Text

Initial Exam Retake 2011-301 Final Administrative JPMs
	ML111930587
Person / Time
Site:	Turkey Point
Issue date:	03/04/2011
From:	Wilson M; Florida Power & Light Co
To:	; NRC/RGN-II
References
	Download: ML111930587 (101)
	v • d • e

I current revision ctncj thc t there are no unresolved TWR AIs.

Ddte vered: / initiais:

TWR A1# AR 00402402 Assgn 02 jJ: DISCT FLORIDA POWER & LIGHT COMPANY TURKEY POINT MJCLEAR STATION NUCLEAR TRAINING IIEPARTMENT JOB PERFORMANCE MEASURE ILC 26 NRC RETAKE EXAM ADMIN 3PM #1 Mark Wilson Preparer:

-, /-

3/3 Date:

,r4- k4/

Technical eviewer (Print/Sign) Date

(. Lc1 /

Dis cip1ineraining Supervisor (Pit!Sign) 3 Date F-630-Rev.1 (01/31/08 NTP-002)

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 02201005100 Determine License Status Task

Title:

(Active-Inactive) JPM No: ILC 26 NRC Retake A.1.a K/A

Reference:

2.1.1 SRO4.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance x Classroom x Simulator Plant 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 Three (3) Reactor Operators (ROs) have the following history:

All three ROs have off-shift assignments at the plant.

All three ROs are current in License Operator Requalification Training.

All three ROs have had a physical in the last two years with no medical restrictions.

None of the three ROs have worked any shifts since March 22, 2011.

Active/Inactive status and time on shift since January 1, 2011 is as follows for each of the Reactor Operators (Assume shift rotation are 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months periods):

Reactor Operator A License was active on January 1, 2011 Watch Date 1/02/2011-Worked day shift as Unit 3 RCO (0700 am 0300 pm) 1/09/2011-Worked peak shift as Admin RCO (0300 pm 1100 pm) 1/26/20 1 1-Worked day shift in the Work Control (0700 am 0300 pm) 1/29/2011-Worked mid shift as Unit 3 RCO (1100 pm 0700 am) 2/03/2011-Worked day shift as Admin RCO (0700 am 0300 pm) 2/04/2011-Worked day shift as Unit 3 RCO (0700 am 0300 pm) 2/20/2011-Worked mid shift as Admin RCO (1100 pm 0700 am) 2/21/2011-Worked mid shift as Unit 3 RCO (1100 pm 0700 am) 2/22/2011-Worked mid shift as Admin RCO (1100 pm 0700 am)

Reactor Operator B License was active on January 1, 2011 Watch Date 1/04/2011-Worked day shift as Admin RCO (0700 am 0300 pm) 1/16/2011-Worked day shift in Work Control (0700 am 0300 pm) 1/22/2011-Worked peak shift in the Tagging Office (0300 pm 1100 pm) 2/03/2011-Worked peak shift in the Tagging Office (0300 pm 1100 pm) 2/06/2011-Worked mid shift on Unit 4 RCO (1100 pm 0700 am) 2/21/2011-Work mid shift as Admin RCO (1100 pm 0700 am) 2/23/2011-Worked mid shift as Unit 4 RCO (1100 pm 0700 am) 2/27/2011-Worked mid shift as Admin RCO (1100 pm 0700 am) 3/22/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm)

NUREG 1021 Rev9AppendixC

Appendix C Page 2 of 10 Form ES-C-I Reactor Operator C - License was inactive on January 1, 2011 1/05/2011 through 1/09/2011- worked 40 hrs under the direction of Unit 4 RCO and completed all requirement for license re-activation Watch Date 2/2/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/3/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/4/2011- Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/5/2011- Worked day shift as Admin RCO (0700 am 0300 pm) 2/6/2011- Worked day shift as Admin RCO (0700 am 0300 pm) 2/7/2011- Worked day shift as Admin RCO (0700 am 0300 pm) 3/2/2011- Worked day shift in LOCT Training (0700 am 0300 pm) 3/3/2011- Worked day shift in LOCT Training (0700 am 0300 pm) 3/4/2011- Worked day shift in LOCT Training (0700 am 0300 pm) 3/5/2011- Worked day shift as LOCT Training (0700 am 0300 pm) 3/6/2011- Worked day shift in Unit 3 RCO (0700 am 0300 pm)

INITIATING CUE:

You are to determine if each of the Reactor Operators is qualified to work as a reactor operator on Unit 3 or Unit 4 on the day shift on June 1, 2011. Circle you answer below (YES or NO)

Reactor Operator A Unit 3: YES/NO Unit 4: YES/NO Reactor Operator B Unit 3: YES / NO Unit 4: YES /NO Reactor Operator C Unit 3: YES / NO Unit 4:YES/NO HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

NUREG 1021 Rev9AppendixC

I Appendix C I Page 3 of 10 Form ES-C-I Task standard:

References Reviewed

Determines that Operator A and C licenses are still active and may stand watch.

Determines Operator B is inactive and is not qualified to stand watches in the control room.

Required Materials:

O-ADM-200, Conduct of Operations

O-ADM-202, Shift Relief and Turnover

NAP-402, Conduct of Operations

NAP-408, License Maintenance and Activation Program General

References:

O-ADM-200, Conduct of Operations

O-ADM-202, Shift Relief and Turnover

NAP-402, Conduct of Operations

NAP-408 License Maintenance and Activation Program Time Critical Task: No Validation Time: 15 minutes NUREG 1021 Rev9AppendixC

Appendix C Page 4 of 10 Form ES-C-I SIMULATOR SETUP Reset to IC#

N/A Load Lesson N/A Ensure Simulator Operator Checklist is complete N!A NUREG 1021 Rev9AppendixC

I Appendix C Page 5 of 10 Form ES-C-I I Denote critical steps with a check rnark(lj - -

Start Time STEP 1 : SAT Obtain the procedural guidance.

UNSAT Standard: The examinee requests to look at Operations procedural guidance.

Make the following required materials available:

. 0-ADM-200, Conduct of Operations Cue

0-ADM-201, Shift Manning

NAP-402, Conduct of Operations

NAP-408, License Maintenance and Activation Program Comment NOTE: NAP-408 requires 56 hrs/qtr for 8 hr shifts and 60 hrs for 12 hr shifts.

STEP Determine status of Reactor Operator A.

2 : SAT q

UNSAT Operator determines that Reactor Operator A license is active Standard: because he stood more than 56 hrs in the previous quarter in a licensed position.

Cue Comment Reactor Operator A Unit 3/ NO Unit 4I NO NOTE:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 10 Form ES-C-I Determines license status of Reactor Operator B.

STEP 3 : SAT q

UNSAT Standard: Operator determines that Reactor Operator B is inactive because he did not stand 56 hrs in a licensed watch standing position.

Cue Comment Reactor Operator B Unit 3: YES Unit 4: YES NOTE: Operator stood 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of watch.

NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 10 Form ES-C-I Determines ilcense status of eactor Operator C.

STEP 4 : SAT q

UNSAT Standar& Determines that Reactor Operator C license is active because it was reactivated in the previous quarter and he stood 56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months of watch.

Cue Comment Reactor Operator C Unit 3 NO Unit 4 NO NOTE:

Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 10 Form ES-C-I Verification of Completion -

Job Performance Measure No. ILC 26 NRC Retake A.1.a 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:

NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET (1 of 2)

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

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

INITIAL CONDITIONS Three (3) Reactor Operators (ROs) have the following history:

All three ROs have off-shift assignments at the plant.

All three ROs are current in License Operator Requalification Training.

All three ROs have had a physical in the last two years with no medical restrictions.

None of the three ROs have worked any shifts since March 22, 2011.

Active/Inactive status and time on shift since January 1, 2011 is as follows for each of the Reactor Operators (Assume shift rotation are 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months periods):

Reactor Operator A License was active on January 1, 2011 Watch Date 1/02/2011-Worked day shift as Unit 3 RCO (0700 am 0300 pm) 1/09/2011-Worked peak shift as Admin RCO (0300 pm 1100 pm) 1/26/2011-Worked day shift in the Work Control (0700 am 0300 pm) 1/29/2011-Worked mid shift as Unit 3 RCO (1100 pm 0700 am) 2/03/20 1 1-Worked day shift as Admin RCO (0700 am 0300 pm) 2/04/2011-Worked day shift as Unit 3 RCO (0700 am 0300 pm) 2/20/2011-Worked mid shift as Admin RCO (1100 pm 0700 am) 2/21/2011-Worked mid shift as Unit 3 RCO (1100 pm 0700 am) 2/22/2011-Worked mid shift as Admin RCO (1100 pm 0700 am)

Reactor Operator B License was active on January 1,

- 2011 Watch Date 1/04/2011-Worked day shift as Admin RCO (0700 am 0300 pm) 1/1 6/201 1-Worked day shift in Work Control (0700 am 0300 pm) 1/22/2011-Worked peak shift in the Tagging Office (0300 pm 1100 pm) 2/03/2011-Worked peak shift in the Tagging Office (0300 pm 1100 pm) 2/06/2011-Worked mid shift on Unit 4 RCO (1100pm 0700 am) 2/21/2011-Work mid shift as Admin RCO (1100pm 0700 am) 2/23/2011-Worked mid shift as Unit 4 RCO (1100pm 0700 am) 2/27/2011-Worked mid shift as Admin RCO (1100 pm 0700 am) 3/22/20 1 1-Worked day shift as Unit 4 RCO (0700 am 0300 pm)

Reactor Operator C License was inactive on January 1, 2011 1/05/2011 through 1/09/2011-worked 40 hrs under the direction of Unit 4 RCO and completed all requirement for license re-activation Watch Date 2/2/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/3/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/4/2011-Worked day shift as Unit 4 RCO (0700 am 0300 pm) 2/5/2011- Worked day shift as Admin RCO (0700 am 0300 pm) 2/6/2011-Worked day shift as Admin RCO (0700 am 0300 pm) 2/7/2011-Worked day shift as Admin RCO (0700 am 0300 pm) 3/2/20 1 1- Worked day shift in LOCT Training (0700 am 0300 pm) 3/3/2011-Worked day shift in LOCT Training (0700 am 0300 pm) 3/4/2011-Worked day shift in LOCT Training (0700 am 0300 pm) 3/5/2011-Worked day shift as LOCT Training (0700 am 0300 pm) 3/6/2011-Worked day shift in Unit 3 RCO (0700 am 0300 pm)

NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 10 Form ES-C-I JPM BRIEFING SHEET (2 of 2,)

INITIATING CUE:

You are to determine if each of the Reactor Operators is qualified to work as a reactor operator on Unit 3 or Unit 4 on the day shift on June 1, 2011. Circle you answer below (YES or NO).

Reactor Operator A Unit 3: YES I NO Unit 4: YES I NO Reactor Operator B Unit 3: YES / NO Unit 4: YES I NO Reactor Operator C Unit 3: YES I NO Unit 4: YES / NO 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.

NUREG 1021 Rev9AppendixC

ce1 current revision cind that there are no unresolved TWR AIs.

Date ver/ied: /1/ II Initials:

TWR A]# AR 00402402 Assgn 02 N

FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR STATION NTJCLEAR TRAIMNG DEPA1TMENT JOB PERFORMANCE MEASURE ILC 26 NRC RETAKE EXAM ADMIN JPM #2 Mark Wilson Preparer:

-, I-,

3/3 Date:

Technical eviewer (Print/Sign) Date Date F-630-Rev.1 (01/31/08 - O-NTP-002)

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 02201026100 Task

Title:

Maintain Operations Key Log JPM No: ILC 26 NRC Retake A.1.b K/A

Reference:

2.1.29 SRO 4.0 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance X Actual Performance Classroom X Simulator Plant 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:

You are the Unit 3 Unit Supervisor. The crew has entered 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, to mitigate the effects of P-3-457, Pressurizer Pressure, failing low. Unit 3 is stable at 100% with no other testing in progress or failures.

Initiating Cue:

You have directed performance of Step 5.11 of 3-ONOP-049.1 to trip the bistables of P-3-457.

Identify which rack(s) the RCO will enter to trip bistables for P-3-457.

Fill out F-527, Operations Key Log, to checkout a key for U3 RCO.

For this plant event, identify 1) why a notification is required and 2) whom if anyone in the NRC is required to be notified.

NOTE: The Senior NRC Resident is off-site.

The NRC Resident is observing LOCT Training in the LOCT Classroom.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

NUREG 1021 Rev 9 Appendix C

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

Control Protection Rack access

Maintain Operations Keg Log

Identify plant event and NRC notification (whom)

Time Critical Task: NO Validation Time: 20 minutes Required Materials:

3-ONOP-049. 1, Deviation or Failure of Safety Related or Reactor Protection Channels

0-ADM-205, Administrative Control of Valves, Locks, and Switches

F-527, Operations Key Log (hard copy & blank)

0-ADM-1 15, Notification of Plant Events

NAP-402, Conduct of Operations

Control Room Master Key Index

PTN Technical Specifications General

References:

3-ONOP-049. 1, Deviation or Failure of Safety Related or Reactor Protection Channels

0-ADM-205, Administrative Control of Valves, Locks, and Switches

F-527, Operations Key Log

0-ADM-1 15, Notification of Plant Events

NAP-402, Conduct of Operations

Control Room Master Key Index

PTN Technical Specifications NUREG 1021 Rev 9 Appendix C

Appendix C I Page 3 of 8 Form ES-C-I I SIMULATOR SETUP Reset to IC N/A Load Lesson N/A Ensure Simulator Operator Checklist is complete N/A NUREG 1021 Rev9AppendixC

Appendix C Page 4 of 8 Form ES-C-I Critical steps are denoted with checkmark (J)

Start Time STEP 1 Obtain a copy of 3-ONOP-049.1 Deviation or Failure of Safety SAT Related or Reactor Protection Channels.

(From the initiating cue.) UNSAT Standard A copy of 3-ONOP-049. 1, Deviation or Failure of Safety Related or Reactor Protection Channels is obtained.

Provide a copy of 3-ONOP-049. 1, Deviation or Failure of Safety Cue Related or Reactor Protection Channels.

Comment STEP 2 : SAT Identify which rack(s) the RCO will enter to trip bistables for P-3-457.

q UNSAT Examinee uses Attachment 4, Failed Channel Bistable List, to identify Standar&

Racks 14 & 15 will be opened to trip bistables Rack(s) for tripping P-3-457 Bistables Comment 14 15 NUREG 1021 Rev 9 Appendix C

L?ppendix C I Page 5 of 8 Form ES-C-I STEP 3 : SAT Fill out F-527, Operations Key Log, to checkout a key for U3 RCO.

