure Mitigation System (COMS)

Setpoint Change H. Evaluation PTN-ENG-SEMS-05-003, Flex Hose Fill Line I. CR-2004-12236, Prolonged RCP Oil Lift Pump Operation Results in Inability to Achieve RCP Prestart Pressure J. CR-2006-34689, RCP Started with VCT Pressure High.

K. PC/M-04-112, Emergency Response Data Acquisition and Display System (ERDADS) Replacement L. MOS Daily Report, dated 11/25/87, from G. M. Smith Item G (CTRAC-87-1 546-34)

M. CEADP-85-9, RCP Motor Oil Seals (CTRAC-87-0014-34)

N. JPN-PTN-SENP-95-026, CCW Flow Balance and Post Accident Alignment Requirements to Support Current and Uprated Conditions (LER 250/95-006)

0. INPO SOER 94-2, Boron Dilution Events in PWRs 7.1.3 Management Directives None 7.2 Commitments None

REVISION NO.: PROCEDURE TITLE: PAGE:

I 3A REACTOR COOLANT PUMP OPERATIONS 32 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 ATTACHMENT I 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP SWITCH ALIGNMENT (Page 1 of 2)

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

COMPLETED: / / COMPLETED:

LINEUP PRINTED NAME! SIGNATURE:

COMPLETED BY:

REVIEW OF LINEUP LINEUP PRINTED NAME / SIGNATURE: DATE (MMIDD/YY):

REVIEWED BY: / /

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATiONS 33 of 36 PROCEDURE NO.:

3-NOP-041 .OIA TURKEY POINT UNIT 3 ATTACHMENT I 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP SWITCH ALIGNMENT (Page 2 of 2)

POSITION ALIGNED VEFIED COMPONENT NOUN DESCRIPTION Control Room Switch Alignment (VPA)

MID AFTER 3A REACTOR COOLANT PUMP MID AFTER 3A RCP OIL LIFT PUMP

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 34 of 36 PROCEDURE NO.:

3-NO P-041 .OIA TURKEY POINT UNIT 3 ATTACHMENT 2 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP BREAKER ALIGNMENT (Page 1 of 2)

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: j COMPLETED:

LINEUP PRINTED NAME! SIGNATURE:

COMPLETED BY: /

REVIEW OF LINEUP LINEUP PRINTED NAME! SIGNATURE: DATE: (MM!DD!YY):

REVIEWED BY: / /

REVISION NO.: PROCEDURE TITLE: PAGE:

1 3A REACTOR COOLANT PUMP OPERATIONS 35 of 36 PROCEDURE NO.:

3-NOP-041 .O1A TURKEY POINT UNIT 3 ATTACHMENT 2 3A REACTOR COOLANT PUMP AND OIL LIFT PUMP BREAKER ALIGNMENT (Page 2 of 2)

COMPONENT POSITION ALIGNED VERIFIED NUMBER COMPONENT DESCRIPTION REQUIRED BY BY 30554 3A RCP OIL LIFT PUMP ON LP-34 LP34-5 3A RCP MOTOR HEATER ON 3A 4160 V Switchgear Room 3AAO1 3A REACTOR COOLANT PUMP RACKED IN

REVISION NO.: PROCEDURE TITLE: PAGE:

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

3-NOP-041.O1A TURKEY POINT UNIT 3 ATTACHMENT 3 UNIT 3 REACTOR COOLANT PUMP OPERATION FIGURE (Page 1 of 1)

NO I SEAL LEAK RATE (GPM) 2500 2250 NO. I SEAL DIFFERENTIAL PRESSURE P.S.!.

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:

013 A4.01 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.

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

Initial Conditions:

o The Unit 3 Reactor has tripped due to a LOCA inside of Containment.

• Safety Injection has occurred.

o Containment Isolation Phase A has occurred.

o The rest of the crew is continuing after Step 5 of 3-EOP-E-0, Reactor Trip or Safety Injection.

Initiating Cue:

• You have been directed to complete 3-EOP-E-0, Attachment 3, starting at Step 15.

2011 NRC Exam (RO) 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-EQ P-E-O, Reactor Trip or Safety Injection, Attachment 3 General

References:

• 3-EOP-E-0, Reactor Trip or Safety Injection, Attachment 3 Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam(R0)JPM-e NUREG 1021 Rev 9 Appendix C

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

1. Reset to IC 195 or equivalent IC.

2. Place simulator in RUN.

3. Open Lesson JPM-0106701 3201 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-0, 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.

8. When ready to begin, then place simulator in RUN.

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

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

SAT STEP I UNSAT 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 I 5.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) JPM-e NtJREG 1021 Rev 9 Appendix C

Appendix C Page 5 of II Form ES-C-I IF containment spray NOT initiated, THEN manually initiate SAT STEP 3 containment spray.

UNSAT (3-EOP-E-O, Attachment 3, Step 15 RNO a.l)

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) 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 pushbuttons.

CUE EVALUATOR NOTE:

COMMENT Phase B pushbuttons are disabled; therefore, depressing the pushbuttons is not critical.

2011 NRCExam(RO)JPMe NUREG 1021 Rev9AppendixC

Appendix C Page 7 of II Form ES-C-I IF any Containment Isolation Phase B valve did NOT close, SAT THEN manually or locally isolate affected containment STEP 6 UNSAT penetration.

I (3-EOP-E-0, Attachment 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:

• RCP CLG WIR 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) 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 a5)

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 UNSA1 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) 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 EM ER. AIR SUPPLY FAN SF-i B (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 I

(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 Evaluator informs Applicant that another operator will CUE complete Attachment 3. This completes the JPM.

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

Appendix C Page 10 of II Form ES-C-I VerificatiOn Of COrn plOtion:

Job Performance Measure 01067013201 JPM: Manually Initiate Containment Spray and No. Control Room Ventilation Isolation 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-e 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 3 Reactor has tripped due to a LOCA inside of Containment.

• Safety Injection has occurred.

o Containment Isolation Phase A has occurred.

o The rest of the crew is continuing after Step 5 of 3-EOP-E-O, Reactor Trip or Safety Injection.

Initiating Cue:

o You have been directed to complete 3-EOP-E-O, 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) 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 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.

• The rest of the crew is continuing after Step 5 of 3-EQ P-E-O, Reactor Trip or Safety Injection.

Initiating Cue:

• You have been directed to complete 3-EQP-E-O, 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:

I 24 I 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 1 of 7)

PROMPT ACTION VERIFICATIONS eck The Load Centers Associated With Close the Load Center supply breakers.

The Energized 4 Ky Buses ENERGIZED LC LC 3C LC 3DLC LC Check If Main Steamlines Should Be Isolated 6i,eck 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 S/G pressure 614 psig Q, low Tavg 543 F OR

• Hi-Hi containment pressure 20 PSIG

_iify main steam isolation and bypass c. Push manual Steamline Isolation push valves CLOSED

- buttons on VPB OR manually close valves.

_erify Feedwater Isolation lace main feedwater pump switches in STOP eedwater control valves 4 CLOSED b. Manually close valves.

&eedwater bypass valves CLOSED c. Manually close valves.

Close feedwater isolation MOVs d. Locally close valves.

1erify standby feedwater pumps OFF e. I.E standby feedwater is aligned to Unit 3, THEN stop standby feedwater pump(s).

W97/In/cls/nw/mr

STEP á 6N1ExPEcTED RESPONSE I I RESPONSE NOT OBTAINED I ATTACHMENT 3 (Page 2 of 7)

PROMPT ACTION VERIFICATIONS Verify Proper ICW System Operation

,ferify 1GW pumps AT LEAST TWO

- a. Start ICW pump(s) to establish at least RUNNING two running.

ferify 1GW to TPCW Heat Exchanger b. Manually close valve(s). E valve(s) can ISOLATED QI 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 1GW headers TIED TOGETHER

- c. IF both 1GW headers are intact, THEN direct operator to tie headers together.

_Ierify Proper CCW System Operation fCW Heat Exchangers THREE IN a. Perform the following:

&./ SERVICE

1) Start or stop GGW pumps as necessary to establish ONLY ONE RUNNING CCW PUMP.

2) Verify Emergency Containment Coolers ONLY iWO RUNNING

3) Go to Step 5c.

GW pumps ONLY TWO RUNNING

- b. Start or stop CCW pumps as necessary to establish ONLY TWO RUNNING CCW PUMPS.

headers TIED TOGETHER

- c. E 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 NOT MOV-3-626 OPEN actuated AND GCW radiation levels are normal, AND RCP number one seal leak-off temperature is less than 235°F, THEN manually open MOV-3-626. IE MOV-3-626 can JQI be manually opened, THEN direct operator to open MOV-3-626 locally.

W9711n/cis/nw/mr

STEP ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATrACHMENT 3 (Page 3 of 7)

PROMPT ACTION VERIFICATIONS Verify Containment Cooling

_&heck emergency containment coolers - a. Manually start or stop emergency ONLY TWO RUNNING containment coolers to establish ONLY TWO RUNNING.

_Verify 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).

ferify SI Flow pressure LESS THAN 1600 PSIG

- a. GotoStep9.

- [2000 PSIG]

,gh-head SI pump flow indicator b. Manually start pumps Q align valves to CHECK FOR FLOW establish an injection flowpath.

RCS pressure LESS THAN 250 PSIG

- c. GotoStep9.

/ [650 PSIG]

pump flow indicator - d. Manually start pumps align valves to CHECK FOR FLOW establish an injection flowpath.

W97/In/clslnw/mr

STEP ACTIONIEXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page 4 of 7)

PROMPT ACTION VERIFICATIONS ReaIign SI System Verify Unit 3 high-head SI pumps TWO

- a. Perform the following:

RUNNING

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.

top both Unit 4 high-head SI pumps JQ 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. E any Containment Isolation Phase A valve is Q] 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 W9711ri/clslnwlmr

STEP ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page 5of 7)

PROMPT ACTION VERIFICATIONS

• Reestablish RCP Cooling Check RCPs AT LEAST ONE

a. Go to Step 15.

RUNNING t 0

b. Open CCW to normal containment cooler b. Stop all RCP5 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 QI Required

a. Containment pressure HAS REMAINED

- a. Perform the following:

LESS THAN 20 PSIG

1) if containment spray I 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) if any Containment Isolation Phase B valve did QI close, THEN manually or locally isolate affected containment penetration.

5) Stop all RCPs.

W97/n/ds/nw/mr

STEP ACTIONIEXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page6of 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 NOTE I I I Hydrogen Monitors should be in service within 30 minutes of a valid SI signal. They should I be available in a timely manner to support decision-making related to hydrogen generation in containment I I 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 Q] running.

W97/In/cls/nw/mr

PFáedureNo.: Procedure

Title:

Page:

Approval Date:

3-EOP-E-0 Reactor Trip or Safety injection 7/13/10 STEP ACTIONIEXPECTED RESPONSE II RESPONSE NOT OBTAINED I

ATTACHMENT 3 (Page 7 of 7)

PROMPT ACTION VERIFICATIONS

19. Verify Power To Emergency 4 KV 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) E the Unit Supervisor decides not to energize the de-energized bus or V buses, THEN go to Step 20.

3) i.E the Unit Supervisor decides to energize 3A, 3B, or 3D bus, THEN perform the following:

V a) IF 3A 4 Ky bus de-energized, THEN restore power to bus using V

3-ONOP-004.2, LOSS OF 3A 4KVBUS.

b) jf 3B 4 KV bus de-energized, THEN restore power to bus using 3-ONOP-004.3, LOSS OF 3B 4KV BUS.

c) E 3D 4 Ky bus de-energized, THEN restore power to bus using 3-ONOP-004.5, LOSS OF 3D 4KVBUS.

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 W9711n/cls/nw/mr

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 01074011300 JPM: Loss of B SG Auto Task

Title:

MFRV Control JPM No: 01074011303 K/A

Reference:

059 A2.12 RO 3.1 SRO 3.4 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 and 4 are in MODE I at 100% power with no equipment out of service.

Initiating Cue:

• You are to respond to plant conditions as the Unit 3 Reactor Operator.

2011 NRCExam(R0)JPM-f NUREG 1021 Rev9AppendixC

Appendix C Page 2 of 9 Form ES-C-I Task Standard:

• Take manual control of B SIG Main Feed Regulating Valve and re-establish and stabilize level at the program level of 60% without tripping the Reactor or Turbine.

Required Materials:

• 3-ARP-097.CR.C, Control Room Response Panel C General

References:

• 3-ARP-097.CR.C, Control Room Response Panel C Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO) JPM-f NUREG 1021 Rev 9 Appendix C

Appendix C Page 3 of 9 Form ES-C-I SIMULATOR SETUP

1. Reset to IC 1 or equivalent IC.

2. Place Simulator in RUN.

3. Open Lesson JPM - 01074011303 and Execute.

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.