-,J UNSAT Standard: The examinee fills out F-527, Operations Key Log, to checkout a key for U3 RCO.

Provide a hardcopy of

. F-527, Operations Key Log

. Control Room Master Key Index Critical Step Parts

. Key#

. Name (similar variation acceptable)

. Work Control Comment System, major component, cubicle or rackdoororpaneltobomanipulated WORK -

KEY CONTROL KEYISSIJED oropened MODE NO. EVAL that allows manipulation TO PERSON NAME 1 IJEVI,ATE NUMBER (procedureor (ijJE& By

U3 Protection Racks 14 & 15 INIT clearance NO.) DEPT) 3-ONOP-049.1 Name- OPs (NAME)

Name j & TIME x/x</.

) Keys 3,37,155,156 or 158 (Any cceptable)

NUREG 1021 Rev9AppendixC

Appendix C Page 6 of 8 Form ES-C-I STEP 4 : SAT For this plant event, identify 1) why a notification is required and 2) q whom if anyone in the NRC is required to be notified. UNSAT The examinee identifies:

1. Unplanned entry into a 72 Hr (or less) Action Statement Standard: 2. NRC Resident Inspector Note: The candidate may also mention Plant Management. Anytime the NRC Resident Inspector is notified, Plant Management is required to be notified.

1) Provide a hardcopy of PTN Technical Specifications, if asked.

2) Provide a hardcopy of O-ADM-1 15, Notification of Plant Events, Cue if asked.

3) Provide a hardcopy of NAP-402, Conduct of Operations, if asked.

Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue the examiner. With no action taken by Examinee, the Examiner STOP

. completes the JPM.

Stop Time NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 8 Form ES-C-I Verification of Completion Job Performance Measure No. ILC 26 NRC Retake A.1.b 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:

NUREG 1021 Rev9AppendixC

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

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

Initial Conditions:

You are the Unit 3 Unit Supervisor. The crew has entered 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, to mitigate the effects of P-3-457, Pressurizer Pressure, failing low. Unit 3 is stable at 100% with no other testing in progress or failures.

Initiating Cue:

You have directed performance of Step 5.11 of 3-ONOP-049.1 to trip the bistables of P-3-457.

Identify which rack(s) the RCO will enter to trip bistables for P-3-457.

Fill out F-527, Operations Key Log, to checkout a key for U3 RCO.

For this plant event, identify 1) why a notification is required and 2) whom j anyone in the NRC is required to be notified.

NOTE: The Senior NRC Resident is off-site.

The NRC Resident is observing LOCT Training in the LOCT Classroom.

Acknowledge to the examiner when you are ready to begin.

Rack(s) for tripping P-3-457 Bistables NRC Notification (whom)?

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

NUREG 1021 Rev 9 Appendix C

OPETATIONS KEY LOG KE slit Ii QATECORDAGE I

System, major component, cubicle or f. WGRK rack door or panI to be manipulated CONTROL KEY ISSUED KEY MODE KEY RETURNEDILOCK RESTORED NO or opened that allows EVAL lNrn manipulation TO PERSON ISSUED DATE BY (NAME & VERIFIED

NAME NUMBER .. (procedure r. :(NJJlE &* BY DATE &

clearance & TIME DEPT) TIME LOCKED No) DEPT) (NOTE 1)

J3 Protection Racks 14 & 15 INIT 3-ONOP-049.1 Name- OPs Name :/xx/ :x HHMM Keys 337,l55,156, or 158 (Any cceptable)

NOTEh Each cubicle, racL door, or panel that was uniocked shall be verified to beclosed and locked:

Enter nanze oi person performing the verification (Ref. Step 5.4.4).

Reviewed By ** Date:

..ShftManag orSRO.Designee

r; -;;; ;

current revision and that there are no unresolved TWR AIs.

Date verfied:

Initials:

TWR AJ# AR00402402 Assgn 02 Nuoiai £in FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR STATION NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE ILC 26 NRC RETAKE EXAM ADMIN JPM #3 Mark Wilson Preparer:

-, I-i Date:

LJc/

1 Technical viewerPrint/Sign) Date

&A . /

Disciple Traiiing Supervisor (rint!Sign) 3/gil, Date F-630-Rev.1 (01/31/08 NTP-002)

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 02201056100 Review Boric Acid Pump Task

Title:

Discharge Valve Clearance JPM No: ILC 26 NRC Retake A.2 K/A

Reference:

2.2.13 SRO 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: Classroom Simulated Performance Yes Actual Performance Classroom Yes Simulator Plant 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 You are the Unit Supervisor.

Valve 342, 3A Boric Acid Transfer Pump Disch to Unit 3 BA Fltr, has a valve body leak.

The Admin RCO has prepared the attached ECO and marked up P&ID for Valve 342 and has submitted it for your review.

NOMS Database is not available for clearance research and preparation.

All Technical Specification issues associated with the removal from service of equipment associated with Valve 342 have already been addressed.

Separate guidance has been developed and approved to ensure the availability of boric acid to Unit 3 while this ECO is in effect.

INITIATING CUE The Shift Manager directs you to review the ECO for Valve 342. If the ECO is correct and complete, sign it showing your approval. If the ECO is not correct or complete, revise it to make it correct and complete.

Note: Restoration steps are NOT required for this ECO.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

NUREG 1021 Rev9AppendixC

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

The clearance order is reviewed.

Errors existing in the clearance ordered are discovered.

Required Materials:

O-ADM-212.1, Operations In-Plant Equipment Clearance Orders

Student ECO Package

Red Pen & Highlighter General

References:

O-ADM-212.1, Operations In-Plant Equipment Clearance Orders Time Critical Task: NO Validation Time: 40 minutes NUREG 1021 Rev9AppendixC

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

NIA Load Lesson NIA Ensure Simulator Operator Checklist is complete NIA NUREG 1021 Rev9AppendixC

Appendix C Page 4 of 8 Form ES-C-I Denote critical steps with a check mark(

Start Time STEP 1 : . SAT Review ECO UNSAT The Examinee:

1. Asks for ECO Package

2. Reviews a marked up copy 561 O-M-3046, Sheet 1 Standard: .. .

3. Identifies the need to isolate and drain the affected equipment.

4. Identifies the ECO Boundary

5. Looks up 3A BA Pump breaker number (30725) in the Breaker Book.

S2i Hand the applicant the EGO Package Gom ment NOTE:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 8 Form ES-C-I STEP 2 : Identifies errors and omissions on the ECO form. SAT q

UNSAT The Examinee:

1. Discovers 3A BA Transfer Pump has wrong breaker number.

Breaker number shown (30610) is for the 3B BA Transfer Pump, not the 3A pump which is actually breaker 30725.

2. Discovers Breaker 30725 step is at the end of the ECO after valves are closed. Notes that 30725 should be tagged out before valves Standard:

are closed.

3. Discovers Valve 337, PW to 3A BA Xfer Pump Suct., has been omitted.

4. Discovers the valve to be worked, Valve 342 is listed on the ECO form as a valve to be Danger tagged close. 342 may be left open for draining.

Cue Corn ment NOTE:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 8 Form ES-C-I STEP 3 : SAT Annotates ECO form to reflect the 4 discovered errors.

UNSAT Standard: The Examinee annotates the ECO form and returns it to the evaluator.

Cue Corn ment NOTE:

Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner.

Stop Time NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 8 Form ES-C-I Verification of Comp!etion Job Performance Measure No. ILC 26 NRC Retake A.2 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:

NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions which stps to simjlate or djscis, and prQVie LnititIfl cues When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS You are the Unit Supervisor.

Valve 342, 3A Boric Acid Transfer Pump Disch to Unit 3 BA Fltr, has a valve body leak.

The Admin RCO has prepared the attached ECO and marked up P&ID for Valve 342 and has submitted it for your review.

NOMS Database is not available for clearance research and preparation.

All Technical Specification issues associated with the removal from service of equipment associated with Valve 342 have already been addressed.

Separate guidance has been developed and approved to ensure the availability of boric acid to Unit 3 while this ECO is in effect.

INITIATING CUE The Shift Manager directs you to review the ECO for Valve 342. If the ECO is correct and complete, sign it showing your approval. If the ECO is not correct or complete, revise it to make it correct and complete.

Note: Restoration steps are Q] required for this ECO.

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.

NUREG 1021 Rev9AppendixC

ECO # 3-XX-XX-XXX ECO FORM TAG HANG LIST FOR ECO Page 1 of 2 Tag Equipment Equipment Equipment Tag Place Place st 1 nd 2

Serial Notes ID Description Location Type Seq Config Number 3A Boric Acid 3P203A Control Room Hang Info Transfer Pump InfoTag 1 Control Console Tag Control Switch Switch 3A Boric Acid Non-Critical Boric Acid Tank 6 Transfer Pump 1 Danger Close Plus Suction valves closed after 338 Room Suct Vlv discharge vlvs-any order Batch Tk to 3A Non-Critical Boric Acid Tank 7 Boric Acid Transfer 2 Danger Close Plus Suction valves closed after 398A Room Pump Suct discharge vlvs-any order 3A Boric Acid Non-Critical Boric Acid Tank Transfer Pump 3 Danger 3 Close Plus Discharge valves closed 332 Room Disch to A BAST before suction vlvs-any order 3B Boric Acid Non-Critical Transfer Pump Boric Acid Tank Discharge valves closed 4 Danger Close Plus 341 Disch to Unit 3 Room before suction vlvs-any order BA_Fltr Non-Critical Unit-3 BA Fltr Boric Acid Tank 5 5 Danger Close Plus Discharge valves closed 3-347 Inlet Isol Room before suction vlvs-any order 3A Boric Acid Boric Acid Tank 9 Drain Line 396A Drain No Tag Transfer Pump Drn Room Installed Line 3A Boric Acid Boric Acid Tank 10 No Tag g Throttle 396A Transfer Pump Drn Room Critical Error 3A Boric Acid Student will not tag valve Transfer Pump Boric Acid Tank close plus.

Danger Close Plus (may be open no tag) 342- Disch to Unit 3 Room BA Fltr i2 3A Boric Acid Boric Acid Tank 11 Place Seq. # may be +1 if 7 Danger Open 342 is OPENwith no tag.

396A Transfer Pump Drn Room F-392/3:5 Rev. 2 (2/5/11 ADM-2 12.1)

ECO FORM TAG HANG LIST FOR ECO Page 2 of 2 Equipment Tag Equipment Equipment Tag Place Place st 1 nd 2

ID Description Location Serial Notes Number Type Seq Config 30725 Critical Error Boric Acid Transfer 3C 480v MCC 8 Danger Off Plus 30610 1) Wrong Bkr #

Pump 3A Bkr

2) Sequence #2 30725 Boric Acid Transfer De- Critical Error 3C 480v MCC - ZVC 12 30610 Pump 3A Bkr Energized 1) Wrong Bkr#

PW to 3A BA Xfer Boric Acid Tannk Critical Error 1 Danger 8 Close Pump Suct. Room Omitted If the ECO is correct and complete, sign it showing your approval.

US Reviewed By F-392/3:5 Rev. 2 (2/5/11 ADM-212. 1)

ATTACHMENT 7 (Page 1 of 9)

ECO CHECKLIST This ECO Checklist is a tool to aid in the preparation and approval of ECOs. It provides guidance for materials that should be included in an ECO package and is for informational purposes.

ECO Preparer Checklist #1 ECO# 3-XX-XX-XXX (J as appropriate)

ECO Package Contents Y N N/A 1 El El Copy of the ECO (cover sheet, tag list).

2. El El Drawings (P& IDs, EWDs, breaker list, etc) marked up to show boundary.

3. El El Any other materials needed or used in the preparation of ECO.

The individual preparing the ECO will review the PWO(s) to identify:

1. El El Principle Equipment.

2. i El El Scope of Work.

3. El El Recommended isolation points (For ECO purpose, the PWO is not a controlled document).

4. El El Notes, emails, etc. to identify communications or corrective actions taken against discrepancies found during the.preparation of the ECO.

ECO Reviewer

1. 1 El El ECO boundary provides proper isolation for described work (verify all components of ECO package checklist).

Wq7.JFhI/rjs/nw

ECO # 3-XX-XX-XXX ECO FORM TAG HANG LIST FOR ECO Page lof 2 Equipment Equipment Equipment Tag Tag Place Serial Place ID Description Location Type Seq Config Notes Number 3A Boric Acid 3P203A Control Room Hang Info Transfer Pump Info Tag 1 Control Console Tag Control Switch Switch 3A Boric Acid Boric Acid Tank Transfer Pump 1 Danger 2 Close Plus 338 Room SuctVlv Batch Tk to 3A Boric Acid Tank Boric Acid Transfer 2 Danger 3 Close Plus 398A Room Pump Suct 3A Boric Acid Boric Acid Tank Transfer Pump 3 Danger 4 Close Plus 332 Room Disch to A BAST 3B Boric Acid Transfer Pump Boric Acid Tank 4 Danger 5 Close Plus 341 Disch to Unit 3 Room BA Fltr Unit-3 BA Fltr Boric Acid Tank 5 Danger 6 Close Plus 3-347 Inlet Isol Room 3A Boric Acid Boric Acid Tank Drain Line 396A Drain No Tag 7 Transfer Pump Drn Room Installed Line 3A Boric Acid Boric Acid Tank No Tag 8 Throffle 396A Transfer Pump Drn Room 3A Boric Acid Transfer Pump Boric Acid Tank 6 Danger 9 Close Plus 342 Disch to Unit 3 Room BA_Fltr 3A Boric Acid Boric Acid Tank 7 Danger 10 Open 396A Transfer Pump Drn Room F-392/3:5 Rev. 2(2/5/11 ADM-212.1)

ECO FORM TAG HANG LIST FOR ECO Page 2of2 Equipment Tag Equipment Equipment Tag Place Place Serial Notes ID Description Location Type Seq Config Number BoricAcidTransfer 3C480vMCC 8 Danger 11 Off Plus 30610 Pump_3A_Bkr Boric Acid Transfer De 30610 3C48OvMCC - ZVC 12 Pump 3A Bkr Energized If the ECO is correct and complete, sign it showing your approval.

US Reviewed By F-392/3:5 Rev. 2 (2/5/11 ADM-2 12.1)

ATTACHMENT 1 (Page 1 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs are tied together and all Boric Acid Transfer Pumps aligned to BASTs) j QA RECORD PAGE (Page 1 of 1)

Procedure Revision Date / /

Check (q) Tag column if tag is missing, mislabeled, illegible, or improperly installed.

REMARKS - Indicate any component not in the NORMAL position and note the reason. For component under clearance, provide clearance number.

Date/Time Started / Date/Time Completed /

PERFORMED BY (Print) INITIALS REVIEWED BY:

S14fi Manager or SRO Designee W2003:TNM/nw/nw/cls

ATTACHMENT 1 (Page 2 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and all BA Transfer Pumps aligned to BASTs)

Checked Component Normal Tag & Vlv Pos Component Description No. Position (J) mit 10 396 PW to Boric Acid Transfer Pump LOCKED Isol CLOSED CLOSED 343B A BAST Drn Hdr Isol AND CAPPED 343J A BAST Sample CLOSED 343K A BAST Drn CLOSED 3A 3B Boric Acid Transfer Pump Suct Hdr Tie OPEN 338 3A Boric Acid Transfer Pump Suct Vlv OPEN 398A Batch Tk to 3A Boric Acid Transfer Pump Suct CLOSED PW to 3A Boric Acid Transfer Pump Suct CLOSED 396A 3A Boric Acid Transfer Pump Drn CLOSED 349E Root Valve 3A Boric Acid Transfer Pump Disch Press md OPEN 342 3A Boric Acid Transfer Pump Disch to Unit 3 BA Fltr OPEN 341 3B Boric Acid Transfer Pump Disch to Unit 3 BA Fltr OPEN 332 3A Boric Acid Transfer Pump Disch to A BAST OPEN BA Pump 3A and 3B Disch Cross Connect Isol Valve CLOSED 3-349A Unit-3 BA Fltr Vent CLOSED 3-349B Unit-3 BA Fltr Drn CLOSED Unit-3 BA Fltr Outlet P1-3-i 13B 3-349C OPEN Root W2003:TNM/nw/nw/cls

Procedure No.: Page:

Procedure

Title:

121 At 00P046 cvcs Boron Concentration Control 11/11/09 ATTACHMENT 1 (Page 3 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and all BA Transfer Pumps aligned to BASTs)

Checked Component Normal Tag&VlvPos Component Description No. Position (J) mit 3-349D Unit-3 BA Fltr Inlet P1-3-i 13A Root OPEN 3-347 Unit-3 BA Fltr Inlet Isol OPEN 3-348 Unit-3 BA Fltr Outlet Isol OPEN Orifice Stop Vlv BA Pp 3A LOCKED Disch to BA Tank A OPEN HCV-1 10 A BAST Recirc Cont Vlv CLOSED 345 A BAST Outlet Isol OPEN 4788A A BAST LT-106 Root OPEN CLOSED 4789A A BAST LT-106 Root &

CAPPED W2003:TNMInw/nw/cls

ATTACHMENT 1 (Page 4 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and all Boric Acid Transfer Pumps aligned to BASTs)

Checked Component Normal Tag&VIvPos No. Component Description Position (J) mit 390 Boric Acid Transfer Pump Suct Hdr X-Conn OPEN 343C B BAST Drn Hdr Isol CLOSED 343G BBASTDrn CLOSED 330 B BAST Local Sample CLOSED 327 Boric Acid Transfer Pump Suct Hdr X-Conn OPEN 3B Boric Acid Transfer Pump Suct OPEN 398B Batch Tank to 3B Boric Acid Transfer Pump Suct CLOSED PW to 3B Boric Acid Transfer 336 CLOSED Pump Suct 396B 3B Boric Acid Transfer Pump Dm CLOSED Root Valve PI-3-105A 3B Boric 349F Acid Transfer Pump Disch Press OPEN md 3B Boric Acid Transfer Pump Disch to B BAST OPEN 3771 4A 3B Boric Acid Transfer CLOSED Pump Disch X-Conn 3B Boric Acid Transfer Pump to 378 CLOSED Unit 4 BA Fltr Byp Isol 3 340 3B BA Pump Disch to Unit 3 BAFltrByp CLOSED 3B Boric Acid Transfer Pump 43401 Disch X-Conn to Unit 4 BA Fltr CLOSED Byp 329 B BAST Orfc Recirc Isol LOCKED OPEN HCV-105 B BAST Recirc Cont Vlv CLOSED Note 1: Opening this valve with either unit in Modes 1 through 4 places the Units in a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO action (LCO 3.l.2.2.a) for cross-tying the BATP flowpaths.

W2003:TNMInw/nw/cls

ATTACHMENT 1 (Page 5 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and all BA Transfer Pumps aligned to BASTs)

Checked Component Normal Tag & Vlv Pos No. Component Description Position 331 B BAST Outlet OPEN 4788B B BAST LT-108 Root OPEN CLOSED 4789B B BAST LT-108 Root &

CAPPED W2OO3:TNM/nw/nwIcs

ATTACHMENT 1 (Page 6 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and all BA Transfer Pumps aligned to BASTs)

Checked Component Normal Tag&VlvPos No. Component Description Position (1) mit 343D C BAST Drn Hdr Isol CLOSED 343E C BAST Drn CLOSED 343F C BAST Local Sample CLOSED 391 4A-4B Boric Acid Transfer Pump Suct Header Tie OPEN 392 4A Boric Acid Transfer Pump Suct OPEN 398C Batch Tank to 4A Boric Acid Transfer Pump Suct Stop CLOSED PW to 4A Boric Acid Transfer Pump Suct CLOSED 396C 4A Boric Acid Transfer Pump Drn CLOSED Root Valve PI-4-105B 4A Boric 349H Acid Transfer Pump Disch Press OPEN md 376 4A Boric Acid Transfer Pump Disch to Unit 4 BA Fltr OPEN 4B Boric Acid Transfer Pump Suct OPEN 398D Batch Tank to 4B Boric Acid Transfer Pump Suct Stop CLOSED PW to 4B Boric Acid Transfer Pump Suct CLOSED 4B Boric Acid Transfer Pump 396D Dm (Located Inside Pp CLOSED Doghouse)

Root Valve P1-4-104 4B Boric 349G Acid Transfer Pump Disch Press OPEN md 4B Boric Acid Transfer Pump Disch to Unit 4 BA Fltr OPEN 4B Boric Acid Transfer Pump Recirc to C BAST OPEN W2003:TNM/nw/nw/cls

ATTACHMENT 1 (Page 7 of 7)

CVCS BORIC ACID SYSTEM VALVE ALIGNMENT (All BASTs tied together and. all BA Transfer Pumps aligned to BASTs)

Checked Component Normal Tag & Vlv Pos No. Component Description Position (J) mit 4-375 BA Filter Recirc to BAST C CLOSED 4-349A Unit 4 BA Fltr Vent CLOSED 4-349B Unit 4 BA Fltr Dm CLOSED 4-349C Unit 4 BA Fltr Outlet P1-4-i 13B Root OPEN 4-349D Unit 4 BA Fltr Inlet P1-4-i 13A Root OPEN 4-347 Unit 4 BA Fltr Inlet Isol OPEN 4-348 Unit 4 BA Fltr Outlet Isol OPEN Orifice Stop Vlv BA Pp 4B to LOCKED 370 BASTC OPEN HCV-104 C BAST Recirc Cont Vlv CLOSED BA Tank C to BA Pps Suct Hdr Outlet OPEN 4788C C BAST LT-102 Root OPEN CLOSED 4789C C BAST LT-102 Root &

CAPPED BIT Recirc 3A Boric Acid

XJI1D 423 Transfer Pump Suct CLOSED

wJj 421 B BAST to Mini Recirc Sys Isol CLOSED 3B Boric Acid Transfer Pump to *WIRED 416 Unit 3 BIT Recirc Sys Isol CLOSED 4B Boric Acid Transfer Pump *IJJND 415 Disch to Unit 4 BIT Recirc Sys Isol CLOSED BA Batch Tank to Mini Recirc *TJJD 403 Sys CLOSED 401 C BAST to Mini Recirc Sys Isol WIRED CLOSED Valves are restrained closed as abandoned equipment isolation valves.

W2003:TNM/nw/nw/cls

ATTACHMENT 3 (Page 1 of 4)

CVCS BORIC ACID SYSTEM BREAKER ALIGNMENT QA RECORD PAGE*

(Page 1 of 1)

Procedure Revision Date / /

Check (J) Tag column if tag is missing, mislabeled, illegible, or improperly installed.

REMARKS - Indicate any component not in the NORMAL position and note the reason. For component under clearance, provide clearance number.

Date/Time Started / Date/Time Completed /

PERFORMED BY (Print) INITIALS I have reviewed this attachment and it has been satisfactorily performed. Deviations or TCs used to perform this attachment are listed under Remarks.

REVIEWED BY:

Shfl Manager or SRO Designee W2003:TNM/riw/nw/cls

ATTACHMENT 3 (Page 2 of 4)

CVCS BORIC ACID SYSTEM BREAKER ALIGNMENT MCC 3B (Turbine Area)

Checked Component Normal Tag & Vlv Pos Component Description No. Position I

30610 Boric Acid Transfer Pump 3B Bkr ON MCC 4B (Turbine Area)

Checked Component Normal Tag & Vlv Pos Component Description No. Position 40696 Boric Acid Transfer Pump 4B Bkr ON MCC 3C (Fuel Area)

Checked Component Normal Tag & VJv Pos Component Description No. Position I mit Boric Acid Transfer Pump 3A 30725 30747 Bkr BA Batch Tank Mixer Bkr ON ON I

MCC 4C (Fuel Area)

Checked Component Normal Tag & VIv Pos No. Component Description Position Boric Acid Transfer Pump 4A 40725 ON Bkr W2003:TNM/nw/nw/cls

Procedure No.: I Page:

Procedure

Title:

I 0-OP-046 L CVCS Boron Concentration Control II AaI Da 130 11/11/09 ATTACHMENT 3 (Page 3 of 4)

CVCS - BORIC ACID SYSTEM BREAKER ALIGNMENT 125 Volt DC Distribution Swar 4D23 Checked Component Normal Tag & Vlv Pos Component Description No. Position (q) mit 4D23-1 1 Pwr Sply to Control Board 4C01 ON 4D23-08 Pwr Sply to Control Board 4C02 ON Fuses FCV-4-1 13A, Boric Acid to Blender Installed FCV-4-1 13B, Blender to Fuses Installed Charging Pump Suction Fuses FCV-4-114A, Primary Water to Blender Installed Fuses FCV-4-1 14B, Blender to VCT Installed 125 Volt DC Distribution Swgr 3D23 Checked Component Normal Tag & Vlv Pos Component Description No. Position (q) mit 3D23l4 Pwr Sply to Control Board 3C01 ON Fuses FCV-3-114A, Primary Water to Installed Blender Fuses FCV-3-1 14B, Blender to VCT Installed W2003:TNM/nw/nw/cls

ATTACHMENT 3 (Page 4 of 4)

CVCS BORIC ACID SYSTEM BREAKER ALIGNMENT 125 Volt DC Distribution Swar 3D01 Checked Component Normal Tag & VIv Pos Component Description No. Posifion 3D01-21 Pwr Sply to Control Board 3C01 ON Control Board 3C01 FCV-3-l 13A, Boric Acid to Fuses Installed Blender FCV-3-1 13B, Blender to Fuses Installed Charging Pump Suction Boric Acid Tank Room Checked Component Normal Tag & Vlv Pos Component Description No. Position (1) mit Boric Acid Transfer Pump 3A SS-3P203A REMOTE Local/Remote SW Boric Acid Transfer Pump 3B XS-3P203B NORMAL Normal/Isolate SW SS-4P203A Boric Acid Transfer Pump 4A Local/Remote SW REMOTE Boric Acid Transfer Pump 4B XS-4P203B NORMAL Normal/Isolate SW W2OO3:TNM/nw/nw/cs

BREAKER LIST PAGENO.

INPUT DATA FILE PTP.BL.124 MCC 3A TURBINE AREA (3B05)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CAT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

233 5613E5 3B01 FEED FROM L.C. 3A (3B0112) (PC/M 87264) 30501 E-1OSH1 VITAL 347 5613E-5 SPARE (DCR-TPE-93-517) 30502 E-1OSH1 VITAL 59 E-10 3P37 HYDROGEN SIDE SEAL OIL PUMP #3 30503 VITAL 289 5613-E-5 3C2A DIESEL GEN. AIR COMPRESSOR #3A (PC/M 87-264) 30504 E-1OSH1 VITAL 59 LP34A(3P04)-65 E-10 3P36 AIR SIDE SEAL OIL PUMP #3 30505 4160V ENGR ROOM VITAL 537 E-27 SM 11B 3P1OA DIESEL GEN. FUEL OIL TRANSFER PUMP #3A CRN-E-17422 (PC/M 04-036) 30506 E-10 SN 1 VITAL (AUX. DEVICES LOCATED IN COMPT. 30511) 289 5613E-S 3V34A DIESEL GEN ROOM VENT FAN #3A (PC/M 87-264) 30507 E-1OSN1 VITAL 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 59 LP34A(3P04)61 E10 3P31 TURNING GEAR OIL PUMP #3 (NO BREAKER 30508,30509) 30510 4160V ENGR ROOM VITAL 537 E-27 SH 11B 3P1OA AUX. DEVICES FOR DIESEL GEN. FUEL OIL CRN-E-17422 (PC/M 04-036) 30511 E-10 SN 1 VITAL TRANSFER PUMP #3A 327 LP34A(3P04)-63 E-1OSH1 3T08 TURNING GEAR DRIVE (3C04) AUTOMATIC (DCR-TPE-93-306) 30512 4160V ENGR ROOM E-29 SH.3A VITAL 445 E-10 SH.1 3T9 INSTRUMENT AIR DRYER #3 (PC/M 99-042) 30513 5613E27 VITAL SN.57A 262 E-1OSN1 3C13A DIESEL GEM AUX EQUIP #3 (PC/M 87-264) 30514 VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E855 SH.124

BREAKER LIST PAGENO. 2 INPUT DATA FILE PTP.BL.124 MCC 3A TURBINE AREA (3B05)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED -

347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 59 LP34A(3P04)-67 H-b 3V1A NORM. CONTAINMENT COOLER FAN 3A 30518 4160V SWGR ROOM VITAL 387 DELETED (PC/N 93-108) 353 E1OSH1 SPARE (PC/N 93148 CRNE15096) 30520 NON-VITAL 477 H-b 3X034 SPACE HEATER TRANSF NO. 34 BREAKER CRN-E-16353 (PC/N 02-065) 30521 NON-VITAL SEE ALSO LP34/34A (AFFECTS SJAE SPING) 508 E-b0 SPACE HTR MCC 3A TRANSF. BREAKER CRN-E-16636 (PC/N 03-106) 30522 VITAL 59 E-10 MOV-3-1420 (SEN. GEN. ED. PP. 3A DISCH STOP) 30523 VITAL 387 E10 SH.1 SPARE (PC/N 93108) 30524 278 E-1OSH1 PWR SG3A MSSBP VLV. (MOV31400) (PC/M 87258) 30525 VITAL 347 DELETED (DCR-TPE-93-517) 262 E-1OSH1 SPARE (PC/N 87258) 30527 VITAL 347 DELETED (DCR-TPE-93-517)

CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E-855 SH.124

BREAKER LIST PAGENO. 3 INPUT DATA FILE PTP.BL.124 MCC 3A TURBINE AREA (3B05)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

78 E-10 MOV-3-1409 S/G 3C FEEDWATER SUPPLY LINE STOP 30529 VITAL 278 E-1OSH1 PWR SG3A WATER SAMPLING CNTMT. ISOL. VLV. (MOV-3-1427) (PC/M 87-258) 30530 VITAL 59 E10 SPARE (DUP-064) 30531 VITAL 278 E-1OSH1 PWR ACCUM. 3A DISCH. STOP VLV. (MOV-3-865A) (PC/M 87258) 30532 VITAL

*** CONTAIN ENTRANCE OPENING BEN NO. 20 ALSO REMOVES HEATER POWER FROM MOV 86 6A CAUTION: & MOV 744A 59 E-10 3P40 TURBINE BEARING OIL LIFT PUMP #3 30533 VITAL 548 E10 SPARE (PC/M 04113) 30534 125 E-10 NON- NON-VITAL INCOMING FEEDER-MCC NV3A (PC/M 86-095) 30535 VITAL 59 E-10 3X03 START-UP TRANSFORMER #3 COOLING EQUIPMENT 30536 NON-VITAL NOTE: SEE BEN 30682 305 E10 SPARE (PC/M 90-240) 30537 NON-VITAL 453 E-10 3X032 LTG TRANSFORMER #32 (MAIN STEAM PLATFORM) CRN-E-16104(PC/M 99-061) 30538 NON-VITAL SEE LP32 500 E-10 SPARE (PC/M 04-091) 30539 NON-VITAL 467 E-10 SH.1 3F6 TURBINE L.O. CONDITIONER. (PC/M 00002) 30540 NON-VITAL 188 E-10 3X254 DIST. PANEL 3DP434 VIA XFMR 3X254 (PC/M 86-190) 30541 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E855 SH.124

BREAKER LIST PAGENO. 4 INPUT DATA FILE PTP.BL.124 14CC 3A TURBINE AREA (3B05)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

235 E-29SH1OC 3V4 TURBINE L.O. RESERVOIR 3 VAPOR EKTR. #3 (DCR-TPE-90-482) 30542 E-10 NON-VITAL 327 E-1OSH1 3P43 CON!) RECOVERY TANK TRANSFER PUMP #3 (DCR-TPE-93-307) 30543 E-26 SH.21A NON-VITAL 59 E-10 3X02 AUX TRANSFORMER COOLING NORMAL FEED 30544 NON-VITAL NOTE: SEE BKR 30675 59 E-10 3P19D 3C S/G CHUM. ADDITION PUMP 3C PHOSPHATE PUMP 3P19D/1 30545 NON-VITAL 347 DELETED (DCR-TPE-93-517) 59 E10 3X317 LTG PANEL LP 317 VIA XFMR 3X317 (PCM 77-28) 30547 NON-VITAL 453 E-10 3X031 LTG TRANSFORMER 31 (3X031) (14CC 3A AREA) CRN-E-16104(PC/M 99-061) 30548 NON-VITAL SEE LP31 59 E-26 3P34A STM GEN FEED PUMP 3A AUX LUBE OIL 30549 E-10 NON-VITAL 235 5613E27SH14A 3P49 GLAND STEAM CON!) DRAIN PUMP (DCR-TPE-90-482) 30550 E-10 NON-VITAL 347 DELETED (DCR-TPE-93-517) 235 5613E27SH12B 3V19A ISOLATED PHASE BUS FAN 3A (DCR-TPE-90-482) 30552 E-10 NON-VITAL 100 E10 SPARE (PC/M 83141) 30553 NON-VITAL 59 E-10 3P232A RCP 3A OIL LIFT PUMP 30554 NON-VITAL 347 DELETED (DCR-TPE-93-517)

CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E-855 SH.124

BREAKER LIST PAGENO. 5 INPUT DATA FILE PTP.BL.124 MCC 3A TURBINE AREA (3B05)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

347 DELETED (DCR-TPE-93-517) 328 E-10 3P19A S/G CHEMICAL ADDITION PUMP A (PC/M 93-040) 30557 NON-VITAL 59 E-10 3P19B UNIT 3 HYDRAZINE PUMP 30558 NON-VITAL 328 E-10 3P19C UNIT 3 AMMONIUN HYDROXIDE PUMP (PC/M 93-040) 30559 NON-VITAL 59 E-10 3V16 GEN OIL VAPOR EXTRACTOR 30560 NON-VITAL 59 E-10 3V14A STM GEN PUMP ROOM EXHAUST FAN 3A 30561 NON-VITAL 493 K-b 3C19 HYDROGEN PNL & PURITY METER BLOWER (CRM-E-16518(PC/M 03-050) 30562 NON-VITAL NOTE: SEE BKR LP31-29,3D01-16, GEN H2 PRESS SIGNAL TO KAYE 78 59 E-10 3V31B SPARE MAIN STEAM PENETR COOLING FAN 3B 30564 NON-VITAL 59 E-10 3P28A CONDENSER PIT SUMP PUMP 3A 30565 NON-VITAL 59 E-b0 (3C09) 3V5 TURBINE GAS DRYER REACTIVATING BLOWER (H2 GEN) 30566 NON-VITAL NOTE: SEE BKR LP31-32 347 DELETED (DCR-TPE-93-517) 59 K-b PS1A SEWAGE PUMP A 30568 NON-VITAL 353 DELETED (PC/M 93-148) 30569 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E855 SH.124

BREAKER LIST PAGENO. 6 INPUT DATA FILE PTP.BL.124 MCC 3A TURBINE AREA (3B05)

CODE BEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

78 E-10 3V6A GLAND STM CONE EXH BLOWER 3A 30570 NON-VITAL 537 E-10 SH 1 3P250 DIESEL FUEL OIL STORAGE TANK 3T36 CRN-E-17422 (PC/N 04-036) 30571 E-27 SB 104 NON-VITAL BERM SUM? PUMP 59 E-10 3P4 LUBE OIL TRANSFER PUMP #3 30572 NON-VITAL 59 E-10 MOV-3-1432 (MAIN SUM TO REHEATER 3B STOP) 30573 NON-VITAL 78 LP34A(3P04)-66 E-10 3P5 CONDENSATE TRANSFER PUMP #3 30574 4160V SWGR ROOM NON-VITAL 59 E-10 MOV-3-1431 (MAIN SUM TO REHEATER 3A STOP) 30575 NON-VITAL 59 E-10 3V32B FEEDWATER PENETRATION COOLING FAN 3B 30576 NON-VITAL 59 E-10 3X01 MAIN TRANSFORMER #3 COOLING EQUIPMENT 30577 NON-VITAL NOTE: SEE BKR 30686 78 E-10 3P14 RECEPTACLE POWER UNIT 3 4160 SWGR RN (3P14) MEZZANINE 30578 NON-VITAL 250 E-10 GENERATOR EXCITER AIR CONDITIONER (PC/M 90-070) 30579 NON-VITAL 78 E-10 3P90C SUM GEN WET LAYUP PUMP 3P90C STARTER (PCM 78-39B) 30580 NON-VITAL 78 E-1O 3P90B SUM GRE WET LAYUP PUMP 3P90B STARTER (PCM 78-39B) 30581 NON-VITAL 78 E-10 3P90A SUM GRE WET LAYUP PUMP 3P90A STARTER (PCM 78-39B) 30582 NON-VITAL 453 E-1O TRANSFORMER 3X84 SEE 3P84 CRNE-16104 (PC/N 99061) 30583 NON-VITAL 153 E-10 VITAL MOV-3856A (S.1. TEST VALVE) (PC/M 86181) 30584 353 E-10 SH1 3NP68B CONDENSER HOTWELL SAMPLE PUMP 3P68B STARTER (PC/M 93-148) 30585 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 342 RES-RESERVED BREAKER LIST 5610E-855 SH.124

BREAKER LIST PAGENO.

INPUT DATA FILE PTPBL. 125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

59 E-10 3B02 FEED FROM L.C. 3B (BKR. 3B0206) 30601 VITAL MCC 3B NON-VITAL SIDE IS SUPPLIED FROM L.C. 3E (SEE BREAKER 30651) 59 E10 SPARE 30602 VITAL 91 K-b MOV-3-861B (ISOL VLV RECIRC SUMP B TO HER PP 3B SUCTION) 30603 VITAL (DUP-369) 91 K-b MOV-3-860B (ISOL VLV RECIRC SUMP B TO HER PP 3B SUCTION) 30604 VITAL (DUP-369) 78 K-b MOV-3864B (RWST ISOL STOP VLV) 30605 VITAL 59 K-b MOV-3-535 (PRESSURIEER RELIEF ISOL) 30606 VITAL 78 E-10 MOV-3-1407 (SUM GEN Ft WTR ISOL VLV 3A) 30607 VITAL 347 5613E1C SH1 SPARE (DCR-TPE-93517) 30608 VITAL 273 E1OSH1 E16E BATT. RM A/C E16E (PC/M 87258) 30609 VITAL 256 E-1OSH1 BORIC ACID TRANSFER PUMP 3B (3P203B) (PC/M 87-258) 30610 VITAL 59 PSSG HR 3 P&V PM K-b 3V3A KMKRG CONTAIN FILTER FAN 3A 30611 LP38(3P05)-b VITAL NOTE: SEE BKR LP36-26 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 56b0-E855 S1L125

BREAKER LIST PAGENO. 2 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

431 E1OSH1 PWR VITAL POWER FEED TO BREAKERS 30669, 30688 & 30689 (PC/M 97039) 30612 E-348 VITAL THROUGH SLUGS MOUNTED IN MCC COMPARTMENT 17D.

E-8-8 59 CONTAIN ENTRANCE E-10 MOV-3-744B RCS INLET ISOL FROM HER 30613 LP37-22 VITAL TO ABOVE IN REF. OPENING BREAKER NO. 22 ALSO REMOVES HEATER POWER FROM MOV 866B A CAUTON: AND MOV 8 65EV 280 E-10 RECEPT 480 V. PWR FEED TO H2 RECOMBINER FOR UNIT-3 OR UNIT-4 (RECP 18/1) 30614 VITAL (PC/M 91-028) 59 E-10 MOV-3-750 HER INLET ISOL FROM RCS 30615 VITAL 78 E-10 MOV-3-862B (RWST TO SI PUMPS) 30616 VITAL 78 E-10 MOV-3-749B HER HT EEC CCW DISCH 30617 VITAL 59 E-10 MOV-3-1402 S/G 3C MAIN STEAM STOP BYPASS VALVE 30618 VITAL 199 E-10 3H6 CONTAINMENT ELEVATOR NO. 3 PC/M 84-202 (PC/M 89-253) 30619 NON-VITAL 347 E-28 3Y05A CVI FOR INVERTER 3Y05 (DCR-TPE-93-517) 30620 SH. 63A VITAL 59 CONTAIN ENTRANCE E-10 MOV-3-866B (SAFETY INJ LOOP B HOT LEG) 30621 LP37-22 VITAL

IN REF. TO ABOVE OPENING BREAKER NO. 22 ALSO REMOVES HEATER POWER FROM MOV CAUTION 865B AND MOV 744B CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610-E855 SH.125

BREAKER LIST PAGENO. 3 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

59 E-10 MOV-3-843B (BORON SI VALVE LOOP B, COLD LEG) 30622 VITAL 59 E-10 MOV-3-1421 (SUM GEN FEED PP 3B DISCH VALVE) 30623 VITAL 59 E-10 CCW RETURN FROM NORMAL CONTAINMENT COOLERS 30624 VITAL MOV-3-1418 59 E-10 MOV-3-863B (RECIRC. SUPPLY TO HHSI PP & CONTAIN SPRAY) 30626 VITAL 78 E-10 3V9 CONTAINMENT PURGE SUPPLY FAN #3 30628 VITAL 140 E-10 3V2A RK-CRDM COOLER FAN 3A (DUP-812) 30629 VITAL 83 E10 SPACE (PC/M 84-84) 30630 VITAL 78 CONTAIN ENTRANCE E-10 MOV-3-865B (ACCUMULATOR 3B DISCHARGE STOP) 30631 LP-37-22 VITAL 59 E-10 MOV-3-880B (CONTAIN SPRAY PP DISCH. ISOL. 3B) 30632 VITAL

IN REF. TO ABOVE CAUTION: OPENING BREAKER NO. 22 ALSO REMOVES HEATER POWER FROM MOV 744A AND MOV 744B 78 E-10 MOV-3-350 (BORIC ACID SUPPLY TO CHARGING PP SUCTION 30633 VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610E855 SH.125

BREAKER LIST PAGENO. 4 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

78 E-10 MOV-3-381 REACTOR COOL PP SEAL WTR RETURN LINE 30634 VITAL 255 E-10 3D25 3B1 BATTERY CHARGER (PC/M 88-350) 30635 VITAL 575 E-10 E16A/E17A S76 (TRANSFER SW) FOR CONTROL NM A/C A CRN-E-18173(PC/M 10-007) 30636 E-27 SH 96A VITAL ALSO SEE BEN 40698 59 E-10 MOV-3-73O (COOLING WTR RETURN ISOL) 30637 VITAL 59 E-1O MOV-3-626 (THERMAL BARRIER CCW ISOL) 30638 VITAL 59 E-10 MOV-3-716B (COME COOLING WTR TO RCP) 30639 VITAL 59 E-10 3V19B ISOLATED PHASE BUS FAN 3B 30640 NON-VITAL 59 E-1O MOV-3-1425 (STM GEN 3C BLOWDOWN SAMPLING STOP) 30641 VITAL 97 (PC/M 84171) 347 DELETED (DCR-TPE-93-517) 153 E-10 VITAL MOV-3-856B (S.I. TEST VALVE) (PC/M 86-181) 30647 78 E-10 3X82 3C24 PART LENGTH ROD CONTROL CABINET #3 PANEL 3P82 (DUP-O64) 30648 NON-VITAL NOTE: SEE BREAKER 3P06-15 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV 317 RES-RESERVED BREAKER LIST 5610-E855 SH125

BREAKER LIST PAGENO. S INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CRT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

347 E-10 5-79 D.C. ENCLOSURE BUILDING HVAC AIR HANDLING UNIT (DCR-TPE-93-517) 30649 NON-VITAL VIA DISC. SW NS-79 59 CONTAIN ENTRANCE E-10 3V30A EMERG. CONTAINMENT COOLER FAN 3A 30650 LP-37-18 VITAL

- - - OPENING BREAKER NO. 18 ALSO REMOVES HEATER POWER FROM EMERG.