7. When ready to begin, then place the Simulator in RUN.

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

Appendix C Page 4 of 9 Form ES-C-I Denote critical steps with a check mark (vj StartTime SAT STEP I Walkdown the boards and assume the Watch.

UNSAT STANDARD Applicant briefly walks down the boards and assumes the Watch.

CUE COMMENT On the Examiners Cue, trigger lesson step LOSS OF B SG BOOTH MFRV AUTO CONTROL (insert TFFI 85CS TRUE delay=0 OPERATOR ramp60 onO offO) and (insert TVS1M3ED TRUE delay=O ramp=0 onO off=0).

. Loss of B SG MFRV Auto Control starts with the B SG Stm Flow Fl-3-484 failing low over 60 seconds and the input from Fl-3-485, if selected, is unavailable.

EVALUATOR o The operator will respond with Prompt Actions to take manua control of B Main Feed Reg Valve and return level NOTE to normal (60%) without tripping either the Reactor or Turbine in accordance with ARP C 4/2, 5/2, 6/2 or 0-ADM-211.

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

Appendix C Page 5 of 9 Form ES-C-I I CAUSES: 1 Steam Generator Level Control Malfunction

2. Instrument Failure Cl 5 5GB LEVEL DEVIATION DEVICE: SETPOINT: LOCATION:

LC-488D 5% above or below program level N/A CAUSES: 1. Steam Generator Level Control Malfunction

2. Instrument Failure

3. Feedwater or steam line leak SGB FEED > STEAM DEVICE: SETPOINT: LOCATION:

• FC-486C 1 out of 2 feed flow 0.665 x 108 lbs/hr greater than N/A a FC-488D steam flow CAUSES: t Steam Generator Level Control Malfunction

2. Instrument Failure C14

3. Feedwater or steam line break 5GB STEAM> FEED DEVICE: SETPOINT: LOCATION:

a FC-488A 1 ouf of 2 steam flow 0.5 x 10 lbs/hr greater than N/A a FC-488B feed flow PROMPT ACTIONS IF malfunctioning SG level controls, THEN:

• TAKE manual control of level.

. RETURN SG levels to normal.

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

Appendix C Page 6 of 9 Form ES-C-I After determining malfunctioning Auto SG Level Controls, then STEP 2 SAT place FCV-3-488, 3B FW Control Valve, to manual. UNSAT STANDARD Applicant places FCV-3-488, 3B FW Control Valve, to manual.

CUE Acknowledge reports from the operator.

COMMENT Auto light extinguishes and manual light illuminates.

STEP 3 Push the increase pushbutton to increase output demand on SAT FCV-3-488, 3B FW Control Valve. UNSAT Applicant pushes the increase pushbutton (up arrow) to increase STANDARD output demand on FCV-3-488, 3B FW Control Valve.

CUE Acknowledge reports from the operator.

COMMENT STEP 4 Push the decrease pushbutton to lower output demand on SAT FCV-3-488, 3B FW Control Valve. As required. UNSA1 Applicant pushes the decrease pushbutton (down arrow) to lower STANDARD output demand on FCV-3-488, 3B FW Control Valve as required.

COMMENT 2011 NRCExam(RO)JPM-f NUREG 1021 Rev9AppendixC

Appendix C Page 7 of 9 Form ES-C-I STEP 5 Re-establish and stabilize level at the program level of 60% without SAT tripping the Reactor or Turbine. UNSAT

.1 Applicant re-establishes and stabilizes level at the program level of STANDARD 60% without tripping the Reactor or Turbine.

CUE COMMENT When B SG Level is stabilized or the Reactor or Turbine is TERMINATING tripped. Then, the Evaluator informs the Applicant that CUE another operator will assume control.

The JPM is complete.

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

Appendix C Page 8 of 9 Form ES-C-I Verification of Completion:

Job Performance Measure No. 01074011303 - JPM: Loss of B SG Auto MFRV Control 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.

Initial Conditions:

• Unit 3 and 4 are in MODE 1 at 100% power.

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-f NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET 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 and 4 are in MODE 1 at 100% power.

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-f NUREG 1021 Rev 9 Appendix C

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:

015 A4.01 RD 3.9 SRO 3.9 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.

• A previous shift operator has completed Steps 7.3.2 through 7.3.2.25.e.

• I&C support is no longer required.

o At the start of the test, N-32 reads 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 directs you to perform Steps 7.3.2.26 through Step 7.3.2.34 of 3-OSP-059.1.

2011 NRC Exam (RO & SRO) JPM -g NUREG 1021 Rev 9 Appendix C

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

• Verify setpoints are within limits

• Confirms results are unsatisfactory.

Required Materials:

• 3-OSP-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test, marked-up to show completion up through Step 7.3.2.25.e (includes Attachment 2).

General

References:

• 3-OSP-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test Time Critical Task: No Validation Time: 20 minutes 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

• Appendix C Page 3 of 12 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. Trigger lesson step N-32 HIGH FLUX TRIP SETPOINT TOO HIGH (insert N1SRHLS2=5.08).

5. Ensure Simulator Operator Checklist is complete.

6. Acknowledge alarms and place Simulator in FREEZE.

7. Provide a copy of 3-OSP-059.1, Source Range Nuclear Instrumentation Analog Channel Operational Test, marked-up to show completion up through Step 7.3.2.25, also include Attachment 2.

8. 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.

9. When ready to begin, then place Simulator in RUN.

2011 NRC Exam (RO & SRO) JPM-g 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 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 Instrumentation Analog Channel Operational Test, marked-CUE up to show completion up through Step 7.3.2.25.e.

(NOTE: Includes some data taken on Attachment 2.)

COMMENT Place HIGH FLUX AT SHUTDOWN switch (NIS panel, N-32) to SAT STEP 2 BLOCK.

UNSAT

• q (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 Rev 9 Appendix C

Appendix C Page 5 of 12 Form ES-C-I Verifies 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 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-I EVALUATOR The LEVEL TRIP status light will light at approximately 1.2 X NOTE 6 CPS which is outside the acceptable band.

10 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.

J (3-OSP-059.1, Step 7.3.2.29)

Applicant rotates the LEVEL ADJ potentiometer (NIS panel, N-STANDARD 32) slowly clockwise until LEVEL TRIP status light (NIS panel, N-32) turns ON.

CUE If the applicant informs the Unit Supervisor, acknowledge the report.

COMMENT Record SOURCE RANGE CPS NEUTRON LEVEL (NIS panel, SAT STEP 6 N-32) for Level Trip bistable trip point on Attachment 2.

UNSAT J

(3-OSP-059.1, Step 7.3.2.30.a)

Applicant records an unacceptable reading of between

> 1.0 x to 2.0 x in the blank for Step 7.3.2.30 on STANDARD Attachment 2.

Tolerance based on the increments of the log scale.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N-32.

2011 NRC Exam (RO & SRO) JPM-g NUREG I 021 Rev 9 Appendix C

Appendix C Page 7 of 12 Form ES-C-I 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 When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N-32.

COMMENT Adjust LEVEL ADJ potentiometer (NIS panel N-32) slowly SAT counterclockwise until LEVEL TRIP status light (NIS panel, N-32)

STEP 8 UNSAT turns OFF.

J (3-OSP-059.1, Step 7.3.231)

Applicant rotates the LEVEL ADJ potentiometer (NIS panel N-32) slowly counterclockwise until LEVEL TRIP status light (NIS panel, STANDARD N-32) turns OFF.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N-32.

2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 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 I

(3-OSP-059.1, Step 7.3.2.32.a)

Applicant records between 6.0 X and 7.0 X in the blank for Step 7.3.2.32 on Attachment 2.

STANDARD Tolerance based on the increments of the log scale.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N-32.

COMMENT Declares the Acceptance Criteria UNSAT and enters 3-ONOP-SAT 059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION.

STEP 10 UNSAT (3-OSP-059.1, Step 7.3.2.32.b)

Applicant confirms results are unsatisfactory, THEN confirms results are unsatisfactory, THEN declares the N-32 channel STANDARD inoperable and enters 3-ONOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

COMMENT 2011 NRC Exam(R0&SRO)JPM-g NUREG 1021 Rev9AppendixC

Appendx C Page 9 of 12 Form ES-C-I Adjust LEVEL ADJ potentiometer (NIS panel, N-32) fully SA1 STEP 11 counterclockwise.

UNSAT q

(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.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N.-32.

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.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report and go to the TERMINATING CUE on Page 10.

EVALUATOR Informs Unit Supervisor or Shift Manager of the UNSAT reading NOTE affecting Channel N-32.

2011 NRCExam(R0&SRO)JPM-g NUREG 1021 Rev9AppendixC

Appendix C Page 10 of 12 Form ES-C-I Declares the Acceptance Criteria UNSAT and enters 3-ONOP-SAT 059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION.

STEP 13 UNSAT (3-OSP-059. 1, Attachment 2)

Applicant confirms results are unsatisfactory, THEN confirms results are unsatisfactory, THEN declares the N-32 channel STANDARD inoperable and enters 3-ONOP-059.5, SOURCE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION.

When the applicant informs the Unit Supervisor or Shift Manager CUE of the UNSAT Acceptance Criteria, then acknowledge the report.

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

Stop Time 2011 NRC Exam (RO & SRO) JPM-g NUREG 1021 Rev 9 Appendix C

[Appendix C Page 11 of 12 I Form ES-C-I Verification of Completion:

Job Performance Measure No. 01059017201 - JPM: Test Source Range Nuclear Instrument Examine&s 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 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.

Initial Conditions:

e The Unit is in MODE 3.

o The SM has authorized performance of 3-OSP-059. 1, Source Range Nuclear Instrumentation Analog Channel Operational Test, for N-32.

o A previous shift operator has completed Steps 7.3.2 through 7.3.2.25.e.

l&C support is no longer required.

0 Atthestartofthetest, N-32 reads 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 directs you to perform 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 EVALUATORWHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

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.

• A previous shift operator has completed Steps 7.3.2 through 7.3.2.25.e.

• l&C support is no longer required.

• At the start of the test, N-32 reads 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 directs you to perform 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

Florida Power & Light Company Turkey Point Nuclear Plant Unit 3 I

Title:

Source Range Nuclear Instrumentation Analog Channel Operational Test (Continuous Use)

Safety Related Procedure Responsible Department: Operations Revision Number 1 Issue Date: 6/3/11 Revision Approval Date: 2/23/11 ARs 564687 RTSs 88-0382P, 89-0472, 89-0672P, 90-0997, 91-1364W, 92-1718P, 93-1178P, 96-1090P, 97-l3l5 98-1096P, 99-0478P, 03-0217P, 04-0288P, 07-0950P PC/Ms90-508, 93-047,02-085 W97:JTNM/nw/In/cls

Procedure No.; Procedure

Title:

Page:

2 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 2/23/11 LIST OF EFFECTIVE PAGES (Rev. 1)

Revision Revision Date jg Date 1 02/23/11 23 09/16/01 2 02/23/11 24 09/16/01 3 11/10/07 25 09/16/01 4 02/23/11 26 11/10/07 5 02/23/11 27 09/16/01 6 02/23/11 28 09/16/01 7 02/23/11 29 09/16/01 8 11/10/07 30 11/10/07 9 09/16/01 31 09/16/01 10 09/16/O1C 32 09/16/O1C 11 11/10/07 33 09/16/Ole 12 09/16/01 34 11/10/07 13 09/16/01 35 09/16/O1C 14 11/10/07 36 09/16/O1C 15 02/23/11 37 11/10/07 16 03/26/03 38 09/16/O1C 17 09/16/01 39 09/16/01 18 11/10/07 40 11/10/07 19 09/16/01 41 09/16/O1C 20 09/16/01 42 09/16/01 21 04/01/04 43 11/10/07 22 11/10/07 44 11/10/07C

Procedure No.: Procedure

Title:

Page:

3 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 11/10/07 TABLE OF CONTENTS Section 1.0 PURPOSE 4

2.0 REFERENCES

/RECORDS REQUIRED!