CAUTION CONTAINMENT COOLER FANS 3B AND 3C 59 K-b MCC 3B N-VITAL INCOMING FEED FROM LC. 3E (BKR 34108) 30651 NON-VITAL 347 E-10 V-8B AUX BUILDING EKE FAN 3B (V-8B) (DCR-TPE-93-517) 30652 VITAL 199 E-10 RCPT 17-17 RECEPTACLE 17 (480V) (CONTAINMENT) (PC/M 89-253) 30653 NON-VITAL 59 E-b0 3X18 ROD CONTROL SYSTEM BACKUP TRANSFORMER 3 30654 NON-VITAL 347 K-b 3Y02A CVI FOR INVERTER 3Y02 (DCR-TPE-93-517) 30655 E-28 SH.63A VITAL 273 E1OSH1 SPARE (PC/M 87258) 30657 NON-VITAL 453 E-10 3X036 LTG. TRANSFORMER #36 (T3P11) (CONTAINMENT EL. 18) 30658 NON-VITAL SEE LP36 CRN-E-16104(PC/M 99-061) 453 E-10 3X311 LTG. TRANSFORMER #311 AUX. BLDG AREA EAST CRN-E-16104(PC/M 99-061) 30659 NON-VITAL SEE LP311/311A 347 E-b0 RCPT 5 RECEPTACLE #5 (480V) (AUX. BLDG AREA WEST) (DCR-TPE-93-517) 30661 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610E855 SH.125

BREAKER LIST PAGENO. 6 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP NO* - BREAKER LOCATION CET DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

59 E-10 3P218A RCS DRAIN TANK PUMP 3A 30662 NON-VITAL 59 E-10 3V20 CONTAIN. PURGE EXHAUST FAN #3 30663 VITAL 59 PSSG NR 3 P&V RN E-10 3P16B PRIMARY WTR MAKEUP PUMP 3B 30664 LP-38 (3P05) 10 NON-VITAL 59 E-10 3V31A MAIN Sm PENETRATION COOLING FAN 3A 30665 NON-VITAL 59 E-10 3V14B Sm GEN PUMP ROOM EXHAUST FAN 3B 30666 NON-VITAL 59 E-10 3P23A CONTAINMENT SUMP PUMP 3A 30667 NON-VITAL 78 E-10 3C203 CONTAINMENT HYDROGEN MONITORS ANALYEER CH. B 3C203 30668 VITAL (5177115E-05) (PC/M 79132C) 431 E-10 LCV-3-115C (VOLUME CONTROL TANK LOW LEVEL ISOL) (PC/M 97-039) 30669 E-25, SH 34A VITAL (POWERED BY BREAKER 30612 THROUGH SLUGS IN MCC COMPARTMENT 17D 78 E-10 3X203A CONTAINMENT HYDROGEN MONITORS HEAT TRACING CHB 3X203A 30670 VITAL (5177115E05) (PC/M 79-132C) 59 E-10 3V32A FEEDWATER PENETRATION COOLING FAN 3A 30671 NON-VITAL 59 E-10 3V6B GLAND SUM CONDENSER EXHAUST BLOWER 3B 30672 NON-VITAL 78 E-10 3P11 MISC CONTAINMENT DISTRIBUTION PNL NO. 2 3P11 (DUP-064) 30673 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610-E-855 SH.125

BREAKER LIST PAGENO. 7 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

378 E-10 RCPT RECEPTACLE #6 ATE. BLDG AREA EAST. (CRN-E-15265 PC/M 95-085) 30674 NON-VITAL 59 E-10 3X02 ATE TRANSFORMER COOLING EQUIPMENT (ALTERNATE) #3 30675 NON-VITAL NOTE: SEE BREAKER 30544 192 E-i0 3V36 CONTAIN AIR PARTICULATE & GAS MONITOR #3 (RD-li & RD-12 30678 VITAL (PC/M 88-530) 59 E-i0 3P232B RCP 3B OIL LIFT PUMP 30679 NON-VITAL 453 Ei0 3X36A LTG TRANSFORMER #36A (PC/M 89253) CRN-E-16104(PC/M 99061) 30680 E-204 NON-VITAL SEE LP36A 59 E-i0 3P34B Sfl! GEN FEED PUMP 3B ATE OIL PUMP 30681 NON-VITAL 78 E-iO 3X03 STARTUP TRANSFORMER #3 COOLING EQUIPMENT (ALTERNATE) 30682 NON-VITAL NOTE: SEE BREAKER 30536 78 E-200 F23 DP-7 SWITCHYARD DISTRIBUTION TRANSF SWITCH DP-7 30684 E-i0 NON-VITAL 59 E-10 3H9 NEW FUEL ELEVATOR #3 30685 NON-VITAL 59 E-i0 3X01 MAIN TRANSFORMER #3 COOLING EQUIPMENT (ALTERNATE) 30686 NON-VITAL NOTE: SEE BREAKER 30577 59 E-i0 3P2BB CONDENSATE PIT SUMP PUMP 3B 30687 NON-VITAL 431 E-i0 PWR MOV-3-1433 MAIN STEAM TO REHEATER 3C (POWERED BY (PC/M 97-039) 30688 E-29, SH. 17 VITAL BREAKER 30612 THROUGH SLUGS IN MCC COMPARTMENT 17D)

CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610E855 511.125

BREAKER LIST PAGENO. 8 INPUT DATA FILE PTP.BL.125 MCC 3B (REACTOR AREA) (3B06)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

431 E-10 MOV-3-1434 (MAIN 5PM TO REHEATER 3D) (PC/N 97-039) 30689 E-29, SH. 17 VITAL (POWERED BY BREAKER 30612 THROUGH SLUGS IN MCC COMPARTMENT 17D) 59 E-10 P51E SEWAGE PUMP B 30690 NON-VITAL 78 E-10 DP13 CONTROL BLDG KITCHEN PNL BKR BOX (DP 13) 30691 NON-VITAL 65 E-10 3X321 TRANSF 3X-321 FOR LP321 SAS REPAIR FACILITY 30692 E-200 NON-VITAL (PC/N 83-185) 189 E-10 3X255 DIST. PANEL 3DP435 VIA XENR 3X255 (PC/N 86-190) 30693 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 317 RES-RESERVED BREAKER LIST 5610E855 SH.125

BREAKER LIST PAGENO.

INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

59 H-b 3B03 FEED FROM L.C. 3C (BKR. 3B03) 30701 VITAL MCC 3C NON-VITAL SIDE IS SUPPLIED FROM L.C. 3G (SEE BREAKER 30750) 59 E-10 SPARE 30702 VITAL 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 347 DELETED (DCR-TPE-93-517) 59 E-10 NOV-878B (SI-PUMP DISCHARGE HEADER ISOL.) 30708 VITAL 347 DELETED (DCR-TPE-93-517) 234 5613E105H1 3V65A SWGR 3D RH. SUPPLY FAN 3A1 (FEED TO LOCAL STARTER) (PC/H 87-264) 30710 VI TAD 91 E-b0 NOV-3-860A (RECIRC SOMP A TO RHR PP 3A SUCTION) 30711 VITAL (DUP-369)

CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 5610-E-855 SE.126

BREAKER LIST PAGENO. 2 INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

78 E-10 MOV-3-864A (RWST ISOL STOP VALVE) 30712 VITAL 59 E-10 MOV-3-536 (PRESSURIZER RELIEF ISOL) 30713 VITAL 59 E-10 MOV-3-1426 (STM GEN 3B BLOWDOWN SAMPLING) 30714 VI TAL 256 E-10 3D02 BATTERY CHARGER 3A1 (Dli) (AC SUPPLY) NOTE: SEE BKR 3D01-43 30715 VITAL (PC/H 88-350) 78 E-10 3C202 CONTAINMENT BYDROGEN MONITOR ANALYEER CEA 3C202 30716 VITAL (5177-115-E-05) (PCM 79-132C) 347 E-10 SPARE (DCR-TPE-93-517) 30717 VITAL 59 E-10 3X202A CONTAINMENT HYDROGEN MONITOR MEAT TRACE CHA 3X202A 30718 VITAL (5177-115-E-05) (PCM 79-132C) 59 LP38(3P05)-4 E-10 3V3C CONTAIN EL 58,EMERG FILTER FAN 3C 30719 PGWY NEAR#3 P&V VITAL NOTE: SEE BREAKER LP36-28 78 E-10 MOV-3-862A (RWST TO S.I. PUMPS STOP) 30720 VITAL 59 H-b MOV-3-749A (RER EX CC ICR ISOL) 30721 VITAL 59 LP37-20 E-10 R.C.S. INLET ISOL FROM RER MOV-3-744A 30722 CONTAIN ENTRANCE VITAL 199 E-941 SE.2 PWR MOV-3-6386 EXCESS LTDN, RCP SEAL WATER RETURN 30723 E-b0 VITAL (PC/H 89-253)

CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 5610-E-855 SM.126

BREAKER LIST PAGENO. 3 INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE EEATER BREAKER SCEEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCEED.

347 S613E1OSE1 SPARE (DCR-TPE-93-517) 30724 VITAL 59 E-10 3P203A BORIC ACID TRANSFER PUMP 3A 30725 VITAL 59 E-10 PWR MOV-3-8S3A RECIRC SUPPLY TO 111151 PP & CONTAIN SPRAY 30726 VITAL 347 LP38(3P05)-8 E-10 3V2B CRDM COOLER FAN 3B (DCR-TPE-93-517) 30727 PG NEAR P&V RN VITAL NOTE: PGWY NEAR *3 PIPE & VALVE ROOM 91 E-10 MOV-3-861A (RECIRC SUMP A TO RER PP 3A SUCTION 30728 VITAL (DUP-369) 59 LP37-18 E-10 3V30C EMERG CONTAIN COOLER FAN 3C 30729 CONTAIN ENTRANCE VITAL 347 DELETED (DCR-TPE-93-517) 78 E-10 MOV-3-751 R.E.R. INLET ISOL. VLV. FROM R.C.S. 30731 VITAL 59 LP37-20 E-10 MOV-3-866A SAFETY INJECTION LOOP A EOT LEG 30732 CONTAIN ENTRANCE VITAL 59 LP37-24 E-10 MOV-3-865C (ACCUMULATOR 3C DISCE STOP) 30733 CONTAIN ENTRANCE VITAL 423 E-10 P207A CONCENTRATE MOLD TANK TRANSF. PUMP NO. 3 (PC/M 95-040) 30734 VITAL (ABANDONED-IN-PLACE LEADS LIFTED) 453 E-10 LP38 SPACE ETR TRANSF. NO. 38 16CC 3C AREA CRN-E-16104 (PC/N 99-061) 30735 NON-VITAL SEE LP38 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 5610-E-855 SE.126

BREAKER LIST PAGENO. 4 INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE EEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCEED.

59 E-10 RCPT 7 RECEPTACLE NO. 7 (480V) (AliT BLDG AREA NORTE) 30736 VITAL 59 B-b LOOP A & B EOT LEG 5.1. STOP NOV-3-869 30737 VITAL 78 E-b0 MOV-3-843A (BORON INJ TANK DISCE. TO LOOP A) 30738 VITAL 59 E-10 MOV-3-1408 (STN GEN 3B FEED WTR ISOL) 30739 VITAL 407 E-26, SH.6 P42A WDS AliT STN CONDENSATE RECOVERY PUMP A (PC/H 95-081) 30740 E-10 NON-VITAL ABANDONED IN PLACE LEADS LIFTED 59 H-b MOV-3-880A (CONTAIN SPRAY PP DISCE ISOL) 30741 VITAL 59 LP38(3P05)-5 E-b0 3V1C NORMAL CONTAINMENT COOLER FAN 3C 30742 PGWY NEAR#3 P&V VITAL 59 E-10 MOV-3-716A (RCP CO WTR ISOL) 30743 VITAL 347 5613E105E1 SPARE (DCR-TPE-93-517) 30744 VITAL 398 E-10 3C33 BORIC ACID EVAP CONTROL PANEL #3 (PC/N 94-141) 30745 NON-VITAL (ABANDONED IN PLACE LEADS LIFTED) 59 H-iC PWR MOV-3-872 (ALT LOW HEAD SI LINE) 30746 VITAL 59 H-b T-206 BORIC ACID BATCHING TANK MIXER 30747 VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 5610-E-855 SE.126

BREAKER LIST PAGENO. 5 INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE EEATER BREAKER SCEEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCEED.

59 E-i0 MOV-3-1401 (MAIN STM BYPASS FROM STM GEN 3B) 30748 VITAL 431 DELETED (PC/M 97-039) 30749 59 E-10 MCC MV 3C INCOMING FEED FROM L.C. 3G (BKR 31508) 30750 NON-VITAL (PC/M 82-100) 59 E-10 3P26A RES MT REMOVAL ROOM 3B AREA SUMP PUMP 3A 30751 NON-VITAL 59 E-10 3P24A RES MT REMOVAL ROOM EXCH AREA SUM? PUMP 3A 30752 NON-VITAL 59 E-10 3P25A RES HT REMOVAL ROOM 3A AREA SUMP PUMP 3A 30753 NON-VITAL 59 E-i0 P27A WDS BASEMENT SUM? PUMP 3 30754 NON-VITAL 347 E-28 3Y07A CVT FOR INVERTER 3Y07 (DCR-TPE-93-517) 30755 SE. 63A VITAL 398 E-10 3C30 GAS STRIPPER PANEL 3 NOTE: SEE BREAKER 3001-10 (PC/M 94-141) 30757 NON-VITAL (ABANDONED IN PLACE LEADS LIFTED) 209 E-10 3P12 SPENT FUEL AREA MISC POWER PANEL OP-li (DCR-89-235) 30758 NON-VITAL 347 E-28 3YO1A CVT FOR INVERTER 3Y01 (DCR-TPE-93-517) 30759 SE. 63A VITAL 199 E-i0 RCPT 8 RECEPTACLE NO. 8 (480V) CASK WASM AREA (PC/M 89-253) 30760 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 56i0-E-855 SM.126

BREAKER LIST PAGENO. 6 INPUT DATA FILE PTP.BL.126 14CC 3C (FUEL AREA) (3B07)

CODE EEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMEER PNL SCHED.

59 E-l0 3P204A GAS STRIPPER FEED PUMP 3 30761 NON-VITAL 59 E-10 3P232C RCP 3C OIL LIFT PUMP 3P232C (DUP-064) 30762 NON-VITAL 494 E-10 3C09 FUEL TRANSFER CONTROL CONSOLE FOR CRN-E-16503 (PC/N 03-050) 30763 NON-VITAL REACTOR FRAME EOIST 3H7B.

461 E-10 DEAERATOR VACUUM PUMP 3P35 OIL EEATER (PC/N 00-005) 30765 NON-VITAL ABANDONED IN PLACE-LEADS LIFTED 214 E-10 3X259 ROD POSITION CVT (PC/N 88-582) 30766 NON-VITAL 453 E-10 3X039 LTG TRANSFORMER NO. 39 (3X039) (SPENT FUEL PIT) 30767 NON-VITAL SEE LP39 CRN-E-16104 (PC/N 99-061) 453 E-10 3X037 LTG TRANSFORMER NO. 37 (3X037) CRN-E-16104 (PC/N 99-061) 30768 NON-VITAL (CONTAINMENT ENTRANCE) SEE LP37 59 H-b 3V21 SPENT FUEL PIT EXHAUST FAN 30769 NON-VITAL 59 H-b 3V12 SPENT FUEL PIT NT EXCHANGER ROOM SUPPLY FAN 30770 NON-VITAL 59 H-b 3PbO MISC CONT DISTRIB PANEL NO. 1 30771 NON-VITAL 59 LP38(3P05)-12 H-b C200 WDS GAS COMPRESSOR #3 30773 PGWY NR#3 P&V EM NON-VITAL NOTE: PGWY NEAR 43 PIPE & VALVE RN 461 H-b 3P252 DEAERATOR VACUUM PUMP #3 (PC/N 00-005) 30774 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 56b0-E-855 SH.126

BREAKER LIST PAGENO. 7 INPUT DATA FILE PTP.BL.126 MCC 3C (FUEL AREA) (3B07)

CODE EEATER BREAKER SCEEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCEED.

431 E-10 PWR PRIMARY WATER MAKEUP TO TEE CCW SURGE TANK, MOV-3-832 (PC/M 97-039)30775 E-25, SE 28M VITAL 59 B-b 3V13 NEW FUEL STORAGE AREA SUPPLY FAN 3 30776 NON-VITAL 59 E-b0 3P213 SPENT FUEL PIT SKIMEER PUMP 30777 NON-VITAL *3 59 E-10 3P23B CONTAIN SUMP PUNT 3B 30778 NON-VITAL 461 E-10 SPARE (PC/M 00-005) 30779 NON-VITAL 347 E-10 NO BREAKER; CONTROL TRANSFORMER COMPARTMENT FOR (DCR-TPE-93-517) 30780 NON-VITAL SFP EKE. FAN B AND DEAERATOR VACUUM PUN?

59 E-10 P206A MONITOR TANK PUMP 30785 NON-VITAL 423 E-b0 P221A WASTE EVAP CONE PUMP *3 (MONITOR TANK RM) (PC/M 95-040) 30786 NON-VITAL (ABANDONED-IN-PLACE LEADS LIFTED) 59 E-10 3P218B RCS DRAIN TANK PUMP 3B 30787 NON-VITAL 59 E-b0 3P209 REFUELING WATER PURIFICATION PUMP 3 30788 NON-VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 280 RES-RESERVED BREAKER LIST 5610-E-855 SE.126

BREAKER LIST PAGENO.

INPUT DATA FILE PTP.BL.126A MCC 3D (WASTE AREA A) (3B08) VITAL SECTION CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

347 5613E10SH2 SPARE (DCRTPE-93-517) 30801 VITAL 253 5613E10SH2 3B50 FEED FROM LC-3H ELEC. EQUIP. ROOM AREA (PC/M 87-258) 30802 VITAL 347 5613E10SH2 SPARE (DCRTPE93517) 30803 VITAL 266 5613E10SH2 Vii AUX BLDG AIR SUPPLY FAN (PCIM 87-258) 30804 VITAL 262 E12 4D25A BATTERY CHARGER 4A2 (PC/M 88350) 30805 VITAL 271 PSSG HR 3 P&V EM 5613E25SH11C 3V3B CONTAIN EL. 58 EMERG. FILTER 3B (PC/M 87-258) 30806 LP38 (3P05)-2 VITAL NOTE: SEE BEA LP36-24 253 Hil CONTROL BUILDING ELEVATOR (PC/M 87-258) 30807 VITAL 538 Ei60 BATTERY ROOM AIR CONDITIONING UNIT C CRN-E-i7444 (PCJM 07-02i) 30808 VITAL 271 E-27,SH.45F V-29B CONTROL ROOM HVAC SUPPLY FAN-SF-iB (PC/M 87-258) 30809 E-9 VITAL 347 DELETED (DCR-TPE-93-5i7) 347 DELETED (DCR-TPE-93-5i7) 347 MOV-6550 DAMPER (Di4) FOR TOILET FAN V28 (DCR-TPE-93-5i7) 308i3 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 330 RES-RESERVED BREAKER LIST 56i0E855 SH.i26A

BREAKER LIST PAGENO. 2 INPUT DATA FILE PTP.BL.126A MCC 3D (WASTE AREA A) (3B08) VITAL SECTION CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

278 MOV-6549 DAMPER (022) FOR KITCHEN FAN V56 (PC/N 87-258) 30814 VITAL 278 ND-i DAMPER DI-B FOR MAKE-UP AIR (PC/M 87-258) 30815 VITAL 453 5613E10SH2 3X312 NORMAL/EMERG. LTG. XFMR 312 CRN-E16104 (PC/N 99-061) 30816 VITAL SEE DP312 & DP312A 347 Ei0, E200 SPARE (DCRTPE-93517) 30817 VITAL 270 5613E10SH2 S74B COMPUTER ROOM CHILLER B (PC/M 87-258) 30818 VITAL 347 5613E10SH2 SPARE (DCRTPE93517) 30819 VITAL 271 CONTAIN ENTRANCE 5613E25SH110 3V30B ENERG. CONTAIN COOLER FAN 3B (PC/N 87-258) 30820 LP37-18 VITAL 347 SPARE (DCRTPE93517) 30821 VITAL 253 5613E25SH32A MOV-3-14i7 (NORM CONTAIN COOLER CCW INLET) (PC/N 87-258) 30822 VITAL 253 E16C E17C CONTROL RN AIR COND. C (ROOF) (PC/M 87-258) 30823 VITAL 253 PWR VITAL AC MAINTENANCE & TRANSFORMER. UNIT 3/UNIT 4 (PC/M 87-258) 30824 VITAL PAGE SYSTEM (NORM. SUPP.) (PAGE & SITE ENTRANCEWAY) 387 Ei0 SH2 SPARE (PC/N 93108) 30825 347 DELETED (DCR-TPE-93-517) 264 5613E10SH2 4002A BATTERY CHARGER 4B2 (PC/MS 88350 & PC/N 87-258) 30828 VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 330 RES-RESERVED BREAKER LIST 5610E855 SH.126A

BREAKER LIST PAGENO. 3 INPUT DATA FILE PTP.BL.126A MCC 3D (WASTE AREA A) (3B08) VITAL SECTION CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SCHED.

543 PSSG NR 3 P&V PM 5613E10SH2 3V1D NORMAL CONTAIN COOLER FAN 3D (CRN-E-17528 PC/N 87-258) 30829 LP38(3P05)-6 VITAL 347 5613E10SH2 S78B COMPUTER ROOM AHU.B2 (DCR-TPE-93-517) 30830 VITAL 253 5613E10SN2 flQR MOV878A (S.I. Pp DISCH. HEADER ISOL) (PC/M 87258) 30831 VITAL 262 5613E105H2 MOV-3-1404 S/G 3B 5Th! SUPPLY TC AUX. FEED WTR. PUMP (PC/N 87-258) 30833 VITAL 271 5613E105H2 SPARE (PC/M 87258) 30880 VITAL 251 5613E105H2 E231/V77 ELECT. EQUIPMENT RN. CONDENSER UNIT E231/V77 (PC/M 89-069) 30890 VITAL 347 DELETED (DCR-TPE-93-517) 347 5613E105H2 577B - COMPUTER ROOM AWl Ri (DCR-TPE-93-517) 30893 VITAL 347 5613E105H2 MOV6543B CONTROL ROOM AIR CIRCULATION DAMPER D-11B (DCR-TPE-93-517) 30894 VITAL 347 5613E105N2 575B CABLE SPREAD ROOM ANtI (DCR-TPE-93-517) 30895 VITAL 347 5613E105H2 SPARE (DCRTPE-93-517) 30896 VITAL CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 330 RES-RESERVED BREAKER LIST 5610E855 SH.126A

BREAKER LIST PAGENO.

INPUT DATA FILE PTP.BL.127 MCC 3E INTAKE AREA (3B09)

CODE EEATER BREAKER SCEEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NONEER PNL SCHED.

E-9 BlO MCC 3E SUPPLY BREAKER FROM MCCF (1001) 30901 E-9 4B09 TIE BREAKER 3E-4E FEED FROM MCC 4E 30902 299 E-9 H2 INTAKE STRUCTURE BRIDGE CRANE (PC/H 91-133) 30903 299 E-9 3P15 TRASH RAKE HOIST. DIST. PNL (PC/M 89-253) (PC/M 91-133) 30904 299 E-9 RCPT 11/12 RECEPTACLE #11 AND #12 (480V) (PC/M 91-133) 30905 299 E-9 P234A FIRE WATER JOCKEY STARTER N234A FOR PUMP (PC/H 91-133) 30906 P234A PC/H 89-253)

E-9 HOV-3-1416 (CIRC WTR PP 3A1 DISC! VLV) 30907 E-9 MOV-3-1414 (CIRC WTR PP 3B1 DISCH VLV) 30908 299 E-9 SPARE (PC/M 92-133) 30911 E-9 3P13B CIRC LUBE WTR PUMP 3B 30912 A PSSG NE 3 P&V RH E-9 3P14 SCREEN WASH PUMP 3 30913 LP38 (3P05) -32 E-9 MOV-3-1415 (CIRC WTR PP 3A2 DISGH VLV) 30916 E-9 MOV-3-1413 (CIRC WTR PP 3B2 DISC!! VLV) 30917 480 PSSG NE 3 P&V RN E-9 P14 SCREEN WASH PUMP S CRN-E-16368(PC/M 02-065) 30918 LP38 (3P05) -31 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 301 RES-RESERVED BREAKER LIST 5610-E-855 SH.127

BREAKER LIST PAGENO. 2 INPUT DATA FILE PTP.BL.127 MCC 3E INTAKE AREA (3B09)

CODE HEATER BREAKER SCHEMATIC EQUIP. NO. BREAKER LOCATION CKT DESC EQUIPMENT AND OR LOCATION NUMBER PNL SIDHED.

299 E-9 SPARE (PC/H 91-133) 30919 299 E-9 SPARE (PC/H 91-133) 30920 E-9 3F1B TRAVELING SCREEN 3B1 30921 E-9 3F1D TRAVELING SCREEN 3E2 30922 DELETED (PC/H 91-133) 30923 299 E-9 3F1A TRAVELING SCREEN 3A1 30924 E-9 3F1C TRAVELING SCREEN 3A2 30925 453 E-200, E-9 FDR FEED TO LEG PANEL 314 TRANSFORMER (INTAKE AREA) 30927 SEE LP314 CRN-E-16104 (PC/H 99-061) 299 E-9 FDR SPARE (PC/H 91-133) 30928 CODES: NAB-NOT AS BUILT TURKEY POINT PLANT UNITS 3 & 4 REV. 301 RES-RESERVED BREAKER LIST 5610-E-855 SH.127

r; 1

I current revision ind th t there are no unresolved TWR AIs.

TWR A]# AR 00402402 Assgn 02

-/ J bi1 ,3 Ji1O1 FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR STATION NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE ILC 26 NRC RETAKE EXAM ADMIN JPM #4 Mark Wilson Preparei:

-, I.-,

3/.,

Date:

?fz(4- t 1

i 1 Technica(Reviewer (Print/Sign) Date L I ./

Discipline TrainingSupervisor (PiiiSign) Date F-630-Rev. 1 (01/31/08 - 0-NTP-002)

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 022033021100 Determine the Airborne Task

Title:

Activity Dose Rate JPM No: ILC 26 NRC Retake A.3 K/A

Reference:

2.3.4 SRO 3.7 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: Classroom Simulated Performance Actual Performance Yes Classroom Yes Simulator Plant 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 An NLO has been assigned the task of performing a valve lineup in the Unit 4 Safety Injection Pump Room. The dose rates for the area are located on the survey map. In this area, there is some airborne activity. From experience, the NLO knows that it will take 60 minutes to perform the valve lineup without a respirator, or 80 minutes to complete the job with a respirator. If the job is done without a respirator, the NLO will receive 2 DAC-hours of internal exposure. (NOTE: Ignore transient time in dose calculation, use only data at the work location.)

INITIATING CUE You have been directed to determine the dose the NLO will receive if he doesnt wear a respirator while performing the valve lineup and the dose he will receive if he wears a respirator. Report back to the Shift Manager which method will result in the lowest dose and keep the exposure ALARA.

ADDITIONAL INFORMATION 2000 DAC-Hours is equivalent to the Annual Federal TEDE exposure limit.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

NUREG 1021 Rev9AppendixC

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

Dose is correctly calculated with a respirator and without a respirator and determines that the job should be performed without a respirator and reports findings.