COMMITMENT DOCUMENTS 4 3.0 PREREQUISITES 6 4.0 PRECAUTIONS/LIMITATIONS 6 5.0 SPECIAL TOOLS/EQUIPMENT 6 6.0 ACCEPTANCE CRITERIA 6 7.0 PROCEDURE 7 ENCLOSURE/ATTACHMENTS Enclosure 1 High Flux at Shutdown Acceptance Criteria for Alarm and Reset

- 31 Attachment I Source Range Channel N-3 1 Test Data (Shutdown) 32 Attachment 2 Source Range Channel N-32 Test Data (Shutdown) 35 Attachment 3 Source Range Channel N-3 1 Test Data (Operating) 38 Attachment 4 Source Range Channel N-32 Test Data (Operating) 41 Attachment 5 P-6 and P-b Verification 44 W97:/TNM/nw/In/cls

Procedure No.: Procedure

Title:

Source Range Nuclear Instrumentation 3-OSP-059.1 Analog Channel Operational Test 1.0 PURPOSE 1.1 This procedure provides the prerequisites, precautions, limitations and instructional guidance to perform the required surveillance prior to reactor startup and monthly surveillance of the Source Range Nuclear Instrumentation. This surveillance satisfies the requirements of Reference 2.1.1.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 2.1 References 2.1.1 Technical Specifications

1. Section 2.2.1, Table 2.2-1, Item 4, Reactor Trip System Instrumentation Setpoints

2. Section 4.3.1.1, Table 4.3-1, Item 4, Reactor Trip System Instrumentation Surveillance Requirements

3. Section 4.9.2, Items b and c, Refueling Operations Instrumentation Surveillance Requirements

4. Section 3.9.2, Refueling Operations Instrumentation

5. Table 4.3-1, Functional Unit 4, Notation (9), High Flux at Shutdown 2.1.2 Final Safety Analysis Report I. Section 7.2, Protective Systems

2. Section 7.4, Nuclear Instrumentation 2.1.3 Plant Procedures

1. 0-ADM-724, Instrumentation Protection Channel Determination of Channel Operability

2. 3-ONOP-05 9.5, Source Range Nuclear Instrumentation Malfunction

3. 0-OP-003.3, 120V Vital Instrument AC System

4. 3-OSP-059.6, High Flux at Shutdown W97:!TN M/nw/In/cls

Procedure No. Procedure

Title:

Page:

5 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 2/23/11 2.1.4 Miscellaneous Documents (i.e., PC/Ms, Correspondence)

1. Inter-Office Correspondence, PTN-TECH-89-121, J. M. Donis to R. G.

Mende, dated January 31, 1989,

Subject:

3/4-OSP-059.1, Acceptance Criteria for Control Room Indicators Operability of Sources Range Channels

2. PC/M 90-508, Implementation of Setpoint Methodology

3. PC/M 93-047, Annunciator Dark Board

4. PC/M (MSP)02-085, Replace Recorder NR-45

5. CR 2009-15410, Half Decade 2.2 Records Required 2.2.1 The date, time, and section completed shall be logged in the Unit Narrative Log.

Also, any problems encountered while performing the procedure should be logged (i.e., malfunctioning equipment, delays due to changes in plant conditions, etc.).

2.2.2 Completed copies of the below listed item(s) document the compliance with Technical Specification surveillance requirements and shall be transmitted to QA Records for retention in accordance with Quality Assurance Records Program requirements:

I. Section 7.0

2. Attachments 1,2, 3,4, and 5 2.2.3 Completed copies of the below listed item(s) shall be transmitted to System Engineer for information.

1. Attachments 1, 2, 3,4, and 5 2.3 Commitment Documents 2.3.1 JPN-PTN-SENP-94-014, No Significant Hazards Evaluation for Extension of Technical Specification Surveillance Intervals and Out of Service Times for the Reactor Protection and Engineered Safety Features Instrumentation Systems

Procedure No.: Procedure

Title:

Source Range Nuclear Instrumentation 3-OSP-059.l Analog Channel Operational Test 3.0 PREREQUISITES 3.1 Instrument AC Panels 3P06 and 3P07 should be powered from their normal sources per 0-OP-003.3, 120V Vital Instrument AC System, during this test.

3.2 Instrument & Controls Department available to jumper high volts.

4.0 PRECAUTIONS/LIMITATIONS 4.1 Tests shall be performed on only one source range channel at a time. The channel not under test must be operable except as indicated in the note below.

= =

With only one source range channel operable, the Shift Manager may authorize testlog the operable channel after reviewing the applicable Action Statements of Technical Specification 3.3.1, Table 3.3-1, item 4, and Section 3.9.2.

a I

a a a a a a a a I 4.2 Any nuclear instrumentation channel should be energized for at least one hour prior to being tested.

4.3 A source range channel should not be tested when neutron flux level changes in the source range are in progress.

4.4 Discrepancies noted during this test shall be investigated for their effect on channel operability and actions taken per 3-ONOP-059.5, Source Range Nuclear Instrumentation Malfunction, as applicable.

4.5 The Shift Manager shall be notified immediately if any Acceptance Criteria is not met or any malfunction or abnormal conditions occur. This information shall also be recorded in the Remarks Section.

5.0 SPECIAL TOOLS/EQUIPMENT 5.1 None 6.0 ACCEPTANCE CRITERIA 6.1 The Reactor Trip System Instrumentation Trip Setpoint for the Source Range, Neutron Flux shall be less than or equal to l0 CPS.

6.2 When in Mode 3, 4, or 5 with Reactor Trip System breakers closed and Control Rod Drive System capable of rod withdrawal, permissives P-6 and P-i 0 are in their required state for existing plant conditions.

6.3 Technical Specification Table 4.3-1, Functional Unit 4, Notation (9), requires High Flux at Shutdown alarm setpoint at 1/2 decade above the existing count rate. Multiplication by 102 increases any number two decades. Multiplication by 101 increases any number b one decade. Multiplication by 101/2 increases any number by 1/2 decade. Since 101/ (the square root of 10) is approximately 3.16, the CPS multiplied by 3.16 usefully approximates this Technical Specification required setpoint within the accuracy of plant equipment.

W97:/TNM)nw/lnlcls

-U CD CD D Cl) o 00 CD i5-

- CD 0

Procedure No.: Procedure

Title:

Page:

19 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 9/16/01 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-31, HTGH FLUX AT SHUTDOWN switch in BLOCK).

Adjust LEVEL ADJ potentiometer (MS panel, N-32) slowly clockwise until

)- HIGH FLUX AT SHUTDOWN status light (NIS panel, N-32) turns ON.

Perform the following:

Record SOURCE RANGE CPS NEUTRON LEVEL (MS panel, N-32)

I for High Flux at Shutdown bistable trip point on Attachment 2.

Verify HIGH FLUX AT SHUTDOWN status light (MS 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 (MS panel N-32) slowly counterclockwise until HIGH FLUX AT SHUTDOWN status light (MS panel, N-32) turns OFF.

Perform the following:

$1 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.

Verify Annunciator B 4/1, SOURCE RANGE HI FLUX AT

. SHUTDOWN, is OFF.

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/In/cls

Procedure No.: Procedure Tilie: Page:

20 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 9/16/01 INITIALS CKD VERIF 7.3.2 (Contd)

26. Place HIGH FLUX AT SHUTDOWN switch (MS 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, THE 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 (MS 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.

Procedure No.: Procedure

Title:

Page:

21 Source Range Nuclear Instrumentation Approval Date:

3-OSP059.1 Analog Channel Operational Test 4/1/04 INITIALS CKD VERIF 7.3.2 (Contd)

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. At NIS panel, N-32, verify the following:

a. INSTRUMENT 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 IN TEST, is OFF.

38. Place HIGH FLUX AT SHJJTDOWN 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-31, HIGH FLUX AT SHUTDOWN switch in BLOCK).

40. Place LEVEL TRIP switch (NTIS 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).

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. IF in Mode 6, 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 Wq7ITJM!nw/InIr

D CD cJ3 0 I

(Q o CD cr C,)

13 N) oi3 (0 0 -

CD 0

Procedure No.: Procedure

Title:

Page:

35 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 9116101C ATTACHMENT 2 (Page 1 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (SHUTDOWN)

QA RECORD PAGE (Page 1 of 3) 1a1 a a a a = a g The NIS Drawer Meter is to be used for channel operability requirements. Deficiencies in the console indications should be brought to the attention of the I&C Departmenl with appropriate prioritization with respect to plant mode.

la a a a a a a a a a a a a a I Ref. Step Operation Selector switch range verification.

faa a a a Iaa a a a a a The symbol +xxx in the acceptance criteria represents greater than 6 1.0x10 CPS by an amount less than or equal to the meter deflection between 8x10 5 CPS and 1.0x10 6 CPS.

L.a. a a a a a a a a a a a a 1 OPERATION NIS CONSOLE* CONSOLE*

SELECTOR Meter Meter Recorder POSITION N-32 N-3-32 NR-3-45, Channel S2 6OCPS 6 55 Acceptance Criteria: (50 to 75 CPS) 1O C

3 PS 3 ixjØ /I)c Acceptance Criteria: (8 x 102 to 1.2 x 1 CPS) 10 CPS Acceptance Criteria:

I C (8 x lO

/ ) /9 to 1.2 x 10 CPS) 4

1. i x 1O6CPS Acceptance Criteria:

l (8 x I

to +xxx) 1 1

1OCPS PREAMP (No Acceptance Criteria)

/ 2 y/ I lO.24xlO CPS PREAMP - / j , /Ø I c /Ø (No Acceptance Criteria)

Return to Step 7.3.2.15 Wg7:/TN MInwln/cIs

Procedure No.: Procedure

Title:

Page:

36 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 9J16/O1C ATTACHMENT 2 (Page 2 of 3)

SOURCE RANGE CHANNEL N32 TEST DATA (Shutdown) 1 QARECORDPAGE I

(Page 2 of 3) 6 High Flux at Shutdown bistable trip point, N-32 Source Range 315 cps High Flux at Shutdown bistable reset point, N-32 Source Range CPS 7.3.2.30 Level Trip bistable trip point, N-32 Source Range CPS Acceptance Criteria ( i0 CPS)

• FOR REVIEW ONLY 7.3.2.32 Level Trip bistable reset point, N-32 Source Range CPS Acceptance Criteria (4.1 x i0 4 to 6.2 x i0 4 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.

If channel(s) did not meet acceptance criteria, then notify l&C to perform O-ADM-724, Instrumentation Protection Channel Determination of Channel Operability, for the failed channels. [Commitment Step 2.3.1]

Wq7ITjM/nw/In/

Procedure No.: Procedure

Title:

Page:

37 Source Range Nuclear Instrumentation Approval Date:

3-OSP-059.1 Analog Channel Operational Test 11/10/07 ATTACHMENT 2 (Page 3 of 3)

SOURCE RANGE CHANNEL N-32 TEST DATA (Shutdown)

I QARECORDPAGE (Page 3 of 3)

REMARKS:

PERFORMED BY (Print) dfiL REVIEWED BY:

Shift Manager or SRO Designee W97:ITNM/nw/In/ds

CD (13 0

-a o CD C) Cl)

-a - (13 Co 01 cc, 0 CD

-I, 0

3

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: 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:

• Unit 3 is in MODE 3.

• Unit 4 is in MODE I at 100% power.

• The following equipment is Out of Service for maintenance 3A CCW Pump, 3A ICW Pump, 4A HHSI Pump.

Initiating Cue:

• You are to respond to plant conditions as the Unit 3 Reactor Operator.

2011 NRC Exam (R0&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 14 Form ES-C-I TaskStanctard(s)

• Stop RCPs, isolate Letdown, and direct alignment of emergency cooling to a Charging Pump in accordance with 3-ONOP-030.

Required Material(s)

• 3-ARP-097.CR.H, Control Room Annunciator Response Panel H

• 3-ONOP-030, Component Cooling Water Malfunction Reference(s)

• 3-ARP-097.CR.H, Control Room Annunciator Response Panel H

• 3-ON OP-030, Component Cooling Water Malfunction Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (R0&SRO) 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 3A CCW Pump (PTL), 3A ICW Pump(Auto/Stop), and 4A HHSI Pump(PTL) are not running.

5. Trigger lesson step SETUP 3A CCW PUMP OOS (insert TFK1A12T=TRUE)

(insert TAK1A12P=RACKOUT)

6. Trigger lesson step SETUP 3A ICW PUMP OOS (insert TAK2A19P=RACKOUT)

7. Trigger lesson step SETUP 4A HHSI PUMP OOS (insert TAM2D4AS=RACKOUT)

8. Hang ECO Information Tags on the handswitches for 3A ccw Pump, 3A ICW Pump, and 4A HHSI Pump.

9. Ensure Simulator Operator checklist is complete.

10. Acknowledge alarms and place Simulator in FREEZE.

11. 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.

12. When ready to begin, then place Simulator in RUN.

2011 NRC Exam (R0&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 14 Form ES-C-I Denote critical steps with a check mark (i4 Start Time NOTE The applicant assumes the duties of Unit 3 Reactor Operator.

On the Examiners Cue, trigger lesson step LOSS OF CCW (insert TVKAOO2X=l .000000 delay=0 ramp=60 on=0 off=0)

OPERATOR (insert TFK1AI7T=TRUE delay=O ramp=0 ori=0 off=0)

SAT STEP I Obtain required reference materials.

U N SAT Applicant acknowledges annunciators and references 3-ARP-STANDARD 097.CR.H, for annunciator H-8/1, 2, or 3; OR 3-ONOP-030, Component Cooling Water Malfunction.

CUE COMMENT Applicant may directly enter 3-ONOP-.030, Component Cooling Water Malfunction. For this reason, use of the ARP is NOT critical.

EVALUATOR Applicant may recognize high amps on 3B CCW pump and NOTES 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&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 14 Form ES-C-I CAUTION F If any RCF bearing temperature snnvniator aami actuates AUD its associated motor bearing temperature is 9reater than 195F oip the reactor ard stop the affected RCFs.

NOTE NOTE I

I 4drzpac bc4ild be monitored th houi thio prcedra I i..... a a a a a S 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 I & 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 The Applicant may perform actions from the Foldout page, NOTE which if completed, would bypass this step, if this occurs, go to Step 7.

2011 NRC Exam (R0&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

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 Acknowledge orders I request if required.

CUE COMMENT The Applicant may have attempted to start the 30 CCW pump using the ARP in step 1.

Applicant may make calls to the field to attempt local start of 30 EVALUATOR CCW pump.

NOTES 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&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 14 Form ES-C-I IF starting an idle CCW pump will NOT overload an EDO, THEN SAT start COW 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 Acknowledge orders I request if required CUE COMMENT The Applicant may have attempted to start the 3C COW pump using the ARP in step 1.

Applicant may make calls to the field to attempt local start of 3C EVALUATOR COW pump.

NOTES 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 COW pump as soon as possible.

This is one of the Alternate Path aspects of this JPM.

2011 NRC Exam (RO&SRO) 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 o FT-3-61 3A for header A STEP 5 0 FT-3-613B for header B (3-ONOP-030, Step 3)

Applicant checks A CCW HDR FLOW FI-3-61 3A & B CCW HDR STANDARD FLOW Fl-3-613B and notes that both indicators are reading 0 GPM. Transitions to the RNO column.

CUE COMMENT EVALUATOR This Step is NOT critical since there are no verifiable operator NOTE actions.

2011 NRC Exam (RO&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 14 Form ES-C-I IF COW flow to RCPs can NOT be established, THEN manually SAT trip the reactor AND verify reactor trip using the EOP Network, STEP 6 UNSAT AND then stop all RCPs AND perform the following:

• q (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 STANDARD the STOP position. Notes that the green STOP light is ON and the red RUN light is OFF for all three RCPs.

OR Per 3-ONOP-030, Foldout Page, Item 1 .A, Applicant may trip RCPs prior to RNO Step 3.

CUE COMMENT EVALUATOR Applicant should acknowledge that the Reactor was previously NOTE tripped and re-verification of trip is not warranted.

2011 NRC Exam (RO&SRO) JPM-h NUREG 1021 Rev9 Appendix C

Appendix C Page 10 of 14 Form ES-C-I STEP 7 Isolate Letdown and Excess Letdown 1 SAT 1

] UNSAT (3-ONOP-030, RNO Step 3.a.l.)

Applicant isolates Letdown by placing the handswitch for the following valves in the CLOSE position.

EITHER:

o CV-3-204, LID FROM RHX. ISOL. VALVE OR

• 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 Applicant should verify excess letdown was previously isolated.

NOTE Verification of excess letdown being isolated is NOT critical since there are no verifiable operator actions.

2011 NRC Exam (R0&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C Page II of 14 Form ES-C-I 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 (G 1/2) will actuate when the pump is at maximum speed.

CUE COMMENT The Applicant may stop one charging pump based on plant EVALUATOR NOTE need. ONLY the Charging pump(s) that are running are operated at a maximum speed.

2011 NRC Exam (RO&SRO) JPM-h NUREG 1021 Rev 9 Appendix C

Appendix C 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 a running pump.

TERMINATING Evaluator informs the Applicant that another operator will CUE continue in this procedure. The JPM is complete.

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

• Appendix C Page 13 of 14 Form ES-C-I Verification of Corn pletion Job Performance Measure 01030008303- JPM: Respond to Component Cooling Water No. System Malfunctions 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 (R0&SRO) JPM-h 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:

• Unit 3 is in MODE 3.

• Unit 4 is in MODE 1 at 100% power.

• The following equipment is Out of Service for maintenance 3A COW Pump, 3A lOW Pump, 4A HHSI Pump.

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 (R0&SRO) JPM-h 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:

a Unit3isinMODE3.

a Unit 4 is in MODE I at 100% power.

• The following equipment is Out of Service for maintenance 3A COW Pump, 3A lOW Pump, 4A HHSI Pump.

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

Florida Power & Light Company Turkey Point Nuclear Plant Unit 3

Title:

Component Cooling Water Malfunction (Continuous Use)

Safety Related Procedure Responsible Department: Operations Revision Number: 2 Issue Date: 6/15/11 Revision Approval Date: 3/25/11 ARs 580245 PCRs 08-3 724,08-216 1, 10-0619 OTSCs 10906, 0543-00, 0301-02, 0195-03 PC/Ms 9 1-064, 92-03 1,92-106, 93-034,94-096, 96-092,96-093, 00-016,04-112, 06-018 W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 3/25/11 LIST OF EFFECTIVE PAGES (Rev. 2)

Revision Revision Date Date 1 03/25/11 19 11/28/07 2 03/25/11 20 11/28/07 3 11/28/07 21 11/28/07 4 10/12/10 22 03/25/11 5 03/25/11 23 11/28/07 6 11/28/07 24 11/28/07 7 01/05/09 25 11/28/07 8 03/25/11 26 10/12/10 9 11/28/07 27 11/28/07 10 11/28/07 28 10/12/10 11 11/28/07 29 10/12/10 12 11/28/07 30 10/12/10 13 03/25/11 31 11/28/07 14 03/25/11 32 11/28/07 15 03/25/11 33 10/12/10 16 03/25/11 34 11/28/07 17 11/28/07 35 11/28/07 18 03/25/11 Foldout 10/12/10 W97/nw/mr/nw

1.0 PURPOSE 1.1 This procedure provides instructions to be followed in the event of a malfunction or failure in the Component Cooling Water System.

1.2 This procedure applies to loss of Component Cooling Water due to system leakage or due to high system temperatures.

2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 Visible evidence of system leakage.

2.2 Rapid decrease in CCW Surge Tank Level, LI-3-613A, or CCW Head Tank Level, LI-3-614A.

2.3 Component Cooling Water Supply Header Temperature, TI-3-607A, greater than 120°F.

2.4 Loss of intake cooling water flow to CCW Heat Exchangers as determined by 3-ONOP-019, INTAKE COOLING WATER MALFUNCTION.

2.5 Annunciators 2.5.1 A 1/1, RCP THERMAL BARR COOLING WATER HI FLOW 2.5.2 A 1/3, RCP THERMAL BARR COOLING WATER LO FLOW 2.5.3 H 7/3, RI-IR PP A COOLING WATER LO FLOW 2.5.4 H 7/4, RHR PP B COOLING WATER LO FLOW 2.5.5 H 7/5, CSP A/B COOLING WATER LO FLOW 2.5.6 H 7/6, CCW SURGE TANK LO LEVEL 2.5.7 H 8/1, CCWPPA/B/C TRIP 2.5.8 H 8/2, CCW PP A/B/C MOTOR OVERLOAD 2.5.9 H 8/3, CCW HEADER LO PRESS 2.5.10 H 8/4, CCW PP SUCTION HI TEMP 2.5.11 H 8/5, CCW FIX OUTLET HI TEMP 2.5.12 H 8/6, CCW HEAD TANK HI/LO LEVEL 2.5.13 H 9/5, RCP MOTOR BRG COOLING WATER LO FLOW 2.5.14 X 3/6, SI PP COOLING WATER LO FLOW W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 10/12/10

3.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 3.1 References 3.1.1 Technical Specifications

1. Section 3/4.5.2, ECCS Subsystems Tavg Greater Than or Equal to 350°F

2. Section 3/4.5.3, ECCS Subsystems Tavg Less Than 3 50°F

3. Section 3/4.7.2, Component Cooling Water System

4. Section 3/4.9.8, Residual Heat Removal and Coolant Circulation 3.1.2 FSAR

1. Section 9, Auxiliary and Emergency Systems 3.1.3 Plant Drawings

1. 5613-M-3047, Sheets 1 and 2, CVCS Charging and Letdown System

2. 5613-M-3030, Sheets 1 through 5, Component Cooling Water System

3. 5613-M-3020, Sheets 1 and 2, Primary Water System 3.1.4 Plant Procedures

1. 0-EPIP-20 101, Duties of Emergency Coordinator

2. 0-NOP-012, Service Water System

3. 3-EOP-E-0, Reactor Trip Or Safety Injection

4. 3-ONOP-019, Loss of Intake Cooling Water

5. 3-ONOP-041.1, Reactor Coolant Pump Off-Normal

6. 3/4-NOP-030, Component Cooling Water System

7. 3-NOP-041.O1A, 3A Reactor Coolant Pump Operations

8. 3-NOP-041.O1B, 3B Reactor Coolant Pump Operations

9. 3-NOP-041.O1C, 3C Reactor Coolant Pump Operations W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 3/25/11 3.1.5 Miscellaneous Documents (i.e. PC/M, Correspondence)

1. PC/M 91-064, Charging Pump Service Water Connections

2. PC/M 92-108, Replacement of Raw Water and Service Water Systems

3. PC/M 93-034, CCW System Reconfiguration to HHSI Pumps Seal/Thrust Bearing Coolers

4. PC/M 94-096, Removal of Valves CV-3-2202

5. PC/M 96-093, Addition of Unit 4 CCW Head Tank

6. PC/M 96-092, Addition of U-3 CCW Head Tank

7. PC/M 00-016, CRN M-10471, CCW Surge Tank Level Indicator Replacement

8. PC/M 04-112, Emergency Response Data Acquisition and Display System (ERDADS) Replacement

9. PC/M 06-018 (EC242212), Unit 3 Cask Handling Facility 3.2 Records Required 3.2.1 None 3.3 Commitment Documents 3.3.1 NRC Inspection Report 89-053, March 14, 1990 3.3.2 JPN-PTN-SENP-95-026, Safety Evaluation for CCW Flow Balance and Post Accident Alignment Requirements to Support Current and Uprated Conditions (LER 250/95-006)

W97/nw/mr/nw

STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION If any RCP bearing temperature annunciator alarm actuates AND its associated motor bearing temperature is greater than 195 CF trip the reactor and stop the affected RCP5.

NOTE I I I Foldout page should be monitored throughout this procedure. I L._ I I Verify Power To 4KV Bus 3D

a. Maintain 4KV Bus 3D energized - a. IF lockout of 4KV Bus 3D NOT present, ALIGNED TO AN ENERGIZED 4KV BUS THEN perform the following:

1. Verify3C CCW Pump-BREAKER OPEN

2. Verify 3C ICW Pump -

BREAKER OPEN

3. Operate bus supply breakers to energize bus.

2 Verify Component Cooling Water Pumps a. E starting an idle COW pump will jQI In Service overload an EDG, THEN start COW pumps as necessary to establish flow in both headers.

3 Verify Flow In Both Component Cooling Perform the following:

Water Headers NORMAL

a. IF COW flow to RCPs can NOT be

• FT-3-61 3A for header A established, THEN manually trip the reactor J4Q verify reactor trip using the

• FT-3-613B for header B EOP Network, then stop all RCPs perform the following:

1. Isolate Letdown and Excess Letdown

2. IF any charging pump is running, THEN operate at maximum speed until Attachment I is completed.

3. Dispatch an operator to establish emergency cooling water to desired charging pump using Attachment 1.

W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 1/5/09 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED NOTES

• The top of the component coo/hg water surge tank divider p/ate is located at approximately 25% indicated level.

I

• If a cross tie valve between the units is leaking or open, the surge tank on the opposite unit may be experiencing level control problems.

I If in Modes I through 3, and CCW System level is NOT maintained within the CCW Head Tanlc restore CCW System level to be within the COW Head Tank within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• LI-3-613A and LI-3-614A are NOT overlapping (i.e., LI-3-614A will go off scale low before Ll-3-613A comes off its high peg with decreasing level).

4 Verify Component Cooling Water Surge Perform the following:

Tank Level Being Maintained

1. Open Component Cooling Water Surge

a. Component Cooling Water Surge Tank Tank Makeup, MOV-3-832 as necessary Level, Ll-3-61 3A - to add makeup.