Required Materials:

Calculator

Unit 4 Safety Injection Pump Room Survey Map

Ops RWP

Valve Locator Map General

References:

O-ADM-600, RADIATION PROTECTION MANUAL

RP-AA-104, ALARA PROGRAM Time Critical Task: No Validation Time: 10 minutes NUREG 1021 Rev 9 Appendix C

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

NIA Load Lesson NIA Ensure Simulator Operator Checklist is complete NIA NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 8 Form ES-C-I Denote critical steps with a check mark()

Start Time STEP Calculates NLO dose without a respirator.

1 : SAT U N SAT Accurately calculates NLO dose without a respirator.

(1.0 hour0 days 0 hours 0 weeks 0 months ) x (34 mR/hour) = 34 mRem Standard:

(2 DAC hours) x (2.5 mRem/DAC-hour) = 5.0 mRem Total = (34.0) + (5.0 mRem) = 39.0 mRem Cue Comment NOTE:

NUREG 1021 Rev 9 Appendix C

Lppendix C Page 5 of 8 Form ES-C-I Calculates NLO dose with a respirator. -

STEP 2 : SAT q

UNSAT Accurately calculates NLO dose with a respirator.

Standard:

(1.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months ) x (34 mRem/hour) = 45.22 mRem (44-46 mRem)

Cue Comment NOTE:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 8 Form ES-C-I Determines that the job should be performed without a respirator.

STEP 3 : SAT q Reports findings UNSAT

. Determines that the job should be performed without a respirator.

Standard:

. Reports findings.

Cue Comment NOTE:

Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time NUREG 1021 Rev9AppendixC

Appendix C I Page 7 of 8 Form ES-C-I Verification of Completion Job Performance Measure No. ILC 26 NRC Retake A.3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Exam iners signature and date:

NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET The examiner will explain the initial CQndItIorls which steps to stmulate or discuss and prQvld& initiating. cues..

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

INITIAL CONDITIONS An NLO has been assigned the task of performing a valve lineup in the Unit 4 Safety Injection Pump Room. The dose rates for the area are located on the survey map. In this area, there is some airborne activity. From experience, the NLO knows that it will take 60 minutes to perform the valve lineup without a respirator, or 80 minutes to complete the job with a respirator. If the job is done without a respirator, the NLO will receive 2 DAC-hours of internal exposure. (NOTE: Ignore transient time in dose calculation, use only data at the work location.)

INITIATING CUE You have been directed to determine the dose the NLO will receive if he doesnt wear a respirator while performing the valve lineup and the dose he will receive if he wears a respirator. Report back to the Shift Manager which method will result in the lowest dose and keep the exposure ALARA.

ADDITIONAL INFORMATION

2000 DAC-Hours is equivalent to the Annual Federal TEDE exposure limit.

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.

NUREG 1021 Rev 9 Appendix C

Tvrkey.Po1utNucJeirPThnt FPL RADIATION WORK PERMIT RWP TWe Rontin Operations and St]rveilJances RM Nutnbcr:

1c0Y

XX-0002 Rev.03 1fl1JThllDfl1F XX-0002 1W/P Tya:J0B SP8CWIC RWp tntust ]3eeln )at Close eq Dnt:

dcrrpm 79000 Acinal Dose J Acluni Uourst

)301141n1L1 I Elovatloii - 1

[ Aw1Ifary Bulidhig Common T ALL General Area f Ru1wasCefluiIdlng -.

ALL . General Area RCA Yan[- C!mnmon Areas ALL OcncralAiJa z:

Auxiliary ulIdIng 0/A Gamma I!ao 1 <.1 -O 1

L Auxillory BulMngG/AConlarniiiatlon <1000 dpm/IOOcm2 Au.dflary Building 0!A Mrborne c30 DAC RWI3 0/A Gamma . 1 <170 mrern4ir RWBG/A Conlanilnedon R\V130/A Airborne

. 1 <1000 dpaVltlOcm2

. I 30. flA(

RCA Yard/lSW/RWST .

(1 10 . mreinthr I P riothrn . . .. .. . .

I__________

I 1 Rodla(ln Prolecilon Routine Avilios AOCIVC 2 J Operations Department Routine Atlv1t(es ] M.tiv 3 ChemIstry DcprUncnt RoutinoActivitlea AclivO 4 Firowatch Personnel ooIine Activilics .

AOt1VO

cn,ja:z.

tiii sir! 110051 A TLD and ElectronIc Dosimeter are roquired Co enter tlto RCA.

A PAM or Tciometric Dosimeter Is equlrcd lor working In a high noise area, Rovlew current survey data prior to csiterin the work area.

Notify the work araa RP Tcehiiitan prior to ellttrlnB ovthend areas.

RP Coverage Is reqolred 10 remove nnflerlat, toots or muIptnciit from a Contaminated ,Vca.

LAPPrOVCVTIIIO _. I tftua . IP LSJPL1RVISOR CARI3ERRY, BRiAN J I II161XX Page 1

Turkey Point Nttclear Plaut tspL RADIATION WORK PERMIT 1tI) Ohife, -

2 XXOO.O2 Rev.O Task Dcj,jplon Operations Department Rotitine Activities Task Status Active 18:00 -

oDnsej00mrcrn I EstinateT120O0 I,oeked Tflh.Rnd:NO A-I IhRah Yes I Igh-Coiitnn.innIlott Yes fit-pnrticic: Yes

, 1Ii Gamma DOse ttlt Cm.mp Rate

&;;;r Authorized Access 1 Neutron Area aceess is not authorized Airborne Raciioaclivity Area access, UrloiThgs Required - A shifliy High RadIion Area brie hag is required for HRA access Contom1atIon Control To work in a High (ontunitnaLtonArea one or more oC the following may be required: A> -

Oecontnrninate area!cquipincnt to <100,000 dpm/l00cin (Pccon(anifnatlon shall be performed as directed by RP), l) Use fIEIA ventilation I vacuum, C) Keep area/equipment wet during 1 D) Cover Or contain nrcaleqaiprneiit repairs

- Notify RP prior ho start of work wHit Highly Contaminated materials Poly bans with absorbetit material should be used to conwin liquids when opening radioactive systems l)osimeiry PAM or Tela,nctricOoeirwtcr is required for working in a high noIse area and/or a High Radiation Area lxpøsur Control. Notify ALAR.A if temporary shIelding ncds to be moved or modified Use tile Valve t,ocn;or eok to 1ocet time valve. Uc iho book not your dose.

Job Coverage in Hot Particle Areas, RP coveigo isreqimired, Worker shall receive a Hot Porliole surve at once every two hours and upon exit from the 1 lot Purtlqto Area;Prior to wk ccntaCl RP to diseuss speotfic Hot fatiMa controls as specified In 0-IIPS-027.)

- Continuous RI> coverage Is required for ocning any portion of4he resin hi) piping

- RI> coverage Is required to remove material, tools or equipment ftom a Contaminated An,n.

Protective CIthing - Shoe oveis nndgloves arc (tic minimum protective clothing required for entry into a Con Inmiunted Area. (A bib coal is required hi light arcus lxim protective clothing Is required to work with HlghlyCon laminated materials, the minimum dress requirenlent Is a MI set of protective clothing, extra glcveammd/

or slice. covers.

. A face shield may be required In a Hut Particle Area. the minimum dress requirement is a fill Set of protective ebmihing, disposable outer coveralls, extre gloves, extra shoe covers and a Thee shitd Water resistant outer protecilvo clothing is reqitlrect to work In n wet Contamination ,\reO

- The minimum Pmtectlve clothing required for opeiTng rcsi loading system and or vealinglopeniog omsy radioactive system Is a hih coat and gloves

- When operating valves across contarniminted boundaries, Operalom shall remove gloves nd discard them into (ho trash receptacte kmcritcd in the area and proccd directly to a frisking station and perform ullsk. A Ml set of proteedve clothing Is requIred for kneeling or crawling in a Contaminated Area -

(enahii instrmiet1ans rJca instructions:

.J,nstrue(lons Page 3

nay I2)4i LiGHT PT l)AY:

Cl At U2I OtI)C, C)

I4) tOGkCZThiMIt*i I (I DCX mill, L WWt4 C4 uJ JrpWJ4%fl)M4 1$)

( -4Q WATffl4GQfli (f) aO1PMXti (1) )&.CIlfWJlQ LCJlfiY ItOI J.21 1) I (A) 2 DAhours ll1 tIRTOLCOAI.)SllI(it10H I4(S$ dil<J J,Ct-Il.

AIM)1flI

,iOfI1OiALI) fOlP.T1OU j f

ØZ HPS I1()4,,. 2hA.

i 14 il4 I?4. 27JL LUC!L u 4L%M 2Mfr I44 10 JJJ _(& ° tfOA n, j d ])1)?1YI 04pi DAVE; I. I

I I

0 w

current revision and th it there are no unresolved TWR ills.

Date vered: Initials:

TWR A!# AR 00402402 Assgn 02

/// V

.1 L

Nu o hr EThJLS]OTi FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR STATION NUCLEAR TRAIMNG DEPARTMENT JOB PERFORMANCE MEASURE ILC 26 NRC RETAKE EXAM ADMIN JPM #5 Mark Wilson Preparer:

-, I-,

Date:

eçf 1ek /3 Ii Technical Reviewer (Print/Sign) Date

,3/y/,

V Dis cipne Training Supervir (Print/Sign) Date F-630-Rev.1 (01/31/08 - Q-NTP-002)

Appendix C Job Performance Measure Form ES-C-I Worksheet Facility: Turkey Point Task No: 02201019400 Classify Event and Determine Task

Title:

PARS JPM No: ILC 26 NRC Retake A.4 K/A

Reference:

2.4.41 SRO 4.6 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance X Actual Performance Classroom X Simulator Plant 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:

UNITS 3 and 4 are at 100% Power.

4A SGFP suction pressure piping ruptured resulting in a rapid loss of both SGFPs.

The reactor trip breakers failed to automatically open.

UNIT 4 RO manually tripped the reactor.

All AFW pumps tripped on overspeed.

SC WR levels are less than 20%.

No Radiation Releases are in progress.

Containment Parameters are normal.

Wind Speed is 10 mph.

Wind Direction is from 260°

4-EOP-E.0, Reactor Trip or Safety Injection, has been exited and actions are being taken per the appropriate EOP procedure.

Initiating Cue:

You are the Emergency Coordinator in the Control Room. Given the initial conditions classify the event using 0-EPIP-20101, Duties of Emergency Coordinator, and if necessary, issue protective action recommendations using 0-EPIP-20134, Offsite Notifications and Protective Action Recommendations.

By raising your hand will signify that you have completed the event declaration. At that time the Examiner will provide you with a Florida State Notification Form. You will then complete the Florida State Notification Form using 0-EPIP-20134, Offsite Notifications and Protective Action Recommendations.

When you have completed the Florida State Notification Form, raise your hand to inform the Examiner you are done.

There is an element of this task that is Time Critical.

HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!

NUREG 1021 Rev 9 Appendix C

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

Classification of Site Area Emergency, FS1, is declared within 15 minutes of starting the task.

A Standard General Emergency Protective Action Recommendation (PAR) is made.

The Florida Nuclear Plant Emergency Notification Form is completed in accordance 0-EPIP-20134 Offsite Notifications and Protective Action Recommendations, with NO errors on required items identified with a

within 15 minutes of event declaration. (Item 2B is not required until offsite agencies are contacted.)

Time Critical Task: Yes Validation Time: 30 minutes Required Materials:

F-439, Florida Nuclear Plant Notification Form (hardcopy)

F-444, Guidance For Determining Protective Action Recommendations (PARs) (hardcopy)

F-668, Hot Conditions Table (hardcopy)

F-669, Cold Conditions Table (hardcopy)

0-EPIP-20101, Duties of Emergency Coordinator

0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations General

References:

F-439, Florida Nuclear Plant Notification Form

F-444, Guidance For Determining Protective Action Recommendations (PARs)

F-668, Hot Conditions Table

F-669, Cold Conditions Table

0-EPIP-20101, Duties of Emergency Coordinator

0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations NUREG 1021 Rev 9 Appendix C

I Appendix C I Page 3 of 9 Form ES-C-I SIMULATOR SETUP Reset to l #

N/A Load Lesson N/A Ensure Simulator Operator Checklist is complete N/A NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 9 Form ES-C-I Critical steps are denoted with explanation point (V Start Time Obtain 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR STEP 1 : and HOT CONDITONS TABLE, F-668. SAT (From the initiating cue.) UNSAT 0-EPIP-20101 DUTIES OF EMERGENCY COORDINATOR is Standard:

obtained with a copy of HOT CON DITONS TABLE, F-668.

Provide a copy of 0-EPIP-20101, DUTIES OF EMERGENCY Cue COORDINATOR and HOT CONDITONS TABLE, F-668.

Comment Review 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR STEP 2 : and HOT CONDITONS TABLE, F-668. SAT UNSAT Examinee reviews 0-EPIP-20101, DUTIES OF EMERGENCY Standard: COORDINATOR and HOT CONDITONS TABLE, F-668 for the event depicted in the initial conditions sheet.

Comment NUREG 1021 Rev 9 Appendix C

Appendix C Page 5 of 9 Form ES-C-I The student should consult 0- EPIP- 20134, Attachment 3, or F-444, NOTE: Guidance For Determining Protective Action Recommendations (PARs) for required Protective Action Recommendations.

Classify Off-Normal Event using present available information, AND STEP 3 : declare the emergency classification using HOT CONDITONS TABLE, SAT q F-668.

UNSAT The examinee classifies the event as a Site Area Emergency (FSI)

Standard: by interpreting the information given in the initial conditions within 15 minutes of starting the JPM.

Corn rnent The SAE Classification is based on the following:

EXAMINER

. Loss or Potential Loss of Two Fission Product Barriers NOTE:

(RED Path on Heat Sink affects the RCS and Fuel Barriers.)

EXAMINER Annotate the STOP TIME for the Event Classification here.

NOTE:

Examinee continues with the task to issue Protective Action EXAMINER Recommendations and complete the State Notification Form using NOTE: 0-EPIP-20134, Offsite Notifications and Protective Action Recommendations. The critical time element continues.

EXAMINER Annotate the START TIME for the Florida State Notification here.

NOTE:

NUREG 1021 Rev9AppendixC

Appendix C Page 6 of 9 Form ES-C-I STEP 4

. Obtain O-EPIP-20134, Offsite Notifications and Protective Action

. Recommendations and Florida State Notification Form F-439. SAT UNSAT O-EPIP-20134, Offsite Notifications and Protective Action Standard: Recommendations and Florida State Notification Form, F-439 are obtained.

Cue Provide a copy of O-EPIP-20134, Offsite Notifications and Protective Action Recommendations and Florida State Notification Form, F-439.

Comment Review O-EPIP-20134, Offsite Notifications and Protective Action STEP 5 : SAT Recommendations.

(O-EPIP-20134, Attachment 3, form F-444) UNSAT Standard Examinee reviews O-EPIP-20134, or equivalent form F-444, Offsite Notifications and Protective Action Recommendations Comment NUREG 1021 Rev 9 Appendix C

Appendix C Page 7 of 9 Form ES-C-I I Issue Protective Action Reommendations. - -

STEP 6 : SAT (Examinee uses 0-EPIP-20134, Attachment 3, or F-444, Offsite Notifications and Protective Action Recommendations Note 1) UNSAT Standard Examinee determines the no Protective Action Recommendations exist.

Comment Note: This is a Critical Step only if the candidate takes Protective Action Recommendations.

STEP Complete Florida Nuclear Plant Emergency Notification Form.

7 : SAT

\J (0-EPIP- 20134, Attachment 1B)

UNSAT (Turkey Point Nuclear Form F 439)

The examinee completes a Florida Nuclear Plant Emergency Notification Standard: Form with no errors noted on required items annotated by a

within 15 minutes. (Item 2B is not required until offsite agencies are contacted.)

Comment Step by step instructions for completing the Florida Nuclear Plant EXAMINER Emergency Notification Form are contained within 0-EPIP- 20134, NOTE: Offsite Notifications and Protective Action Recommendations, Attachment I B.

EXAMINER The time critical element is complete when the Florida State Notification Form is complete.

NOTE:

EXAMINER See the exam key for a copy of the completed Florida State Notification NOTE: Form.

Terminating The task is complete when the Examinee returns the cue sheet to ue. the examiner.

STOP TIME NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 9 Form ES-C-I Verification of Completion Job Performance Measure No. ILC 26 NRC Retake A.4 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:

NUREG 1021 Rev9AppendixC

JPM BRIEFING SHEET The examiner will explain the inal condltLon.s whLQl-i 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:

UNITS 3 and 4 are at 100% Power.

4A SGFP suction pressure piping ruptured resulting in a rapid loss of both SGFPs.

The reactor trip breakers failed to automatically open.

UNIT 4 RO manually tripped the reactor.

All AFW pumps tripped on overspeed.

SG WR levels are less than 20%.

No Radiation Releases are in progress.

Containment Parameters are normal.

Wind Speed is 10 mph.

Wind Direction is from 2600

4-EOP-E.0, Reactor Trip or Safety Injection, has been exited and actions are being taken per the appropriate EOP procedure.

Initiating Cue:

You are the Emergency Coordinator in the Control Room. Given the initial conditions classify the event using 0-EPIP-201 01, Duties of Emergency Coordinator, and if necessary, issue protective action recommendations using 0-EPI P-20 134, Offsite Notifications and Protective Action Recommendations.

By raising your hand will signify that you have completed the event declaration. At that time the Examiner will provide you with a Florida State Notification Form. You will then complete the Florida State Notification Form using 0-EPIP-201 34, Offsite Notifications and Protective Action Recommendations.

When you have completed the Florida State Notification Form, raise your hand to inform the Examiner you are done.

There is an element of this task that is Time Critical.

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.

NUREG 1021 Rev9AppendixC

S INUrnNNUIN1NUINRNII.

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION N N

N .

OnUn VerIfat C STATE El MIAMi-DADE COUNTY El MONROEa

1. A. This Is A Drill B. Q This Is An Actual Event N

2. A. Date I I AB Contact TIme: C. Reported by: Name________

N N N U N N N U I N I N I N U I U UN D. Message Number: I B. Reported From: Control Fcoom U i U F. InitialINew Classification OR El Update Notification

3 SITE A. El Crystal River UNIT4 B. El St-huIe4JNIT4 C. El St-Luoie-UNIT4 D. El Turkey Point UNIT 3 E. Turkey Point UNIT 4

4 EMERGENCY CLASSIFIC ATION: A. D Notification Of Unusual Event B. El Alert C. Site Area Emergency D. El General Emergency j *5 A. EMERGENCY DECLARATION: B. LI EMERGENCY TERMINATION Date: XX IXX !XX Time: XX:X)(

6. REASON FOR EMERGENCY DECLARATION** A. EAL Number:FSI OR B. Li Description______________

7. ADDITIONAL INFORMATiON OR UPDATE: A. None OR B. El Description_______________________________

8. WEATHER DATA: A. Wind direction from 260 degrees. B. Downwind Sectors Affected D,EF

9 RELEASE STATUS: A.

None (Go to Itefli 11) B. El In Progress C. El Has occurred, but stopped (go to Item II)

10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)

A. fl Under evaluation B. Li Release within Normal Operating Limits (Tech Specs)

C. El Non-Significant (Fraction of PAG Rango)D. El PAG Range (Protective Actions required)

E. El Liquid release (no actions required)

F UTILITYRECOMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC:

No recommended actions at this tIme. B. LI The utility recommends the following protective actions:

EVACUATE ZONES:NOT APPLICABLE OR Miles Evacuate Sectors Shelter Sectors No Action Sectors SHELTER ZONES:NOT APPLICABL E

0 -2 2-5 5-10 AND consider issuance of potassium Iodide (KI).

If form is completed In the Control Room, go to item 15. If completed in the TSC or EOF, continue with Item 12.

12. PLANT CONDITIONS:

A. Reactor Shutdown? El YES El NO B. Core Adequately Cooled? El YES El NO C. Containment Intact? El YES El NO D. Core Condition: El Stable LI Degrading

13. WEATHER DATA: A. Wind Speed mph B. Stability Class_______

14. ADDITIONAL RELEASE INFORMATION: A. El Not applicable (Go to Item 15)

Distance Projected Thyroid Dose (CDE) for 1 Hour Projected Total Dose (TEDE) for 1 Hour I Mite (Site Boundary) B... _mrem C. m rem 2 Miles 0, _mrem E. mrem 5 Miles F... _mrem G. mrem 10 Miles H. m rem I. m rem

16. (Do not read to State) EC or RM Approval Signature SIGNATURE DateXXIXXIXX TimeXX:XX MESSAGE RECEIVED BY: Name Date 1 1 Time______

IF EMERGENCY CLASS ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICATION FORM WILL BE TRANSMITrED WITHIN 15 MINUTES, THEN YOU MAY GO TO ECIRM APPROVAL SIGNATURE LINE.

ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (Pis)

F-43911:2 Rev 9(11109109)

FLORIDA NUCLEAR PLANT EMERGENCY NOTII?ICATIQN FORM METEOROLOGICAL WORKSHEET

¶ECTOR

REFERENCE:

ike chart below can be used to determine sectors affected by a radiological release, through comparison with wind direction fiom the meteorological recorders in the Control Room.

If the wind direction is directly on the edge of two sectors (e.g., 110, 33°, 56°, etc.), an additional should be added to the protective action recommendations. For example, if the wind direction is fromsector78°,

then the affected sectors for PARs should be L, M, N and P.

SECTOR INFORMATION:

WIND SECTOR WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED

[A] N 348-11 S FISK

[B] NNE 11-33 SSW JKL

[C] NE 33-56 SW KLM

[DJ ENE 56-78 wsw LMN

[E] E 78-101 W MNP

[F] ESE 101-123 WNW NPQ

[0] SE 123-146 NW PQR

[H] SSE 146-168 NNW QRA

[J] S 168-191 N RAB

[K] SSW 191-213 NNE ABC

[U SW 213-236 NE BCD

[M] WSW 236-258 ENE CDE

[N] W 258-281 E DEF

[P1 WNW 28 1-303 ESE EFG

[Qj NW 303-326 SE FGH

[RI NNW 326-348 SSE 01-U CLASSIFICATION

REFERENCE:

Either ERDADS or the below chart can be used to determine atmospheric stability classification for notification to the State of Florida. Primary method is from .T via the South Dade (60 meter) tower. Backup method is from Sigma Theta via the Ten Meter Tower. If neither meteorological tower is available, Classification shall be determined using data from National Weather Service (See 0-EPIP-20126, StabilityOff-site Dose Calculations).

CLASSIFICATION OF ATMOSPHERIC STABILITY:

Primary Backup Stability Pasquill Delta T Sigma Theta Classification Categories (°F) Range (Deerees)

Extremely unstable A AT-l.7 ST 22.5 Moderately unstable B -1.7 <AT -1.5 22.5>ST 17.5 Slightly unstable C -l,5<tT-1.4 17.5>ST 12.5 Neutral D -1.4 <AT-0.5 12.5> ST7.5 Slightly stable E -0.5 <AT + 1.4 7.5> ST3.8 Moderately stable F +1,4 <AT +3.6 3.8 > ST 2.1 Extremely stable G +3.6 <AT 2.1 > ST Meteorological information needed to fill out the Florida Nuclear Plant Emergency Notification Form is available from the Dose Calculation Worksheet (O-EPIP-20 126). The Worksheet shall be filled out by Chemistry and given to the Emergency Coordinator.

F-43912:2 Rev 9 (11109109)

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM Online Verification: El STATE El MIAMI-DADE COUNTY El MONROE COUNTY

1. A. El This Is A Drill B. El This Is An Actual Event 2.A. Date I I *B. Contact Time:________ C. Reported by: Name____________________________

D. Message Number:______________ E. Reported From: El Control Room El TSC El EOF F. El Initial/New Classification OR El Update Notification

3 SITE A. El Cryctal River UNIT 3 B. St. Lucie UNIT I C. El St. Lucie UNIT 2 D. El Turkey Point UNIT3 E. El TurkeyPointUNlT4

4 EMERGENCY CLASSIFICATION: A. El Notification Of Unusual Event B. El Alert C. El Site Area Emergency D. El General Emergency

5 A. El EMERGENCY DECLARATION: B. El EMERGENCY TERMINATION Date: I I Time:

6. REASON FOR EMERGENCY DECLARATION:** A. El EAL Number: OR B. El Description_____________

7. ADDITIONAL INFORMATION OR UPDATE: A. El None OR B. El Description

8. WEATHER DATA: A. Wind direction from B. Downwind Sectors Affected

9 RELEASE STATUS: A.

El None (Go to Item 11) B. El In Progress C. El Has occurred, but stopped (go to Item 11)

10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)

A. El Under evaluation B. El Release within Normal Operating Limits (Tech Specs)

C. El Non-Significant (Fraction of PAG Range)D. El PAG Range (Protective Actions required)

E. El Liquid release (no actions required)

11. UTILITY RECOMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC:

A. El No recommended actions at this time. B. El The utility recommends the following protective actions:

EVACUATE ZONES:NOT APPLICABLE OR Miles Evacuate Sectors Shelter Sectors No Action Sectors SHELTER ZONES:NOT APPLICABLE 0 - 2 2-5 5 -10 AND consider issuance of potassium iodide (KI)

If form is completed in the Control Room, go to item 15. If completed in the TSC or EOF, continue with item 12.

12. PLANT CONDITIONS:

A. Reactor Shutdown? ElYES El NO B. Core Adequately Cooled? El YES El NO C. Containment Intact? El YES El NO D. Core Condition: El Stable El Degrading

13. WEATHER DATA: A. Wind Speed mph B. Stability Class______

14. ADDITIONAL RELEASE INFORMATION: A. El Not applicable (Go to Item 15)

Distance Projected Thyroid Dose (CDE) for 1 Hour Proiected Total Dose (TEDE) for 1 Hour I Mile (Site Boundary) B. rem C. mrem 2 Miles D. mrem 5 Miles F. mrem m rem 10 Miles H. mrem I.

15. (Do not read to State) EC or RM Approval Signature Date I I Time_______

MESSAGE RECEIVED BY: Name Date I I Time______

IF EMERGENCY CLfiSS ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICATION FORM WILL BE TRANSMITTED WITHIN 15 MINUTES, THEN YOU MAY GO TO ECIRM APPROVAL SIGNATURE LINE.

ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (PIs)

F-439/1 :2 Rev 9 (11/09109)

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM METEOROT OGICAL WORKSUEET SECTOR

REFERENCE:

The chart below can be used to determine sectors affected by a radiological release, through comparison with wind direction from the meteorological recorders in the Control Room.

If the wind direction is directly on the edge of two sectors (e.g., 110, 330, 56°, etc.), an additional sector should be added to the protective action recommendations. For example, if the wind direction is from 78°,

then the affected sectors for PARs should be L, M, N and P.

SECTOR INFORMATION:

WIND SECTOR WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED

[A] N 348-11 5 HJK

[B] NNE 11-33 SSW JKL

[C] NE 33-56 SW KLM

[D] ENE 56-78 WSW LMI.J

[El E 78-101 W MNP

[F] ESE 101-123 WNW NPQ

[G] SE 123-146 NW PQR

[H] SSE 146-168 NNW QRA

[J] 5 168-191 N RAB

[K] SSW 191-213 NNE ABC

[L] SW 213-236 NE BCD

[MJ WSW 236-258 ENE CDE

[N] W 258-281 E DEF

[P] WNW 281-303 ESE EFG

[Q] NW 303-326 SE FGH

[Ri NNW 326-348 SSE GHJ STABILITY CLASSIFICATION

REFERENCE:

Either ERDADS or the below chart can be used to determine atmospheric stability classification for notification to the State of Florida. Primary method is from AT via the South Dade (60 meter) tower. Backup method is from Sigma Theta via the Ten Meter Tower. If neither meteorological tower is available, Stability Classification shall be determined using data from National Weather Service (See 0-EPIP-20 126, Off-site Dose Calculations).

CLASSIFICATION OF ATMOSPHERIC STABILITY:

Primary Backup Stability Pasquill DeltaT Sigma Theta Classification Categories (°F) Range (Degrees)

Extremely unstable A AT -1.7 ST22.5 Moderately unstable B -1.7 <AT -1.5 22.5>ST 17.5 Slightly unstable C -1.5 <AT -1.4 17.5>ST 12.5 Neutral D -1.4 <AT -0.5 12.5 > ST 7.5 Slightly stable E -0.5 <AT+l.4 7.5> ST 3.8 Moderately stable F +1.4 <AT +3.6 3.8 > ST 2.1 Extremely stable G +3.6 <AT 2.1 > ST Meteorological information needed to fill out the Florida Nuclear Plant Emergency Notification Form is available from the Dose Calculation Worksheet (0-EPIP-20126). The Worksheet shall be filled out by Chemistry and given to the Emergency Coordinator.

F-43912:2 Rev 9 (11/09109)

ML111930587

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