• GREATER THAN 25% 2. jf Component Cooling Water Surge Tank Level can NOT be maintained, AND THEN perform the following:

• STABLE OR INCREASING. a) Trip the reactor AND perform 3-EOP-E-O, Reactor Trip or Safety Injection, while continuing with this procedure.

b) WHEN rector verified tripped, THEN stop all RCP5.

3. Observe NOTES prior to Step 8 and go to Step 8.

W97/nw/mr/nw

j STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

5 Check If Component Cooling Water Headers Should Be Tied Together

a. Check CCW headers SPLIT- a. GotoStep34.

b. Check if flow has been lost in any CCW b. flow in both CCW headers is normal, header THEN go to Step 34.

FT-3-61 3A for header A FT-3-613B for header B 6 Tie Component Cooling Water Headers Together

a. Direct operator to terminate activities which require splitting CCW headers Heavy load transport in Cask Handling Facility In-service testing

b. Locally open CCW pump Suction Header Sectionalizing valves

• 3-787A

• 3-787B

c. Locally open CCW pump Discharge Header Sectionalizing valves

• 3-787C

• 3-7870

d. Locally open all Component Cooling Water Heat Exchanger Outlet Header Sectionalizing valves

• 3-787E

• 3-787F

• 3-787G

• 3-787H 7 Go To Step 34 W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

NOTES I

• Steps 8 through 33 are only applicable when leakage from the Component Cooling Water System is in progress.

I I a When leakage has been located and isolateci recoveiy actions shall continue starting with Step 27.

a a a I 8 Establish Stable Plant Parameters

a. Station a watch at Header B local surge tank level indicator, Ll-3-61 5

b. Isolate Letdown and Excess Letdown

c. Dispatch an operator to establish emergency cooling water to desired charging pump using Attachment I

d. Dispatch an operator to locate and isolate d. f the system walkdown fails to identify CCW System leakage by performing a the leak and CCW Surge Tank Level is System Walkdown. still decreasing Qfi makeup still required, THEN perform the following:

1. Stop and PULL-TO-LOCK all but one COW Pump.

2. Attempt to determine if the leak is in a Heat Exchanger by removing ONLY one CCW Heat Exchanger from service at a time using the following CCW isolation valves:

HX Inlet Outlet 3A 3-712A 3-713A 3B 3-712B 3-713B 3C 3-71 20 3-713C W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 9 Check If Additional Makeup Is Required

a. Component Cooling Water Surge Tank a. Perform the following:

Level, Ll-3-613A DECREASING OR EMPTY 1) if surge tank level can QI be maintained during subsequent recovery actions, THEN do Steps 9b, 9c and 9d.

2) GotoSteplO.

b. Locally open Component Cooling Water i-leader A Makeup Water Isolation, 3-71 IA

c. Throttle closed DWDS-OO1 to provide Demin Water Flow to the COW Surge Tank

d. Locally throttle Demin Water Supply Valve, 3-724D, as necessary to maintain surge tank level stable or increasing 10 Verify CCW Pumps - NOT CAVITATING Stop any cavitating COW pumps and place all COW pumps in Pull-To-Lock.

a. Running COW pump amps STABLE -

b. Component Cooling Water Header Flows -

STABLE

• Fl-3-613A

• Fl-3-613B W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I CAUTION After dispatching an operator to locally split the Component Cooling Water headers, the Control Room operator shall continue with Step 13.

11 Check If Headers Should Be Split Between The B And C CCW Pumps

a. Leakage KNOWN TO EXIST ON

a. jf leakage is on header A QE location of HEADER B leakage is NQI known, THEN go to Step 15.

b. Check on one of the following pumps - b. Perform the following; RUNNING

1) IF CCW pumps were placed in 3A CCW Pump PULL-TO-LOCK due to cavitation, THEN DO NOT start the 3A or 3B CCW Pump J.4Q go to Step I lc.

3B CCW Pump 2) IF ONLY 3C CCW Pump running, THEN start 3A or 3B COW Pump.

c. Place the 30 CCW Pump in STOP and PULL-TO-LOCK 12 Isolate B CCW Header Locally close the listed valves to separate the headers.

a. Check the CCW Header Sectionalizing valves closed

• CCW Hx Outlet Hdr Sect Valve, 3-787G OR COW Hx Outlet Hdr Sect Valve, 3-787H

• COW Pump Dischg Hdr Sect Valve, 3-787D

• CCW Pump Suct Hdr Sect Valve, 3-787B

• COW Sys Demin Water Primary Water Supply, 3-7370 13 Check CCW Pump Operation Start either 3A or 3B COW Pump.

a. Either 3A or 3B COW Pump running 14 GotoStepl8 W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED I

S a a 3C CCW Pump should be off if 38 COW Pump is available to minimize the potential for exceeding the flow limits on the CCW Heat Exchangers.

15 Check If Headers Should Be Split Between The A And B CCW Pumps

a. Check on one of the following pumps - a. Perform the following:

RUNNING

1) f COW pumps were placed in 3B COW Pump PULL-TO-LOCK due to cavitation, OR THEN DO NOT start the 3B or 30 3000W Pump COW Pump AND go to Step 1 5b.

2) IF ONLY 3A COW Pump running, THEN start 3B or 30 COW Pump.

b. Place the 3A COW Pump in STOP and PULL-TO-LOCK 16 Isolate A CCW Header Locally close the listed valves to separate the header.

a. Check the COW Header Sectionalizing valves closed

• COW Hx Outlet Hdr Sect Valve, 3-787E OR COW Hx Outlet Hdr Sect Valve, 3-787F

• COW Pump Dischg Hdr Sect Valve, 3-7870

• COW Pump Suct Hdr Sect Valve, 3-787A

• COW Sys Demin Water Primary Water Supply, 3-7370 17 Check CCW Pump Operation Start either 3B or 30 COW Pump.

a. Either 3B or 30 COW Pump running 18 Check If Components Supplied By The B Go to Step 23.

Header Should Be Shut Down Header B Flow, Fl-3-613B NO FLOW OR Local Header B Surge Tank Level, Ll-3-61 5

- EMPTY OR Local Header B Surge Tank Level, Ll-3-61 5

- DECREASING IN AN UNCONTROLLED MANNER W97/nw/mr/nw

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3-ONOP-030 Component Cooling Water Malfunction 3/25/11 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED a a a a a i

I The remainder of this procedure shall be performed concurrently with E- REACTOR I TRIP OR SAFETY INJECTION, and any other applicable Emergency Operating i Procedures.

a a a a I 19 Shut Down Components Cooled By The B Component Cooling Water Header

a. Manually trip the reactor

b. Place the following in Pull-To-Lock or Off

• All RCPs

• 3BRHRPump

• 3B Containment Spray Pump 3B Emergency Containment Cooler

• 3C Emergency Containment Cooler

c. Check component cooling water to Unit 3 c. Go to Step 20, High-Head SI pumps ALIGNED TO UNIT 3

d. Place the following in Pull-To-Lock

• 3A High-Head SI pump

• 3B High-Head SI pump

e. Realign Unit 3 High-Head SI pumps component cooling water to Unit 4 per 3-NOP-030

f. WHEN the Unit 3 High-Head SI pumps have been realigned to Unit 4, THEN place the Unit 3 High-Head SI pumps back in AUTO 20 Check The Following Valves Closed

a. HCV-3-1 37, Excess Letdown Flow a. Close HCV-3-1 37.

Controller

b. CV-3-387, Excess Letdown Heat b. WHEN HCV-3-137 has been closed for Exchanger Isolation Valve From Cold Leg iOUt5 II1P ciose - -

To Excess Letdown 21 Check If Components Supplied By Cask Go to Step 23.

Handling Facility Piping Should Be Isolated

• Check component cooling water Cask Handling Facility piping ALIGNED TO THE B HEADER PRIOR TO COMPONENT COOLING WATER MALFUNCTION W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 3/25/11 f STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION Operation of the Charging Pump without cooling at less than maximum speed will result in excessive coupling oil temperatures. These temperatures may exceed the design limits within 20 seconds at half load. At maximum speed, temperature limits are expected to remain within specificatIon limits indefinitely.

22 Isolate Components Supplied By Cask Handling Facility Piping

a. Close all letdown orifice isolation valves

b. Close High Pressure Letdown Isolation From Loop B Cold Leg, LCV-3-460

c. Increase charging flow to maximum on one pump

d. Start and stop charging pump at maximum speed as necessary to maintain Pressurizer level and RCP seal temperatures

e. Dispatch operator to establish emergency cooling water to desired charging pumps using ATTACHMENT I

f. WHEN cooling water established to charging pump, THEN operate the pump as necessary to maintain Pressurizer level and RCP seal cooling

g. Verify Cask Handling Facility component g. Dispatch operator to close the following:

cooling water piping !iI LEAKING

1) Both CCW Header Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.

• 3-835E

• 3-835F

2) Both CCW Header Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.

• 3-835G

• 3-835H 23 Check If Components Supplied By The A Go to Step 27.

Header Should Be Shut Down Header A Flow, Fl-3-61 3A NO FLOW OR Header A Surge Tank Level, Ll-3-61 3A

- EMPTY OR Header A Surge Tank Level, LI-3-6l3A

- DECREASING IN AN UNCONTROLLED MANNER W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

24 Shut Down Components Cooled By The A Component Cooling Water Header

a. Place the following in Pull-To-Lock or Off 3ARHRPump 3A Containment Spray Pump 3A Emergency Containment Cooler

b. Check component cooling water to Unit 4 b. GotoStep25.

High-Head SI pumps ALIGNED TO UNIT 3

c. Place the following pump in Pull-To-Lock

• 4A High-Head SI Pump

• 4B High-Head SI pump

d. Realign Unit 4 High-Head SI pump component cooling water to Unit 4 using Section 5.4 of 4-NOP-030, COMPONENT COOLING WATER SYSTEM

e. WHEN the Unit 4 High-Head SI pumps have be realigned to Unit 4 component cooling water, THEN place the Unit 4 High-Head SI pumps back in AUTO 25 Check If Components Supplied By Cask Go to Step 27.

Handling Facility Piping Should Be Isolated Check component cooling water Cask Handling Facility piping ALIGNED TO THE A HEADER PRIOR TO COMPONENT COOLING WATER MALFUNCTION W97/nw/mr/nw

Procedure No.: Procedure

Title:

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16 Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 3/25/11 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION Operation of the Charging Pump without cooling at less than maximum speed will result in excessive coupling oil temperatures. These temperatures may exceed the design limits within 20 seconds at half load. At maximum speed, temperature limits are expected to remain within specification limits indefinitely.

26 Isolate Components Supplied By Cask Handling Facility Piping

a. Close all letdown orifice isolation valves

b. Close High Pressure Letdown Isolation From Loop B Cold Leg, LCV-3-460

c. Increase charging flow to maximum on one pump

d. Start and stop charging pump at maximum speed as necessary to maintain Pressurizer level and RCP seal temperatures

e. Dispatch operator to establish emergency cooling water to desired charging pumps using ATTACHMENT 1

f. WHEN cooling water established to a charging pump, THEN operate the pump as necessary to maintain Pressurizer level and RCP seal cooling

g. Verify Cask Handling Facility component g. Dispatch operator to close the following:

cooling water piping NOT LEAKING

1) Both CCW Header Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.

• 3-835E

• 3-835F

2) Both CCW Header Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx.

• 3-835G

• 3-835H W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 27 Check If Headers Are Leaking

a. Locally check Header B Surge Tank Level, a. Go to Step 27d.

LI-3-61 5 LEVEL ABOVE BOTTOM OF SIGHTGLASS

b. Stop makeup to the B header

c. Check header B surge tank level - c. jf header B is intact, THEN go to DECREASING Step 34.

d. Check Header A Surge Tank Level, d. Go to Step 28.

LI.-3-61 3A GREATER THAN 0%

e. Stop makeup to the A header

f. Check Header A Surge Tank Level - f. j header A is intact, THEN observe DECREASING CAUTION and NOTE prior to Step 29 and go to Step 29.

28 Try To Establish One Intact Component Cooling Water Header

a. Continue efforts to locate and isolate Component Cooling Water System leakage

b. Continue adding makeup to intact portions of the Component Cooling Water System

c. Return to Step 9 W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page: -

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 3/25/11 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION Transferring components to the A header may cause surge tank level to decrease rapidly.

NOTE Steps 29 through 33 are only applicable when the B CCW header is not intact.

29 Transfer Components Supplied By Cask Handling Facility Piping To The A Header

a. Verify Cask Handling Facility piping - a. Go to Step 30.

INTACT

b. GotoStep3o.

b. Isolate Cask Handling Facility piping from the B header

1) Close CCW Header B Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835H

2) Close CCW Header B Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835E

c. Align Cask Handling Facility piping to the A header

1) Open CCW Header A Supply To Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835F

2) Open CCW Header A Return From Charging Pumps, Spent Fuel Pit Hx, Non-Regen Hx, And Seal Water Hx, 3-835G W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page: -

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

30 Transfer 3C Emergency Containment Cooler To The A Header

a. Isolate 3C Emergency Containment Cooler a. Go to Step 31.

from the B header

1) Close Emergency Cooler C Tie To CCW Header B, 3-652

2) Close CCW Header B Tie To Emergency Containment Cooler C, 3-650

b. Align 3C Emergency Containment Cooler to the A header

1) Open CCW Header A Tie To Emergency Containment Cooler C, 3-651

2) Open Emergency Cooler C Tie To CCW Header A, 3-653 31 Transfer Components To The A Header

a. Isolate components from the B header a. Go to Step 32.

1) Close CCW Return Header B Isolation, 3-835B

2) Close CCW Header B Supply To RCP, Containment Coolers, Rod Drive Coolers, Primary Shield, Excess Letdown Hx, Evaporator Coolers, And Sample Coolers, 3-835C

b. Align components to the A header

1) Open CCWHeaderASupplyTo RCP, Containment Coolers, Rod Drive Coolers, Primary Shield, Excess Letdown Hx, Evaporator Coolers, And Sample Coolers, 3-835D

2) Open CCW Return Header A Isolation, 3-835A W97/nw/mr/nw

Procedure No. Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

32 Isolate CCW Pump B From The B Header

a. Place CCW pump C in Pull-To-Lock

b. Check CCW pump B ALIGNED TO

- b. IF COW pump B is already aligned to HEADER B header A, THEN go to Step 34.

c. Place COW pump B in Pull-To-Lock

d. Locally isolate COW pump B from the B d. IF COW pump B can jI be isolated header from the B header, THEN perform the following:

1) Locally close at least one Component Cooling Water Heat Exchanger Outlet a) Locally verify at least one Header Sectionalizing valve Component Cooling Water Heat Exchanger Outlet Header 3-787G Sectionalizing valves CLOSED:

3-787H

• 3-787E

2) Locally close COW pump Discharge

• 3-787F Header Sectionalizing Valve, 3-787D b) Locally verify COW pump Discharge

3) Locally close COW pump Suction Header Sectionalizing Valve, Header Sectionalizing Valve, 3-787B 3-7870 CLOSED c) Locally verify CCW pump Suction Header Sectionalizing Valve, 3-787A

- CLOSED d) GotoStep34.

33 Align CCW Pump B To The A Header

a. Locally open both Component Cooling Water Heat Exchanger Outlet Header Sectionalizing valves

• 3-787E

• 3-787F

b. Locally open COW Pump Discharge Header Sectionalizing Valve, 3-7870

c. Locally open CCW Pump Suction Header Sectionalizing Valve, 3-787A

d. Check flow on the A header d. Start the CCW Pump B W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

34 Verify Component Cooling Water From Unit 4- NOT REQUIRED

a. Unit 3 CCW headers filled and intact a. ReturntoStep4.

b. Verify CCW pumps AT LEAST ONE

b. Start a Standby COW pump.

RUNNING

c. Verify flow in at least one intact CCW c. Perform the following:

header

1) Try to establish flow in at least one Fl-3-61 3A for header A intact CCW header.

Fl-3-613B for header B 2) IF flow in at least one intact CCW header can NOT be established, THEN observe NOTE prior to Step 36 and go to Step 36.

d. Verify intake cooling water flow to all in d. Perform the following:

service CCW heat exchangers

1) Try to establish intake cooling water Fl-3-l4O7forHxA flow to in-service CCW heat exchangers.

FI-3-1 408 for Hx B

2) Stop components cooled by FI-3-1 409 for Hx C component cooling water as necessary to stabilize component cooling water temperature.

3) IF any component cooled by component cooling water must be operated AND stable component cooling water temperature can Q]

be maintained, THEN observe NOTE prior to Step 36 and go to Step 36.

35 Observe CAUTION Prior To Step 43 And Go To Step 43 W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

= a a a a a Steps 36 through 42 are only applicable when component cooling water from Unit 4 is required and the Unit 3 CCW Headers are intact and filled.

a a _

36 Prepare To Establish CCW Flow From Unit 4

a. Obtain permission from Shift Manager to a. DO NOT CROSS-CONNECT CCW cross-connect Unit 3 and Unit 4 component SYSTEMS. Observe CAUTION prior to cooling water systems Step 43 and go to Step 43.

b. Verify Unit 4 component cooling water b. Direct Unit 4 Reactor Operator to headers TIED TOGETHER

- perform the following:

1) Stop spent fuel transfer in Unit 4 Cask Handling Facility.

2) Tie Unit 4 component cooling water headers together using 4-NOP-030, COMPONENT COOLING WATER SYSTEM.

c. Verify Unit 4 CCW pumps AT LEAST

- c. Direct Unit 4 Reactor Operator to start TWO RUNNING CCW pumps as necessary to establish two Unit 4 CCW pumps running.

d. Verify Unit 4 CCW Heat Exchangers ALL - d. Direct personnel to restore out-of IN SERVICE service CCW Heat Exchanger to service.

e. Direct Unit 4 Reactor Operator to start intake cooling water pumps as necessary to establish at least two Unit 4 intake cooling water pumps running

f. Direct Unit 4 Reactor Operator to closely monitor Unit 4 CCW System

g. Locally verify the following valves OPEN

• 3-789A, PASS Gas Compressors And Boric Acid Evaporator CCW Supply

• 3-789B, PASS Gas Compressors And Boric Acid Evaporator CCW Outlet

• 4-789A, PASS Gas Compressors And Boric Acid Evaporator CCW Supply

• 4-789B, PASS Gas Compressors And Boric Acid Evaporator CCW Outlet W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED Unit 3 cow surge tanks are isolated to prevent loss of Unit 4 component cooling water through Unit 3 surge tank vent lines when the COW Systems are cross-connected.

a a a I 37 Isolate Unit 3 CCW Surge Tank

a. Locally check Component Cooling Water a. Locally close 3-71 1A.

Header A Makeup Water Isolation, 3-71 IA -

CLOSED

b. Locally close the following valves

• 3-71 OA, CCW Header A Surge Tank Isolation

• 3-710B, COW Header B Surge Tank Isolation 38 Establish CCW Flow From Unit 4

a. Locally unlock both Unit 3- Unit 4 COW Tie Between Boric Acid Evaporator And Waste Gas Compressor valves

• 779A

• 779B

b. Direct Unit 4 Reactor Operator to locally open both CCW Header Makeup Isolation Valves

• 4-711A

• 4-711B

c. Stop all Unit 3 CCW pumps

d. Locally throttle open Unit 3 Unit 4 CCW Tie Between Boric Acid Evaporator And Waste Gas Compressors (Inlet), 779A 39 Maintain Stable Unit 4 CCW Inventory Direct Unit 4 Reactor Operator to add makeup as necessary to stabilize Unit 4

• Ll-4-614A Stable CCW System inventory using one or both of the following:

• Ll-4-61 3A Stable Open component Cooling Water Surge Tank Makeup, MOV-4-832.

Locally throttle Demin Water Supply Valve, 4-724D.

W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED 1 a a a a a a a The top of the component cooling water surge tank divider plate is located at approximately 25% indicated level.

a a a a a a a I 40 Maintain Unit 4 Surge Tank Level, Ll-4-613A Perform the following:

- GREATER THAN 25%

a. Locally close both Unit 3 Unit 4 CCW Tie Between Boric Acid Evaporator And Waste Gas Compressor valves

• 779A

• 779B

b. Determine and try to correct cause for Unit 4 CCW System level decrease.

c. if the cause for Unit 4 CCW System level decrease can be corrected, THEN return to Step 38.

d. if the cause for Unit 4 CCW System level decrease can NOT be corrected, THEN perform the following:

1) Locally open the following valves:

• 3-710A, CCWHeaderA Surge Tank Isolation

• 3-710B, CCW Header B Surge Tank Isolation

2) Restart any previously running Unit 3 CCW pumps.

3) Locally lock both Unit 3 Unit 4 CCW Tie Between Boric Acid Evaporator And Waste Gas Compressor valves

• 779A

• 779B

4) WHEN makeup to Unit 4 CCW System is no longer required, THEN direct Unit 4 Reactor Operator to locally close CCW Header Makeup Isolation Valve, 4-71 IA

5) GotoStep43.

W97/nw/mr/nw

STEP AC11ON/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 1

41 Fully Open Both Unit 3 Unit 4 CCW Tie Between Boric Acid Evaporator And Waste Gas Compressor Valves

• 779A

• 779B 42 Maintain Unit 4 Component Cooling Water Temperatures

a. Check Unit 4 Component Cooling Water a. Stop Unit 3 and Unit 4 components as Supply Header Temperature LESS THAN

- necessary to reduce heat load on Unit 4 120°F Component Cooling Water System.

• TI-4-607A

• TT-4-607B W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 10/12/10 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

CAUTION If component cooling water to any component has been lost and can not be restored, that component shall be maintained in Pull-To-Lock or Off to prevent equipment damage.

43 Verify Component Cooling Water Is Being Perform the following:

Supplied To The Following Components

a. Verify headers are not leaking, THEN

• High-head SI pumps locally align valves as necessary to establish component cooling water flow

• RHR pumps to each component. Refer to 3-NOP-030, COMPONENT COOLING

• Containment spray pumps WATER SYSTEM, for proper valve alignment.

• Emergency containment coolers b. ffl component cooling water can .QI be established to any component, THEN perform the following:

1) Place the affected components in Pull-To-Lock or Off.

2) DO NOT START AFFECTED COMPONENTS in subsequent steps.

3) DO NOT PLACE AFFECTED COMPONENTS IN STANDBY in subsequent steps.

44 Verify Proper Component Alignment

a. Restart previously running components High-head SI pumps RHR pumps Containment spray pumps Emergency containment coolers

b. Place idle components in standby High-head SI pumps RHR pumps Containment spray pumps Emergency containment coolers W97/nw/mr/nw

TST1 I ACTIONIEXPECTED RESPONSE I [ESPONSE NOT OBTAINED I

45 Establish Charging Flow

a. Locally verify component cooling water flow a. Verify emergency cooling water has from charging pumps, FI-3-660 been established to desired charging pump using Attachment 1.

b. Check charging pumps AT LEAST ONE

- b. LE any charging pumps were running RUNNING prior to component cooling water malfunction, THEN start one charging pump.

c. Maintain minimum charging flow for RCP seal injection 46 Verify CCW To RCPs AVAILABLE

- Perform the following:

a. Verify component cooling water to RCPs - 1. Verify reactor TRIPPED AVAILABLE

2. Verify all RCPs STOPPED

b. Verify CCW Inlet valves OPEN

3. Close RCP Thermal Barrier CCW Outlet,

• MOV-3-71 6A MOV-3-626.

• MOV-3-716B 4. Adjust charging flow and Charging Flow to Regen Heat Exchanger, HCV-3-121, to maintain thermal barrier AP greater than 0 inches of water.

5. Verify natural circulation.

6. GotoStep49.

47 Verify RCP Bearing CCW Outlet, MOV-3-730 Perform the following:

- OPEN

a. Verify reactor TRIPPED

b. Verify all RCPs STOPPED

c. Verify natural circulation.

48 Verify RCP Thermal Barrier CCW Outlet, Adjust charging flow and Charging Flow to MOV-3-626 -OPEN Regen Heat Exchanger, HCV-3-121, to maintain thermal barrier DP greater than 0 inches of water.

W97/nw/mr/nw

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTMNED 49 Verify Containment Cooling

a. Check normal containment coolers a. GotoStep5O.

RUNNING

b. Establish normal containment cooling b. Consult with Shift Manager to determine if one of the following methods should

1) Verify component cooling water to be used to cool containment:

normal containment coolers -

AVAILABLE

• Emergency containment coolers.

2) Verify Component Cooling Water To OR Normal Containment Cooler valve -

OPEN

• Containment purge.

• MOV-3-1417

• MOV-3-1418 50 Maintain Reactor Coolant System Circulation

a. Check RCPs ALL STOPPED

- a. GotoStep5l.

b. Obtain permission from Plant Manager to b. Perform the following:

start RCPs

1) Verify natural circulation.

2) GotoStep5l.

c. Start RCPs as desired using 3-NOP-041 .O1A, 3A REACTOR COOLANT PUMP OPERATIONS; 3-NOP-041 .01 B, 3B REACTOR COOLANT PUMP OPERATIONS; and 3-NOP-041 .01 C, 3C REACTOR COOLANT PUMP OPERATIONS, as appropriate 51 Check If Letdown Or Excess Letdown Go to Step 53.

Should Be Placed In Service

a. Charging pumps AT LEAST ONE RUNNING

b. Letdown OR excess letdown IN SERVICE PRIOR TO COMPONENT COOLING WATER MALFUNCTION

c. Letdown AND excess letdown SECURED W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 19/12/10 STEP ACTIONIEXPECTED RESPONSE j RESPONSE NOT OBTAINED I

52 Establish Letdown Establish excess letdown

a. Verify letdown orifice isolation valves - 1. Verify Excess Letdown Heat Exchanger CLOSED CCW Outlet, CV-3-739, OPEN.

b. Place L/D Temp Controller, TC-3-144A, in 2. Verify Excess Letdown Flow Controller, MANUAL and control letdown temperature HCV-3-1 37 CLOSED.

manually

3. Verify Excess Letdown Isolation Valve

c. Open Letdown From Regen Heat CV-3-387 CLOSED.

Exchanger Isolation, CV-3-204

4. Locally verify Component Cooling Water

d. Open High Pressure Letdown Isolation Flow From Excess Letdown Heat From Loop B Cold Leg, LCV-3-460 Exchanger, Fl-3-624. IF flow is NOT available, THEN go to Step 53.

e. Manually control Low Pressure Letdown 5. Verify Excess Letdown From Heat Controller, PCV-3-145, to limit pressure Exchanger to VCT Or RCDT CV-3-389 spike when opening letdown orifice is in the desired position:

isolation valves RCDT Divert

f. Open letdown orifice isolation valves to establish desired letdown flow OR

g. Place Low Pressure Letdown Controller,

• VCT Normal PCV-3-145, in Automatic

6. Slowly open Excess Letdown Flow

h. Place Charging pump controls in Automatic Control Valve, HCV-3-1 37.

to maintain Pressurizer level

7. Close Excess Letdown Flow Control

i. WHEN letdown temperature is 115°F to Valve, HCV-3-137.

121°F and stable, THEN place TC-3-144A in AUTO 8. Open Excess Letdown Heat Exchanger Isolation Valve From Cold Leg To Excess Letdown, CV-3-387.

9. Open Excess Letdown Flow Controller, HCV-3-1 37.

10. Verify Excess Letdown Heat Exchanger Outlet Temperature, Tl-3-1 39 less than 190°F.

11. if volume control tank temperature increases to greater than 130°F, THEN place Excess Letdown From Heat Exchanger To VCT Or RCDT, CV-3-389, in RCDT Divert position.

12. Continue efforts to establish normal letdown. WHEN normal letdown has been established, THEN stop excess letdown. Continue with Step 53.

W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 10/12/10 STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

53 Locally Verify Component Cooling Water Perform the following:

Flow From Seal Water Heat Exchanger, Fl-3-618 a. Place Excess Letdown From Heat Exchanger To VCT Or RCDT, CV-3-389, in RCDT Divert position.

b. Close Excess Letdown And RCP Seal Return To VCT, MOV-3-381.

54 Locally Verify Component Cooling Water Perform the following:

Flow From Spent Fuel Pool Heat Exchanger, Fl-3-622 a. Monitor spent fuel pool temperatures.

b. Add makeup as necessary to maintain spent fuel pool level greater than 7 inches below normal level of 57 feet.

55 Direct Shift Manager To Evaluate Plant Conditions

a. Check for applicability to conditions listed in O-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR

b. Verify applicable Technical Specification b. Perform applicable Technical Limiting Conditions for Operation - Specification corrective actions.

SATISFI ED 56 Verify Component Cooling Water System - Perform the following:

ALIGNED FOR NORMAL OPERATIONS

a. WHEN normal system operation is possible, THEN realign the system using 3-NOP-030, COMPONENT COOLING WATER SYSTEM.

b. IF component cooling water is being supplied by Unit 4, THEN place both units in cold shutdown as soon as possible.

57 Go To Appropriate Plant Procedure As Determined By The Shift Manager END OF TEXT W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

31 Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 ATTACHMENT 1 (Page 1 of 5)

CONTROL OF EMERGENCY COOLING WATER TO CHARGING PUMPS NOTES Emergency cooling water SUPPLY hose has a quick disconnect fitting on one end and a cam lock fitting on the other end.

• Loss of off-site power in coincidence with a loss of CCW will require the diesel driven seivice water pump to be in service in order to provide emergency cooling water to the charging pumps.

Connect cam lock fitting end of emergency cooling water supply hose to Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179A.

2. Consult with Unit 3 Reactor Operator to determine desired charging pump.

3. Verify desired charging pump is stopped j running at maximum speed.

4. Connect quick disconnect fitting end of emergency cooling water supply hose to emergency hose connection on desired charging pump.

a. Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-291 OR

b. Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-289 OR

c. Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-299 i NOTE I Emergency cooling water OUTLET hose has a quick disconnect fitting on one end and no I i fittingontheotherend.

C S a I

5. Connect quick disconnect fitting end of emergency cooling water outlet hose to emergency hose connection on desired charging pump.

a. Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-290 OR

b. Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-288 OR

c. Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-298 W97/nw/mr/nw

ATTACHMENT 1 (Page 2 of 5)

CONTROL OF EMERGENCY COOLING WATER TO CHARGING PUMPS

6. Remove cover from floor drain to be used in Charging Pump Room.

7. Route open end of emergency cooling water outlet hose to floor drain being used in Charging Pump Room.

8. Isolate CCW to hydraulic oil cooler on desired charging pump:

a. Close CCW to A Charging Pump Oil Cooler Inlet, 3-825A OR

b. Close CCW to B Charging Pump Oil Cooler Inlet, 3-825 C OR

c. Close CCW to C Charging Pump Oil Cooler Inlet, 3-825E

9. Isolate CCW from hydraulic oil cooler on desired charging pump:

a. Close CCW from A Charging Pump Oil Cooler Inlet, 3-825B OR

b. Close CCW from B Charging Pump Oil Cooler Inlet, 3-825D OR

c. Close CCW from C Charging Pump Oil Cooler Inlet, 3-825F

10. Open Service Water Connection Inside Unit 3 Charging Pump Room Root Valve, 3-70-179.

11. Open Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179A.

12. Establish service water to desired Charging Pump:

a. Open Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-29 1 OR

b. Open Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-289 OR

c. Open Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-299 W97/nw/mrlriw

ATTACHMENT 1 (Page 3 of 5)

CONTROL OF EMERGENCY COOLING WATER TO CHARGING PUMPS

13. Adjust service water flow from desired charging pump to provide maximum flow.

a. Open Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-290 OR

b. Open Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-288 OR

c. Open Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-298

14. IF service water flow is not obtained, THEN have the Service Water System placed in service using 0-NOP-012, SERVICE WATER SYSTEM, using any available pump including the diesel driven SWP D.

15. Notify Unit 3 Reactor Operator that emergency cooling water has been established to desired charging pump.

NOTE I Maximum charging pump oil temperature is 220°F to prevent oil break down. The installed temperature indicators only indicate up to 200°F. Some indicators are located on the I cooler inlet and others on the cooler outlet. Maximum expected L T across the cooler is 20°F. At 195°F on the cooler outlet (oil to the hydraulic coupling), this would equate to 2 15°F on the cooler inlet (oil from the hydraulic coupling). I I

16. Monitor oil temperatures on running charging pump.

17. IF hydraulic coupling oil temperature on running charging pump exceeds 195°F, THEN perform the following:

a. Notify Unit 3 Reactor Operator that operating charging pump should be stopped.

b. Consult with Unit 3 Reactor Operator to determine if emergency cooling water should be realigned to a different charging pump.

c. j[ Unit 3 Reactor Operator determines that emergency cooling water must be realigned to a different charging pump, THEN go to Step 20 of this attachment.

18. Unit 3 Reactor Operator determines that emergency cooling water to charging pumps is no longer required, THEN go to Step 20 of this attachment.

19. Return to Step 16 of this attachment.

20. Verify charging pump being supplied with emergency cooling water is stopped.

W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

34-Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 11/28/07 ATTACHMENT 1 (Page 4 of 5)

CONTROL OF EMERGENCY COOLING WATER TO CHARGING PUMPS

21. Isolate emergency cooling water flow from previously running charging pump:

a. Close Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-290 OR

b. Close Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-288 OR

c. Close Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-298

22. Isolate emergency cooling water flow to previously running charging pump:

a. Close Emergency Hose Connection to Charging Pump A Oil Cooler, 3-10-29 1 OR

b. Close Emergency Hose Connection to Charging Pump B Oil Cooler, 3-10-289 OR

c. Close Emergency Hose Connection to Charging Pump C Oil Cooler, 3-10-299

23. Reestablish CCW to hydraulic oil cooler on previously running charging pump:

a. Open CCW to A Charging Pump Oil Cooler Inlet, 3-825A OR

b. Open CCW to B Charging Pump Oil Cooler Inlet, 3-825C OR

c. Open CCW to C Charging Pump Oil Cooler Inlet, 3-825E W97/nw/mr/nw

ATTACHMENT 1 (Page 5 of 5)

CONTROL OF EMERGENCY COOLING WATER TO CHARGING PUMPS

24. Reestablish CCW from hydraulic oil cooler on previously running charging pump.

a. Open CCW from A Charging Pump Oil Cooler Inlet, 3-825B OR

b. Open CCW from B Charging Pump Oil Cooler Inlet, 3-825D OR

c. Open CCW from C Charging Pump Oil Cooler Inlet, 3825F

25. Disconnect emergency cooling water outlet hose from previously running charging pump.

26. Close Service Water Connection Inside Unit 3 Charging Pump Room Root Valve, 3-7O179.

27. Close Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179A.

28. Disconnect emergency cooling water supply hose from previously running charging pump.

29. IF emergency cooling water must be realigned to a different charging pump, THEN return to Step 2.

30. Disconnect emergency cooling water supply hose from Service Water Connection Inside Unit 3 Charging Pump Room, 3-70-179A.

31. Return emergency cooling water supply and outlet hoses to their designated storage locations.

32. Replace cover on floor drain used for emergency cooling water.

33. Notifi Unit 3 Reactor Operator that emergency cooling water alignment has been terminated.

FINAL PAGE W97/nw/mr/nw

Procedure No.: Procedure

Title:

Page:

Fokiout Approval Date:

3-ONOP-030 Component Cooling Water Malfunction 10/12/10 FOLDOUT FOR 3-ONOP-030 TOTAL LOSS OF CCW FLOW A. Manually trip the reactor, verify reactor trip using the EOP network, THEN stop the RCPs.

B. Isolate letdown and excess letdown.

C. Establish one charging pump running at maximum speed AND dispatch operator to establish emergency cooling water to one of the remaining two charging pumps using Attachment 1. Monitor RCS pressure closely while running charging pump at maximum speed.

D. WhEN Attachment 1 is complete, THEN operate charging pump supplied with emergency cooling as necessary to maintain RCP seal cooling.

2. LOSS OF CCW TO ANY COMPONENT j component cooling water flow to any component cooled by CCW is lost, THEN shut down the affected component.

3. CHARGING PUMP EMERGENCY COOLING CRITERIA IF Cooling Water is NOT available to charging pumps, THEN charging pump operation shall be at maximum speed until cooling is restored from CCW System or using Attachment 1.

4. CCW PUMP STOPPING CRITERIA IF any Component Cooling Water Pump is cavitating, THEN stop the affected Component Cooling Water Pumps and place in Pull-To-Lock.

5. REACTOR TRIP CRITERIA IF tripping a RCP is required, THEN manually trip the reactor prior to stopping the RCP.

6. RCP STOPPING CRITERIA any RCP bearing temperature annunciator alarm actuates AND its associated motor bearing temperature is greater than 195°F, THEN trip reactor and stop the affected RCPs.

7. CCW System operation once CCW System Hdr has been restored shall be within the operating restrictions of 3-NOP-030 summarized as follows: [Commitment Step 3.3.2]

CCW Pumps, Heat Exchangers, and Flows/Loads.

• N-i CCW Pumps (where N number of CCW Hxs aligned to CCW)

• All CCW Hxs in service when RHR in service OR with only 2 CCW Hxs in service, place 2 CCW Pumps in Pull-To-Lock.

• Maximum of 5 out of 6 CCW Heat Loads.

W97/nw/mr/nw

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 UNIT4.

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.

2011 NRC Exam (RO & SRO) JPM-i NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 10 Form ES-C-I Taslcstandard:

• Reactor is Tripped by locally opening the Unit 4A and 48 Reactor Trip and Bypass Breakers in the 4B MCC room (Time Critical).

• Unit 4A and Unit 4B Rod Drive Motor Generator set input and output breakers are opened locally in the 4B MCC room.

o Main Turbine is tripped from the Front Standard.

Required Materials:

• 4-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS, Step 7.

General

References:

o 4-EQ P-FR-S. 1, Response to Nuclear Power Generation/A TWS Time Critical Task: Yes 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 (i4 Start Time SAT STEP I Obtain required reference materials.

UNSAT STANDARD Applicant obtains a copy of 4-EOP-FR-S. I Response to Nuclear Power Generation/A 714S.

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 RTB5, 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.

TIME STOP for Time Critical action_____________

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

. 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

,j 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 (RD & 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:

. 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 ESC-1 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

Result: 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 wiN be satisfied.

Initial Conditions:

o 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.

• 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

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:

• 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.

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 []ACTION/EXPECTED RESPONSE fl 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 NB 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 GOBs OPEN (Normally c. Perform the following:

30 seconds delay)

1) Manually open breakers.

2) ffl breakers do QI open THEN actuate Emergency Gen Bkr Trip Switch for the affected breaker(s).

3) IF breaker position indication is QI available AND 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 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 Al .01 RO 3.7 SRO 4.1 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:

• Unit3isatl00%.

• Containment Pressure is -1.5 psig and must be increased.

The R-1 1, R-l 2 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 (R0&SRO) 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:

o 3-NOP-094, Containment Post Accident Monitoring System.

General

References:

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

Page 3 of 13 Form ES-C-I dixC te critical steps with a check mark (j Start Time SAT STEP I Obtain the required reference materials. UNSAT App!icant obtains a copy of 3-NO P-094, Containment Post STANDARD 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 and 3 OR Step 4 Evaluator Note: Student will perform either Steps 2 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 J DISCHARGE TO RADWASTE BUILDING.

(3-NOP-094, 5.3.1.A.(1) the Unit Applicant locates the floor cap for MPAS-OO1 outside of coun ter-c lock wise STANDARD 3A BA Evaporator Room. Rotates the cap until it is off, and then sets it aside.

after Applicant describes obtaining the tools from the wall operators.

unlocking them with the key, normally maintained by CUE tually Inform the Applicant that the cap rotates freely and even comes loose.

COMMENT NUREG 1021 Rev 9 2011 NRC Exam (RO&SRO) JPM-j Appendix C

Appendix C Page 4 of 13 Form ES-C-I NOTE NOTE Full travel for valve is provided in parentheses. Turning these valves beyond ful[ travel may damage the reach rod assemblies.

CLOSE MPAS-001, WHT PUMP DISCHARGE TO RADWASTE SAT STEP 3 BUILDING (1/4 turn).

UNSAT q

(3-NOP-094, 5.3.1.A.(2)

Applicant rotates the reach-rod operator for MPAS-001 STANDARD clockwise % turn.

CUE Inform the Applicant that the valve operator rotates freely.

COMMENT EVALUATOR NOTE:

NOTE Because MPAS-001 (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&SRO) 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 q

(3-NOP-094, 5.3.1B.)

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&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 13 Form ES-C-I On the Auxiliary Building roof near the Unit 3 containment wall SAT PERFORM the following:

UNSAT STEP 5 UNLOCK and OPEN MPAS-3-004, CONTAINMENT PURGE 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.

/ (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&SRO) JPM-j NUREG 1021 Rev9 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 STANDARD Fan Room and removes the red hose with the tag labeled for UNIT 3 CONTAINMENT VENT ALTERNATE AIR SUPPLY HOSE.

EVALUATOR CUE:

Red Hose with Tan identification tag marked with procedure CUE reference 3-ONOP-094.4 (3-ONOP-094 has been replaced with 3-NOP-094). Cue student if necessary that this hose has been verified as the correct hose iaw 3-NOP-094.

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 (R0&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 13 Form ES-C-I CONNECT Containment Vent Alternate Air Supply Hose to valve SAT 40-946, INST AIR TO N-S HALLWAY HOSE CONN STEP 9 ISOLATION. UNSAT I

(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-11, 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 (R0&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 9 of 13 Form ES-C-I 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 (R0&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 13 Form ES-C-I ENSURE 3-11-030, CNMT RAD MON R-3-11 & 12 GRAB SAT SAMPLE SPLY ISOL VLV, is LOCKED CLOSED.

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 SAT Supply Hose to 3-11-035, PACV ALTERNATE AIR STEP 13 UNSAT_____

PRESSURIZER valve.

J (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 (R0&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 11 of 13 Form ES-C-I OPEN 3-11-035, PACV ALTERNATE AIR PRESSURIZER SAT STEP 14 valve.

UNSAT q

(3-NOP-094, 5.3.H.)

Applicant locates 3-11-035 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 (RO&SRO) JPM-j NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 13 Form ES-C-I Venfication of Completiow -

Job Performance Measure No. 01053002101 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 (R0&SRO) JPM-j 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:

• 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&SRO) JPM-j 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:

• Unit3isatlO0%.

• 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 I-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 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 Brian Stamp 12/08/10 DOCN 3-NOP-094 SYS STATUS COMPLETED REV o

1. OFPGS

REVISION NO.: PROCEDURE TITLE: PAGE:

0 CONTAINMENT POST ACCIDENT 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 (SAM G).

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 POST ACCIDENT 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-001, 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-001, WHT PUMP DISCHARGE TO RADWASTE BUILDING (1/4 turn).

B. At the Waste Evaporator Feed Pump Room in the Radwaste BIdg, CLOSE valve 1731, WHT TO 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.

D. ENSURE R-1 1, 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 58 3-NO P-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, SQL VLV FOR CNTMT AIR MONIT INLET ISOL, is CLOSED.

7. PLACE SV-3-291 1, SQL VLV FOR CNTMT AIR MONIT INLET, hand switch to OPEN.

8. CHECK SV-3-2912, SOL VLV FOR CNTMT AIR MONIT 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 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 Unit 3 and Unit 4 are operating at 100%

• A loss of Instrument Air is in progress.

o 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:

o The US has directed you to check the operation of the Instrument Air Dryers per 0-ONOP-013, Loss of Instrument Air, starting with step 8.

2011 NRC Exam (RO) JPM-k

Appendix C Page 2 of 9 Form ES-C-I Task Standard:

• The Instrument Air Dryers have been aligned per 0-ONOP-Ol 3, Loss of Instrument Air, Steps 8 and 9.

Required Materials:

• 0-ONOP-0 13, Loss of Instrument Air General

References:

Time Critical Task: No Validation Time: 10 minutes 2011 NRC Exam (RO) 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 (1) Start Time SAT STEP I Obtain the required reference materials.

UNSAT STANDARD Applicant obtains a copy of O-ONOP-013, Loss of Instrument Air.

Provide Applicant with a copy of 0-ONOP-Ol 3, Loss of Instrument CUE Air.

COMMENT Check Locally That The Instrument Air Dryers Properly Aligned SAT STEP 2 And NOT Purging Excessively.

UNSAT STANDARD Applicant determines from the Initial C?nditions that the Unit 3 Instrument Air Dryer is purging excessively.

Inform Applicant that the dryer is purging excessively.

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

Appendix C Page 4 of 9 Form. ES-C-I JAlign the Instrument Air Dryers In accordance with 314-NOP-013.

SAT STEP 3 UNSAT (0-ONOP-013, RNO Step 8)

STANDARD Applicant notes from the Initial Conditions that the IA System is in a normal alignment.

CUE Inform Applicant that the l.A. Dryers are in a normal alignment per 3/4-NOP-013.

COMMENT IF air dryer is excessively purging, THEN CLOSE the associated purge exhaust block valve: SAT UNSAT STEP 4 U-3 (3T9): 3-40-380 J 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 longer rotates.

CUE Inform Applicant that 3-40-380 rotates freely in the clockwise 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) JPM-k NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 9 Form ES-C-I I

I IAS-3-O2 and i4S4-O12 th be cpaned AFTER the SM hai erured that Syt Oeradcr ha anabled the NERC oad heddYng condneny ftware.

Check Locally The Pressure Drop Across The Inservice Instrument Air Dryer To Be Less Than 10 PSID SAT Pl*6280 (2 ft off ground back of Instrument Air UNSAT Dryer) minus P1-

• 3423 STEP 5 q OR PI*6280 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.

STAN DARD 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 P 1-3-3423 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) JPM-k NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 9 Form ES-C-I Contact System Operations, ensure NERC load shedding contingency software has been enabled. SAT STEP 6 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 Operations, inform applicant that Systems Operations will be notified by the SM.

COMMENT IF the air dryer is available on the opposite unit, THEN cross-tie the Instrument Air Systems by opening the Instrument Air Cross-tie Valves:

IAS-3-O 12 STEP 7 j AND IAS-4-O 12 (O-ONOP-013, RNO Step 9.b)

Applicant notes from the Initial Conditions that the Unit 4 Air STANDARD 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 CAUTION tag on IAS-4-O1 2.

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

Appendix C Page 7 of 9 Form ES-C-I IF the Air Dryer on the opposite unit is NOT available, THEN open the Instrument Air Dryer Bypass Valve to supply 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 handle STANDARD 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) JPM-k NUREG 1021 Rev9AppendixC

Appendix C Page 8 of 9 Form ES-C-I Verification of Completiom 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) JPM-k 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 perform ance measure will be satisfied.

Initial Conditions:

• Reactor Power is 100%

• 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 0-ONOP-Ol 3, Loss of Instrument Air, 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-k

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:

• Reactor Power is 100%

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 0-ONOP-Ol 3, Loss of Instrument Air, 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 & SRO) JPM-k

STEP ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED

- I 6 WHEN It Is Desired To Return An Isolated Instrument Air Compressor To Service, THEN Perform The Following For 3CM, OPEN IAC 3CM Discharge Isol VIv IAS-3-058 For 3CD, OPEN IAC 3CD Discharge Isol VIv IAS-3-059 For 4CM, OPEN IAC 4CM Discharge lsol Z

• Vtv For 4CD, OPEN AC 4CD Discharge Isol O Vlv IAS-4-059 IF EC 246991, Unit 4 Instrument Air System O

• Upgrade, is in progress, THEN:

For TC 1 (Unit 3 temporary instrument air Z compressor)) OPEN IAS-3-037 Supply Line Drain Valve Z

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 GotoStepli 0 8 Check Locally That The Instrument Air Dryers Properly Aligned And NOT Purging Excessively Align the Instrument Air Dryers In accordance with 0-NOP-Ol 3.

I.E 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 W97:JWG/emc/cls/cls

STEP ACTION/EXPECTED RESPONSE I 1 RESPONSE NOT OBTAINED I

10 S 5 I

I. IAS-3-012 and IAS-4-012 shall be opened AFTER the SM has ensured that Operations has enabled the NERC load shedding contingency software.

System I

a a a a a a a

• 9 Check Locally The Pressure Drop Across Perform the following:

The Inservice Instrument Air Dryer To Be z

• Less Than 10 PSID Pl..*..6280 (2 ft off ground back of Instrument Air Dryer) minus PI*..3423

a. Contact System Operations, ensure NERC load shedding contingency software has been enabled.

b. IF the air dryer is available on the 0 OR P1*6280 minus PI*3424 opposite unit, THEN cross-tie the Instrument Air Systems by opening the Instrument Air Cross-tie Valves:

0

• IAS-3-012 z

• AND IAS-4-01 2

c. IF the Air Dryer on the opposite unit is NOT available, THEN open the Instrument Air Dryer Bypass Valve to supply air to the affected unit(s).

IAS-3-016

• IAS-4-030 OR

d. Notify the System Engineer to investigate cause of the high DP Q to coordinate immediate repairs as required.

I e. Refer to 0-ONOP-013.1, 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.

W97:JWG/emc/cls/cls

Procedure No.: Procedure

Title:

Page:

Approval Date:

0-ONOP-013 Loss of Instrument Air 7/20/11 STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I

ioF I a 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 a a

• 10 Check Locally The Pressure Drop Across Perform the following:

The Instrument Air Particulate Filters To Be Less Than 5 PSID a. Contact System Operations, ensure NERC load shedding contingency

. DPl--6282 Z AND software has been enabled.

b. Verify the Filters are aligned in O DPI*63OO accordance with O-NOP-013, Instrument Air System.

O c. ffl the air filter is properly aligned, the high DP still exists, THEN cross-tie the Instrument Air Systems by opening the Z Instrument Air Cross-tie Valves:

• IAS-3-012 AND

• IAS-4-012

d. the Filters were properly aligned had a high DP, THEN notify the System Engineer to investigate cause of the high DP AND to coordinate immediate repairs to restore the system to normal.

e. WHEN IAS-3-012 or IAS-4-012 have been closed, notify System Operations that the NERC load shedding 0 contingency software can be disabled.

II W97:JWG/emc/cls/cls